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1

Lajos Grof-Tisza | Department of Energy  

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

Lajos Grof-Tisza Lajos Grof-Tisza About Us Lajos Grof-Tisza - Director, Office of Corporate Information Systems Lajos Grof-Tisza Mr. Lajos Grof-Tisza joined the Department of Energy in 2003 and currently serves as the Director of Corporate Information Systems. As the Director of Corporate Information Systems, Mr. Grof-Tisza is responsible for planning and managing the design, development, operation and maintenance of the Department's Integrated Management Navigation (iManage) program and projects; identify and implement business process automation initiatives; provide technical support for legacy systems operations and maintenance; provide technical support for web design, development and maintenance; manage cyber security and enterprise architecture activities; and serve as

2

Appendix 7 - Stripes Architecture Overview  

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

Name: Department of Energy iManage Program Name: Department of Energy iManage Program Project ID: iManage Program STRIPES Project Project Manager: Mathew Sparks Program Mgr: Lajos Grof-Tisza Doc ID: STRIPES Technical Architecture Page i 8/30/2012 U.S. Department of Energy Office of the Chief Financial Officer iManage Strategic Integrated Procurement Enterprise System STRIPES Technical Architecture Overview Status of Document Draft Delivered Accepted Program Name: Department of Energy iManage Program Project ID: iManage Program STRIPES Project Project Manager: Mathew Sparks Program Mgr: Lajos Grof-Tisza Doc ID: STRIPES Technical Architecture Page ii 8/30/2012 Title Page Document Name: Strategic Integrated Procurement Enterprise System (STRIPES) Technical Architecture Overview

3

Appendix 8 - iManage Change Management Standards  

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

Appendix 8 iManage Change Management Standards Department of Energy Deliverable ID: PM1001 Version number: 1.0 Draft/Final as of: 7/23/2012 Printed on: 27 Jul 2012 Author: Michael Preis Michael.Preis@hq.doe.gov (301)903-3812 Owner: Lajos Grof-Tisza, iManage Program Manager Status of Document Draft Delivered Accepted Program Name: Department of Energy iManage Program Project ID: iManage Configuration Management Plan Program Mgr: Lajos Grof-Tisza Doc ID: PM1001 Draft ii Document information Document source This document is maintained as an online document. Contact the author for the latest version. Revision history Version number Date Summary of changes Revised By 1.00 26 Feb 2007 Initial Version Michael Preis Approvals

4

CLASSIFICATION OF THE MGR HEALTH SAFETY SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) health safety system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

J.A. Ziegler

1999-08-31T23:59:59.000Z

5

CLASSIFICATION OF THE MGR CARRIER/CASK TRANSPORT SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) carrier/cask transport system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

S.E. Salzman

1999-08-30T23:59:59.000Z

6

CLASSIFICATION OF THE MGR SITE COMPRESSED AIR SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site compressed air system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

J.A. Ziegler

1999-08-31T23:59:59.000Z

7

CLASSIFICATION OF THE MGR SUBSURFACE ELECTRICAL DISTRIBUTION SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) subsurface electrical distribution system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333PY ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

R.J. Garrett

1999-08-31T23:59:59.000Z

8

CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING ELECTRICAL SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building electrical system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

S.E. Salzman

1999-08-31T23:59:59.000Z

9

CFO.pdf  

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

Financial Officer Financial Officer Vacant CF-1 Deputy Chief Financial Officer Alison Doone Asst. Deputy Chief Financial Officer Penny Mefford CF-2 Office of the Chief Financial Officer October 2013 Office of Finance and Accounting Joanne Choi, Director CF-10 Office of Budget Christopher Johns, Director CF-30 Office of Corporate Information Systems Lajos Grof-Tisza, Director CF-40 Office of Financial Risk, Policy & Controls April Stephenson, Director CF-50 Energy Finance and Accounting Service Center Jared Martin, Director CF-11 Office of Financial Control and Reporting Vacant, Director CF-12 Office of Finance and Accounting October 2013 Office of Finance and Accounting Joanne Choi, Director CF-10 Office of Budget Christopher Johns Director CF-30 Budget Analysis Deputy Director CF-31 Budget Operations

10

CLASSIFICATION OF THE MGR SITE ELECTRICAL POWER SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality As.surance (QA) classification of the Monitored Geologic Repository (MGR) site fire protection system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998b).

J.A. Ziegler

1999-08-31T23:59:59.000Z

11

iManage Presentation | Department of Energy  

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

iManage Presentation iManage Presentation TuesdayDallasBallroomD1425Grof-Tisza.pdf More Documents & Publications Request for Information - Operations and Maintenance (O & M)...

12

Leo Sain President & Proj Mgr UCOR July 10 2012 SB Summit  

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

Safely Delivering the Department of Energy's Vision Safely Delivering the Department of Energy's Vision for the East Tennessee Technology Park Mission Small Business Overview Leo Sain, President and Project Manager July 10, 2012 Safely Delivering DOE's Vision for the East Tennessee Technology Park Mission UCOR Overview * UCOR is DOE's Environmental Management contractor for cleanup work on the Oak Ridge Reservation. * Our major project is demolition of the K-25 Building (to be completed in the summer of 2014). * Contract Information - Size - $2.3 Billion - Partners: URS Energy & Construction, Inc. (primary) and CH2M HILL Constructors, Inc. - Contract duration  August 1, 2011, through July 31, 2016  4 Option Contract Line Items that could extend contract to July 31, 2020 K-25 Demolition Safely Delivering DOE's Vision for the

13

Leo Sain President & Proj Mgr UCOR July 10 2012 SB Summit  

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

* Safely shipped more than 10,000 loads of waste from K-25 demolition * Placed six Poplar Creek facilities into a "cold and dark" state * Established ETTP as one of the leaders...

14

2006  

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

Big Sky Carbon Sequestration Partnership Contacts: DOENETL Project Mgr. Name Organization E-Mail David Lang NETL lang@netl.doe.gov Principal Investigator Lee Spangler Field Test...

15

Hydrogen, Fuel Cells, and Infrastructure Technologies Program...  

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

incentives available - target CFOfacility mgr Educate utilitiesPUC Develop hydrogen and CNG blend-fired generators Co-market and encourage available fuel cell products in...

16

2006  

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

FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name West Coast Regional Carbon Sequestration Partnership (WESTCARB) Contacts: DOENETL Project Mgr. Name Organization...

17

Scott Pigg  

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

Pigg Principal Project Mgr. Energy Center of Wisconsin NOTICE Due to the current lapse of federal funding, Berkeley Lab websites are accessible, but may not be updated until...

18

Anne Pellegrino  

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

Pellegrino Mgr., Energy Efficiency Policy Section Dept. of Industry, Tourism & Resources (DITR) Australian Government This speaker was a visiting speaker who delivered a talk or...

19

Microsoft Word - JAS-WillistonBasin-Oct09  

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

EOR Field Test 1 FACT SHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase II Contacts: DOENETL Project Mgr. Name...

20

2006  

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

Enhanced Coalbed Methane Test 1 FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Midwest Geological Sequestration Consortium Contacts: DOENETL Project Mgr. Name...

Note: This page contains sample records for the topic "mgr lajos grof-tisza" 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

Microsoft Word - JAS-Williston Basin Demo Test.doc  

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

Demonstration Test 1 FACT SHEET FOR PARTNERSHIP DEMONSTRATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase III Contacts: DOENETL Project Mgr. Name...

22

SWP.SanJuanBasin.factsheet0919  

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

FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Southwest Regional Partnership on Carbon Sequestration Contacts: DOENETL Project Mgr. Name Organization E-Mail...

23

Nuclear Engineering Division of Argonne National Laboratory...  

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

Director Tom Ewing, Associate Director Robert N. Hill, Technical Director Research & Test Reactor John Stevens, Department Mgr Nuclear Systems Analysis Temitope Taiwo,...

24

Comments Received on SP 800-131: Recommendation for ...  

Science Conference Proceedings (OSTI)

... Jim Knoke Lab Mgr and CC Evaluator, Security Evaluation Lab (SEL) Lab ... This may deter vendors from further investment and delay the availability ...

2012-05-07T23:59:59.000Z

25

Event Speakers List  

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

Naboni Guest Scientist Lawrence Berkeley National Laboratory David Najewicz Mgr GE Appliances Ram Narayanamurthy Chief Science Officer Satish Narayanan Project Leader UTRC Robert...

26

Boston College Facilities Management Summer Projects 2013  

E-Print Network (OSTI)

# Building / Location Project Description Resp Mgr Project Mgr 1 8131515 2000 Comm Ave Cooling Towers : This project completes this phase of the renewal of 2000 Commonwealth Ave with cooling tower upgrades. Mike split system for the UPS room. Terence Leahy Terence Leahy 9 8141205 Carney Hall Cooling Tower Upgrades

Huang, Jianyu

27

IN MEMORIAM PAUL ERD OS (1913-1996)  

E-Print Network (OSTI)

'antibiotiques : pleur´eesie s´eev`eere. Il s'approche du lit, et parle (trop) fort : -- Au revoir, Monsieur, j'ai laiss'ombre. Paul Erdos est n´ee `aa Budapest le 26 mars 1913, dans une famille juive. Son p`eere, Lajos, et sa m`eere demandera, bien plus tard, s'il a jamais ´eet´ee tent´ee par le mariage il r´eepondra : Mon caract`eere est

Tenenbaum, Gérald - Institut de Mathématiques ?lie Cartan, Université Henri Poincaré

28

Sylvia Williams  

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

Sylvia Williams Bus. Development Mgr. Global GTL Development, Shell International Gas, Ltd., UK This speaker was a visiting speaker who delivered a talk or talks on the date(s)...

29

Dennis Symanski  

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

Committee EMergeSr. Project Mgr Energy Efficiency Program, Power Utilization Sector, EPRI This speaker was a visiting speaker who delivered a talk or talks on the date(s) shown...

30

David Najewicz  

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

Portrait Not Available David Najewicz Mgr External Technology Program GE Appliances David.Najewicz@ge.com This speaker was a visiting speaker who delivered a talk or talks on the...

31

RESPONSE TRACKING INFORMATION BEH W.Wagner BPM M. Redmon BPM  

Office of Legacy Management (LM)

RESPONSE RESPONSE TRACKING INFORMATION BEH W.Wagner BPM M. Redmon BPM . Palau BPM P. Huber BPM S. Priest BPM BCR BFC ENVIR TECH/DATA BET ENGINEERING BET GEOTE~ BET DEPUTY PROGRAM MGR.: P. Crotwell BPM PROGRAM MANAGER: R. Harbert BPM PROJECT MANAGER: COMMUNITY RELATIONS CONSTRUCTION ENGINEERING & TECHNOLOGY BET ENVIRON SAFETY & HEALTH F~~-~~~~-~-~---+-r~-~ W/A W/O K. Renfro SAIC J. Waddell SAIC S. Heptinstall SAIC DEPUTY PROGRAM MGR: T. Patlerson SAIC PROGRAM MANAGER: MGMT. SYSTEMS: SECRETARY: AFFECTED DOCUMENT _ ""')::~ 119033 ,..,::.().: CCN: ..t.:;,;;..:.=..:..:..;:.,.;;.;.:.;~;.;:....c",-,-~~~~ lli::JSRAP COMMUNICATIONS DISTRIBUTION FSRD C¥J COMM TYPE ,-,,-1e<~..::........L---J DOE/ORO FORMER SITES RESTORATION

32

Slide 1  

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

Bookshelves Lab Mgr. 12 Rack Bays, 1m Deep Bookshelves Workbench Cooper 5 MVA PEAK Transformer 23,700 lbs. 54 ft. 8.0 in. x 41 ft. Room 27 ft. 4.0 in. x 23 ft. 8.0 in. Room...

33

AN OPTIMIZED TWO-CAPACITY ADVANCED ELECTRIC HEAT PUMP S. E. Veyo, Manager, Heat Exchange Systems Research  

E-Print Network (OSTI)

exchanger, comfort. #12;AN OPTIMIZED TWO-CAPACITY ADVANCED ELECTRIC HEAT PUMP S. E. Veyo* ABSTRACT A two constrained optimization procedure was used to select heat exchanger proportions, air flow rates National Laboratory. * S. E. Veyo, Mgr., Heat Exchange Systems, Westinghouse R&D Center, Pittsburgh, PA

Oak Ridge National Laboratory

34

Transient Responses in Ecosystem Free-air CO2 Enrichment  

SciTech Connect

OAK - 270 There is no final report on this grant, P.I. has transferred from DRI to the Univ. of Oklahoma. Per the Doe Project Officer - Roger C. Dahlman, PhD he agrees to waive the report because of such a short period of funding. Waiver from DOE Project Mgr attached to closeout file.

Yiai Lou

2002-10-23T23:59:59.000Z

35

Traffic and Transportation Committee Summary of Meeting Notes  

E-Print Network (OSTI)

Traffic and Transportation Committee Summary of Meeting Notes March 31, 2006 ­ 1:30pm ­ 1210 Annex Young Salt Lake City - Transportation Tim Harpst Salt Lake City - Transportation Dan Bergenthal Salt Lake City - Transportation Robin Carbaugh Yalecrest Neighborhood Council Hal Johnson UTA-Mgr. BRT

Capecchi, Mario R.

36

2010 Annual Workforce Analysis and Staffing Plan Report - SR  

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

OOEF Jl2$U OOEF Jl2$U United States Government Department of Energy (DOE) memorandum Savannah River Operations Office (SR) DATE: REPLY TO ATTN OF: SUBJECT: JAN 2 6 2011 MGR (Moody/(803) 952-9468) Annual Workforce Analysis and Staffing Plan Report for Calendar Year 2010- 10-NA SC-09 TO: Karen L. Boardman, Chairperson, Federal Technical Capability Panel The Calendar Year 2010 DOE-SR Workforce Analysis and Staffing Plan Report is attached. This analysis was conducted in conjunction with the development of the DOE-SR 5-Year Workforce Management Plan. If you have any questions, please contact me or have your staff contact Mr. Edgar Gates at 803-952-9227 or Mr. Lee Moody at 803-952-5978. MGR:LHM:bcp OHCM-11-1053 Attachment: DOE-SR Annual Workforce Analysis and Staffing Plan Report

37

2012 Annual Workforce Analysis and Staffing Plan Report - SR  

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

lllS.81 lllS.81 United States Government Department of Energy (DOE\ memorandum Savannah River Operations Office (SR) DATE: REPLY TO ATINOF: FEB 132811: MGR (Moody/(803) 952-9468) SUBJECT: Annual Workforce Analysis and Staffing Plan Report for Calendar Year 2012 To: Karen L. Boardman, Chairperson, Federal Technical Capability Panel The Calendar Year 2012 DOE-SR Workforce Analysis and Staffing Plan Report is attached. This analysis was conducted in conjunction with the development of the DOE-SR 5-Y ear Workforce Management Plan. If you have any questions, please contact me or have your staff contact Mr. Edgar Gates at 803-952-9227 or Mrs. Deanna Yates at 803-952-6925. MGR:EG:lec OHCM-13-0025 Attachment: DOE-SR Annual Workforce Analysis and Staffing Plan Report

38

2011 Annual Workforce Analysis and Staffing Plan Report - SR  

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

# # United States Government Department of Energy (DOE) memorandum Savannah River Operations Office (SR) DATE: REPLY TO ATTN OF: SUBJECT: JAN 2 O 2012 MGR (Moody/(803) 952-9468) Annual Workforce Analysis and Staffing Plan Report for Calendar Year 2011 - 10-NA SC-09 TO: Karen L. Boardman, Chairperson, Federal Technical Capability Panel The Calendar Year 2011 DOE-SR Workforce Analysis and Staffing Plan Report is attached. This analysis was conducted in conjunction with the development of the DOE-SR 5-Year Workforce Management Plan. If you have any questions, please contact me or have your staff contact Mr. Edgar Gates at 803-952-9227 or Mr. Lee Moody at 803-952-5978. MGR:EG:bcp OHCM-12-1035 Attachment: DOE-SR Annual Workforce Analysis and Staffing Plan Report

39

STEM, Innovation and Bio-Rad: Common Links  

E-Print Network (OSTI)

STEM, Innovation and Bio-Rad: Common Links Feb. 10, 2012 Laurie Usinger, PhD BioEducation Business Unit Mgr. laurie_usinger@bio-rad.com 510-741-6665 Erika Fong Laurie Laurie Usinger #12;Bio Bio: · Bay ­Postdoctoral Fellow (Beth Burnside) · Bio-Rad ­Life Science Group #12;First Thoughts? #12;Fortuitous Entry · 81

Hammock, Bruce D.

40

Light-Emitting Tag Testing in Conjunction with Testing of the Minimum Gap Runner Turbine Design at Bonneville Dam Powerhouse 1  

DOE Green Energy (OSTI)

This report describes a pilot study conducted by Tom Carlson of PNNL and Mark Weiland of MEVATEC Corp to test the feasibility of using light-emitting tags to visually track objects passing through the turbine environment of a hydroelectric dam. Light sticks were released at the blade tip, mid-blade, and hub in the MGR turbine and a Kaplan turbine at Bonneville Dam and videotaped passing thru the dam to determine visibility and object trajectories.

Carlson, Thomas J

2001-01-30T23:59:59.000Z

Note: This page contains sample records for the topic "mgr lajos grof-tisza" 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

Monitored Geologic Repository Project Description Document  

SciTech Connect

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the Yucca Mountain Site Characterization Project Requirements Document (YMP RD) (YMP 2001a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).

P. Curry

2001-06-26T23:59:59.000Z

42

SWP.phase3factsheet0919  

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

Deep Saline Deployment Project 1 Deep Saline Deployment Project 1 FACTSHEET FOR SOUTHWEST PARTNERSHIP FIELD VALIDATION TEST Partnership Name Southwest Regional Partnership on Carbon Sequestration Contacts: DOE/NETL Project Mgr. Name Organization E-Mail William O'Dowd NETL William.ODowd@NETL.DOE.GOV 1-412-386-4778 Principal Investigator Reid Grigg/Brian McPherson NMT reid@prrc.nmt.edu / brian@nmt.edu Field Test Information: Field Test Name Southwest Deep Saline Sequestration Test Location Farnham Dome near Price, Utah Amount and Source of CO 2 Tons Source

43

Microsoft Word - Cropland P2.doc  

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

7.0 Cropland Field Validation Test 1 7.0 Cropland Field Validation Test 1 FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Big Sky Carbon Sequestration Partnership Contacts: DOE/NETL Project Mgr. Name Organization E-Mail David Lang NETL Lang@netl.doe.gov Principal Investigator Lee Spangler Field Test Information: Field Test Name Cropland Field Validation (+ remote sensing work) Test Location North central Montana Amount and Source of CO 2 Tons Source: atmosphere Field Test Partners (Primary Sponsors) Washington State University, Montana State University, Los Alamos National Lab Summary of Field Test Site and Operations:

44

Microsoft PowerPoint - EastBend_NETL Meeting_Nov 18_ 2009 MK_rev2.ppt  

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

II CO II CO 2 Sequestration Test Cincinnati Arch MRCSP Site for: Regional Carbon Sequestration Partnerships Annual Review November 16-19, 2009 by: Mark E. Kelley, P.G. (Battelle) 2 Acknowledgements - Traci Rodosta, DOE/NETL Program Mgr - Darlene Radcliffe, Duke Energy, Director, Environmental Technology & Fuel Policy - Brian Weisker, Plant Manger for Duke Energy East Bend Station - Joe Clark, Technical Manager, Duke Energy East Bend Station - Kentucky Geological Survey (Steve Greb and others) - Indiana Geological Survey (John Rupp and others) - Ohio Geological Survey (Larry Wickstrom and others) - Bill Rike Consulting Geologist - Sarah Wade, AJW Incorporated - Battelle Staff - Dave Ball (Program Manager), Neeraj Gupta (Technical Advisor), Matt Place (Field Lead), Linc Remmert,

45

SWP.terrestrial.factsheet0919  

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

FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Southwest Regional Partnership on Carbon Sequestration Contacts: DOE/NETL Project Mgr. Name Organization E-Mail William O'Dowd NETL William.odowd@netl.doe.gov Principal Investigator Reid Grigg / Brian McPherson NMT reid@prrc.nmt.edu / brian@nmt.edu Field Test Information: Field Test Name Terrestrial Sequestration Programs - Regional Terrestrial and Local Terrestrial Sequestration (Combined With Enhanced Coalbed Methane Sequestration) Test Location Entire Region (Regional Program); San Juan Basin (Local Pilot Test) Amount and Source of CO 2

46

Microsoft Word - Basalt Pilot Phase II Fact Sheet FY08  

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

16.0 Basalt Pilot 1 16.0 Basalt Pilot 1 FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Big Sky Regional Carbon Partnership Contacts: DOE/NETL Project Mgr. Name Organization E-Mail David Lang NETL LANG@netl.doe.gov Principal Investigator Lee Spangler Field Test Information: Basalt Sequestration Pilot Test Test Location Near Wallula township in Eastern Washington State Amount and Source of CO 2 Tons Source 3000 Refinery Field Test Partners (Primary Sponsors) Pacific Northwest National Lab - Pacific Northwest Division, Idaho

47

2006  

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

Enhanced Coalbed Methane Test 1 Enhanced Coalbed Methane Test 1 FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Midwest Geological Sequestration Consortium Contacts: DOE/NETL Project Mgr. Name Organization E-Mail John Litynski NETL John.Litynski@netl.doe.gov Principal Investigator Robert J. Finley Illinois State Geological Survey finley@isgs.uiuc.edu Field Test Information: Field Test Name Task 7: Enhanced Coalbed Methane Test Location NE NW Sec.27, T1S, R14W, western Wabash County, IL Amount and Source of CO 2 Tons Source 750 (budgeted) Air Liquide (refinery or ethanol plant)

48

Dose Calculations for the Co-Disposal WP-of HLW-Glass and the Triga SNF  

SciTech Connect

This calculation is prepared by the Monitored Geologic Repository (MGR) Waste Package Operations (WPO). The purpose of this calculation is to determine the surface dose rates of a codisposal waste package (WP) containing a centrally located Department of Energy (DOE) standardized 18-in. spent nuclear fuel (SNF) canister, loaded with the TRIGA (Training, Research, Isotopes, General Atomics) SNF. This canister is surrounded by five 3-m long canisters, loaded with Savannah River Site (SRS) high-level waste (HLW) glass. The results are to support the WP design and radiological analyses.

G. Radulescu

1999-08-02T23:59:59.000Z

49

ENRICO FERMI FAST REACTOR SPENT NUCLEAR FUEL CRITICALLY CALCULATIONS: INTACT MODE  

SciTech Connect

The purpose of this calculation is to perform intact mode and partially degraded mode criticality evaluations of the Department of Energy's (DOE) Enrico Fermi (EF) Spent Nuclear Fuel (SNF) co-disposed in a 5 Defense High-Level Waste (5-DHLW) Waste Package (WP) and emplaced in a Monitored Geologic Repository (MGR). The criticality evaluations estimate the values of the effective neutron multiplication factor, k{sub eff}, a measure of nuclear criticality potential, for the 5-DHLW/DOE SNF WP with intact or partially degraded internal configurations. These evaluations contribute to the WP design.

A.S. Mobasheran

1999-04-12T23:59:59.000Z

50

BSCSP Basalt Pilot Phase II Factsheet 2009  

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

Basalt Sequestration Pilot Test 1 Basalt Sequestration Pilot Test 1 FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Big Sky Regional Carbon Partnership Contacts: DOE/NETL Project Mgr. Name Organization E-Mail William Aljoe NETL William.Aljoe@netl.doe.gov Principal Investigator Lee Spangler Field Test Information: Field Test Name Basalt Sequestration Pilot Test Test Location Near Wallula township in Eastern Washington State Amount and Source of CO 2 Tons Source 1000 Refinery Field Test Partners (Primary Sponsors) Boise White Paper L.L.C., Shell Exploration and Production Company, Port of Walla Walla,

51

Microsoft Word - BB-Terrestrial.doc  

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

PCOR Terrestrial Field Validation Test PCOR Terrestrial Field Validation Test 1 FACT SHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase II Contacts: DOE/NETL Project Mgr. Name Organization E-Mail Darin Damiani, U.S. Department of Energy, Darin.Damiani@netl.doe.gov Principal Investigator Edward Steadman Field Test Information: Field Test Name PCOR Terrestrial Field Validation Test Test Location North Dakota, South Dakota, Minnesota, Montana, Iowa Amount and Source of CO 2 Tons N/A Source Atmospheric CO 2 Ducks Unlimited, Inc. U.S. Geological Survey Northern Prairie Wildlife Research Center Field Test Partners (Primary Sponsors) North Dakota State University

52

SUBSURFACE EMPLACEMENT TRANSPORTATION SYSTEM  

SciTech Connect

The objective of this analysis is to identify issues and criteria that apply to the design of the Subsurface Emplacement Transportation System (SET). The SET consists of the track used by the waste package handling equipment, the conductors and related equipment used to supply electrical power to that equipment, and the instrumentation and controls used to monitor and operate those track and power supply systems. Major considerations of this analysis include: (1) Operational life of the SET; (2) Geometric constraints on the track layout; (3) Operating loads on the track; (4) Environmentally induced loads on the track; (5) Power supply (electrification) requirements; and (6) Instrumentation and control requirements. This analysis will provide the basis for development of the system description document (SDD) for the SET. This analysis also defines the interfaces that need to be considered in the design of the SET. These interfaces include, but are not limited to, the following: (1) Waste handling building; (2) Monitored Geologic Repository (MGR) surface site layout; (3) Waste Emplacement System (WES); (4) Waste Retrieval System (WRS); (5) Ground Control System (GCS); (6) Ex-Container System (XCS); (7) Subsurface Electrical Distribution System (SED); (8) MGR Operations Monitoring and Control System (OMC); (9) Subsurface Facility System (SFS); (10) Subsurface Fire Protection System (SFR); (11) Performance Confirmation Emplacement Drift Monitoring System (PCM); and (12) Backfill Emplacement System (BES).

T. Wilson; R. Novotny

1999-11-22T23:59:59.000Z

53

ESF Mine Power Center Platforms  

SciTech Connect

The purpose and objective of this analysis is to structurally evaluate the existing Exploratory Studies Facility (ESF) mine power center (MPC) support frames and to design service platforms that will attach to the MPC support frames. This analysis follows the Development Plan titled ''Produce Additional Design for Title 111 Evaluation Report'' (CRWMS M&O 1999a). This analysis satisfies design recommended in the ''Title III Evaluation Report for the Surface and Subsurface Power System'' (CRWMS M&O 1999b, Section 7.6) and concurred with in the ''System Safety Evaluation of Title 111 Evaluation Reports Recommended Work'' (Gwyn 1999, Section 10.1.1). This analysis does not constitute a level-3 deliverable, a level-4 milestone, or a supporting work product. This document is not being prepared in support of the Monitored Geologic Repository (MGR) Site Recommendation (SR), Environmental Impact Statement (EIS), or License Application (LA) and should not be cited as a reference in the MGR SR, EIS, or LA.

T.A. Misiak

2000-02-10T23:59:59.000Z

54

CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

E.F. Loros

2000-06-23T23:59:59.000Z

55

Modeling for Airborne Contamination  

SciTech Connect

The objective of Modeling for Airborne Contamination (referred to from now on as ''this report'') is to provide a documented methodology, along with supporting information, for estimating the release, transport, and assessment of dose to workers from airborne radioactive contaminants within the Monitored Geologic Repository (MGR) subsurface during the pre-closure period. Specifically, this report provides engineers and scientists with methodologies for estimating how concentrations of contaminants might be distributed in the air and on the drift surfaces if released from waste packages inside the repository. This report also provides dose conversion factors for inhalation, air submersion, and ground exposure pathways used to derive doses to potentially exposed subsurface workers. The scope of this report is limited to radiological contaminants (particulate, volatile and gaseous) resulting from waste package leaks (if any) and surface contamination and their transport processes. Neutron activation of air, dust in the air and the rock walls of the drift during the preclosure time is not considered within the scope of this report. Any neutrons causing such activation are not themselves considered to be ''contaminants'' released from the waste package. This report: (1) Documents mathematical models and model parameters for evaluating airborne contaminant transport within the MGR subsurface; and (2) Provides tables of dose conversion factors for inhalation, air submersion, and ground exposure pathways for important radionuclides. The dose conversion factors for air submersion and ground exposure pathways are further limited to drift diameters of 7.62 m and 5.5 m, corresponding to the main and emplacement drifts, respectively. If the final repository design significantly deviates from these drift dimensions, the results in this report may require revision. The dose conversion factors are further derived by using concrete of sufficient thickness to simulate the drift walls. The gamma-ray scattering properties of concrete are sufficiently similar to those of the host rock and proposed insert material; use of concrete will have no significant impact on the conclusions. The information in this report is presented primarily for use in performing pre-closure radiological safety evaluations of radiological contaminants, but it may also be used to develop strategies for contaminant leak detection and monitoring in the MGR. Included in this report are the methods for determining the source terms and release fractions, and mathematical models and model parameters for contaminant transport and distribution within the repository. Various particle behavior mechanisms that affect the transport of contaminant are included. These particle behavior mechanisms include diffusion, settling, resuspension, agglomeration and other deposition mechanisms.

F.R. Faillace; Y. Yuan

2000-08-31T23:59:59.000Z

56

Microsoft Word - JAS-Fort Nelson.doc  

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

Fort Nelson Demonstration Test Fort Nelson Demonstration Test 1 FACT SHEET FOR PARTNERSHIP DEMONSTRATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase III Contacts: DOE/NETL Project Mgr. Name Organization E-Mail Darin Damiani, U.S. Department of Energy, Darin.Damiani@netl.doe.gov Principal Investigator Edward Steadman Field Test Information: Field Test Name Fort Nelson Demonstration Test Test Location British Columbia, Canada Amount and Source of CO 2 Tons Approximately 1.2 million tons of CO 2 per year Source Fort Nelson natural gas-processing plant Spectra Energy Natural Resources Canada Field Test Partners (Primary Sponsors) British Columbia Ministry of Energy, Mines, and Petroleum Resources

57

u.s. DEPARn.'lENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERlVIINATION  

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

MC·EFl. MC·EFl. u.s. DEPARn.'lENT OF ENERGY EERE PROJECT MANAGEMENT CENTER NEPA DETERlVIINATION RECIPIENT:Clark County PROJECT TITLE: EECBG ~ WSU Building Upgrades & Resource Conservation Mgr Page 1 01'2 STATE: WA Funding Opportunity Announcement Number DE-FOA-0000013 Procurement Instrument Number NEPA Control Number CID Number DE-EE0000856 GFO-OOOO856-001 EEO Based on my review or the infonnation concerning the proposed action, as NEPA Compliance Officer (authoriud under DOE Order 451.1A), I have made the following determination: ex, EA, EIS APPENDIX AND NUMBER: Description: A11 Technical advice and planning assistance to international, national, state, and local organizations. 85.1 Actions to conserve energy, demonstrate potential energy conservation, and promote energy-efficiency that do not

58

Slide 1  

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

MA-50 MA-50 DOE/OECM 1 OECM PARS II Working Group: OA Module May 14, 2009 Created by: EES/Dekker PARS II Team 2 Agenda * User Roles with Screens Access Rights * Budget Screen (Revised) * Contacts/Certifications Screens * Gold Card Screen * Standard Reports 3 Roles (Group Names) * Federal Project Director (L4) * Deputy FPD (L4) * Program Point of Contact (L4) * Capital Program Manager (L3) * Program Office Manager (L2) * Program Manager (L1) * Program Analyst (L1) * Interested Party * OECM Senior Management * OECM Analyst * Alternate OECM Analyst * Acquisition Executive * Contracting Officer Representative * Contractor Project Mgr. (CPP) * Contractor Analyst (CPP) MA-50 DOE/OECM 3 PARS II Initiating a Capital Program MA-50 DOE/OECM 4 5. Capital Program Description* 2. Level 1: Program 3. Level 2: Program Office

59

SWP.SACROC.factsheet919  

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

M i d l a n d B a s i n Claytonville Pennsylvanian reef reservoirs Modified from Galloway, et al. (1983) SACROC LYNN G ARZA KENT STONEW ALL DA W SON TERRY HASKELL KNO X BO RDEN SCURRY FISHER JO NES T AYLO R NO LAN M ITCHELL HO W ARD MARTIN CO KE 0 20 mi 0 30 km QAd4569x Figure 1. Regional Location Map. FACTSHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Southwest Regional Partnership on Carbon Sequestration Contacts: DOE/NETL Project Mgr. Name Organization E-Mail William O'Dowd NETL William.ODowd@NETL.DOE.GOV Principal Investigator Reid Grigg / Brian McPherson NMT reid@prrc.nmt.edu / brian@nmt.edu Field Test Information: Field Test Name

60

Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode]  

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

i i h i h j Presentation Title Linac Coherent Light Source Project at the SLAC National Accelerator Laboratory Hanley Lee, Federal Project Director DOE Project Management Workshop j g p March 10, 2010 1 1.1 Management, Global Controls g 1.2 Injector 1.3 Linac F CLO Building N E i t H ll Far Experiment Hall Near Experiment Hall Far Experiment Hall Near Experiment Hall 2 LCLS Office of Science William Brinkman, Director Acquisition Executive Basic Energy Sciences Harriet Kung, Associate Dir. Tom Brown, LCLS Prog. Mgr. SLAC Site Office Paul Golan, Site Manager Hanley Lee FPD Hanley Lee, FPD Linac Coherent Light Source John Galayda, Project Director Mark Reichanadter, Deputy Proj. Dir. ES&H, QA Business, Admin 3 X-ray Transport Undulator Injector/Linac Conventional Facilities Instrument

Note: This page contains sample records for the topic "mgr lajos grof-tisza" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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61

Utility Data Collection Service  

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

Data Collection Service Data Collection Service Federal-Utility Partnership Working Group 4 May 2006 Paul Kelley, Chief of Operations, 78 th CES, Robins AFB David Dykes, Industrial Segment Mgr, Federal, GPC Topics  Background  Commodities Metered  Data Collection  Cost  Results Background  Robins AFB (RAFB) needed to:  Control electricity usage and considered Demand Control  Track and bill base tenants for energy usage  Metering Project Originated in 1993  $$ requirements limited interest  Developed criteria for available $$  Energy Policy Act 2005:  All facilities sub-metered by 2012  $$ no longer restricts metering project Metering Criteria prior to EPACT 2005  All New Construction - (per Air Force Instructions)

62

Working With Your Utility to Obtain Metering Services  

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

Dykes Dykes Federal Segment Mgr Georgia Power/Southern Company Wednesday, 22 May 2013 Federal Utility Partnership Working Group Spring 2013 - May 22-23 San Francisco, CA Hosted by: Pacific Gas and Electric Company  What is the Government Requirement ◦ New DoD Directive  What is Available from Your Serving Utility  Customer Metering Services  Issues to Consider  Conclusion 4.4 million customers 42,000+ MW 27,000 miles of transmission lines 3,700 substations 26,000 employees Other subsidiaries: Southern Linc, Southern Power, Southern Telecom, Southern Nuclear Retail Service Territory across 120,000 square miles  Section 103, EPAct 2005 - All Federal Agencies ◦ Meter electricity on all facilities 30,000 SqFt and larger ◦ Meter those facilities with significant energy usage

63

Document  

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

716 Federal Register 716 Federal Register / Vol. 76, No. 74 / Monday, April 18, 2011 / Notices Information Management and Privacy Services, Office of Management, invites comments on the submission for OMB review as required by the Paperwork Reduction Act of 1995 (Pub. L. 104-13). DATES: Interested persons are invited to submit comments on or before May 18, 2011. ADDRESSES: Written comments should be addressed to the Office of Information and Regulatory Affairs, Attention: Education Desk Officer, Office of Management and Budget, 725 17th Street, NW., Room 10222, New Executive Office Building, Washington, DC 20503, be faxed to (202) 395-5806 or e-mailed to oira_submission@omb.eop.gov with a cc: to ICDocketMgr@ed.gov. Please note that written comments received in response to this notice will be

64

Federal Technical Capability Panel Contacts list  

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

1 1 U. S. Department of Energy and National Nuclear Security Administration Federal Technical Capability Panel Organization Name Telephone Fax E-Mail FTCP CHAIR Chair (DOE/NTC) Karen L. Boardman (505) 845-6444 (505) 845-6079 kboardman@ntc.doe.gov FTCP Deputy Dave Chaney (505) 845-4300 (505) 845-4879 david.chaney@nnsa.doe.gov FTCP Technical Standards Mgr. Jeanette Yarrington (301) 903-7030 (301) 903-3445 Jeanette.Yarrington@hq.doe.gov FTCP Coordinator Patricia Parrish (505) 845-4057 (505) 284-7057 patricia.parrish@nnsa.doe.gov FTCP Agents DOE Headquarters Chief of Nuclear Safety (CNS) Richard Lagdon (202) 586-9471 (202) 586-5533 Chip.Lagdon@eh.doe.gov Office of Health, Safety & Security Pat Worthington (301) 903-6929 (301) 903-3445 pat.worthington@hq.doe.gov

65

Experimental Test Plan for Grouting H-3 Calcine  

Science Conference Proceedings (OSTI)

Approximately 4400 cubic meters of solid high-level waste called calcine are stored at the Idaho Nuclear Technology and Engineering Center. Under the Idaho Cleanup Project, dual disposal paths are being investigated. The first path includes calcine retrieval, package "as-is", and ship to the Monitored Geological Repository (MGR). The second path involves treatment of the calcine with such methods as vitrification or grouting. This test plan outlines the hot bench scale tests to grout actual calcine and verify that the waste form properties meet the waste acceptance criteria. This is a necessary sequential step in the process of qualifying a new waste form for repository acceptance. The archive H-3 calcine samples at the Contaminated Equipment Maintenance Building attached to New Waste Calcining Facility will be used in these tests at the Remote Analytical Laboratory. The tests are scheduled for the second quarter of fiscal year 2007.

Alan K. Herbst

2006-01-01T23:59:59.000Z

66

Qualifying Officials Designation Letter - Savannah River Operations Office  

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

DOEP IUUI DOEP IUUI United States Government Department of Energy (DOE) memorandum Savannah River Operations Office (SR) DATE: REPLY TO ATTN OF: SUBJECT: NOV 3 o 2010 MGR (Moody, 2-9468) Technical Qualification Program (TQP) Qualifying Officials (QO) ro: DISTRIBUTION Each employee whose name appears on the attached listings is designated as a TQP QO. You were chosen by your supervisor because you have demonstrated an in-depth level of knowledge and abilities in the functional area or functional competency for which you are designated. As a designated TQP QO, you play a significant role in the qualification process of TQP participants and have a grave responsibility for maintaining the intent and integrity of the program. Your signature on the qualification record validates the

67

Notices  

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

4 Federal Register 4 Federal Register / Vol. 76, No. 38 / Friday, February 25, 2011 / Notices mailed to ICDocketMgr@ed.gov or mailed to U.S. Department of Education, 400 Maryland Avenue, SW., LBJ, Washington, DC 20202-4537. Please note that written comments received in response to this notice will be considered public records. SUPPLEMENTARY INFORMATION: Section 3506 of the Paperwork Reduction Act of 1995 (44 U.S.C. chapter 35) requires that Federal agencies provide interested parties an early opportunity to comment on information collection requests. The Director, Information Collection Clearance Division, Regulatory Information Management Services, Office of Management, publishes this notice containing proposed information collection requests at the beginning of the Departmental review of the

68

Notices  

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

1 Federal Register 1 Federal Register / Vol. 77, No. 102 / Friday, May 25, 2012 / Notices be addressed to U.S. Department of Education, 400 Maryland Avenue SW., LBJ, Washington, DC 20202-4537. Requests may also be electronically mailed to ICDocketMgr@ed.gov or faxed to 202-401-0920. Please specify the complete title of the information collection and OMB Control Number when making your request. Individuals who use a telecommunications device for the deaf (TDD) may call the Federal Information Relay Service (FIRS) at 1-800-877- 8339. SUPPLEMENTARY INFORMATION: Section 3506 of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35) requires that Federal agencies provide interested parties an early opportunity to comment on information collection requests. The Director, Information Collection

69

Microsoft Word - BB-Terrestrial-Oct09  

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

Terrestrial Field Validation Test Terrestrial Field Validation Test 1 FACT SHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase II Contacts: DOE/NETL Project Mgr. Name Organization E-Mail Andrea McNemar, U.S. Department of Energy, andrea.mcnemar@netl.doe.gov Principal Investigator Edward Steadman Field Test Information: Field Test Name Terrestrial Field Validation Test Test Location North Dakota, South Dakota, Minnesota, Montana, Iowa Amount and Source of CO 2 Tons N/A Source Atmospheric CO 2 Field Test Partners (Primary Sponsors) Ducks Unlimited, Inc. U.S. Geological Survey Northern Prairie Wildlife Research Center North Dakota State University Summary of Field Test Site and Operations:

70

Notice of Availability of the Record of Decision for the South Fork Flathead Watershed Westslope Cutthroat Trout Conservation Program (DOE/EIS-0353) (05/12/06)  

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

714 Federal Register 714 Federal Register / Vol. 71, No. 92 / Friday, May 12, 2006 / Notices 6623. Please specify the complete title of the information collection when making your request. Comments regarding burden and/or the collection activity requirements should be electronically mailed to IC DocketMgr@ed.gov. Individuals who use a telecommunications device for the deaf (TDD) may call the Federal Information Relay Service (FIRS) at 1- 800-877-8339. [FR Doc. E6-7288 Filed 5-11-06; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF EDUCATION Office of Special Education and Rehabilitative Services; Special Education-Technology and Media Services for Individuals With Disabilities-Access to Emerging Technologies (CFDA No. 84.327C) ACTION: Notice inviting applications for new awards for fiscal year (FY) 2006;

71

EIS-0437-NoticeofCancellation-2012.pdf  

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

320 Federal Register 320 Federal Register / Vol. 77, No. 168 / Wednesday, August 29, 2012 / Notices DATES: Interested persons are invited to submit comments on or before October 29, 2012. ADDRESSES: Written comments regarding burden and/or the collection activity requirements should be electronically mailed to ICDocketMgr@ed.gov or mailed to U.S. Department of Education, 400 Maryland Avenue SW., LBJ, Washington, DC 20202-4537. Copies of the proposed information collection request may be accessed from http://edicsweb.ed.gov, by selecting the ''Browse Pending Collections'' link and by clicking on link number 04922. When you access the information collection, click on ''Download Attachments'' to view. Written requests for information should be addressed to U.S. Department of

72

Microsoft Word - JAS-WillistonBasin-Oct09  

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

EOR Field Test EOR Field Test 1 FACT SHEET FOR PARTNERSHIP FIELD VALIDATION TEST Partnership Name Plains CO 2 Reduction (PCOR) Partnership - Phase II Contacts: DOE/NETL Project Mgr. Name Organization E-Mail Andrea McNemar, U.S. Department of Energy, andrea.mcnemar@netl.doe.gov Principal Investigator Edward Steadman Field Test Information: Field Test Name Williston Basin EOR Field Test Test Location Northwest McGregor Oil Field, Williams County, North Dakota Amount and Source of CO 2 Tons 440 tons Source Commercial vendor Field Test Partners (Primary Sponsors) Eagle Operating, Inc. Schlumberger Carbon Services Praxair Summary of Field Test Site and Operations: The Plains CO 2 Reduction (PCOR) Partnership, working closely with Eagle Operating, Inc. (Eagle), has

73

Mark Palmer  

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

Palmer Palmer Program Mgr. & Group Leader Building & Fire Research Laboratory (BFRL) National Institute of Standards & Technology mark.palmer@nist.gov This speaker was a visiting speaker who delivered a talk or talks on the date(s) shown at the links below. This speaker is not otherwise associated with Lawrence Berkeley National Laboratory, unless specifically identified as a Berkeley Lab staff member. Mark Palmer leads the Computer Integrated Building Processes Group at the Building and Fire Research Laboratory (BFRL) of the National Institute of Standards and Technology (NIST). Mr. Palmer conducts research on measurement science for the integration of information, communication and automation technologies and work process optimization to improve engineering, construction and manufacturing. P> Mr. Palmer is active in

74

Document  

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

3 Federal Register 3 Federal Register / Vol. 76, No. 204 / Friday, October 21, 2011 / Notices e-mailed to oira_submission@omb.eop.gov with a cc: to ICDocketMgr@ed.gov. Please note that written comments received in response to this notice will be considered public records. SUPPLEMENTARY INFORMATION: Section 3506 of the Paperwork Reduction Act of 1995 (44 U.S.C. chapter 35) requires that the Office of Management and Budget (OMB) provide interested Federal agencies and the public an early opportunity to comment on information collection requests. The OMB is particularly interested in comments which: (1) Evaluate whether the proposed collection of information is necessary for the proper performance of the functions of the agency, including whether the information will have

75

NETL F 451.1-1/1 Categorical Exclusion (CX) Designation Form  

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

NETL Site Operations Division NETL Site Operations Division FE Solicitation DE-SOL0002990 Site Operations Division 2011 Bernard M. Avon Prjct Mgr/COR 6/08/2009 through 08/10/2011 NETL: Pittsburgh, PA (Building 167) Install Government-Supplied HVAC Equipment for NETL's Pittsburgh B-167 Fitness Facility Remove decommissioned HVAC system and install a government-supplied HVAC system for B-167, NETL Pittsburgh's fitness facility. See description of construction. 05 31 2011 Bernard Avon Digitally signed by Bernard Avon DN: cn=Bernard Avon, c=US, o=NETL, ou=DOE, email=bernard.avon@netl.doe.gov Date: 2010.03.22 14:07:40 -04'00' 6 4 2011 john ganz Digitally signed by john ganz DN: cn=john ganz, o=netl, ou=environmental compliance division, email=john.ganz@netl.doe.gov, c=US Date: 2011.06.04 11:12:25

76

DOE Webcast: GTI Super Boiler Technology  

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

Webcast Webcast GTI Super Boiler Technology by Dennis Chojnacki, Senior Engineer by Curt Bermel, Business Development Mgr. R&D > November 20, 2008 November 20, 2008 2 November 20, 2008 2 WHO WE ARE Gas Technology Institute >Leading U.S. research, development, and training organization serving the natural gas industry and energy markets ─ An independent, 501c (3) not-for-profit Serving the Energy Industry Since 1941 > Over 1,000 patents > Nearly 500 products commercialized November 20, 2008 3 November 20, 2008 3 Super Boiler Background > U.S. industrial and commercial steam boilers ─ Consume over 6 quads of natural gas per year ─ Wide range of steam uses from process steam to space heating > Installed base of steam boilers ─ Largely over 30 years old

77

Slide 1  

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

Geospatial Technologies from the Geospatial Technologies from the Ground Up: The State Perspective Department of Energy Geospatial Technology Summit August 16, 2011 NATIONAL STATES GEOGRAPHIC INFORMATION COUNCIL Jon Gottsegen President, National States Geographic Information Council State GIS Coordinator/Enterprise GIS Services Mgr, State of Colorado Office of Information Technology NATIONAL STATES GEOGRAPHIC INFORMATION COUNCIL What is NSGIC? (www.nsgic.org) * Small 501 (c) 6 nonprofit organization (~579 members) * Formed in 1991 * We Promote - Effective and efficient government through the prudent adoption of geospatial technologies - Statewide GIS coordination efforts * We serve as the voice of States for geospatial issues * Actively engaged with many Federal organizations - Especially focused on the FGDC and the National Spatial Data

78

TRIGA FUEL PHASE I AND II CRITICALITY CALCULATION  

SciTech Connect

The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA (Training, Research, Isotopes, General Atomic) reactor spent nuclear fuel (SNF) with Savannah River Site (SRS) high-level waste (HLW). The TRIGA SNF is loaded into a Department of Energy (DOE) standardized SNF canister which is centrally positioned inside a five-canister defense SRS HLW waste package (WP). The objective of the calculation is to investigate the criticality issues for the WP containing the five SRS HLW and DOE SNF canisters in various stages of degradation. This calculation will support the analysis that will be performed to demonstrate the viability of the codisposal concept for the Monitored Geologic Repository (MGR).

L. Angers

1999-11-23T23:59:59.000Z

79

Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Degraded Mode  

SciTech Connect

The objective of this calculation is to characterize the nuclear criticality safety concerns associated with the codisposal of the Department of Energy's (DOE) Enrico Fermi (EF) Spent Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP) and placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for the degraded mode internal configurations of the codisposal WP. The results of this calculation and those of Ref. 8 will be used to evaluate criticality issues and support the analysis that will be performed to demonstrate the viability of the codisposal concept for the Monitored Geologic Repository.

D.R. Moscalu; L. Angers; J. Monroe-Rammsey; H.R. Radulesca

2000-07-21T23:59:59.000Z

80

Slide 1  

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

1 1 MA-50 DOE/OECM 1 OECM PARS II Working Group Oversight & Assessment Module April 30, 2009 Created by: EES/Dekker PARS II Team 2 Agenda * Obtain consensus on screen data elements * Screens to be covered in this meeting are: * PARS II Roles & Access Rights * Budget (Requirements & Discussion) * Gold Card 3 Roles & Access Rights * List of Group Names * Business Rules (draft) * Two Security Models * Supporting Details 4 Group Names * Federal Project Director * Deputy Federal Project Director * OECM Senior Management * OECM Analyst * Alternate OECM Analyst * Contracting Officer Rep. * Interested Party * Federal Program Manager * Program Manager * Program Analyst * Program Point of Contact * Acquisition Executive * Contractor Project Mgr. (CPP) * Contractor Analyst (CPP) MA-50 DOE/OECM 4 5 Business Rules (Draft)

Note: This page contains sample records for the topic "mgr lajos grof-tisza" 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
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81

Notices  

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

8 Federal Register 8 Federal Register / Vol. 76, No. 73 / Friday, April 15, 2011 / Notices requirements and provide the requested data in the desired format. The Director, Information Collection Clearance Division, Information Management and Privacy Services, Office of Management, invites comments on the proposed information collection requests as required by the Paperwork Reduction Act of 1995. DATES: Interested persons are invited to submit comments on or before June 14, 2011. ADDRESSES: Comments regarding burden and/or the collection activity requirements should be electronically mailed to ICDocketMgr@ed.gov or mailed to U.S. Department of Education, 400 Maryland Avenue, SW., LBJ, Washington, DC 20202-4537. Please note that written comments received in response to this notice will be

82

Validation Test Report For The CRWMS Analysis and Logistics Visually Interactive Model Calvin Version 3.0, 10074-Vtr-3.0-00  

SciTech Connect

This report describes the tests performed to validate the CRWMS ''Analysis and Logistics Visually Interactive'' Model (CALVIN) Version 3.0 (V3.0) computer code (STN: 10074-3.0-00). To validate the code, a series of test cases was developed in the CALVIN V3.0 Validation Test Plan (CRWMS M&O 1999a) that exercises the principal calculation models and options of CALVIN V3.0. Twenty-five test cases were developed: 18 logistics test cases and 7 cost test cases. These cases test the features of CALVIN in a sequential manner, so that the validation of each test case is used to demonstrate the accuracy of the input to subsequent calculations. Where necessary, the test cases utilize reduced-size data tables to make the hand calculations used to verify the results more tractable, while still adequately testing the code's capabilities. Acceptance criteria, were established for the logistics and cost test cases in the Validation Test Plan (CRWMS M&O 1999a). The Logistics test cases were developed to test the following CALVIN calculation models: Spent nuclear fuel (SNF) and reactivity calculations; Options for altering reactor life; Adjustment of commercial SNF (CSNF) acceptance rates for fiscal year calculations and mid-year acceptance start; Fuel selection, transportation cask loading, and shipping to the Monitored Geologic Repository (MGR); Transportation cask shipping to and storage at an Interim Storage Facility (ISF); Reactor pool allocation options; and Disposal options at the MGR. Two types of cost test cases were developed: cases to validate the detailed transportation costs, and cases to validate the costs associated with the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M&O) and Regional Servicing Contractors (RSCs). For each test case, values calculated using Microsoft Excel 97 worksheets were compared to CALVIN V3.0 scenarios with the same input data and assumptions. All of the test case results compare with the CALVIN V3.0 results within the bounds of the acceptance criteria. Therefore, it is concluded that the CALVIN V3.0 calculation models and options tested in this report are validated.

S. Gillespie

2000-07-27T23:59:59.000Z

83

Bottom/Side Lift Gantry Conceptual Design Rev. 01  

SciTech Connect

The purpose of this task is to update the existing bottom/side lift gantry analysis so that the design is consistent with Enhanced Design Alternative II (EDA II) design constraints listed in the Monitored Geologic Repository Project Description Document (CRWMS M and O 1999a, Section 2.2.1.1, p. 9a). This update is consistent with the requirements of the Technical Guidance Document for License Application Preparation (YMP 1999, Section 6.2.5.1). This update will also take into account the latest available equipment classification and Waste Emplacement/Retrieval System Description Document (SDD) (CRWMS M and O 2000c) requirements. The principal objective of this analysis is to verify that the newly developed bottom/side lift gantry concept continues to be a suitable design concept for the current Monitored Geologic Repository (MGR) design. This analysis includes an examination of the waste package (WP) transfer operation at the emplacement drift transfer dock. In addition, this analysis verifies that the gantry is compatible with the WP transporter, which has been redesigned to handle WPs sitting on pallets (CRWMS M and O 2000a). The scope of this work is to examine the existing analysis and to determine what, if any, modifications to the analysis may be required as a result of additional requirements imposed by the EDA II concept. Then, a revision will be made to the conceptual design accordingly. The analysis will also be revised to show the approximate sizes and locations of the electrical equipment and control cabinets, and to take into account the weight of that equipment in the total gantry weight. The analytical portions of the analysis are revised, as required, to address changes resulting from modifications to the conceptual design or from changes in classification and/or SDD requirements. Finally, the revised conceptual design is evaluated to verify that it continues to be a suitable method for handling the WPs within the emplacement drift. Except as noted, the scope of this work does not include any new analytical investigations or any detailed studies regarding the mechanical or electrical subsystems of the gantry beyond those in Revision 00 of this analysis. This analysis has been prepared in accordance with the requirements set forth in Bottom/Side Lift Gantry Analysis (CRWMS M and O 1999b). This analysis supports the MGR design that will be presented as part of the Site Recommendation.

Bair, P.S.

2000-04-11T23:59:59.000Z

84

BWR Source Term Generation and Evaluation  

SciTech Connect

This calculation is a revision of a previous calculation (Ref. 7.5) that bears the same title and has the document identifier BBAC00000-01717-0210-00006 REV 01. The purpose of this revision is to remove TBV (to-be-verified) -41 10 associated with the output files of the previous version (Ref. 7.30). The purpose of this and the previous calculation is to generate source terms for a representative boiling water reactor (BWR) spent nuclear fuel (SNF) assembly for the first one million years after the SNF is discharged from the reactors. This calculation includes an examination of several ways to represent BWR assemblies and operating conditions in SAS2H in order to quantify the effects these representations may have on source terms. These source terms provide information characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, and radionuclide inventories in curies. Source terms are generated for a range of burnups and enrichments (see Table 2) that are representative of the waste stream and stainless steel (SS) clad assemblies. During this revision, it was determined that the burnups used for the computer runs of the previous revision were actually about 1.7% less than the stated, or nominal, burnups. See Section 6.6 for a discussion of how to account for this effect before using any source terms from this calculation. The source term due to the activation of corrosion products deposited on the surfaces of the assembly from the coolant is also calculated. The results of this calculation support many areas of the Monitored Geologic Repository (MGR), which include thermal evaluation, radiation dose determination, radiological safety analyses, surface and subsurface facility designs, and total system performance assessment. This includes MGR items classified as Quality Level 1, for example, the Uncanistered Spent Nuclear Fuel Disposal Container (Ref. 7.27, page 7). Therefore, this calculation is subject to the requirements of the Quality Assurance Requirements and Description (Ref. 7.28). The performance of the calculation and development of this document are carried out in accordance with AP-3.124, ''Design Calculation and Analyses'' (Ref. 7.29).

J.C. Ryman

2003-07-31T23:59:59.000Z

85

Emplacement Drift System Description Document  

SciTech Connect

The Emplacement Drift System is part of the Engineered Barrier System and provides the interface between the various waste package (WP) systems and the Ground Control System. In conjunction with the various WPs, the Emplacement Drift System limits the release and transport of radionuclides from the WP to the Natural Barrier following waste emplacement. Collectively, the Emplacement Drift System consists of the structural support hardware (emplacement drift invert and WP emplacement pallet) and any performance-enhancing barriers (drip shields and invert ballast) installed or placed in the emplacement drifts. The Emplacement Drift System is entirely located within the emplacement drifts in the subsurface portion of the Monitored Geologic Repository (MGR); specifically, it is physically bounded by the Subsurface Facility System, the Ground Support System, and the Natural Barrier. The Emplacement Drift System supports the key MGR functions of limiting radionuclide release to the Natural Barrier, minimizing the likelihood of a criticality external to the WPs, limiting natural and induced environmental effects, and providing WP support. The Emplacement Drift System limits radionuclide release to the Natural Barrier by controlling the movement of radionuclides within the emplacement drift and to the Natural Barrier, and by limiting water contact with the WPs. The Emplacement Drift System provides physical support and barriers for emplaced WPs that reduce water contact. The Emplacement Drift WP spacing supports the thermal loading performance by complimenting drift layout and orientation as described in the system description document for the Subsurface Facility System. The Emplacement Drift System supports the WP and also provides an environment that aids in enhancing WP confinement performance. As part of the Engineered Barrier System, the Emplacement Drift System interfaces with the WP systems. The Emplacement Drift System also interfaces with the Natural Barrier, Subsurface Facility System, and Ground Control System for the space and location of emplaced WPs, for the controlled release of radionuclides, and for controlling the heat, chemical, and physical effects that interact between these systems. The Emplacement Drift System interfaces with the Subsurface Ventilation System for preclosure heat removal from WPs. The Emplacement Drift System interfaces with the Waste Emplacement/Retrieval System and the Performance Confirmation Emplacement Drift Monitoring System for equipment clearance for the emplacement, retrieval, and monitoring of waste.

Eric Loros

2001-07-31T23:59:59.000Z

86

MESSAGE: WIA W/O CLOSING REF CLOSING REF  

Office of Legacy Management (LM)

MESSAGE: MESSAGE: WIA W/O CLOSING REF CLOSING REF _ CONSTRUCTION COMPL DATE J. King SAIC J. Waddell SAIC R. Wright SAIC T. Gangwer SAIC M. Khan SAIC T. Patterson SAIC R. Tucker SAIC C.Helie SAIC K. Renfro SAIC S. Heptinstall SAIC PLEASE RETURN TO PDCC FOR CORRECTIONS MGMT. SYSTEMS: PROGRAM ADMIN.: DEPUTY PROGRAM MGR: PROJECT MANAGER: () I PROGRAM MANAGER: I I ANL: AJ. Dvorak ANL A Geisler ANL G. Maraman ANL D. Dunning ANL J. Wing BNI DIRECTOR. FSRD: L Price FSRD DEP. DIRECTOR. FSRD: W.Seay FSRD SITE MANAGER: D.Adler FSRD " S. Cange FSRD R. Kirk FSRD J. Kopotic FSRD M. Nee FSRD PROJECT SUPPORT GRP: J.Hart FSRD S. Oldham FSRD 4- G. Hartman FSRD L Marz FSRD PRGM ANALYST: B. Hughlett FSRD SECRETARY: M. Seiber"''' Dyke FSRD FSRD CHRON FILE FSRD NOTEBOOKS READING FILE DOEIP&CD: French/Sistrunk DCO DOEIHO: J. Wagoner DHO RESeDNSE TRACKING INFORMATION SECONDARY: / : SECONDARY: ~ OWED TO: / lOWED

87

I I  

Office of Legacy Management (LM)

Header Sheet Header Sheet .Doc ID # 7 e) AW-h a""- - 'IN r 1,9- / q 1-1- 31 0 )c // C) SC CCN: FUSRAP COMMUNICATIONS DISTRIBUTION FSRD= COMM. TYPELL-1-1 FORMER SITES RESTORATION DIVISION (EW-93) SAIC SENSITIVE DATE PROCESSED BY PDCC APR 0 3 1997 COMM REF ADMIN RCD SUBJECT .1 lrhnu rn t FROM To r P, COMM DATE ADDR CODE I I CLOSES CNN Wes I - RESPONSE TRACKING INFORMATION AC TION DESCRIPTION: 01: Ioi: OWEOTO- OWED BY: (ORG) I (ORG) TARGETDAT9.A IcLosiNr cco..coaoip. DATE CLOSING REF- 02: 1 02'. OWED M. OWED BY: (ORG) fORG). .TARGET-DATE CLOSING CCN..COMP. DATE CLOSING REF- MESSAGE: FSRD W/A W/0 SITES: W/A W/0 BNI W/A W/o ACTNG DIRECTOR: W S.., las nup 138 MIS PROGRAM MANAGER: k B.. WIA W/O W/A W/O 112 PNV 139 CIS DEPUTY PROGRAM MGR-: W. F.Vell D. AcK., R. Kii* IISSLD 140 His PROGRAM INT. MGk: G. D..,

88

CRITICALITY CALCULATION FOR THE MOST REACTIVE DEGRADED CONFIGURATIONS OF THE FFTF SNF CODISPOSAL WP CONTAINING AN INTACT IDENT-69 CONTAINER  

Science Conference Proceedings (OSTI)

The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins. The configurations have been identified in a previous analysis (CRWMS M&O 1999a) and the present evaluations include additional relevant information that was left out of the original calculations. The additional information describes the exact distribution of fissile material in each container (DOE 2002a). The effects of the changes that have been included in the baseline design of the codisposal WP (CRWMS M&O 2000) are also investigated. The calculation determines the effective neutron multiplication factor (k{sub eff}) for selected degraded mode internal configurations of the codisposal waste package. These calculations will support the demonstration of the technical viability of the design solution adopted for disposing of MOX (FFTF) spent nuclear fuel in the potential repository. This calculation is subject to the Quality Assurance Requirements and Description (QARD) (DOE 2002b) per the activity evaluation under work package number P6212310M2 in the technical work plan TWP-MGR-MD-000010 REV 01 (BSC 2002).

D.R. Moscalu

2002-08-28T23:59:59.000Z

89

Lower-Temperature Subsurface Layout and Ventilation Concepts  

Science Conference Proceedings (OSTI)

This analysis combines work scope identified as subsurface facility (SSF) low temperature (LT) Facilities System and SSF LT Ventilation System in the Technical Work Plan for Subsurface Design Section FY 01 Work Activities (CRWMS M&O 2001b, pp. 6 and 7, and pp. 13 and 14). In accordance with this technical work plan (TWP), this analysis is performed using AP-3.10Q, Analyses and Models. It also incorporates the procedure AP-SI.1Q, Software Management. The purpose of this analysis is to develop an overall subsurface layout system and the overall ventilation system concepts that address a lower-temperature operating mode for the Monitored Geologic Repository (MGR). The objective of this analysis is to provide a technical design product that supports the lower-temperature operating mode concept for the revision of the system description documents and to provide a basis for the system description document design descriptions. The overall subsurface layout analysis develops and describes the overall subsurface layout, including performance confirmation facilities (also referred to as Test and Evaluation Facilities) for the Site Recommendation design. This analysis also incorporates current program directives for thermal management.

Christine L. Linden; Edward G. Thomas

2001-06-20T23:59:59.000Z

90

Identification of Aircraft Hazards  

Science Conference Proceedings (OSTI)

Aircraft hazards were determined to be potentially applicable to a repository at Yucca Mountain in ''Monitored Geological Repository External Events Hazards Screening Analysis'' (BSC 2005 [DIRS 174235], Section 6.4.1). That determination was conservatively based upon limited knowledge of flight data in the area of concern and upon crash data for aircraft of the type flying near Yucca Mountain. The purpose of this report is to identify specific aircraft hazards that may be applicable to a monitored geologic repository (MGR) at Yucca Mountain, using NUREG-0800, ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987 [DIRS 103124], Section 3.5.1.6), as guidance for the inclusion or exclusion of identified aircraft hazards. The intended use of this report is to provide inputs for further screening and analysis of identified aircraft hazards based upon the criteria that apply to Category 1 and Category 2 event sequence analyses as defined in 10 CFR 63.2 [DIRS 176544] (Section 4). The scope of this report includes the evaluation of military, private, and commercial use of airspace in the 100-mile regional setting of the repository at Yucca Mountain with the potential for reducing the regional setting to a more manageable size after consideration of applicable screening criteria (Section 7).

K. Ashley

2006-12-08T23:59:59.000Z

91

Preliminary Transportation, Aging and Disposal Canister System Performance Specification  

SciTech Connect

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2. The TAD canister, in conjunction with specialized overpacks will accomplish a number of functions in the management and disposal of spent nuclear fuel. Some of these functions will be accomplished at purchaser sites where commercial spent nuclear fuel (CSNF) is stored, and some will be performed within the Office of Civilian Radioactive Waste Management (OCRWM) transportation and disposal system. This document contains only those requirements unique to applications within Department of Energy's (DOE's) system. DOE recognizes that TAD canisters may have to perform similar functions at purchaser sites. Requirements to meet reactor functions, such as on-site dry storage, handling, and loading for transportation, are expected to be similar to commercially available canister-based systems. This document is intended to be referenced in the license application for the Monitored Geologic Repository (MGR). As such, the requirements cited herein are needed for TAD system use in OCRWM's disposal system. This document contains specifications for the TAD canister, transportation overpack and aging overpack. The remaining components and equipment that are unique to the OCRWM system or for similar purchaser applications will be supplied by others.

C.A Kouts

2006-11-22T23:59:59.000Z

92

EXTERNAL CRITICALITY CALCULATION FOR DOE SNF CODISPOSAL WASTE PACKAGES  

SciTech Connect

The purpose of this document is to evaluate the potential for criticality for the fissile material that could accumulate in the near-field (invert) and in the far-field (host rock) beneath the U.S. Department of Energy (DOE) spent nuclear fuel (SNF) codisposal waste packages (WPs) as they degrade in the proposed monitored geologic repository at Yucca Mountain. The scope of this calculation is limited to the following DOE SNF types: Shippingport Pressurized Water Reactor (PWR), Enrico Fermi, Fast Flux Test Facility (FFTF), Fort St. Vrain, Melt and Dilute, Shippingport Light Water Breeder Reactor (LWBR), N-Reactor, and Training, Research, Isotope, General Atomics reactor (TRIGA). The results of this calculation are intended to be used for estimating the probability of criticality in the near-field and in the far-field. There are no limitations on use of the results of this calculation. The calculation is associated with the waste package design and was developed in accordance with the technical work plan, ''Technical Work Plan for: Department of Energy Spent Nuclear Fuel and Plutonium Disposition Work Packages'' (Bechtel SAIC Company, LLC [BSC], 2002a). This calculation is subject to the Quality Assurance Requirements and Description (QARD) per the activity evaluation under work package number P6212310Ml in the technical work plan TWP-MGR-MD-0000 10 REV 01 (BSC 2002a).

H. Radulescu

2002-10-18T23:59:59.000Z

93

Naval Spent Nuclear Fuel disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

N. E. Pettit

2001-07-13T23:59:59.000Z

94

Defense High Level Waste Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents.

N. E. Pettit

2001-07-13T23:59:59.000Z

95

The role of actinide burning and the Integral Fast Reactor in the future of nuclear power  

Science Conference Proceedings (OSTI)

A preliminary assessment is made of the potential role of actinide burning and the Integral Fast Reactor (IFR) in the future of nuclear power. The development of a usable actinide burning strategy could be an important factor in the acceptance and implementation of a next generation of nuclear power. First, the need for nuclear generating capacity is established through the analysis of energy and electricity demand forecasting models which cover the spectrum of bias from anti-nuclear to pro-nuclear. The analyses take into account the issues of global warming and the potential for technological advances in energy efficiency. We conclude, as do many others, that there will almost certainly be a need for substantial nuclear power capacity in the 2000--2030 time frame. We point out also that any reprocessing scheme will open up proliferation-related questions which can only be assessed in very specific contexts. The focus of this report is on the fuel cycle impacts of actinide burning. Scenarios are developed for the deployment of future nuclear generating capacity which exploit the advantages of actinide partitioning and actinide burning. Three alternative reactor designs are utilized in these future scenarios: The Light Water Reactor (LWR); the Modular Gas-Cooled Reactor (MGR); and the Integral Fast Reactor (FR). Each of these alternative reactor designs is described in some detail, with specific emphasis on their spent fuel streams and the back-end of the nuclear fuel cycle. Four separation and partitioning processes are utilized in building the future nuclear power scenarios: Thermal reactor spent fuel preprocessing to reduce the ceramic oxide spent fuel to metallic form, the conventional PUREX process, the TRUEX process, and pyrometallurgical reprocessing.

Hollaway, W.R.; Lidsky, L.M.; Miller, M.M.

1990-12-01T23:59:59.000Z

96

WASTE HANDLING BUILDING ELECTRICAL SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Electrical System performs the function of receiving, distributing, transforming, monitoring, and controlling AC and DC power to all waste handling building electrical loads. The system distributes normal electrical power to support all loads that are within the Waste Handling Building (WHB). The system also generates and distributes emergency power to support designated emergency loads within the WHB within specified time limits. The system provides the capability to transfer between normal and emergency power. The system provides emergency power via independent and physically separated distribution feeds from the normal supply. The designated emergency electrical equipment will be designed to operate during and after design basis events (DBEs). The system also provides lighting, grounding, and lightning protection for the Waste Handling Building. The system is located in the Waste Handling Building System. The system consists of a diesel generator, power distribution cables, transformers, switch gear, motor controllers, power panel boards, lighting panel boards, lighting equipment, lightning protection equipment, control cabling, and grounding system. Emergency power is generated with a diesel generator located in a QL-2 structure and connected to the QL-2 bus. The Waste Handling Building Electrical System distributes and controls primary power to acceptable industry standards, and with a dependability compatible with waste handling building reliability objectives for non-safety electrical loads. It also generates and distributes emergency power to the designated emergency loads. The Waste Handling Building Electrical System receives power from the Site Electrical Power System. The primary material handling power interfaces include the Carrier/Cask Handling System, Canister Transfer System, Assembly Transfer System, Waste Package Remediation System, and Disposal Container Handling Systems. The system interfaces with the MGR Operations Monitoring and Control System for supervisory monitoring and control signals. The system interfaces with all facility support loads such as heating, ventilation, and air conditioning, office, fire protection, monitoring and control, safeguards and security, and communications subsystems.

S.C. Khamamkar

2000-06-23T23:59:59.000Z

97

Subsurface Contamination Control  

Science Conference Proceedings (OSTI)

There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.

Y. Yuan

2001-12-12T23:59:59.000Z

98

Subsurface Contamination Control  

Science Conference Proceedings (OSTI)

There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.

Y. Yuan

2001-11-16T23:59:59.000Z

99

SITE ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Site Electrical Power System receives and distributes utility power to all North Portal site users. The major North Portal users are the Protected Area including the subsurface facility and Balance of Plant areas. The system is remotely monitored and controlled from the Surface Operations Monitoring and Control System. The system monitors power quality and provides the capability to transfer between Off-Site Utility and standby power (including dedicated safeguards and security power). Standby power is only distributed to selected loads for personnel safety and essential operations. Security power is only distributed to essential security operations. The standby safeguards and security power is independent from all other site power. The system also provides surface lighting, grounding grid, and lightning protection for the North Portal. The system distributes power during construction, operation, caretaker, and closure phases of the repository. The system consists of substation equipment (disconnect switches, breakers, transformers and grounding equipment) and power distribution cabling from substation to the north portal switch gear building. Additionally, the system includes subsurface facility substation (located on surface), switch-gear, standby diesel generators, underground duct banks, power cables and conduits, switch-gear building and associated distribution equipment for power distribution. Each area substation distributes power to the electrical loads and includes the site grounding, site lighting and lightning protection equipment. The site electrical power system distributes power of sufficient quantity and quality to meet users demands. The Site Electrical Power System interfaces with the North Portal surface systems requiring electrical power. The system interfaces with the Subsurface Electrical Distribution System which will supply power to the underground facilities from the North Portal. Power required for the South Portal and development side activities of the subsurface facility will be provided at the South Portal by the Subsurface Electrical Distribution System. The Site Electrical Power System interfaces with the Off-Site Utility System for the receipt of power. The System interfaces with the Surface Operations Monitoring and Control System for monitoring and control. The System interfaces with MGR Site Layout System for the physical location of equipment and power distribution.

E.P. McCann

1999-04-16T23:59:59.000Z

100

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the specific design chosen (see Assumption 3.4). A more current design will be included in the next revision of the criticality calculations for the Aging Facility. In addition, this calculation is valid for the current design as provided in Attachment III of the DTF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document.

C.E. Sanders

2005-05-17T23:59:59.000Z

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101

FUEL HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling Facility (FHF) and the operations and processes performed therein. The current intent of the FHF is to receive transportation casks whose contents will be unloaded and transferred to waste packages (WP) or MGR Specific Casks (MSC) in the fuel transfer bays. Further, the WPs will also be prepared in the FHF for transfer to the sub-surface facility (for disposal). The MSCs will be transferred to the Aging Facility for storage. The criticality evaluation of the FHF features the following: (I) Consider the types of waste to be received in the FHF as specified below: (1) Uncanistered commercial spent nuclear fuel (CSNF); (2) Canistered CSNF (with the exception of horizontal dual-purpose canister (DPC) and/or multi-purpose canisters (MPCs)); (3) Navy canistered SNF (long and short); (4) Department of Energy (DOE) canistered high-level waste (HLW); and (5) DOE canistered SNF (with the exception of MCOs). (II) Evaluate the criticality analyses previously performed for the existing Nuclear Regulatory Commission (NRC)-certified transportation casks (under 10 CFR 71) to be received in the FHF to ensure that these analyses address all FHF conditions including normal operations, and Category 1 and 2 event sequences. (III) Evaluate FHF criticality conditions resulting from various Category 1 and 2 event sequences. Note that there are currently no Category 1 and 2 event sequences identified for FHF. Consequently, potential hazards from a criticality point of view will be considered as identified in the ''Internal Hazards Analysis for License Application'' document (BSC 2004c, Section 6.6.4). (IV) Assess effects of potential moderator intrusion into the fuel transfer bay for defense in depth. The SNF/HLW waste transfer activity (i.e., assembly and canister transfer) that is being carried out in the FHF has been classified as safety category in the ''Q-list'' (BSC 2003, p. A-6). Therefore, this design calculation is subject to the requirements of the ''Quality Assurance Requirements and Description'' (DOE 2004), even though the FHF itself has not yet been classified in the Q-list. Performance of the work scope as described and development of the associated technical product conform to the procedure AP-3.124, ''Design Calculations and Analyses''.

C.E. Sanders

2005-06-30T23:59:59.000Z

102

WASTE HANDLING BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Handling Building (WHB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for equipment operation and personnel comfort, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WHB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement areas ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination within the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WHB. The Waste Handling Building Ventilation System is designed to perform its safety functions under accident conditions and other Design Basis Events (DBEs) (such as earthquakes, tornadoes, fires, and loss of the primary electric power). Additional system design features (such as compartmentalization with independent subsystems) limit the potential for cross-contamination within the WHB. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Handling Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits. The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The Waste Handling Building Ventilation System interfaces with the Waste Handling Building System by being located within the WHB and by maintaining specific pressures, temperatures, and humidity within the building. The system also depends on the WHB for water supply. The system interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air; the Waste Handling Building Fire Protection System for detection of fire and smoke; the Waste Handling Building Electrical System for normal, emergency, and standby power; and the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of the system.

P.A. Kumar

2000-06-21T23:59:59.000Z

103

WASTE TREATMENT BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Treatment Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Treatment Building (WTB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for personnel comfort and equipment operation, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WTB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement area ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination with the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WTB. The Waste Treatment Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits, The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Treatment Building Ventilation System interfaces with the Waste Treatment Building System by being located in the WTB, and by maintaining specific pressure, temperature, and humidity environments within the building. The system also depends on the WTB for normal electric power supply and the required supply of water for heating, cooling, and humidification. Interface with the Waste Treatment Building System includes the WTB fire protection subsystem for detection of fire and smoke. The Waste Treatment Building Ventilation System interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air and key areas within the WTB, the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of system operations, and the Site Generated Radiological Waste Handling System and Site Generated Hazardous, Non-Hazardous & Sanitary Waste Disposal System for routing of pretreated toxic, corrosive, and radiologically contaminated effluent from process equipment to the HEPA filter exhaust ductwork and air-cleaning unit.

P.A. Kumar

2000-06-22T23:59:59.000Z

104

AGING FACILITY CRITICALITY SAFETY CALCULATIONS  

Science Conference Proceedings (OSTI)

The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: (1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). (2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). (3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging Facility. As the ongoing design evolution remains fluid, the results from this design calculation should be evaluated for applicability to any new or modified design. Consequently, the results presented in this document are limited to the current design. The information contained in this document was developed by Environmental and Nuclear Engineering and is intended for the use of Design and Engineering in its work regarding the various criticality related activities performed in the Aging Facility. Yucca Mountain Project personnel from Environmental and Nuclear Engineering should be consulted before the use of the information for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering.

C.E. Sanders

2004-09-10T23:59:59.000Z

105

USE OF ONE-ON ANALYSIS TO EVALUATE TOTAL SYSTEM PERFORMANCE  

SciTech Connect

This report presents the results of analyses of the hypothetical performance of the various configurations of selected natural and engineered elements of the proposed Yucca Mountain nuclear-waste repository. These analyses were conducted upon the recommendation of the Nuclear Waste Technical Review Board (NWTRB) regarding an alternative approach to investigate the identified natural and engineered barriers and associated processes with respect to the postclosure performance of the proposed Yucca Mountain repository. The analyses were conducted per Technical Work Plan (TWP) TWP-MGR-PA-000011 REV 00, Section 3.2.4, Task 2, which states that the task involves ''Identification of barriers that are important to repository performance:'' by means of ''one-on'' analyses to gain a better understanding of repository performance relative to previously identified barriers.'' The ''One-on Analysis'' was performed per Administrative Procedure AP-SIII.9Q. The NWTRB previously reviewed similar analyses conducted by Electric Power Research Institute (EPRI) (EPRI 2002 [158069]). The approach of the investigation was to simulate the hypothetical performance of the repository after an arbitrarily chosen successive addition of each of the selected natural and engineered barrier components and associated processes that provide for the overall safety of the repository. Because the repository system will behave as an integrated system, the combined interaction of all the processes and barriers identified in this report will provide the ultimate repository performance as indicated in various performance-assessment analyses for the Civilian Radioactive Waste Management System (CRWMS) M&O 2000 [153246]; Bechtel SAIC Company, LLC (BSC) 2001 [155950]; and Williams 2001 [157307]. The analyses presented in this report should not be construed as an indication, for the chosen additive sequence, of the relative importance on any one barrier or process. Rather, the results of these analyses provide an indication of the relative performance of those barriers and processes and an understanding of their contribution to the overall performance of the proposed repository system. The analyses in this report considered the nominal-performance scenario only, and did not address performance following unlikely disruptive events (e.g., volcanic activity) (10 Code of Federal Regulations (CFR) 63.342).

G.J. Saulnier Jr.

2002-12-18T23:59:59.000Z

106

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

107

Defense High Level Waste Disposal Container System Description  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

108

DOE Hydropower Program Biennial Report for FY 2005-2006  

DOE Green Energy (OSTI)

SUMMARY The U.S. Department of Energy (DOE) Hydropower Program is part of the Office of Wind and Hydropower Technologies, Office of Energy Efficiency and Renewable Energy. The Program's mission is to conduct research and development (R&D) that will increase the technical, societal, and environmental benefits of hydropower. The Department's Hydropower Program activities are conducted by its national laboratories: Idaho National Laboratory (INL) [formerly Idaho National Engineering and Environmental Laboratory], Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and National Renewable Energy Laboratory (NREL), and by a number of industry, university, and federal research facilities. Programmatically, DOE Hydropower Program R&D activities are conducted in two areas: Technology Viability and Technology Application. The Technology Viability area has two components: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Water Use Optimization, and Improved Mitigation Practices) and (2) Supporting Research and Testing (Environmental Performance Testing Methods, Computational and Physical Modeling, Instrumentation and Controls, and Environmental Analysis). The Technology Application area also has two components: (1) Systems Integration and Technology Acceptance (Hydro/Wind Integration, National Hydropower Collaborative, and Integration and Communications) and (2) Supporting Engineering and Analysis (Valuation Methods and Assessments and Characterization of Innovative Technology). This report describes the progress of the R&D conducted in FY 2005-2006 under all four program areas. Major accomplishments include the following: Conducted field testing of a Retrofit Aeration System to increase the dissolved oxygen content of water discharged from the turbines of the Osage Project in Missouri. Contributed to the installation and field testing of an advanced, minimum gap runner turbine at the Wanapum Dam project in Washington. Completed a state-of-the-science review of hydropower optimization methods and published reports on alternative operating strategies and opportunities for spill reduction. Carried out feasibility studies of new environmental performance measurements of the new MGR turbine at Wanapum Dam, including measurement of behavioral responses, biomarkers, bioindex testing, and the use of dyes to assess external injuries. Evaluated the benefits of mitigation measures for instream flow releases and the value of surface flow outlets for downstream fish passage. Refined turbulence flow measurement techniques, the computational modeling of unsteady flows, and models of blade strike of fish. Published numerous technical reports, proceedings papers, and peer-reviewed literature, most of which are available on the DOE Hydropower website. Further developed and tested the sensor fish measuring device at hydropower plants in the Columbia River. Data from the sensor fish are coupled with a computational model to yield a more detailed assessment of hydraulic environments in and around dams. Published reports related to the Virtual Hydropower Prospector and the assessment of water energy resources in the U.S. for low head/low power hydroelectric plants. Convened a workshop to consider the environmental and technical issues associated with new hydrokinetic and wave energy technologies. Laboratory and DOE staff participated in numerous workshops, conferences, coordination meetings, planning meetings, implementation meetings, and reviews to transfer the results of DOE-sponsored research to end-users.

Sale, Michael J [ORNL; Cada, Glenn F [ORNL; Acker, Thomas L. [Northern Arizona State University and National Renewable Energy Laboratory; Carlson, Thomas [Pacific Northwest National Laboratory (PNNL); Dauble, Dennis D. [Pacific Northwest National Laboratory (PNNL); Hall, Douglas G. [Idaho National Laboratory (INL)

2006-07-01T23:59:59.000Z