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1

Dry Natural Gas Proved Reserves Revision Decreases (Summary)  

Gasoline and Diesel Fuel Update (EIA)

2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 Alabama 208 35 732 328 173 157 1977-2011 Alaska 376 112 4,068 108 452 206 1977-2011 Arkansas 113 146 189 621 301 324 1977-2011 California 419 273 491 189 451 1,889 1977-2011 Colorado 1,524 582 3,029 4,044 3,645 2,921 1977-2011 Florida 32 0 183 0 0 9 1977-2011 Kansas 1,020 221 498 403 166 240 1977-2011 Kentucky 21 152 133 760 540 639 1977-2011 Louisiana 1,417 1,104 1,376 3,105 3,184 5,843 1981-2011 Michigan 291 210 430 406 378 267 1977-2011 Mississippi 40 50 96 250 70 156 1977-2011 Montana 78 74 56 210 100 97 1977-2011 New Mexico 1,203 2,431 2,657 1,708 1,833 2,229 1977-2011 New York 38 45 47 59 83 50 1977-2011 North Dakota 31 62 75 81 722 375 1977-2011

2

Dry Natural Gas Reserves Revision Increases  

U.S. Energy Information Administration (EIA) Indexed Site

0,833 32,174 30,674 31,416 40,521 53,601 1977-2011 0,833 32,174 30,674 31,416 40,521 53,601 1977-2011 Federal Offshore U.S. 2,030 1,815 1,699 2,312 2,978 2,467 1990-2011 Pacific (California) 43 49 23 79 23 39 1977-2011 Louisiana & Alabama 1,606 1,430 1,230 1,637 2,617 2,050 1981-2011 Texas 381 336 446 596 338 378 1981-2011 Alaska 2,853 2,147 184 1,868 622 928 1977-2011 Lower 48 States 17,980 30,027 30,490 29,548 39,899 52,673 1977-2011 Alabama 234 163 283 99 206 455 1977-2011 Arkansas 101 321 1,249 1,912 1,072 631 1977-2011 California 156 355 263 259 548 1,486 1977-2011 Coastal Region Onshore 28 32 21 41 38 20 1977-2011 Los Angeles Basin Onshore 7 15 1 35 9 11 1977-2011 San Joaquin Basin Onshore 112 296 239 180 488 1,444 1977-2011 State Offshore

3

Dry Natural Gas Reserves Revision Increases  

Gasoline and Diesel Fuel Update (EIA)

0,833 32,174 30,674 31,416 40,521 53,601 1977-2011 0,833 32,174 30,674 31,416 40,521 53,601 1977-2011 Federal Offshore U.S. 2,030 1,815 1,699 2,312 2,978 2,467 1990-2011 Pacific (California) 43 49 23 79 23 39 1977-2011 Louisiana & Alabama 1,606 1,430 1,230 1,637 2,617 2,050 1981-2011 Texas 381 336 446 596 338 378 1981-2011 Alaska 2,853 2,147 184 1,868 622 928 1977-2011 Lower 48 States 17,980 30,027 30,490 29,548 39,899 52,673 1977-2011 Alabama 234 163 283 99 206 455 1977-2011 Arkansas 101 321 1,249 1,912 1,072 631 1977-2011 California 156 355 263 259 548 1,486 1977-2011 Coastal Region Onshore 28 32 21 41 38 20 1977-2011 Los Angeles Basin Onshore 7 15 1 35 9 11 1977-2011 San Joaquin Basin Onshore 112 296 239 180 488 1,444 1977-2011 State Offshore

4

Dry Natural Gas Reserves Revision Decreases  

U.S. Energy Information Administration (EIA) Indexed Site

2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 Federal Offshore U.S. 2,798 1,864 2,017 1,871 2,242 2,993 1990-2011 Pacific (California) 22 10 87 7 10 21 1977-2011 Louisiana & Alabama 2,201 1,429 1,312 1,417 1,771 2,260 1981-2011 Texas 575 425 618 447 461 712 1981-2011 Alaska 376 112 4,068 108 452 206 1977-2011 Lower 48 States 22,293 16,601 29,734 32,927 36,119 53,267 1977-2011 Alabama 208 35 732 328 173 157 1977-2011 Arkansas 113 146 189 621 301 324 1977-2011 California 419 273 491 189 451 1,889 1977-2011 Coastal Region Onshore 12 26 69 14 16 31 1977-2011 Los Angeles Basin Onshore 29 16 66 24 5 4 1977-2011 San Joaquin Basin Onshore 371 217 327 148 427 1,854 1977-2011 State Offshore

5

Dry Natural Gas Reserves Revision Decreases  

Gasoline and Diesel Fuel Update (EIA)

2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 2,669 16,713 33,802 33,035 36,571 53,473 1977-2011 Federal Offshore U.S. 2,798 1,864 2,017 1,871 2,242 2,993 1990-2011 Pacific (California) 22 10 87 7 10 21 1977-2011 Louisiana & Alabama 2,201 1,429 1,312 1,417 1,771 2,260 1981-2011 Texas 575 425 618 447 461 712 1981-2011 Alaska 376 112 4,068 108 452 206 1977-2011 Lower 48 States 22,293 16,601 29,734 32,927 36,119 53,267 1977-2011 Alabama 208 35 732 328 173 157 1977-2011 Arkansas 113 146 189 621 301 324 1977-2011 California 419 273 491 189 451 1,889 1977-2011 Coastal Region Onshore 12 26 69 14 16 31 1977-2011 Los Angeles Basin Onshore 29 16 66 24 5 4 1977-2011 San Joaquin Basin Onshore 371 217 327 148 427 1,854 1977-2011 State Offshore

6

Federal Offshore, Pacific (California) Dry Natural Gas Proved...  

Annual Energy Outlook 2012 (EIA)

811 805 704 739 724 710 1977-2011 Adjustments 2 -7 -1 0 0 -1 1977-2011 Revision Increases 43 49 23 79 23 39 1977-2011 Revision Decreases 22 10 87 7 10 21 1977-2011 Sales 0 1 0 0 0...

7

Ohio Dry Natural Gas Proved Reserves  

U.S. Energy Information Administration (EIA) Indexed Site

975 1,027 985 896 832 758 1977-2011 Adjustments 129 138 210 70 127 -99 1977-2011 Revision Increases 49 144 135 70 68 17 1977-2011 Revision Decreases 112 198 333 43 59 38 1977-2011...

8

Table 5.17 Strategic Petroleum Reserve, 1977-2011 (Million Barrels ...  

U.S. Energy Information Administration (EIA)

1 Imported crude oil received represents volumes of imported crude oil received at ... 5 The quantity of domestic fuel oil which was in storage prior to injection of ...

9

Utah Dry Natural Gas Proved Reserves  

Gasoline and Diesel Fuel Update (EIA)

5,146 6,391 6,643 7,257 6,981 7,857 1977-2011 Adjustments -11 17 -4 1 -80 134 1977-2011 Revision Increases 218 1,113 379 1,342 872 813 1977-2011 Revision Decreases 502 325 564 491...

10

Radiological control manual. Revision 1  

SciTech Connect

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

Kloepping, R.

1996-05-01T23:59:59.000Z

11

Colorado Dry Natural Gas Proved Reserves  

Annual Energy Outlook 2012 (EIA)

17,149 21,851 23,302 23,058 24,119 24,821 1977-2011 Adjustments 52 136 -250 306 449 801 1977-2011 Revision Increases 1,178 3,924 3,244 1,601 2,973 2,509 1977-2011 Revision...

12

Microsoft Word - FINAL Class 1 Revise TRUPACT-III Management...  

NLE Websites -- All DOE Office Websites (Extended Search)

Dear Mr. Kieling: Enclosed is a Class 1 Permit Modification Notification to: * Revise TRUPACT-III Management Language * Revise Procedure Reference for the Bolting Station in Table...

13

California Dry Natural Gas Proved Reserves  

U.S. Energy Information Administration (EIA) Indexed Site

794 2,740 2,406 2,773 2,647 2,934 1977-2011 Adjustments -74 33 -6 11 10 923 1977-2011 Revision Increases 156 355 263 259 548 1,486 1977-2011 Revision Decreases 419 273 491 189 451...

14

FTCP Corrective Action Plan- Revision 1  

Energy.gov (U.S. Department of Energy (DOE))

January 2007 FTCP Corrective Action Plan, Revision 1, which is Deliverable B for Commitment 13 in the Department of Energy (DOE) Implementation Plan to Improve Oversight of Nuclear Operations, issued in response to Defense Nuclear Facilities Safety Board Recommendation 2004- 1, Oversight of Complex, High-Hazard Nuclear Operations

15

JM to Revise DOE O 150.1, Continuity Programs  

Directives, Delegations, and Requirements

The revision will bring DOE O 150.1 into compliance with mandatory Department of Homeland Security (DHS) directives published since the Order was issued in ...

2013-10-03T23:59:59.000Z

16

SNS FY 2013 Q1-4 Revision 2 Approved  

NLE Websites -- All DOE Office Websites (Extended Search)

3 Q1-4 Revision 2 Approved Revised 6112013 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 5 5 5 5 5 5 5 5 5 5 5 5 6 6 6 6 6 6 6 6...

17

Page 1 of 2 Revised 1 Feb 2013 UBC Utilities  

E-Print Network (OSTI)

SERVICES: WATER, SANITARY, STORM, GAS, and DISTRICT HEATING Part 3 (a). Water Distribution. Water service.5.7 and Section 02730, Clause 2.5.6). #12;Page 2 of 2 Revised 1 Feb 2013 Part 3 (c). Gas and District Heating (%) District Heating Contractor or UBC Dept Telephone Fax Contractor Primary Contact Email Design by (Company

Vellend, Mark

18

Computer Engineering Undergraduate Handbook Revised: April 1, 2010  

E-Print Network (OSTI)

Computer Engineering Undergraduate Handbook Revised: April 1, 2010 BACHELOR OF SCIENCE IN COMPUTER-278-5987 Fax: 657-278-5804 http://www.fullerton.edu/ecs/cpe #12;Computer Engineering Undergraduate Handbook Engineering Undergraduate Handbook Revised: April 1, 2010 TOC 1 COMPUTER ENGINEERING PROGRAM UNDERGRADUATE

de Lijser, Peter

19

CAO-94-1001 Revision 1  

NLE Websites -- All DOE Office Websites (Extended Search)

S. Department of Energy Carlsbad Field Office Information Management Plan DOEWIPP-12-3429 Revision 0 May 2012 DOEWIPP-12-3429 Rev. 0 2 U. S. Department of Energy Carlsbad Field...

20

Revision of DOE Manual 460.2-1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

, 2005 , 2005 TEC/WG 1 Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual Ella McNeil Office of Transportation, EM-11 September 20, 2005 TEC/WG 2 Getting Started Getting Started * Establish an internal writing team, lead by EM: - Field Representatives - Naval Reactors - NNSA - RW * Kick-off on August 3 (conference call) * Second conference call on Sept. 8 September 20, 2005 TEC/WG 3 Proposed Revision Timeline Proposed Revision Timeline Writing team completes new draft of Manual 1/06 Begin informal DOE review of revised Manual (field, GC, PSOs) 2/06 (3 weeks) Comment resolution by writing team complete, provide draft to internal management for review 3/06 (2 weeks) Draft Manual is provided to SRGs

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Advanced Lighting Guidelines: 1993 (Revision 1)  

Science Conference Proceedings (OSTI)

This series of guidelines, originally published in 1990 by the California Energy Commission, provides both technical and practical information about energy-efficient lighting equipment and design techniques. This revised version updates the 1990 information and adds four new sections on lighting controls and daylighting. EPRI's cofunding and publication of these guidelines will facilitate utility access to this information, resulting in increased lighting quality and energy efficiency.

1993-05-01T23:59:59.000Z

22

Microsoft Word - TLVT Manual Revision 1 _122012_ - Final.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

INL-EXT-12-27920 U.S. Department of Energy Vehicle Technologies Program Battery Technology Life Verification Test Manual Revision 1 DECEMBER 2012 The Idaho National Laboratory is...

23

Revision of DOE Manual 460.2-1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 TEC/WG 1 Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual Revision of DOE M 460.2-1, Radioactive Material Transportation Practices Manual DOE Writing Team March 2006 TEC/WG 2 Proposed Revision Timeline Proposed Revision Timeline Complete new draft of Manual 2/06 Draft Manual provided to Manual Review Topic Group for review & comment 3/14/06 Comments due from Topic Group 5/01/06 Final draft Manual 7/06 Comment resolution (thru conference calls with Topic Group, as needed) 6/06 March 2006 TEC/WG 3 Proposed Timeline (contd.) Proposed Timeline (contd.) Manual is submitted into the formal Directives process 9/06 Manual reissued 12/06 March 2006 TEC/WG 4 Major Changes Made to the Manual Major Changes Made to the Manual * Clarification/update of information relative

24

JM to Revise DOE O 483.1, Notice of Intent to Revise DOE O 483.1, Cooperative Research and Development Agreements and DOE M 483.1-1, Cooperative Research and Development Agreements Manual  

Directives, Delegations, and Requirements

Justification memorandum approving revision of the outdated DOE O 483.1 to incorporate DOE M 483.1-1 into the revised order.

2013-02-21T23:59:59.000Z

25

Revision to DOE Order 435.1 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Management » Compliance » Revision to DOE Program Management » Compliance » Revision to DOE Order 435.1 Revision to DOE Order 435.1 The Office of Environmental Management has primary responsibility, within DOE, for DOE Order 435.1, the self-regulation of radioactive waste management. As part of this responsibility, EM has decided to update the Order to incorporate several changes to the regulatory process that have taken place over the last decade as well as streamline the Order to improve management of the waste. A comprehensive complex-wide review of DOE radioactive waste management activities associated with implementation of the requirements of DOE Order 435.1, Radioactive Waste Management, was conducted in 2010 in order to gather feedback on the effectiveness of the DOE Order 435.1 requirements (not to assess compliance with the

26

Revised: September 24, 2013 Page 1 of 2  

E-Print Network (OSTI)

Revised: September 24, 2013 Page 1 of 2 ISP Certification Audit Checklist Certification for: (Area Sample Physical Inspection Locations YES NO 6.1 Are PPE hazard assessments and their certifications.3 Are minimum HCP requirements met for all applicable areas? 6.4 Are minimum CHP requirements met for all

Jiang, Wen

27

NISTIR 7511 Revision 1, Security Content Automation ...  

Science Conference Proceedings (OSTI)

... CONTENT AUTOMATION PROTOCOL (SCAP) VERSION 1.0 VALIDATION PROGRAM TEST REQUIREMENTS (DRAFT) XCCDF.V.2: The vendor ...

2013-04-29T23:59:59.000Z

28

Desalination with carbon aerogel electrodes. Revision 1  

SciTech Connect

Electrically regenerated electrosorption process (carbon aerogel CDI) was developed by LLNL for continuously removing ionic impurities from aqueous streams. A salt solution flows in a channel formed by numerous pairs of parallel carbon aerogel electrodes. Each electrode has a very high BET surface area (2-5.4x10{sup 6}ft{sup 2}lb{sup -1} or 400-1100 m{sup 2}g{sup -1}) and very low electrical resistivity ({le}40 m{Omega}). Ions are removed from the electrolyte by the electric field and electrosorbed onto the carbon aerogel. It is concluded that carbon aerogel CDI may be an energy-efficient alternative to electrodialysis and reverse osmosis for desalination of brackish water ({le}5000 ppM). The intrinsic energy required by this process is about QV/2, where Q is the stored electrical charge and V is the voltage between the electrodes, plus losses. Estimated requirement for desalination of a 2000 ppM feed is -0.53-2.5 Wh/gal{sup -1} (0.5-2.4 kJ L{sup -1}), depending on voltage, flow rate, cell dimensions, aerogel density, recovery ratio, etc. This assumes that 50-70% of the stored electrical energy is reclaimed during regeneration (electrical discharge). Though the energy requirement for desalination of sea water is also low, this application will be much more difficult. Additional work will be required for desalination of streams that contain more than 5000 ppM total dissolved solids (2000 ppM will require electrochemical cells with extremely tight, demanding tolerances). At this present time, the process is best suited for streams with dilute impurities, as recently demonstrated during a field test at LLNL Treatment Facility C.

Farmer, J.C.; Richardson, J.H.; Fix, D.V. [Lawrence Livermore National Lab., CA (United States); Thomson, S.L.; May, S.C. [Bechtel National, Inc., San Francisco, CA (United States)

1996-12-04T23:59:59.000Z

29

1992 Annual Capacity Report. Revision 1  

SciTech Connect

The Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) requires the Department of Energy (DOE) to issue an Annual Capacity Report (ACR) for planning purposes. This report is the fifth in the series published by DOE. In May 1993, DOE published the 1992 Acceptance Priority Ranking (APR) that established the order in which DOE will allocate projected acceptance capacity. As required by the Standard Contract, the acceptance priority ranking is based on the date the spent nuclear fuel (SNF) was permanently discharged, with the owners of the oldest SNF, on an industry-wide basis, given the highest priority. The 1992 ACR applies the projected waste acceptance rates in Table 2.1 to the 1992 APR, resulting in individual allocations for the owners and generators of the SNF. These allocations are listed in detail in the Appendix, and summarized in Table 3.1. The projected waste acceptance rates for SNF presented in Table 2.1 are nominal and assume a site for a Monitored Retrievable Storage (MRS) facility will be obtained; the facility will initiate operations in 1998; and the statutory linkages between the MRS facility and the repository set forth in the Nuclear Waste Policy Act of 1982, as amended (NWPA), will be modified. During the first ten years following projected commencement of Civilian Radioactive Waste Management System (CRWMS) operation, the total quantity of SNF that could be accepted is projected to be 8,200 metric tons of uranium (MTU). This is consistent with the storage capacity licensing conditions imposed on an MRS facility by the NWPA. The annual acceptance rates provide an approximation of the system throughput and are subject to change as the program progresses.

Not Available

1993-05-01T23:59:59.000Z

30

Perspectives on reactor safety. Revision 1  

Science Conference Proceedings (OSTI)

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01T23:59:59.000Z

31

A:\1FRONT(REVISED).PDF  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ACKNOWLEDGMENTS ACKNOWLEDGMENTS Special "Thanks" are given to the many individuals who participated in the multi-disciplinary team from DOE Headquarters and Field Elements. They wrote the chapters or provided insight, input and information arising from their own experiences. It was their valuable expertise which formed the basis for this Reference Book. Sponsor: Richard H. Hopf, Director, Office of Procurement & Assistance Management Lead Office Director: Stephen J. Michelsen, Director, Office of Contract & Resource Management Team Lead: James Tower, Office of Contract & Resource Management Sounding Board Advisors: Donette Cappello, PC-1 Gwendolyn Cowan, MA-51 Leif Erickson, RL Linda Johnson, GC-61 John LaBarge, SC-7 Richard Mehl, FI-10 William C. Meyers, AL

32

GXQ program verification and validation. Revision 1  

Science Conference Proceedings (OSTI)

This report documents the program user`s guide of a general purpose atmospheric dispersion code named GXQ. GXQ is an IBM Compatible microcomputer based program for calculating atmospheric dispersion coefficients using Hanford site specific joint frequency data. It uses the Gaussian straight line model to calculate either an atmospheric dispersion coefficient (X/Q{prime}) or a maximum normalized air concentration (X/Q). Several options are available to the user which alter the standard Gaussian model to allow for plume depletion, building wake, plume meander, sector averaging, gravitational settling and plume rise. Additional options control handling of the joint frequency data and output. Combinations of the above allow calculation of X/Q{prime} in accordance with Nuclear Regulatory Commission Regulatory Guide 1.145. The GXQ source code listing is provided in an appendix.

Hey, B.E.

1995-05-10T23:59:59.000Z

33

International Energy: Subject Thesaurus. Revision 1  

SciTech Connect

The International Energy Agency: Subject Thesaurus contains the standard vocabulary of indexing terms (descriptors) developed and structured to build and maintain energy information databases. Involved in this cooperative task are (1) the technical staff of the USDOE Office of Scientific and Technical Information (OSTI) in cooperation with the member countries of the International Energy Agency`s Energy Technology Data Exchange (ETDE) and (2) the International Atomic Energy Agency`s International Nuclear Information System (INIS) staff representing the more than 100 countries and organizations that record and index information for the international nuclear information community. ETDE member countries are also members of INIS. Nuclear information prepared for INIS by ETDE member countries is included in the ETDE Energy Database, which contains the online equivalent of the printed INIS Atomindex. Indexing terminology is therefore cooperatively standardized for use in both information systems. This structured vocabulary reflects thscope of international energy research, development, and technological programs. The terminology of this thesaurus aids in subject searching on commercial systems, such as ``Energy Science & Technology`` by DIALOG Information Services, ``Energy`` by STN International and the ``ETDE Energy Database`` by SilverPlatter. It is also the thesaurus for the Integrated Technical Information System (ITIS) online databases of the US Department of Energy.

Not Available

1993-11-01T23:59:59.000Z

34

Guidelines for Electromagnetic Interference Testing in Power Plants: Revision 1  

Science Conference Proceedings (OSTI)

Concern about the effect of electromagnetic emissions on the safe, reliable operation of digital equipment has resulted in requirements for utilities to create detailed emissions maps. This guide identifies emissions sources in nuclear power plants, recommends susceptibility and emissions standards, and details design and layout practices for minimizing susceptibility to electromagnetic interference (EMI). Revision 1 reflects modifications to the original document, which received NRC approval in a Safety...

1997-04-16T23:59:59.000Z

35

Field Guide Visual Inspection of NCI: Revision 1  

Science Conference Proceedings (OSTI)

The EPRI "Field Guide Visual Inspection of NCI, Revision 1" is a compilation of photographs that illustrate various conditions and factors that commonly affect transmission line non-ceramic insulators (NCI, also called polymer or composite insulators) in the field, along with their likely causes, a maintenance priority rating, and suggested actions to be taken by utility personnel. The photos are arranged according to the portion of the NCI affected, that is, the shed, sheath, shed and sheath, co...

2004-06-30T23:59:59.000Z

36

EM Quality Assurance Program (EM-QA-001 Revision 1) | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program (EM-QA-001 Revision 1) EM Quality Assurance Program (EM-QA-001 Revision 1) The purpose of this document is to describe the U.S. Department of Energy (DOE), Office of...

37

1. Revised Guide Chapter 70.4, Cooperative Audit Strategy:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revised Guide Chapter 70.4, Cooperative Audit Strategy: Revised Guide Chapter 70.4, Cooperative Audit Strategy: Establishes a requirement for the contractor to provide an Internal Audit Design for each 5-year period of a contract. The design is to consist of: (1) Organizational placement of the internal audit function to assure functional independence; (2) Size, experience, and educational requirements of audit staff; (3) Audit standards to be applied; (4) (5) (6) allo (7) a. Plan for internal audit function over 5-year period; Plan for audit of allowable costs; Use ofDCAA for supplementing audit of prime or subcontract wable costs; and Schedule for peer review. b. Provides detailed standards for the Annual Audit Plan. c. Provides detailed standards for the Annual Audit Report. 2.AL 2005-04, Class Deviation to Reflect Changes to the Cooperative Audit Strategy,

38

Preliminary hazards analysis of thermal scrap stabilization system. Revision 1  

SciTech Connect

This preliminary analysis examined the HA-21I glovebox and its supporting systems for potential process hazards. Upon further analysis, the thermal stabilization system has been installed in gloveboxes HC-21A and HC-21C. The use of HC-21C and HC-21A simplified the initial safety analysis. In addition, these gloveboxes were cleaner and required less modification for operation than glovebox HA-21I. While this document refers to glovebox HA-21I for the hazards analysis performed, glovebox HC-21C is sufficiently similar that the following analysis is also valid for HC-21C. This hazards analysis document is being re-released as revision 1 to include the updated flowsheet document (Appendix C) and the updated design basis (Appendix D). The revised Process Flow Schematic has also been included (Appendix E). This Current revision incorporates the recommendations provided from the original hazards analysis as well. The System Design Description (SDD) has also been appended (Appendix H) to document the bases for Safety Classification of thermal stabilization equipment.

Lewis, W.S.

1994-08-23T23:59:59.000Z

39

Microsoft Word - CHAP02ESH _REVISED1_3.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

-1 -1 CHAPTER 2 ENVIRONMENT, SAFETY AND HEALTH (revised September 25, 2003) WHAT ARE THE BASIC PRINCIPLES/OBJECTIVES OF THE DEPARTMENT'S ENVIRONMENT, SAFETY AND HEALTH (ES&H) PROGRAM? 1. Work is performed in a manner that protects workers, the public and the environment. 2. The Department holds contractors accountable for the safe performance of work. 3. ES&H functions and activities are an integral and visible part of contractors' business processes. WHY IS THE DEPARTMENT'S ENVIRONMENT, SAFETY AND HEALTH PROGRAM IMPORTANT? The Department has a responsibility to protect people, the environment, and property in the performance of the various missions under its contracts. Because of the sensitivity and potential liabilities associated

40

NIST SP 800-53A Revision 1, Guide for Assessing the ...  

Science Conference Proceedings (OSTI)

Page 1. NIST Special Publication 800-53A Guide for Assessing the Security Revision 1 Controls in Federal Information Systems and Organizations ...

2012-02-06T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

JM to Revise DOE O 420.1B, Facility Safety (9-23-10)  

Directives, Delegations, and Requirements

This approval includes revision of the three implementing Guides: DOE G 420.1-1, Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide ...

2010-09-23T23:59:59.000Z

42

Steam Generator Management Program Administrative Procedures, Revision 1  

Science Conference Proceedings (OSTI)

The Steam Generator Management Program (SGMP) developed many of the guidelines that implement NEI 97-06, Steam Generator Program Guidelines, including a 2001 document that defined and formalized the programmatic elements of SGMP itself. This revision of SGMP Administrative Procedures aligns SGMP with the May 2003 guideline NEI 03-08, which addressed several recent issues involving materials degradation. The revision defines how guidelines are to be revised and approved and presents the SGMP charter, whic...

2004-12-09T23:59:59.000Z

43

NRC drug-free workplace plan. Revision 1  

SciTech Connect

On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ``NRC Drug-Free Workplace Plan,`` supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance.

1997-11-01T23:59:59.000Z

44

Fuel Reliability Guidelines: Fuel Surveillance and Inspection, Revision 1  

Science Conference Proceedings (OSTI)

This Electric Power Research Institute (EPRI) report presents revised guidance for performing nuclear fuel assessments and inspections. The revision provides technical guidance on the scope and frequency of fuel performance assessments and inspections to support the industry goal of zero fuel failures and performance issues. To help achieve this goal, both failed and healthy fuel must be inspected. Such inspections advance the understanding of fuel failure mechanisms and unit-specific fuel margins, leadi...

2012-03-30T23:59:59.000Z

45

Approved Site Treatment Plan, Volumes 1 and 2. Revision 4  

SciTech Connect

The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information.

Helmich, E.H.; Molen, G.; Noller, D.

1996-03-22T23:59:59.000Z

46

(1) Shaw AREVA MOX Services Revised Updated Reply to Notice of Violation 70-  

E-Print Network (OSTI)

Materials" This letter corrects an error in our letter of September 1,2011. In that letter, we stated in Item 5 on Page 6 of the Enclosure, that document DCSOI-ZMJ-DS-NTE-N-65973 had been revised. The revision was not approved until September 6, 2011. The Enclosure has been revised accordingly. If you have any questions, please contact Jim O'Dell, Regulatory Compliance Manager, at (803) 819-2234. Sincerely,

Kelly Trice; Eric Chassard; Mox Services; Sam Glenn Nnsa/srs; William Gloersen Nrc/rii; Mark Gober; Mox Services; Dealis Gwyn; Mox Services; Melvin Shannon Nrc/srs

2011-01-01T23:59:59.000Z

47

Orientation Checklist revised 06/11/10 #100 page 1 of 1  

E-Print Network (OSTI)

Orientation Checklist revised 06/11/10 #100 page 1 of 1 New Employee Orientation Checklist INSTRUCTIONS This form is intended as a guide for HR Liaisons to document a new employee's orientation at Texas on employee orientations is available on the website at http://employees.tamu.edu/managers/liaisonResources/Orientation

48

EFFECTS OF GAMMA IRRADIATION ON EPDM ELASTOMERS (REVISION 1)  

SciTech Connect

Two formulations of EPDM elastomer, one substituting a UV stabilizer for the normal antioxidant in this polymer, and the other the normal formulation, were synthesized and samples of each were exposed to gamma irradiation in initially pure deuterium gas to compare their radiation stability. Stainless steel containers having rupture disks were designed for this task. After 130 MRad dose of cobalt-60 radiation in the SRNL Gamma Irradiation Facility, a significant amount of gas was created by radiolysis; however the composition indicated by mass spectroscopy indicated an unexpected increase in the total amount deuterium in both formulations. The irradiated samples retained their ductility in a bend test. No change of sample weight, dimensions, or density was observed. No change of the glass transition temperature as measured by dynamic mechanical analysis was observed, and most of the other dynamic mechanical properties remained unchanged. There appeared to be an increase in the storage modulus of the irradiated samples containing the UV stabilizer above the glass transition, which may indicate hardening of the material by radiation damage. Revision 1 adds a comparison with results of a study of tritium exposed EPDM. The amount of gas produced by the gamma irradiation was found to be equivalent to about 280 days exposure to initially pure tritium gas at one atmosphere. The glass transition temperature of the tritium exposed EPDM rose about 10 ?C. over 280 days, while no glass transition temperature change was observed for gamma irradiated EPDM. This means that gamma irradiation in deuterium cannot be used as a surrogate for tritium exposure.

Clark, E.

2013-09-13T23:59:59.000Z

49

Sourcebook for Plant Layup and Equipment Preservation (Revision 1)  

Science Conference Proceedings (OSTI)

This revision of a 1987 sourcebook documents preferred industry layup practices for the various systems and components of PWR and BWR nuclear plants. Plants that have not implemented layup programs will find the sourcebook a useful reference document in program development.

1992-07-14T23:59:59.000Z

50

Non-Power Reactor Operator Licensing Examiner Standards. Revision 1  

SciTech Connect

The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience.

NONE

1995-06-01T23:59:59.000Z

51

PWR Primary Water Chemistry Guidelines: Volume 1 Revision 4  

Science Conference Proceedings (OSTI)

State-of-the art water chemistry programs help ensure the continued integrity of reactorcoolant system (RCS) materials of construction and fuel cladding, ensure satisfactorycore performance, and support the industry trend toward reduced radiation fields. These revised PWR Primary Water Chemistry Guidelines, prepared by a committee ofindustry experts, reflect the recent field and laboratory data on primary coolant systemcorrosion and performance issues. PWR operators can use these Guidelines to updatethei...

1999-03-31T23:59:59.000Z

52

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1  

Science Conference Proceedings (OSTI)

This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01T23:59:59.000Z

53

Advanced Nuclear Technology: Regulatory Performance Requirements for Safety-Related Instrumentation, Revision 1  

Science Conference Proceedings (OSTI)

This report proposes an acceptable methodology to apply to safety-related instrumentation to demonstrate 95% probability and 95% confidence (95/95) uncertainties in support of the requirements of Nuclear Regulatory Commission Regulatory Guide (RG) 1.105 Revision 3. This methodology should serve as a means to specify testing and analysis requirements to instrumentation manufacturers and suppliers for their use in meeting the RG 1.105 Revision 3 95% probability and 95% confidence requirements. A ...

2013-08-07T23:59:59.000Z

54

COMSOL MULTIPHYSICS MODEL FOR DWPF CANISTER FILLING, REVISION 1  

SciTech Connect

This revision is an extension of the COMSOL Multiphysics model previously developed and documented to simulate the temperatures of the glass during pouring a Defense Waste Processing Facility (DWPF) canister. In that report the COMSOL Multiphysics model used a lumped heat loss term derived from experimental thermocouple data based on a nominal pour rate of 228 lbs./hr. As such, the model developed using the lumped heat loss term had limited application without additional experimental data. Therefore, the COMSOL Multiphysics model was modified to simulate glass pouring and subsequent heat input which, replaced the heat loss term in the initial model. This new model allowed for changes in flow geometry based on pour rate as well as the ability to increase and decrease flow and stop and restart flow to simulate varying process conditions. A revised COMSOL Multiphysics model was developed to predict temperatures of the glass within DWPF canisters during filling and cooldown. The model simulations and experimental data were in good agreement. The largest temperature deviations were {approx} 40 C for the 87 inch thermocouple location at 3000 minutes and during the initial cool down at the 51 inch location occurring at approximately 600 minutes. Additionally, the model described in this report predicts the general temperature trends during filling and cooling as observed experimentally. The revised model incorporates a heat flow region corresponding to the glass pouring down the centerline of the canister. The geometry of this region is dependent on the flow rate of the glass and can therefore be used to see temperature variations for various pour rates. The equations used for this model were developed by comparing simulation output to experimental data from a single pour rate. Use of the model will predict temperature profiles for other pour rates but the accuracy of the simulations is unknown due to only a single flow rate comparison.

Kesterson, M.

2011-09-08T23:59:59.000Z

55

Tank safety screening data quality objective. Revision 1  

DOE Green Energy (OSTI)

The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

Hunt, J.W.

1995-04-27T23:59:59.000Z

56

Technical Repair Guidelines for Limitorque Model SMB-000 Valve Actuators: Revision 1  

Science Conference Proceedings (OSTI)

This technical repair guide (TRG) for Limitorque motor-operated valve (MOV) actuator model SMB-000 is the first in a series of documents devoted to the comprehensive maintenance and repair of Limitorque actuators. This guide provides instructions for engineering, operations, and maintenance personnel on MOV actuator repair, maintenance, adjustment, and troubleshooting methods. Originally published in 1989, this document has now been thoroughly revised (Revision 1) to incorporate new information and techn...

1994-10-02T23:59:59.000Z

57

US Department of Energy radiological control manual. Revision 1  

SciTech Connect

This manual establishes practices for the conduct of Department of Energy radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. This Manual is not a substitute for Regulations; it is intended to be consistent with all relevant statutory and regulatory requirements and shall be revised whenever necessary to ensure such consistency. Some of the Manual provisions, however, challenge the user to go well beyond minimum requirements. Following the course of action delineated in the Manual will result in achieving and surpassing related statutory or regulatory requirements.

Not Available

1994-04-01T23:59:59.000Z

58

Transportation system requirements document. Revision 1 DCN01. Supplement  

SciTech Connect

The original Transportation System Requirements Document described the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of that document was to define the system-level requirements. These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presented an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. This revision of the document contains only the pages that have been modified.

1995-05-01T23:59:59.000Z

59

Dry Natural Gas New Reservoir Discoveries in Old Fields (Summary)  

Gasoline and Diesel Fuel Update (EIA)

,155 1,188 1,622 2,598 1,668 1,227 1977-2011 ,155 1,188 1,622 2,598 1,668 1,227 1977-2011 Alabama 7 17 1 0 0 0 1977-2011 Alaska 2 0 5 0 0 3 1977-2011 Arkansas 32 27 41 36 27 23 1977-2011 California 4 1 14 0 0 0 1977-2011 Colorado 26 23 17 0 27 0 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 3 0 2 0 1 1 1977-2011 Kentucky 4 0 0 0 0 0 1977-2011 Louisiana 185 134 650 1,542 279 167 1981-2011 Michigan 5 0 1 9 0 0 1977-2011 Mississippi 6 1 3 0 0 0 1977-2011 Montana 28 1 0 0 1 1 1977-2011 New Mexico 140 10 7 3 3 9 1977-2011 New York 0 0 0 0 0 27 1977-2011 North Dakota 3 3 5 5 2 17 1977-2011 Ohio 0 0 0 0 0 0 1977-2011 Oklahoma 12 56 85 178 1 18 1977-2011 Pennsylvania 0 3 32 0 904 322 1977-2011 Texas 253 535 178 425 122 425 1981-2011

60

Dry Natural Gas Proved Reserves New Field Discoveries (Summary)  

U.S. Energy Information Administration (EIA) Indexed Site

409 796 1,170 1,372 850 947 1977-2011 409 796 1,170 1,372 850 947 1977-2011 Alabama 0 0 2 0 3 2 1977-2011 Alaska 0 0 0 0 0 0 1977-2011 Arkansas 7 0 0 0 0 0 1977-2011 California 0 0 0 1 1 0 1977-2011 Colorado 14 15 17 8 22 18 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 0 0 9 0 4 0 1977-2011 Kentucky 0 0 0 0 0 1 1977-2011 Louisiana 27 0 191 257 48 47 1981-2011 Michigan 1 0 4 19 2 14 1977-2011 Mississippi 0 0 2 2 0 1 1977-2011 Montana 19 0 0 0 0 7 1977-2011 New Mexico 35 20 0 1 0 3 1977-2011 New York 45 7 0 0 56 0 1977-2011 North Dakota 1 0 6 6 25 10 1977-2011 Ohio 0 0 1 0 0 0 1977-2011 Oklahoma 0 6 21 0 51 47 1977-2011 Pennsylvania 13 7 61 128 50 165 1977-2011 Texas 80 78 472 476 519 69 1981-2011 Utah

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Dry Natural Gas Proved Reserves New Field Discoveries (Summary)  

Gasoline and Diesel Fuel Update (EIA)

409 796 1,170 1,372 850 947 1977-2011 409 796 1,170 1,372 850 947 1977-2011 Alabama 0 0 2 0 3 2 1977-2011 Alaska 0 0 0 0 0 0 1977-2011 Arkansas 7 0 0 0 0 0 1977-2011 California 0 0 0 1 1 0 1977-2011 Colorado 14 15 17 8 22 18 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 0 0 9 0 4 0 1977-2011 Kentucky 0 0 0 0 0 1 1977-2011 Louisiana 27 0 191 257 48 47 1981-2011 Michigan 1 0 4 19 2 14 1977-2011 Mississippi 0 0 2 2 0 1 1977-2011 Montana 19 0 0 0 0 7 1977-2011 New Mexico 35 20 0 1 0 3 1977-2011 New York 45 7 0 0 56 0 1977-2011 North Dakota 1 0 6 6 25 10 1977-2011 Ohio 0 0 1 0 0 0 1977-2011 Oklahoma 0 6 21 0 51 47 1977-2011 Pennsylvania 13 7 61 128 50 165 1977-2011 Texas 80 78 472 476 519 69 1981-2011 Utah

62

Transuranic waste characterization sampling and analysis methods manual. Revision 1  

DOE Green Energy (OSTI)

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits.

Suermann, J.F.

1996-04-01T23:59:59.000Z

63

PNNL-18845, Revision 1 Prepared for the U.S. Department of Energy  

E-Print Network (OSTI)

200-BP-1 Prototype Hanford Barrier ­ 15 Years of Performance Monitoring AL Ward SO Link KE Draper RE/2003) #12;PNNL-18845, Revision 1 200-BP-1 Prototype Hanford Barrier ­ 15 Years of Performance Monitoring AL waste disposal site at the DOE Hanford Site. Monitoring has been almost continuous for the last 15 years

64

JM to Revise DOE P 434.1, Notice of Intent to Revise Department of Energy Policy 434.1, Conduct and Approval of Select Agent and Toxin Work at Department of Energy Sites  

Directives, Delegations, and Requirements

This memorandum provides justification for the revision of Department of Energy (DOE) Policy (P) 434.1 Conduct and Approval of Select Agent and Toxin Work at ...

2013-04-18T23:59:59.000Z

66

January 19, 2001, DOE letter enclosing Revision 1 of Implementation...  

NLE Websites -- All DOE Office Websites (Extended Search)

STABILIZATION ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 5.1 Inventory Summaries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....

67

Selection of 3013 containers for field surveillance: LA-14310, Revision 1  

SciTech Connect

This document is the fifth in a series of reports that document the binning, statistical sampling, and sample selection of 3013 containers for field surveillance. 1,2,3,39 Revisions to binning assignments documented in this report are primarily a result of new prompt gamma data. This report also documents changes to the random sample specification resulting from these binning changes and identifies and provides the rationale for the engineering judgment sample items for Fiscal Year (FY) 2008 and 2009. This revision also updates the changes to the previous surveillance sample resulting from changes to the order that specific containers undergo surveillance. This report will continue to be reviewed regularly and revised as needed to meet the requirements of the surveillance program.

Peppers, Larry; Kelly, Elizabeth; McClard, James; Friday, Gary; Venetz, Theodore; Stakebake, Jerry

2009-04-01T23:59:59.000Z

68

U.S. NUCLEAR REGULATORY COMMISSION Revision 1 February 1996  

E-Print Network (OSTI)

From Table 3.1 in NUREG-0713 (Ref. 9). 17. How do I know how much my occupational dose (exposure) is? If you

Meagher, Mary

69

Search Committee Guide revised 05/29/2013 #420 Page 1 of 17  

E-Print Network (OSTI)

Search Committee Guide revised 05/29/2013 #420 Page 1 of 17 Search Committee Guide for Non-Faculty Positions INTRODUCTION This document provides an information resource for search committees for non are available upon request to brief search committees on this guide. Links to online resources are included

70

ENERGY COMMITTEE ENERGY TALKING POINTS (ETP) SERIES Revision (or Issued): > 1 of 2  

E-Print Network (OSTI)

that is generated by all of the nation's hydroelectric dams in a typical year. THE ENERGY-WATER NEXUS The Department. As the U.S.'s appetite for energy grows so does the demand for increased water usage and the potentialENERGY COMMITTEE ­ ENERGY TALKING POINTS (ETP) SERIES Revision (or Issued): > 1 of 2 ETP

71

HRSG/SR Revised 07/01/08 Page 1 of 2 HAZARD ASSESSMENT SURVEY & ANALYSIS  

E-Print Network (OSTI)

HRSG/SR Revised 07/01/08 Page 1 of 2 HAZARD ASSESSMENT SURVEY & ANALYSIS PERSONAL PROTECTIVE is accomplished by surveying the workplace to determine where physical or health hazards are present or likely to noise levels. (>85 dBA 8-hour TWA) Ear muffs or plugs Nuisance dust/mist Welding fumes Asbestos

Eirinaki, Magdalini

72

Clemson University Standard Terms of Purchase Revision B Effective April 1, 2011  

E-Print Network (OSTI)

Clemson University Standard Terms of Purchase ­ Revision B Effective April 1, 2011 This document contains standard terms and conditions that apply to all solicitations and procurements made by Clemson University. Any Supplier terms and conditions included with Supplier's invoice or any other document provided

Stuart, Steven J.

73

Portland General Electric Company Fourth Revision of Sheet No. 32-1 P.U.C. Oregon No. E-17 Canceling Third Revision of Sheet No. 32-1  

E-Print Network (OSTI)

Portland General Electric Company Fourth Revision of Sheet No. 32-1 P.U.C. Oregon No. E-17, Vice President on and after January 1, 2004 #12;Portland General Electric Company Fifth Revision) Renewable Usage 0.800¢ per kWh in addition to Energy Charge Fixed Renewable $3.50 per month per block

74

Clean Slate 1 Corrective Action Plan, Revision 0  

Science Conference Proceedings (OSTI)

This Corrective Action Plan (CAP) has been prepared to meet the requirements specified in the Federal Facility Agreement and Consent Order (FFACO, 1996). A Corrective Action Decision Document (CADD) (DOE, 1997) was submitted to the Nevada Department of Environmental Protection (NDEP) January 31, 1997 for the Clean Slate 1 (CS-1) Site in accordance with the Corrective Action Investigation Plan (CAIP) (DOE, 1996) and the Soils Media Operable Unit Quality Assurance Project Plan (DOE, 1995). The FFACO lists CS-1 as Corrective Action Unit (CAU) number 412.

NONE

1997-04-01T23:59:59.000Z

75

Microsoft Word - FinalReportRevised1.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

Oil & Natural Gas Technology DOE Award No.: DE-PS26-04NT42072-1 (Round 2) Final Report PETROPHYSICAL ANALYSIS AND GEOGRAPHIC INFORMATION SYSTEM FOR SAN JUAN BASIN TIGHT GAS...

76

Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1  

SciTech Connect

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

NONE

1995-04-01T23:59:59.000Z

77

Page 1 of 2 Revised 8 February 2013 UBC Utilities  

E-Print Network (OSTI)

(Pre-board,1,2,3 or 4) Part 3. MECHANICAL SERVICES: WATER, SANITARY, STORM, GAS, and DISTRICT HEATING 3 (c). Gas and District Heating Distribution · Service to meet requirements of UBC Technical Guidelines Division 2, Section 02685 (gas) and Section (TBA-District Heating ­ contact UBC Utilities. · Fax

Vellend, Mark

78

PDP-6 LISP (LISP 1.5) Revised  

E-Print Network (OSTI)

This is a mosaic description of PDP-6 LISP, intended for readers familiar with the LISP 1.5 Programmer's Manual or who have used LISP on some other computer. Many of the features, such as the display, are subject to ...

listed, None

1967-04-01T23:59:59.000Z

79

Hanford analytical sample projections FY 1995--FY 2000. Revision 1  

Science Conference Proceedings (OSTI)

Sample projections have been categorized into 7 major areas: Environmental Restoration, Tank Waste Remediation, Solid Waste, Liquid Effluents, Site Monitoring, Industrial Hygiene, and General Process Support Programs. The estimates are through the Fiscal Year 2000 and are categorized by radiation level. The yearly sample projection for each program will be categorized as follows: Category 1: Non-Radioactive; Category 2: 100 mR/hr {beta}/{gamma}; and Category 7: >200 nCi/g {alpha}.

Simmons, F.M.

1994-12-02T23:59:59.000Z

80

Integrated thermal treatment system study -- Phase 2 results. Revision 1  

SciTech Connect

This report presents the second phase of a study on thermal treatment technologies. The study consists of a systematic assessment of nineteen thermal treatment alternatives for the contact-handled mixed low-level waste (MLLW) currently stored in the US Department of Energy complex. The treatment alternatives consist of widely varying technologies for safely destroying the hazardous organic components, reducing the volume, and preparing for final disposal of the MLLW. The alternatives considered in Phase 2 were innovative thermal treatments with nine types of primary processing units. Other variations in the study examined the effect of combustion gas, air pollution control system design, and stabilization technology for the treatment residues. The Phase 1 study examined ten initial thermal treatment alternatives. The Phase 2 systems were evaluated in essentially the same manner as the Phase 1 systems. The alternatives evaluated were: rotary kiln, slagging kiln, plasma furnace, plasma gasification, molten salt oxidation, molten metal waste destruction, steam gasification, Joule-heated vitrification, thermal desorption and mediated electrochemical oxidation, and thermal desorption and supercritical water oxidation. The quantities, and physical and chemical compositions, of the input waste used in the Phase 2 systems differ from those in the Phase 1 systems, which were based on a preliminary waste input database developed at the onset of the Integrated Thermal Treatment System study. The inventory database used in the Phase 2 study incorporates the latest US Department of Energy information. All systems, both primary treatment systems and subsystem inputs, have now been evaluated using the same waste input (2,927 lb/hr). 28 refs., 88 figs., 41 tabs.

Feizollahi, F.; Quapp, W.J.

1996-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Water resources protection strategy: Revision 1, Attachment 4  

SciTech Connect

The US Department of Energy (DOE) must provide a demonstration of compliance with the final US Environmental Protection Agency (EPA) ground water protection standards for inactive mill sites pursuant to 40 CFR Part 192. This plan outlines the proposed strategy to demonstrate compliance with the ground water standards at the Maybell, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site. This demonstration consists of (1) the ground water protection standard, (2) a performance assessment, (3) a closure performance demonstration, and (4) a performance monitoring and corrective action program.

NONE

1996-12-10T23:59:59.000Z

82

TRAC-P validation test matrix. Revision 1.0  

SciTech Connect

This document briefly describes the elements of the Nuclear Regulatory Commission`s (NRC`s) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC`s software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort.

Hughes, E.D.; Boyack, B.E.

1997-09-05T23:59:59.000Z

83

Nevada Test Site Radiation Protection Program - Revision 1  

SciTech Connect

Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

Radiological Control Managers' Council

2008-06-01T23:59:59.000Z

84

EM Quaility Assurance Program (EM-QA-001 Revision 1)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM-QA-001 EM-QA-001 Rev. 1 Issue Date 06/11/12 2 Project lifecycles including design, engineering, construction, commissioning, operation, and post-operation, e.g., surveillance and maintenance, deactivation, decommissioning, and environmental restoration. 3.0 APPLICABILITY The requirements contained within this document apply to EM HQ, EM Field/Project Offices, and EM contractors (including flow down to subcontractors, vendors, and suppliers) as applicable to the work being performed by each entity. Each organization will have an organizational-specific Quality Assurance Implementation Plan (QIP) describing how the applicable requirements of this QAP are implemented and/or passed down to lower- tier organizations. This requirement does not alter personnel (i.e., federal, contractor, or

85

Battery Technology Life Verification Test Manual Revision 1  

SciTech Connect

The purpose of this Technology Life Verification Test (TLVT) Manual is to help guide developers in their effort to successfully commercialize advanced energy storage devices such as battery and ultracapacitor technologies. The experimental design and data analysis discussed herein are focused on automotive applications based on the United States Advanced Battery Consortium (USABC) electric vehicle, hybrid electric vehicle, and plug-in hybrid electric vehicle (EV, HEV, and PHEV, respectively) performance targets. However, the methodology can be equally applied to other applications as well. This manual supersedes the February 2005 version of the TLVT Manual (Reference 1). It includes criteria for statistically-based life test matrix designs as well as requirements for test data analysis and reporting. Calendar life modeling and estimation techniques, including a users guide to the corresponding software tool is now provided in the Battery Life Estimator (BLE) Manual (Reference 2).

Jon P. Christophersen

2012-12-01T23:59:59.000Z

86

DRAFT REVISION  

NLE Websites -- All DOE Office Websites (Extended Search)

4-1 4-1 Records Management Self-Assessment Revised Version Issued as P200.4-1B LM Procedure 200.4-1, Records Management Self-Assessment of 4/17/07, has undergone minor revisions. The procedure has been revised to reflect changes in definitions and formatting. Please replace LM Procedure 200.4-1A with LM Procedure 200.4-1B. The most recent and official controlled hard copy version of this document resides with LM's Directives Coordinator. An electronic version of the controlled document has been placed on the LM Intranet for employee use. Printed hard copies of this electronic version are considered uncontrolled documents. INITIATED BY: Office of Business Operations NO. OF PAGES/ATTACHMENTS: 8 pages, 2 attachments U.S. Department of Energy

87

DRAFT REVISION  

NLE Websites -- All DOE Office Websites (Extended Search)

Summary of Changes To Procedure 200.1-5 Records Disaster Prevention, Mitigation, and Recovery Procedure Revised Version Issued as P 200.1-5B LM Procedure 200.1-5, Records Disaster Prevention, Mitigation, and Recovery Procedure of 1/19/07, has undergone revisions. The procedure has been revised to reflect changes in definitions and formatting and updates to the attached Plan. Please replace LM Procedure 200.1-5A with LM Procedure 200.1-5B. The most recent and official controlled hard copy version of this document resides with LM's Directives Coordinator. An electronic version of the controlled document has been placed on the LM Intranet for employee use. Printed hard copies of this electronic version are considered uncontrolled documents.

88

Plutonium Focus Area research and development plan. Revision 1  

SciTech Connect

The Department of Energy (DOE) committed to a research and development program to support the technology needs for converting and stabilizing its nuclear materials for safe storage. The R and D Plan addresses five of the six material categories from the 94-1 Implementation Plan: plutonium (Pu) solutions, plutonium metals and oxides, plutonium residues, highly enriched uranium, and special isotopes. R and D efforts related to spent nuclear fuel (SNF) stabilization were specifically excluded from this plan. This updated plan has narrowed the focus to more effectively target specific problem areas by incorporating results form trade studies. Specifically, the trade studies involved salt; ash; sand, slag, and crucible (SS and C); combustibles; and scrub alloy. The plan anticipates possible disposition paths for nuclear materials and identifies resulting research requirements. These requirements may change as disposition paths become more certain. Thus, this plan represents a snapshot of the current progress and will continue to be updated on a regular basis. The paper discusses progress in safeguards and security, plutonium stabilization, special isotopes stabilization, highly-enriched uranium stabilization--MSRE remediation project, storage technologies, engineered systems, core technology, and proposed DOE/Russian technology exchange projects.

NONE

1996-11-01T23:59:59.000Z

89

Tank 41H bounding uranium enrichment. Revision 1  

Science Conference Proceedings (OSTI)

The intent of this document is to combine data from salt samples and historical process information to bound the uranium (U-235) enrichment which could be expected in the upper portion of the salt in Tank 41H. This bounding enrichment will be used in another document to establish a nuclear safety basis for initial salt removal operations. Any number of mixing scenarios could have been examined for the components which fed the evaporator during the formation of the last five feet of salt. The scenario presented was designed to be conservative, while still incorporating process knowledge and available data where possible. In the scenario, the lowest enrichment seen in any feed material was for the L4 feed which was evaporated to form the top part of the salt in Tank 41H. The lowest enrichment of 17% is still higher than the 16% (95% confidence) maximum enrichment actually found at the salt surface (from sample results). This leads to the conclusion that the uranium enrichment of the material (L1) which was being fed to the evaporate when the last five feet began to form, was lower than 22%. The conservatism used in this analysis, combined with the available sample data are believed to provide a defensible basis for establishing an upper bounding enrichment of 22% for the top five feet of salt.

Cavin, W.S.

1994-09-30T23:59:59.000Z

90

International energy: Research organizations, 1988--1992. Revision 1  

Science Conference Proceedings (OSTI)

This publication contains the standardized names of energy research organizations used in energy information databases. Involved in this cooperative task are (1) the technical staff of the US DOE Office of Scientific and Technical Information (OSTI) in cooperation with the member countries of the Energy Technology Data Exchange (ETDE) and (2) the International Nuclear Information System (INIS). ETDE member countries are also members of the International Nuclear Information System (INIS). Nuclear organization names recorded for INIS by these ETDE member countries are also included in the ETDE Energy Database. Therefore, these organization names are cooperatively standardized for use in both information systems. This publication identifies current organizations doing research in all energy fields, standardizes the format for recording these organization names in bibliographic citations, assigns a numeric code to facilitate data entry, and identifies report number prefixes assigned by these organizations. These research organization names may be used in searching the databases ``Energy Science & Technology`` on DIALOG and ``Energy`` on STN International. These organization names are also used in USDOE databases on the Integrated Technical Information System. Research organizations active in the past five years, as indicated by database records, were identified to form this publication. This directory includes approximately 31,000 organizations that reported energy-related literature from 1988 to 1992 and updates the DOE Energy Data Base: Corporate Author Entries.

Hendricks, P.; Jordan, S. [eds.] [USDOE Office of Scientific and Technical Information, Oak Ridge, TN (United States)

1993-06-01T23:59:59.000Z

91

The mixed waste management facility. Project baseline revision 1.2  

Science Conference Proceedings (OSTI)

Revision 1.2 to the Project Baseline (PB) for the Mixed Waste Management Facility (MWMF) is in response to DOE directives and verbal guidance to (1) Collocate the Decontamination and Waste Treatment Facility (DWTF) and MWMF into a single complex, integrate certain and overlapping functions as a cost-saving measure; (2) Meet certain fiscal year (FY) new-BA funding objectives ($15.3M in FY95) with lower and roughly balanced funding for out years; (3) Reduce Total Project Cost (TPC) for the MWMF Project; (4) Include costs for all appropriate permitting activities in the project TPC. This baseline revision also incorporates revisions in the technical baseline design for Molten Salt Oxidation (MSO) and Mediated Electrochemical Oxidation (MEO). Changes in the WBS dictionary that are necessary as a result of this rebaseline, as well as minor title changes, at WBS Level 3 or above (DOE control level) are approved as a separate document. For completeness, the WBS dictionary that reflects these changes is contained in Appendix B. The PB, with revisions as described in this document, were also the basis for the FY97 Validation Process, presented to DOE and their reviewers on March 21-22, 1995. Appendix C lists information related to prior revisions to the PB. Several key changes relate to the integration of functions and sharing of facilities between the portion of the DWTF that will house the MWMF and those portions that are used by the Hazardous Waste Management (HWM) Division at LLNL. This collocation has been directed by DOE as a cost-saving measure and has been implemented in a manner that maintains separate operational elements from a safety and permitting viewpoint. Appendix D provides background information on the decision and implications of collocating the two facilities.

Streit, R.D.; Throop, A.L.

1995-04-01T23:59:59.000Z

92

Fiscal year 1998 Battelle performance evaluation agreement revision 1  

SciTech Connect

Fiscal Year 1998 represents the second full year utilizing a results-oriented, performance-based contract. This document describes the critical outcomes, objectives, performance indicators, expected levels of performance, and the basis for the evaluation of the Contractors performance for the period October 1, 1997 through September 30, 1998, as required by Articles entitled Use of Objective Standards of Performance, Self Assessment and Performance Evaluation and Critical Outcomes Review of the Contract DE-AC08-76RLO1830. In partnership with the Contractor and other key customers, the Department of Energy (DOE) Richland Operations Office has defined six critical outcomes that same as the core for the Contractors performance evaluation. The Contractor also utilizes these outcomes as a basis for overall management of the Laboratory. As stated above six critical outcomes have been established for FY 1998. These outcomes are based on the following needs identified by DOE-HQ, RL and other customers of the Laboratory. Our Energy Research customer desires relevant, quality and cost effective science. Our Environmental Management customer wants technology developed, demonstrated, and deployed to solve environmental cleanup issues. To ensure the diversification and viability of the Laboratory as a National asset, RL and HQ alike want to increase the Science and Technical contributions of PNNL related to its core capabilities. RL wants improved leadership/management, cost-effective operations, and maintenance of a work environment, which fosters innovative thinking and high morale. RL and HQ alike desire compliance with environment, safety and health (ES and H) standards and disciplined conduct of operations for protection of the worker, environment, and the public, As with all of Hanford, DOE expects contribution of the Laboratory to the economic development of the Tri-Cities community, and the region, to build a new local economy that is less reliant on the Hanford mission, as well as enhancing the status of the Laboratory as a valued corporate citizen of the Northwest Region. The Critical Outcome system focuses all of these customer desires into specific objectives and performance indicators, with supporting measures to track and foster continued improvement in meeting the needs (outcomes) of the Laboratory's customers.

DAVIS, T.L.

1998-10-22T23:59:59.000Z

93

DRAFT REVISION  

NLE Websites -- All DOE Office Websites (Extended Search)

Summary of Changes Summary of Changes to Procedure 243.1 Records Inventory Revised Version Issued as P 243.1B LM Procedure 243.1A, Records Inventory of 7/18/07, has undergone minor revisions. The procedure has been revised to reflect changes in definitions and formatting and to ensure the references cited and associated forms remain current. Please replace LM Procedure 243.1A with LM Procedure 243.1B. The most recent and official controlled hard copy version of this document resides with LM's Directives Coordinator. An electronic version of the controlled document has been placed on the LM Intranet for employee use. Printed hard copies of this electronic version are considered uncontrolled documents. INITIATED BY: Office of Business Operations NO. OF PAGES/ATTACHMENTS: 9 pages, 3 attachments

94

JM-DOE O 200.1A, Notice of Intent to Revise DOE O 200.1A, Information Technology Management  

Directives, Delegations, and Requirements

Although DOEO 200.1A was revised in December 2008, there have been significant changes in IT governance processes and Departmental use of new technologies such ...

2011-12-15T23:59:59.000Z

95

JM to Revise DOE O 320.1, Acquiring and Positioning Human Resources  

Directives, Delegations, and Requirements

The revision clarifies provisions in regulations and assists in the administration of human capital programs.

2011-09-15T23:59:59.000Z

96

773revision:2002-01-18modified:2002-01-19 Cotorsion theories cogenerated by 1-free abelian groups  

E-Print Network (OSTI)

773revision:2002-01-18modified:2002-01-19 Cotorsion theories cogenerated by 1-free abelian groups of the cotorsion class singly cogenerated by a torsion-free group G. Cotorsion theories were introduced by Salce

Shelah, Saharon

97

Portland General Electric Company Second Revision of Sheet No. 7-1 P.U.C. Oregon No. E-17 Canceling First Sheet No. 7-1  

E-Print Network (OSTI)

Portland General Electric Company Second Revision of Sheet No. 7-1 P.U.C. Oregon No. E-17 Canceling on and after January 1, 2003 #12;Portland General Electric Company First Revision of Sheet No. 7-2 PWh in addition to Energy Charge Renewable Usage 0.800¢ per kWh in addition to Energy Charge Fixed Renewable $3

98

Columbia nano 02-02.ppt revised 02/26/02 jty Page 1 ColumbiaUniversityintheCityofNewYorkintheCityofNewYork  

E-Print Network (OSTI)

Columbia nano 02-02.ppt revised 02/26/02 jty Page 1 Columbia. Yardley Director, Center for Integrated Science and Engineering #12;Columbia nano 02-02.ppt revised 02;Columbia nano 02-02.ppt revised 02/26/02 jty Page 3 Columbia

Kim, Philip

99

REVISED-FINAL-1ST-QUARTER-FY-2013-SCORECARD-09-05-13.xlsx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-SCORECARD-09-05-13.xlsx 3-SCORECARD-09-05-13.xlsx Page 1 of 95 EA & PEA MILESTONES MET DURING QUARTER (10/2012 - 12/2012) / TOTAL QUARTER EA & PEA MILESTONES ON SCHEDULE EA & PEA MILESTONES NEXT FOUR QUARTERS (01/2013 - 12/2013) / TOTAL FOUR QUARTERS EA & PEA MILESTONES Argonne (ANL) GREEN N / A (0 / 0) N / A (0 / 0) N / A N / A N / A Brookhaven (BNL) GREEN GREEN (1 / 1) GREEN (0 / 0) N / A N / A N / A Carlsbad / Waste Isolation Pilot Plant (CBFO / WIPP) GREEN N / A (0 / 0) N / A (0 / 0) N / A N / A SA Completed Energy Technology Engineering Center (ETEC) GREEN GREEN (0 / 0) GREEN (0 / 0) N / A N / A EIS Idaho (INL) GREEN GREEN (2 / 2) GREEN (7 / 7) N / A PA Revision ROD Lawrence Livermore National Laboratory (LLNL) GREEN GREEN (0 / 0) GREEN (1 / 1) N / A N / A N / A Los Alamos National Laboratory (LANL)

100

Dry Natural Gas Estimated Production (Summary)  

Annual Energy Outlook 2012 (EIA)

274 257 254 223 218 1977-2011 Alaska 408 388 354 358 317 327 1977-2011 Arkansas 188 269 456 698 951 1,079 1977-2011 California 255 253 237 239 243 311 1977-2011 Colorado 1,174...

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Liquid effluent FY 1996 program plan WBS 1.2.2.1. Revision 1  

Science Conference Proceedings (OSTI)

The Liquid Effluents Program supports the three Hanford Site mission components: (1) Clean up the site, (2) provide scientific and technological excellence to meet global needs, and (3) Partner in the economic diversification of the region. Nine Hanford Site objectives have been established for the Hanford Site programs to accomplish all three components of this mission.

NONE

1995-09-01T23:59:59.000Z

102

Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1  

SciTech Connect

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

NONE

1995-08-01T23:59:59.000Z

103

Feasibility study of tank leakage mitigation using subsurface barriers. Revision 1  

SciTech Connect

This document reflects the evaluations and analyses performed in response to Tri-Party Agreement Milestone M-45-07A - {open_quotes}Complete Evaluation of Subsurface Barrier Feasibility{close_quotes} (September 1994). In addition, this feasibility study was revised reflecting ongoing work supporting a pending decision by the DOE Richland Operations Office, the Washington State Department of Ecology, and the US Environmental Protection Agency regarding further development of subsurface barrier options for SSTs and whether to proceed with demonstration plans at the Hanford Site (Tri-Party Agreement Milestone M-45-07B). Analyses of 14 integrated SST tank farm remediation alternatives were conducted in response to the three stated objectives of Tri-Party Agreement Milestone M-45-07A. The alternatives include eight with subsurface barriers and six without. Technologies used in the alternatives include three types of tank waste retrieval, seven types of subsurface barriers, a method of stabilizing the void space of emptied tanks, two types of in situ soil flushing, one type of surface barrier, and a clean-closure method. A no-action alternative and a surface-barrier-only alternative were included as nonviable alternatives for comparison. All other alternatives were designed to result in closure of SST tank farms as landfills or in clean-closure. Revision 1 incorporates additional analyses of worker safety, large leak scenarios, and sensitivity to the leach rates of risk controlling constituents. The additional analyses were conducted to support TPA Milestone M-45-07B.

Treat, R.L.; Peters, B.B.; Cameron, R.J. [Enserch Environmental, Inc., Richland, WA (United States)] [and others

1995-01-01T23:59:59.000Z

104

Michigan Dry Natural Gas Proved Reserves  

U.S. Energy Information Administration (EIA) Indexed Site

065 3,630 3,174 2,763 2,919 2,505 1977-2011 Adjustments 112 -45 -48 -279 243 8 1977-2011 Revision Increases 460 780 143 367 260 210 1977-2011 Revision Decreases 291 210 430 406 378...

105

Dry Natural Gas New Reservoir Discoveries in Old Fields  

U.S. Energy Information Administration (EIA) Indexed Site

1,155 1,188 1,622 2,598 1,668 1,227 1977-2011 1,155 1,188 1,622 2,598 1,668 1,227 1977-2011 Federal Offshore U.S. 410 368 532 300 237 76 1990-2011 Pacific (California) 1 0 0 0 0 0 1977-2011 Louisiana & Alabama 343 330 379 223 213 76 1981-2011 Texas 66 38 153 77 24 0 1981-2011 Alaska 2 0 5 0 0 3 1977-2011 Lower 48 States 1,153 1,188 1,617 2,598 1,668 1,224 1977-2011 Alabama 7 17 1 0 0 0 1977-2011 Arkansas 32 27 41 36 27 23 1977-2011 California 4 1 14 0 0 0 1977-2011 Coastal Region Onshore 0 0 0 0 0 0 1977-2011 Los Angeles Basin Onshore 0 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 1 1 14 0 0 0 1977-2011 State Offshore 3 0 0 0 0 0 1977-2011 Colorado 26 23 17 0 27 0 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 3 0 2 0 1 1 1977-2011

106

Dry Natural Gas New Reservoir Discoveries in Old Fields  

Gasoline and Diesel Fuel Update (EIA)

1,155 1,188 1,622 2,598 1,668 1,227 1977-2011 1,155 1,188 1,622 2,598 1,668 1,227 1977-2011 Federal Offshore U.S. 410 368 532 300 237 76 1990-2011 Pacific (California) 1 0 0 0 0 0 1977-2011 Louisiana & Alabama 343 330 379 223 213 76 1981-2011 Texas 66 38 153 77 24 0 1981-2011 Alaska 2 0 5 0 0 3 1977-2011 Lower 48 States 1,153 1,188 1,617 2,598 1,668 1,224 1977-2011 Alabama 7 17 1 0 0 0 1977-2011 Arkansas 32 27 41 36 27 23 1977-2011 California 4 1 14 0 0 0 1977-2011 Coastal Region Onshore 0 0 0 0 0 0 1977-2011 Los Angeles Basin Onshore 0 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 1 1 14 0 0 0 1977-2011 State Offshore 3 0 0 0 0 0 1977-2011 Colorado 26 23 17 0 27 0 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 3 0 2 0 1 1 1977-2011

107

Revision History  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revision History Revision History Rev. 0, August 2012 Original submittal for milestone M3FT-12SN0804032 (Sandia programmatic and classification review) Rev. 1, September 2012 Corrected transposition errors in costing tables; recalculated stainless steel overpacks to be carbon steel; corrected various editorial problems. (SAND2012-7979P) Rev. 2, November 2012 Performed peer review and retitled. Submittal for milestone M2FT-13SN0804031 (formerly milestone M2FT- 12SN0804031) (SAND2012-9737P) Unclassified Unlimited Release Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

108

JM to Revise DOE G 414.1-4, Safety Software Guide for Use with 10 CFR 830, Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance  

Directives, Delegations, and Requirements

The revision to DOE G 414.1-4 will conform to the revised DOE O 414.1D and incorporate new information and lessons learned since 2005, including information ...

2013-07-17T23:59:59.000Z

109

Codes and standards and other guidance cited in regulatory documents. Revision 1  

Science Conference Proceedings (OSTI)

As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800).

Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R. [Pacific Northwest Lab., Richland, WA (United States)

1994-08-01T23:59:59.000Z

110

New Field Discoveries of Dry Natural Gas Reserves  

U.S. Energy Information Administration (EIA) Indexed Site

409 796 1,170 1,372 850 947 1977-2011 409 796 1,170 1,372 850 947 1977-2011 Federal Offshore U.S. 111 608 311 308 68 562 1990-2011 Pacific (California) 0 0 0 0 0 0 1977-2011 Louisiana & Alabama 82 304 279 48 68 562 1981-2011 Texas 29 304 32 260 0 0 1981-2011 Alaska 0 0 0 0 0 0 1977-2011 Lower 48 States 409 796 1,170 1,372 850 947 1977-2011 Alabama 0 0 2 0 3 2 1977-2011 Arkansas 7 0 0 0 0 0 1977-2011 California 0 0 0 1 1 0 1977-2011 Coastal Region Onshore 0 0 0 0 0 0 1977-2011 Los Angeles Basin Onshore 0 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 0 0 0 1 1 0 1977-2011 State Offshore 0 0 0 0 0 0 1977-2011 Colorado 14 15 17 8 22 18 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 0 0 9 0 4 0 1977-2011 Kentucky

111

New Field Discoveries of Dry Natural Gas Reserves  

Gasoline and Diesel Fuel Update (EIA)

409 796 1,170 1,372 850 947 1977-2011 409 796 1,170 1,372 850 947 1977-2011 Federal Offshore U.S. 111 608 311 308 68 562 1990-2011 Pacific (California) 0 0 0 0 0 0 1977-2011 Louisiana & Alabama 82 304 279 48 68 562 1981-2011 Texas 29 304 32 260 0 0 1981-2011 Alaska 0 0 0 0 0 0 1977-2011 Lower 48 States 409 796 1,170 1,372 850 947 1977-2011 Alabama 0 0 2 0 3 2 1977-2011 Arkansas 7 0 0 0 0 0 1977-2011 California 0 0 0 1 1 0 1977-2011 Coastal Region Onshore 0 0 0 0 0 0 1977-2011 Los Angeles Basin Onshore 0 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 0 0 0 1 1 0 1977-2011 State Offshore 0 0 0 0 0 0 1977-2011 Colorado 14 15 17 8 22 18 1977-2011 Florida 0 0 0 0 0 0 1977-2011 Kansas 0 0 9 0 4 0 1977-2011 Kentucky

112

Technical assessment of TRUSAF for compliance with work place air sampling. Revision 1  

Science Conference Proceedings (OSTI)

The purpose of this Technical Work Document is to satisfy WHC-CM-1-6, the ``WHC Radiological Control Manual.`` This first revision of the original Supporting Document covers the period from January 1, 1994 to December 31, 1994. WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ``Hanford Site Radiological Control Manual`` and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. this document also provides an evaluation of the compliance of the TRUSAF workplace air sampling program to the criteria, standards, and requirements and documents. Where necessary, it also indicates changes needed to bring specific locations into compliance.

Butler, J.D.

1995-01-23T23:59:59.000Z

113

UNBC HPC Policy last revised: 2/1/2007, 2:49:29 PM UNBC Enhanced High Performance Computing Center  

E-Print Network (OSTI)

UNBC HPC Policy last revised: 2/1/2007, 2:49:29 PM UNBC Enhanced High Performance Computing Center and contracts are sought by Principal Investigators. Membership Policies The UNBC Enhanced High Performance Computing Center (called " UNBC HPC" hereafter) provides computing resources and services to members

Northern British Columbia, University of

114

Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1  

SciTech Connect

This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B&W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the B&W Owners Group (BWOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

NONE

1995-04-01T23:59:59.000Z

115

Technical Review Report for the Mound 1KW Package Safety Analysis Report for Packaging Addendum No. 1, through Revision b  

SciTech Connect

This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) staff, at the request of the U.S. Department of Energy (DOE), on the 'Mound 1KW Package Safety Analysis Report for Packaging, Addendum No. 1, Revision b', dated May 2007 (Addendum 1). The Mound 1KW Package is certified by DOE Certificate of Compliance (CoC) number USA/9516/B(U)F-85 for the transportation of Type B quantities of plutonium heat source material. The safety analysis of the package is documented in the 'Safety Analysis Report for Packaging (SARP) for the Mound 1KW Package' (i.e., the Mound 1KW SARP, or the SARP). Addendum 1 incorporates a new fueled capsule assembly payload. The following changes have been made to add this payload: (1) The primary containment vessel (PCV) will be of the same design, but will increase in height to 11.16 in.; (2) A new graphite support block will be added to support up to three fueled capsule assemblies per package; (3) The cutting groove height on the secondary containment vessel (SCV) will be heightened to accommodate the taller PCV; and (4) A 3.38 in. high graphite filler block will be placed on top of the PCV. All other packaging features, as described in the Mound 1KW SARP [3], remain unchanged. This report documents the LLNL review of Addendum 1[1]. The specific review for each SARP Chapter is documented herein.

DiSabatino, A; West, M; Hafner, R; Russell, E

2007-10-04T23:59:59.000Z

116

Dry Natural Gas Estimated Production (Summary)  

Gasoline and Diesel Fuel Update (EIA)

8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 Federal Offshore Gulf of Mexico 2,738 NA 1992-2007 Alabama 287 274 257 254 223 218 1977-2011 Alaska 408 388 354 358 317 327 1977-2011 Arkansas 188 269 456 698 951 1,079 1977-2011 California 255 253 237 239 243 311 1977-2011 Colorado 1,174 1,326 1,441 1,524 1,590 1,694 1977-2011 Florida 2 4 3 0 15 0 1977-2011 Kansas 350 361 357 334 305 285 1977-2011 Kentucky 66 80 93 108 96 101 1977-2011 Louisiana 1,309 1,257 1,319 1,544 2,189 2,985 1981-2011 Michigan 197 184 157 153 154 139 1977-2011 Mississippi 83 100 110 100 87 75 1977-2011 Montana 117 112 114 113 93 75 1977-2011 New Mexico 1,426 1,349 1,349 1,350 1,220 1,170 1977-2011 New York

117

Dry Natural Gas Reserves Adjustments  

Gasoline and Diesel Fuel Update (EIA)

743 1,147 207 5,098 509 1,731 1977-2011 743 1,147 207 5,098 509 1,731 1977-2011 Federal Offshore U.S. -39 -62 14 22 -123 -28 1990-2011 Pacific (California) 2 -7 -1 0 0 -1 1977-2011 Louisiana & Alabama -37 -16 10 2 -106 -28 1981-2011 Texas -4 -39 5 20 -17 1 1981-2011 Alaska -46 1 -3 3 1 -1 1977-2011 Lower 48 States 789 1,146 210 5,095 508 1,732 1977-2011 Alabama -11 12 -71 46 32 -49 1977-2011 Arkansas -26 -27 -64 5 -34 728 1977-2011 California -74 33 -6 11 10 923 1977-2011 Coastal Region Onshore -62 3 0 2 1 13 1977-2011 Los Angeles Basin Onshore 0 0 2 5 5 7 1977-2011 San Joaquin Basin Onshore -12 31 -8 2 4 902 1977-2011 State Offshore 0 -1 0 2 0 1 1977-2011 Colorado 52 136 -250 306 449 801 1977-2011 Florida 2 4 79 6 64 -54 1977-2011

118

Dry Natural Gas Reserves Adjustments  

U.S. Energy Information Administration (EIA) Indexed Site

743 1,147 207 5,098 509 1,731 1977-2011 743 1,147 207 5,098 509 1,731 1977-2011 Federal Offshore U.S. -39 -62 14 22 -123 -28 1990-2011 Pacific (California) 2 -7 -1 0 0 -1 1977-2011 Louisiana & Alabama -37 -16 10 2 -106 -28 1981-2011 Texas -4 -39 5 20 -17 1 1981-2011 Alaska -46 1 -3 3 1 -1 1977-2011 Lower 48 States 789 1,146 210 5,095 508 1,732 1977-2011 Alabama -11 12 -71 46 32 -49 1977-2011 Arkansas -26 -27 -64 5 -34 728 1977-2011 California -74 33 -6 11 10 923 1977-2011 Coastal Region Onshore -62 3 0 2 1 13 1977-2011 Los Angeles Basin Onshore 0 0 2 5 5 7 1977-2011 San Joaquin Basin Onshore -12 31 -8 2 4 902 1977-2011 State Offshore 0 -1 0 2 0 1 1977-2011 Colorado 52 136 -250 306 449 801 1977-2011 Florida 2 4 79 6 64 -54 1977-2011

119

6ka_PanMonsoons , Liu et al., final revision, 09/05/2003 1 Global Monsoons in the mid-Holocene and Oceanic Feedback*  

E-Print Network (OSTI)

6ka_PanMonsoons , Liu et al., final revision, 09/05/2003 1 Global Monsoons in the mid., Madison, WI 53706; zliu3@wisc.edu #12;6ka_PanMonsoons , Liu et al., final revision, 09/05/2003 2 Abstract The response of the six major summer monsoon systems (the North American monsoon, the northern Africa monsoon

Wisconsin at Madison, University of

120

*Revisions to POS List, i.e. updates, additions and/or deletions NILAND GAS TURBINE PLANT, DOCKET NO.O6-SPPE-1  

E-Print Network (OSTI)

*Revisions to POS List, i.e. updates, additions and/or deletions NILAND GAS TURBINE PLANT, DOCKET OF CALIFORNIA SMALL POWER PLANT EXEMPTION FOR THE NILAND GAS TURBINE PLANT DOCKET NO. 06-SPPE-1 (Imperial_hahn@urscorp.com #12;*Revisions to POS List, i.e. updates, additions and/or deletions NILAND GAS TURBINE PLANT, DOCKET

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Florida Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

Wellhead Wellhead NA NA NA NA 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 7.97 9.73 5.76 5.49 5.07 3.93 1984-2012 Residential 20.61 21.07 20.18 17.89 18.16 18.31 1967-2012 Commercial 13.07 14.45 11.09 10.60 11.14 10.41 1967-2012 Industrial 10.56 11.72 9.41 8.33 8.07 6.96 1997-2012 Vehicle Fuel 12.82 15.56 13.16 17.98 5.56 9.83 1989-2012 Electric Power 9.35 10.41 7.90 6.54 5.86 4.80 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 108 1 7 56 6 1977-2011 Adjustments 4 79 6 64 -54 1977-2011 Revision Increases 110 0 0 0 13 1977-2011 Revision Decreases 0 183 0 0 9 1977-2011 Sales 47 0 0 0 0 2000-2011 Acquisitions 0 0 0 0 0 2000-2011 Extensions 0 0 0 0 0 1977-2011

122

Addendum to Revision 1 of the Corrective Action Investigation Plan for Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nevada (Addendum Revision No. 1)  

SciTech Connect

This document is submitted as an addendum to the Corrective Action Investigation Plan (CAIP) for Corrective Action Unit (CAU) 98: Frenchman Flat, Nevada Test Site (NTS), Nevada. The addendum was prepared to propose work activities in response to comments resulting from the U.S. Department of Energy's (DOE's) review of the draft Frenchman Flat CAU model of groundwater flow and contaminant transport completed in April 1999. The reviewers included an external panel of experts and the Nevada Division of Environmental Protection. As a result of the review, additional work scope, including new data-collection and modeling activities, has been identified for the Frenchman Flat CAU. The proposed work scope described in this addendum will be conducted in accordance with the revised Underground Test Area strategy contained in the December 2000 amendment to the Federal Facility Agreement and Consent Order. The Frenchman Flat CAU model is a group of interdependent models designed to predict the extent of contamination in groundwater due to the underground nuclear tests conducted within this CAU. At the time of the DOE review, the CAU model consisted of a CAU groundwater flow and transport model comprised of two major components: a groundwater flow model and a recharge model. The CAU groundwater flow model is supported by a hydrostratigraphic model and a recharge model, whereas the CAU transport model is supported by a source-term model. As part of the modeling activities proposed in this addendum, two new major components may be added to the Frenchman Flat CAU model: a total-system model and two local groundwater flow and transport models. The reviewers identified several issues relating to insufficiency of data and inadequacy of the modeling process that should be addressed to provide additional confidence in the modeling results with respect to the potential for contaminant migration to the Lower Carbonate Aquifer. The proposed additional work scope includes new data-collection activities, development and use of local-scale models of the two underground nuclear testing areas, and potential revisions of draft CAU groundwater flow and transport models. Upon completion of this work, an evaluation will be made by DOE to ensure that all issues have been resolved.

U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office

2001-06-06T23:59:59.000Z

123

Y-12 Groundwater Protection Program Groundwater Monitoring Data Compendium, Revision 1  

SciTech Connect

This document is a compendium of water quality and hydrologic characterization data obtained through December 2005 from the network of groundwater monitoring wells and surface water sampling stations (including springs and building sumps) at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee that have been sampled since January 2003. The primary objectives of this document, hereafter referenced as the Y-12 Groundwater Protection Program (GWPP) Compendium, are to: (1) Serve as a single-source reference for monitoring data that meet the requirements of the Y-12 GWPP, as defined in the Y-12 GWPP Management Plan (BWXT Y-12 L.L.C. [BWXT] 2004); (2) Maintain a detailed analysis and evaluation of the monitoring data for each applicable well, spring, and surface water sampling station, with a focus on results for the primary inorganic, organic, and radiological contaminants in groundwater and surface water at Y-12; and (3) Ensure retention of ''institutional knowledge'' obtained over the long-term (>20-year) history of groundwater and surface water monitoring at Y-12 and the related sources of groundwater and surface water contamination. To achieve these goals, the Y-12 GWPP Compendium brings together salient hydrologic, geologic, geochemical, water-quality, and environmental compliance information that is otherwise disseminated throughout numerous technical documents and reports prepared in support of completed and ongoing environmental contamination assessment, remediation, and monitoring activities performed at Y-12. The following subsections provide background information regarding the overall scope and format of the Y-12 GWPP Compendium and the planned approach for distribution and revision (i.e., administration) of this ''living'' document.

None

2006-12-01T23:59:59.000Z

124

Foodservice Sourcebook: A Quick-Reference Guide to Industry Information and Sources (Revision 1)  

Science Conference Proceedings (OSTI)

The directories in this first revision of the foodservice sourcebook contain 1989 information relevant to the foodservice industry. Included is material on commercial equipment, associations, electric utility contacts and activities, and 10 categories of leading foodservice operators. This concise updated reference will help utilities better understand and serve the foodservice industry.

1990-04-01T23:59:59.000Z

125

FGD Chemistry and Analytical Methods Handbook, Volume 2: Chemical and Physical Test Methods, Revision 1  

Science Conference Proceedings (OSTI)

Utilities operating flue gas desulfurization (FGD) systems can increase system reliability and reduce operating costs by monitoring and controlling process chemistry. A revision of volume 2 of this handbook, an industry standard for FGD chemistry labs, incorporates the latest advances in FGD analytical chemistry and introduces methods for determining liquid-phase thiosulfate and boron concentrations.

1988-11-01T23:59:59.000Z

126

COL Application Content Guide for HTGRs: Revision to RG 1.206, Part 1 - Status Report  

SciTech Connect

A combined license (COL) application is required by the Nuclear Regulatory Commission (NRC) for all proposed nuclear plants. The information requirements for a COL application are set forth in 10 CFR 52.79, Contents of Applications; Technical Information in Final Safety Analysis Report. An applicant for a modular high temperature gas-cooled reactor (HTGR) must develop and submit for NRC review and approval a COL application which conforms to these requirements. The technical information necessary to allow NRC staff to evaluate a COL application and resolve all safety issues related to a proposed nuclear plant is detailed and comprehensive. To this, Regulatory Guide (RG) 1.206, Combined License Applications for Nuclear Power Plants (LWR Edition), was developed to assist light water reactor (LWR) applicants in incorporating and effectively formatting required information for COL application review (Ref. 1). However, the guidance prescribed in RG 1.206 presumes a LWR design proposal consistent with the systems and functions associated with large LWR power plants currently operating under NRC license.

Wayne Moe

2012-08-01T23:59:59.000Z

127

APS beamline standard components handbook, Version 1.3. Revision 1  

SciTech Connect

This Handbook in its current version (1.3) contains descriptions, specifications, and preliminary engineering design drawings for many of the standard components. The design status and schedules have been provided wherever possible. In the near future, the APS plans to update engineering drawings of identified standard beamline components and complete the Handbook. The completed version of this Handbook will become available to both the CATs and potential vendors. Use of standard components should result in major cost reductions for CATs in the areas of beamline design and construction.

Hahn, U.; Shu, D.; Kuzay, T.M.

1993-02-01T23:59:59.000Z

128

Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1  

DOE Green Energy (OSTI)

This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade.

Schlosser, R.L.

1996-02-05T23:59:59.000Z

129

A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)  

Science Conference Proceedings (OSTI)

EPRI's seismic margin methodology enables utility engineers to quantify a nuclear power plant's ability to withstand an earthquake greater than design and still safely shut down for at least 72 hours. This cost-effective, practical methodology uses generic screening of systems and component seismic ruggedness and does not require probabilistic calculations. The revision adds depth, detail, and more complete procedures to the original report but does not change the basic method.

1991-08-01T23:59:59.000Z

130

Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2  

SciTech Connect

The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site`s preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised.

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1995-07-13T23:59:59.000Z

131

Waste generation forecast for DOE-ORO`s Environmental Restoration OR-1 Project: FY 1995-FY 2002, September 1994 revision  

Science Conference Proceedings (OSTI)

A comprehensive waste-forecasting task was initiated in FY 1991 to provide a consistent, documented estimate of the volumes of waste expected to be generated as a result of U.S. Department of Energy-Oak Ridge Operations (DOE-ORO) Environmental Restoration (ER) OR-1 Project activities. Continual changes in the scope and schedules for remedial action (RA) and decontamination and decommissioning (D&D) activities have required that an integrated data base system be developed that can be easily revised to keep pace with changes and provide appropriate tabular and graphical output. The output can then be analyzed and used to drive planning assumptions for treatment, storage, and disposal (TSD) facilities. The results of this forecasting effort and a description of the data base developed to support it are provided herein. The initial waste-generation forecast results were compiled in November 1991. Since the initial forecast report, the forecast data have been revised annually. This report reflects revisions as of September 1994.

Not Available

1994-12-01T23:59:59.000Z

132

Long-Term Surveillance Plan for the Burrell Vicinity Property, Blairsville, Pennsylvania, GJO-2002-331-TAR, MAC-LBUR 1.1, Revised April 2000  

NLE Websites -- All DOE Office Websites (Extended Search)

Long-Term Surveillance and Maintenance Program Long-Term Surveillance and Maintenance Program Long-Term Surveillance Plan for the U.S. Department of Energy Burrell Vicinity Property Blairsville, Pennsylvania April 2000 Revised This document supersedes document number UMTRA-DOE/AL/62350-3F Ver.2, Rev.2 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work Performed Under DOE Contract Number DE-AC13-96GJ87335 Task Order Number MAC 00-06 Document Number S00350 DOE/Grand Junction Office LTSP for Burrell April 2000 Revision Page iii Contents 1.0 Introduction ........................................................................................................................ 1-1 1.1 Purpose ..................................................................................................................... 1-1

133

Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Volume 1  

Science Conference Proceedings (OSTI)

The 1995 Hanford Mission Plan specifically addresses the tank waste issue and clarifies the link with other initiatives, such as improving management practices and the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE/RL-91-31). This document captures the results of decision making regarding the application of systems engineering at the Hanford Site, external involvement policy, and site end-state goals. Section 3.5 of the Hanford Mission Plan on Decisions and Directives provides an integrating discussion of the actions of the National Environmental Policy Act (NEPA), and DOE policy, guidance, and decisions associated with binding agreements such as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Two significant components of the Hanford Mission Plan 1994 planning basis are (1) the decisions regarding the disposition of onsite material inventory, and the key programs and interfaces to accomplish this; and (2) the Program Interface Issues section, which identified issues that stretch across program boundaries.

NONE

1995-09-01T23:59:59.000Z

134

REVISION POLICY  

U.S. Energy Information Administration (EIA) Indexed Site

REVISION POLICY REVISION POLICY March 2007 Data are collected at the million cubic feet per month level and all calculations mentioned below are carried out at that precision. However, the data published in the Form EIA-914 Monthly Gas Production Report are rounded to the nearest 0.01 billion cubic feet per day (roughly 300 million cubic feet per month). Monthly estimates of gross production published in the Natural Gas Monthly at the national level are rounded to billion cubic feet and those for marketed production at the State level are rounded to million cubic feet. The prior month's production estimate will always be revised each month, when the production estimate for the latest data month is released. For example, a June estimate would be revised when a July estimate is released.

135

JM to Revise DOE O 350.1, Notice of Intent to Revise Department of Energy Order 350.1, Contractor Human Resources Management Program  

Directives, Delegations, and Requirements

DOE O 350.1 establishes responsibilities, requirements, and cost allow-ability criteria for the management an oversight of contractor human resource management ...

2012-10-19T23:59:59.000Z

136

Engineering work plan for container venting system drill press assembly troubleshooting. Revision 1  

SciTech Connect

This work plan is for troubleshooting the current CVS drill press to ensure that the drill bit assembly doesn`t bind in the press plate. A drill press assembly has been fabricated for the Container Venting System (CVS). The drill bit assembly has bound in the press plate in previous revisions of this design. Initial troubleshooting of the drill press per Rev. 0 of this work plan was performed at the 200W Kaiser Machine Shop under Work Package 2H9401670F, Internal Work Order E20027. The drill press operated without jamming. Then, during the pre-operational test on 11/14/17 and the operational test on 11/17/94, two drum lids were drilled. Immediately after the test on 11/17/94, the drill was again operated, and it jammed. An inspection found shavings at the bottom of the drill bit assembly, between the drill bit sleeve and the press plate bore. This revised work plan provides direction for the machine shop to diagnose and correct this recent problem.

Prather, M.C.

1994-11-01T23:59:59.000Z

137

Preliminary environmental assessment for the Satellite Power System (SPS). Revision 1. Volume 2. Detailed assessment  

DOE Green Energy (OSTI)

The Department of Energy (DOE) is considering several options for generating electrical power to meet future energy needs. The satellite power system (SPS), one of these options, would collect solar energy through a system of satellites in space and transfer this energy to earth. A reference system has been described that would convert the energy to microwaves and transmit the microwave energy via directive antennas to large receiving/rectifying antennas (rectennas) located on the earth. At the rectennas, the microwave energy would be converted into electricity. The potential environmental impacts of constructing and operating the satellite power system are being assessed as a part of the Department of Energy's SPS Concept Development and Evaluation Program. This report is Revision I of the Preliminary Environmental Assessment for the Satellite Power System published in October 1978. It refines and extends the 1978 assessment and provides a basis for a 1980 revision that will guide and support DOE recommendations regarding future SPS development. This is Volume 2 of two volumes. It contains the technical detail suitable for peer review and integrates information appearing in documents referenced herein. The key environmental issues associated with the SPS concern human health and safety, ecosystems, climate, and electromagnetic systems interactions. In order to address these issues in an organized manner, five tasks are reported: (I) microwave-radiation health and ecological effects; (II) nonmicrowave health and ecological effectss; (III) atmospheric effects; (IV) effects on communication systems due to ionospheric disturbance; and (V) electromagnetic compatibility. (WHK)

Not Available

1980-01-01T23:59:59.000Z

138

Dry Natural Gas Reserves Extensions  

U.S. Energy Information Administration (EIA) Indexed Site

21,778 27,107 26,687 42,139 44,783 45,909 1977-2011 21,778 27,107 26,687 42,139 44,783 45,909 1977-2011 Federal Offshore U.S. 733 657 903 289 326 94 1990-2011 Pacific (California) 0 0 0 0 0 0 1977-2011 Louisiana & Alabama 530 525 610 270 186 81 1981-2011 Texas 203 132 293 19 140 13 1981-2011 Alaska 49 28 18 2 14 4 1977-2011 Lower 48 States 21,729 27,079 26,669 42,137 44,769 45,905 1977-2011 Alabama 146 123 59 20 28 3 1977-2011 Arkansas 491 1,148 1,754 4,627 3,082 2,093 1977-2011 California 176 16 101 450 12 73 1977-2011 Coastal Region Onshore 5 0 0 0 0 1 1977-2011 Los Angeles Basin Onshore 4 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 166 13 96 446 8 69 1977-2011 State Offshore 1 3 5 4 4 3 1977-2011 Colorado 1,980 2,812 2,294 3,346 2,838 2,015 1977-2011

139

Dry Natural Gas Reserves Extensions  

Gasoline and Diesel Fuel Update (EIA)

21,778 27,107 26,687 42,139 44,783 45,909 1977-2011 21,778 27,107 26,687 42,139 44,783 45,909 1977-2011 Federal Offshore U.S. 733 657 903 289 326 94 1990-2011 Pacific (California) 0 0 0 0 0 0 1977-2011 Louisiana & Alabama 530 525 610 270 186 81 1981-2011 Texas 203 132 293 19 140 13 1981-2011 Alaska 49 28 18 2 14 4 1977-2011 Lower 48 States 21,729 27,079 26,669 42,137 44,769 45,905 1977-2011 Alabama 146 123 59 20 28 3 1977-2011 Arkansas 491 1,148 1,754 4,627 3,082 2,093 1977-2011 California 176 16 101 450 12 73 1977-2011 Coastal Region Onshore 5 0 0 0 0 1 1977-2011 Los Angeles Basin Onshore 4 0 0 0 0 0 1977-2011 San Joaquin Basin Onshore 166 13 96 446 8 69 1977-2011 State Offshore 1 3 5 4 4 3 1977-2011 Colorado 1,980 2,812 2,294 3,346 2,838 2,015 1977-2011

140

Health effects models for nuclear power plant accident consequence analysis. Part 1, Introduction, integration, and summary: Revision 2  

SciTech Connect

This report is a revision of NUREG/CR-4214, Rev. 1, Part 1 (1990), Health Effects Models for Nuclear Power Plant Accident Consequence Analysis. This revision has been made to incorporate changes to the Health Effects Models recommended in two addenda to the NUREG/CR-4214, Rev. 1, Part 11, 1989 report. The first of these addenda provided recommended changes to the health effects models for low-LET radiations based on recent reports from UNSCEAR, ICRP and NAS/NRC (BEIR V). The second addendum presented changes needed to incorporate alpha-emitting radionuclides into the accident exposure source term. As in the earlier version of this report, models are provided for early and continuing effects, cancers and thyroid nodules, and genetic effects. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes are considered. Linear and linear-quadratic models are recommended for estimating the risks of seven types of cancer in adults - leukemia, bone, lung, breast, gastrointestinal, thyroid, and ``other``. For most cancers, both incidence and mortality are addressed. Five classes of genetic diseases -- dominant, x-linked, aneuploidy, unbalanced translocations, and multifactorial diseases are also considered. Data are provided that should enable analysts to consider the timing and severity of each type of health risk.

Evans, J.S. [Harvard School of Public Health, Boston, MA (United States); Abrahmson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Inhalation Toxicology Research Inst., Albuquerque, NM (United States); Gilbert, E.S. [Battelle Pacific Northwest Lab., Richland, WA (United States)

1993-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

DRAFT REVISION  

NLE Websites -- All DOE Office Websites (Extended Search)

-2 -2 Processing Inactive Records Revised Version Issued as P 200.2-2B LM Procedure 200.2-2A, Processing Internal Inactive Records for Storage of 7/18/07, has undergone revision. The revised procedure includes updated references, definitions, and formatting. Please replace LM Procedure 200.2-2A with LM Procedure 200.2-2B. The most recent and official controlled hard copy version of this document resides with LM's Directives Coordinator. An electronic version of the controlled document has been placed on the LM Intranet for employee use. Printed hard copies of this electronic version are considered uncontrolled documents. Procedure 200.2-2B INITIATED BY: Office of Business Operations NO. OF PAGES/ATTACHMENTS: 10 pages, 4 attachments U.S. Department of Energy

142

SCALE: A modular code system for performing Standardized Computer Analyses for Licensing Evaluation. Volume 1, Part 2: Control modules S1--H1; Revision 5  

SciTech Connect

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automated the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.3 of the system.

NONE

1997-03-01T23:59:59.000Z

143

April 27, 2010, Department letter transmitting revised Implementation Plan for Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities  

NLE Websites -- All DOE Office Websites (Extended Search)

April 27, 20 10 April 27, 20 10 The Honorable Peter S. Winokur Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, DC 20004-294 1 Dear Mr. Chairman: In a letter to the Defense Nuclear Facilities Safety Board dated February 1, 20 10, I reaffirmed our acceptance of Recommendation 2009- 1, Risk Assessment Methodologies at Defense Nuclear Facilities, and committed to several changes to the Department's Plan for implementing the recommendations therein. Enclosed please find the revised Implementation Plan for Defense Nuclear Facilities Safity Board Recommendation 2009-1 that incorporates those changes. I want to express my thanks for your staffs input on this revision and look forward to similar contributions as we revise the Department's Nuclear Safety Policy and implement

144

JM to Revise DOE O 100.1D, Secretarial Succession, Threat Level Notification, and Successor Tracking  

Directives, Delegations, and Requirements

The purpose of revising this directive is to update the established Secretarial Order of Succession in the Department of Energy (DOE).

2012-11-08T23:59:59.000Z

145

Assessment of plutonium in the Savannah River Site environment. Revision 1  

Science Conference Proceedings (OSTI)

Plutonium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fifth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. These are living documents, each to be revised and updated on a two-year schedule. This document describes the sources of plutonium in the environment, its release from SRS, environmental transport and ecological concentration of plutonium, and the radiological impact of SRS releases to the environment. Plutonium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite SNAP 9-A, plane crashes involving nuclear weapons, and small releases from reactors and reprocessing plants. Plutonium has been produced at SRS during the operation of five production reactors and released in small quantities during the processing of fuel and targets in chemical separations facilities. Approximately 0.6 Ci of plutonium was released into streams and about 12 Ci was released to seepage basins, where it was tightly bound by clay in the soil. A smaller quantity, about 3.8 Ci, was released to the atmosphere. Virtually all releases have occurred in F- and H-Area separation facilities. Plutonium concentration and transport mechanisms for the atmosphere, surface water, and ground water releases have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases to the offsite maximum individual can be characterized by a total dose of 15 mrem (atmospheric) and 0.18 mrem (liquid), compared with the dose of 12,960 mrem from non-SRS sources during the same period of time (1954--1989). Plutonium releases from SRS facilities have resulted in a negligible impact to the environment and the population it supports.

Carlton, W.H.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

1992-12-31T23:59:59.000Z

146

Dry Natural Gas Reserves Estimated Production  

Gasoline and Diesel Fuel Update (EIA)

8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 Federal Offshore U.S. 2,775 2,731 2,250 2,377 2,154 1,660 1990-2011 Pacific (California) 37 40 36 37 28 31 1977-2011 Louisiana & Alabama 1,973 2,066 1,752 1,886 1,717 1,311 1981-2011 Texas 765 625 462 454 409 318 1981-2011 Alaska 408 388 354 358 317 327 1977-2011 Lower 48 States 18,137 19,078 20,169 21,236 21,922 23,228 1977-2011 Alabama 287 274 257 254 223 218 1977-2011 Arkansas 188 269 456 698 951 1,079 1977-2011 California 255 253 237 239 243 311 1977-2011 Coastal Region Onshore 9 12 11 12 12 11 1977-2011 Los Angeles Basin Onshore 8 8 6 7 6 6 1977-2011 San Joaquin Basin Onshore 232 227 217 214 220 289 1977-2011 State Offshore 6 6 3 6 5 5 1977-2011

147

Dry Natural Gas Reserves Estimated Production  

U.S. Energy Information Administration (EIA) Indexed Site

8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 8,545 19,466 20,523 21,594 22,239 23,555 1977-2011 Federal Offshore U.S. 2,775 2,731 2,250 2,377 2,154 1,660 1990-2011 Pacific (California) 37 40 36 37 28 31 1977-2011 Louisiana & Alabama 1,973 2,066 1,752 1,886 1,717 1,311 1981-2011 Texas 765 625 462 454 409 318 1981-2011 Alaska 408 388 354 358 317 327 1977-2011 Lower 48 States 18,137 19,078 20,169 21,236 21,922 23,228 1977-2011 Alabama 287 274 257 254 223 218 1977-2011 Arkansas 188 269 456 698 951 1,079 1977-2011 California 255 253 237 239 243 311 1977-2011 Coastal Region Onshore 9 12 11 12 12 11 1977-2011 Los Angeles Basin Onshore 8 8 6 7 6 6 1977-2011 San Joaquin Basin Onshore 232 227 217 214 220 289 1977-2011 State Offshore 6 6 3 6 5 5 1977-2011

148

Microsoft Word - S03924_ITL STP Final RevisionA-3-1-10.doc  

Office of Legacy Management (LM)

Office of Environmental Management and Office of Environmental Management and Office of Legacy Management Site Transition Plan for the Inhalation Toxicology Laboratory March 2010 This page intentionally left blank U.S. Department of Energy Site Transition Plan for the Inhalation Toxicology Laboratory March 2010 Doc. No. S03924 Rev. 0 Page i Contents Abbreviations...................................................................................................................................v Executive Summary ...................................................................................................................... vii 1.0 Introduction......................................................................................................................1-1 1.1 Overview of the Site Transition Planning Process...............................................

149

New Mexico Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

6.88 8.40 4.17 5.32 1967-2010 6.88 8.40 4.17 5.32 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 6.45 7.05 4.07 4.84 4.52 3.70 1984-2012 Residential 11.99 12.23 9.53 9.63 9.14 8.69 1967-2012 Commercial 10.04 10.39 7.52 7.47 6.98 6.31 1967-2012 Industrial 8.54 10.27 5.41 6.17 6.22 4.87 1997-2012 Vehicle Fuel 5.77 -- 3.77 4.46 9.43 10.11 1994-2012 Electric Power W 8.18 W W W W 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 17,245 16,285 15,598 15,412 15,005 1977-2011 Adjustments 136 -6 525 -89 73 1977-2011 Revision Increases 2,534 2,735 1,396 2,211 2,114 1977-2011 Revision Decreases 2,431 2,657 1,708 1,833 2,229 1977-2011 Sales 570 402 287 145 1,016 2000-2011 Acquisitions

150

Alaska Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

5.63 7.39 2.93 3.17 1967-2010 5.63 7.39 2.93 3.17 1967-2010 Exports 6.21 7.69 8.59 12.19 12.88 15.71 1989-2012 Pipeline and Distribution Use 1970-2005 Citygate 6.75 6.74 8.22 6.67 6.53 6.14 1988-2012 Residential 8.68 8.72 10.23 8.89 8.77 8.47 1967-2012 Commercial 7.57 8.66 9.51 8.78 8.09 8.09 1967-2012 Industrial 4.67 5.49 4.02 4.23 3.84 5.11 1997-2012 Electric Power 3.58 W W W 5.04 4.32 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 11,917 7,699 9,101 8,838 9,424 1977-2011 Adjustments 1 -3 3 1 -1 1977-2011 Revision Increases 2,147 184 1,868 622 928 1977-2011 Revision Decreases 112 4,068 108 452 206 1977-2011 Sales 10 0 5 131 36 2000-2011 Acquisitions 6 0 0 0 221 2000-2011 Extensions

151

West Virginia Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

NA NA NA NA 1967-2010 NA NA NA NA 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.62 10.32 7.06 6.31 5.91 4.99 1984-2012 Residential 14.59 14.51 14.75 11.39 10.91 10.83 1967-2012 Commercial 13.37 13.54 14.24 10.27 9.65 9.39 1967-2012 Industrial 8.51 10.94 5.55 5.40 4.89 3.56 1997-2012 Vehicle Fuel -- -- -- -- -- -- 1992-2012 Electric Power W 10.08 4.78 5.14 W 3.33 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 4,729 5,136 5,946 7,000 10,345 1977-2011 Adjustments 14 315 258 -359 -1 1977-2011 Revision Increases 310 390 383 1,034 1,218 1977-2011 Revision Decreases 359 444 865 1,075 759 1977-2011 Sales 2 160 54 895 265 2000-2011 Acquisitions 25 118 2 984 590 2000-2011

152

ARPA TRP turboalternator development: Quarterly Report, July--September 1995. Revision 1  

DOE Green Energy (OSTI)

This report presents information on 4 major tasks: under-armor auxiliary power unit (UAAPU) demonstration on an M1A1 tank; low-cost turbogenerator design; negligible emission catalytic combustor development; and turbogenerator demonstration on an electric bus.

NONE

1995-10-01T23:59:59.000Z

153

Revised Prediction of Seasonal Atlantic Basin Tropical Cyclone Activity from 1 August  

Science Conference Proceedings (OSTI)

Predictions of the remainder of the seasons Atlantic basin tropical cyclone activity from 1 August have been issued by Gray and his colleagues at the Tropical Meteorology Project at Colorado State University since 1984. The original 1 August ...

Philip J. Klotzbach

2007-10-01T23:59:59.000Z

154

NIST SP 800-81 Revision 1, Secure Domain Name System ...  

Science Conference Proceedings (OSTI)

... guidelines for the cost-effective security ... Key Rollovers (Key Lifetimes)....11-1 ... as a standalone administrative entity ...

2012-02-21T23:59:59.000Z

155

Arkansas Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

6.61 8.72 3.43 3.84 1967-2010 6.61 8.72 3.43 3.84 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.55 8.88 7.86 6.76 6.27 5.36 1984-2012 Residential 13.08 14.09 13.39 11.53 11.46 11.82 1967-2012 Commercial 10.07 11.32 10.72 8.89 8.90 7.99 1967-2012 Industrial 9.51 10.56 8.44 7.28 7.44 6.38 1997-2012 Vehicle Fuel 8.39 -- -- -- -- 9.04 1994-2012 Electric Power 7.04 9.23 4.14 5.11 W 3.19 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 3,305 5,626 10,869 14,178 16,370 1977-2011 Adjustments -27 -64 5 -34 728 1977-2011 Revision Increases 321 1,249 1,912 1,072 631 1977-2011 Revision Decreases 146 189 621 301 324 1977-2011 Sales 298 19 54 393 6,760 2000-2011 Acquisitions 280 5 36 807 6,880 2000-2011

156

JM to Revise DOE O 328.1, Human Capital Accountability Program  

Directives, Delegations, and Requirements

The purpose of maintaining and updating this directive is to (1) Ensure compliance with applicable laws, regulations, and other directives. (2) Reduce the risk ...

2012-11-15T23:59:59.000Z

157

Title: Sampling Soil and Vegetation at Facility Sites No.: SOP-5139 Page 2 of 9 Revision: 1 Effective Date: June 24, 2011  

E-Print Network (OSTI)

#12;Title: Sampling Soil and Vegetation at Facility Sites No.: SOP-5139 Page 2 of 9 Revision: 1 for collecting soil, sediment, and vegetation samples at facilities such as the Material Disposal Area G (Area G the basic requirements for collecting soil, sediment and vegetation samples at certain facilities. Work

158

Corrective Action Investigation Plan: Roller Coaster Lagoons and North Disposal Trench, Tonopah Test Range, Revision 1  

SciTech Connect

1.1 Purpose The purpose of this investigation is to collect data to confirm the presence or absence of contamination, evaluate the potential for contaminant migration, and select appropriate closure methods for these sites. The potential closure methods for these sites involve either clean closure, closure in place, or no further action. 1.2 Scope The scope of this investigation includes collecting surface and subsurface soil samples at the Roller Coaster Lagoons; and collecting surface soil samples at the North Disposal Trench and the small spill area associated with the Voluntary Cotiective Action (VCA) that was conducted in 1995.

IT Corporation, Las Vegas, NV

1996-06-27T23:59:59.000Z

159

Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools, Revision 4  

Science Conference Proceedings (OSTI)

As part of the application process for license renewal, U.S. nuclear utilities must perform an evaluation to confirm that they have appropriately considered aging effects on plant components within the scope of the License Renewal Rule. An aging management plan must be developed for all Class 1 and non-Class 1 components subject to aging effects. This report presents a set of "mechanical tools" utilities can use to determine which aging effects are applicable to non-Class 1 mechanical components.

2006-01-23T23:59:59.000Z

160

Policy: Workplace Violence Page 1 of 4 Issued: October 10, 2007 Revised  

E-Print Network (OSTI)

or threats may include gestures or symbols. 3.2 Workplace or Premises ­ Includes all CSM property, facilities programs, or activities. 4.0 PROCEDURES 4.1 Reporting: Faculty and staff involvement is essential

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Test plan/procedure for the SPM-1 shipping container system. Revision 0  

SciTech Connect

The 49 CFR 173.465 Type A packaging tests will verify that SPM-1 will provide adequate protection and pass as a Type A package. Test will determine that the handle of the Pig will not penetrate through the plywood spacer and rupture the shipping container. Test plan/procedure provides planning, pre-test, setup, testing, and post-testing guidelines and procedures for conducting the {open_quotes}Free Drop Test{close_quotes} procedure for the SPM-1 package.

Flanagan, B.D.

1995-07-01T23:59:59.000Z

162

MA FI QPR Scoring Elements 4th Qtr FY 2009 Revision v1.xls  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reference Reference Due Date Element Measure Critical? Score > ≤ 8/15 8/15 8/22 8/22 95% 100% 80% 95% 0% 80% 2.0% 1.8% 2.0% 0.0% 1.8% 1.0% 0.5% 1.0% 0.0% 0.5% 8/30 8/30 99.9% 0.0% 99.9% 9/30 9/30 9/30 9/30 Program specific elements, negotiated with Programs: Program specific measures, negotiated with Programs: Overall Score: Green * All critical elements green, and * No more then one non-critical element yellow Yellow * Any critical element yellow, or * Any non-critical red, or * Two or more non-critical elements yellow Red * Any critical element red or * Two or more non-critical elements red TYRT September 30, 2009 Input submitted to update TYRT Submission timeliness 1 1 2 2 Enter Date or Percentage Proximity to spending target August 15, 2009 Overall Score: Yes MA F&I Quarterly Performance Report

163

Pennsylvania Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

NA NA NA NA 1967-2010 NA NA NA NA 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 9.35 10.39 7.81 7.04 6.28 5.52 1984-2012 Residential 14.66 16.22 14.74 12.90 12.46 11.99 1967-2012 Commercial 12.77 14.29 11.83 10.47 10.42 10.24 1967-2012 Industrial 10.64 12.09 9.19 8.23 9.86 9.58 1997-2012 Vehicle Fuel 10.83 8.30 5.15 3.76 3.40 7.96 1990-2012 Electric Power 8.01 10.46 4.60 5.27 4.85 3.15 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 3,361 3,577 6,985 13,960 26,529 1977-2011 Adjustments 181 -201 65 -373 -224 1977-2011 Revision Increases 326 655 668 2,892 7,077 1977-2011 Revision Decreases 418 502 502 1,938 4,872 1977-2011 Sales 4 275 52 678 799 2000-2011 Acquisitions

164

Kansas Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

69 6.85 3.16 4.23 1967-2010 69 6.85 3.16 4.23 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.27 8.85 6.12 6.08 5.53 4.74 1984-2012 Residential 12.97 13.00 11.10 10.61 9.93 10.13 1967-2012 Commercial 12.04 12.24 10.01 9.65 8.89 8.82 1967-2012 Industrial 7.17 9.42 4.59 5.49 5.28 3.95 1997-2012 Vehicle Fuel -- -- -- -- 9.87 9.00 1994-2012 Electric Power 6.31 8.11 4.13 5.05 4.79 3.28 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 3,982 3,557 3,279 3,673 3,486 1977-2011 Adjustments 79 -6 224 140 125 1977-2011 Revision Increases 407 334 212 687 152 1977-2011 Revision Decreases 221 498 403 166 240 1977-2011 Sales 65 17 2 17 124 2000-2011 Acquisitions 63 30 1 23 122 2000-2011

165

Ohio Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

7.59 7.88 4.36 4.63 1967-2010 7.59 7.88 4.36 4.63 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.64 10.41 6.60 6.87 5.51 4.47 1984-2012 Residential 13.47 14.53 12.68 11.13 10.78 9.91 1967-2012 Commercial 11.74 12.77 10.42 9.25 8.55 7.11 1967-2012 Industrial 10.63 12.71 8.71 7.40 6.77 5.48 1997-2012 Vehicle Fuel -- -- -- -- -- -- 1990-2012 Electric Power 7.88 10.79 4.40 5.01 W 3.05 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 1,027 985 896 832 758 1977-2011 Adjustments 138 210 70 127 -99 1977-2011 Revision Increases 144 135 70 68 17 1977-2011 Revision Decreases 198 333 43 59 38 1977-2011 Sales 0 31 196 374 0 2000-2011 Acquisitions 0 32 79 239 4 2000-2011 Extensions

166

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4  

SciTech Connect

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries.

Landers, N.F.; Petrie, L.M.; Knight, J.R. [Oak Ridge National Lab., TN (United States)] [and others

1995-04-01T23:59:59.000Z

167

Microsoft Word - Revised LM SMG Dec 2013 Update 15 FINAL 1-9-14.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Table of Contents Table of Contents 1.0 - Introduction ......................................................................................................... Page 3 2.0 - Purpose ................................................................................................................. Page 3 3.0 - Site Types ............................................................................................................. Page 4 4.0 - Site Counts ........................................................................................................... Page 4 5.0 - Site Nomenclature ............................................................................................... Page 5 6.0 - Site Transition Policy .......................................................................................... Page 6

168

Public Records Laws Connecticut General Statutes revised to January 1, 2008  

E-Print Network (OSTI)

are related to public records in Connecticut, state agencies, and the Office of the Public Records and conversion of written records by governmental agencies. TITLE 4, CHAPTER 38: ORGANIZATION OF STATE AGENCIES to serve purposes of originals. Sec.1-17a. Photographs and computerized images of individuals. State

Oliver, Douglas L.

169

Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1  

Science Conference Proceedings (OSTI)

Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ``Draft`` Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ``Draft`` MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million.

Cartmell, D.B.

1995-09-01T23:59:59.000Z

170

Savannah River Site Environmental Monitoring Plan. Volume 1, Section 1000 Addendum: Revision 3  

SciTech Connect

This document -- the Savannah River Site Environmental Monitoring Plan (SRS EM Plan) -- has been prepared according to guidance contained in the DOE 5400 Series orders, in 10 CFR 834, and in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and environmental Surveillance [DOE, 1991]. The SRS EM Plan`s purpose is to define the criteria, regulations, and guideline requirements with which SRS will comply. These criteria and requirements are applicable to environmental monitoring activities performed in support of the SRS Environmental Monitoring Program (SRS EM Program), WSRC-3Q1-2, Volume 1, Section 1100. They are not applicable to monitoring activities utilized exclusively for process monitoring/control. The environmental monitoring program requirements documented in the SRS EM Plan incorporate all applicable should requirements of DOE/EH-0173T and expand upon them to include nonradiological environmental monitoring program requirements.

Jannik, G.T.

1994-10-01T23:59:59.000Z

171

Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1  

Science Conference Proceedings (OSTI)

This reference manual compiles information on technology, requirements, and experience pertaining to the qualification of safety-related equipment for use in nuclear power plants under normal operating conditions and under adverse environments such as steam line breaks and earthquakes. The manual covers both environmental and seismic qualification of all safety-related electrical and mechanical equipment, but places emphasis on environmental qualification of Class 1E electrical equipment subject to harsh...

2010-09-16T23:59:59.000Z

172

Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1  

SciTech Connect

The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements.

Groth, B.D.

1995-01-11T23:59:59.000Z

173

Sampling and analysis plan for Mount Plant D & D soils packages, Revision 1  

SciTech Connect

There are currently 682 containers of soils in storage at Mound Plant, generated between April 1 and October 31, 1990 as a result of excavation of soils containing plutonium-238 at two ongoing Decontamination and Decommissioning (D&D) Program sites. These areas are known as Area 14, the waste transfer system (WTS) hillside, and Area 17, the Special Metallurgical (SM) Building area. The soils from these areas are part of Mound Plant waste stream number AMDM-000000010, Contaminated Soil, and are proposed for shipment to the Nevada Test Site (NTS) for disposal as low-level radioactive waste. The sealed waste packages, constructed of either wood or metal, are currently being stored in Building 31 and at other locations throughout the Mound facility. At a meeting in Las Vegas, Nevada on October, 26, 1990, DOE Nevada Operations Office (DOE-NV) and NTS representatives requested that the Mound Plant D&D soils proposed for shipment to NTS be sampled for Toxicity Characteristic Leaching Procedure (TCLP) constituents. On December 14, 1990, DOE-NV also requested that additional analyses be performed on the soils from one of the soils boxes for polychlorinated biphenyls (PCBs), particle size distribution, and free liquids. The purpose of this plan is to document the proposed sampling and analyses of the packages of D&D soils produced prior to October 31, 1990. In order to provide a thorough description of the soils excavated from the WTS and SM areas, sections 1.1 and 1.2 provide historical Information concerning the D&D soils, including waste stream evaluations and past sampling data.

NONE

1991-02-01T23:59:59.000Z

174

Technical assessment of workplace air sampling requirements at tank farm facilities. Revision 1  

Science Conference Proceedings (OSTI)

WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE N 5480.6 ``US Department of Energy Radiological Control Manual`` as it applies to programs at Hanford which are now overseen by WHC. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ``Hanford Site Radiological Control Manual`` and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of Tank Farms` workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance.

Olsen, P.A.

1994-09-21T23:59:59.000Z

175

Test plan, the Czechowice Oil Refinery bioremediation demonstration of a process waste lagoon. Revision 1  

SciTech Connect

The overall objective of the bioremediation project is to provide a cost effective bioremediation demonstration of petroleum contaminated soil at the Czechowice Oil Refinery. Additional objectives include training of personnel, and transfer of this technology by example to Poland, and the Risk Abatement Center for Central and Eastern Europe (RACE). The goal of the remediation is to reduce the risk of PAH compounds in soil and provide a green zone (grassy area) adjacent to the site boundary. Initial project discussions with the Czechowice Oil Refinery resulted in helping the refinery find an immediate cost effective solution for the dense organic sludge in the lagoons. They found that when mixed with other waste materials, the sludge could be sold as a fuel source to local cement kilns. Thus the waste was incinerated and provided a revenue stream for the refinery to cleanup the lagoon. This allowed the bioremediation project to focus on remediation of contaminated soil that unusable as fuel, less recalcitrant and easier to handle and remediate. The assessment identified 19 compounds at the refinery that represented significant risk and would require remediation. These compounds consisted of metals, PAH`s, and BTEX. The contaminated soil to be remediated in the bioremediation demonstration contains only PAH (BTEX and metals are not significantly above background concentrations). The final biopile design consists of (1) dewatering and clearing lagoon A to clean clay, (2) adding a 20 cm layer of dolomite with pipes for drainage, leachate collection, air injection, and pH adjustment, (3) adding a 1.1 m layer of contaminated soil mixed with wood chips to improve permeability, and (4) completing the surface with 20 cm of top soil planted with grass.

Altman, D.J.; Hazen, T.C.; Tien, A.J. [Westinghouse Savannah River Co., Aiken, SC (United States). Savannah River Technology Center; Worsztynowicz, A.; Ulfig, K. [Inst. for Ecology of Industrial Areas, Katowice (Poland)

1997-05-10T23:59:59.000Z

176

Microsoft PowerPoint - 15 Baker 2010 PM workshop draft 28 Feb1 (2) revised  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Title Title Project Management Career Presentation Title Project Management Career Development Program (PMCDP) Marylee H. Baker Lead Professional Career Development Analyst Lead Professional Career Development Analyst Project Management Career Development Program Department of Energy Office of Engineering & Construction Management 1 Office of Engineering & Construction Management 3/15/2010 Agenda * Program Objective * PMCDP in FY 2009 * FY 2009 Program Statistics * PMCDP in FY 2010 * Future Initiatives 2 3/15/2010 2 PMCDP Objective Ensure that we have well Ensure that we have well trained, qualified and experienced Federal Project Directors overseeing our Directors overseeing our projects 3 3/15/2010 3 PMCDP in FY 2009 PMCDP met all its 2009 goals

177

Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1  

SciTech Connect

The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies.

Dukelow, G.T.; Hanson, G.A. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States)

1995-05-01T23:59:59.000Z

178

Assessment of nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility. Revision 1  

SciTech Connect

The S-Area Defense Waste Processing Facility (DWPF) will initially process Batch 1 sludge in the sludge-only processing mode, with simulated non-radioactive Precipitate Hydrolysis, Aqueous (PHA) product, without the risk of nuclear criticality. The dilute concentration of fissile material in the sludge combined with excess of neutron absorbers during normal operations make criticality throughout the whole process incredible. Subsequent batches of the DWPF involving radioactive precipitate slurry and PHA will require additional analysis. Any abnormal or upset process operations, which are not considered in this report and could potentially separate fissile material, must be individually evaluated. Scheduled maintenance operation procedures are not considered to be abnormal.

Ha, B.C.

1993-07-20T23:59:59.000Z

179

Automated Estimating System (AES): Version 6.1: User`s manual. Revision 6  

SciTech Connect

This document describes Version 6.1 of the Automated Estimating System (AES), a personal computer-based software package. The AES is designed to aid in the creation, updating, and reporting of project cost estimates for the Estimating and Scheduling Engineering Department of Central Engineering Services of Lockheed Martin Energy Systems,Inc. AES provides formatted input screens to guide the user through the estimate creation/update process and provides several standardized reports that allow cost to be sorted and summarized in many different formats and at several levels of aggregation.

Schwarz, R.K. [ed.; Holder, D.A.

1996-03-01T23:59:59.000Z

180

State Environmental Policy Act (SEPA) Environmental Checklist Form 216-B-3 Expansion Ponds Closure Plan. Revision 1  

SciTech Connect

The 216-B-3 Expansion Ponds Closure Plan (Revision 1) consists of a Part A Dangerous Waste Permit Application and a Resource Conservation and Recovery Act Closure Plan. An explanation of the Part A submitted with this document is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. The 216-B-3 Pond System consists of a series of four earthen, unlined, interconnected ponds and the 216-B-3-3 Ditch that receive waste water from various 200 East Area operating facilities. These four ponds, collectively. Waste water (primarily cooling water, steam condensate, and sanitary water) from various 200 East Area facilities is discharged to the 216-B-3-3 Ditch. Water discharged to the 216-8-3-3 Ditch flows directly into the 216-B-3 Pond. In the past, waste water discharges to B Pond and the 216-B-3-3 Ditch contained mixed waste (radioactive waste and dangerous waste). The radioactive portion of mixed waste has been interpreted by the US Department of Energy (DOE) to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous portion of mixed waste is regulated under RCRA. Mixed waste also may be considered a hazardous substance under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) when considering remediation of waste sites.

1993-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1  

Science Conference Proceedings (OSTI)

The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required.

Conner, J.C.

1994-11-15T23:59:59.000Z

182

UMTRA Surface Project management action process document. Final report: Revision 1  

Science Conference Proceedings (OSTI)

A critical mission of the US Department of Energy (DOE) is the planning, implementation, and completion of environmental restoration (ER) programs at facilities that were operated by or in support of the former Atomic Energy Commission (AEC) from the late 1940s into the 1970s. Among these facilities are the 24 former uranium mill sites designed in the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (42 USC {section} 7901 et seq.) Title 1 of the UMTRCA authorized the DOE to undertake remedial actions at these designated sites and associated vicinity properties (VP), which contain uranium mill tailings and other residual radioactive materials (RRM) derived from the processing sites. Title 2 of the UMTRCA addresses uranium mill sites that were licensed at the time the UMTRCA was enacted. Cleanup of these Title 2 sites is the responsibility of the licensees. The cleanup of the Title 1 sites has been split into two separate projects: the Surface Project, which deals with the mill buildings, tailings, and contaminated soils at the sites and VPs; and the Ground Water Project, which is limited to the contaminated ground water at the sites. This management action process (MAP) document discusses the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project only; a separate MAP document has been prepared for the UMTRA Ground Water Project.

NONE

1996-04-01T23:59:59.000Z

183

Word Pro - Untitled1  

U.S. Energy Information Administration (EIA) Indexed Site

8 8 Crude Oil Domestic First Purchase Prices U.S. Average Prices, 1949-2011 Alaska North Slope, California, and Texas 1977-2011 160 U.S. Energy Information Administration / Annual Energy Review 2011 1 In chained (2005) dollars, calculated by using gross domestic product implicit price defla- tors in Table D1. See "Chained Dollars" in Glossary. 2 See "Nominal Dollars" in Glossary. 3 Alaska North Slope. Source: Table 5.18. Real¹ Nominal² 1950 1955 1960 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 0 20 40 60 80 100 120 Dollars per Barrel Texas Texas 1980 1985 1990 1995 2000 2005 2010 0 25 50 75 100 125 Nominal Dollars² per Barrel Nominal² Prices 1980 1985 1990 1995 2000 2005 2010 0 100 200 300 400 500 600 100 Index: 1977=100 Real¹ Prices, Indexed 1977=100 ANS³ California Texas 1980

184

Conversion and Blending Facility highly enriched uranium to low enriched uranium as oxide. Revision 1  

SciTech Connect

This Conversion and Blending Facility (CBF) will have two missions: (1) convert HEU materials into pure HEU oxide and (2) blend the pure HEU oxide with depleted and natural uranium oxide to produce an LWR grade LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. To the extent practical, the chemical and isotopic concentrations of blended LEU product will be held within the specifications required for LWR fuel. Such blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry. Otherwise, blended LEU will be produced as a waste suitable for storage or disposal.

1995-07-05T23:59:59.000Z

185

Conversion and Blending Facility Highly enriched uranium to low enriched uranium as uranium hexafluoride. Revision 1  

SciTech Connect

This report describes the Conversion and Blending Facility (CBF) which will have two missions: (1) convert surplus HEU materials to pure HEU UF{sub 6} and a (2) blend the pure HEU UF{sub 6} with diluent UF{sub 6} to produce LWR grade LEU-UF{sub 6}. The primary emphasis of this blending be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The chemical and isotopic concentrations of the blended LEU product will be held within the specifications required for LWR fuel. The blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry.

1995-07-05T23:59:59.000Z

186

Microsoft Word - Final_CRB_Panel_questions_Revisions_6_1_2011 (2)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

from the Certification Review Board Panel Discussion from the Certification Review Board Panel Discussion OECM Annual Project Management Workshop, March 16, 2011 1 Question: Does the Certification Review Board (CRB or the Board) consider past performance when determining whether to grant or deny Federal Project Director (FPD) certification? Answer: The Board does consider past performance. An FPD's performance on his/her projects is one indicator of his/her ability to successfully manage future projects, especially at Levels 3 and 4 which tend to be more complicated and have a higher level of risk. Question: If I take over a failing project, does that automatically mean that my performance will be judged as inadequate? Answer: The Board is interested in a candidate's performance to determine if he/she made a positive

187

Microsoft Word - Final_CRB_Panel_questions_Revisions_6_1_2011 (2)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

from the Certification Review Board Panel Discussion from the Certification Review Board Panel Discussion OECM Annual Project Management Workshop, March 16, 2011 1 Question: Does the Certification Review Board (CRB or the Board) consider past performance when determining whether to grant or deny Federal Project Director (FPD) certification? Answer: The Board does consider past performance. An FPD's performance on his/her projects is one indicator of his/her ability to successfully manage future projects, especially at Levels 3 and 4 which tend to be more complicated and have a higher level of risk. Question: If I take over a failing project, does that automatically mean that my performance will be judged as inadequate? Answer: The Board is interested in a candidate's performance to determine if he/she made a positive

188

RECON: a computer program for analyzing repository economics. Documentation and user's manual. Revision 1  

SciTech Connect

From 1981 through 1984 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evaluate the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through September of 1984. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input using either card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained. 2 refs.

Clark, L.L.; Schutz, M.E.; Luksic, A.T.

1985-07-01T23:59:59.000Z

189

Uranium hexafluoride packaging tiedown systems overview at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio. Revision 1  

SciTech Connect

The Portsmouth Gaseous Diffusion Plant (PORTS) in Piketon, Ohio, is operated by Martin Marietta Energy Systems, Inc., through the US Department of Energy-Oak Ridge Operations Office (DOE-ORO) for the US Department of Energy-Headquarters, Office of Nuclear Energy. The PORTS conducts those operations that are necessary for the production, packaging, and shipment of uranium hexafluoride (UF{sub 6}). Uranium hexafluoride enriched uranium than 1.0 wt percent {sup 235}U shall be packaged in accordance with the US Department of Transportation (DOT) regulations of Title 49 CFR Parts 173 (Reference 1) and 178 (Reference 2), or in US Nuclear Regulatory Commission (NRC) or US Department of Energy (DOE) certified package designs. Concerns have been expressed regarding the various tiedown methods and condition of the trailers being used by some shippers/carriers for international transport of the UF{sub 6} cylinders/overpacks. Because of the concerns about international shipments, the US Department of Energy-Headquarters (DOE-HQ) Office of Nuclear Energy, through DOE-HQ Transportation Management Division, requested Westinghouse Hanford Company (Westinghouse Hanford) to review UF{sub 6} packaging tiedown and shipping practices used by PORTS, and where possible and appropriate, provide recommendations for enhancing these practices. Consequently, a team of two individuals from Westinghouse Hanford visited PORTS on March 5 and 6, 1990, for the purpose of conducting this review. The paper provides a brief discussion of the review activities and a summary of the resulting findings and recommendations. A detailed reporting of the is documented in Reference 4.

Becker, D.L.; Green, D.J.; Lindquist, M.R.

1993-07-01T23:59:59.000Z

190

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado. Revision 1  

SciTech Connect

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [ 1 0 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial action would result in the loss of approximately 164 ac (66 ha) of soils, but 132 ac (53 ha) of these soils are contaminated and cannot be used for other purposes. Another 154 ac (62 ha) of soils would be temporarily disturbed. Approximately 57 ac (23 ha) of open range land would be permanently removed from livestock grazing and wildlife use. The removal of the contaminated materials would affect the 1 00-year floodplain of the San Miguel River and would result in the loss of riparian habitat along the river. The southwestern willow flycatcher, a Federal candidate species, may be affected by the remedial action, and the use of water from the San Miguel River ``may affect`` the Colorado squawfish, humpback chub, bonytail chub, and razorback sucker. Traffic levels on State Highways 90 and 141 would be increased during the remedial action, as would the noise levels along these transportation routes. Measures for mitigating the adverse environmental impacts of the proposed remedial action are discussed in Section 6.0 of this environmental assessment (EA).

Not Available

1993-08-01T23:59:59.000Z

191

FY 93 thermal loading systems study final report: Volume 2. Revision 1  

Science Conference Proceedings (OSTI)

The ability to meet the overall performance requirements for the proposed Mined Geology Disposal System at Yucca Mountain, Nevada requires the two major subsystem (natural barriers and engineered barriers) to positively contribute to containment and radionuclide isolation. In addition to the postclosure performance the proposed repository must meet preclosure requirements of safety, retrievability, and operability. Cost and schedule were also considered. The thermal loading strategy chosen may significantly affect both the postclosure and preclosure performance of the proposed repository. Although the current Site Characterization Plan reference case is 57 kilowatts (kW)/acre, other thermal loading strategies (different areal mass loadings) have been proposed which possess both advantages and disadvantages. The objectives of the FY 1993 Thermal Loading Study were to (1) place bounds on the thermal loading which would establish the loading regime that is ``too hot`` and the loading regime that is ``too cold``, to (2) ``grade`` or evaluate the performance, as a function of thermal loading, of the repository to contain high level wastes against performance criteria and to (3) evaluate the performance of the various options with respect to cost, safety, and operability. Additionally, the effort was to (4) identify important uncertainties that need to be resolved by tests and/or analyses in order to complete a performance assessment on the effects of thermal loading. The FY 1993 Thermal Loading Study was conducted from December 1, 1992 to December 30, 1993 and this final report provides the findings of the study. Volume 2 consists of 10 appendices which contain the following: Waste Stream Analysis; Waste Package Design Inputs; Subsurface Design Inputs; Thermal-Hydrologic Model Inputs; Near-Field Calculations; Far-Field; Reliability of Electronics as a Function of Temperature; Cost Analysis Details; Geochemistry; and Areas of Uncertainty in Thermal Loading.

NONE

1994-08-29T23:59:59.000Z

192

SRS ES&H standards compliance program management plan. Revision 1  

SciTech Connect

On March 8, 1990, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 90-2 to the Secretary of Energy. This recommendation, based upon the DNFSB`s initial review and evaluation of the content and implementation of standards relating to the design, construction, operations, and decommissioning of defense nuclear facilities of the Department of Energy (DOE), called for three actions: (1) identification of specific standards that apply to design, construction, operation and decommissioning of DOE facilities; (2) assessment of the adequacy of those standards for protecting public health and safety; and (3) determination of the extent to which they have and are being implemented. This document defines the elements of the SRS program required to support the HQ program in response to DNFSB Recommendation 90-2. The objective is to ensure a consistent approach for all sitewide ES and H Standards Compliance Program efforts that satisfied the intent of Recommendation 90-2 and the HQ 90-2 Implementation Plan in a cost-effective manner. The methodology and instructions for implementation of the SRS program are contained in the Standards Compliance Program Implementation Plan. The Management Plan shall be used in conjunction with the Implementation Plan.

Hearn, W.H.

1993-09-08T23:59:59.000Z

193

The optical constants and spectral specular reflectivity of highly oriented pyrolytic graphite (HOPG). Revision 1  

Science Conference Proceedings (OSTI)

Measurements of the specular reflectivity and the optical constants of highly ordered pyrolytic graphite (HOPG) have been made using two independent optical systems. The first measures reflectance (at 1.06 {mu}m and 293 K) by comparing the intensity of a laser beam before and after reflecting off the sample. The second determines the complex index of raft-action (from 0.55 to 8.45 {mu}m, with sample temperatures of 293, 480, 900 and 1300 K) by ellipsometry. Agreement between the two methods is good. Moderate reflectivities are observed over the full spectral range of measurement: the spectral directional-hemispherical reflectivity at normal incidence varies from 0.41 at 0.55 {mu}m to 0.74 at 8.45 {mu}m. The components of the complex index of refraction increase smoothly with wavelength. The index of refraction increases from 3.10 at 0.55 {mu}m to 7.84 at 8.45 {mu}m. The extinction coefficient varies from 2.01 to 6.66 over the same range.

Havstad, M.A.; Schildbach, M.A.; McLean, W. II

1993-08-01T23:59:59.000Z

194

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

195

External Peer Review Team Report Underground Testing Area Subproject for Frenchman Flat, Revision 1  

Science Conference Proceedings (OSTI)

An external peer review was conducted to review the groundwater models used in the corrective action investigation stage of the Underground Test Area (UGTA) subproject to forecast zones of potential contamination in 1,000 years for the Frenchman Flat area. The goal of the external peer review was to provide technical evaluation of the studies and to assist in assessing the readiness of the UGTA subproject to progress to monitoring activities for further model evaluation. The external peer review team consisted of six independent technical experts with expertise in geology, hydrogeology,'''groundwater modeling, and radiochemistry. The peer review team was tasked with addressing the following questions: 1. Are the modeling approaches, assumptions, and model results for Frenchman Flat consistent with the use of modeling studies as a decision tool for resolution of environmental and regulatory requirements? 2. Do the modeling results adequately account for uncertainty in models of flow and transport in the Frenchman Flat hydrological setting? a. Are the models of sufficient scale/resolution to adequately predict contaminant transport in the Frenchman Flat setting? b. Have all key processes been included in the model? c. Are the methods used to forecast contaminant boundaries from the transport modeling studies reasonable and appropriate? d. Are the assessments of uncertainty technically sound and consistent with state-of-the-art approaches currently used in the hydrological sciences? 3. Are the datasets and modeling results adequate for a transition to Corrective Action Unit monitoring studiesthe next stage in the UGTA strategy for Frenchman Flat? The peer review team is of the opinion that, with some limitations, the modeling approaches, assumptions, and model results are consistent with the use of modeling studies for resolution of environmental and regulatory requirements. The peer review team further finds that the modeling studies have accounted for uncertainty in models of flow and transport in the Frenchman Flat except for a few deficiencies described in the report. Finally, the peer review team concludes that the UGTA subproject has explored a wide range of variations in assumptions, methods, and data, and should proceed to the next stage with an emphasis on monitoring studies. The corrective action strategy, as described in the Federal Facility Agreement and Consent Order, states that the groundwater flow and transport models for each corrective action unit will consider, at a minimum, the following: Alternative hydrostratigraphic framework models of the modeling domain. Uncertainty in the radiological and hydrological source terms. Alternative models of recharge. Alternative boundary conditions and groundwater flows. Multiple permissive sets of calibrated flow models. Probabilistic simulations of transport using plausible sets of alternative framework and recharge models, and boundary and groundwater flows from calibrated flow models. Ensembles of forecasts of contaminant boundaries. Sensitivity and uncertainty analyses of model outputs. The peer review team finds that these minimum requirements have been met. While the groundwater modeling and uncertainty analyses have been quite detailed, the peer review team has identified several modeling-related issues that should be addressed in the next phase of the corrective action activities: Evaluating and using water-level gradients from the pilot wells at the Area 5 Radioactive Waste Management Site in model calibration. Re-evaluating the use of geochemical age-dating data to constrain model calibrations. Developing water budgets for the alluvial and upper volcanic aquifer systems in Frenchman Flat. Considering modeling approaches in which calculated groundwater flow directions near the water table are not predetermined by model boundary conditions and areas of recharge, all of which are very uncertain. Evaluating local-scale variations in hydraulic conductivity on the calculated contaminant boundaries. Evaluat

Sam Marutzky

2010-09-01T23:59:59.000Z

196

"INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE FORD NUCLEAR REACTOR, REVISION 1, ANN ARBOR, MICHIGAN  

SciTech Connect

At the NRC?s request, ORAU conducted confirmatory surveys of the FNR during the period of December 4 through 6, 2012. The survey activities included visual inspections and measurement and sampling activities. Confirmatory activities also included the review and assessment of UM?s project documentation and methodologies. Surface scans identified elevated activity in two areas. The first area was on a wall outside of Room 3103 and the second area was in the southwest section on the first floor. The first area was remediated to background levels. However, the second area was due to gamma shine from a neighboring source storage area. A retrospective analysis of UM?s FSS data shows that for the SUs investigated by the ORAU survey team, UM met the survey requirements set forth in the FSSP. The total mean surface activity values were directly compared with the mean total surface activity reported by UM. Mean surface activity values determined by UM were within two standard deviations of the mean determined by ORAU. Additionally, all surface activity values were less than the corresponding gross beta DCGL{sub W}. Laboratory analysis of the soil showed that COC concentrations were less than the respective DCGL{sub W} values. For the inter-lab comparison, the DER was above 3 for only one sample. However, since the sum of fractions for each of the soil samples was below 1, thus none of the samples would fail to meet release guidelines. Based on the findings of the side-by-side direct measurements, and after discussion with the NRC and ORAU, UM decided to use a more appropriate source efficiency in their direct measurement calculations and changed their source efficiency from 0.37 to 0.25.

ALTIC, NICK A

2013-08-01T23:59:59.000Z

197

Core science and technology development plan for indirect-drive ICF ignition. Revision 1  

SciTech Connect

To define the development work needed to support inertial confinement fusion (ICF) program goals, the authors have assembled this Core Science and Technology (CS and T) Plan that encompasses nearly all science research and technology development in the ICF program. The objective of the CS and T Plan described here is to identify the development work needed to ensure the success of advanced ICF facilities, in particular the National Ignition Facility (NIF). This plan is intended as a framework to facilitate planning and coordination of future ICF programmatic activities. The CS and T Plan covers all elements of the ICF program including laser technology, optic manufacturing, target chamber, target diagnostics, target design and theory, target components and fabrication, and target physics experiments. The CS and T Plan has been divided into these seven different technology development areas, and they are used as level-1 categories in a work breakdown structure (WBS) to facilitate the organization of all activities in this plan. The scope of the CS and T Plan includes all research and development required to support the NIF leading up to the activation and initial operation as an indirect-drive facility. In each of the CS and T main development areas, the authors describe the technology and issues that need to be addressed to achieve NIF performance goals. To resolve all issues and achieve objectives, an extensive assortment of tasks must be performed in a coordinated and timely manner. The authors describe these activities and present planning schedules that detail the flow of work to be performed over a 10-year period corresponding to estimated time needed to demonstrate fusion ignition with the NIF. Besides the benefits to the ICF program, the authors also discuss how the commercial sector and the nuclear weapons science may profit from the proposed research and development program.

Powell, H.T.; Kilkenny, J.D. [eds.

1995-12-01T23:59:59.000Z

198

CRADA Order Revision  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRADA Order Revision CRADA Order Revision Linda Field Patent Counsel Department of Energy Goal CRADA Order DOE O 483.1 CRADA Manual DOE M 483.1-1 CRADA Order DOE O XXXX.X Departmental Directive Program Types of Directives Policies Regulations Orders Notices Manuals Guides Technical Standards Departmental Directive Program Directives Life Cycle Development Coordination Implementation Review (Certification) Development Phase *Orders are uploaded to RevCom for review and comment by all affected parties *60 days to develop draft & submit to MA-90 *Solicits input from stakeholders ( incl. field, contractors, and/or program counsel) Coordination Phase *MA-90 parses directive & sets due dates for review & comment *HQ Directives Points of Contact (DPCs) *Have 45 days to submit official comments on behalf of their

199

OMB Circular A-76 (Revised)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EXECUTIVE OFFICE OF THE PRESIDENT EXECUTIVE OFFICE OF THE PRESIDENT OFFICE OF MANAGEMENT AND BUDGET WASHINGTON, DC 20503 May 29, 2003 CIRCULAR NO. A-76 (REVISED) TO THE HEADS OF EXECUTIVE DEPARTMENTS AND ESTABLISHMENTS SUBJECT: Performance of Commercial Activities 1. Purpose. This circular establishes federal policy for the competition of commercial activities. 2. Supersession. This circular supersedes Office of Management and Budget (OMB) Circular No. A-76 (Revised 1999), August 4, 1983; Circular No. A-76 Revised Supplemental Handbook (Revised 2000), March 1996; Office of Federal Procurement Policy Letter 92-1, "Inherently Governmental Functions," September 23, 1992; and OMB Transmittal Memoranda 1 through 25, Performance of Commercial Activities. 3. Authority. Reorganization Plan No. 2 of 1970 (31 U.S.C. § 1111); Executive Order 11541; the Office

200

Guidelines for PWR Steam Generator Tubing Specifications and Repair: Volume 2, Revision 1: Guidelines for Procurement of Alloy 690 S team Generator Tubing  

Science Conference Proceedings (OSTI)

This revised document provides guidelines for procuring Alloy 690 steam generator tubing and sleeve material.

1999-04-14T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

JM to Revise DOE G 423.1-1A, Implementation Guide for Use in Developing Technical Safety Requirements  

Directives, Delegations, and Requirements

As part of the one-year accuracy review of the November 2010 change to the Guide, as required by DOE O 251.1C, Departmental Directives Progrom, Section 7, ...

2013-06-21T23:59:59.000Z

202

,"Shale Natural Gas Reserves Revision Decreases "  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Shale Natural Gas Reserves Revision Decreases ",36,"Annual",2011,"6302009" ,"Release...

203

,"Shale Natural Gas Reserves Revision Increases "  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Shale Natural Gas Reserves Revision Increases ",36,"Annual",2011,"6302009" ,"Release...

204

Evaluation of severe accident risks: Methodology for the containment, source term, consequence, and risk integration analyses; Volume 1, Revision 1  

SciTech Connect

NUREG-1150 examines the risk to the public from five nuclear power plants. The NUREG-1150 plant studies are Level III probabilistic risk assessments (PRAs) and, as such, they consist of four analysis components: accident frequency analysis, accident progression analysis, source term analysis, and consequence analysis. This volume summarizes the methods utilized in performing the last three components and the assembly of these analyses into an overall risk assessment. The NUREG-1150 analysis approach is based on the following ideas: (1) general and relatively fast-running models for the individual analysis components, (2) well-defined interfaces between the individual analysis components, (3) use of Monte Carlo techniques together with an efficient sampling procedure to propagate uncertainties, (4) use of expert panels to develop distributions for important phenomenological issues, and (5) automation of the overall analysis. Many features of the new analysis procedures were adopted to facilitate a comprehensive treatment of uncertainty in the complete risk analysis. Uncertainties in the accident frequency, accident progression and source term analyses were included in the overall uncertainty assessment. The uncertainties in the consequence analysis were not included in this assessment. A large effort was devoted to the development of procedures for obtaining expert opinion and the execution of these procedures to quantify parameters and phenomena for which there is large uncertainty and divergent opinions in the reactor safety community.

Gorham, E.D.; Breeding, R.J.; Brown, T.D.; Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Murfin, W.B. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States); Hora, S.C. [Hawaii Univ., Hilo, HI (United States)

1993-12-01T23:59:59.000Z

205

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4  

SciTech Connect

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries.

Greene, N.M.; Petrie, L.M.; Westfall, R.M.; Bucholz, J.A.; Hermann, O.W.; Fraley, S.K. [Oak Ridge National Lab., TN (United States)

1995-04-01T23:59:59.000Z

206

DRAFT REVISION  

Office of Legacy Management (LM)

f. The System Owner is responsible for generating an Electronic System RegistrationInventory form (LM Form 200.1-5) for each system and working with the RLO and EMR to clarify...

207

DRAFT REVISION  

Office of Legacy Management (LM)

Handling h. U.S. Environmental Protection Agency (EPA), Office of Solid Waste and Emergency Response (OSWER) Directive No. 9833.3A-1, December 1990, Final Guidance on...

208

RELAP5/MOD3 code manual: Summaries and reviews of independent code assessment reports. Volume 7, Revision 1  

Science Conference Proceedings (OSTI)

Summaries of RELAP5/MOD3 code assessments, a listing of the assessment matrix, and a chronology of the various versions of the code are given. Results from these code assessments have been used to formulate a compilation of some of the strengths and weaknesses of the code. These results are documented in the report. Volume 7 was designed to be updated periodically and to include the results of the latest code assessments as they become available. Consequently, users of Volume 7 should ensure that they have the latest revision available.

Moore, R.L.; Sloan, S.M.; Schultz, R.R.; Wilson, G.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1996-10-01T23:59:59.000Z

209

Selection of a computer code for Hanford low-level waste engineered-system performance assessment. Revision 1  

Science Conference Proceedings (OSTI)

Planned performance assessments for the proposed disposal of low-activity waste (LAW) glass produced from remediation of wastes stored in underground tanks at Hanford, Washington will require calculations of radionuclide release rates from the subsurface disposal facility. These calculations will be done with the aid of computer codes. The available computer codes with suitable capabilities at the time Revision 0 of this document was prepared were ranked in terms of the feature sets implemented in the code that match a set of physical, chemical, numerical, and functional capabilities needed to assess release rates from the engineered system. The needed capabilities were identified from an analysis of the important physical and chemical processes expected to affect LAW glass corrosion and the mobility of radionuclides. This analysis was repeated in this report but updated to include additional processes that have been found to be important since Revision 0 was issued and to include additional codes that have been released. The highest ranked computer code was found to be the STORM code developed at PNNL for the US Department of Energy for evaluation of arid land disposal sites.

McGrail, B.P.; Bacon, D.H.

1998-02-01T23:59:59.000Z

210

JM to Revise DOE G 420.2-1, Accelerator Facility Safety Implementation Guide for DOE Order (0) 420.2C, Safety of Accelerator Facilities  

Directives, Delegations, and Requirements

The revision will address implementation of roles and responsibilities, improve operational efficiency using operating experience, and clarify the use of ...

2013-07-17T23:59:59.000Z

211

NIST SP 800-53 Revision 3, Recommended Security Controls ...  

Science Conference Proceedings (OSTI)

Page 1. NIST Special Publication 800-53 Revision 3 Recommended Security Controls for Federal Information Systems and Organizations ...

2012-02-06T23:59:59.000Z

212

Revised (05/06)  

U.S. Energy Information Administration (EIA) Indexed Site

U.S. DEPARTMENT OF ENERGY OMB No. 1901-0260 U.S. DEPARTMENT OF ENERGY OMB No. 1901-0260 (Revised 03/12) Germantown, MD 20874-1290 Expires: General Information 1. Purpose Standard Remittance Advice (RA) form is a mandatory form designed to serve as the source document for entries into the Department's accounting records under Public Law 97-425 data from Purchasers concerning payment of their contribution to the Nuclear Waste Fund. 2. Who Shall Submit The RA must be submitted by Purchasers who signed the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste. Submit Copy 1, 2, and 3 to DOE, Energy Finance and Accounting Service Center and retain Copy 4.

213

Phase II Transport Model of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

This document, the Phase II Frenchman Flat transport report, presents the results of radionuclide transport simulations that incorporate groundwater radionuclide transport model statistical and structural uncertainty, and lead to forecasts of the contaminant boundary (CB) for a set of representative models from an ensemble of possible models. This work, as described in the Federal Facility Agreement and Consent Order (FFACO) Underground Test Area (UGTA) strategy (FFACO, 1996; amended 2010), forms an essential part of the technical basis for subsequent negotiation of the compliance boundary of the Frenchman Flat corrective action unit (CAU) by Nevada Division of Environmental Protection (NDEP) and National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Underground nuclear testing via deep vertical shafts was conducted at the Nevada Test Site (NTS) from 1951 until 1992. The Frenchman Flat area, the subject of this report, was used for seven years, with 10 underground nuclear tests being conducted. The U.S. Department of Energy (DOE), NNSA/NSO initiated the UGTA Project to assess and evaluate the effects of underground nuclear tests on groundwater at the NTS and vicinity through the FFACO (1996, amended 2010). The processes that will be used to complete UGTA corrective actions are described in the Corrective Action Strategy in the FFACO Appendix VI, Revision No. 2 (February 20, 2008).

Gregg Ruskuaff

2010-01-01T23:59:59.000Z

214

Table 5.17 Strategic Petroleum Reserve, 1977-2011 (Thousand ...  

U.S. Energy Information Administration (EIA)

... as well as additional barrels to create a Northeast ... 5 The quantity of domestic fuel oil which was in storage prior to injection of foreign crude oil.

215

Table 5.17 Strategic Petroleum Reserve, 1977-2011 (Million Barrels ...  

U.S. Energy Information Administration (EIA)

Short-Term Energy Outlook Annual Energy Outlook ... 1984: 72.04.00.05.00.00.00: 450.51: 56.6: 28.9: 96: 1985: 43.12.00.17.00.00.00: 493.32: 60.6: 32.5: 115: 1986:

216

Federal Offshore California Natural Gas Gross Withdrawals and...  

Annual Energy Outlook 2012 (EIA)

40,407 45,516 44,902 41,229 41,200 36,579 1977-2011 From Gas Wells 2,094 2,137 1,601 1,206 1,757 1,560 1977-2011 From Oil Wells 38,313 43,379 43,300 40,023 39,444 35,020 1977-2011...

217

,"U.S. Shale Proved Reserves Revision Decreases (Billion Cubic...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Shale Proved Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

218

,"U.S. Shale Proved Reserves Revision Increases (Billion Cubic...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Shale Proved Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

219

,"U.S. Coalbed Methane Proved Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

ame","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

220

,"U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

ame","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

,"California Dry Natural Gas Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","California Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2011...

222

,"California Dry Natural Gas Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","California Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2011...

223

,"Texas Dry Natural Gas Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Texas Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2011...

224

,"Texas Dry Natural Gas Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Texas Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2011...

225

,"U.S. Crude Oil + Lease Condensate Reserves Revision Increases...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Crude Oil + Lease Condensate Reserves Revision Increases (Million Barrels)",1,"Annual",2011...

226

,"U.S. Crude Oil + Lease Condensate Reserves Revision Decreases...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Crude Oil + Lease Condensate Reserves Revision Decreases (Million Barrels)",1,"Annual",2011...

227

,"New Mexico Dry Natural Gas Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New Mexico Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)",1,"Annual",2011...

228

,"New Mexico Dry Natural Gas Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New Mexico Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet)",1,"Annual",2011...

229

Technical Review Report for the Model 9978-96 Package Safety Analysis Report for Packaging (S-SARP-G-00002, Revision 1, March 2009)  

Science Conference Proceedings (OSTI)

This Technical Review Report (TRR) documents the review, performed by Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the Department of Energy (DOE), on the 'Safety Analysis Report for Packaging (SARP), Model 9978 B(M)F-96', Revision 1, March 2009 (S-SARP-G-00002). The Model 9978 Package complies with 10 CFR 71, and with 'Regulations for the Safe Transport of Radioactive Material-1996 Edition (As Amended, 2000)-Safety Requirements', International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9978 Packaging is designed, analyzed, fabricated, and tested in accordance with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PVC). The review presented in this TRR was performed using the methods outlined in Revision 3 of the DOE's 'Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages'. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's Regulatory Guide 7.9, i.e., 'Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material'. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9978 Packaging is a single containment package, using a 5-inch containment vessel (5CV). It uses a nominal 35-gallon drum package design. In comparison, the Model 9977 Packaging uses a 6-inch containment vessel (6CV). The Model 9977 and Model 9978 Packagings were developed concurrently, and they were referred to as the General Purpose Fissile Material Package, Version 1 (GPFP). Both packagings use General Plastics FR-3716 polyurethane foam as insulation and as impact limiters. The 5CV is used as the Primary Containment Vessel (PCV) in the Model 9975-96 Packaging. The Model 9975-96 Packaging also has the 6CV as its Secondary Containment Vessel (SCV). In comparison, the Model 9975 Packagings use Celotex{trademark} for insulation and as impact limiters. To provide a historical perspective, it is noted that the Model 9975-96 Packaging is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then-newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The Model 9978 Package has six Content Envelopes: C.1 ({sup 238}Pu Heat Sources), C.2 ( Pu/U Metals), C.3 (Pu/U Oxides, Reserved), C.4 (U Metal or Alloy), C.5 (U Compounds), and C.6 (Samples and Sources). Per 10 CFR 71.59 (Code of Federal Regulations), the value of N is 50 for the Model 9978 Package leading to a Criticality Safety Index (CSI) of 1.0. The Transport Index (TI), based on dose rate, is calculated to be a maximum of 4.1.

West, M

2009-03-06T23:59:59.000Z

230

Reference: Revised Tariff Sheet  

E-Print Network (OSTI)

Company (TrAILCo), a revised tariff sheet to correct the FERC Form No. 1 line reference in TrAILCos formula rate. Pursuant to the authority delegated to the Director, Division of Electric Power Regulation- East, under 18 C.F.R. 375.307, your submittal filed in the above referenced docket is accepted for filing, effective May 17, 2010, as requested. 1 Notice of the filing was published in the Federal Register, with comments, protests, or interventions due on or before June 3, 2010. No protests or adverse comments were filed. American Municipal Power, Inc. and PJM Interconnection, LLC filed timely motions to intervene. Notices of intervention and unopposed timely filed motions to intervene are granted pursuant to Rule 214 of the Commissions Rules of Practice and Procedure (18 C.F.R. 385.214). Any opposed or untimely filed motion to intervene is governed by the provisions of Rule 214. This acceptance for filing shall not be construed as constituting approval of any rate, charge, classification or any rule, regulation, or practice affecting such rate or 1

Stephen Angle Esq; Dear Mr. Angle; Jignasa P. Gadani

2010-01-01T23:59:59.000Z

231

Integrated test vehicle program plan: revision C  

DOE Green Energy (OSTI)

This edition dated August 26, 1977, is Revision C of the Integrated Test Vehicle, Program Plan, Phase II - Deliverable Item 2-7-1. The original edition was issued on May 27, 1977. Corrections were made and issued as Proposed Modifications for Integrated Test Vehicle, Program Plan, dated July 8, 1977. For the purpose of documenting changes, the July 8, 1977, version is caled Revision A. The edition dated August 5, 1977, is called Revision B. Each paragraph in this edition is marked to indicate technical changes from previous editions.

Not Available

1977-08-26T23:59:59.000Z

232

2009 Revisions EIA-914  

Annual Energy Outlook 2012 (EIA)

for Texas, which was partially the cause for the review of the EIA-914, which, in turn, led to the development and implementation of this new methodology. Downward revisions in...

233

Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site  

SciTech Connect

This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7).

Bohrman, D.E.; Ingram, E.M. [Oak Ridge Y-12 Plant, TN (United States)

1993-09-01T23:59:59.000Z

234

Colorado Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

4.57 6.94 3.21 3.96 1967-2010 4.57 6.94 3.21 3.96 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 6.23 6.98 5.09 5.26 4.94 4.26 1984-2012 Residential 8.84 9.77 8.80 8.13 8.25 8.31 1967-2012 Commercial 8.10 9.01 7.56 7.58 7.84 7.58 1967-2012 Industrial 7.21 8.76 6.57 5.84 6.42 5.79 1997-2012 Vehicle Fuel 8.72 13.57 9.12 10.79 9.56 11.65 1990-2012 Electric Power 4.35 7.02 4.27 5.16 4.98 W 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 21,851 23,302 23,058 24,119 24,821 1977-2011 Adjustments 136 -250 306 449 801 1977-2011 Revision Increases 3,924 3,244 1,601 2,973 2,509 1977-2011 Revision Decreases 582 3,029 4,044 3,645 2,921 1977-2011 Sales 750 747 374 242 1,244 2000-2011

235

California Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

6.62 8.38 3.96 4.87 1967-2010 6.62 8.38 3.96 4.87 1967-2010 Imports -- 9.15 2.83 4.76 3.57 -- 2007-2012 Exports 6.53 8.06 3.76 4.51 4.18 2.90 1997-2012 Pipeline and Distribution Use 1967-2005 Citygate 6.82 8.11 4.17 4.86 4.47 3.46 1984-2012 Residential 11.57 12.75 9.43 9.92 9.93 9.14 1967-2012 Commercial 10.20 11.75 7.75 8.30 8.29 7.05 1967-2012 Industrial 9.07 10.80 6.56 7.02 7.04 5.77 1997-2012 Vehicle Fuel 7.72 11.32 7.61 5.55 7.32 7.01 1990-2012 Electric Power 6.72 8.23 4.44 4.99 4.71 3.68 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 2,740 2,406 2,773 2,647 2,934 1977-2011 Adjustments 33 -6 11 10 923 1977-2011 Revision Increases 355 263 259 548 1,486 1977-2011 Revision Decreases 273 491 189 451 1,889 1977-2011

236

Montana Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

5.72 7.50 3.16 3.64 1967-2010 5.72 7.50 3.16 3.64 1967-2010 Imports 6.66 8.22 3.88 4.13 3.75 2.45 1989-2012 Exports 6.16 8.14 3.63 4.05 3.82 2.40 1989-2012 Pipeline and Distribution Use 1967-2005 Citygate 6.42 7.71 5.63 5.17 5.11 4.23 1984-2012 Residential 9.91 11.45 9.50 8.64 8.80 8.06 1967-2012 Commercial 9.76 11.32 9.41 8.54 8.66 7.98 1967-2012 Industrial 9.75 11.04 9.06 8.07 8.13 7.54 1997-2012 Vehicle Fuel 7.64 11.50 9.08 9.60 8.20 6.48 1990-2012 Electric Power W W W W W W 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 1,052 1,000 976 944 778 1977-2011 Adjustments 9 -3 135 -19 -59 1977-2011 Revision Increases 92 41 132 103 43 1977-2011 Revision Decreases 74 56 210 100 97 1977-2011

237

Oklahoma Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

6.24 7.56 3.53 4.71 1967-2010 6.24 7.56 3.53 4.71 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.14 8.40 7.15 6.18 5.67 5.00 1984-2012 Residential 12.06 12.32 11.39 11.12 10.32 11.10 1967-2012 Commercial 10.94 11.54 10.59 9.77 8.94 8.95 1967-2012 Industrial 9.18 13.03 12.53 8.23 7.37 7.65 1997-2012 Vehicle Fuel 12.83 11.01 9.69 8.18 10.98 9.13 1991-2012 Electric Power 6.69 8.18 3.92 4.84 W 3.04 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 19,031 20,845 22,769 26,345 27,830 1977-2011 Adjustments 13 99 984 -394 -368 1977-2011 Revision Increases 2,115 2,786 2,894 3,224 5,142 1977-2011 Revision Decreases 1,366 2,580 3,592 3,474 6,856 1977-2011 Sales 1,545 395 600 219 2,995 2000-2011

238

JM to Revise DOE G 226.1-2, Federal Line Management Oversight of Department of Energy Nuclear Facilities  

Directives, Delegations, and Requirements

The Guide was developed in support of DOE O 226.1B to provides guidance that may be useful to DOE line management organizations in meeting the provisions of ...

2013-04-04T23:59:59.000Z

239

Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Bid schedule, special conditions, specifications, and subcontract drawings  

SciTech Connect

This volume contains: bidding requirements; terms and conditions; specifications for Division 1 -- general requirements; specifications for Division 2 -- sitework; specifications for Divisions 5 -- metals; subcontract drawings, (general, Union Carbide processing site, North Continent processing site, and Burro Canyon disposal site).

NONE

1995-10-01T23:59:59.000Z

240

Microsoft Word - AL 2010-07 Acquistion Letters Remaining in Effect May 2010 revision 1 June 2010  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

No. AL 2010-07 Rev. 1 No. AL 2010-07 Rev. 1 Acquisition Regulation Date 06/01/2010 ACQUISITION LETTER This Acquisition Letter is issued under the authority of the DOE and NNSA Senior Procurement Executives. Acquisition Letters (AL) that remain in effect are identified below. All other previously issued ALs have been superseded by a formal rule-making, incorporated into other guidance, and/or canceled. * * * * * * * * * * * * * * * * ACQUISITION LETTERS REMAINING IN EFFECT NUMBER DATE SUBJECT 93-4 04/07/1993 Displaced Workers Benefits Program 94-19 12/09/1994 Basic Labor Policies Fringe Benefits 95-06 06/28/1995 Personal Property Letter System 2000-09 11/11/2000 Source Selection Authority 2005-11 07/15/2005 Home Office Expenses for Management and

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

1Page ofProduct Code: 051000 Revision: 5 07 MAR 2002Issued: 7 Material Safety Data Sheet  

E-Print Network (OSTI)

ratings of 1, 3, 6, 10, 15, 20, 25, 30, 35, 40, 45, 60, 70, 80, 90, 100, 110, 125, 150, 175, 200, 225, 250. The 1999 NEC and the NEC Handbook are available from the NFPA, 11 Tracy Dr., Avon, MA 02322 800-344-3555 or 508-895-8300 · Fax: 800-593-6372 or 508-895-8301 · custserv@nfpa.org · www.nfpa.org #12;

Choi, Kyu Yong

242

Environmental assessment of remedial action at the Maybell Uranium Mill Tailings Site near Maybell, Colorado. Revision 1  

SciTech Connect

The purpose of this environmental assessment (EA) is to evaluate the environmental impacts resulting from remedial action at the Maybell uranium mill tailings site near Maybell, Colorado. A biological assessment (Attachment 1) and a floodplain/wetlands attachments describe the proposed action, affected environment, and environmental impacts associated with the proposed remedial action, including impacts to threatened and endangered species listed or proposed for listing by the US Fish and Wildlife Service (FWS).

Not Available

1994-04-01T23:59:59.000Z

243

Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18  

SciTech Connect

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

NONE

1995-10-01T23:59:59.000Z

244

Mixed Waste Focus Area Working Group: An Integrated Approach to Mercury Waste Treatment and Disposal. Revision 1  

SciTech Connect

May 1996, the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Work Group (HgWG). The HgWG was established to address and resolve the issues associated with Mercury- contaminated mixed wastes (MWs). During the initial technical baseline development process of the MWFA, three of the top four technology deficiencies identified were related to (1) amalgamation, (2) stabilization, and (3) separation and removal for the treatment of mercury and mercury-contaminated mixed waste (MW). The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these needs.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1997-09-08T23:59:59.000Z

245

Conversion and Blending Facility highly enriched uranium to low enriched uranium as uranyl nitrate hexahydrate. Revision 1  

SciTech Connect

This Conversion and Blending Facility (CBF) will have two missions: (1) convert HEU materials to pure HEU uranyl nitrate (UNH) and (2) blend pure HEU UNH with depleted and natural UNH to produce HEU UNH crystals. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. To the extent practical, the chemical and isotopic concentrations of blended LEU product will be held within the specifications required for LWR fuel. Such blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry. Otherwise, blended LEU Will be produced as a waste suitable for storage or disposal.

1995-07-05T23:59:59.000Z

246

Economic impact study of the Uranium Mill Tailings Remedial Action Project in Colorado: Colorado State fiscal year 1994. Revision 1  

SciTech Connect

The Colorado economic impact study summarizes employment and economic benefits to the state from activities associated with the Uranium Mill Tailings Remedial Action (UMTRA) Project during Colorado state fiscal year 1994 (1 July 1993 through 30 June 1994). To capture employment information, a questionnaire was distributed to subcontractor employees at the active UMTRA Project sites of Grand Junction, Naturita, Gunnison, and Rifle, Colorado. Economic data were requested from each site prime subcontractor, as well as from the Remedial Action Contractor. Information on wages, taxes, and subcontract expenditures in combination with estimates and economic multipliers is used to estimate the dollar economic benefits to Colorado during the state fiscal year. Finally, the fiscal year 1994 estimates are compared to fiscal year 1993 employment and economic information.

Not Available

1994-12-01T23:59:59.000Z

247

Remedial Investigation/Feasibility Study Work Plan for the 200-UP-1 Groundwater Operable Unit, Hanford Site, Richland, Washington. Revision  

Science Conference Proceedings (OSTI)

This work plan identifies the objectives, tasks, and schedule for conducting a Remedial Investigation/Feasibility Study for the 200-UP-1 Groundwater Operable Unit in the southern portion of the 200 West Groundwater Aggregate Area of the Hanford Site. The 200-UP-1 Groundwater Operable Unit addresses contamination identified in the aquifer soils and groundwater within its boundary, as determined in the 200 West Groundwater Aggregate Area Management Study Report (AAMSR) (DOE/RL 1992b). The objectives of this work plan are to develop a program to investigate groundwater contaminants in the southern portion of the 200 West Groundwater Aggregate Area that were designated for Limited Field Investigations (LFIs) and to implement Interim Remedial Measures (IRMs) recommended in the 200 West Groundwater AAMSR. The purpose of an LFI is to evaluate high priority groundwater contaminants where existing data are insufficient to determine whether an IRM is warranted and collect sufficient data to justify and implement an IRM, if needed. A Qualitative Risk Assessment (QRA) will be performed as part of the LFI. The purpose of an IRM is to develop and implement activities, such as contaminant source removal and groundwater treatment, that will ameliorate some of the more severe potential risks of groundwater contaminants prior to the RI and baseline Risk Assessment (RA) to be conducted under the Final Remedy Selection (FRS) at a later date. This work plan addresses needs of a Treatability Study to support the design and implementation of an interim remedial action for the Uranium-{sup 99}{Tc}-Nitrate multi-contaminant IRM plume identified beneath U Plant.

Not Available

1994-01-01T23:59:59.000Z

248

DWPF saltstone study: Effects of thermal history on leach index and physical integrity. Part 2, Final report: Revision 1  

SciTech Connect

This report summarizes the observations made during the curing and testing of DWPF simulated saltstones which have been cured under isothermal conditions in sealed glass envelopes at temperatures from room temperature to 95{degrees}C. This study was performed to evaluate the effect of curing at and around temperatures representing conditions created within large pours of grout. There appears to be no difference in the leaching resistance of samples cured at the same temperature for varying times to 1 year. Curing at higher temperatures decreases the effective diffusivity of this waste formulation. These results are encouraging in that leaching resistance for samples near the expected maximum vault temperature (55{degrees}C) show effective diffusion coefficients (D{sub effective} {approximately}10{sup {minus}8} cm{sup 2}/sec) that agree with previous work and values that are believed to adequately protect the groundwater. The isothermal conditions of these tests simulate the nearly adiabatic conditions existing near the centerline of the monolith. The elevated temperatures due to hydration heat decrease over long times. This has been simulated by a series (1X) of staged isothermal cures. Since modeling indicated it would take nearly two years for emplaced grout to cool to near ambient temperatures, accelerated (2X) cooling curves were also tested. Specimens cured under these staged-isothermal conditions appear to be no different from specimens cured under isothermal conditions for the same time at the maximum temperature. The unexpected generation of nitrous oxide within saltstone creates internal stresses which cause fracturing when exposed to leaching conditions. Such fracturing is not considered significant for saltstone emplaced in engineered vaults for disposal.

Orebaugh, E.G.

1992-11-18T23:59:59.000Z

249

Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevadas groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations are used to compute radionuclide concentrations in time and space within the CAU for the 1,000-year contaminant boundary. These three-dimensional (3-D) concentration simulations are integrated into probabilistic forecasts of the likelihood of groundwater exceeding or remaining below the radiological standards of the Safe Drinking Water Act (CFR, 2009) defined as the contaminant boundary. Contaminant boundaries are not discrete predictions of the location or concentration of contaminants, but instead are spatial representations of the probability of exceeding Safe Drinking Water Act radiological standards. The forecasts provide planning tools to facilitate regulatory decisions designed to protect the health and safety of the public.

Greg Ruskauff

2010-04-01T23:59:59.000Z

250

Hydrologic Tests at Characterization Wells R-9i, R-13, R-19, R-22, and R-31, Revision 1  

Science Conference Proceedings (OSTI)

Hydrologic information is essential for environmental efforts at Los Alamos National Laboratory. Testing at new characterization wells being drilled to the regional aquifer (''R wells'') to improve the conceptual hydrogeologic model of the Pajarito Plateau is providing such information. Field tests were conducted on various zones of saturation penetrated by the R wells to collect data needed for determining hydraulic properties. This document provides details of the design and execution of testing as well as an analysis of data for five new wells: R-9i, R-13, R-19, R-22, and R-31. One well (R-13) was evaluated by a pumping test and the rest (R-9i, R-19, R-22, and R-31) were evaluated by injection tests. Characterization well R-9i is located in Los Alamos Canyon approximately 0.3 mi west of the Route 4/Route 502 intersection. It was completed at a depth of 322 ft below ground surface (bgs) in March 2000. This well was constructed with two screens positioned below the regional water table. Both screens were tested. Screen 1 is completed at about 189-200 ft bgs in fractured basalt, and screen 2 is completed at about 270-280 ft bgs in massive basalt. Specific capacity analysis of the screen 1 data suggests that the fractured basalt has a transmissivity (T) of 589 ft{sup 2}/day and corresponds to a hydraulic conductivity (K) of 7.1 ft/day based on a saturated thickness of 83 ft. The injection test data from the massive basalt near screen 2 were analyzed by the Bouwer-Rice slug test methodology and suggest that K is 0.11 ft/day, corresponding to a T of about 2.8 ft{sup 2}/day based on a saturated thickness of 25 ft. Characterization well R-13 is located in Mortandad Canyon just west of the eastern Laboratory boundary. It was completed at a depth of 1029 ft bgs in February 2002. This well was constructed with one 60-ft long screen positioned about 125 ft below the regional water table. This screen is completed at about 958-1019 ft bgs and straddles the geologic contact between the Puye fanglomerate and unassigned pumiceous units. The specific capacity analysis of a 12 minute pumping test indicates that the Puye fanglomerates near the R-13 screen have a T of 5269 ft{sup 2}/day and correspond to a hydraulic conductivity (K) of 17.6 ft/day based on a saturated thickness of 300 ft. Characterization well R-19 is located east of firing site IJ in Technical Area (TA) 36 on the mesa between Three-mile and Potrillo Canyons. It was completed at a depth of 1885 ft bgs in April 2000. This well was constructed with two screens positioned above the regional water table and five screens positioned below the regional water table. Only the bottom two screens were tested. Screen 6 is completed at about 1727-1734 ft bgs in Puye fanglomerate, and screen 7 is completed at about 1832-1849 ft bgs in Puye fanglomerate. Specific capacity analysis of the screen 6 data suggests that T is about 6923 ft{sup 2}/day and corresponds to a K of 18.6 ft/day based on a saturated thickness of 373 ft. Specific capacity analysis of the screen 7 data suggests that T is about 8179 ft{sup 2}/day and corresponds to a K of 22.0 ft/day based on a saturated thickness of 373 ft. Characterization well R-22 is located on Mesita del Buey between Canada del Buey and Pajarito Canyons immediately east of Material Disposal Area (MDA) G in TA-54. It was completed at a depth of 1489 ft bgs in October 2000. This well was constructed with five screens positioned at or below the regional water table; however, only screens 2-5 were tested. Screen 1 is completed at the regional water table at about 872-914 ft bgs in Cerros del Rio basalt. Screen 2 is completed at about 947-989 ft bgs in Cerros del Rio basalt. Screen 3 is completed at about 1272-1279 ft bgs in Puye fanglomerate. Screen 4 is completed at about 1378-1452 ft bgs in older basalt. Screen 5 is completed at about 1447-1452 ft bgs in older fanglomerate. Bouwer-Rice analyses of the injection-test recovery data suggest K values of 0.04, 0.32, 0.54, and 0.27 ft/day for screens 2, 3, 4, and 5, respectively. These values correspond to

S.G.McLin; W.J. Stone

2004-06-01T23:59:59.000Z

251

Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Rifle, Colorado. Revision 1  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase 1) and the Ground Water Project (Phase 2). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment.

NONE

1995-08-01T23:59:59.000Z

252

Economic impact study of the Uranium Mill Tailings Remedial Action project in Colorado: Colorado state fiscal year 1995. Revision 1  

Science Conference Proceedings (OSTI)

As required by the Romer-Twining Agreement of 1990, the US Department of Energy (DOE) has prepared this annual economic impact study for the state of Colorado. This report assesses the economic impacts related to the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project in Colorado during the state fiscal year (FY) between 1 July 1994 and 30 June 1995. To estimate net economic benefit, employment, salaries and wages, and other related economic benefits are discussed, quantified, and then compared to the state`s 10 percent share of the remedial action costs. Actual data obtained from sites currently undergoing remedial action were used as the basis for analyses. If data were not available, estimates were used to derive economic indicators. This study describes the types of employment associated with the UMTRA Project and estimates of the numbers of people employed by UMTRA Project subcontractors in Colorado during state FY 1995. Employment totals are reported in estimated average annual jobs; however, the actual number of workers at the site fluctuates depending on weather and on the status of remedial action activities. In addition, the actual number of people employed on the Project during the year may be higher than the average annual employment reported due to the temporary nature of some of the jobs.

NONE

1995-12-01T23:59:59.000Z

253

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Green River, Utah. Revision 1  

Science Conference Proceedings (OSTI)

The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase 1) and the Ground Water Project (phase 2). For the UMTRA Project site located near Green River, Utah, the Surface Project cleanup occurred from 1988 to 1989. The tailings and radioactively contaminated soils and materials were removed from their original locations and placed into a disposal cell on the site. The disposal cell is designed to minimize radiation emissions and minimize further contamination of ground water beneath the site. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. For the Green River site, the risk assessment helps determine whether human health risks result from exposure to ground water contaminated by uranium processing. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Green River site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.

NONE

1995-09-01T23:59:59.000Z

254

Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites, Slick Rock, Colorado. Revision 1  

SciTech Connect

The Uranium Mill Tailings Radiation Control Act of 1978 (42 USC {section}7901 et seq.), hereafter referred to as the UMTRCA, authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miquel County. Contaminated materials cover an estimated 63 acres of the Union Carbide (UC) processing site and 15 ac of the North Continent (NC) processing site. The sites are within 1 mile of each other and are adjacent to the Dolores River. The sites contain concrete foundations of mill buildings, tailings piles, and areas contaminated by windblown and waterborne radioactive tailings materials. The total estimated volume of contaminated materials is approximately 621,300 cubic yards (yd{sup 3}). In addition to the contamination in the two processing site areas, four VPs were found to contain contamination. As a result of the tailings being exposed to the environment, contamination associated with the UC and NC sites has leached into shallow ground water. Surface water has not been affected. The closest residence is approximately 0.3 air mi from either site. The proposed action is to remediate the UC and NC sites by removing all contaminated materials within the designing site boundaries or otherwise associated with the sites, and relocating them to, and stabilizing them at, a location approximately 5 road mi northeast of the sites on land administered by the Bureau of Land Management (BLM).

1994-09-01T23:59:59.000Z

255

Corrrective action decision document for the Cactus Spring Waste Trenches (Corrective Action Unit No. 426). Revision No. 1  

SciTech Connect

The Corrective Action Decision Document (CADD) for the Cactus Spring Waste Trenches (Corrective Action Unit [CAU] No. 426) has been prepared for the US Department of Energy`s (DOE) Nevada Environmental Restoration Project. This CADD has been developed to meet the requirements of the Federal Facility Agreement and Consent Order (FFACO) of 1996, stated in Appendix VI, {open_quotes}Corrective Action Strategy{close_quotes} (FFACO, 1996). The Cactus Spring Waste Trenches Corrective Action Site (CAS) No. RG-08-001-RG-CS is included in CAU No. 426 (also referred to as the {open_quotes}trenches{close_quotes}); it has been identified as one of three potential locations for buried, radioactively contaminated materials from the Double Tracks Test. The trenches are located on the east flank of the Cactus Range in the eastern portion of the Cactus Spring Ranch at the Tonopah Test Range (TTR) in Nye County, Nevada, on the northern portion of Nellis Air Force Range. The TTR is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada, by air and approximately 56 km (35 mi) southeast of Tonopah, Nevada, by road. The trenches were dug for the purpose of receiving waste generated during Operation Roller Coaster, primarily the Double Tracks Test. This test, conducted in 1963, involved the use of live animals to assess the biological hazards associated with non-nuclear detonation of plutonium-bearing devices (i.e., inhalation uptake of plutonium aerosol). The CAS consists of four trenches that received solid waste and had an overall impacted area of approximately 36 meters (m) (120 feet [ft]) long x 24 m (80 ft) wide x 3 to 4.5 m (10 to 15 ft) deep. The average depressions at the trenches are approximately 0.3 m (1 ft) below land surface.

NONE

1997-06-01T23:59:59.000Z

256

Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1  

Science Conference Proceedings (OSTI)

The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

Not Available

1993-01-01T23:59:59.000Z

257

Analysis of removal alternatives for the Heavy Water Components Test Reactor at the Savannah River Site. Revision 1  

SciTech Connect

This engineering study evaluates different alternatives for decontamination and decommissioning of the Heavy Water Components Test Reactor (HWCTR). Cooled and moderated with pressurized heavy water, this uranium-fueled nuclear reactor was designed to test fuel assemblies for heavy water power reactors. It was operated for this purpose from march of 1962 until December of 1964. Four alternatives studied in detail include: (1) dismantlement, in which all radioactive and hazardous contaminants would be removed, the containment dome dismantled and the property restored to a condition similar to its original preconstruction state; (2) partial dismantlement and interim safe storage, where radioactive equipment except for the reactor vessel and steam generators would be removed, along with hazardous materials, and the building sealed with remote monitoring equipment in place to permit limited inspections at five-year intervals; (3) conversion for beneficial reuse, in which most radioactive equipment and hazardous materials would be removed and the containment building converted to another use such as a storage facility for radioactive materials, and (4) entombment, which involves removing hazardous materials, filling the below-ground structure with concrete, removing the containment dome and pouring a concrete cap on the tomb. Also considered was safe storage, but this approach, which has, in effect, been followed for the past 30 years, did not warrant detailed evaluation. The four other alternatives were evaluate, taking into account factors such as potential effects on the environment, risks, effectiveness, ease of implementation and cost. The preferred alternative was determined to be dismantlement. This approach is recommended because it ranks highest in the comparative analysis, would serve as the best prototype for the site reactor decommissioning program and would be most compatible with site property reuse plans for the future.

Owen, M.B.

1997-04-01T23:59:59.000Z

258

Standard format and content acceptance criteria for the Material Control and Accounting (MC and A) Reform Amendment: 10 CFR Part 74, Subpart E. Revision 1  

SciTech Connect

In 1987 the NRC revised the material control and accounting requirements for NRC licensees authorized to possess and use a formula quantity (i.e., 5 formula kilograms or more) of strategic special nuclear material. Those revisions issued as 10 CFR 74.51-59 require timely monitoring of in-process inventory and discrete items to detect anomalies potentially indicative of material losses. Timely detection and enhanced loss localization capabilities are beneficial to alarm resolution and also for material recovery in the event of an actual loss. NUREG-1280 was issued in 1987 to present criteria that could be used by applicants, licensees, and NRC license reviewers in the initial preparation and subsequent review of fundamental nuclear material control (FNMC) plans submitted in response to the Reform Amendment. This document is also intended for both licensees and license reviewers with respect to FNMC plan revisions. General performance objectives, system capabilities, process monitoring, item monitoring, alarm resolution, quality assurance, and accounting are addressed. This revision to NUREG-1280 is an expansion of the initial edition, which clarifies and expands upon several topics and addresses issues identified under Reform Amendment implementation experience.

NONE

1995-04-01T23:59:59.000Z

259

System Performance Comparison of Stencil Operations with the Convey HC-1Revised version 2011/02/17, fixed peak performance of the HC-1  

E-Print Network (OSTI)

/02/17, fixed peak performance of the HC-1 Julian M. Kunkel, Petra Nerge Research Group: Scientifc Computing: // for all rows for j: // for all columns m[i][j] = a * o[i][j+1] + b * o[i][j-1] + c * o[i-1][j] + d * o[i+1++) / over a l l columns / { star = Matrix [m2 ] [ i -1][ j ] + Matrix [m2 ] [ i ] [ j -1] + Matrix [m2 ] [ i

260

Word Pro - Untitled1  

U.S. Energy Information Administration (EIA) Indexed Site

7 7 Strategic Petroleum Reserve, 1977-2011 End-of-Year Stocks in SPR Crude Oil Imports for SPR¹ SPR as Share of Domestic Stocks SPR Stocks as Days of Petroleum Net Imports² 158 U.S. Energy Information Administration / Annual Energy Review 2011 1 Imported by SPR and imported by others for SPR. 2 Derived by dividing end-of-year SPR stocks by annual average daily net imports of all petroleum. Note: SPR=Strategic Petroleum Reserve. Source: Table 5.17. 1980 1985 1990 1995 2000 2005 2010 0 200 400 600 800 Million Barrels 8 59 24 16 93 60 85 72 43 18 27 19 20 10 0 4 5 4 0 1 0 8 7 5 9 41 23 34 19 3 3 7 20 0 0 1980 1985 1990 1995 2000 2005 2010 0 25 50 75 100 Million Barrels 1 8 11 17 43 68 88 96 115 94 91 85 81 82 86 83 77 73 75 67 62 59 57 52 50 57 57 56

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261

HNF-37489-FP Revision  

Office of Scientific and Technical Information (OSTI)

HNF-37489-FP HNF-37489-FP Revision 0 Project Hanford Management Contractor foc the US. Deparbnsnt of Energy under Contract DE-ACO6-96RL13200 FLUOR, P.O. Box 1000 Richland, Washington Implementation of the Seismic Design Criteria for DOE-STD-I 189-2008, Appendix A HNF-37489-FP Revision 0 Implementation of the Seismic Design Criteria for DOE-STD-1189- 2008, Appendix A S. K. Omberg Fluor Government Group Date Published April 2008 To Be Presented at The Nuclear Renaissanm. Safety Analysls for the New Nuclear Age Energy Facility Contractow Group May 3 - 8,2008 Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Pmject Hanford Management CcntractOr for the US. Department of Energy under Contract DE-AC0696RL132W FLUOR, P.O. Box I000

262

ADR Revised Policy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Alternative Dispute Resolution Alternative Dispute Resolution AGENCY: Department of Energy. ACTION: Notice of Revised Policy Statement. SUMMARY: On October 24, 1995, the Department of Energy (DOE) published an interim Statement of Policy on Alternative Dispute Resolution (ADR) (60 FR 54482) to further its commitment to the use of ADR for resolving issues in controversy in a fair, timely, and cost efficient manner, and to comply with the Administrative Dispute Resolution Act (ADRA), 5 U.S.C. §571 et seq. Today, DOE publishes a revised Statement of Policy on Alternative Dispute Resolution to reaffirm its commitment to the use of ADR, including the use of Environmental Conflict Resolution (ECR) and other collaborative processes that may be utilized to prevent or avoid potential conflicts.

263

Addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada, Revision 1  

SciTech Connect

This document constitutes an addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada (Revision 1), December 2002 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: This page that refers the reader to the SIR document for additional information The cover, title, and signature pages of the SIR document The NDEP approval letter The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 06-25-01, CP-1 Heating Oil Release. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

Grant Evenson

2009-05-01T23:59:59.000Z

264

The Ohio State University Office of Human Resources Page 1 of 1 Retirement & SRA Provider Lists Revised 11/25/13  

E-Print Network (OSTI)

, and the Pryor Investment Team 41 S. High St. (HC0220) Columbus, OH 43215 614-480-0720 TIAA-CREF1 485 Metro Place S, Ste 450 Dublin, OH 43017-5335 614-659-1000 1-877-ARP-OHIO (1-877-277-6446 tiaa-cref.org/osu VALIC 44131 1-800-417-9099 legendgroup.com TIAA-CREF3 485 Metro Place S, Ste 450 Dublin, OH 43017 614

265

The Ohio State University Office of Human Resources Page 1 of 1 Retirement & SRA Provider Lists Revised 06/13/13  

E-Print Network (OSTI)

, and the Pryor Investment Team 41 S. High St. (HC0220) Columbus, OH 43215 (614) 480-0720 TIAA-CREF1 485 Metro Place S, Ste 450 Dublin, OH 43017-5335 (614) 659-1000 1-877-ARP-OHIO (1-877-277-6446 tiaa Independence, OH 44131 1-800-417-9099 legendgroup.com TIAA-CREF 3 485 Metro Place S, Ste 450 Dublin, OH 43017

266

IEEE TRANSACTIONS ON IMAGE PROCESSING, EDICS 2.3 / 1.4. REVISED 7/12/99. 1 Exact Distribution of Edge-Preserving MAP Estimators  

E-Print Network (OSTI)

-parametric estimation in the case of incomplete data," Signal Processing, vol. 42, no. 1, pp. 3­17, 1995. [7] L Bedini

Erdogan, Hakan

267

INTEGRATED ENERGY POLICY REPORT COMMITTEE REVISED HEARING AGENDA  

E-Print Network (OSTI)

INTEGRATED ENERGY POLICY REPORT COMMITTEE REVISED HEARING AGENDA DAY 1 Committee's Draft 2007 Integrated Energy Policy Report Monday, October 15, 2007 9:00 a.m. Hearing Room A ­ California Energy. General Public Comments #12;INTEGRATED ENERGY POLICY REPORT COMMITTEE REVISED HEARING AGENDA DAY 2

268

Computer Engineering Undergraduate Handbook Revised: June 4, 2012  

E-Print Network (OSTI)

Computer Engineering Undergraduate Handbook Revised: June 4, 2012 BACHELOR OF SCIENCE IN COMPUTER-278-5987 Fax: 657-278-5804 http://www.fullerton.edu/ecs/cpe #12;Computer Engineering Undergraduate Handbook Engineering Undergraduate Handbook Revised: June 4, 2012 TOC 1 COMPUTER ENGINEERING PROGRAM UNDERGRADUATE

de Lijser, Peter

269

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada Test Site, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. The Test Cell C (TCC) Facility is located in Area 25 of the Nevada Test Site (NTS) approximately 25 miles northwest of Mercury, Nevada (Figure 1). CAU 116 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) of 1996 (as amended February 2008) and consists of two Corrective Action Sites (CASs): (1) CAS 25-23-20, Nuclear Furnace Piping; and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 is described in the FFACO as the TCC Facility but actually includes Building 3210 and attached concrete shield wall only. CAU 116 will be closed by demolishing Building 3210, the attached concrete shield wall, and the nuclear furnace piping. In addition, as a best management practice (BMP), Building 3211 (moveable shed) will be demolished due to its close proximity to Building 3210. This will aid in demolition and disposal operations. Radiological surveys will be performed on the demolition debris to determine the proper disposal pathway. As much of the demolition debris as space allows will be placed into the Building 3210 basement structure. After filling to capacity with demolition debris, the basement structure will be mounded or capped and closed with administrative controls. Prior to beginning demolition activities and according to an approved Sampling and Analysis Plan (SAP), representative sampling of surface areas that are known, suspected, or have the potential to contain hazardous constituents such as lead or polychlorinated biphenyls (PCBs) will be performed throughout all buildings and structures. Sections 2.3.2, 4.2.2.2, 4.2.2.3, 4.3, and 6.2.6.1 address the methodologies employed that assure the solid debris placed in the basement structure will not contain contaminants of concern (COCs) above hazardous waste levels. The anticipated post-closure-posting requirements for the mounded/capped basement structure, as well as for the entire CAU, are addressed in Section 4.2.10. The site contains radiologically impacted surfaces and hazardous materials. Based on review of the historical information for CAU 116 and recent site inspections, there is sufficient process knowledge to close CAU 116 using the SAFER process. CAUs that may be closed using the SAFER process have conceptual corrective actions that are clearly identified. Consequently, corrective action alternatives can be chosen prior to completing a corrective action investigation, given anticipated investigation results. The SAFER process combines elements of the data quality objective (DQO) process and the observational approach to plan and conduct closure activities. The DQOs are used to identify the problem and define the type and quality of data needed to complete the investigation phase of the SAFER process. The purpose of the investigation phase is to verify the adequacy of existing information used to determine the chosen corrective action. The observational approach provides a framework for managing uncertainty during the planning and decision-making phases of the project. The SAFER process allows for technical decisions to be made based on information gathered during site visits, interviews, meetings, research, and a consensus of opinion by the decontamination and decommissioning (D&D) team members. Any uncertainties are addressed by documented assumptions that are verified by sampling and analysis, data evaluation, onsite observations, and contingency plans, as necessary. Closure activities may proceed simultaneously with site characterization as sufficient data are gathered to confirm or disprove the assumptions made during selection of the corrective action. If, at any time during the closure process, new information is discovered that indicates that closure activities should be revised, closure activities will be reevaluated as appropriate. Based on a detailed review of historical documentation, there is sufficient process know

NSTec Environmental Restoration

2008-12-01T23:59:59.000Z

270

FTCP Corrective Action Plan- Revision 2  

Energy.gov (U.S. Department of Energy (DOE))

March 2009 FTCP Corrective Action Plan, Revision 2, which is Deliverable B for Commitment 13 in the Department of Energy (DOE) Implementation Plan to Improve Oversight of Nuclear Operations, issued in response to Defense Nuclear Facilities Safety Board Recommendation 2004-1, Oversight of Complex, High-Hazard Nuclear Operations

271

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST  

E-Print Network (OSTI)

CALIFORNIA ENERGY DEMAND 2014­2024 REVISED FORECAST Volume 1: Statewide Electricity Demand in this report. #12;i ACKNOWLEDGEMENTS The demand forecast is the combined product of the hard work listed previously, Mohsen Abrishami prepared the commercial sector forecast. Mehrzad Soltani Nia helped

272

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022  

E-Print Network (OSTI)

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022 Volume 1: Statewide Electricity Demand in this report. #12;i ACKNOWLEDGEMENTS The staff demand forecast is the combined product of the hard work listed previously, Mohsen Abrishami prepared the commercial sector forecast. Mehrzad Soltani Nia helped

273

Coal Data Publication Revision Policy  

U.S. Energy Information Administration (EIA) Indexed Site

THEN Survey Manager determines impact: WHAT happens next to the database and in our coal reports: Respondent provides data that are clearly incorrect or revised data for any...

274

EPA Revises Emissions Estimation Methodology  

U.S. Energy Information Administration (EIA)

The changes to the historical emission estimates are the result of revisions to the data and estimation ... b K.D . Smythe, RAND ... RAND Environmental Science and ...

275

Calculation of releases of radioactive materials in gaseous and liquid effluents from pressurized water reactors (PWR-GALE Code). Revision 1  

SciTech Connect

This report revises the original issuance of NUREG-0017, ''Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE-Code)'' (April 1976), to incorporate more recent operating data now available as well as the results of a number of in-plant measurement programs at operating pressurized water reactors. The PWR-GALE Code is a computerized mathematical model for calculating the releases of radioactive material in gaseous and liquid effluents (i.e., the gaseous and liquid source terms). The US Nuclear Regulatory Commission uses the PWR-GALE Code to determine conformance with the requirements of Appendix I to 10 CFR Part 50.

Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

1985-04-01T23:59:59.000Z

276

Corrective Action Decision Document for Corrective Action Unit 322: Areas 1 and 3 Release Sites and Injection Wells Nevada Test Site, Nevada, Revision 0 with ROTC 1  

Science Conference Proceedings (OSTI)

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 322, Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 322 is comprised of the following corrective action sites (CASs): (1) 01-25-01 - AST Release Site; (2) 03-25-03 - Mud Plant and AST Diesel Release; and (3) 03-20-05 - Injection Wells and BOP Shop. The purpose of this Corrective Action Decision Document is to identify and provide the rationale for the recommendation of a corrective action alternative for each CAS within CAU 322. Corrective action investigation activities were performed from April 2004 through September 2004, as set forth in the Corrective Action Investigation Plan. The purposes of the activities as defined during the data quality objectives process were: (1) Determine if contaminants of concern (COCs) are present; (2) If COCs are present, determine their nature and extent; and (3) Provide sufficient information and data to recommend appropriate corrective actions for the CASs. Analytes detected during the corrective action investigation were evaluated against appropriate preliminary action levels to identify contaminants of concern for each corrective action site. Radiological field measurements were compared to unrestricted release criteria. Assessment of the data generated from investigation activities revealed the following: (1) CAS 01-25-01 contains an AST berm contaminated with total petroleum hydrocarbons (TPH) diesel-range organics (DRO). (2) CAS 03-25-03 includes two distinct areas: Area A where no contamination remains from a potential spill associated with an AST, and Area B where TPH-DRO contamination associated with various activities at the mud plant was identified. The Area B contamination was found at various locations and depths. (3) CAS 03-25-03 Area B contains TPH-DRO contamination at various locations and depths in the area associated with the Mud Plant. (4) CAS 03-20-05 contains TPH-DRO, metals, and radiological contamination within the injection well casing soil and TPH-DRO contamination at the depth coincidental with the bottom of the injection well sump. Based on the evaluation of analytical data from the corrective action investigation, review of future and current operations in Areas 1 and 3 of the Nevada Test Site, and the detailed and comparative analysis of the potential corrective action alternatives, the following corrective actions are recommended for the Corrective Action Unit 322 CASs. Closure in Place with Administrative Controls is the preferred corrective action for the following CASs: (1) CAS 01-25-01, removal of TPH-DRO contamination would pose a significant safety hazard due to the site location. (2) CAS 03-25-03 No contamination remains at Area A (AST Berm); and thus, no further action is the preferred alternative at this part of the CAS. However at Area B, TPH-DRO contamination is varied in concentration and location and the footprint of the CAS is large, removal of contaminated ''pockets'' would be laborious and cost prohibitive. The plutonium-239 surface contamination identified at CAS 03-25-03 Area B has been removed and drummed as a best management practice. (3) CAS 03-20-05, TPH-DRO, metals, and radiological contamination are present in the injection well casing soils. Recommend corrective action includes removal of the liquid in the injection well sump (approximately 3 feet (ft) of liquid at 60 ft below ground surface), grouting the sump, and the area within the injection well casing. The plutonium-239 surface contamination identified at CAS 03-20-05 has been removed and drummed as a best management practice and will be disposed of as low-level radioactive waste. It is recommended that the liquids be removed from the holding tank wells and the sumps of the two outer holding tanks within the BOP Shop, and the sumps be grouted, and the holding tanks filled in to the BOP Shop floor surface. The preferred corrective action alternatives were ev

Boehlecke, Robert

2004-12-01T23:59:59.000Z

277

REPORT NO. 6 revised fallout  

E-Print Network (OSTI)

REPORT NO. 6 revised fallout estimates for 1964-1965 and verification of the 1963 predictions October 1964 Report of the FEDERAL RADIATION COUNCIL #12;REPORT NO. 6 revised fallout estimates - #12;SUMMARY On the basis of information available in June 1964, new estimates of the levels of fallout

278

2008 MERRTT Revision Letter  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

November 2, 2007 November 2, 2007 The U.S. Department of Energy (DOE) Transportation Emergency Preparedness Program (TEPP) is pleased to announce the release of the 2008 Modular Emergency Response Radiological Transportation Training (MERRTT). This revision replaces the 2005 MERRTT CD-ROM set. As required by the WIPP Land Withdrawal Act, the 2008 MERRTT has been sent to the Occupational, Safety and Health Administration (OSHA) for review. The 2008 version of MERRTT includes several enhancements, but the primary enhancement is the addition of the decontamination dress-down video. Comments received on the decontamination video script in the fall 2006 were incorporated into the script and the filming and final editing were completed in the spring 2007. The decontamination video was added to MERRTT to support the students'

279

Recent Revisions to PVWATTS  

DOE Green Energy (OSTI)

PVWATTS is an Internet-accessible software program that allows the user to easily calculate the energy production and cost savings for grid-connected photovoltaic (PV) systems located throughout the United States. To ensure that PVWATTS continues to meet its users' needs, an online survey form was provided to users to identify areas for improvement. The results of the survey were used to prioritize improvements to PVWATTS in FY2005. PVWATTS was revised by changing the PV system specification input for system size from an AC power rating to a nameplate DC power rating; adding an input for an overall DC to AC derate factor; updating the residential electric rates; adding monthly and yearly solar radiation values for the PV array; and simplifying the user interface for Version 2.

Marion, B.; Anderberg, M.; Gray-Hann, P.

2005-11-01T23:59:59.000Z

280

2013-2014 Additions and Revisions  

Science Conference Proceedings (OSTI)

The 2013 2014 Additions and Revisions are now available with seven new methods, including three for testing 3-MCPD, and revisions to 25 previously approved methods. 2013-2014 Additions and Revisions Hardback Books Methods - Analyses Books Methods - An

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281

Supplemental design requirements document, Project W026. Revision 3  

SciTech Connect

This document supplements and extends the Functional Design Criteria, SP-W026-FDC-001, for the Waste Receiving and Processing Facility (WRAP), Module 1. It provides additional detailed requirements, summarizes key Westinghouse Hanford Company design guidance, and establishes baseline technical agreements to be used in definitive design of the WRAP-1 facility. Revision 3 of the Supplemental Design Requirements Document has been assigned an Impact Level of 3ESQ based on the content of the entire revision. The actual changes made from Revision 2 have an Impact Level of 3S and the basis for these changes was previously reviewed and approved per WHC correspondence No. 9355770.

Weidert, J.R.

1993-10-08T23:59:59.000Z

282

Building Technologies Office: Standards Development and Revision  

NLE Websites -- All DOE Office Websites (Extended Search)

and Revision to someone by E-mail Share Building Technologies Office: Standards Development and Revision on Facebook Tweet about Building Technologies Office: Standards Development...

283

Utah Dry Natural Gas Reserves Revision Decreases (Billion Cubic...  

Gasoline and Diesel Fuel Update (EIA)

Decreases (Billion Cubic Feet) Utah Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

284

Utah Crude Oil + Lease Condensate Reserves Revision Decreases...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Million Barrels) Utah Crude Oil + Lease Condensate Reserves Revision Decreases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

285

Utah Natural Gas, Wet After Lease Separation Reserves Revision...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Utah Natural Gas, Wet After Lease Separation Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6...

286

Utah Natural Gas, Wet After Lease Separation Reserves Revision...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Utah Natural Gas, Wet After Lease Separation Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6...

287

Utah Coalbed Methane Proved Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Utah Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

288

Utah Coalbed Methane Proved Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Utah Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

289

Utah Dry Natural Gas Reserves Revision Increases (Billion Cubic...  

Annual Energy Outlook 2012 (EIA)

Increases (Billion Cubic Feet) Utah Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

290

Utah Crude Oil + Lease Condensate Reserves Revision Increases...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Million Barrels) Utah Crude Oil + Lease Condensate Reserves Revision Increases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

291

Miscellaneous States Shale Gas Proved Reserves Revision Increases...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Miscellaneous States Shale Gas Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

292

Miscellaneous States Shale Gas Proved Reserves Revision Decreases...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Miscellaneous States Shale Gas Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

293

California Dry Natural Gas Reserves Revision Decreases (Billion...  

Annual Energy Outlook 2012 (EIA)

Decreases (Billion Cubic Feet) California Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

294

California Dry Natural Gas Reserves Revision Increases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) California Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

295

Ohio Dry Natural Gas Reserves Revision Increases (Billion Cubic...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Ohio Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

296

Ohio Dry Natural Gas Reserves Revision Decreases (Billion Cubic...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Ohio Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

297

U.S. Natural Gas Plant Liquids, Reserves Revision Decreases ...  

Gasoline and Diesel Fuel Update (EIA)

Decreases (Million Barrels) U.S. Natural Gas Plant Liquids, Reserves Revision Decreases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

298

U.S. Natural Gas Plant Liquids, Reserves Revision Increases ...  

Annual Energy Outlook 2012 (EIA)

Increases (Million Barrels) U.S. Natural Gas Plant Liquids, Reserves Revision Increases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

299

Michigan Dry Natural Gas Reserves Revision Increases (Billion...  

Annual Energy Outlook 2012 (EIA)

Increases (Billion Cubic Feet) Michigan Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

300

Michigan Dry Natural Gas Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Michigan Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

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301

U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion...  

Annual Energy Outlook 2012 (EIA)

Decreases (Billion Cubic Feet) U.S. Coalbed Methane Proved Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

302

U.S. Coalbed Methane Proved Reserves Revision Increases (Billion...  

Annual Energy Outlook 2012 (EIA)

Increases (Billion Cubic Feet) U.S. Coalbed Methane Proved Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

303

Colorado Dry Natural Gas Reserves Revision Decreases (Billion...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Colorado Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

304

U.S. Crude Oil + Lease Condensate Reserves Revision Decreases...  

Gasoline and Diesel Fuel Update (EIA)

Decreases (Million Barrels) U.S. Crude Oil + Lease Condensate Reserves Revision Decreases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

305

U.S. Crude Oil + Lease Condensate Reserves Revision Increases...  

Gasoline and Diesel Fuel Update (EIA)

Increases (Million Barrels) U.S. Crude Oil + Lease Condensate Reserves Revision Increases (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

306

New Mexico - West Dry Natural Gas Reserves Revision Increases...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) New Mexico - West Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

307

New Mexico Dry Natural Gas Reserves Revision Increases (Billion...  

Annual Energy Outlook 2012 (EIA)

Increases (Billion Cubic Feet) New Mexico Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

308

New Mexico - East Dry Natural Gas Reserves Revision Decreases...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) New Mexico - East Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

309

New Mexico - West Dry Natural Gas Reserves Revision Decreases...  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) New Mexico - West Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

310

New Mexico - East Dry Natural Gas Reserves Revision Increases...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) New Mexico - East Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

311

Texas Dry Natural Gas Reserves Revision Increases (Billion Cubic...  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Texas Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

312

Southeast Regional Clean Energy Policy Analysis (Revised)  

NLE Websites -- All DOE Office Websites (Extended Search)

Southeast Regional Clean Southeast Regional Clean Energy Policy Analysis Revised Joyce McLaren Technical Report NREL/TP-6A20-49192 Revised April 2011 ERRATA SHEET NREL REPORT/PROJECT NUMBER: TP-6A20-49192 TITLE: Southeast Regional Clean Energy Policy Analysis AUTHOR(S): Joyce McLaren ORIGINAL PUBLICATION DATE: January 2011 DATE OF CORRECTIONS (MM/YYYY): 04/2011 The following figures and tables were replaced: Page vii, Figure ES-2 Page ix, Table ES-1 Page 12, Table 1 Page 20, Figure 10 Page 51, Table 11 Page 52, Figure 18 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401

313

Preference revision via declarative debugging  

Science Conference Proceedings (OSTI)

Preference criteria are rarely static. Often they are subject to modification and aggregation. The resulting preference criteria may not satisfy the properties of the original ones and must therefore be revised. This paper investigates the problem of ...

Pierangelo DellAcqua; Lus Moniz Pereira

2005-12-01T23:59:59.000Z

314

Coal within a revised energy perspective  

SciTech Connect

The author considers the use of coal within a revised energy perspective, focusing on the factors that will drive which fuels are used to generate electricity going forward. He looks at the world markets for fossil fuels and the difficulties of predicting oil and natural gas supply and prices, as demonstrated by the variability in projections from one year to another in the EIA's Annual Energy Outlook. 4 refs., 1 tab.

Darmstadter, J. [Resources for the Future (RFF), Washington, DC (United States)

2006-07-15T23:59:59.000Z

315

L S U H S C -N O S t u d e n t F i n a n c i a l A i d O f f i c e AdditionalFederalStaffordLoanRequestForm Page 1 of 1 Revised 2/11/2010  

E-Print Network (OSTI)

L S U H S C - N O S t u d e n t F i n a n c i a l A i d O f f i c e AdditionalFederalStaffordLoanRequestForm Page 1 of 1 Revised 2/11/2010 Federal Stafford Loan for 2010-2011 Additional Amount Request Form You have already requested a Federal Stafford loan for the 2010-2011 academic year using the Master

316

Original","Revised","Data  

U.S. Energy Information Administration (EIA) Indexed Site

,,"Original","Revised","Data" ,,"Original","Revised","Data" "Data Type","Product","End Use","PADD","State","Data 2003","Data 2003","Different" "Sales","No. 1 Distillate","Residential","U.S. TOTAL",,110032,110032 "Sales","No. 1 Distillate","Residential","PADD 1",,4232,4232 "Sales","No. 1 Distillate","Residential","PADD 1A",,2085,2085 "Sales","No. 1 Distillate","Residential","Connecticut","CT" "Sales","No. 1 Distillate","Residential","Maine","ME",536,536 "Sales","No. 1 Distillate","Residential","Massachusetts","MA",678,678

317

Word Pro - Untitled1  

U.S. Energy Information Administration (EIA) Indexed Site

9 9 Table 5.17 Strategic Petroleum Reserve, 1977-2011 (Million Barrels, Except as Noted) Year Foreign Crude Oil Receipts Domestic Crude Oil Receipts Withdrawals End-of-Year Stocks Days of Petroleum Net Imports 4 Imported by SPR Imported by Others 1,2 Purchases Exchanges 2 Sales Exchanges Quantity Percent of Crude Oil 3 Stocks Percent of Total Petroleum Stocks 1977 7.54 0.00 5 0.37 0.00 0.00 0.00 7.46 2.1 0.6 1 1978 58.80 .00 .00 .00 .00 .00 66.86 17.8 5.2 8 1979 24.43 .00 (s) .00 .00 .00 91.19 21.2 6.8 11 1980 16.07 .00 1.30 .00 .00 .00 107.80 23.1 7.7 17 1981 93.30 .00 28.79 .00 .00 .00 230.34 38.8 15.5 43 1982 60.19 .00 3.79 .00 .00 .00 293.83 45.7 20.5 68 1983 85.29 .00 .42 .00 .00 .00 379.09 52.4 26.1 88 1984 72.04 .00 .05 .00 .00 .00 450.51 56.6 28.9 96 1985 43.12 .00 .17 .00 .00 .00 493.32 60.6 32.5 115 1986 17.56 .00 1.21 .00 .00 .00 511.57 60.7

318

Condensate Polishing Guidelines for PWR and BWR Plants -- 1997 Revision  

Science Conference Proceedings (OSTI)

Successful condensate polishing operations maintain control of ionic and particulate impurity transport to the PWR steam generator and the BWR reactor and recirculation system. This report presents revisions of EPRI's 1993 nuclear industry consensus guidelines for the design and operation of deep bed and filter demineralizer condensate polishers. This advice is consistent with the 1996 revisions of EPRI's BWR Water Chemistry Guidelines (TR-103515-R1) and PWR Secondary Water Chemistry Guidelines (TR-10213...

1997-10-31T23:59:59.000Z

319

Revised OMB Circular A-76 (Revised November 14, 2002)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

OMB Circular A-76 Revision Comments OMB Circular A-76 Revision Comments DRAFT OMB CIRCULAR A-76 (NOVEMBER 14, 2002) REVIEW COMMENTS AND RECOMMENDATIONS GENERAL COMMENTS: The Department of Energy (DOE) supports the overarching goal of OMB Circular A-76 that agencies should obtain "the best deal to the Taxpayer." We also support revisions to the Circular that "Keep the Process Moving" with the end result being: Faster/Cheaper Competitions; Improved Performance and Measures; Enhanced/Expanded Competition; Fairness; Realizing Significant Savings; and the Redirection of Resources to Mission Critical Requirements. Upon review of the draft Circular, the Department believes the proposed changes to Circular reflect a general improvement over the current version. The Department does, however, have

320

Original","Revised","Data  

U.S. Energy Information Administration (EIA) Indexed Site

1 Distillate","Residential","Oklahoma","OK",7,7 "Sales","No. 1 Distillate","Residential","South Dakota","SD",3656,3656 "Sales","No. 1 Distillate","Residential","Tennessee","TN",157...

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While these samples are representative of the content of NLEBeta,
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321

NE-20 ACTION: SSDP Project Charter Revision CONCURRENCES RTG SYMBOL  

Office of Legacy Management (LM)

0 0 ACTION: SSDP Project Charter Revision CONCURRENCES RTG SYMBOL James W. Vaughan, Jr. N-923 Acting Assistant Secretary . for Nuclear Energy Murphi Attached for your signature is a revised Project Charter for the 1/ 86 Shippingport Station Decommissioning Project (SSDP). Since our original M determination in July that there was a need to revise the SSDP Charter, we N K23 have been in discussion with the Richland Operations Field Office (RL). INe Significant differences in management philosophy surfaced between RL and DeLaney Headquarters that required discussions up to and including the RL Manager DAE/86 and myself. I now feel that the revised Charter reflects a mutually acceptable working arrangement between the appropriate organizations. The RTGSYMBOL general roles and responsibilities defined in this Charter will facilitate

322

REVISED INDEPENDENT VERIFICATION SURVEY OF A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH BROOKHAVEN NATIONAL LABORATORY  

SciTech Connect

REVISED INDEPENDENT VERIFICATION SURVEY OF THE A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH, BROOKHAVEN NATIONAL LABORATORY 5062-SR-01-1

P.C. Weaver

2010-02-10T23:59:59.000Z

323

Biosafety Manual Draft Revision  

NLE Websites -- All DOE Office Websites (Extended Search)

copies are not official versions of this manual. Before using the printed copy, verify that it is the most current version. copies are not official versions of this manual. Before using the printed copy, verify that it is the most current version. Biosafety Manual Lawrence Berkeley National Laboratory May 18, 2010 This work was supported by the U.S. Department of Energy under Contract No. DE-AC02- 05CH11231. Biosafety Manual IBC-approved version (May 18, 2010) Printed copies are not official versions of this manual. Before using the printed copy, verify that it is the most current version. 2 Biosafety Manual Contents 1.0 Introduction 1.1 Policy 1.2 Purpose 1.3 Scope 1.4 Manual Administration and Presentation 1.5 Terms, Acronyms, and Abbreviations 1.6 Roles, Responsibilities, and Whom to Call 2.0 Starting and Conducting Work Safely 3.0 Work and Risk Assessment

324

Long-Term Surveillance Plan for the Upper Burbank Disposal Cell, Uravan, Colorado, DOE/AL/62350-250, Revision 1, July 1999  

NLE Websites -- All DOE Office Websites (Extended Search)

LONG-TERM SURVEILLANCE PLAN LONG-TERM SURVEILLANCE PLAN FOR THE UPPER BURBANK DISPOSAL CELL URAUAN, COLORADO July 1999 Prepared for U.S. Department of Energy Environmental Restoration Dhrision U MTRA Project Team Albuquerque, New Mexico DOElAU62350-250 REV. 1 Prepared by Jacobs Engineering Group Inc. Albuquerque, New Mexico This page intentionally left blank LONG-TERM GURMIWNCE P U N FOR THE UPPER BURBANK DrsPosAL CEU. WYAAI. COhORAOD TABLE OF DONENTe TABLE OF CONTENTS 1.0 PURPOSEANDSCOPE .............................................................................................. 1-1 2 . 1 1 FINAL SlTE CONDITIONS ................... ...-.... ...............................................*.............. 2-1 ..................................................................... ................... 2

325

Last Revision Date: 8/16/2010 Last Merged Filing ID:  

NLE Websites -- All DOE Office Websites (Extended Search)

Revision Date: 8/16/2010 Last Merged Filing ID: Revision Date: 8/16/2010 Last Merged Filing ID: Tariffs, Rate Schedules, and Other Tariff Documents Southwestern Power Administration Tariffs, Rate Schedules, and Other Tariff Documents Document Generated On: 10/1/2010 Contents TABLE OF CONTENTS ....................................................................................................................................1 PREAMBLE: AUTHORITIES AND OBLIGATIONS .............................................................................................1

326

Infrared Thermography Guide (Revision 3)  

Science Conference Proceedings (OSTI)

Costly equipment outages can be reduced by implementing a comprehensive predictive maintenance program. Infrared thermography (IR), a fundamental component of such programs, uses nonintrusive techniques to monitor the operating condition of equipment and components. This revised report provides updated information to assist utilities in implementing an effective IR program.

2002-05-30T23:59:59.000Z

327

EXPGUI Revision Log  

Science Conference Proceedings (OSTI)

... 03/24 fix bug in save options Add unix capability to print selected text (should work on OS X if lpr points to desired printer -- I think) orient.tcl 1.9 2005 ...

328

Google Doc projects 1.2: Exploring NCEP atmospheric reanalysis data GFD-1 Winter 2011 1 Feb 2011 to be revised frequently (stay tuned). We will load some ocean data and  

E-Print Network (OSTI)

Google Doc projects 1.2: Exploring NCEP atmospheric reanalysis data GFD-1 Winter 2011 1 Feb 2011/calculating tools available), and write your findings as a `journal' in your Google Doc. Don't try to do everything

329

EM Quality Assurance Program (EM-QA-001 Revision 0) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Program Management » Quality Assurance » EM Quality Services » Program Management » Quality Assurance » EM Quality Assurance Program (EM-QA-001 Revision 0) EM Quality Assurance Program (EM-QA-001 Revision 0) Previous revision of the Environmental Management Quality Assurance Program. The program is the EM management system to ensure we"do work correctly." This document has been superseded by Revision 1 of the program, but is still in use at some EM sites. EM Quality Assurance Program (EM-QA-001 Revision 0) More Documents & Publications Quality Assurance Program EM Quality Assurance Program (EM-QA-001 Revision 1) SOPP-43, EM-23 Quality Assurance Oversight Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration

330

Acquisition Career Management Program Handbook, Partial Revision...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Procurement and Assistance Management SUBJECT: Acquisition Career Management Program Handbook, Partial Revision of Chapter 11, Contracting Officer's Representative SUMMARY: The...

331

Oklahoma Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet)  

U.S. Energy Information Administration (EIA) Indexed Site

Decreases (Billion Cubic Feet) Decreases (Billion Cubic Feet) Oklahoma Dry Natural Gas Reserves Revision Decreases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 1,016 969 1,211 1980's 1,303 1,371 2,520 1,891 1,611 1,648 1,963 2,047 2,280 1,732 1990's 1,542 1,456 1,263 1,008 932 1,049 1,602 1,282 1,997 2,251 2000's 1,331 1,895 1,513 2,843 1,912 2,945 1,868 1,366 2,580 3,592 2010's 3,474 6,856 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Dry Natural Gas Reserves Revision Decreases Oklahoma Dry Natural Gas Proved Reserves Dry Natural Gas Proved Reserves Revision Decreases

332

2011-2012 Methods Additions and Revisions  

Science Conference Proceedings (OSTI)

Additions and revisions (new, updated, or revised methods) are included in print form. Corrections (minor typographical errors) are included in an accompanying CD-ROM. 2011-2012 Methods Additions and Revisions DVD & CD-ROMs Soft Bound Books Methods - An

333

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0 with ROTC 1, 2, and Errata  

SciTech Connect

This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 204 Storage Bunkers, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE); and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) north of Las Vegas, Nevada (Figure 1-1). The Corrective Action Sites (CASs) within CAU 204 are located in Areas 1, 2, 3, and 5 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Unit 204 is comprised of the six CASs identified in Table 1-1. As shown in Table 1-1, the FFACO describes four of these CASs as bunkers one as chemical exchange storage and one as a blockhouse. Subsequent investigations have identified four of these structures as instrumentation bunkers (CASs 01-34-01, 02-34-01, 03-34-01, 05-33-01), one as an explosives storage bunker (CAS 05-99-02), and one as both (CAS 05-18-02). The six bunkers included in CAU 204 were primarily used to monitor atmospheric testing or store munitions. The ''Corrective Action Investigation Plan (CAIP) for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada'' (NNSA/NV, 2002a) provides information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for each CAS within CAU 204. The evaluation of corrective action alternatives is based on process knowledge and the results of investigative activities conducted in accordance with the CAIP (NNSA/NV, 2002a) that was approved prior to the start of the Corrective Action Investigation (CAI). Record of Technical Change (ROTC) No. 1 to the CAIP (approval pending) documents changes to the preliminary action levels (PALs) agreed to by the Nevada Division of Environmental Protection (NDEP) and DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This ROTC specifically discusses the radiological PALs and their application to the findings of the CAU 204 corrective action investigation.

Wickline, Alfred

2004-04-01T23:59:59.000Z

334

Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1  

SciTech Connect

This Special Analysis (SA) was prepared to assess the potential impact of inadvertent disposal of a limited quantity of transuranic (TRU) waste in classified Trench 4 (T04C) within the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS). The Area 5 RWMS is a low-level radioactive waste disposal site in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS is regulated by the U.S. Department of Energy (DOE) under DOE Order 435.1 and DOE Manual (DOE M) 435.1-1. The primary objective of the SA is to evaluate if inadvertent disposal of limited quantities of TRU waste in a shallow land burial trench at the Area 5 RWMS is in compliance with the existing, approved Disposal Authorization Statement (DAS) issued under DOE M 435.1-1. In addition, supplemental analyses are performed to determine if there is reasonable assurance that the requirements of Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes, can be met. The 40 CFR 191 analyses provide supplemental information regarding the risk to human health and the environment of leaving the TRU waste in T04C. In 1989, waste management personnel reviewing classified materials records discovered that classified materials buried in trench T04C at the Area 5 RWMS contained TRU waste. Subsequent investigations determined that a total of 102 55-gallon drums of TRU waste from Rocky Flats were buried in trench T04C in 1986. The disposal was inadvertent because unclassified records accompanying the shipment indicated that the waste was low-level. The exact location of the TRU waste in T04C was not recorded and is currently unknown. Under DOE M 435.1-1, Chapter IV, Section P.5, low-level waste disposal facilities must obtain a DAS. The DAS specifies conditions that must be met to operate within the radioactive waste management basis, consisting of a performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated by the results of the Area 5 RWMS CA. Supplemental analyses in the SA indicate there is a

Greg Shott, Vefa Yucel, Lloyd Desotell

2008-05-01T23:59:59.000Z

335

Ohio Natural Gas Reserves Summary as of Dec. 31  

Annual Energy Outlook 2012 (EIA)

975 1,027 985 896 832 758 1977-2011 Natural Gas, Wet After Lease Separation 975 1,027 985 896 832 758 1979-2011 Natural Gas Nonassociated, Wet After Lease Separation 801 926 886...

336

RPP-RPT-42583 Revision  

Office of Scientific and Technical Information (OSTI)

RPP-RPT-42583 RPP-RPT-42583 Revision 0 Synthetic Sling Failure - Evaluations and Recommendations Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Contractor for the U.S. Department of Energy Office of River Protection under Contract DE-AC27-08RV14800 Approved for Public Release; Further Dissemination Unlimited RPP-RPT-42583 Revision 0 Synthetic Sling Failure - Evaluations and Recommendations C. S. Henderson T. C. Mackey Washington River Protection Solutions Date Published October 2009 Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Contractor for the U.S. Department of Energy Office of River Protection under Contract DE-AC27-08RV14800 ~. washington river ~ protectionso/utions P.O. Box 850 Richland, Washington Approved for Public Release; Further Dissemination Unlimited TRADEMARK

337

Clean Air Act. Revision 5  

SciTech Connect

This Reference Book contains a current copy of the Clean Air Act, as amended, and those regulations that implement the statute and appear to be most relevant to DOE activities. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. This Reference Book has been completely revised and is current through February 15, 1994.

Not Available

1994-02-15T23:59:59.000Z

338

Revised Version DESY 96203 Hiroshima Univ. HUPD9615  

E-Print Network (OSTI)

Revised Version DESY 96­203 Hiroshima Univ. HUPD­9615 September 1996 ################ hep , and T. Morozumi x Department of Physics, Hiroshima University 1­3­1 Kagamiyama, Higashi Hiroshima ­ 7393FT­LIPI, Indonesia. E­mail address: handoko@theo.phys.sci.hiroshima­u.ac.jp x E­mail address

339

Memorandum: Revised Guidance for the Office of Environmental Management  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revised Guidance for the Office of Environmental Revised Guidance for the Office of Environmental Management Site Specific Advisory Boards Memorandum: Revised Guidance for the Office of Environmental Management Site Specific Advisory Boards From: Assistant Secretary, Jessie H. Roberson (EM-1) To: SSAB Members (J. Bierer, T. Martin, M. Wilson, P. Claire, J. Brannon, D. Mosby, B. Tanner, V. Holm, W. Waters) The purpose of this memorandum is to provide guidance and direction for restructuring and managing the Environmental Management (EM) Site Specific Advisory Boards procurement mechanisms that support activities of the Boards. Roberson Memorandum - July 7, 2003 More Documents & Publications Letter: Implementation of the Guidance for the Environmental Management Site Specific Advisory Boards Letter from EM-1, Assistant Secretary, Jessie H. Roberson regarding

340

RyneRevised.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

Robert Robert D . R yne LBNL NERSC BES Requirements for 2017 October 8-9, 2013 Gaithersburg, MD Present and Future Computing Requirements for "Frontiers in Accelerator Design: Advanced Modeling for Next-Generation BES Accelerators" (repo m669) 1. P roject D escrip6on PI: R obert R yne ( LBNL) Senior p ersonnel: J i Q iang ( LBNL), C ho N g ( SLAC), B ruce C arlsten ( LANL) * repo m 669 s upports B ES a ccelerator d esign * concept e xplora6on; a ccelerator s ystem & a ccelerator component d esign; c ode d evelopment * This p resenta6on f ocuses o n b eam d ynamics m odeling f or future l ight s ources, e specially X ---ray F ree E lectron L asers (XFELs) The LCLS XFEL is a spectacular success γε x,y = 0.4 µm (slice) I pk = 3.0 kA σ E /E = 0.01% (slice) What is so challenging about future XFEL modeling?

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

REVISED FINAL REPORT INDEPENDENT VERIFICATION SURVEY ACTIVITIES AT THE SEPARATIONS PROCESS RESEARCH UNIT SITES, NISKAYUNA, NEW YORK DCN 0496-SR-06-1  

SciTech Connect

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpenau

2011-10-10T23:59:59.000Z

342

Test plan for the M-100 container, (model M-101/7A/12/90) docket 96-43-7A, type A container. Revision 1  

Science Conference Proceedings (OSTI)

This report concerns the packaging configurations being tested by the U.S. DOE and its contractors, and according to U.S. DOT specification 7A Type A (DOT-7A) requirements. The objective of this Test Plan is to describe the testing for the qualification of the M-100 Container, Model M-101/7A/12/90 as a DOT-7A Type A packaging. This packaging system is designed to ship Type A solid radioactive materials, normal form, Form Number 1, Form Number 2, and Form Number 3.

Kelly, D.L.

1997-07-22T23:59:59.000Z

343

Waste Generation Forecast for DOE-ORO`s Environmental Restoration OR-1 Project: FY 1994--FY 2001. Environmental Restoration Program, September 1993 Revision  

Science Conference Proceedings (OSTI)

This Waste Generation Forecast for DOE-ORO`s Environmental Restoration OR-1 Project. FY 1994--FY 2001 is the third in a series of documents that report current estimates of the waste volumes expected to be generated as a result of Environmental Restoration activities at Department of Energy, Oak Ridge Operations Office (DOE-ORO), sites. Considered in the scope of this document are volumes of waste expected to be generated as a result of remedial action and decontamination and decommissioning activities taking place at these sites. Sites contributing to the total estimates make up the DOE-ORO Environmental Restoration OR-1 Project: the Oak Ridge K-25 Site, the Oak Ridge National Laboratory, the Y-12 Plant, the Paducah Gaseous Diffusion Plant, the Portsmouth Gaseous Diffusion Plant, and the off-site contaminated areas adjacent to the Oak Ridge facilities (collectively referred to as the Oak Ridge Reservation Off-Site area). Estimates are available for the entire fife of all waste generating activities. This document summarizes waste estimates forecasted for the 8-year period of FY 1994-FY 2001. Updates with varying degrees of change are expected throughout the refinement of restoration strategies currently in progress at each of the sites. Waste forecast data are relatively fluid, and this document represents remediation plans only as reported through September 1993.

Not Available

1993-12-01T23:59:59.000Z

344

Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2  

SciTech Connect

The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for Nuclear Power Plant Consequence Analysis{close_quotes}, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled {open_quotes}Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low LET Radiation, Part 2: Scientific Bases for Health Effects Models,{close_quotes} was published in 1991 as NUREG/CR-4214, Rev. 1, Part 2, Addendum 1. This second addendum addresses the possibility that some fraction of the accident source term from an operating nuclear power plant comprises alpha-emitting radionuclides. Consideration of chronic high-LET exposure from alpha radiation as well as acute and chronic exposure to low-LET beta and gamma radiations is a reasonable extension of the health effects model.

Abrahamson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Inhalation Toxicology Research Inst.; Gilbert, E.S. [Pacific Northwest Lab., Richland, WA (United States)

1993-05-01T23:59:59.000Z

345

Corrective Action Investigation Plan for Corrective Action Unit 428: Area 3 Septic Waste Systems 1 and 5, Tonopah Test Range, Nevada, REVISION 0, march 1999  

Science Conference Proceedings (OSTI)

The Corrective Action Investigation Plan for Corrective Action Unit 428, Area 3 Septic Waste Systems 1 and 5, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U. S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U. S. Department of Defense. Corrective Action Unit 428 consists of Corrective Action Sites 03- 05- 002- SW01 and 03- 05- 002- SW05, respectively known as Area 3 Septic Waste System 1 and Septic Waste System 5. This Corrective Action Investigation Plan is used in combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada , Rev. 1 (DOE/ NV, 1998c). The Leachfield Work Plan was developed to streamline investigations at leachfield Corrective Action Units by incorporating management, technical, quality assurance, health and safety, public involvement, field sampling, and waste management information common to a set of Corrective Action Units with similar site histories and characteristics into a single document that can be referenced. This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 428. A system of leachfields and associated collection systems was used for wastewater disposal at Area 3 of the Tonopah Test Range until a consolidated sewer system was installed in 1990 to replace the discrete septic waste systems. Operations within various buildings at Area 3 generated sanitary and industrial wastewaters potentially contaminated with contaminants of potential concern and disposed of in septic tanks and leachfields. Corrective Action Unit 428 is composed of two leachfield systems in the northern portion of Area 3. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern for the site include oil/ diesel range total petroleum hydrocarbons, and Resource Conservation and Recovery Act characteristic volatile organic compounds, semivolatile organic compounds, and metals. A limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from four of the septic tanks and if radiological field screening levels are exceeded. Additional samples will be analyzed for geotechnical and hydrological properties and a bioassessment may be performed. The technical approach for investigating this Corrective Action Unit consists of the following activities: (1) Perform video surveys of the discharge and outfall lines. (2) Collect samples of material in the septic tanks. (3) Conduct exploratory trenching to locate and inspect subsurface components. (4) Collect subsurface soil samples in areas of the collection system including the septic tanks and outfall end of distribution boxes. (5) Collect subsurface soil samples underlying the leachfield distribution pipes via trenching. (6) Collect surface and near- surface samples near potential locations of the Acid Sewer Outfall if Septic Waste System 5 Leachfield cannot be located. (7) Field screen samples for volatile organic compounds, total petroleum hydrocarbons, and radiological activity. (8) Drill boreholes and collect subsurface soil samples if required. (9) Analyze samples for total volatile organic compounds, total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, and total petroleum hydrocarbons (oil/ diesel range organics). Limited number of samples will be analyzed for gamma- emitting radionuclides and isotopic uranium from particular septic tanks and if radiological field screening levels are exceeded. (10) Collect samples from native soils beneath the distribution system and analyze for geotechnical/ hydrologic parameters. (11) Collect and analyze bioassessment samples at the discretion of the Site Supervisor if total petroleum hydrocarbons exceed field- screening levels.

DOE /NV

1999-03-26T23:59:59.000Z

346

Corrective Action Decision Document/Closure Report for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada (Revision 0) with ROTC 1 and 2  

SciTech Connect

The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 137 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from February 28 through August 17, 2006, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. ROTC-1: Downgrade FFACO UR at CAU 137, CAS 07-23-02, Radioactive Waste Disposal Site to an Administrative UR. ROTC-2: Downgrade FFACO UR at CAU 137, CAS 01-08-01, Waste Disposal Site to an Administrative UR.

Krauss, Mark J

2007-03-01T23:59:59.000Z

347

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

This CADD/CAP follows the Corrective Action Investigation (CAI) stage, which results in development of a set of contaminant boundary forecasts produced from groundwater flow and contaminant transport modeling of the Frenchman Flat CAU. The Frenchman Flat CAU is located in the southeastern portion of the NNSS and comprises 10 underground nuclear tests. The tests were conducted between 1965 and 1971 and resulted in the release of radionuclides in the subsurface in the vicinity of the test cavities. Two important aspects of the corrective action process are presented within this CADD/CAP. The CADD portion describes the results of the Frenchman Flat CAU data-collection and modeling activities completed during the CAI stage. The corrective action objectives and the actions recommended to meet the objectives are also described. The CAP portion describes the corrective action implementation plan. The CAP begins with the presentation of CAU regulatory boundary objectives and initial use restriction boundaries that are identified and negotiated by NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The CAP also presents the model evaluation process designed to build confidence that the flow and contaminant transport modeling results can be used for the regulatory decisions required for CAU closure. The first two stages of the strategy have been completed for the Frenchman Flat CAU. A value of information analysis and a CAIP were developed during the CAIP stage. During the CAI stage, a CAIP addendum was developed, and the activities proposed in the CAIP and addendum were completed. These activities included hydrogeologic investigation of the underground testing areas, aquifer testing, isotopic and geochemistry-based investigations, and integrated geophysical investigations. After these investigations, a groundwater flow and contaminant transport model was developed to forecast contaminant boundaries that enclose areas potentially exceeding the Safe Drinking Water Act radiological standards at any time within 1,000 years. An external peer review of the groundwater flow and contaminant transport model was completed, and the model was accepted by NDEP to allow advancement to the CADD/CAP stage. The CADD/CAP stage focuses on model evaluation to ensure that existing models provide adequate guidance for the regulatory decisions regarding monitoring and institutional controls. Data-collection activities are identified and implemented to address key uncertainties in the flow and contaminant transport models. During the CR stage, final use restriction boundaries and CAU regulatory boundaries are negotiated and established; a long-term closure monitoring program is developed and implemented; and the approaches and policies for institutional controls are initiated. The model evaluation process described in this plan consists of an iterative series of five steps designed to build confidence in the site conceptual model and model forecasts. These steps are designed to identify data-collection activities (Step 1), document the data-collection activities in the 0CADD/CAP (Step 2), and perform the activities (Step 3). The new data are then assessed; the model is refined, if necessary; the modeling results are evaluated; and a model evaluation report is prepared (Step 4). The assessments are made by the modeling team and presented to the pre-emptive review committee. The decision is made by the modeling team with the assistance of the pre-emptive review committee and concurrence of NNSA/NSO to continue data and model assessment/refinement, recommend additional data collection, or recommend advancing to the CR stage. A recommendation to advance to the CR stage is based on whether the model is considered to be sufficiently reliable for designing a monitoring system and developing effective institutional controls. The decision to advance to the CR stage or to return to step 1 of the process is then made by NDEP (Step 5).

Irene Farnham and Sam Marutzky

2011-07-01T23:59:59.000Z

348

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 465: Hydronuclear Nevada National Security Site, Nevada, with ROTC 1, Revision 0  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 465, Hydronuclear, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 465 comprises the following four corrective action sites (CASs) located in Areas 6 and 27 of the Nevada National Security Site: (1) 00-23-01, Hydronuclear Experiment; (2) 00-23-02, Hydronuclear Experiment; (3) 00-23-03, Hydronuclear Experiment; (4) 06-99-01, Hydronuclear. The sites will be investigated based on the data quality objectives (DQOs) developed on July 6, 2011, by representatives of the Nevada Division of Environmental Protection (NDEP) and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 465. For CAU 465, two potential release components have been identified. The subsurface release component includes potential releases of radiological and nonradiological contaminants from the subsurface hydronuclear experiments and disposal boreholes. The surface release component consists of other potential releases of radiological and nonradiological contaminants to surface soils that may have occurred during the pre- and post-test activities. This plan provides the methodology for collection of the necessary information for closing each CAS component. There is sufficient information and process knowledge from historical documentation, contaminant characteristics, existing regional and site groundwater models, and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 465 using the SAFER process. For potential subsurface releases, flow and transport models will be developed to integrate existing data into a conservative description of contaminant migration in the unsaturated zone from the hydronuclear experiments and disposal boreholes. For the potential surface releases, additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS component. It is anticipated that results of the flow and transport models, the field investigation, and implementation of the corrective action of closure in place will support a defensible recommendation that no further corrective action is necessary. This will be presented in a closure report that will be prepared and submitted to NDEP for review and approval. The following text summarizes the SAFER activities that will support the closure of CAU 465: (1) Perform site preparation activities (e.g., utilities clearances, and radiological and visual surveys). (2) Move or remove and dispose of debris at various CASs, as required. (3) Collect environmental samples from designated target populations (e.g., stained soil) to confirm or disprove the presence of contaminants of concern as necessary to supplement existing information. (4) Evaluate and analyze existing data to develop conservative flow and transport models to simulate the potential for contaminant migration from the hydronuclear experiments and disposal boreholes to the water table within 1,000 years. (5) Confirm the preferred closure option (closure in place with use restrictions) is sufficient to protect human health and the environment.

Patrick Matthews

2011-11-01T23:59:59.000Z

349

Report for Batch Leach Analyses on Sediments at 100-HR-3 Operable Unit, Boreholes C7620, C7621, C7622, C7623, C7626, C7627, C7628, C7629, C7630, and C7866. Revision 1.  

Science Conference Proceedings (OSTI)

This is a revision to a previously released report. This revision contains additional analytical results for the sample with HEIS number B2H4X7. Between November 4, 2010 and October 26, 2011 sediment samples were received from 100-HR-3 Operable Unit for geochemical studies. The analyses for this project were performed at the 331 building located in the 300 Area of the Hanford Site. The analyses were performed according to Pacific Northwest National Laboratory (PNNL) approved procedures and/or nationally recognized test procedures. The data sets include the sample identification numbers, analytical results, estimated quantification limits (EQL), and quality control data. The preparatory and analytical quality control requirements, calibration requirements, acceptance criteria, and failure actions are defined in the on-line QA plan 'Conducting Analytical Work in Support of Regulatory Programs' (CAW). This QA plan implements the Hanford Analytical Services Quality Assurance Requirements Documents (HASQARD) for PNNL. Samples were received with a chain of custody (COC) and were analyzed according to the sample identification numbers supplied by the client. All Samples were refrigerated upon receipt until prepared for analysis. All samples were received with custody seals intact unless noted in the Case Narrative. Holding time is defined as the time from sample preparation to the time of analyses. The prescribed holding times were met for all analytes unless noted in the Case Narrative. All reported analytical results meet the requirements of the CAW or client specified SOW unless noted in the case narrative. Due to the requirements of the statement of work and sampling events in the field, the 28 day and the 48 hr requirements cannot be met. The statement of work requires samples to be selected at the completion of the borehole. It is not always possible to complete a borehole and have the samples shipped to the laboratory within the hold time requirements. Duplicate RPD for Uranium 238 (38.9%) was above the acceptance limit (35) in 1E05003-DUP1 for ICPMS-Tc-U-WE The sample result is less than 10 times the detection limits. Duplicate recoveries are not applicable to this analyte. Duplicate RPD for Silver 107 (68.2%) was above the acceptance limit (35) in 2C06004-DUP1 for ICPMS-RCRA-AE The sample result is less than 10 times the detection limits. Duplicate recoveries are not applicable to this analyte. Matrix Spike Recovery for Chromium, Hexavalent (48.8%) was outside acceptance limits (75-125) in 1E23001-MS1 for Hexavalent Chromium/Soil. Potential Matrix interference. Sample results associated with this batch are below the EQL. There should be no impact to the data as reported. Matrix Spike Recovery for Chromium, Hexavalent (50.2%) was outside acceptance limits (75-125) in 2B22010-MS1 for Hexavalent Chromium/Soil. Potential Matrix interference. Sample results associated with this batch are below the EQL. There should be no impact to the data as reported.

Lindberg, Michael J.

2012-04-25T23:59:59.000Z

350

Pahute Mesa Well Development and Testing Analyses for Wells ER-20-7, ER-20-8 #2, and ER-EC-11, Revision 1  

Science Conference Proceedings (OSTI)

This report analyzes the following data collected from ER-20-7, ER-20-8 No.2, and ER-EC-11 during WDT operations: (1) Chemical indicators of well development (Section 2.0); (2) Static hydraulic head (Section 3.0); (3) Radiochemistry and geochemistry (Section 4.0); (4) Drawdown observed at locations distal to the pumping well (Section 5.0); and (5) Drilling water production, flow logs, and temperature logs (Section 6.0). The new data are further considered with respect to existing data as to how they enhance or change interpretations of groundwater flow and transport, and an interim small-scale conceptual model is also developed and compared to Phase I concepts. The purpose of well development is to remove drilling fluids and drilling-associated fines from the formation adjacent to a well so samples reflecting ambient groundwater water quality can be collected, and to restore hydraulic properties near the well bore. Drilling fluids can contaminate environmental samples from the well, resulting in nonrepresentative measurements. Both drilling fluids and preexisting fines in the formation adjacent to the well can impede the flow of water from the formation to the well, creating artifacts in hydraulic response data measured in the well.

Greg Ruskauff

2011-12-01T23:59:59.000Z

351

?Framework for a Risk-Informed Groundwater Compliance Strategy for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nye County, Nevada, Revision 1  

SciTech Connect

Note: This document was prepared before the NTS was renamed the Nevada National Security Site (August 23, 2010); thus, all references to the site herein remain NTS. Corrective Action Unit (CAU) 98, Frenchman Flat, at the Nevada Test Site (NTS) was the location of ten underground nuclear tests between 1965 and 1971. As a result, radionuclides were released in the subsurface in the vicinity of the test cavities. Corrective Action Unit 98 and other CAUs at the NTS and offsite locations are being investigated. The Frenchman Flat CAU is one of five Underground Test Area (UGTA) CAUs at the NTS that are being evaluated as potential sources of local or regional impact to groundwater resources. For UGTA sites, including Frenchman Flat, contamination in and around the test cavities will not be remediated because it is technologically infeasible due to the depth of the test cavities (150 to 2,000 feet [ft] below ground surface) and the volume of contaminated groundwater at widely dispersed locations on the NTS. Instead, the compliance strategy for these sites is to model contaminant flow and transport, estimate the maximum spatial extent and volume of contaminated groundwater (over a period of 1,000 years), maintain institutional controls, and restrict access to potentially contaminated groundwater at areas where contaminants could migrate beyond the NTS boundaries.

Sam Marutzky

2010-09-01T23:59:59.000Z

352

Phase I Flow and Transport Model Document for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada National Security Site, Nye County, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

The Underground Test Area (UGTA) Corrective Action Unit (CAU) 97, Yucca Flat/Climax Mine, in the northeast part of the Nevada National Security Site (NNSS) requires environmental corrective action activities to assess contamination resulting from underground nuclear testing. These activities are necessary to comply with the UGTA corrective action strategy (referred to as the UGTA strategy). The corrective action investigation phase of the UGTA strategy requires the development of groundwater flow and contaminant transport models whose purpose is to identify the lateral and vertical extent of contaminant migration over the next 1,000 years. In particular, the goal is to calculate the contaminant boundary, which is defined as a probabilistic model-forecast perimeter and a lower hydrostratigraphic unit (HSU) boundary that delineate the possible extent of radionuclide-contaminated groundwater from underground nuclear testing. Because of structural uncertainty in the contaminant boundary, a range of potential contaminant boundaries was forecast, resulting in an ensemble of contaminant boundaries. The contaminant boundary extent is determined by the volume of groundwater that has at least a 5 percent chance of exceeding the radiological standards of the Safe Drinking Water Act (SDWA) (CFR, 2012).

Andrews, Robert

2013-09-01T23:59:59.000Z

353

Corrective Action Investigation Plan for Corrective Action Unit 266: Area 25 Building 3124 Leachfield, Nevada Test Site, Nevada, Revision 1, February 1999  

SciTech Connect

The Corrective Action Investigation Plan for Corrective Action Unit 266, Area 25 Building 3124 Leachfield, has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the U.S. Department of Energy, Nevada Operations Office; the State of Nevada Division of Environmental Protection; and the U.S. Department of Defense. Corrective Action Unit 266 consists of the Corrective Action Site 25-05-09 sanitary leachfield and associated collection system. This Corrective Action Investigation Plan is used in combination with the Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada (DOE/NV, 1998d). This Corrective Action Investigation Plan provides investigative details specific to Corrective Action Unit 266. Corrective Action Unit 266 is located southwest of Building 3124 which is located southwest and adjacent to Test Cell A. Test Cell A was operational during the 1960s to test nuclear rocket reactors in support of the Nuclear Rocket Development Station. Operations within Building 3124 from 1962 through the early 1990s resulted in effluent releases to the leachfield and associated collection system. The subsurface soils in the vicinity of the collection system and leachfield may have been impacted by effluent containing contaminants of potential concern generated by support activities associated with Test Cell A reactor testing operations, various laboratories including a high-level radioactivity environmental sample handling laboratory, and possibly the Treatability Test Facility. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern for the site include radionuclides, oil/diesel range total petroleum hydrocarbons, and Resource Conservation and Recovery Act characteristic volatile organic compounds, semivolatile organic compounds, and metals. Samples will also be analyzed for radionuclides and polychlorinated biphenyls not considered during the DQO process. Additional samples will be analyzed for geotechnical and hydrological properties and a bioassessment may be performed. The technical approach for investigating this Corrective Action Unit consists of the following activities: (1) Perform a radiological walkover survey. (2) Perform video and radiation surveys of the discharge and outfall lines. (3) Collect samples from within the septic tank. (4) Mark approximate locations of leachfield distribution lines on the ground surface. (5) Collect subsurface soil samples in areas of the collection system including the septic tank and outfall end of the diversion chamber. (6) Collect subsurface soil samples underlying the leachfield distribution pipes. (7) Field screen samples for volatile organic compounds and radiological activity. (8) Drill boreholes and collect subsurface soil samples if required. (9) Analyze soil samples for total volatile organic compounds, total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, total petroleum hydrocarbons (oil/diesel-range organics), and polychlorinated biphenyls. (1) Analyze a minimum of 25 percent of the soil samples for gamma-emitting radionuclides, isotopic uranium, isotopic plutonium, isotopic americium, and strontium-90 if radiological field screening levels are exceeded. (2) Collect samples from native soils beneath the distribution system and analyze for geotechnical/hydrologic parameters. (3) Collect and analyze bioassessment samples at Site Supervisors discretion if volatile organic compounds exceed field-screening levels. Additional sampling and analytical details are presented.

U.S. Department Of Energy, Nevada Operations Office

1999-02-24T23:59:59.000Z

354

Bench-scale testing of on-line control of column flotation using a novel analyzer. Revised final report, [October 1992--October 1993]: Volume 1  

Science Conference Proceedings (OSTI)

The main advantage of the project is that it allowed PTI to gain knowledge and experience about the proper approach, methods and hardware required to properly optimize and control column flotation performance. Many operational problems were incurred during the project, some of that PTI was able to solve during the project and other that must be overcome as the technology is further developed and commercialized. The key operating problems experienced with the KEN-FLOTE{sup TM} Column that must be further researched and overcome include: (1)The low concentrate solids content which limited the throughput capacity of the column, due to high froth washing requirements. The low concentrate solids content also lead to difficulty obtaining accurate On-Line Monitor measurements, due to the poor measurement sensitivity obtained with low solids content samples (particularly less than 5.0 wt %). (2) The higher-than-anticipated reagent dosages that undoubtedly contributed to the low solids content listed above, and also caused foaming problems within PTI`s On-Line Monitor. A defoaming reagent addition (Nalco 7810) was required to provide consistent sample size and reproducible On-Line Monitor counts for the concentrate samples collected within the circuit. PTI and UK`s CAER staff will continue to research alternative column design, particularly alternative air bubble generation and air distribution systems, to try to maximize column concentrate solids content while reducing reagent dosage requirements. In addition to the KEN-FLOTE{sup TM} Column operation there were also a number of hardware problems with PTI`s On-Line Quality Monitor that must be remedied for future commercial installations.

Not Available

1993-10-27T23:59:59.000Z

355

Corrective Action Investigation Plan for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada with ROTC 1 (Revision 0, September 2000)  

Science Conference Proceedings (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate Corrective Action Alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 97 under the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 97, collectively known as the Yucca Flat/Climax Mine CAU, consists of 720 Corrective Action Sites (CASs). The Yucca Flat/Climax Mine CAU extends over several areas of the NTS and constitutes one of several areas used for underground nuclear testing in the past. The nuclear tests resulted in groundwater contamination in the vicinity as well as downgradient of the underground test areas. Based on site history, the Yucca Flat underground nuclear tests were conducted in alluvial, volcanic, and carbonate rocks; whereas, the Climax Mine tests were conducted in an igneous intrusion located in northern Yucca Flat. Particle-tracking simulations performed during the regional evaluation indicate that the local Climax Mine groundwater flow system merges into the much larger Yucca Flat groundwater flow systems during the 1,000-year time period of interest. Addressing these two areas jointly and simultaneously investigating them as a combined CAU has been determined the best way to proceed with corrective action investigation (CAI) activities. The purpose and scope of the CAI includes characterization activities and model development conducted in five major sequential steps designed to be consistent with FFACO Underground Test Area Project's strategy to predict the location of the contaminant boundary, develop and implement a corrective action, and close each CAU. The results of this field investigation will support a defensible evaluation of CAAs in the subsequent corrective action decision document.

Robert Andrews; Sam Marutzky

2000-09-27T23:59:59.000Z

356

C-1 coproduct development for N Reactor: Excerpts from N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966  

SciTech Connect

This report discusses the production of weapon grade plutonium and tritium as an economically attractive mode of operation for N-Reactor. With the successful completion of the proposed research and development program coproduct production in N-Reactor could begin in January 1967. Approximately 5 kg of tritium could be produced at a reduction in unit total cost of up to $7 per gram equivalent when compared to other modes of operation of N-Reactor that yield only-weapon grade plutonium. Achieving this production level and unit cost requires a fuel and target design that will subject the materials to more severe temperature and exposure conditions than for the tube-in-tube design. Analyses of existing knowledge and experimental results obtained to date are very encouraging. However, there is a continuing need for additional experimental verification of the limiting conditions for both fuel and target to permit the specification of a production fuel and target design. The incremental cost of this program is estimated to be $1,055 million in FY-1965, $0.796 million in FY-1966 and $0.450 million in FY-1967 for a total of $2.3 million. The principal benefits to be derived from this expenditure of research and development funds are lower unit grade plutonium. When the reactor reaches equilibrium operation as a costs for both tritium and weapon dual-purpose reactor producing process steam for credit, it will be a highly competitive producer of plutonium and tritium in the AEC complex.

1965-04-19T23:59:59.000Z

357

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Chapter D, Appendix D1 (beginning), Revision 3  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP), which is designed for receipt, handling, storage, and permanent isolation of defense-generated transuranic wastes, is being excavated at a depth of approximately 655 m in bedded halites of the Permian Salado Formation of southeastern New Mexico. Site-characterization activities at the present WIPP site began in 1976. Full construction of the facility began in 1983, after completion of ``Site and Preliminary Design Validation`` (SPDV) activities and reporting. Site-characterization activities since 1983 have had the objectives of updating or refining the overall conceptual model of the geologic, hydrologic, and structural behavior of the WIPP site and providing data adequate for use in WIPP performance assessment. This report has four main objectives: 1. Summarize the results of WIPP site-characterization studies carried out since the spring of 1983 as a result of specific agreements between the US Department of Energy and the State of New Mexico. 2. Summarize the results and status of site-characterization and facility-characterization studies carried out since 1983, but not specifically included in mandated agreements. 3. Compile the results of WIPP site-characterization studies into an internally consistent conceptual model for the geologic, hydrologic, geochemical, and structural behavior of the WIPP site. This model includes some consideration of the effects of the WIPP facility and shafts on the local characteristics of the Salado and Rustler Formations. 4. Discuss the present limitations and/or uncertainties in the conceptual geologic model of the WIPP site and facility. The objectives of this report are limited in scope, and do not include determination of whether or not the WIPP Project will comply with repository-performance criteria developed by the US Environmental Protection Agency (40CFR191).

Not Available

1993-03-01T23:59:59.000Z

358

Implementation of the Resource Disincentive in 40 CFR part 191.14 (e) at the Waste Isolation Pilot Plant. Revision 1  

SciTech Connect

In 1986, the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) (DOE-WPO) prepared a strategy for complying with the Environmental Protection Agency`s (EPA`s) Standards for the management of transuranic (TRU) waste. Section 3.2.2.2 of the DOE`s report addressed compliance with the Assurance Requirements found in 40 CFR {section} 191.14. One of the Assurance Requirements addresses the selection of repository sites that contain recoverable natural resources. This report documents that the site selection process for the WIPP facility did indeed comply with the natural resource disincentive requirement in 40 CFR {section} 191,14(e) at the time selected and therefore complies with the standard at this time. Thus, it shall be shown that it is reasonably certain that the WIPP site provides better overall protection than practical alternatives that were available when the site was selected. It is important to point out here, and it will be discussed later in the report, that the resource disincentive requirement is a preliminary siting criterion that requires further evaluation of sites that have resources (i.e, hydrocarbons, minerals and groundwater) in the vicinity or on the site. This further evaluation requires that for sites that do have resources, a qualitative determination must be made that the site will provide better overall protection than practical alternatives. The purpose of this report is not to provide a quantitative evaluation for selection of the WIPP site. A further discussion on the difference between the qualitative analysis required under 40 CFR {section} 191.14(e) and the quantitative analysis under other sections of 40 CFR 191 is provided in {section}2.1 of this report.

Not Available

1993-06-01T23:59:59.000Z

359

Addendum to the Closure Report for Corrective Action Unit 322: Areas 1 & 3 Release Sites and Injection Wells Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the June 2006, Closure Report for Corrective Action Unit 322: Areas 1 & 3 Release Sites and Injection Wells as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: This cover page that refers the reader to the UR Modification document for additional information The cover and signature pages of the UR Modification document The NDEP approval letter The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: CAS 01-25-01, AST Release CAS 03-25-03, Mud Plant AST Diesel Release These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Lynn Kidman

2008-10-01T23:59:59.000Z

360

Corrective Action Investigation Plan for Corrective Action Unit 561: Waste Disposal Areas, Nevada Test Site, Nevada with ROTC 1, Revision 0  

SciTech Connect

Corrective Action Unit (CAU) 561 is located in Areas 1, 2, 3, 5, 12, 22, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 561 is comprised of the 10 corrective action sites (CASs) listed below: 01-19-01, Waste Dump 02-08-02, Waste Dump and Burn Area 03-19-02, Debris Pile 05-62-01, Radioactive Gravel Pile 12-23-09, Radioactive Waste Dump 22-19-06, Buried Waste Disposal Site 23-21-04, Waste Disposal Trenches 25-08-02, Waste Dump 25-23-21, Radioactive Waste Dump 25-25-19, Hydrocarbon Stains and Trench These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 561. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the Corrective Action Investigation for CAU 561 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological surveys. Perform exploratory excavations. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. Collect samples of source material to determine the potential for a release. Collect samples of potential remediation wastes. Collect quality control samples.

Grant Evenson

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Corrective Action Investigation Plan for Corrective Action Unit 410: Waste Disposal Trenches, Tonopah Test Range, Nevada, Revision 0 (includes ROTCs 1, 2, and 3)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 410 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 410 is located on the Tonopah Test Range (TTR), which is included in the Nevada Test and Training Range (formerly the Nellis Air Force Range) approximately 140 miles northwest of Las Vegas, Nevada. This CAU is comprised of five Corrective Action Sites (CASs): TA-19-002-TAB2, Debris Mound; TA-21-003-TANL, Disposal Trench; TA-21-002-TAAL, Disposal Trench; 09-21-001-TA09, Disposal Trenches; 03-19-001, Waste Disposal Site. This CAU is being investigated because contaminants may be present in concentrations that could potentially pose a threat to human health and/or the environment, and waste may have been disposed of with out appropriate controls. Four out of five of these CASs are the result of weapons testing and disposal activities at the TTR, and they are grouped together for site closure based on the similarity of the sites (waste disposal sites and trenches). The fifth CAS, CAS 03-19-001, is a hydrocarbon spill related to activities in the area. This site is grouped with this CAU because of the location (TTR). Based on historical documentation and process know-ledge, vertical and lateral migration routes are possible for all CASs. Migration of contaminants may have occurred through transport by infiltration of precipitation through surface soil which serves as a driving force for downward migration of contaminants. Land-use scenarios limit future use of these CASs to industrial activities. The suspected contaminants of potential concern which have been identified are volatile organic compounds; semivolatile organic compounds; high explosives; radiological constituents including depleted uranium, beryllium, total petroleum hydrocarbons; and total Resource Conservation and Recovery Act metals. Field activities will consist of geophysical and radiological surveys, and collecting soil samples at biased locations by appropriate methods. A two-step data quality objective strategy will be followed: (1) define the nature of contamination at each CAS location by identifying any contamination above preliminary action levels (PALs); and, (2) determine the extent of contamination identified above PALs. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NV

2002-07-16T23:59:59.000Z

362

Polychlorinated Biphenyls (PCBs) in Catfish and Carp Collected from the Rio Grande Upstream and Downstream of Los Alamos National Laboratory: Revision 1  

Science Conference Proceedings (OSTI)

Concern has existed for years that the Los Alamos National Laboratory (LANL), a complex of nuclear weapons research and support facilities, has released polychlorinated biphenyls (PCBs) to the environment that may have reached adjacent bodies of water through canyons that connect them. In 1997, LANL's Ecology Group began measuring PCBs in fish in the Rio Grande upstream and downstream of ephemeral streams that cross LANL and later began sampling fish in Abiquiu and Cochiti reservoirs, which are situated on the Rio Chama and Rio Grande upstream and downstream of LANL, respectively. In 2002, we electroshocked channel catfish (Ictalurus punctatus) and common carp (Carpiodes carpio) in the Rio Grande upstream and downstream of LANL and analyzed fillets for PCB congeners. We also sampled soils along the Rio Chama and Rio Grande drainages to discern whether a background atmospheric source of PCBs that could impact surface water adjacent to LANL might exist. Trace concentrations of PCBs measured in soil (mean = 4.7E-05 {micro}g/g-ww) appear to be from background global atmospheric sources, at least in part, because the bimodal distribution of low-chlorinated PCB congeners and mid-chlorinated PCB congeners in the soil samples is interpreted to be typical of volatilized PCB congeners that are found in the atmosphere and dust from global fallout. Upstream catfish (n = 5) contained statistically (P = 0.047) higher concentrations of total PCBs (mean = 2.80E-02 {micro}g/g-ww) than downstream catfish (n = 10) (mean = 1.50E-02 {micro}g/g-ww). Similarly, upstream carp (n = 4) contained higher concentrations of total PCBs (mean = 7.98E-02 {micro}g/g-ww) than downstream carp (n = 4) (3.07E-02 {micro}g/g-ww); however, the difference was not statistically significant (P = 0.42). The dominant PCB homologue in all fish samples was hexachlorobiphenyls. Total PCB concentrations in fish in 2002 are lower than 1997; however, differences in analytical methods and other uncertainties exist. A review of historical quantitative PCB data for fish from the Rio Grande and Abiquiu and Cochiti reservoirs does not indicate a distinct contribution of PCBs from LANL to fish in the Rio Grande or Cochiti. Analysis of homologue patterns for fish does not provide sufficient evidence of a LANL contribution. Nevertheless, concentrations of PCBs in fillets of fish sampled from the Rio Grande are indicative of potential adverse chronic health impact from consumption of these fish on a long-term basis.

Gilbert J. Gonzales Philip R. Fresquez

2008-05-12T23:59:59.000Z

363

Fig 9-revised Flowchart.xls  

Office of Legacy Management (LM)

9 9 Soil Nature and Extent AOI Identification Process d The PRG value for lead is not a calculated PRG, but rather is taken from the EPA guidance document Revised Interim Soil Lead Guidance for CERCLA Sites and RCRA Correction Action Facilities (1994). e For surface soil (0 to 0.5 ft), WRW surface soil (0 to 0.5 ft) PRGs are used. For subsurface soil (0.5 ft to a maximum depth of 209 ft), WRW subsurface soil (0.5 to 8 ft) PRGs are used. a Soil "superset" for soil samples collected from June 28, 1991 through August 22, 2005. c Soil PRGs are defined as 1 x 10 -6 WRW PRGs based on using an HI of 0.1 or a risk of 1 x 10 -6 (the more conservative of the two values was used for the PRG). b Background level is defined as the background M2SD. RI-Ready Soil Data

364

ISM Plan - Chemical Sciences Division - Revised May 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

ISM Plan - Chemical Sciences Division - Revised May 2012 ISM Plan - Chemical Sciences Division - Revised May 2012 Page 2 of 25 Page intentionally left blank ISM Plan - Chemical Sciences Division - Revised May 2012 Page 3 of 25 Chemical Sciences Division ISM Plan May 2012 Page 1.0 Policy Statement 5 2.0 Description of Division/Organization, Mission and Scope of Work 5 3.0 Accountability 7 3.01 Line Management Responsibility and Accountability 8 3.02 Specific Principal Investigator Responsibilities 8 3.03 Work Lead EH&S Responsibilities 8 3.04 CSD personnel EH&S Responsibilities (Non-Supervisor or Work Lead) 9 3.05 Students 10 3.06 Work Off-Site 10 3.07 Telecommuting 11

365

Oklahoma Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Increases (Billion Cubic Feet) Oklahoma Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 837 962 1,026 1980's 1,293 1,262 2,374 2,189 2,245 2,357 2,158 2,251 2,538 1,984 1990's 1,803 1,710 1,988 1,554 1,580 1,892 1,886 2,396 2,995 3,029 2000's 2,498 1,458 2,159 2,892 2,173 3,064 1,515 2,115 2,786 2,894 2010's 3,224 5,142 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Dry Natural Gas Reserves Revision Increases Oklahoma Dry Natural Gas Proved Reserves Dry Natural Gas Proved Reserves Revision Increases

366

Policy Flash 2013-38 Revised Merit Review Guide For Financial Assistance |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 Revised Merit Review Guide For Financial 8 Revised Merit Review Guide For Financial Assistance Policy Flash 2013-38 Revised Merit Review Guide For Financial Assistance Attached is Policy Flash 2013-38 Revised Merit Review Guide for Financial Assistance Questions concerning this policy flash should be directed to Richard Bonnell of the Contract and Financial Assistance Policy Division at (202) 287-1747 or at richard.bonnell@hq.doe.gov. Flash 2013-38 Revisions to the Merit Review Guide 2013.pdf Merit Review Guide FINAL JULY 2013 ATTACHMENT 1 Sample Merit Rev Panel Appt Letter 1-10.docx ATTACHMENT 2 Sample COI ADDED WB LANGUAGE JULY 2013.docx ATTACHMENT 3 - Sample Evaluation and Selection Plan JULY 2013.docx ATTACHMENT 4 Sample Noncompetitive Review Plan.docx ATTACHMENT 5 Sample Initial Compliance Review 1-16.docx

367

ALS Beamline Design Requirements - Revision 1  

E-Print Network (OSTI)

the beamline including: Electrical power requirements e.at the ALS include: Electrical power: 480VAC, 208VAC, 120terminations, and electrical power requirements. Beamline

Heimann, Phil

2010-01-01T23:59:59.000Z

368

Advanced lighting guidelines, 1993: Revision 1  

SciTech Connect

The 1993 Advanced Lighting Guidelines document consists of twelve guidelines that provide an overview of specific lighting technologies and design application techniques utilizing energy-efficient lighting practice. Lighting Design Practice assesses energy-efficient lighting strategies, discusses lighting issues, and explains how to obtain quality lighting design and consulting services. Luminaires and Lighting Systems surveys luminaire equipment designed to take advantage of advanced technology lamp products and includes performance tables that allow for accurate estimation of luminaire light output and power input. The additional ten guidelines -- Computer-Aided Lighting Design, Energy-Efficient Fluorescent Ballasts, Full-Size Fluorescent Lamps, Compact Fluorescent Lamps, Tungsten- Halogen Lamps, Metal Halide and HPS Lamps, Daylighting and Lumen Maintenance, Occupant Sensors, Time Scheduling Systems, and Retrofit Control Technologies -- each provide a product technology overview, discuss current products on the lighting equipment market, and provide application techniques. This document is intended for use by electric utility personnel involved in lighting programs, lighting designers, electrical engineers, architects, lighting manufacturers' representatives, and other lighting professionals.

Eley, C.; Tolen, T.M. (Eley Associates, San Francisco, CA (United States)); Benya, J.R. (Luminae Souter Lighting Design, San Francisco, CA (United States)); Rubinstein, F.; Verderber, R. (Lawrence Berkeley Lab., CA (United States))

1993-05-01T23:59:59.000Z

369

Comprehensive Epidemiologic Data Resource. Revision 1  

Science Conference Proceedings (OSTI)

The Department of Energy has established the Comprehensive Epidemiologic Data Resource (CEDR) as a public-use data base with the goal of broadening independent access to data collected during studies of the health effects of exposure to radiation and other physical or chemical agents associated with the production of nuclear materials. This catalog is intended for use by any individual interested in obtaining information about, or access to, CEDR data. This catalog provides information that will help users identify and request data file sets of interest.

NONE

1995-05-01T23:59:59.000Z

370

Integrated Materials Information DVD - Revision 1  

Science Conference Proceedings (OSTI)

This EPRI Materials Initiative Document Suite on CD is an interim step toward implementation of an internet-based system for presentation and maintenance of EPRI materials initiative documents and associated links to key EPRI products. The EPRI materials initiative was developed to address NEI 03-08, "Guideline for the Management of Materials Issues." NEI 03-08 outlines the policy and practices that the industry has committed to follow in managing materials aging issues. Two standing committees were esta...

2011-06-07T23:59:59.000Z

371

Programming in Fortran M. Revision 1  

SciTech Connect

Fortran M is a small set of extensions to Fortran that supports a modular approach to the construction of sequential and parallel programs. Fortran M program use channels to plug together processes which may be written in Fortran M or Fortran 77. Processes communicate by sending and receiving messages on channels. Channels and processes can be created dynamically, but programs remain deterministic unless specialized nondeterministic constructs are used. Fortran M programs can execute on a range of sequential, parallel, and networked computers. This report incorporates both a tutorial introduction to Fortran M and a users guide for the Fortran M compiler developed at Argonne National Laboratory. The Fortran M compiler, supporting software, and documentation are made available free of charge by Argonne National Laboratory, but are protected by a copyright which places certain restrictions on how they may be redistributed. See the software for details. The latest version of both the compiler and this manual can be obtained by anonymous ftp from Argonne National Laboratory in the directory pub/fortran-m at info.mcs.anl.gov.

Foster, I.T.; Olson, R.D.; Tuecke, S.J.

1993-10-01T23:59:59.000Z

372

Hanford Internal Dosimetry Project manual. Revision 1  

SciTech Connect

This document describes the Hanford Internal Dosimetry Project, as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy and its Hanford contractors. Project services include administrating the bioassay monitoring program, evaluating and documenting assessment of potential intakes and internal dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. Specific chapters deal with the following subjects: practices of the project, including interpretation of applicable DOE Orders, regulations, and guidance into criteria for assessment, documentation, and reporting of doses; assessment of internal dose, including summary explanations of when and how assessments are performed; recording and reporting practices for internal dose; selection of workers for bioassay monitoring and establishment of type and frequency of bioassay measurements; capability and scheduling of bioassay monitoring services; recommended dosimetry response to potential internal exposure incidents; quality control and quality assurance provisions of the program.

Carbaugh, E.H.; Bihl, D.E.; MacLellan, J.A.; Long, M.P.

1994-07-01T23:59:59.000Z

373

Alloy 690 Procurement Specification - Revision 1  

Science Conference Proceedings (OSTI)

The metallurgical characteristics of Alloy 690 can play a role in its resistance to primary water stress corrosion cracking (PWSCC) propensity and UT inspectibility. This specification guideline was created to provide guidance on the procurement of Alloy 690 to ensure that it has the metallurgical characteristics to optimize its PWSCC resistance and eliminate microstructure which could affect the Ultrasonic test (UT) inspectability of the material. The Alloy 690 procurement specification guideline ...

2012-10-11T23:59:59.000Z

374

Revised 7/10 1 RICE UNIVERSITY  

E-Print Network (OSTI)

are fully vested and may contact TIAA-CREF or Fidelity directly to discuss your options regarding the funds. (TIAA-CREF: www.tiaa-cref.org or 800-842-2776; Fidelity:www.netbenefits.fidelity.com or 800 and self-fund. If you enrolled, contact TIAA-CREF or Fidelity directly to discuss your options regarding

375

NMAC Post Maintenance Testing Guide, Revision 1  

Science Conference Proceedings (OSTI)

This Nuclear Maintenance Applications Center (NMAC) guide addresses the concern of member utilities regarding the adequacy and consistency of post-maintenance testing programs. The guide provides information on structuring, developing, organizing, and controlling a post-maintenance testing program in a power plant. It stresses the importance of advance planning to post-maintenance testing.

2004-12-08T23:59:59.000Z

376

Technical Foundation of Reactor Safety, Revision 1  

Science Conference Proceedings (OSTI)

Following the 1979 accident at the Three Mile Island Unit 2involving damaged fuel and fission product releaseEPRI undertook an intensive research program to investigate fission product behavior during light water reactor (LWR) severe accident scenarios. The EPRI program included experiments to obtain fundamental data and the development of computer-based models of the phenomena involved. The U.S. Nuclear Regulatory Commission (NRC) and various international organizations also initiated similar research p...

2010-10-25T23:59:59.000Z

377

FFCAct Clearinghouse, Directory of abstracts. Revision 1  

SciTech Connect

The Federal Facility Compliance Act (FFCAct) Clearinghouse is a card catalog of information about the FFCAct and its requirements for developing Site Treatment Plans (STP). The information available in the clearinghouse includes abstracts describing computer applications, technical reports, and a list of technical experts. Information can be accessed for use in responding to FFCAct requirements, and the clearinghouse provides search capabilities on particular topics and issues related to STP development. Appendix A includes: contacts from each site, for which contact has been made, who are developing STPs; the FFCAct Clearinghouse Fact Sheet and; additional hard copy forms to be used to populate the database. This report contains 50 abstracts related to the Radioactive Waste Technical Support Program.

Harwood, T.

1994-05-01T23:59:59.000Z

378

ALS Beamline Design Requirements - Revision 1  

E-Print Network (OSTI)

Source Photon Beam LinesBNL/NSLS XI Beamline Mirror SystemSynchrotron Light Source (NSLS) at Brookhaven NationalMay 1996. ' R Stefan, NSLS-BNL, personal communication.

Heimann, Phil

2010-01-01T23:59:59.000Z

379

ALS Beamline Design Requirements - Revision 1  

E-Print Network (OSTI)

materials are not allowed in the ALS experiment area withoutlocations provided by the ALS. c. Cleaning proceduresa successful walkthrough, the ALS Director or designee gives

Heimann, Phil

2010-01-01T23:59:59.000Z

380

Reported Significant Observation (RSO) studies. Revision 1  

SciTech Connect

The Reported Significant Observation (RSO) study used in the field of safety is an information-gathering technique where employee-participants describe situations they have personally witnessed involving good and bad practices and safe and unsafe conditions. This information is useful in the risk assessment process because it focuses on hazards and thereby facilitates their elimination. However, RSO cannot be the only component in a risk assessment program. Used by the Air Force in their aviation psychology program and further developed by John C. Flanagan, RSO is more commonly known as the ``Critical Incident Technique.`` However, the words ``Critical`` and ``Incident`` had other connotations in nuclear safety, prompting early users within the Aerojet Nuclear Company to coin the more fitting title of ``Reported Significant Observations.`` The technique spread slowly in the safety field primarily because the majority of users were researchers interested in after-the-fact data, with application to everyday problems and behavioral factors. RSO was formally recognized as a significant hazard reduction tool during the development of the Management Oversight and Risk Tree (MORT) program for the US Atomic Energy Commission. The Department of Energy (DOE) has, in turn, adopted MORT for its system safety program, and this has resulted in RSO being a modern and viable technique for DOE contractor safety programs.

Eicher, R.W.

1992-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Radiation interactions for tomography. Revision 1  

SciTech Connect

There are new requirements emerging in the field of tomography: the need for spatial resolution in the micrometre range, atomic species specificity, and quantitative density discrimination.

Zolnay, A.S.

1985-05-20T23:59:59.000Z

382

Parallel programming with PCN. Revision 1  

SciTech Connect

PCN is a system for developing and executing parallel programs. It comprises a high-level programming language, tools for developing and debugging programs in this language, and interfaces to Fortran and C that allow the reuse of existing code in multilingual parallel programs. Programs developed using PCN are portable across many different workstations, networks, and parallel computers. This document provides all the information required to develop parallel programs with the PCN programming system. In includes both tutorial and reference material. It also presents the basic concepts that underly PCN, particularly where these are likely to be unfamiliar to the reader, and provides pointers to other documentation on the PCN language, programming techniques, and tools. PCN is in the public domain. The latest version of both the software and this manual can be obtained by anonymous FTP from Argonne National Laboratory in the directory pub/pcn at info.mcs.anl.gov (c.f. Appendix A).

Foster, I.; Tuecke, S.

1991-12-01T23:59:59.000Z

383

Health Physics Positions Data Base: Revision 1  

SciTech Connect

The Health Physics Positions (HPPOS) Data Base of the Nuclear Regulatory Commission (NRC) is a collection of NRC staff positions on a wide range of topics involving radiation protection (health physics). It consists of 328 documents in the form of letters, memoranda, and excerpts from technical reports. The HPPOS Data Base was developed by the NRC Headquarters and Regional Offices to help ensure uniformity in inspections, enforcement, and licensing actions. Staff members of the Oak Ridge National Laboratory (ORNL) have assisted the NRC staff in summarizing the documents during the preparation of this NUREG report. These summaries are also being made available as a {open_quotes}stand alone{close_quotes} software package for IBM and IBM-compatible personal computers. The software package for this report is called HPPOS Version 2.0. A variety of indexing schemes were used to increase the usefulness of the NUREG report and its associated software. The software package and the summaries in the report are written in the context of the {open_quotes}new{close_quotes} 10 CFR Part 20 ({section}{section}20.1001--20.2401). The purpose of this NUREG report is to allow interested individuals to familiarize themselves with the contents of the HPPOS Data Base and with the basis of many NRC decisions and regulations. The HPPOS summaries and original documents are intended to serve as a source of information for radiation protection programs at nuclear research and power reactors, nuclear medicine, and other industries that either process or use nuclear materials.

Kerr, G.D.; Borges, T.; Stafford, R.S.; Lu, P.Y. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States); Carter, D. [US Nuclear Regulatory Commission, Washington, DC (United States)] [US Nuclear Regulatory Commission, Washington, DC (United States)

1994-02-01T23:59:59.000Z

384

ALS Beamline Design Requirements - Revision 1  

E-Print Network (OSTI)

80, Room 40. REFERENCES DOE Order 5480.19, Conduct ofGuidelines, Chapter 8 DOE Order 5280.25, Safety of

Heimann, Phil

2010-01-01T23:59:59.000Z

385

ADR Revised Policy | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revised Policy Revised Policy ADR Revised Policy SUMMARY: On October 24, 1995, the Department of Energy (DOE) published an interim Statement of Policy on Alternative Dispute Resolution (ADR) (60 FR 54482) to further its commitment to the use of ADR for resolving issues in controversy in a fair, timely, and cost efficient manner, and to comply with the Administrative Dispute Resolution Act (ADRA), 5 U.S.C. §571 et seq. Today, DOE publishes a revised Statement of Policy on Alternative Dispute Resolution to reaffirm its commitment to the use of ADR, including the use of Environmental Conflict Resolution (ECR) and othercollaborative processes that may be utilized to prevent or avoid potential conflicts. ADR Revised Policy More Documents & Publications Microsoft Word - ADR Revised Policy82508Reformatted.doc

386

NIST Leads Revision of International Coordinate Measuring ...  

Science Conference Proceedings (OSTI)

NIST Leads Revision of International Coordinate Measuring Machine Standard. ... ASME) represents the final step in a decade-long effort led by the ...

2011-04-25T23:59:59.000Z

387

Revision to the Canada Country Analysis Brief  

U.S. Energy Information Administration (EIA)

Revision to the Canada Country Analysis Brief. December 10, 2012. Text incorrectly implied that Encana is developing another major natural gas project off ...

388

1  

NLE Websites -- All DOE Office Websites (Extended Search)

4.1 4.1 The Shortwave (SW) Clear-Sky Detection and Fitting Algorithm: Algorithm Operational Details and Explanations Revision 1, January 2004 C. N. Long and K. L. Gaustad Pacific Northwest National Laboratory Richland, Washington Work supported by the U.S. Department of Energy, Office of Energy Research, Office of Health and Environmental Research C. N. Long and K. L. Gaustad, December 2000, ARM TR-004.1 Contents 1. Introduction........................................................................................................................................... 1 2. Preparing the Raw Input Files............................................................................................................... 2 3. Running the Clear ID and Fitting Algorithm (swclrid1a)

389

Kentucky Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

35 8.42 NA 4.47 1967-2010 35 8.42 NA 4.47 1967-2010 Pipeline and Distribution Use 1967-2005 Citygate 8.22 10.14 5.98 5.69 5.18 4.17 1984-2012 Residential 12.05 13.84 11.97 10.02 10.44 10.19 1967-2012 Commercial 11.29 13.25 10.89 8.61 8.79 8.28 1967-2012 Industrial 8.37 10.41 6.04 5.57 5.16 3.96 1997-2012 Vehicle Fuel -- -- -- -- -- -- 1992-2012 Electric Power W W W W W W 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 2,469 2,714 2,782 2,613 2,006 1977-2011 Adjustments 37 81 97 -58 -34 1977-2011 Revision Increases 62 187 126 103 178 1977-2011 Revision Decreases 152 133 760 540 639 1977-2011 Sales 4 10 0 0 100 2000-2011 Acquisitions 6 13 0 39 84 2000-2011 Extensions 373 200 713 383 4 1977-2011

390

Colorado Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet)  

U.S. Energy Information Administration (EIA) Indexed Site

Increases (Billion Cubic Feet) Increases (Billion Cubic Feet) Colorado Dry Natural Gas Reserves Revision Increases (Billion Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 116 226 373 1980's 250 131 322 167 160 368 372 340 473 431 1990's 394 719 718 1,000 696 555 802 959 1,898 2,788 2000's 1,825 1,882 2,029 2,114 1,505 2,018 1,178 3,924 3,244 1,601 2010's 2,973 2,509 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Dry Natural Gas Reserves Revision Increases Colorado Dry Natural Gas Proved Reserves Dry Natural Gas Proved Reserves Revision Increases

391

Dry Natural Gas Proved Reserves as of Dec. 31  

U.S. Energy Information Administration (EIA) Indexed Site

211,085 237,726 244,656 272,509 304,625 334,067 1925-2011 211,085 237,726 244,656 272,509 304,625 334,067 1925-2011 Federal Offshore U.S. 15,360 14,439 13,546 12,552 11,765 10,420 1990-2011 Pacific (California) 811 805 704 739 724 710 1977-2011 Louisiana & Alabama 11,824 11,090 10,450 9,362 8,896 8,156 1981-2011 Texas 2,725 2,544 2,392 2,451 2,145 1,554 1981-2011 Alaska 10,245 11,917 7,699 9,101 8,838 9,424 1977-2011 Lower 48 States 200,840 225,809 236,957 263,408 295,787 324,643 1977-2011 Alabama 3,911 3,994 3,290 2,871 2,629 2,475 1977-2011 Arkansas 2,269 3,305 5,626 10,869 14,178 16,370 1977-2011 California 2,794 2,740 2,406 2,773 2,647 2,934 1977-2011 Coastal Region Onshore 206 205 146 163 173 165 1977-2011 Los Angeles Basin Onshore 153 144 75 84 87 97 1977-2011

392

Archived Weekly Files, Revised, 1984 Forward EIA revises its first-round  

U.S. Energy Information Administration (EIA) Indexed Site

Weekly Coal Production> Archive of weekly and monthly coal production data Weekly Coal Production> Archive of weekly and monthly coal production data Archive weekly and monthly coal production -- revised and original estimates About coal production revision estimates EIA revises its weekly (and monthly) original estimates of state-level coal production using quarterly mine-level coal production data from the Mine Safety and Health Administration (MSHA) as soon as the data are available. This method guarantees that EIA’s revised coal production estimates for each past quarter conform with the MSHA survey data. The state level revised estimates include refuse coal. EIA uses this equation to revise its weekly coal production estimates: Revised weekly estimate (State A) = original EIA estimate (State A) x MSHA quarterly data (State A) ÷

393

BOREAS SSA-YJP Tower Flux Data Revised  

NLE Websites -- All DOE Office Websites (Extended Search)

Tower Flux Data Revised A revised version of the BOREAS TF04 tower flux data is now available from the ORNL DAAC. Data providers have revised the data set entitled "BOREAS TF-04...

394

Property:NEPA RevisedApplicationDate | Open Energy Information  

Open Energy Info (EERE)

RevisedApplicationDate RevisedApplicationDate Jump to: navigation, search Property Name NEPA RevisedApplicationDate Property Type Date This is a property of type Date. Pages using the property "NEPA RevisedApplicationDate" Showing 19 pages using this property. D DOI-BLM-CA-ES-2013-002+1793-EIS + 5 June 2012 + DOI-BLM-NV-C010-2010-0006-EA + 16 November 2009 + DOI-BLM-NV-C010-2010-0010-EA + 15 October 2009 + DOI-BLM-NV-C010-2011-0016-EA + 15 March 2011 + DOI-BLM-NV-C010-2012-0050-EA + 14 February 2012 + DOI-BLM-NV-C010-2012-0051-EA + 1 December 2011 + DOI-BLM-NV-C010-2012-0069-CX + 9 August 2012 + DOI-BLM-NV-C010-2012-0070-CX + 27 July 2012 + DOI-BLM-NV-E030-2011-0017-CX + 2 March 2011 + DOI-BLM-NV-W010-2010-0004-EA + 23 November 2009 + DOI-BLM-NV-W010-2011-0001-EA + 4 June 2010 +

395

Microsoft Word - DOE-EA-1707D_Revised_Predecisional_EA Closure_NRDWL-SWL08232011.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7D 7D REVISED PREDECISIONAL DRAFT AUGUST 2011 Environmental Assessment Closure of Nonradioactive Dangerous Waste Landfill (NRDWL) and Solid Waste Landfill (SWL), Hanford Site, Richland, Washington U.S. Department of Energy Richland Operations Office Richland, Washington 99352 DOE/EA-1707D REVISED PREDECISIONAL DRAFT AUGUST 2011 DOE/EA-1707D REVISED PREDECISIONAL DRAFT iii AUGUST 2011 Contents 1 1 Introduction and Purpose and Need ............................................................................................. 1-1 2 1.1 Introduction ............................................................................................................................ 1-1 3 1.2 Purpose and Need ................................................................................................................... 1-2 4

396

Classification Bulletin GEN-16 Revision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Classification Bulletin GEN-16 Revision Classification Bulletin GEN-16 Revision Provides guidance to DOE Federal and contractor employees with access to classified information on...

397

Forrestal Garage Parking Guidelines, Revised August 12, 2010...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Forrestal Garage Parking Guidelines, Revised August 12, 2010 Forrestal Garage Parking Guidelines, Revised August 12, 2010 Forrestal Garage Parking Guidelines Forrestal Garage...

398

Revised November 20, 2009 Department of Electrical & Computer Engineering  

E-Print Network (OSTI)

Revised November 20, 2009 Department of Electrical & Computer Engineering Colorado State University for the appropriate semester. #12;Revised November 20, 2009 Department of Electrical & Computer Engineering Colorado

399

Petroleum products demand data revised at regional level ...  

U.S. Energy Information Administration (EIA)

A recent revision to petroleum product movements in the Petroleum ... The data revision involves movements of motor gasoline as reported to EIA by one or more survey ...

400

Revised Continuing Appropriations Resolution, 2007, P.L. 110...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Marketing Administration Other Agencies You are here Home Revised Continuing Appropriations Resolution, 2007, P.L. 110-5 Revised Continuing Appropriations Resolution, 2007,...

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

EIS-0218: Revision to the Record of Decision | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revision to the Record of Decision EIS-0218: Revision to the Record of Decision Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear...

402

ACMP Handbook Change 2011-01 - Revised Financial Assistance Certification  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1-01 - Revised Financial Assistance Certification 1-01 - Revised Financial Assistance Certification 1 Chapter 4 Financial Assistance Certification Financial Assistance Qualification Standards Financial assistance award and administration within DOE is performed by both GS-1102 contracting personnel and non-GS1102 contracting personnel. In order to ensure that personnel in the financial assistance area possess the requisite skill set the Financial Assistance Program (FAP), certification is required. The Financial Assistance Certification Program (FACP) curriculum is designed to provide members with the necessary financial assistance skills and with experience in a wide range of thinking, approaches, and practices. Level IV is for only those individuals involved in the award and administration of Technology

403

Materials Reliability Program: Computer-Based NDE Training for Thermal Fatigue Cracking (MRP-36, Revision 2)  

Science Conference Proceedings (OSTI)

This product comes packaged together and contains both #1022875, Materials Reliability Program: NDE Technology for Detection of Thermal Fatigue Damage in Piping, (MRP-23, Revision 1) and Product #1024915, Computer-Based NDE Training for Thermal ...

2012-11-20T23:59:59.000Z

404

UCSC Injury and Illness Prevention Program Revised 10/01 University of California  

E-Print Network (OSTI)

UCSC Injury and Illness Prevention Program Revised 10 Code of Regulations 8-3203 INJURY AND ILLNESS PREVENTION PROGRAM DEPARTMENTAL PLAN #12;TABLE OF CONTENTS Statement of Purpose 1 Authority and Responsibility 2 Compliance with Safe Work Practices 3

California at Santa Cruz, University of

405

1  

Office of Legacy Management (LM)

77-2005 77-2005 Long-Term Surveillance and Maintenance Plan for the U.S. Department of Energy Miamisburg Closure Project, Mound Site, Miamisburg, Ohio Volume I: (LTS&M Plan and referenced LM Plans and information) September 2005 Information in this document is subject to revision until the EM mission is completed at the Miamisburg Closure Project at the Mound Site S0136900 Draft Document U.S. Department of Energy LTS&M Plan⎯Mound Site, Miamisburg, Ohio September 2005 Doc. No. S0136900 Page iii Contents Acronyms...................................................................................................................................... vii 1.0 Purpose and Objective........................................................................................................1-1

406

Predictive Maintenance Primer: Revision to NP-7205  

Science Conference Proceedings (OSTI)

The "Predictive Maintenance Primer" revision provides nuclear plant personnel with current information regarding the predictive maintenance technologies and their applications. This guide will assist a plant in improving its predictive maintenance program.

2003-11-06T23:59:59.000Z

407

Water Mass Formation from Revised COADS Data  

Science Conference Proceedings (OSTI)

Surface heat and freshwater fluxes from the Comprehensive 0cean-Atmosphere Data Set are revised and used diagnostically to compute air-sea transformation rates on density, temperature, and salinity classes over the domain of the data. Maximum ...

Kevin G. Speer; H-J. Isemer; A. Biastoch

1995-10-01T23:59:59.000Z

408

Green Vegetable Oil Processing, Revised First Edition  

Science Conference Proceedings (OSTI)

This book addresses alternative green technologies at various stages of oilseed and vegetable oil processing. The Revised First Edition includes much of the content of the first edition, but incorporates updated data, details, images, figures, and captions

409

Requesting a Revision to PUB-3000  

NLE Websites -- All DOE Office Websites (Extended Search)

Requesting a Change to the ES&H Manual Requesting a Change to the ES&H Manual The following procedure describes the process for making changes to Berkeley Lab's ES&H Manual (PUB-3000). It identifies Responsible Authors who participate in the revision process. A request to revise the ES&H Manual may be initiated by any Berkeley Lab employee; however, all requests must be sent to the Responsible Author and approved by the ES&H Manual Manager, Mike Wisherop. If you wish to request a change to a PUB-3000 chapter, follow these steps: Contact the Responsible Author for the chapter in need of revision. Submit PUB-3000 revisions to the Responsible Author and the ES&H Manual Manager. Direct all questions or comments concerning ES&H Manual content to the ES&H Manual Manager.

410

2008 MERRTT Revision Letter | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 MERRTT Revision Letter 8 MERRTT Revision Letter 2008 MERRTT Revision Letter The 2008 version of MERRTT includes several enhancements, but the primary enhancement is the addition of the decontamination dress-down video. Comments received on the decontamination video script in the fall 2006 were incorporated into the script and the filming and final editing were completed in the spring 2007. The decontamination video was added to MERRTT to support the students' understanding of the decontamination dress-down process at an accident scene. Additional enhancements included the streamlining of objectives from the Terminology & Units and Assessing Package Integrity modules into other existing modules. 2008 MERRTT Revision Letter More Documents & Publications 2009 TEPP Annual Report

411

A Revised Version of Lettau's Evapoclimatonomy Model  

Science Conference Proceedings (OSTI)

In this paper a revised version of Lettau's evapoclimatonomy model is introduced. Climatonomy is a one-dimensional representation of mean climate, which includes a complete characterization of the surface energy and water balances. The model is ...

Sharon E. Nicholson; Andrew R. Lare; JosiA. Marengo; Pablo Santos

1996-04-01T23:59:59.000Z

412

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST  

E-Print Network (OSTI)

CALIFORNIA ENERGY DEMAND 20142024 REVISED FORECAST Volume 2: Electricity Demand Robert P. Oglesby Executive Director #12;i ACKNOWLEDGEMENTS The demand forecast is the combined prepared the commercial sector forecast. Mehrzad Soltani Nia helped prepare the industrial forecast

413

EPRI Maintenance Excellence Matrix Revision Status  

Science Conference Proceedings (OSTI)

This report documents the progress in revising the Electric Power Research Institute EPRI 2002 Report 1004705, Maintenance Excellence Matrix Assessment Guideline for Fossil Power Plants, which provides utilities a comprehensive self-assessment guideline for improving maintenance processes.

2008-12-23T23:59:59.000Z

414

New and revised standards for coke production  

SciTech Connect

The need for new and revised standards for coke production in Ukraine and Russia is outlined. Such standards should address improvements in plant operation, working conditions, environmental protection, energy conservation, fire and explosion safety, and economic indices.

G.A. Kotsyuba; M.I. Alpatov; Y.G. Shapoval [Giprokoks, the State Institute for the Design of Coke-Industry Enterprises, Kharkov (Ukraine)

2009-07-15T23:59:59.000Z

415

Date Issued: 1/78 Date Revised: 1/86, 7/86, 12/88, 8/91, 5/97, 2/00, 10/03, 9/05  

E-Print Network (OSTI)

: To effectively and safely handle emergencies involving radiation exposure and/or radioactive contamination radiation detection equipment for determination of radiation doses, radioactive contamination, internal: QUALITY MANAGEMENT NUMBER: 11-009 SUBJECT: RADIOACTIVE MATERIAL EXPOSURE EMERGENCIES PAGE: 1 OF 1 PURPOSE

Oliver, Douglas L.

416

Revision of the DELFIC Particle Activity Module  

SciTech Connect

The Defense Land Fallout Interpretive Code (DELFIC) was originally released in 1968 as a tool for modeling fallout patterns and for predicting exposure rates. Despite the continual advancement of knowledge of fission yields, decay behavior of fission products, and biological dosimetry, the decay data and logic of DELFIC have remained mostly unchanged since inception. Additionally, previous code revisions caused a loss of conservation of radioactive nuclides. In this report, a new revision of the decay database and the Particle Activity Module is introduced and explained. The database upgrades discussed are replacement of the fission yields with ENDF/B-VII data as formatted in the Oak Ridge Isotope Generation (ORIGEN) code, revised decay constants, revised exposure rate multipliers, revised decay modes and branching ratios, and revised boiling point data. Included decay logic upgrades represent a correction of a flaw in the treatment of the fission yields, extension of the logic to include more complex decay modes, conservation of nuclides (including stable nuclides) at all times, and conversion of key variables to double precision for nuclide conservation. Finally, recommended future work is discussed with an emphasis on completion of the overall radiation physics upgrade, particularly for dosimetry, induced activity, decay of the actinides, and fractionation.

Hooper, David A [ORNL; Jodoin, Vincent J [ORNL

2010-09-01T23:59:59.000Z

417

Belief revision in non-monotonic reasoning and logic programming  

Science Conference Proceedings (OSTI)

Keywords: belief revision, logic programming, logics of knowledge and beliefs, non-monotonic reasoning

Jos Jlio Alferes; Lus Moniz Pereira; Teodor C. Przymusinski

1996-11-01T23:59:59.000Z

418

EFDA(05)-27/4.10 revision 1 (revision 0: STAC 10/4.1)  

E-Print Network (OSTI)

&D and Integration Facility h ardware integration, mock-ups & in stallation Shielding/Remote Handling Integration in numerical aperture. · Running fibers hot only affects the long-term absorption. · Great disparity° 45° 20° Vacuum Vessel Test Cell Floor Quartz coherent fiber optic bundles Radiation Shielding

419

Revised FINALREPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004) 2018-SR-02-1  

Science Conference Proceedings (OSTI)

The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963. The reactor was tested at low power during the first couple years of operation. Power ascension testing above 1 MW commenced in December 1965 immediately following the receipt of a high-power operating license. In October 1966 during power ascension, zirconium plates at the bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel subassemblies. Two subassemblies started to melt and the reactor was manually shut down. No abnormal releases to the environment occurred. Forty-two months later after the cause had been determined, cleanup completed, and the fuel replaced, Fermi 1 was restarted. However, in November 1972, PRDC made the decision to decommission Fermi 1 as the core was approaching its burn-up limit. The fuel and blanket subassemblies were shipped off-site in 1973. Following that, the secondary sodium system was drained and sent off-site. The radioactive primary sodium was stored on-site in storage tanks and 55 gallon (gal) drums until it was shipped off-site in 1984. The initial decommissioning of Fermi 1 was completed in 1975. Effective January 23, 1976, DPR-9 was transferred to the Detroit Edison Company (DTE) as a 'possession only' license (DTE 2010a). This report details the confirmatory activities performed during the second Oak Ridge Institute for Science and Education (ORISE) site visit to Fermi 1 in November 2010. The survey was strategically planned during a Unit 2 (Fermi 2) outage to take advantage of decreased radiation levels that were observed and attributed to Fermi 2 from the operating unit during the first site visit. However, during the second visit there were elevated radiation levels observed and attributed to the partially dismantled Fermi 1 reactor vessel and a waste storage box located on the 3rd floor of the Fermi 1 Turbine Building. Confirmatory surveys (unshielded) performed directly in the line of sight of these areas were affected. The objective of the confirmatory survey was to verify that the final radiological conditions were accurately and adequately described in Final Status Survey (FSS) documentation, relative to the established release criteria. This objective was achieved by performing document reviews, as well as independent measurements and sampling. Specifically, documentation of the planning, implementation, and results of the FSS were evaluated; side-by-side FSS measurement and source comparisons were performed; site areas were evaluated relative to appropriate FSS classification; and areas were assessed for residual, undocumented contamination.

Erika Bailey

2011-10-27T23:59:59.000Z

420

Corrective Action Investigation Plan for Corrective Action Unit 322: Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 322, Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 322 consists of three Corrective Action Sites (CASs): 01-25-01, AST Release (Area 1); 03-25-03, Mud Plant AST Diesel Release (Area 3); 03-20-05, Injection Wells (Area 3). Corrective Action Unit 322 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. The investigation of three CASs in CAU 322 will determine if hazardous and/or radioactive constituents are present at concentrations and locations that could potentially pose a threat to human health and the environment. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-07-16T23:59:59.000Z

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Corrective Action Investigation Plan for Corrective Action Unit 527: Horn Silver Mine, Nevada Test Site, Nevada: Revision 1 (Including Records of Technical Change No.1, 2, 3, and 4)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 527, Horn Silver Mine, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 527 consists of one Corrective Action Site (CAS): 26-20-01, Contaminated Waste Dump No.1. The site is located in an abandoned mine site in Area 26 (which is the most arid part of the NTS) approximately 65 miles northwest of Las Vegas. Historical documents may refer to this site as CAU 168, CWD-1, the Wingfield mine (or shaft), and the Wahmonie mine (or shaft). Historical documentation indicates that between 1959 and the 1970s, nonliquid classified material and unclassified waste was placed in the Horn Silver Mine's shaft. Some of the waste is known to be radioactive. Documentation indicates that the waste is present from 150 feet to the bottom of the mine (500 ft below ground surface). This CAU is being investigated because hazardous constituents migrating from materials and/or wastes disposed of in the Horn Silver Mine may pose a threat to human health and the environment as well as to assess the potential impacts associated with any potential releases from the waste. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office

2002-12-06T23:59:59.000Z

422

Enforcement Guidance Supplement 03-02: Revision to Occurrence Report-Based  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-02: Revision to Occurrence 3-02: Revision to Occurrence Report-Based Noncompliance Tracking System Reporting Criteria Enforcement Guidance Supplement 03-02: Revision to Occurrence Report-Based Noncompliance Tracking System Reporting Criteria Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. OE typically issues such guidance in the form of Enforcement Guidance Supplements (EGS), which provide information or recommendations only and impose no requirements or actions on Department of Energy (DOE) contractors. Enforcement Guidance Supplement 03-02: Revision to Occurrence Report-Based

423

EIS-0200: Revision to the Record of Decision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

: Revision to the Record of Decision : Revision to the Record of Decision EIS-0200: Revision to the Record of Decision Department of Energy's Waste Management Program: Treatment and Storage of Transuranic Waste The Department has now decided to establish the capability at WIPP to prepare for disposal up to 1,250 cubic meters of contact-handled transuranic (CH-TRU) waste out of about 7,000 cubic meters expected to be received annually for disposal at WIPP. In addition, DOE has decided to increase the time that CH-TRU waste may be stored above ground at WIPP to one year and to increase the total above-ground storage capacity at WIPP by 25 percent, for a total of 152 cubic meters. DOE/EIS-0200, Revision to the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of Transuranic

424

Revised version of essay for volume edited by Bill Stoeger on philosophical issues in cosmology, in Pachart Press Philosophy in Science series  

E-Print Network (OSTI)

1 Revised version of essay for volume edited by Bill Stoeger on philosophical issues in cosmology defined realms. Encompassing is intellectually respectful, and a worldwide community of creativity

California at Santa Cruz, University of

425

Development of Revised Energy Standards for Texas Buildings: Preliminary Results  

E-Print Network (OSTI)

In 1977, the State of Texas published a two-part Energy Conservation Manual to aid designers, builders, and contractors in the design of energy-efficient state buildings. Under the sponsorship of the Governor's Energy Management Center, the Center for Energy Studies (CES) at The University of Texas at Austin is revising and updating the nonresidential building portion of the Energy Conservation Manual. The proposed revision is a Texas-specific adaptation of ASHRAE Standard 90.1P ("Energy Efficient Design of New Buildings Except Low-Rise Residential Buildings"). These modifications include editorial changes, such as deletion of criteria that do not apply to Texas climates, as well as improved envelope criteria and the addition of HVAC system performance criteria. This paper documents the approach taken in the development of the revised Texas standards. Preliminary results are presented for the new envelope calculation procedures that will be included in the compliance software. This software will parallel that provided for the envelope and lighting sections in the ASHRAE Standard and will ultimately extend the standard to include a performance-based approach for HVAC systems and whole-building Energy Targets.

Hunn, B. D.; Jones, J. W.; Silver, S. C.

1988-01-01T23:59:59.000Z

426

Microsoft Word - Midway Benton Draft_EA_Revision_Sheet_5Dec2012.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Midway-Benton No. 1 Transmission Line Rebuild Project 1 Midway-Benton No. 1 Transmission Line Rebuild Project 1 Revision Sheet for Final Environmental Assessment Midway-Benton No. 1 Transmission Line Rebuild Project Department of Energy Bonneville Power Administration Revision Sheet DOE/EA-1912 December 6, 2012 Summary Bonneville Power Administration (BPA) released the Midway-Benton No. 1 Transmission Line Rebuild Project Preliminary Environmental Assessment (EA) in June 2012 for public comment. BPA sent the Preliminary EA to agencies and interested parties who requested a copy. Notification that the EA was available and instructions of how to request a copy was sent to the mailing list of potentially affected parties. BPA received four comments and have responded to these comments in this revision sheet.

427

Microsoft Word - LBNL-57260-Revision.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

7260-Revision 7260-Revision ERNEST ORLANDO LAWRENCE BERKELEY NATIONAL LABORATORY Energy Efficiency Improvement and Cost Saving Opportunities for the Pharmaceutical Industry An ENERGY STAR ® Guide for Energy and Plant Managers Christina Galitsky, Sheng-chieh Chang, Ernst Worrell, and Eric Masanet Environmental Energy Technologies Division Sponsored by the U.S. Environmental Protection Agency March 2008 Disclaimer This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes

428

Radiation Safety (Revised March 2010)  

E-Print Network (OSTI)

.8 106.3 13.1 (14.5°) 9.3 1.3952 0.256 62 Triethylene glycol dimethyl ether -45 216 7.5 1.4224 0.253 63 2 CALIFORNIUM EINSTEINIUM FERMIUM MENDELEVIUM NOBELIUM SAMARIUM EUROPIUM GADOLINIUM TERBIUM DYSPROSIUM HOLMIUM

Ford, James

429

Page 1 of 1 Revised Oct. 30, 2012 UBC Utilities  

E-Print Network (OSTI)

( ) DISTRICT HEATING ( ) Size of Service: Signature of Requestor: ______ Location of Service: Date and Time Gas Permit Number: _______________________________ Gas Pressure: _______________ DISTRICT HEATING

Vellend, Mark

430

Steam Generator Reference Book, Revision 1: Volume 1  

Science Conference Proceedings (OSTI)

The Steam Generator Reference Book documents the state of the art in PWR steam generator technology, providing a comprehensive source for operators, owners, and designers of PWR nuclear power plants. The book summarizes pertinent steam generator operating issues and provides recommendations to improve operational efficiency. Information in the book represents 15 years of research and development activity over the course of several hundred research projects involving PWR steam generator issues.

1994-12-31T23:59:59.000Z

431

mph_hpca_revise.dvi  

NLE Websites -- All DOE Office Websites (Extended Search)

Examples are call MPHgetargument("alpha",alpha2) call MPHgetargument("beta",beta) call MPHgetargument(fieldnum1,fieldvalfilename) Thus alpha2 will get the value...

432

Date issued: Date approved: Date revised: Date revision approved:  

E-Print Network (OSTI)

1.0 Reason for Terms of Reference The terms of Reference for the Radiation Protection Committee 1 are set out in accordance with the Procedures and the Policy entitled "Radiation Safety", in connection with the Radiation Safety program for all radioactive material, X-ray equipment and other sources of ionizing radiation in all areas under the control of the University of Manitoba. 2.0 Terms of Reference 2.1 Radiation Protection Committee The University has established and shall maintain a Radiation Protection Committee comprising members of the University community and stakeholders knowledgeable in the safe use of radioactive material, X-ray equipment and other sources of ionizing radiation. The Committee shall report to the Executive Director of Human Resources. The Radiation Protection Committee is authorized to: a) Advise on the safe use of radioactive material, X-ray equipment and other sources of ionizing radiation;

unknown authors

2004-01-01T23:59:59.000Z

433

BSCMeasuresInformationRevisionSept2005.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Federal Procurement System Balanced Scorecard Performance Measures Information Document Office of Procurement and Assistance Management Revised: September 2005 2 Table of Contents Purpose ...................................................................................................... 4 CUSTOMER PERSPECTIVE Customer Satisfaction: Timeliness ........................................................................................... 5 Quality ................................................................................................ 7 Effective Service/Partnership ........................................................................... 9 INTERNAL BUSINESS PERSPECTIVE Acquisition Excellence .................................................................................. 11

434

Anomalies of Nuclear Criticality, Revision 6  

SciTech Connect

This report is revision 6 of the Anomalies of Nuclear Criticality. This report is required reading for the training of criticality professionals in many organizations both nationally and internationally. This report describes many different classes of nuclear criticality anomalies that are different than expected.

Clayton, E. D.; Prichard, Andrew W.; Durst, Bonita E.; Erickson, David; Puigh, Raymond J.

2010-02-19T23:59:59.000Z

435

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022  

E-Print Network (OSTI)

REVISED CALIFORNIA ENERGY DEMAND FORECAST 20122022 Volume 2: Electricity Demand by Utility ACKNOWLEDGEMENTS The staff demand forecast is the combined product of the hard work and expertise of numerous, Mohsen Abrishami prepared the commercial sector forecast. Mehrzad Soltani Nia helped prepare

436

JM to revise DOE G 414.1-1B, Management and Independent Assessments Guide for Use with 10 CFR, Part 830, Subpart A, and DOE O 414.1C, Quality Assurance; DOE M 450.4-1, Integrated Safety Management System Manual; and DOE O 226.1A  

Directives, Delegations, and Requirements

Management and Independent Assessments Guide for Use with 10 CFR, Part 830, Subpart A, and DOE O 414.1C, Quality Assurance; DOE M 450.4-1, Integrated Safety ...

2013-04-18T23:59:59.000Z

437

SOLAR NEUTRINOS REVIEW Revised December  

NLE Websites -- All DOE Office Websites (Extended Search)

+ + 2 e . (1) Positrons annihilate with electrons. Therefore, when consider- ing the solar thermal energy generation, a relevant expression is 4p + 2e - 4 He + 2 e + 26.73...

438

Revision Policy for EIA Weekly Underground Natural Gas Storage Estimates  

Weekly Natural Gas Storage Report (EIA)

April 26, 2005 April 26, 2005 This report consists of the following sections: General EIA Weekly Natural Gas Storage Report Revisions Policy - a description of how revisions to the Weekly Natural Gas Storage Report estimates may occur EIA Weekly Natural Gas Storage Report Policy to Allow Unscheduled Release of revisions - a description of the policy that will be implemented in the event of an out-of-cycle release Revisions to the Historical Database - a description of how revisions will be noted in the Historical database Revisions may be presented for the most recent estimates of working gas in storage under a number of circumstances that occur after release of the estimates. These include: I. A respondent revises previously submitted data (respondents are requested to submit revisions if the change is greater than 500 million

439

U.S. Shale Proved Reserves Revision Increases (Billion Cubic...  

Annual Energy Outlook 2012 (EIA)

View History: Annual Download Data (XLS File) U.S. Shale Proved Reserves Revision Increases (Billion Cubic Feet) U.S. Shale Proved Reserves Revision Increases (Billion Cubic Feet)...

440

U.S. Shale Proved Reserves Revision Decreases (Billion Cubic...  

Gasoline and Diesel Fuel Update (EIA)

View History: Annual Download Data (XLS File) U.S. Shale Proved Reserves Revision Decreases (Billion Cubic Feet) U.S. Shale Proved Reserves Revision Decreases (Billion Cubic Feet)...

Note: This page contains sample records for the topic "1 1977-2011 revision" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Microsoft Word - NDA Box PDP Plan-Revision 4-final  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization Program Revision 4 May 2013 This document supersedes Revision 3 of DOECBFO-01-1006 U.S. Department of Energy Carlsbad Field Office Office of the National TRU...

442

Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 Acquisition Letter 09 - Revision of Department 2 Acquisition Letter 09 - Revision of Department of Energy (DOE) Order 350.1 and Special H Clause Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department of Energy (DOE) Order 350.1 and Special H Clause Questions concerning this policy flash should be directed to Robert M. Myers, Director, Contractor Human Resources Policy Division (MA-612) at (202) 287-1584 or robert.myers@hq.doe.gov. Policy Flash - DOE O 350 1.pdf Consolidated Model H-Clause 06-27-13.pdf Acquisition Letter - DOE O 350 1 6-27-13.pdf More Documents & Publications Chapter 30 - Cost Accounting Standards Administration OPAM Policy Acquisition Guides GAO-04-539 Department of Energy: Certain Postretirement Benefits for Contractor Employees Are Unfunded and Program Oversight Could Be Improved

443

Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department of Energy (DOE) Order 350.1 and Special H Clause Policy Flash 2013-62 Acquisition Letter 09 - Revision of Department of Energy (DOE) Order 350.1 and Special H Clause Questions concerning this policy flash should be directed to Robert M. Myers, Director, Contractor Human Resources Policy Division (MA-612) at (202) 287-1584 or robert.myers@hq.doe.gov. Policy Flash - DOE O 350 1.pdf Consolidated Model H-Clause 06-27-13.pdf Acquisition Letter - DOE O 350 1 6-27-13.pdf More Documents & Publications GAO-04-539 Department of Energy: Certain Postretirement Benefits for Contractor Employees Are Unfunded and Program Oversight Could Be Improved Chapter 30 - Cost Accounting Standards Administration

444

Coalbed Methane Reserves Revision Decreases  

Gasoline and Diesel Fuel Update (EIA)

2,486 2,914 1,668 2009-2011 2,486 2,914 1,668 2009-2011 Federal Offshore U.S. 0 0 0 2009-2011 Pacific (California) 0 0 0 2009-2011 Louisiana & Alabama 0 0 0 2009-2011 Texas 0 0 0 2009-2011 Alaska 0 0 0 2009-2011 Lower 48 States 2,486 2,914 1,668 2009-2011 Alabama 316 51 86 2009-2011 Arkansas 0 1 3 2009-2011 California 0 0 0 2009-2011 Coastal Region Onshore 0 0 0 2009-2011 Los Angeles Basin Onshore 0 0 0 2009-2011 San Joaquin Basin Onshore 0 0 0 2009-2011 State Offshore 0 0 0 2009-2011 Colorado 566 1,557 367 2009-2011 Florida 0 0 0 2009-2011 Kansas 107 0 14 2009-2011 Kentucky 0 0 0 2009-2011 Louisiana 0 0 0 2009-2011 North 0 0 0 2009-2011 South Onshore 0 0 0 2009-2011 State Offshore 0 0 0 2009-2011 Michigan 0 0 0 2009-2011 Mississippi 0 0 0 2009-2011

445

Environmental Monitoring Plan, Revision 5  

SciTech Connect

The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 450.1A, Environmental Protection Program. Specifically, in conformance with DOE Order 450.1A, Attachment 1, paragraph 1(b)(5), environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring also serves to demonstrate compliance with permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality. (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work. (3) An integrated sampling approach to avoid duplicative data collection. Until its cancellation in January 2003, DOE Order 5400.1 required the preparation of an environmental monitoring plan. Neither DOE Order 450.1A nor the ISO 14001 standard are as prescriptive as DOE Order 5400.1, in that neither expressly requires an EMP. However, LLNL continues to prepare the EMP because it provides an organizational framework for ensuring that this work, which is integral to the implementation of LLNL's Environmental Management System, is conducted appropriately. Furthermore, the Environmental Monitoring Plan helps LLNL ensure compliance with DOE Order 5400.5, Radiation Protection of the Public and the Environment, and DOE Order 231.1 Change 2, Environment, Safety and Health Reporting, which require the publication of an annual report that characterizes the site's environmental management performance. To summarize, the general regulatory drivers for this environmental monitoring plan are ISO 14001, DOE Order 450.1A, DOE Order 5400.5, and DOE Order 231.1. The environmental monitoring addressed by this plan includes preoperational characterization and assessment, effluent and surveillance monitoring, and permit and regulatory compliance monitoring. Additional environmental monitoring is conducted at LLNL as part of compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, also known as Superfund). LLNL coordinates its ground water surveillance monitoring program with the CERCLA monitoring program to gain sampling efficiencies. (See LLNL [1992] and LLNL [2008] for information about LLNL's CERCLA activities).

Gallegos, G M; Blake, R G; Bertoldo, N A; Campbell, C G; Coty, J; Folks, K; Grayson, A R; Jones, H E; Nelson, J C; Revelli, M A; Wegrecki, T; Williams, R A; Wilson, K

2010-01-27T23:59:59.000Z

446

Utility Energy Services Contracts: Enabling Documents, May 2009 (Revised) (Book)  

NLE Websites -- All DOE Office Websites (Extended Search)

www.femp.energy.gov ENERGY U.S. DEPARTMENT OF Energy Efficiency & Renewable Energy Utility Energy Services Contracts: Enabling Documents Prepared for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy Federal Energy Management Program Revised June 2013 DOE/GO-102009-2588 UESCs: Enabling Documents 1 Department of Energy Washington, D.C. Dear Colleagues, The U.S. Department of Energy's (DOE) Federal Energy Management Program (FEMP) is pleased to present this third edition of Utility Energy Services Contracts: Enabling Documents. These documents provide a selected set of background information materials that clarify the authority for Federal agencies to enter into utility energy services

447

Utility Energy Services Contracts: Enabling Documents, May 2009 (Revised) (Book)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

www.femp.energy.gov ENERGY U.S. DEPARTMENT OF Energy Efficiency & Renewable Energy Utility Energy Services Contracts: Enabling Documents Prepared for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy Federal Energy Management Program Revised June 2013 DOE/GO-102009-2588 UESCs: Enabling Documents 1 Department of Energy Washington, D.C. Dear Colleagues, The U.S. Department of Energy's (DOE) Federal Energy Management Program (FEMP) is pleased to present this third edition of Utility Energy Services Contracts: Enabling Documents. These documents provide a selected set of background information materials that clarify the authority for Federal agencies to enter into utility energy services

448

REVISED NATURAL GAS MARKET ASSESSMENT  

E-Print Network (OSTI)

pipeline reverses and expands to allow the flow of regasified LNG from the Costa Azul LNG terminal in Baja natural gas LNG terminal in Southern California and one assuming dry hydro conditions. For all cases the "lower 48" states was expected to increase by 1.6 percent per year. · Proposed LNG facilities on the East

449

2011-2012 and 2013-2014 Additions and Revisions Package  

Science Conference Proceedings (OSTI)

2011-2012 Additions and Revisions + 2013 2014 Additions and Revisions package 2011-2012 and 2013-2014 Additions and Revisions Package Methods - Analyses Books Methods - Analyses Books The 2013 2014 Additions and Revisions are now av

450

Coalbed Methane Reserves Revision Increases  

Gasoline and Diesel Fuel Update (EIA)

1,563 2,589 2,071 2009-2011 1,563 2,589 2,071 2009-2011 Federal Offshore U.S. 0 0 0 2009-2011 Pacific (California) 0 0 0 2009-2011 Louisiana & Alabama 0 0 0 2009-2011 Texas 0 0 0 2009-2011 Alaska 0 0 0 2009-2011 Lower 48 States 1,563 2,589 2,071 2009-2011 Alabama 17 134 23 2009-2011 Arkansas 3 9 0 2009-2011 California 0 0 0 2009-2011 Coastal Region Onshore 0 0 0 2009-2011 Los Angeles Basin Onshore 0 0 0 2009-2011 San Joaquin Basin Onshore 0 0 0 2009-2011 State Offshore 0 0 0 2009-2011 Colorado 126 937 698 2009-2011 Florida 0 0 0 2009-2011 Kansas 8 157 24 2009-2011 Kentucky 0 0 0 2009-2011 Louisiana 0 0 0 2009-2011 North 0 0 0 2009-2011 South Onshore 0 0 0 2009-2011 State Offshore 0 0 0 2009-2011 Michigan 0 0 0 2009-2011 Mississippi 0 0 0 2009-2011

451

Executive Director for Operations REVISION OF NUREG-0654, SUPPLEMENT 3, CRITERIA FOR PROTECTIVE ACTION RECOMMENDATIONS FOR SEVERE  

E-Print Network (OSTI)

The purpose of this paper is to seek Commission approval to revise Nuclear Regulatory Commission (NRC) protective action recommendation (PAR) guidance contained in NUREG-0654, Supplement 3 to reflect the results of NUREG/CR-6953, Vol. 1, Review of

Luis A. Reyes

2007-01-01T23:59:59.000Z

452

Environmental Monitoring Plan, Revision 6  

SciTech Connect

The purpose of environmental monitoring is to promote the early identification of, and response to, potential adverse environmental impacts associated with Lawrence Livermore National Laboratory (LLNL) operations. Environmental monitoring supports the Integrated Safety Management System (ISMS), International Organization for Standardization (ISO) 14001 Environmental Management Systems standard, and U. S. Department of Energy (DOE) Order 458.1, Radiation Protection of the Public and the Environment. Specifically, environmental monitoring enables LLNL to detect, characterize, and respond to releases from LLNL activities; assess impacts; estimate dispersal patterns in the environment; characterize the pathways of exposure to members of the public; characterize the exposures and doses to individuals and to the population; and to evaluate the potential impacts to the biota in the vicinity of LLNL. Environmental monitoring is also a major component of compliance demonstration for permits and other regulatory requirements. The Environmental Monitoring Plan (EMP) addresses the sample collection and analytical work supporting environmental monitoring to ensure the following: (1) A consistent system for collecting, assessing, and documenting environmental data of known and documented quality; (2) A validated and consistent approach for sampling and analysis of samples to ensure laboratory data meets program-specific needs and requirements within the framework of a performance-based approach for analytical laboratory work; and (3) An integrated sampling approach to avoid duplicative data collection. LLNL prepares the EMP because it provides an organizational framework for ensuring that environmental monitoring work, which is integral to the implementation of LLNL's Environmental Management System, is conducted appropriately. Furthermore, the Environmental Monitoring Plan helps LLNL ensure compliance with DOE Order 231.1 Change 2, Environment, Safety and Health Reporting, which require the publication of an annual report that characterizes the site's environmental management performance. To summarize, the general regulatory drivers for this environmental monitoring plan are ISO 14001, DOE Order 458.1, and DOE Order 231.1. The environmental monitoring addressed by this plan includes preoperational characterization and assessment, effluent and surveillance monitoring, and permit and regulatory compliance monitoring. Additional environmental monitoring is conducted at LLNL as part of compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, also known as Superfund). LLNL coordinates its ground water surveillance monitoring program with the CERCLA monitoring program to gain sampling efficiencies.

Gallegos, G M; Bertoldo, N A; Blake, R G; Campbell, C G; Grayson, A R; Nelson, J C; Revelli, M A; Rosene, C A; Wegrecki, T; Williams, R A; Wilson, K R; Jones, H E

2012-03-02T23:59:59.000Z

453

NEPA Lessons Learned December 2011 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 1 1 1 The Department of Energy (DOE) has revised its National Environmental Policy Act (NEPA) Implementing Procedures (10 CFR Part 1021) to better align them with current DOE missions and improve the efficiency and transparency of its environmental reviews. The revisions focus on the categorical exclusion provisions. Since DOE last revised its categorical exclusions 15 years

454

1  

National Nuclear Security Administration (NNSA)

56 56 Page 2 of 2 The purpose of this modification is to revise and replace the following: A. Part I, Section H, Clause H-6, Parent Organization's Oversight Plan, Paragraph (c), the first sentence is deleted and replaced with the following: The estimated cost for the Parent Organization's Oversight Plan for FY11 (October 1, 2010 - September 30, 2011) is NTE $2,599,106.00. B. Part I, Section H, Clause H-31, Service Contract Act of 1965 (41 U.S.C. 351), is replaced with: H-31 SERVICE CONTRACT ACT OF 1965 (41 U.S.C. 351) The Service Contract Act of 1965 is not applicable to this contract. However, in accordance with the Section I Clause DEAR 970.5244-1, entitled, "Contractor Purchasing

455

MESON LISTINGS UNDER REVISION (FOR ENCODERS)  

NLE Websites -- All DOE Office Websites (Extended Search)

MESON LISTINGS UNDER REVISION MESON LISTINGS UNDER REVISION (FOR ENCODERS) This WWW page is designed so that encoders can get current Listings of encoded particles with the 'NODES' on the right-hand side of the page. Disclaimer These sections are private PDG files. Please do not quote or refer to them. The authors reserve the right to radically alter these non-completed sections from minute to minute. They are certainly not error free. Conservation Laws The List by Particle Code (includes hidden particle codes) The List in Book Order by Name Light Unflavored Mesons Summary Table Other Light Unflavored Mesons Strange Mesons Summary Table Charmed Mesons Summary Table Charmed, Strange Mesons Summary Table (c cbar) Mesons Summary Table (b bbar) Mesons Summary Table Non (q qbar) Candidates

456

Revisions to Energy Efficiency Enforcement Regulations  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6450-01-P 6450-01-P DEPARTMENT OF ENERGY 10 CFR Parts 430 and 431 Docket No. EERE-2010-BT-CE-0014 RIN 1904-AC23 Revisions to Energy Efficiency Enforcement Regulations AGENCY: Office of Energy Efficiency and Renewable Energy and Office of the General Counsel, Department of Energy. ACTION: Request for Information (RFI); request for comment. SUMMARY: The U.S. Department of Energy (DOE or the "Department") intends to expand and revise its existing energy efficiency enforcement regulations for certain consumer products and commercial and industrial equipment covered under the Energy Policy and Conservation Act of 1975, as amended (EPCA or the "Act"). These regulations provide for manufacturer submission of compliance statements and

457

Last Revised: 7/23/10 (Gades  

NLE Websites -- All DOE Office Websites (Extended Search)

Revised: 7/23/10 (Gades) Revised: 7/23/10 (Gades) Instructions for Requesting Dry Ice at the APS Dry Ice requests are handled by APS Detector Pool staff. Dry ice should be requested through the Detector Pool database, similar to how detectors are requested. Dry ice is only available during normal business hours. Since dry ice must be obtained from a building other than the APS, requests must be made in advance to ensure availability of a government vehicle for transporting dry ice. Access the Detector Pool database via the link below. Requestors will be taken to a log-in page similar to the log-in page for the ESAF system. https://beam.aps.anl.gov/pls/apsweb/wam0002.dds_main_menu The page can also be found on the Optics and Detector Group homepage (the "Submit a Detector

458

New York Natural Gas Summary  

Gasoline and Diesel Fuel Update (EIA)

8.85 8.94 4.21 4.65 1967-2010 8.85 8.94 4.21 4.65 1967-2010 Imports 7.43 9.36 4.67 5.43 4.96 3.83 1989-2012 Exports 12.07 -- -- -- 4.69 3.61 1999-2012 Pipeline and Distribution Use 1967-2005 Citygate 9.02 10.07 7.35 6.86 6.04 5.35 1984-2012 Residential 15.73 16.78 15.05 14.04 13.71 12.97 1967-2012 Commercial 11.82 12.86 10.72 10.88 9.32 7.84 1967-2012 Industrial 11.43 12.30 9.52 8.55 8.18 6.92 1997-2012 Vehicle Fuel 13.45 18.54 11.87 8.32 9.81 21.00 1990-2012 Electric Power 8.09 10.85 5.26 5.73 5.56 3.95 1997-2012 Dry Proved Reserves (Billion Cubic Feet) Proved Reserves as of 12/31 376 389 196 281 253 1977-2011 Adjustments 33 -11 -84 104 -22 1977-2011 Revision Increases 46 72 39 35 48 1977-2011 Revision Decreases 45 47 59 83 50 1977-2011

459

EPRI Materials Degradation Matrix, Revision 3  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) Materials Degradation Matrix (MDM) identifies knowledge gaps associated with degradation phenomena that may detrimentally affect reactor operation, reactor safety, or regulatory climate. Where gaps are identified, the MDM assesses the status of research and development (R&D) needed to resolve the knowledge gap. In addition to a general update to address new operating experience and research results, specific objectives for this revision of the MDM ...

2013-05-30T23:59:59.000Z

460

Revision Policy for EIA Weekly Underground Natural Gas Storage Estimates  

Weekly Natural Gas Storage Report (EIA)

September 23, 2013 September 23, 2013 This report consists of the following sections: General EIA Weekly Natural Gas Storage Report Revisions Policy - a description of how revisions to the Weekly Natural Gas Storage Report estimates may occur EIA Weekly Natural Gas Storage Report Policy to Allow Unscheduled Release of revisions - a description of the policy that will be implemented in the event of an out-of-cycle release Revisions to the Historical Database - a description of how revisions will be noted in the Historical database The U.S. Energy Information Administration (EIA) is announcing changes Revisions may be presented for the most recent estimates of working gas in storage under a number of circumstances that occur after release of the estimates. These include: I. A respondent revises previously submitted data (respondents are

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