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Note: This page contains sample records for the topic "nuclear safety workshop" 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.


1

Nuclear Safety Workshops  

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

Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical Standards Program Search Approved Standards Recently Approved RevCom...

2

Nuclear Safety Workshop Summary  

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

Workshop Summary Workshop Summary September 19-20, 2012 1 Nuclear Safety Workshop Summary On September 19-20, 2012, the U.S. Department of Energy (DOE) held a second Nuclear Safety Workshop covering the results of the Department's actions to improve its posture for analyzing and responding to severe accidents in light of lessons learned from the March 2011 nuclear accident in Japan. Sponsored by DOE and championed by Deputy Secretary of Energy Daniel Poneman, the two-day workshop discussed the lessons learned in a national and international context. The workshop's theme

3

2012 Nuclear Safety Workshop | Department of Energy  

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

Services Nuclear Safety 2012 Nuclear Safety Workshop 2012 Nuclear Safety Workshop 1 of 5 Podonsky This is the Title 2 of 5 This is the Title DOE Deputy Secretary Daniel...

4

Nuclear Safety Workshop Summary | Department of Energy  

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

Workshop Summary Workshop Summary Nuclear Safety Workshop Summary September 19-20, 2012 Nuclear Safety Workshop Summary On September 19-20, 2012, the U.S. Department of Energy (DOE) held a second Nuclear Safety Workshop covering the results of the Department's actions to improve its posture for analyzing and responding to severe accidents in light of lessons learned from the March 2011 nuclear accident in Japan. Sponsored by DOE and championed by Deputy Secretary of Energy Daniel Poneman, the two-day workshop discussed the lessons learned in a national and international context. The workshop's theme was Post Fukushima Initiatives and Results, and included technical breakout sessions focused on beyond design basis events (BDBEs) analysis and response, safety culture, and risk assessment and management.

5

2012 Nuclear Safety Workshop | Department of Energy  

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

Nuclear Safety » 2012 Nuclear Safety Workshop Nuclear Safety » 2012 Nuclear Safety Workshop 2012 Nuclear Safety Workshop Glenn Podonsky 1 of 13 Glenn Podonsky Glenn Podonsky (DOE Chief Health, Safety and Security Officer) provides his welcoming remarks. Daniel Poneman 2 of 13 Daniel Poneman DOE Deputy Secretary Daniel Poneman discusses maintaining our focus on nuclear safety. Akira Kawano 3 of 13 Akira Kawano Akira Kawano, Tokyo Electric Power Company, provides lessons learned from the Fukushima nuclear accident. Bill Ostendorff 4 of 13 Bill Ostendorff NRC Commissioner Bill Ostendorff gives his perspective on the NRC's response to the Fukushima nuclear accident. Miroslav Lipar 5 of 13 Miroslav Lipar Miroslav Lipar, IAEA, provides an international perspective on the Fukushima nuclear accident. Dr. Sonja Haber 6 of 13

6

Advanced research workshop: nuclear materials safety  

SciTech Connect

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of nuclear experience on a common objectivethe safe and secure storage and disposition of excess fissile nuclear materials.

Jardine, L J; Moshkov, M M

1999-01-28T23:59:59.000Z

7

2012 Nuclear Safety Workshop Presentations | Department of Energy  

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

2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations Wednesday, September 19 - Plenary Session September 19, 2012 Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company September 19, 2012 A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Presenter: Honorable William C. Ostendorff, Commissioner US Nuclear Regulatory Commission September 19, 2012 International Perspective on Fukushima Accident Presenter: Miroslav Lipár, Head, Operational Safety Section, Department of

8

Nuclear Safety Research and Development Status Workshop Summary  

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

NSR&D STATUS WORKSHOP SUMMARIES Caroline Garzon Chief of Nuclear Safety Staff NUCLEAR SAFETY R&D Perform a peer review of Risk Assessment Corporation WTP analysis by a team...

9

NUCLEAR SAFETY WORKSHOP AGENDA Post Fukushima Initiatives and Results  

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

NUCLEAR SAFETY WORKSHOP AGENDA NUCLEAR SAFETY WORKSHOP AGENDA Post Fukushima Initiatives and Results September 19-20, 2012 - Bethesda North Marriott TUESDAY, SEPTEMBER 18 - Grand Ballroom, Salons F/G/H 1 9/14/12 6:00 - 8:00 pm Registration WEDNESDAY, SEPTEMBER 19 - Grand Ballroom, Salons F/G/H 7:00 - 8:00 am Registration 8:00 - 8:05 am Logistics Stephen A. Kirchhoff, Office of Health, Safety and Security US Department of Energy 8:05 - 8:15 am Welcoming Remarks and Workshop Objectives Glenn S. Podonsky, Chief Health, Safety and Security Officer US Department of Energy 8:15 - 8:45 am Maintaining Our Focus on Nuclear Safety Daniel B. Poneman, Deputy Secretary US Department of Energy 8:45 - 9:30 am Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - the

10

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop  

Science Conference Proceedings (OSTI)

This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

Sanchez, R.G. [comp.

1994-01-01T23:59:59.000Z

11

2012 Nuclear Safety Workshop Photos | Department of Energy  

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

You are here You are here Home » 2012 Nuclear Safety Workshop Photos 2012 Nuclear Safety Workshop Photos Addthis Glenn Podonsky 1 of 13 Glenn Podonsky Glenn Podonsky (DOE Chief Health, Safety and Security Officer) provides his welcoming remarks. Daniel Poneman 2 of 13 Daniel Poneman DOE Deputy Secretary Daniel Poneman discusses maintaining our focus on nuclear safety. Akira Kawano 3 of 13 Akira Kawano Akira Kawano, Tokyo Electric Power Company, provides lessons learned from the Fukushima nuclear accident. Bill Ostendorff 4 of 13 Bill Ostendorff NRC Commissioner Bill Ostendorff gives his perspective on the NRC's response to the Fukushima nuclear accident. Miroslav Lipar 5 of 13 Miroslav Lipar Miroslav Lipar, IAEA, provides an international perspective on the Fukushima nuclear accident.

12

A Look Back at the Nuclear Safety Workshop | Department of Energy  

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

nuclear facilities. That is why, in response to the March accident at the Fukushima Daiichi nuclear complex, the Department hosted a Nuclear Safety Workshop to bring...

13

A Look Back at the Nuclear Safety Workshop  

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

Hear from Glenn Podonsky -- the Energy Departments Chief Health, Safety and Security Officer -- about how we're continuing to improve the safety of our nuclear facilities.

14

Proceedings of the Nuclear Criticality Technology Safety Workshop  

SciTech Connect

This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

Rene G. Sanchez

1998-04-01T23:59:59.000Z

15

Nuclear and Facility Safety Policy Rules  

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

Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical Standards Program Search ...

16

2012 DOE Safety System Oversight Workshop Presentation ? Nuclear...  

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

Criteria (Fn Req's, S f t F ) Maintain the I t it f Inspections, Surveillances, Health Safety Fn) Operability Integrity of the Safety Assessments; Manage Configuration Basis...

17

Nuclear Safety Research and Development (NSR&D) Program  

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

Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical Standards Program Search ...

18

Integrated Safety Management Workshop Registration, PIA, Idaho...  

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

Integrated Safety Management Workshop Registration, PIA, Idaho National Laboratory Integrated Safety Management Workshop Registration, PIA, Idaho National Laboratory Integrated...

19

Office of Nuclear Safety  

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

Office of Nuclear Safety (HS-30) Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us

20

Nuclear Safety  

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

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

Note: This page contains sample records for the topic "nuclear safety workshop" 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

2013 DOE Safety and Security Enforcement Workshop  

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

2013 DOE Safety and Security Workshop 2013 Workshop Home Registration Agendas Hotel and Training Center Information Enforcement Home 2013 DOE Safety and Security Enforcement...

22

Safety System Oversight: 2010 Safety System Oversight Workshop  

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

Safety System Oversight Workshop Safety System Oversight Workshop May 12 - 13, 2010 Las Vegas, NV 2010 Facility Representative and Safety System Oversight Workshops Summary: PDF SSO Steering Committee Meeting Minutes: PDF 2009 Safety System Oversight Annual Award Workshop Agenda: PDF Workshop Presentations: Panel Discussion on the Integration of Facility Representatives and Safety System Oversight Personnel at Site Programs Presentation Panel Highlights Introduction, Goals, and Objectives for SSO Workshop Community Update Demographic Survey Results Introduction of the Safety System Oversight Steering Committee Earl Hughes Presentation Oak Ridge Fire Protection SSO Program Pat Smith, Oak Ridge Office Presentation Commercial Grade Dedication Fran Lemieux, NSTec, Nevada Test Site Presentation

23

2007 Integrated Safety Management Workshop  

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

ISM ISM Workshop 2007 a vision for Integrated Safety Management in the Department of Energy complex ISM Workshop 2007 ® Sample of how the graphic may be used on documents where the "Good to Great" verbiage is not includ "Good to Great" is a registered trademark of Jim Collins and is being used with permission. November 27-30, 2007 Hosted by Brookhaven National Laboratory "Good to Great" is a registered trademark of Jim Collins and is being used with permission. 2 Special Thanks Brookhaven National Laboratory Safety, Emergency and Traffic Information Safety, Health and Security Environment, Safety & Health Hotline: 631-344-8800 Occupational Medicine Clinic: 631-344-3670 Security Badging Office: 631-344-5149 Computer Security: 631-344-5522

24

Safety System Oversight: 2010 Safety System Oversight Workshop  

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

Safety System Oversight Office of Nuclear Safety Home Safety System Oversight Home Annual SSO/FR Workshop DOE Safety Links › ORPS Info › Operating Experience Summary › DOE Lessons Learned › Accident Investigation Program Assessment Tools › SSO CRADS Subject Matter Links General Program Information › Program Mission Statement › SSO Program Description › SSO Annual Award Program › SSO Annual Award › SSO Steering Committee › SSO Program Assessment CRAD SSO Logo Items Site Leads and Steering Committee Archive Facility Representative Contact Us HSS Logo SSO SSO 2012 SAFETY SYSTEM OVERSIGHT ANNUAL AWARD Congratulations to Ronnie Alderson, Nevada Field Office, the Winner of the 2012 DOE Safety System Oversight Annual Award! 2012 NOMINEES: Charles Maggart Idaho Operations Office

25

Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop  

Science Conference Proceedings (OSTI)

This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

None

2000-09-01T23:59:59.000Z

26

Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop  

Science Conference Proceedings (OSTI)

This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

2000-09-07T23:59:59.000Z

27

Criticality Safety  

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

Left Tab EVENTS Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical...

28

Integrated Safety Management (ISM) Workshop - August 2009  

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

ISM Workshop Presentations Knoxville Convention Center, Knoxville, TN August 2009 ism logo Track 1: Safety Culture - Taking ISMS to the Next Level Track 2: Worker Engagement Track...

29

The Office of Nuclear Energy Announces Central Europe Nuclear Safety  

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

The Office of Nuclear Energy Announces Central Europe Nuclear The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague October 3, 2011 - 2:04pm Addthis The Office of Nuclear Energy, in partnership with Czech Republic Ministry of Industry and Trade, Ministry of Foreign Affairs, the State Agency for Nuclear Safety of the Czech Republic, and Argonne National Laboratory, is conducting a regional Nuclear Safety Workshop on Trends in Nuclear Power Plant Safety for Robust Civil Nuclear Programs on Oct. 10-13, 2011 in Prague. U.S. Ambassador Norman Eisen and Department of Energy Assistant Secretary for Nuclear Energy Dr. Pete Lyons will deliver speeches welcoming participants. Representatives from the Czech Republic, Bulgaria, Lithuania,

30

Integrated Safety Management Workshop - Building Mission Success  

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

Image layout spacer Integrated Safety Management Workshop - Building Mission Success Acting Deputy Secretary Jeff Kupfer addresses the audience at the 2008 ISM Workshop. Over 500 U.S. Department of Energy and contractor employees started the Labor Day weekend with safety in mind. Hosted by the U.S. Department of Energy's Idaho Operations Office, along with the prime contractors at the Idaho National Laboratory Site, the 2008 Integrated Safety Management Workshop, which was held in Idaho Falls, concluded Aug. 28. Acting Deputy Secretary for the Department of Energy, Jeff Kupfer described the workshop as "the Department of Energy's signature safety event," stating that safety enables the Department's mission success, and complacent work is safety's enemy. Kupfer also noted that workshop participation helps to

31

Fast Reactor Curriculum Workshop - Nuclear Engineering Division...  

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

Fast Reactor Curriculum Workshop Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear...

32

Safety Training Collaborative Workshop Summary Reports | Department of  

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

Safety Training Collaborative Workshop Summary Reports Safety Training Collaborative Workshop Summary Reports Safety Training Collaborative Workshop Summary Reports Performed in Collaboration with DOE National Training Center/National Institute of Environmental Health Sciences The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the Los Alamos National Laboratory (LANL) complex, Idaho National Laboratory (INL) complex, Savannah River Site (SRS) complex and Oak Ridge reservation. Documents Available for Download Idaho Worker Safety Training Workshop Report [January 2011] Los Alamos Worker Safety Training Workshop Report [December 2010] Oak Ridge Worker Safety Training Workshop Report [August 2009] Savannah River Site Worker Safety Training Workshop Report [May 2010]

33

Office of Nuclear Facility Safety Programs: Nuclear Facility Training  

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

Safety (HS-30) Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us » Facility Representative Program

34

2011 DOE Safety and Security Enforcement Workshop  

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

2011 DOE Safety and Security Workshop 2011 DOE Safety and Security Workshop Enforcement Home Registration - CLOSED Agendas Day 1 Agenda and Presentations Day 2 Agenda and Presentations Hotel Information Enforcement Home 2011 DOE Safety and Security Enforcement Workshop Office of Enforcement and Oversight The Office of Health, Safety and Security's (HSS) Office of Enforcement will be hosting its 2011 DOE Safety and Security Enforcement Workshop on the dates and location provided below. When: April 5 - 7, 2011 April 5 and 6 are open to Federal employees and contractors (8 am - 5 pm) April 7 is a half-day session for Federal participants only (8 - 11:30 am) The Energy Facility Contractors Group (EFCOG) Enforcement Coordination Working Group will be holding a meeting on April 7 at the Nevada Support Facility. For more information about that meeting, click here.

35

Nuclear Criticality Safety: Current Activities - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

36

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

37

WORKSHOP ON NUCLEAR DYNAMICS  

E-Print Network (OSTI)

L. Wilets, "Theories of Nuclear Fission", Clarendon Press,of the nuclear force, result in lower calculated fission

Myers, W.D.

2010-01-01T23:59:59.000Z

38

WORKSHOP ON NUCLEAR DYNAMICS  

E-Print Network (OSTI)

Physics of the Office of High Energy and Nuclear Physics ofPhysics of the Office of High Energy and Nuclear Physics ofPhysics of the Office of High Energy and Nuclear Physics of

Myers, W.D.

2010-01-01T23:59:59.000Z

39

WORKSHOP ON NUCLEAR DYNAMICS  

E-Print Network (OSTI)

Complete Events in Medium-Energy Nuclear Collisions" C-Y.+ corrections. (A) The nuclear potential-energy problem isquantum dynamics in high-energy nuclear collisions. We have

Myers, W.D.

2010-01-01T23:59:59.000Z

40

PRIVACY IMPACT ASSESSMENT: Integrated Safety Management Workshop  

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

Integrated Integrated Safety Management Workshop Registration PIA Template Version 3 - May, 2009 Department of Energy Privacy Impact Assessment (PIA) Guidance is provided in the template. See DOE Order 206.1, Department of Energy Privacy Program, Appendix A, Privacy Impact Assessments, for requirements and additional guidance for conducting a PIA: http://www.directives.doe.gov/pdfs/doe/doetextlneword/206/o2061.pdf Please complete electronically: no hand-written submissions will be accepted. This template may not be modified. MODULE 1- PRIVACY NEEDS ASSESSMENT Date Departmental Element&·Slte 16/Jun/09 Idaho National Laboratory Engineering Research Office Building (EROB) Name of-Information System or IT Project Integrated Safety Management Workshop Registration Exhibit Project UID 207765 NewPIA D Update 0 DOE PIA - ISMS Workshop Finallxw.doc N T "tl I

Note: This page contains sample records for the topic "nuclear safety workshop" 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

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

and Safety System Oversight Combined Workshop Panel Discussion: The Integration of Facility Representatives and Safety System Oversight Personnel Panel Highlights i Panel...

42

2013 Integreated Safety Management Champions Workshop - May 15...  

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

Integreated Safety Management Champions Workshop May 15-16, 2013 DOE Forrestal Headquarters Auditorium and Web Conferencing Procedings of the "2013 Special Integrated Safety...

43

9th Annual DOE Laser Safety Officer Workshop  

Science Conference Proceedings (OSTI)

... Annual Department of Energy Laser Safety Officer Workshop is for individuals with laser safety responsibility and interest in a research, industrial or ...

2013-08-08T23:59:59.000Z

44

Integrated Safety Management (ISM) Workshop - November 28-30, 2007  

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

D - Developing Effective Safety Culture D - Developing Effective Safety Culture ISM Workshop Presentations November 28-30, 2007 Wednesday, November 28, 2007 11:00 - 12:30 Tank S-102 Waste Spill, Shirley Olinger, ORP and Jerry Long, CH2MHill Practices in Implementing Human Performance Initiative, Bill Hartley, BWXT Pantex 2:00 - 3:30 Safety Observation to Support Human Performance Improvement, Chris Contwell, Todd Conklin and John Tseng, LANL Human Performance Training and Job Aid for Nuclear Materials Applications, William Brown, BNL Developing Effective Safety Cultures, Dr. Isabel Perry 4:00 - 5:30 Commercial Nuclear Industry Progress on Safety Culture (Sensitive Material - Contact Presenter Directly), George Mortensen, INPO Communication with the Dead is only Slightly Harder than talking with an Engineer, William Rigot, WSRC

45

Nuclear criticality safety guide  

Science Conference Proceedings (OSTI)

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

46

International Workshop on Nuclear Forensics Strengthens Global...  

National Nuclear Security Administration (NNSA)

Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > International Workshop on Nuclear Forensics Strengthens Global Security...

47

Nuclear Safety Regulatory Framework  

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

Department of Energy Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting DOE Directives & Manuals DOE Standards Central Technical Authorities (CTA) Office of Health, Safety, and Security (HSS) Line Management SSO/ FAC Reps 48 CFR 970 48 CFR 952 Federal Acquisition Regulations External Oversight *Defense Nuclear Facility

48

Integrated Safety Management (ISM) - Workshops  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

49

1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM)  

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

1,200 To Attend DOE Safety Workshop - Integrated Safety Management 1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM) Workshop Features Nationally Renowned Speakers 1,200 To Attend DOE Safety Workshop - Integrated Safety Management (ISM) Workshop Features Nationally Renowned Speakers September 9, 2011 - 12:00pm Addthis KENNEWICK, WASH. - The Department of Energy (DOE) offices at Hanford will host the 2011 Integrated Safety Management (ISM) Champions Workshop at the Three Rivers Convention Center in Kennewick for DOE and contractor employees from sites across the country on September 12-15. More than 1,200 people are expected to attend the workshop, which features nationally acclaimed keynote speakers and high-level DOE officials. The workshop agenda also includes tours of Hanford, a safety symposium,

50

Workshop on nuclear power growth and nonproliferation  

Science Conference Proceedings (OSTI)

It is widely viewed that an expansion of nuclear power would have positive energy, economic and environmental benefits for the world. However, there are concerns about the economic competitiveness, safety and proliferation and terrorism risks of nuclear power. The prospects for a dramatic growth in nuclear power will depend on the ability of governments and industry to address these concerns, including the effectiveness of, and the resources devoted to, plans to develop and implement technologies and approaches that strengthen nonproliferation, nuclear materials accountability and nuclear security. In his Prague speech, President Obama stated: 'we should build a new framework for civil nuclear cooperation, including an international fuel bank, so that countries can access peaceful power without increasing the risks of proliferation. That must be the right of every nation that renounces nuclear weapons, especially developing countries embarking on peaceful programs. And no approach will succeed if it's based on the denial of rights to nations that play by the rules. We must harness the power of nuclear energy on behalf of our efforts to combat climate change, and to advance peace opportunity for all people.' How can the President's vision, which will rekindle a vigorous public debate over the future of nuclear power and its relation to proliferation, be realized? What critical issues will frame the reemerging debate? What policies must be put into place to address these issues? Will US policy be marked more by continuity or change? To address these and other questions, the Los Alamos National Laboratory in cooperation with the Woodrow Wilson International Center for Scholars will host a workshop on the future of nuclear power and nonproliferation.

Pilat, Joseph F [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

51

Nuclear criticality safety  

SciTech Connect

Important facts of the nuclear criticality safety field are covered in this volume. Both theoretical and practical aspects of the subject are included, based on insights provided by criticality experts and published information from many sources. An overview of nuclear criticality safety theory and a variety of practical in-plant operation applications are presented. Underlying principles of nuclear criticality safety are introduced and the state of the art of this technical discipline is reviewed. Criticality safety theoretical concepts, accident experience, standards, experiments computer calculations, integration of safety methods into individual practices, and overall facility operations are all included.

Knief, R.A.

1985-01-01T23:59:59.000Z

52

Nuclear Safety Information Dashboard  

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

provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into...

53

Nuclear Physics Science Network Requirements Workshop, May 2008 - Final Report  

E-Print Network (OSTI)

Requirements Workshop Nuclear Physics Program Office, DOEDOE Nuclear Physics Programs .. 6 Nuclear Physics Network Requirementsbandwidth and services requirements. 3 DOE Nuclear Physics

Tierney, Ed., Brian L

2008-01-01T23:59:59.000Z

54

Nuclear Separations Technologies Workshop Report 2011  

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

i i NUCLEAR SEPARATIONS TECHNOLOGIES WORKSHOP REPORT November 7, 2011 FINAL TABLE OF CONTENTS Acronyms and Initialisms............................................................................................................ iii Executive Summary ...................................................................................................................... 1 1. Introduction ............................................................................................................................. 9 1.1 Overview .......................................................................................................................... 9 1.2 Background .................................................................................................................... 10

55

2012 DOE Facility Representatives/Safety System Oversight Workshop...  

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

Safety System Oversight Fire Safety Overall Workshop Agenda May 14-18, 2012 Alexis Park Hotel Las Vegas, Nevada Monday, May 14, 2012 8:00 a.m. - 5:00 p.m. SAF-271, SSO...

56

Nuclear Facility Safety Basis  

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

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS:  10 CFR 830 Subpart B Guidance:  DOE STD 3009  DOE STD 1104  DOE STD  DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830  DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements  DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

57

Office of Nuclear Safety | Department of Energy  

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

Nuclear Safety Office of Nuclear Safety Mission The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of...

58

2012 DOE Safety and Security Enforcement WorkshopOffice of Enforcemen...  

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

2 DOE Safety and Security Enforcement Workshop Enforcement Home 2012 DOE Safety and Security Enforcement Workshop March 27 and 28, 2012 Presentations Agenda Preview and Program...

59

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

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

Criticality Safety Nuclear Criticality Safety Overview Experience Analysis Tools Current NCS Activities Current R&D Activities DOE Criticality Safety Support Group (CSSG) Other...

60

International Safety Projects - Nuclear Engineering Division...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

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


61

Facility Safety Assessment - Nuclear Engineering Division (Argonne...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

62

Safety - Vulnerability Assessment Team - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

63

Nuclear regulation and safety  

SciTech Connect

Nuclear regulation and safety are discussed from the standpoint of a hypothetical country that is in the process of introducing a nuclear power industry and setting up a regulatory system. The national policy is assumed to be in favor of nuclear power. The regulators will have responsibility for economic, reliable electric production as well as for safety. Reactor safety is divided into three parts: shut it down, keep it covered, take out the afterheat. Emergency plans also have to be provided. Ways of keeping the core covered with water are discussed. (DLC)

Hendrie, J.M.

1982-01-01T23:59:59.000Z

64

Intermediate-energy nuclear chemistry workshop  

SciTech Connect

This report contains the proceedings of the LAMPF Intermediate-Energy Nuclear Chemistry Workshop held in Los Alamos, New Mexico, June 23-27, 1980. The first two days of the Workshop were devoted to invited review talks highlighting current experimental and theoretical research activities in intermediate-energy nuclear chemistry and physics. Working panels representing major topic areas carried out indepth appraisals of present research and formulated recommendations for future research directions. The major topic areas were Pion-Nucleus Reactions, Nucleon-Nucleus Reactions and Nuclei Far from Stability, Mesonic Atoms, Exotic Interactions, New Theoretical Approaches, and New Experimental Techniques and New Nuclear Chemistry Facilities.

Butler, G.W.; Giesler, G.C.; Liu, L.C.; Dropesky, B.J.; Knight, J.D.; Lucero, F.; Orth, C.J.

1981-05-01T23:59:59.000Z

65

International Cooperation on Safety of Nuclear Plants - Nuclear...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

66

Current R&D Activities in Nuclear Criticality Safety - Nuclear...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

67

Analysis Tools for Nuclear Criticality Safety - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

68

Nuclear Safety Management  

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

[6450-01-P] [6450-01-P] DEPARTMENT OF ENERGY 10 CFR Part 830 Nuclear Safety Management AGENCY: Department of Energy (DOE). ACTION: Final Rule. SUMMARY: The Department of Energy (DOE) is issuing a final rule regarding Nuclear Safety Management. This Part establishes requirements for the safe management of DOE contractor and subcontractor work at the Department's nuclear facilities. Today's rule adopts the sections that will make up the generally applicable provisions for Part 830. It also adopts the specific section on provisions for developing and implementing a formalized quality assurance program. EFFECTIVE DATE: This regulation becomes effective [insert 30 days after publication in the Federal Register.] FOR FURTHER INFORMATION CONTACT: Frank Hawkins, U.S. Department of Energy, Nuclear Safety

69

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

& Compliance National Security Technologies, LLC Nevada Test Site May 12, 2010 1 Safety System Oversight Workshop, Las Vegas, NV D di ti f C i l G d It Dedication of...

70

Nuclear fuel cycle information workshop  

SciTech Connect

This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work; second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity; and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US.

1983-01-01T23:59:59.000Z

71

Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings  

SciTech Connect

These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission`s Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements.

Dey, M. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Arsenault, F.; Patterson, M.; Gaal, M. [SCIENTECH, Inc., Rockville, MD (United States)

1993-09-01T23:59:59.000Z

72

Office of Nuclear Safety | Department of Energy  

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

Nuclear Safety Office of Nuclear Safety Organization Office of Health and Safety Office of Environmental Protection, Sustainability Support & Corporate Safety Analysis Office of...

73

Safety System Oversight Workshop (May 12-13, 2010) - Agenda  

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

Opening Remarks James Heffner, Facility Representative Program Manager Earl Hughes, Safety System Oversight Program Manager Office of Nuclear Safety Policy and Assistance Office...

74

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

75

December 23, 2010, Los Alamos Worker Safety Training Workshop Report  

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

December 23, 2010 December 23, 2010 MEMORANDUM FOR KEVIN W. SMITH MANAGER LOS ALAMOS SITE OFFICE FROM: LESLEY A. GASPERO . f i'l.1J 4 y---- ACTING DIRECTOR /v ,.., /I NATIONAL TRAININ C .'.fE'R OFFICE OF HEALTH S ETY A SECURITY t SUBJECT: Los Alamos Safety Trainirlg Workshop Report Attached please find the final report from the July 26-27, 2010 Safety Training Collaborative Workshop conducted for the Los Alamos Site Office (LASO), which was attended by key LASO federal, contractor and union representatives. The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the Los Alamos National Laboratory {LANL) complex. It should be noted that LANL has already implemented numerous initiatives to gain efficiencies in safety

76

May 6, 2010, Savannah River Site Safety Training Workshop Report  

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

MAY o G aorn MAY o G aorn MEMORANDUM FOR JACK CRAIG MANAGER SAVANNAH RIVER sr~~ FROM: ARNOLDE.GUEVA~ DIRECTOR NATIONAL TRAINING CENTER OFFICE OF HEAL TH, SAFETY AND SECURITY SUBJECT: Savannah River Site Safety Training Workshop Report Attached please find the final report from the December 8-9, 2009 collaborative safety training workshop conducted in Savannah River Site (SRS), which was attended by key SRS federal, contractor and union representatives. We apologize for the belated delivery of this report. The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the SRS complex. It should be noted that SRS has already implemented numerous initiatives to gain

77

Nuclear Separations Technologies Workshop Report | Department of Energy  

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

Separations Technologies Workshop Report Separations Technologies Workshop Report Nuclear Separations Technologies Workshop Report The Department of Energy (DOE) sponsored a workshop on nuclear separations technologies in Bethesda, Maryland, on July 27 and 28, 2011, to (1) identify common needs and potential requirements in separations technologies and opportunities for program partnerships, and (2) evaluate the need for a DOE nuclear separations center of knowledge to improve cross- program collaboration in separations technology. The workshop supported Goal 3 of the DOE Strategic Plan1 to enhance nuclear security through defense, nonproliferation, and environmental management. The Office of Environmental Management (EM), Office of Nuclear Energy (NE), and National Nuclear Security Administration (NNSA) jointly sponsored the workshop. The Office of Science

78

National Nuclear SecurityAdministration's Nuclear ExplosiveSafety...  

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

National Nuclear SecurityAdministration's Nuclear ExplosiveSafety Study Program, IG-0581 National Nuclear SecurityAdministration's Nuclear ExplosiveSafety Study Program, IG-0581 To...

79

2012 Facility Representative/Safety System Oversight/Fire Safety Workshop Agenda  

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

Facility Representative  Safety System Oversight  Fire Safety Facility Representative  Safety System Oversight  Fire Safety Overall Workshop Agenda May 14-18, 2012  Alexis Park Hotel  Las Vegas, Nevada Monday, May 14, 2012 8:00 a.m. - 5:00 p.m. SAF-271, SSO Assessments (Day 1) Zeus B Quality Assurance Overview for FR/SSO Personnel Zeus A 5:00 p.m. - 7:00 p.m. Workshop Registration Zeus Foyer Tuesday, May 15, 2012 8:00 a.m. - 5:00 p.m. Fire Safety Workshop Track Begins (see track agenda) Parthenon 4 SAF-271, SSO Assessments (Day 2) Zeus B . Safety Culture Workshop Zeus A Federal Technical Capability Panel Parthenon 2 5:00 p.m. - 7:00 p.m. Workshop Registration Zeus Foyer Wednesday, May 16, 2012 6:30 a.m. - 7:45 a.m. Workshop Registration Zeus Foyer 8:00 a.m. - 11:30 a.m. FR/SSO Tracks Begin; Plenary session with Fire Safety Track Parthenon 2 & 4

80

Nuclear reactor safety device  

DOE Patents (OSTI)

A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

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


81

Nuclear Safety and Global Cooperation.  

E-Print Network (OSTI)

??The thesis of is to strengthen the capacity building of nuclear safety and disaster prevention all over the world from a preventive perspective, and to (more)

Chang, Yu-shan

2012-01-01T23:59:59.000Z

82

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

1B * The System Engineer Program is defined by DOE O 420.1B, Chapter V, and applied to safety class and safety significant SSCs as described within each nuclear facility's DOE-...

83

2012 Facility Representative/Safety System Oversight/Fire Safety Workshop - Registrants  

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

Facility Representative / Safety System Oversight Workshop Facility Representative / Safety System Oversight Workshop DOE Fire Safety Workshop Federal Technical Capability Panel (FTCP) Meeting May 14 - 18, 2012, at the Alexis park Resort Hotel, Las Vegas, NV Registrants As of 5/15/2012 Total Number: 218 First Name Last Name Government /Contractor Agency Secretarial Office Site Position Training Course FTCP FS 5/15 FS 5/16 FR/SSO Plenary FR Track SSO Track Fire Safety Training Tour Ron Alderson Government Employee DOE NNSA Nevada SSO SAF-271 No No No Yes No Yes No No Josh Allen Government Employee DOE EM Richland FR No No No No Yes Yes No No No Mark Alsdorf Government Employee DOE HSS Headquarters NTC Safety Training Manager SAF-271 Yes No No Yes No No No No Xavier Aponte Government Employee

84

Office of Nuclear Safety - Directives  

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

Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives The HSS Office of Nuclear Safety is the responsible office for the development, interpretation, and revision of the following Department of Energy (DOE) directives. Go to DOE's Directives Web Page to view these directives. DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

85

Nuclear reactor safety device  

DOE Patents (OSTI)

A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

Hutter, E.

1983-08-15T23:59:59.000Z

86

A Safer Nuclear Enterprise - Application to Nuclear Explosive Safety (NES)(U)  

SciTech Connect

Activities and infrastructure that support nuclear weapons are facing significant challenges. Despite an admirable record and firm commitment to make safety a primary criterion in weapons design, production, handling, and deployment - there is growing apprehension about terrorist acquiring weapons or nuclear material. At the NES Workshop in May 2012, Scott Sagan, who is a proponent of the normal accident cycle, presented. Whether a proponent of the normal accident cycle or High Reliability Organizations - we have to be diligent about our safety record. Constant vigilance is necessary to maintain our admirable safety record and commitment to Nuclear Explosive Safety.

Morris, Tommy J. [Los Alamos National Laboratory

2012-07-05T23:59:59.000Z

87

2013 Integrated Safety Management Champions Workshop - Registration  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

88

DOE/Contractor Fire Safety Workshop Information  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

89

NNSA Hosts International Nuclear Forensics Workshop with Participants from  

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

Hosts International Nuclear Forensics Workshop with Participants from Hosts International Nuclear Forensics Workshop with Participants from Ten Countries | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > NNSA Hosts International Nuclear Forensics Workshop with ... Press Release NNSA Hosts International Nuclear Forensics Workshop with Participants from

90

Reactor Safety Testing and Analysis - Nuclear Engineering Division...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

91

Risk and Safety Assessments - Nuclear Engineering Division (Argonne...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

92

Nuclear Safety Research and Development Committee Charter  

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

Research and Development Committee Charter I. Purpose The intent of the Nuclear Safety Research and Development (NSR&D) Committee is to identify nuclear safety research needs and...

93

Office of Nuclear Facility Safety Programs  

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

Safety Programs establishes requirements related to safety management programs that are essential to the safety of DOE nuclear facilities. In addition, establishes requirements...

94

AIRCRAFT NUCLEAR PROPULSION DEPARTMENT NUCLEAR SAFETY GUIDE  

SciTech Connect

The limitations and operating techniques which were in effect at ANPD for the prevention of criticality accidents are summarized. The standards followed by the atomic industry were followed; however, the safe mass of U/sup 235/ moderated with beryllium oxide and hydrogeneous materials was based upon criticality experiments conducted at ANPD. Although the guide was primarily for the use of the ANPD nuclear safety control organization, it may also be of assistance to designers and operating management in maintaining nuclear safety. (auth)

Pryor, W.A.

1961-06-01T23:59:59.000Z

95

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

A - Work Planning and Control A - Work Planning and Control ISM Workshop Presentations August 25-28, 2008 Wednesday, August 27, 2008 1:00 - 2:30 Safety Directives: Providing a Systems-Based Approach to Directives Management, Steve Kirchoff, DOE-HSS New International Standards and Organizational Principles for Integrated Management Systems, Michael Penders, Esq, Environmental Security International Moving From The Integrated Safety Management System (ISMS) to Integrated Management (IM) to Build Mission Success, Cary Staffo, DOE-EERE 3:00 - 5:00 Integrating Safety and Security into the EMS Life Cycle: A Body Contact Sport, Dennis Hjeresen, Los Alamos A Team Approach to Making Safety Signs Effective, Lynne Coe-Leavitt/Charlene Johnson, INL Managing Chemicals Using an Integrated Lifecycle Strategy at Pacific Northwest National Laboratory, Cindy Caldwell, PNL

96

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

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

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

97

Integrated Safety Management Workshop - Building Mission Success  

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

No. 08-164 September 8, 2008 NRC DOCKETS YUCCA MOUNTAIN APPLICATION, ADOPTS DOE'S ENVIRONMENTAL IMPACT STATEMENT The Nuclear Regulatory Commission has formally docketed the Department of Energy's license application for the proposed high-level nuclear waste repository at Yucca Mountain, Nev. The agency staff has also recommended that the Commission adopt, with further supplementation, DOE's Environmental Impact Statement for the repository project. The decision to docket the application follows the NRC staff's determination that the application, submitted June 3, is sufficiently complete for the staff to begin its full technical review. Docketing the application does not indicate whether the Commission will approve or reject the construction authorization for the repository, nor does it preclude the Commission or the agency staff from requesting additional information from DOE during the course of its comprehensive technical review.

98

Nuclear Security & Safety  

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

The Energy Department is working to enhance nuclear security through defense, nonproliferation, and environmental efforts.

99

2012 DOE Safety System Oversight Workshop Presentation ? QA...  

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

Sykes NA-SH-10 (CDNS staff) Why do we have CSEs and SSOs? CD NS Chief, Defense Nuclear Safety Why do we have CSEs and SSOs? NS , y Why do we have Cognizant System Engineers? * 10...

100

Hanford to Host ISMS Safety Workshop in Kennewick: Abstracts Due in June  

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

Hanford to Host ISMS Safety Workshop in Kennewick: Abstracts Due in Hanford to Host ISMS Safety Workshop in Kennewick: Abstracts Due in June for September Event Hanford to Host ISMS Safety Workshop in Kennewick: Abstracts Due in June for September Event May 18, 2011 - 12:00pm Addthis Media Contact Cameron Hardy, DOE (509) 376-5365 Cameron.Hardy@rl.doe.gov RICHLAND, WASH. - The U.S. Department of Energy (DOE) at Hanford will hold its annual DOE Integrated Safety Management (ISM) Champions Workshop on September 12-15, 2011, at the Three Rivers Convention Center in Kennewick, Wash. DOE's Richland Operations Office and Office of River Protection are hosting this year's event. The purpose of the workshop is to promote a robust safety culture and educate attendees on safety developments and environmental compliance methods for effective implementation of the

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


101

Nuclear Safety: Software Quality Assurance  

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

Nuclear Safety: Software Quality Assurance Nuclear Safety: Software Quality Assurance cd Welcome to the Department of Energy's Office of Health, Safety and Security (HSS) Software Quality Assurance (SQA) homepage. The purpose of this Web site is to promote continuous improvement and the sharing of knowledge of safety software quality assurance among interested parties across the DOE complex. It consolidates information and contains links to subject matter experts, procedures, training material, program descriptions, good practices, lessons learned and the Central Registry Toolbox Codes. The Portal also provides capabilities for member collaboration in product development and threaded discussions. Central Registry: The Central Registry provides a library of DOE "Toolbox" Codes covering site boundary accident dose consequences, fire accident source terms, leakpath factors, chemical release/dispersion and consequence, and radiological dispersion and consequence.

102

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

Panel Discussion Panel Discussion ISM Workshop Presentations August 25-28, 2008 Intergration of Management Systems, Mike Kirkpatrick The Need for Integration of All Functional Areas with Line Management into a Single Management System, Elizabeth Sellers, Idaho Operations Office The Role of Effective Integration in the Successful Startup of the Interim Savannah River Site High Level Waste Salt Processing Campaign, Frank McCoy, Washington Safety Management Solutions Integrating the Environmental and Occupational Safety & Health Management Systems, Jim Tarpinian, Battelle Memorial Institute Integration in Assuring the Successful Startup of the W80 Weapons System Campaign, Greg Meyer, B&W Pantex Resolution of the Hanford Tank Farm Vapor Issues, Mark Spears, CH2M Hill

103

Proceedings: 2012 EPRI Groundwater Protection Workshop, In Collaboration with the Nuclear Energy Institute  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) organized the 2012 EPRI Groundwater Protection Workshop in collaboration with the Nuclear Energy Institute (NEI). The workshop focused on nuclear plant leak prevention, groundwater monitoring and remediation techniques, and industry experience.BackgroundEPRI has conducted 13 such topical workshops over the past decade. In 2005, EPRI conducted a decommissioning topical workshop on groundwater contamination ...

2013-05-02T23:59:59.000Z

104

Integrated Safety Management (ISM) Workshop - April 25-26, 2006  

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

ISM Workshop Presentations Albuquerque, New Mexico April 25-26, 2006 ism logo ISM Workshop: April 25-26, 2006 Workshop Meeting Notes Agenda & Presentations Contractor Break-out...

105

Nuclear Safety (Pennsylvania) | Department of Energy  

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

Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Safety and Operational Guidelines Provider Pennsylvania Department of Environmental Protection The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the activities associated with management and disposal of a low-level radioactive waste disposal facility in Pennsylvania and provides planning and support for Bureau response to incidents involving nuclear power plants and/or radioactive material in

106

Nuclear data for criticality safety  

SciTech Connect

A brief overview is presented on emerging requirements for new criticality safety analyses arising from applications involving nuclear waste management, facility remediation, and the storage of nuclear weapons components. A derivation of criticality analyses from the specifications of national consensus standards is given. These analyses, both static and dynamic, define the needs for nuclear data. Integral data, used primarily for analytical validation, and differential data, used in performing the analyses, are listed, along with desirable margins of uncertainty. Examples are given of needs for additional data to address systems having intermediate neutron energy spectra and/or containing nuclides of intermediate mass number.

Westfall, R.M.

1994-09-01T23:59:59.000Z

107

Executive Summary: Research in Nuclear PowerWorkshop on the Needs of the Next Generation of Nuclear Power Technology  

Science Conference Proceedings (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor

A. David Rossin; Kunmo Chung; K. L. Peddicord

108

International Workshop on Characterization and PIE Needs for Fundamental Understanding of Fuels Performance and Safety  

SciTech Connect

The International Workshop on Characterization and PIE Needs to Support Science-Based Development of Innovative Fuels was held June 16-17, 2011, in Paris, France. The Organization for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA) Working Party on the Fuel Cycle (WPFC) sponsored the workshop to identify gaps in global capabilities that need to be filled to meet projected needs in the 21st century. First and foremost, the workshop brought nine countries and associated international organizations, together in support of common needs for nuclear fuels and materials testing, characterization, PIE, and modeling capabilities. Finland, France, Germany, Republic of Korea, Russian Federation, Sweden, Switzerland, United Kingdom, United States of America, IAEA, and ITU (on behalf of European Union Joint Research Centers) discussed issues and opportunities for future technical advancements and collaborations. Second, the presentations provided a base level of understanding of current international capabilities. Three main categories were covered: (1) status of facilities and near term plans, (2) PIE needs from fuels engineering and material science perspectives, and (3) novel PIE techniques being developed to meet the needs. The International presentations provided valuable data consistent with the outcome of the National Workshop held in March 2011. Finally, the panel discussion on 21st century PIE capabilities, created a unified approach for future collaborations. In conclusion, (1) existing capabilities are not sufficient to meet the needs of a science-based approach, (2) safety issues and fuels behavior during abnormal conditions will receive more focus post-Fukushima; therefore we need to adopt our techniques to those issues, and (3) International collaboration is needed in the areas of codes and standards development for the new techniques.

Not Listed

2011-12-01T23:59:59.000Z

109

Integrated Safety Management (ISM) Workshop - November 28-30, 2007  

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

A - Work Planning and Control A - Work Planning and Control ISM Workshop Presentations November 28-30, 2007 Wednesday, November 28, 2007 11:00 - 12:30 Workplace Hazards Monitoring and Recent Oversight Results, Thomas Staker, DOE-HSS SAFER Dialogue as Pre-Job and Activity Review Tool, Brian Harkins, DOE-ORP Hazard Analysis Process, William Schleyer, DOE-AL 2:00 - 3:30 ISM Implementation at R&D User Facility, Allison Campbell, PNL Experimental Safety Review - SMBS Process, Rob Doty, BNL R&D Work Planning and Control at SRNL, John Miller, SRNL 4:00 - 5:30 A Three Tiered Work Planning Process, Steven Coleman, BNL WSRC Work Planning and Control for all Activity - Level of Work, Tim Flake, WSRC SWPF Construction Work Planning and Control Process, Stephen Lindamood, Persons Thursday, November 29, 2007

110

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

C - Work Planning and Control C - Work Planning and Control ISM Workshop Presentations August 25-28, 2008 Wednesday, August 27, 2009 1:00 - 2:30 Role of ISM in Nano-Material Research at DOE Facilities, Marvin Mielke, DOE-HSS Y-12 Sitewide Risk Management Program, Abe Mathews, NNSA Y12 Applying Safe System Work Control Processes to Integrate Safety Management Achieve Target Zero, Mike Brooks/Adam Hotzel, Bechtel, BWXT Idaho 3:00 - 5:00 Utilizing ISM Core Functions to Control PNNL Contractor Activities, Todd Haynie, PNNL IMWOG Work Management Subgroup Peer Assist Visit Best Practice, Steve Little, B&W Y12 Lean/Six Sigma Approach to Work Control Process Improvements at the WVDP, Joe Jablonski, WVES Integrating Human Performance Improvement into ISMS, T. Shane Bush Thursday, August 28, 2008

111

Nuclear Safety Information Dashboard | Department of Energy  

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

Reporting » Analytical Dashboards » Nuclear Safety Reporting » Analytical Dashboards » Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard The Nuclear Safety Information (NSI) Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. The NSI Dashboard displays information developed from occurrence information reported into DOE's ORPS database. Events or conditions associated with nuclear safety are reported into ORPS, assigned unique ORPS reporting criteria and used for trending. ORPS reporting criteria are assigned a weighted value to indicate their relative importance to nuclear safety; associated ORPS reporting criteria are combined in key groups and charted over time to index trends in nuclear

112

Nuclear Criticality Safety | More Science | ORNL  

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

Criticality Safety Criticality Safety SHARE Criticality Safety Nuclear Criticality Safety ORNL is the lead national laboratory responsible for supporting the National Nuclear Security Administration (NNSA) in managing the US Nuclear Criticality Safety Program. NCSP is chartered to maintain the technical infrastructure (integral experiments, computational tools, training, data, etc.) needed to support safe, efficient fissionable material operations. ORNL has extensive expertise in the area of nuclear criticality safety (NCS) based upon years of experience in the following areas: Operations Support: providing fissionable material operations support for enrichment, fabrication, production, and research; Critical Experiments: performing experiments at the Y-12 Critical Experiment Facility;

113

Nuclear rapprochement in Argentina and Brazil: Workshop summary  

Science Conference Proceedings (OSTI)

On October 21 and 22, 1998, the Center for International Security Affairs at Los Alamos National Laboratory and the Center for Global Security and Cooperation at Science Applications International Corporation hosted the first of a series of work-shops on states that have chosen to roll back their pursuit of nuclear arms. The objective of the workshop series is to conduct a systematic evaluation of the roles played by U.S. nonproliferation policy in cases of nuclear rollback or restraint and to provide recommendations for future nonproliferation efforts based on lessons learned. Key attendees at the workshop included officials and former officials from the foreign ministries of Argentina and Brazil, and current and former officials from the U.S. Department of State, the Arms Control and Disarmament Agency (ACDA), and the Department of Energy (DOE). Scholars and independent researchers who have examined nuclear policy in Argentina and Brazil also participated. This workshop report includes important background information that helps set the stage for assessing nuclear policies in Argentina and Brazil. It describes national perspectives and areas of consensus and debate among the participants, particularly on the questions of lessons learned and their salience to proliferation challenges in other states. It also summarizes key questions and propositions regarding the roles played in these cases by U.S. nonproliferation policy.

James E. Doyle

1999-10-01T23:59:59.000Z

114

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

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

Aerial photo of Argonne National Laboratory Argonne National Laboratory University of Chicago Chicago Photography courtesy Thomas F Ewing Privacy and Security Notice The MMSNF Workshops The goal of the Materials Modeling and Simulation for Nuclear Fuels (MMSNF) workshops is to stimulate research and discussions on modeling and simulations of nuclear fuels, to assist the design of improved fuels and the evaluation of fuel performance. In addition to research focused on existing or improved types of LWR reactors, recent modeling programs, networks, and links have been created to develop innovative nuclear fuels and materials for future generations of nuclear reactors. Examples can be found in Europe (e.g. F-BRIDGE project and ACTINET network and SAMANTHA cooperative network), in the USA (e.g. CASL, NEAMS, CESAR and CMSN network

115

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

DOE Green Energy (OSTI)

Two of the major challenges the U.S. energy sector faces are greenhouse gas emissions and oil that is both imported and potentially reaching a peak (the point at which maximum extraction is reached). Interest in development of both renewable and nuclear energy has been strong because both have potential for overcoming these challenges. Research in both energy sources is ongoing, but relatively little research has focused on the potential benefits of combining nuclear and renewable energy. In September 2011, the Joint Institute for Strategic Energy Analysis (JISEA) convened the Nuclear and Renewable Energy Synergies Workshop at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to identify potential synergies and strategic leveraging opportunities between nuclear energy and renewable energy. Industry, government, and academic thought leaders gathered to identify potential broad categories of synergies and brainstorm topic areas for additional analysis and research and development (R&D). This report records the proceedings and outcomes of the workshop.

Ruth, M.; Antkowiak, M.; Gossett, S.

2011-12-01T23:59:59.000Z

116

Integrated Safety Management (ISM) Workshop - September 12-13...  

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

ISM Workshop Presentations Aurora (near Denver), Colorado September 12-13, 2006 Presentations Topic Summaries Agenda Attendees Note for CIHs...

117

Carlsbad Industrial Safety and Health PIA, Carlsbad Field Offce...  

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

Publications Integrated Safety Management Workshop Registration, PIA, Idaho National Laboratory MOX Services Unclassified Information System PIA, National Nuclear Services...

118

Nuclear containment steel liner corrosion workshop : final summary and recommendation report.  

SciTech Connect

This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanisms of corrosion for the steel liner in nuclear containment buildings. The U.S. Nuclear Regulatory Commission (NRC) sponsored this work which was conducted by Sandia National Laboratories. A workshop was conducted at the NRC Headquarters in Rockville, Maryland on September 2 and 3, 2010. Due to the safety function performed by the liner, the expert panel was assembled in order to address the full range of issues that may contribute to liner corrosion. This report is focused on corrosion that initiates from the outer surface of the liner, the surface that is in contact with the concrete containment building wall. Liner corrosion initiating on the outer diameter (OD) surface has been identified at several nuclear power plants, always associated with foreign material left embedded in the concrete. The potential contributing factors to liner corrosion were broken into five areas for discussion during the workshop. Those include nuclear power plant design and operation, corrosion of steel in contact with concrete, concrete aging and degradation, concrete/steel non-destructive examination (NDE), and concrete repair and corrosion mitigation. This report also includes the expert panel member's recommendations for future research.

Erler, Bryan A. (Erler Engineering Ltd., Chicago, IL); Weyers, Richard E. (Virginia Tech University, Blacksburg, VA); Sagues, Alberto (University of South Florida, Tampa, FL); Petti, Jason P.; Berke, Neal Steven (Tourney Consulting Group, LLC, Kalamazoo, MI); Naus, Dan J. (Oak Ridge National Laboratory, Oak Ridge, TN)

2011-07-01T23:59:59.000Z

119

Nuclear criticality safety: 2-day training course  

SciTech Connect

This compilation of notes is presented as a source reference for the criticality safety course. At the completion of this training course, the attendee will: be able to define terms commonly used in nuclear criticality safety; be able to appreciate the fundamentals of nuclear criticality safety; be able to identify factors which affect nuclear criticality safety; be able to identify examples of criticality controls as used as Los Alamos; be able to identify examples of circumstances present during criticality accidents; have participated in conducting two critical experiments; be asked to complete a critique of the nuclear criticality safety training course.

Schlesser, J.A. [ed.] [comp.

1997-02-01T23:59:59.000Z

120

Western University Nuclear Radiation Safety Inspection Checklist  

E-Print Network (OSTI)

with unsealed nuclear substances. Print out of wipe test kept in the logbook . For safety work practices, rightMay 2012 Western University Nuclear Radiation Safety Inspection Checklist Permit Holder to nuclear substances or radiation devices is restricted to authorized radiation users listed on the permit

Sinnamon, Gordon J.

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


121

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

122

DOE Nuclear Criticality Safety Program - Nuclear Engineering Division  

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

DOE Nuclear Criticality Safety Program DOE Nuclear Criticality Safety Program Nuclear Criticality Safety Overview Experience Analysis Tools Current NCS Activities Current R&D Activities DOE Criticality Safety Support Group (CSSG) Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr The DOE Nuclear Criticality Safety Program Bookmark and Share J. Morman and R. Bucher load J. Morman and R. Bucher load samples into the ZPR-6 critical assembly for material worth measurements. Click on image to view larger image. The DOE Nuclear Criticality Safety Program (NCSP) is focused on maintaining fundamental infrastructure that enables retention of DOE capabilities and expertise in nuclear criticality safety necessary to support line

123

FAQS Reference Guide Nuclear Safety Specialist  

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

This reference guide addresses the competency statements in the November 2007 edition of DOE-STD-1183-2007, Nuclear Safety Specialist Functional Area Qualification Standard.

124

Facility Representative Program: Nuclear Safety Basis Fundamentals...  

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

Qualification Information Qualification Standards DOE Order Self-Study Modules DOE Fundamentals Handbooks Nuclear Safety Basis Self-Study Guide Energy Online Courses Available...

125

Nuclear Safety Technical Positions/Interpretations  

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

(OPI) responsible for the development, interpretation, and revision of a number of DOE directives. Technical Positions to directives issued by Nuclear and Facility Safety...

126

Report of workshop on radiological effects of nuclear war, SCOPE-ENUWAR workshop, Moscow, USSR, March 21-25, 1988  

Science Conference Proceedings (OSTI)

The workshop on radiological consequences of nuclear war addressed specific issues that built on the foundation of the results that were published in the SCOPE-ENUWAR report (SCOPE-28) in 1986. 14 refs.

Shapiro, C.S.

1988-03-01T23:59:59.000Z

127

NUCLEAR SAFETY SPECIALIST QUALIFICATION STANDARD REFERENCE GUIDE  

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

Nuclear Nuclear Safety Specialist Qualification Standard Reference Guide AUGUST 2008 This page is intentionally blank. i Table of Contents LIST OF FIGURES ..................................................................................................................... iv LIST OF TABLES ........................................................................................................................ v ACRONYMS ................................................................................................................................ vi PURPOSE...................................................................................................................................... 1 SCOPE ...........................................................................................................................................

128

August 21, 2009, Transmittal Memorandum and ORO safety Training Workshop Report  

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

August 21, 2009 August 21, 2009 MEMORANDUM FOR GERALD BOYD MANAGER FROM: SUBJECT: OAK RIDGE OFFICE TED SHERRY MANAGER Y-12 SITE OFFICE /\fl; ARNOLD E. GUEVA~ ACTING DIRECTOR NATIONAL TRAINING CENTER OFFICE OF HEAL TH, SAFETY AND SECURITY OR/YSO Safety Training Workshop Report Attached please find the final report from the July 21 -22, 2009 collaborative safety training workshop conducted in Oak Ridge, which was attended by key Oak Ridge Office (OR) and Y-12 Plant federal, contractor and union representatives. The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the Oak Ridge reservation. It should be noted that OR and the Y-12 Site Office (YSO) have already implemented numerous initiatives to gain efficiencies in

129

January 20, 2011, Memo for Idaho National Laboratory Safety Training Collaboration Workshop Summary Report  

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

January 20, 2011 January 20, 2011 MEMORANDUM FOR RICHARD B. PROVENCHER MANAGER IDAHO OPERATIONS OFFICE FROM: SUBJECT: LESLEY A. GASPEROW ACTING DIRECTOR NATIONAL TRAINING C OFFICE OF HEALTH, SAF TER Y AND SECURITY Idaho Safety Training Workshop Report Attached is the final report from the October 19-20, 2010 Safety Training Collaborative Workshop conducted for the Idaho Operations Office (DOE-ID), which was attended by key DOE-ID federal, contractor and union representatives. The report provides results and recommendations developed by workshop attendees on possible enhancements to the safety training programs across the Idaho National Laboratory (INL) complex. It should be noted that INL has already implemented numerous initiatives to gain efficiencies in safety training,

130

Nuclear Explosive Safety Study Process  

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

3015-2001 3015-2001 February 2001 Superseding DOE-STD-3015-97 January 1997 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY PROCESS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3015-2001 iii CONTENTS FOREWORD . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v 1. PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2. SCOPE . . . . . . . . . . . . . . . . . . . . . . .

131

The history of nuclear weapon safety devices  

SciTech Connect

The paper presents the history of safety devices used in nuclear weapons from the early days of separables to the latest advancements in MicroElectroMechanical Systems (MEMS). Although the paper focuses on devices, the principles of Enhanced Nuclear Detonation Safety implementation will also be presented.

Plummer, D.W.; Greenwood, W.H.

1998-06-01T23:59:59.000Z

132

Report of the Advanced Neutron Source (ANS) safety workshop, Knoxville, Tennessee, October 25--26, 1988  

SciTech Connect

On October 25--26, 1988, about 60 people took part in an Advanced Neutron Source (ANS) Safety Workshop, organized in cooperation with the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) and held in Knoxville, Tennessee. After a plenary session at which ANS Project staff presented status reports on the ANS design, research and development (R and D), and safety analysis efforts, the workshop broke into three working groups, each covering a different topic: Environmental and Waste Management, Applicable Regulatory Safety Criteria and Goals, and Reactor Concepts. Each group was asked to review the Project's approach to safety-related issues and to provide guidance on future reactor safety needs or directions for the Project. With the help of able chairmen, assisted by reporters and secretarial support, the working groups were extremely successful. Draft reports from each group were prepared before the workshop closed, and the major findings of each group were presented for review and discussion by the entire workshop attendance. This report contains the final version of the group reports, incorporating the results of the overall review by all the workshop participants.

Buchanan, J.R.; Dumont, J.N.; Kendrick, C.M.; Row, T.H.; Thompson, P.B.; West, C.D.; Marchaterre, J.F.; Muhlheim, M.D.; McBee, M.R. (comp.)

1988-12-01T23:59:59.000Z

133

Integrated Safety Management (ISM) Workshop - November 28-30...  

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

E - Implementing DOE ISM Requirements ISM Workshop Presentations November 28-30, 2007 Thursday, November 29, 2007 1:30 - 3:00 Panel Discussion on Best Practices and Lessons...

134

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

SciTech Connect

Two of the major challenges the U.S. energy sector faces are greenhouse gas emissions and oil that is both imported and potentially reaching a peak (the point at which maximum extraction is reached). Interest in development of both renewable and nuclear energy has been strong because both have potential for overcoming these challenges. Research in both energy sources is ongoing, but relatively little research has focused on the potential benefits of combining nuclear and renewable energy. In September 2011, the Joint Institute for Strategic Energy Analysis (JISEA) convened the Nuclear and Renewable Energy Synergies Workshop at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to identify potential synergies and strategic leveraging opportunities between nuclear energy and renewable energy. Industry, government, and academic thought leaders gathered to identify potential broad categories of synergies and brainstorm topic areas for additional analysis and research and development (R&D). This report records the proceedings and outcomes of the workshop.

Ruth, M.; Antkowiak, M.; Gossett, S.

2011-12-01T23:59:59.000Z

135

U.S. and India Conclude First Workshop of the Civil Nuclear Working Group |  

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

Conclude First Workshop of the Civil Nuclear Working Conclude First Workshop of the Civil Nuclear Working Group U.S. and India Conclude First Workshop of the Civil Nuclear Working Group January 12, 2006 - 10:31am Addthis Aimed at Fostering Cooperation on Peaceful Uses of Nuclear Energy MUMBAI, INDIA -- The U.S. and India today concluded a four-day workshop on civilian nuclear energy, building on the U.S.-India Energy Dialogue initiated by President George W. Bush and Indian Prime Minister Manmohan Singh in September 2004, and launched by Secretary of Energy Samuel Bodman and India Deputy Chairman of Planning Commission Dr. Montek Singh Ahluwalia in May, 2005. The U.S. was represented at the first workshop of the Civil Nuclear Working Group by R. Shane Johnson, acting director of the U.S. Department of Energy's Office of Nuclear Energy, Science and Technology. India was

136

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

Maximizing SSO Maximizing SSO Effectiveness SSO for 99 Safety Systems SSO o 99 Sa ety Syste s 1 LASO SSO Work Breadth LASO SSO Work Breadth 99 Safety Systems covered by 7 Safety 99...

137

Y-12 PLANT NUCLEAR SAFETY HANDBOOK  

SciTech Connect

Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

Wachter, J.W. ed.; Bailey, M.L.; Cagle, T.J.; Mee, W.T.; Pletz, R.H.; Welfare, F.G.; Youngblood, B.J. comps

1963-03-27T23:59:59.000Z

138

Independent Oversight Assessment of the Nuclear Safety Culture...  

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

and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization...

139

Proceedings of the Neighborhood Electric Vehicle Workshop  

E-Print Network (OSTI)

Electric Vehicle Workshop Proceedings Vehicle Safety DesignElectric Vehicle Workshop Proceedings Federal Motor Vehicle SafetyElectric Vehicle Workshop Proceedings FEDERAL MOTOR VEHICLE SAFETY

Lipman, Timothy

1994-01-01T23:59:59.000Z

140

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

Miller Creating a Safety Culture in a High Reliability Organization, Greg Meyer, B&W Pantex Status of EFCOG-DOE ISMS Safety Culture Task, John McDonald, DOE-HSS 3:00 - 5:00...

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


141

Nuclear criticality safety department training implementation  

SciTech Connect

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document.

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1996-09-06T23:59:59.000Z

142

Nuclear data needs for application in nuclear criticality safety programs  

SciTech Connect

In nuclear criticality safety applications, a number of important uncertainties have to be addressed to establish the required criticality safety margin of a nuclear system. One source of these uncertainties is the basic nuclear data used to calculate the effective multiplication factor of the system. Before criticality safety calculations are performed, the bias and uncertainties of the codes and cross sections that are used must be determined. Cross-section data are measured, evaluated, and tested prior to their inclusion in nuclear data libraries. Traditionally, nuclear data evaluations are performed to support the analysis and design of thermal and fast reactors. The neutron spectra characteristic of the thermal and fast systems used for data testing are predominantly in the low- and high-energy ranges, with a relatively minor influence from the intermediate-energy range. In the area of nuclear criticality safety, nuclear systems involving spent fuel elements from reactors can lead to situations very different from those most commonly found in reactor analysis and design. These systems are not limited to thermal or fast neutron spectra and may have their most significant influence from the intermediate energy range. This requires extending the range of applicability of the nuclear data evaluation beyond thermal and fast systems. The aim here is to focus on the evaluated nuclear data pertaining to applications in nuclear criticality safety.

Leal, L.C.; Westfall, R.M.; Jordan, W.C.; Wright, R.Q. [Oak Ridge National Lab., TN (United States). Computational Physics and Engineering Div.

1995-09-01T23:59:59.000Z

143

Association of State Dam Safety Officials (ASDSO)/EPRI Spillway Gate Workshop: January 5 & 6, 2000  

Science Conference Proceedings (OSTI)

Maintaining the integrity of dams at hydroelectric projects is essential to the protection of communities, the surrounding environment, and the power and resource management infrastructure. The Spillway Gate Workshop, sponsored by the Association of State Dam Safety Officials (ASDSO) and EPRI, and with funding from the Federal Emergency Management Agency (FEMA), focused on a critical aspect of the safety issues related to analysis, inspection, maintenance, and performance of spillway gates. The intent of...

2000-06-16T23:59:59.000Z

144

Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

SciTech Connect

Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

1994-02-01T23:59:59.000Z

145

Sharing of Nuclear Safety Information through Distributed Database Systems  

SciTech Connect

This presentation discusses the sharing of nuclear safety information through distributed database systems.

Ley, H.

2004-10-03T23:59:59.000Z

146

FAQS Qualification Card - Nuclear Safety Specialist | Department of  

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

Nuclear Safety Specialist Nuclear Safety Specialist FAQS Qualification Card - Nuclear Safety Specialist A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearSafetySpecialist-2007.docx Description Nuclear Safety Specialist Qualification Card - 2007 FAQC-NuclearSafetySpecialist-2004.docx

147

Nuclear data for criticality safety - current issues  

SciTech Connect

Traditionally, nuclear data evaluations have been performed in support of the analysis and design of thermal and fast reactors. In general, the neutron spectra characteristic of the thermal and fast systems used for data testing are predominantly in the low- and high-energy range with a relatively small influence from the intermediate-energy range. In the area of nuclear criticality safety, nuclear systems arising from applications involving fissionable materials outside reactors can lead to situations very different from those most commonly found in reactor analysis and design. These systems are not limited to thermal or fast and may have significant influence from the intermediate energy range. The extension of the range of applicability of the nuclear data evaluation beyond thermal and fast systems is therefore needed to cover problems found in nuclear criticality safety. Before criticality safety calculations are performed, the bias and uncertainties of the codes and cross sections that are used must be determined. The most common sources of uncertainties, in general, are the calculational methodologies and the uncertainties related to the nuclear data, such as the microscopic cross sections, entering into the calculational procedure. The aim here is to focus on the evaluated nuclear data pertaining to applications in nuclear criticality safety.

Leal, L.C.; Jordan, W.C.; Wright, R.Q.

1995-06-01T23:59:59.000Z

148

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

Safety Systems & Engineering Oversight Strategy SSO Conference May 2010 James Hinderer ABSSO Engineer Y 12 Site Office Y-12 Site Office Overview Background Requirements per DOE...

149

Safety System Oversight Workshop (May 12-13, 2010) Presentation...  

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

Facility Representatives and Safety System Oversight Personnel DOE Oversight Policy DOE P 226.1A, Department of Energy Oversight Policy Comprehensive & rigorous assurance system at...

150

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

WSRC ISMS Implementation for Hanford River Corridor Contract, Ray Skwarek, WCH Integrated Safety Management Recertification at Lawrence Livermore National Laboratory, Frank...

151

Integrated Safety Management (ISM) Workshop - November 28-30...  

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

- Integrating Management and Systems Track D - Developing an Effective Safety Culture Track E - Implementing DOE ISM Requirement This page was last updated on Tuesday, December 11...

152

DOE/Contractor Fire Safety Workshop Proceedings, May 14 - May...  

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

and Integrated Testing of Fire and Life Safety Systems: Charles Kilfoil NFPA 652 Fundamentals of Combustible Dusts: Robert F. Bitter Overview: Enterprise-Level Industrial Fire...

153

Intermodal safety research needs report of the sixth workshop on national transportation problems  

DOE Green Energy (OSTI)

This conference brought together DOT policymakers, university principal investigators and other professionals to consider the intermodal safety research requirements of the Department of Transportation. The objectives of the conference were: (1) to highlight safety problems and needed transportation safety research identified by DOT modal safety managers and to stimulate university or university/industry teams to respond with research proposals which emphasize multi-modal applicability and a system view; and (2) to provide a forum for university research groups to inform DOT safety managers of promising new directions in transportation safety research and new tools with which to address safety related problems. The conference addressed the research requirements for safety as identified by the Statement of National Transportation Policy and by the modal safety managers in three principal contexts, each a workshop panel: I, Inter-Institutional Problems of Transportation Safety. Problems were described as: Federal-State, local; Federal-Industry; Federal-Public, Consumer groups. II, Goal Setting and Planning for Transportation Safety Programs. Issues were: modifying risk behavior, safety as a social value, and involving citizens in development of standards as a way of increasing probability of achieving program objectives. III, DOT Information, Management, and Evaluation Systems Requirements. Needs were: data requirements and analytic tools for management of safety programs.

Warshawer, A.J. (ed.)

1976-04-01T23:59:59.000Z

154

Nuclear Safety Enforcement Documents | Department of Energy  

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

Enforcement » Nuclear Safety Enforcement Documents Enforcement » Nuclear Safety Enforcement Documents Nuclear Safety Enforcement Documents Documents Available for Download July 22, 2013 Enforcement Letter, NEL-2013-03 Issued to Lawrence Livermore National Security, LLC related to Programmatic Deficiencies in the Software Quality Assurance Program at the Lawrence Livermore National Laboratory February 12, 2013 Enforcement Letter, NEL-2013-02 Issued to Los Alamos National Security, LLC related to a Radiological Contamination Event at the Los Alamos Neutron Science Center at Los Alamos National Laboratory January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 23, 2012 Enforcement Letter, Controlled Power Company - WEL-2012-02

155

Office of Nuclear Safety Enforcement  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

156

Nuclear Power - Operation, Safety and Environment  

E-Print Network (OSTI)

Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. At the same time, catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, design requirements and facilitated growing interests in advanced nuclear energy systems, next generation nuclear reactors, which are inherently capable to withstand natural disasters and avoid catastrophic consequences without any environmental impact. This book is one in a series of books on nuclear power published by InTech. Under the single-volume cover, we put together such topics as operation, safety, environment and radiation effects. The book is not offering a comprehensive coverage of the material in each area. Instead, selected themes are highlighted by authors of individual chapters representing contemporary interests worldwide. With all diversity of topics in 16 chapters, the integrated system analysis approach of nuclear power operation, safety and environment is the common thread. The goal of the book is to bring nuclear power to our readers as one of the promising energy sources that has a unique potential to meet energy demands with minimized environmental impact, near-zero carbon footprint, and competitive economics via robust potential applications. The book targets everyone as its potential readership groups - students, researchers and practitioners - who are interested to learn about nuclear power.

Tsvetkov, Pavel

2011-09-01T23:59:59.000Z

157

Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings  

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

Joint Institute for Strategic Energy Analysis is operated by the Alliance Joint Institute for Strategic Energy Analysis is operated by the Alliance for Sustainable Energy, LLC, on behalf of the U.S. Department of Energy's National Renewable Energy Laboratory, the University of Colorado-Boulder, the Colorado School of Mines, the Colorado State University, the Massachusetts Institute of Technology, and Stanford University. Contract No. DE-AC36-08GO28308 Nuclear and Renewable Energy Synergies Workshop: Report of Proceedings Mark Ruth, Mark Antkowiak, and Scott Gossett Technical Report NREL/TP-6A30-52256 December 2011 The Joint Institute for Strategic Energy Analysis is operated by the Alliance for Sustainable Energy, LLC, on behalf of the U.S. Department of Energy's National Renewable Energy Laboratory, the University of Colorado-Boulder,

158

World Institute for Nuclear Security Workshop at Y-12 Brings...  

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

Countries represented at the workshop include Argentina, Australia, Brazil, Canada, Indonesia, Jordan, Kazakhstan, Lithuania, Malaysia, Mexico, Morocco, Nigeria, Pakistan, South...

159

Integrated Safety Management (ISM) Workshop - August 25-28, 2008  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

160

Nuclear safety guide TID-7016 Revision 2  

SciTech Connect

The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available, information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

Thomas, J.T.

1980-01-01T23:59:59.000Z

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


161

Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers  

SciTech Connect

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project.

Bougaenko, S.E.; Kraev, A.E. [International Nuclear Safety Center of the Russian MINATOM, Moscow (Russian Federation); Hill, D.L.; Braun, J.C.; Klickman, A.E. [Argonne National Lab., IL (United States). International Nuclear Safety Center

1998-08-01T23:59:59.000Z

162

FAQS Qualification Card - Nuclear Explosive Safety Study | Department of  

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

Nuclear Explosive Safety Study Nuclear Explosive Safety Study FAQS Qualification Card - Nuclear Explosive Safety Study A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearExplosiveSafetyStudy.docx Description Nuclear Explosive Safety Study Qualification Card More Documents & Publications

163

Microsoft Word - Nuclear Safety Reporting Criteria.docx  

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

of other TSROSR requirement (3) Violation of DSA hazard control B. Documented Safety Analysis (DSA) Inadequacies (1) Positive unreviewed safety question C. Nuclear Criticality...

164

Assessment of Nuclear Safety Culture at the Idaho Cleanup Project...  

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

Oversight Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project May 2011 November 2012 Office of Safety and Emergency...

165

Defense Nuclear Facilitiets Safety Board Visit and Site Lead...  

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

Office of Safety and Emergency Management Evaluations Activity Report for the Defense Nuclear Facilities Safety Board Visit and Site Lead Planning Activities at the Los Alamos...

166

Nuclear safety surveillance and control of National Nuclear Safety Administration of PRC during commissioning and operation of nuclear power plants  

Science Conference Proceedings (OSTI)

This article describes the method of nuclear safety surveillance and control of National Nuclear Safety Administration (NNSA) of PRC during commissioning and operation of nuclear power plants (NPPs) and the practice for Qinshan NPP and for Guangdong Daya Bay NPP (GNPS). The results of the practice show that the surveillance models set up for Qinshan NPP and for GNPS commissioning were effective and the surveillance has played an important role for ensuring the quality and safety of the commissioning testing and consequently the nuclear safety of these two plants.

Feng, W.; Zhang, C.

1994-12-31T23:59:59.000Z

167

Program on Technology Innovation: Summary of 2012 EPRI Nuclear Fuel Cycle Assessment Workshop  

Science Conference Proceedings (OSTI)

Government, industry, and academic stakeholders met at an EPRI-sponsored Nuclear Fuel Cycle Assessment Workshop, held July 2324, 2012, to exchange perspectives, plans, and insights concerning how fuel cycle technology options should be evaluated for the purposes of research, development, and demonstration (RD&D) as well as eventual deployment. The workshop reviewed efforts in the screening and assessment of advanced nuclear fuel cycle options for future energy systems and focused on the ...

2012-12-07T23:59:59.000Z

168

June 2010, Risk Assessment in Support of DOE Nuclear Safety  

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

Office of Nuclear Safety Policy and Assistance Office of Nuclear Safety Policy and Assistance Nuclear Safety, Quality Assurance and Environment Information Notice June 2010 1 BACKGROUND & PURPOSE: On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of

169

Siting of nuclear facilities. Selections from Nuclear Safety  

SciTech Connect

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Buchanan, J.R.

1976-07-01T23:59:59.000Z

170

GSO Workshops March 2011  

Science Conference Proceedings (OSTI)

Workshops on GCC Progress Toward Creating a Single Market - Focus on Electrical Safety, Product Safety, and Toys. Purpose: ...

2011-03-02T23:59:59.000Z

171

Small Business Teaming Workshop Program | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

for Our Jobs Our Jobs Working at NNSA Blog Small Business Teaming Workshop Program Home > About Us > Our Operations > Acquisition and Project Management > Small Business >...

172

Environmental safety evaluations for nuclear installations  

SciTech Connect

Environmental safety has been an important consideration in the siting, design, and operation of nuclear installations. As a result there have been very few cases in which the releases of radioactive materials from these installations have posed a dosimetrically significant environmental risk, and almost all of these have been connected with accidents or other unintentional situations. In no situation do the intentional releases from nuclear installations appear to have posed significant environmental risks, and with adequate planning and design a high degree of environmental safety may be assured. Many disciplines are involved in the evaluation of safety for nuclear installations. These include such fundamental ones as physics, chemistry, and biology, and more specialized ones such as meteorology, engineering, ecology, medicine, and electronics. A comprehensive review of environmental surveillance data and estimates of dose commitments from nuclear installations suggests that compared to the doses from background and from fallout, those attributable to the effluents from nuclear facilities have been small and for the most part quite local. it is concluded that, the upper limit of the risk associated with exposure of up to a few millirems per year is indeed small compared to many other commonly accepted risks of living in present day society. (72 refurences) (CH)

Hull, A.P.

1973-01-01T23:59:59.000Z

173

Nuclear Safety Research and Development Committee Charter  

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

Research and Development Committee Charter Research and Development Committee Charter I. Purpose The intent of the Nuclear Safety Research and Development (NSR&D) Committee is to identify nuclear safety research needs and opportunities within the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) and their program offices. The Committee promotes communication and coordination among DOE and NNSA program offices to enhance synergy on NSR&D efforts that can benefit the Department. The Committee will foster and facilitate networking and information exchange on NSR&D needs and activities across DOE/NNSA programs and with external national and international organizations. The Committee should not be construed to have any authority to direct DOE and/or NNSA program

174

Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT | Department...  

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

of DOE nuclear facilities. Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT More Documents & Publications Code of Federal Regulations TRESPASSING ON DEPARTMENT OF ENERGY...

175

NNSA, Tajikistan Nuclear and Radiation Safety Agency Sign MOU...  

National Nuclear Security Administration (NNSA)

Tajikistan Nuclear and Radiation Safety Agency Sign MOU to Combat Illicit Trafficking | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing...

176

Management of National Nuclear Power Programs for assured safety  

SciTech Connect

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

Connolly, T.J. (ed.)

1985-01-01T23:59:59.000Z

177

FTCP Site Specific Information - Chief of Nuclear Safety | Department...  

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

of Nuclear Safety FTCP Site Specific Information - Chief of Nuclear Safety FTCP Agent Organization Name Phone E-Mail CNS Richard Lagdon 202586-9471 chip.lagdon@hq.doe.gov...

178

Technical Basis for U. S. Department of Energy Nuclear Safety...  

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

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1, 711 Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1,...

179

Safety of Decommissioning of Nuclear Facilities  

Science Conference Proceedings (OSTI)

Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

Batandjieva, B.; Warnecke, E.; Coates, R. [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

180

Workshop on the Role of the Nuclear Physics Research Community in Combating Terrorism: Scientific Posters  

DOE Data Explorer (OSTI)

This 2002 workshop brought together members of the nation's nuclear physics research community with expertise in nuclear physics, detector development, and accelerator development from DOE and NSF laboratories and universities, with terrorism experts from government agencies familiar with technologies, strategies and policy for the combat of terrorism. The focus of the workshop included conventional explosive and weapon detection and radiological and nuclear threats. Each of these topics included research for field applications, detector and accelerator research in transportation (air, surface, maritime), detector and accelerator research in laboratory forensic detection and preventive measures against clandestine activities [Copied, with editing, from http://www.sc.doe.gov/np/homeland/descript.html]. Of the 45 posters presented at the workshop, 35 have been made available in PDF format on this webpage. The 62 page report from the workshop is also available at http://www.sc.doe.gov/np/homeland/index.html.

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


181

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers  

SciTech Connect

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these joint projects are given.

Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

2000-05-05T23:59:59.000Z

182

Department of Energy to Co-Sponsor Workshop on Nuclear Power Plant Life Extension R&D  

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

The U.S. Department of Energy (DOE), U.S. Nuclear Regulatory Commission (NRC), and the Nuclear Energy Institute (NEI) will co-sponsor a Second Workshop on U.S. Nuclear Power Plant Life Extension Research and Development.

183

Nuclear Physics Science Network Requirements Workshop, May 2008 - Final Report  

Science Conference Proceedings (OSTI)

The Energy Sciences Network (ESnet) is the primary provider of network connectivity for the US Department of Energy Office of Science, the single largest supporter of basic research in the physical sciences in the United States of America. In support of the Office of Science programs, ESnet regularly updates and refreshes its understanding of the networking requirements of the instruments, facilities, scientists, and science programs that it serves. This focus has helped ESnet to be a highly successful enabler of scientific discovery for over 20 years. In May 2008, ESnet and the Nuclear Physics (NP) Program Office of the DOE Office of Science organized a workshop to characterize the networking requirements of the science programs funded by the NP Program Office. Most of the key DOE sites for NP related work will require significant increases in network bandwidth in the 5 year time frame. This includes roughly 40 Gbps for BNL, and 20 Gbps for NERSC. Total transatlantic requirements are on the order of 40 Gbps, and transpacific requirements are on the order of 30 Gbps. Other key sites are Vanderbilt University and MIT, which will need on the order of 20 Gbps bandwidth to support data transfers for the CMS Heavy Ion program. In addition to bandwidth requirements, the workshop emphasized several points in regard to science process and collaboration. One key point is the heavy reliance on Grid tools and infrastructure (both PKI and tools such as GridFTP) by the NP community. The reliance on Grid software is expected to increase in the future. Therefore, continued development and support of Grid software is very important to the NP science community. Another key finding is that scientific productivity is greatly enhanced by easy researcher-local access to instrument data. This is driving the creation of distributed repositories for instrument data at collaborating institutions, along with a corresponding increase in demand for network-based data transfers and the tools to manage those transfers effectively. Network reliability is also becoming more important as there is often a narrow window between data collection and data archiving when transfer and analysis can be done. The instruments do not stop producing data, so extended network outages can result in data loss due to analysis pipeline stalls. Finally, as the scope of collaboration continues to increase, collaboration tools such as audio and video conferencing are becoming ever more critical to the productivity of scientific collaborations.

Tierney, Ed., Brian L; Dart, Ed., Eli; Carlson, Rich; Dattoria, Vince; Ernest, Michael; Hitchcock, Daniel; Johnston, William; Kowalski, Andy; Lauret, Jerome; Maguire, Charles; Olson, Douglas; Purschke, Martin; Rai, Gulshan; Watson, Chip; Vale, Carla

2008-11-10T23:59:59.000Z

184

Nuclear and Facility Safety Directives | Department of Energy  

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

Nuclear Safety » Nuclear and Facility Safety Nuclear Safety » Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment. HS-30 Contact: James O'Brien

185

Nuclear Safety Specialist Functional Area Qualification Standard  

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

83-2007 83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1183-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1183-2007 iv INTENTIONALLY BLANK DOE-STD-1183-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................9

186

Double-clad nuclear fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, William H. (Los Altos, CA); Atcheson, Donald B. (Cupertino, CA); Vaidyanathan, Swaminathan (San Jose, CA)

1984-01-01T23:59:59.000Z

187

Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants  

SciTech Connect

This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States); Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications

1995-03-01T23:59:59.000Z

188

DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules |  

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

Safety and Ecology Corp. for Violating Nuclear Safety Safety and Ecology Corp. for Violating Nuclear Safety Rules DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules June 14, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Safety and Ecology Corporation, the contractor responsible for radiological safety at the Portsmouth Gaseous Diffusion Project in Portsmouth, Ohio, that it will fine the company $55,000 for violating the department's regulations prohibiting retaliation against employees who raise nuclear safety concerns. "We take safety very seriously at the Department of Energy," said Assistant Secretary for Environment, Safety and Health John Shaw. "Today's action illustrates the department's commitment to ensuring that any and all valid

189

Proceedings: EPRI/NEI Technical Information Workshop - Nuclear Plant Groundwater Monitoring  

Science Conference Proceedings (OSTI)

The EPRI Groundwater Protection Workshop focused on the subject of groundwater monitoring related to nuclear plant sites. This subject is very important to both decommissioning and operating plants. The Workshop provided information to assist operating plants in the development of technically sound plant site groundwater monitoring programs. Presentations provided the latest information on groundwater assessments, such as related tools, strategies, technologies and experience. The program included inform...

2007-07-19T23:59:59.000Z

190

Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight  

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

Safety Culture in the US Nuclear Regulatory Commission's Reactor Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process September 19, 2012 Presenter: Undine Shoop, Chief, Health Physics and Human Performance Branch, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission Topics covered: Purpose of the Reactor Oversight Process (ROP) ROP Framework Safety Culture within the ROP Safety Culture Assessments Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process More Documents & Publications A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11

191

Facility Representative Program: 2010 Facility Representative Workshop  

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

10 Facility Representative Workshop 10 Facility Representative Workshop May 12 - 13, 2010 Las Vegas, NV Facility Rep of the Year Award | Attendees | Summary Report Workshop Agenda and Presentations Day 1: Wednesday, May 12, 2010 8:00 a.m. Opening Remarks James Heffner, Facility Representative Program Manager Earl Hughes, Safety System Oversight Program Manager Office of Nuclear Safety Policy and Assistance Office of Health, Safety and Security 8:15 a.m. Welcome from the Nevada Site Office John Mallin, Deputy Assistant Manager for Site Operations Nevada Site Office 8:30 a.m. Workshop Keynote Address Todd Lapointe Chief of Nuclear Safety Central Technical Authority Staff 9:15 a.m. Facility Representative and Safety System Oversight Award Ceremony James Heffner, Facility Representative Program Manager

192

Development of the DOE Nuclear Criticality Safety Program Web Site for the Nuclear Criticality Safety Professional  

SciTech Connect

Development of the DOE Nuclear Criticality Safety Program (NCSP) web site is the result of the efforts of marry members of the Nuclear Criticality Safety (NCS) community and is maintained by Lawrence Livermore National Laboratory under the direction of the NCSP Management Team. This World Wide Web (WWW) resource was developed as part of the DOE response to the DNFSB Recommendation 97-2, which reflected the need to make criticality safety information available to a wide audience. The NCSP web site provides information of interest to NCS professionals and includes links to other sites actively involved in the collection and dissemination of criticality safety information. To the extent possible, the hyperlinks on this web site direct the user to the original source of the referenced material in order to ensure access to the latest, most accurate version.

Lee, C.K.; Huang, S.; Morman, J.A.; Garcia, A.S.

2000-02-01T23:59:59.000Z

193

Enforcement Regulations and Directives - Nuclear Safety | Department of  

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

Nuclear Safety Nuclear Safety Enforcement Regulations and Directives - Nuclear Safety 10 C.F.R. Part 820 and Amendments 10 C.F.R. Part 820 - Procedural Rules for DOE Nuclear Activities 10 C.F.R. Part 820 - Procedural Rules for DOE Nuclear Activities; General Statement of Enforcement Policy; Final rule; amendment of enforcement policy statement and confirmation of interim rule 10 C.F.R. Part 830 10 C.F.R. Part 830 - Nuclear Safety Management; Final Rule Office of General Counsel Interpretation regarding the Application of DOE Technical Standard 1027-92 under 10 C.F.R. Part 830 Office of General Counsel Interpretation regarding Noncompliant Documented Safety Analyses and Exemption Relief (9/28/2011) Related Guidance DOE-STD-1083-2009, Processing Exemptions to Nuclear Safety Rules and

194

Workshops  

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

NASA Tools for Remote-Sensing in Ecology Research NASA Tools for Remote-Sensing in Ecology Research NASA Tools for Remote-Sensing in Ecology Research Ecological Society of America Annual Meeting WK 2 Pittsburgh, PA - July 31, 2010 Abstract Land remote sensing data can be effectively used by ecologists to understand ecosystem dynamics and to expand site measurements to larger scales. These data can be used to improve our understanding of processes occurring on land and in the lower atmosphere, and play a vital role tin the development of global interactive Earth system models used to predict global change. However, most remote sensing products require special knowledge and software packages to extract information useful for ecologists. This workshop will focus on NASA's MODIS (Moderate Resolution Imaging Spectroradiometer) which views the Earth's surface every 2 to 8

195

Princeton Plasma Physics Lab - Nuclear safety  

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

safety Actions taken to safety Actions taken to prevent nuclear and radiation accidents or to limit their consequences. en Celebrating the 20th anniversary of the tritium shot heard around the world http://www.pppl.gov/news/2013/12/celebrating-20th-anniversary-tritium-shot-heard-around-world-2

Tensions rose in the U.S. Department of Energy's (DOE) Princeton Plasma Physics Laboratory (PPPL) as the seconds counted down. At stake was the first crucial test of a high-powered mixture of fuel for producing fusion energy. As the control-room clock reached "zero," a flash of light on a closed-circuit television monitor marked a historic achievement:

196

HANFORD NUCLEAR CRITICALITY SAFETY PROGRAM DATABASE  

Science Conference Proceedings (OSTI)

The Hanford Database is a useful information retrieval tool for a criticality safety practitioner. The database contains nuclear criticality literature screened for parameter studies. The entries, characterized with a value index, are segregated into 16 major and six minor categories. A majority of the screened entries have abstracts and a limited number are connected to the Office of Scientific and Technology Information (OSTI) database of full-size documents. Simple and complex searches of the data can be accomplished very rapidly and the end-product of the searches could be a full-size document. The paper contains a description of the database, user instructions, and a number of examples.

TOFFER, H.

2005-05-02T23:59:59.000Z

197

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

198

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

199

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

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

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

200

Microsoft Word - Nuclear Safety Pamphlet Final September 1 2010...  

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

A Basic Overview of NUCLEAR SAFETY AT THE DEPARTMENT OF ENERGY Outreach & Awareness Series Office of Health, Safety and Security (HSS) U.S. Department of Energy September 2010...

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


201

Applicability of trends in nuclear safety analysis to space nuclear power systems  

SciTech Connect

A survey is presented of some current trends in nuclear safety analysis that may be relevant to space nuclear power systems. This includes: lessons learned from operating power reactor safety and licensing; approaches to the safety design of advanced and novel reactors and facilities; the roles of risk assessment, extremely unlikely accidents, safety goals/targets; and risk-benefit analysis and communication.

Bari, R.A.

1992-10-01T23:59:59.000Z

202

Tutorial on nuclear thermal propulsion safety for Mars  

DOE Green Energy (OSTI)

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-01-01T23:59:59.000Z

203

Tutorial on nuclear thermal propulsion safety for Mars  

DOE Green Energy (OSTI)

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-08-01T23:59:59.000Z

204

Spent Nuclear Fuel project integrated safety management plan  

SciTech Connect

This document is being revised in its entirety and the document title is being revised to ``Spent Nuclear Fuel Project Integrated Safety Management Plan.

Daschke, K.D.

1996-09-17T23:59:59.000Z

205

Assessment of Nuclear Safety Culture at the Salt Waste Processing...  

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

BARS Behavioral Anchored Rating Scales DNFSB Defense Nuclear Facilities Safety Board DOE U.S. Department of Energy DPO Differing Professional Opinion ECP Employee Concern...

206

Nuclear Safety Component and Services Procurement, June 29, 2011...  

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

Office of Enforcement and Oversight Criteria Review and Approach Document Subject: Nuclear Safety Component and Services Procurement Inspection Criteria, Inspection Activities,...

207

DOE's Nuclear Weapons Complex: Challenges to Safety, Security...  

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

and Investigations Committee on Energy and Commerce U.S. House of Representatives "DOE's Nuclear Weapons Complex: Challenges to Safety, Security, and Taxpayer Stewardship" FOR...

208

NNSA and Defense Nuclear Facilities Safety Board certifications...  

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

allocated funding NNSA and Defense Nuclear Facilities Safety Board certifications free up 47 million in previously allocated funding The DNFSB and NNSA required the CMRR...

209

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

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

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

210

Recent Progress in U.S. Nuclear Power Plant Safety  

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

Recent Progress in U.S. Nuclear Power Plant Safety Speaker(s): Robert Budnitz Date: April 15, 2010 - 12:00pm Location: 90-3122 The U.S. commercial nuclear-power industry consists...

211

Nuclear Safety Information Dashboard QuickStart Guide  

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

Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard QuickStart Guide September 2012 Office of Analysis (HS-24) Office of Environmental Protection, Sustainability Support and Corporate Safety Analysis Office of Health, Safety and Security (HSS) Purpose of Nuclear Safety Information (NSI) Dashboard * The NSI Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. * ORPS reporting criteria associated with events at nuclear facilities have pre-assigned weighting factors according to their relative importance and are placed into groups. * This information can be evaluated to identify trends and, using insights from current events and nature of operations, enable

212

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope  

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

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

213

Experience with performance based training of nuclear criticality safety engineers  

SciTech Connect

For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas.

Taylor, R.G.

1993-07-13T23:59:59.000Z

214

Application of Risk Assessment and Management to Nuclear Safety |  

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

Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety September 20, 2012 Presenter: Commissioner George Apostolakis US Nuclear Regulatory Commission Topics covered: Management of (unquantified at the time) uncertainty was always a concern. Defense-in-depth and safety margins became embedded in the regulations. "Defense-in-Depth is an element of the NRC's safety philosophy that employs successive compensatory measures to prevent accidents or mitigate damage if a malfunction, accident, or naturally caused event occurs at a nuclear facility." [Commission's White Paper, February 1999] Design Basis Accidents are postulated accidents that a nuclear facility must be designed and built to withstand without loss to the

215

Chief of Nuclear Safety (CNS) Senior Technical Safety Manager (STSM) Qualification Program Self-Assessment Report - August 2013  

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

Chief of Nuclear Safety (CNS) Chief of Nuclear Safety (CNS) Self-Assessment Report Senior Technical Safety Manager Qualification Program CONTENTS Background ................................................................................................................................ 1 Results ....................................................................................................................................... 1 Assessment Criteria ................................................................................................................... 1 Finding ....................................................................................................................................... 2 Observation ............................................................................................................................... 2

216

Nuclear Safety Enforcement Documents | Department of Energy  

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

14, 2002 14, 2002 Preliminary Notice of Violation, Fluor Hanford, Incorporated - EA-2002-03 Preliminary Notice of Violation issued to Fluor Hanford, Incorporated, related to Quality Assurance issues at the Hanford Site. June 19, 2002 Enforcement Letter, Kaiser-Hill Company, L.L.C. - June 19, 2002 Enforcement Letter issued to Kaiser-Hill Company, LLC related to Unplanned Radioactive Material Uptakes at the Rocky Flats Environmental Technology Site October 22, 2001 Special Report Order, CH2M Hill Hanford Group, Inc. - October 22, 2001 Special Report Order issued to CH2M Hill Hanford Group, Inc., related to Multiple Nuclear Safety Issues at the Hanford Site October 9, 2001 Enforcement Letter, LANL - October 9, 2001 Enforcement Letter issued to Los Alamos National Laboratory related to

217

FAQS Job Task Analyses - Nuclear Safety Specialist  

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

JOB / TASK ANALYSIS for JOB / TASK ANALYSIS for Nuclear Safety Specialist (NSS) Functional Area Qualification Standard (FAQS) DOE-STD-1183-2007 Instructions for Step 1: Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even

218

Defense Nuclear Facilities Safety Board's enabling legislation  

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

ENABLING STATUTE OF THE ENABLING STATUTE OF THE DEFENSE NUCLEAR FACILITIES SAFETY BOARD 42 U.S.C. § 2286 et seq. NATIONAL DEFENSE AUTHORIZATION ACT, FISCAL YEAR 1989 (Pub. L. No. 100-456, September 29, 1988), AS AMENDED BY NATIONAL DEFENSE AUTHORIZATION ACT, FISCAL YEAR 1991 (Pub. L. No. 101-510, November 5, 1990), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEARS 1992 AND 1993 (Pub. L. No. 102-190, December 5, 1991), ENERGY POLICY ACT OF 1992 (Pub. L. No. 102-486, October 24, 1992), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEAR 1994 (Pub. L. No. 103-160, November 30, 1993), FEDERAL REPORTS ELIMINATION ACT OF 1998 (Pub. L. No. 105-362, November 10, 1998), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEAR 2001 (Pub. L. No. 106-398, October 30, 2000), AND

219

Natural Phenomena Hazards (NPH) Workshop | Department of Energy  

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

Natural Phenomena Hazards (NPH) Workshop Natural Phenomena Hazards (NPH) Workshop Natural Phenomena Hazards (NPH) Workshop The Energy Department Natural Phenomena Hazards (NPH) Workshop, sponsored by the Chief of Nuclear Safety and the Chief of Defense Nuclear Safety, was held October 25-26, 2011, in Germantown, Maryland. The workshop brought together approximately 80 experts involved in the characterization of, and mitigation against, natural hazards that can impact nuclear facilities. The workshop featured twenty presentations as well as a breakout session devoted to discussing the status of the commonly used structural analysis code SASSI, a System for Analysis of Soil-Structure Interaction. A Method for Evaluating Fire after Earthquake Scenarios for Single Buildings_1.pdf Addressing Uncertainties in Design Inputs - A Case Study of Probabilistic

220

Natural Phenomena Hazards (NPH) Workshop | Department of Energy  

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

Natural Phenomena Hazards (NPH) Workshop Natural Phenomena Hazards (NPH) Workshop Natural Phenomena Hazards (NPH) Workshop The Energy Department Natural Phenomena Hazards (NPH) Workshop, sponsored by the Chief of Nuclear Safety and the Chief of Defense Nuclear Safety, was held October 25-26, 2011, in Germantown, Maryland. The workshop brought together approximately 80 experts involved in the characterization of, and mitigation against, natural hazards that can impact nuclear facilities. The workshop featured twenty presentations as well as a breakout session devoted to discussing the status of the commonly used structural analysis code SASSI, a System for Analysis of Soil-Structure Interaction. A Method for Evaluating Fire after Earthquake Scenarios for Single Buildings_1.pdf Addressing Uncertainties in Design Inputs - A Case Study of Probabilistic

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


221

Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)  

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

February 1996 February 1996 CHANGE NOTICE NO. 2 Date November 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, Fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Adminis tration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

222

DOE Cites Bechtel Jacobs Company for Nuclear Safety Violations | Department  

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

Jacobs Company for Nuclear Safety Violations Jacobs Company for Nuclear Safety Violations DOE Cites Bechtel Jacobs Company for Nuclear Safety Violations August 4, 2005 - 2:36pm Addthis WASHINGTON, D.C. - The Department of Energy (DOE) today notified the Bechtel Jacobs Company (BJC) that it will fine the company $247,500 for violations of the department's nuclear safety requirements. The company is the department's contractor responsible for environmental cleanup and waste management at its Oak Ridge Reservation in Tennessee. "One of our top safety priorities is to improve the performance of subcontractors, and to do that we need to hold prime contractors responsible," said John Shaw, Assistant Secretary for Environment, Safety and Health. "Our goal is to have work conducted in a manner that protects

223

The Department of Energy nuclear criticality safety program.  

SciTech Connect

This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

Felty, J. R. (James R.)

2004-01-01T23:59:59.000Z

224

Accurate fission data for nuclear safety  

E-Print Network (OSTI)

The Accurate fission data for nuclear safety (AlFONS) project aims at high precision measurements of fission yields, using the renewed IGISOL mass separator facility in combination with a new high current light ion cyclotron at the University of Jyvaskyla. The 30 MeV proton beam will be used to create fast and thermal neutron spectra for the study of neutron induced fission yields. Thanks to a series of mass separating elements, culminating with the JYFLTRAP Penning trap, it is possible to achieve a mass resolving power in the order of a few hundred thousands. In this paper we present the experimental setup and the design of a neutron converter target for IGISOL. The goal is to have a flexible design. For studies of exotic nuclei far from stability a high neutron flux (10^12 neutrons/s) at energies 1 - 30 MeV is desired while for reactor applications neutron spectra that resembles those of thermal and fast nuclear reactors are preferred. It is also desirable to be able to produce (semi-)monoenergetic neutrons for benchmarking and to study the energy dependence of fission yields. The scientific program is extensive and is planed to start in 2013 with a measurement of isomeric yield ratios of proton induced fission in uranium. This will be followed by studies of independent yields of thermal and fast neutron induced fission of various actinides.

A. Solders; D. Gorelov; A. Jokinen; V. S. Kolhinen; M. Lantz; A. Mattera; H. Penttila; S. Pomp; V. Rakopoulos; S. Rinta-Antila

2013-03-12T23:59:59.000Z

225

Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation  

SciTech Connect

One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

John D. Bess; J. Blair Briggs; David W. Nigg

2009-11-01T23:59:59.000Z

226

Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation  

SciTech Connect

One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

John D. Bess; J. Blair Briggs; David W. Nigg

2009-11-01T23:59:59.000Z

227

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

DOE Green Energy (OSTI)

The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

Steven R. Sherman

2007-06-01T23:59:59.000Z

228

Microsoft Word - Nuclear Safety Reporting Criteria.docx  

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

Safety Noncompliance Reporting Criteria (as of January 1, 2012) Safety Noncompliance Reporting Criteria (as of January 1, 2012) Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) Consult the DOE Order for the full text of each occurrence criterion 1 Reporting Criteria Group Subgroup Occurrence Category and Summary Description 2 1. Operational Emergencies 3 N/A (1) Operational Emergency (2) Alert (3) Site Area Emergency (4) General Emergency 2. Personnel Safety and Health C. Fires (1) Fire within primary confinement/containment (2d) Self-extinguishing fires D. Explosions (1) Unplanned explosion within primary confinement/containment 3. Nuclear Safety Basis A. Technical Safety Requirement (TSR) Violations (1) Violation of TSR/Operational Safety Requirement (OSR) Safety Limit (2) Violation of other TSR/OSR requirement

229

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated toolkit consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Timothy J. Leahy

2010-06-01T23:59:59.000Z

230

Nuclear Safety Reserch and Development Program Operating Plan  

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

Safety Research and Development Safety Research and Development Program Operating Plan Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy June 2012 INTENTIONALLY BLANK NSR&D Program Operating Plan June 2012 Table of Contents 1.0 INTRODUCTION................................................................................................................. 1 2.0 BACKGROUND ................................................................................................................... 1 3.0 OBJECTIVES ....................................................................................................................... 2 4.0 NSR&D PROGRAM PROCESSES .................................................................................... 3

231

Nuclear safety as applied to space power reactor systems  

SciTech Connect

Current space nuclear power reactor safety issues are discussed with respect to the unique characteristics of these reactors. An approach to achieving adequate safety and a perception of safety is outlined. This approach calls for a carefully conceived safety program which makes uses of lessons learned from previous terrestrial power reactor development programs. This approach includes use of risk analyses, passive safety design features, and analyses/experiments to understand and control off-design conditions. The point is made that some recent accidents concerning terrestrial power reactors do not imply that space power reactors cannot be operated safety.

Cummings, G.E.

1987-01-01T23:59:59.000Z

232

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

Hoopingarner, K.R.; Vause, J.W.

1987-08-01T23:59:59.000Z

233

March 13-15, 2012 14th Annual Joint DOE/EFCOG Chemical Safety and Worker Safety and Health Program (10 CFR 851) Workshop - Agenda  

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

/2/12 Page 4 of 11 /2/12 Page 4 of 11 Day 3 - Thursday, March 15, 2012 FORRESTAL MAIN AUDITORIUM (GE-086) 10 CFR 851 Workshop The purpose of this workshop is to foster continuous improvement of the implementation of 10 CFR 851 by sharing implementation experiences and ideas for enhancements gathered over the nearly 5 years since the rule's date for full implementation. 8:00 - 10:00 Registration/Name Tags - Large Auditorium (GE-086) 9:15 - 9:25 Welcome to 10 CFR 851 Workshop Pat Worthington Director, DOE Office of Health and Safety 9:25 - 9 :35 Introduction to HSS Focus Group Bill Eckroade

234

Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report  

SciTech Connect

The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented.

Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

1981-06-01T23:59:59.000Z

235

Work for Nuclear Regulatory Commission, Safety Related Applications  

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

Nuclear Regulatory Nuclear Regulatory Commission Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share Nuclear Regulatory Commission International Steam Generator Tube Integrity Program Key objectives of the International Steam Generator Tube Integrity Program

236

Safety Related Applications (Sensors and Instrumentation and NDE) - Nuclear  

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

DOE Office of DOE Office of Nuclear Energy, Science, and Technology Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share DOE Office of Nuclear Energy, Science, and Technology The objective of this Nuclear Energy Plant Optimization Project is to

237

Pantex sets safety record | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

sets safety record | National Nuclear Security Administration sets safety record | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Pantex sets safety record Pantex sets safety record Posted By Office of Public Affairs Pantex has set a new safety record with the lowest recordable case rate in the plant's history. The record total recordable case rate of 0.26 is a fitting end to an

238

Pantex receives two safety awards | National Nuclear Security  

National Nuclear Security Administration (NNSA)

two safety awards | National Nuclear Security two safety awards | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Pantex receives two safety awards Pantex receives two safety awards Posted By Office of Public Affairs B&W Pantex was honored last week with a pair of awards for its exemplary safety record. The President's Award for Best Performing Business Unit and the Target

239

DOE Cites University of Chicago for Nuclear Safety Violations | Department  

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

University of Chicago for Nuclear Safety Violations University of Chicago for Nuclear Safety Violations DOE Cites University of Chicago for Nuclear Safety Violations March 7, 2006 - 11:42am Addthis WASHINGTON , DC - The Department of Energy (DOE) today issued a Preliminary Notice of Violation (PNOV) to the University of Chicago (University), the Management and Operating contractor for DOE's Argonne National Laboratory (ANL), for nuclear safety violations identified through several safety reviews and inspections conducted by DOE. A series of reviews and inspections, the most recent of which occurred in 2005, identified breakdowns in the contractor's quality improvement, radiation protection, work process, and independent and management assessment programs. Prior to 2005, senior contractor management at ANL

240

DOE O 410.1, Central Technical Authority Responsibilities Regarding Nuclear Safety Requirements  

Directives, Delegations, and Requirements

The order establishes Central Technical Authority and Chief of Nuclear Safety/Chief of Defense Nuclear Safety responsibilities and requirements directed by the ...

2007-08-28T23:59:59.000Z

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


241

Nuclear Safety Research and Development Committee Charter | Department of  

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

Research and Development Committee Charter Research and Development Committee Charter Nuclear Safety Research and Development Committee Charter July 5, 2012 Nuclear Safety Research and Development Committee Charter The intent of the Nuclear Safety Research and Development (NSR&D) Committee is to identify nuclear safety research needs and opportunities within the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) and their program offices. The Committee promotes communication and coordination among DOE and NNSA program offices to enhance synergy on NSR&D efforts that can benefit the Department. The Committee will foster and facilitate networking and information exchange on NSR&D needs and activities across DOE/NNSA programs and with external national and international organizations. The Committee should not be construed to have

242

Deputy Secretary Poneman Discusses Nuclear Safety at the IAEA | Department  

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

Discusses Nuclear Safety at the IAEA Discusses Nuclear Safety at the IAEA Deputy Secretary Poneman Discusses Nuclear Safety at the IAEA June 20, 2011 - 12:00am Addthis Washington, D.C. - U.S. Deputy Secretary of Energy Daniel Poneman today addressed the plenary session at the International Atomic Energy Agency's Ministerial Conference on Nuclear Safety. Deputy Secretary Poneman emphasized the importance of international cooperation and information sharing for developing lessons learned from the Fukushima accident. The IAEA is leading the process to develop these international best practices, which will help strengthen the international nuclear regulatory regime. Remarks as prepared for delivery are below. Thank you, Mr. Ambassador, for your work in organizing this important Conference and to Director General Amano and his staff for convening it.

243

Nuclear Safety Research and Development Program Operating Plan | Department  

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

Program Operating Plan Program Operating Plan Nuclear Safety Research and Development Program Operating Plan July 5, 2012 Nuclear Safety Research and Development Program Operating Plan This operating plan outlines the mission, goals, and processes for the Department of Energy's (DOE) Nuclear Safety Research & Development (NSR&D) Program. This first version of the operating plan also discusses the startup phase of the program. NSR&D involves a systematic search for knowledge to advance the fundamental understanding of nuclear safety science and technology through scientific study, analysis, modeling, and experiments. Maintaining an effective NSR&D program will support DOE and the National Nuclear Security Administration (NNSA) in standards development, validation of analytical models and

244

Licensed reactor nuclear safety criteria applicable to DOE reactors  

SciTech Connect

This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

Not Available

1993-11-01T23:59:59.000Z

245

Summary Report of the INL-JISEA Workshop on Nuclear Hybrud Energy Systems  

Science Conference Proceedings (OSTI)

Hybrid energy systems utilize two or more energy resources as inputs to two or more physically coupled subsystems to produce one or more energy commodities as outputs. Nuclear hybrid energy systems can be used to provide load-following electrical power to match diurnal to seasonal-scale changes in power demand or to compensate for the variability of renewable wind or solar generation. To maintain economical, full rate operation of the nuclear reactor, its thermal energy available when power demand is low could be diverted into making synthetic vehicle fuels of various types. The Institute for Nuclear Energy Science and Technology (INEST) and the Joint Institute for Strategic Energy Analysis (JISEA) co-sponsored an international workshop to identify research topics important in advancing the potential use of hybrid systems with a specific focus on nuclear-renewable hybrid systems. The workshop included presentations ranging from energy challenges and research and development (R&D) directions being pursued by nations to multiple options for hybrid systems. Those options include one that is being commercialized to other opportunities and analysis results quantifying them. The workshop also involved two breakout sessions - one focused on thermal energy management issues especially at unit-operation scale and the second focused on system operations issues including system controls, regulatory issues, technical and economic analysis, and market challenges. A discussion involving the full group focused on more general issues such as societal involvement and participation. Key criteria for selecting hybrid energy system projects and metrics for comparing them were also identified by the full group. The workshop's findings are being used initially by INEST to define topics for a research preproposal solicitation.

Mark Antkowiak; Richard Boardman; Shannon Bragg-Sitton; Robert Cherry; Mark Ruth

2012-07-01T23:59:59.000Z

246

Licensed reactor nuclear safety criteria applicable to DOE reactors  

SciTech Connect

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

Not Available

1991-04-01T23:59:59.000Z

247

NEET Workshop 2010 | Department of Energy  

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

Workshop 2010 NEET Workshop 2010 The Nuclear Energy Enabling Technologies Workshop Report was held in Rockville, MD on July 29, 2010. DOE's primary purposes in convening the NEET...

248

Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Volume Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant Supplemental Volume Table of Contents Foreword ...................................................................................................................................................... iii Acronyms ...................................................................................................................................................... v

249

Quadrennial Technology Review's Alternative Generation Workshop...  

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

Technology Review's Alternative Generation Workshop Slides Preliminary Slides for Alternative Generation Workshop including Carbon Capture and Sequestration, Nuclear Power,...

250

DOE Cites Washington TRU Solutions for Nuclear Safety Violations |  

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

Washington TRU Solutions for Nuclear Safety Violations Washington TRU Solutions for Nuclear Safety Violations DOE Cites Washington TRU Solutions for Nuclear Safety Violations December 22, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Washington TRU Solutions (WTS) that it will fine the company $192,500 for violations of the department's nuclear safety requirements. The Preliminary Notice of Violation (PNOV) issued today cites a number of deficiencies that led to a series of low-level plutonium uptakes by workers at a WTS mobile facility (MOVER) stationed at the Lawrence Livermore National Laboratory (LLNL) in Livermore, Calif. The violations reflected WTS' limited understanding of the design and operational limitations of the MOVER facility, a portable waste processing facility designed to be

251

Reliability quantification of nuclear safety-related software  

E-Print Network (OSTI)

The objective of this study is to improve quality and reliability of safety-critical software in the nuclear industry. It is accomplished by focusing on the following two areas: Formulation of a standard extensive integrated ...

Zhang, Yi, 1973-

2004-01-01T23:59:59.000Z

252

Development of the Nuclear Safety Information Dashboard - September 2012 |  

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

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

253

Development of the Nuclear Safety Information Dashboard - September 2012 |  

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

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

254

FAQS Job Task Analyses - Nuclear Explosive Safety Study  

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

Nuclear Explosive Safety Study FAQS Nuclear Explosive Safety Study FAQS STEP 1: Job Task Analysis for Tasks Task (and Number) Source Importance Frequency (1) Serves as a member or chair of the NESSG. FAQS Duties and Responsibilities Paragraph A 5 3 (2) Provides guidance on and interpretation of nuclear explosive safety (NES) requirements and policy. FAQS Duties and Responsibilities Paragraph B 5 4 (3) Drafts policy directives for the DOE/NNSA, Nuclear Explosive Safety Operations Branch (NESB) and reviews DOE/NNSA policies on NES. FAQS Duties and Responsibilities Paragraph D 5 3 (4) Provides instruction and guidance regarding NES to individuals assigned NES responsibilities. FAQS Duties and Responsibilities Paragraph E 5 3-4 (5) Monitors ongoing NEOs to ensure compliance with NES standards and

255

Exelon Statement Regarding Nuclear Safety and 10 CFR 810  

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

Exelon respectfully submits that the existing 810 rule, as currently interpreted, and the proposed revised rule, both work as deterrents to improving safety in nuclear operations around the world.

256

DOE Cites Fluor Fernald Inc. for Nuclear Safety Violations  

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

Washington, D.C. -The Department of Energy (DOE) today notified Fluor Fernald, Inc. (Fluor Fernald) that it will fine the company $33,000 for violations of the department's nuclear safety...

257

10 CFR Part 830, Nuclear Safety Management  

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

construction such as environmental restoration activities, decontamination and decommissioning activities, specific nuclear explosives operations, or transition...

258

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

Zull, Lawrence M.; Yeniscavich, William [Defense Nuclear Facilities Safety Board, 625 Indiana Ave., NW, Suite 700, Washington, DC 20004-2901 (United States)

2008-01-15T23:59:59.000Z

259

Tank waste remediation system nuclear criticality safety program management review  

SciTech Connect

This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999.

BRADY RAAP, M.C.

1999-06-24T23:59:59.000Z

260

Martin Marietta Energy Systems Nuclear Criticality Safety Improvement Program  

SciTech Connect

This report addresses questions raised by criticality safety violation at several DOE plants. Two charts are included that define the severity and reporting requirements for the six levels of accidents. A summary is given of all reported criticality incident at the DOE plants involved. The report concludes with Martin Marietta's Nuclear Criticality Safety Policy Statement. (JDH)

Speas, I.G.

1987-04-29T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear safety workshop" 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.


261

MACCS2/Deposition Velocity Workshop | Department of Energy  

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

You are here You are here Home » MACCS2/Deposition Velocity Workshop MACCS2/Deposition Velocity Workshop The Department of Energy's Chief of Nuclear Safety hosted a MACCS2/Deposition Velocity Workshop on June 5-6, 2012, in Germantown, Maryland. Approximately 70 participants attended. The purpose of the workshop was to: Discuss MACCS2 and atmospheric dispersion models as applied to DOE consequence analysis. Discuss implementation of HSS Safety Bulletin 2011-2, Accident Analysis Parameter Update, at field sites. Develop a consistent Department-wide approach for responding to the HSS Safety Bulletin. Identify areas for improved DOE guidance for ensuring defensible consequence analyses. June Workshop Agenda- Final.docx Atmospheric Dispersion Modeling in Safety Analyses; GENII

262

Experience with performance based training of nuclear criticality safety engineers  

SciTech Connect

Historically, new entrants to the practice of nuclear criticality safety have learned their job primarily by on-the-job training (OJT) often by association with an experienced nuclear criticality safety engineer who probably also learned their job by OJT. Typically, the new entrant learned what he/she needed to know to solve a particular problem and accumulated experience as more problems were solved. It is likely that more formalism will be required in the future. Current US Department of Energy requirements for those positions which have to demonstrate qualification indicate that it should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis i`s incompletely developed in some areas. Details of this analysis are provided in this report.

Taylor, R.G.

1993-12-20T23:59:59.000Z

263

Nuclear Safety News | Department of Energy  

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

Alliance, LLC. News & Blog Blog Archive News Archive Program Highlights Enforcement News Organizational Chart Office of Health and Safety Office of Environmental Protection,...

264

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL  

SciTech Connect

A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results.

Almeida, C.

2004-10-06T23:59:59.000Z

265

Summary Report of the INL-JISEA Workshop on Nuclear Hybrid Energy Systems  

Science Conference Proceedings (OSTI)

The Institute for Nuclear Energy Science and Technology (INEST) and the Joint Institute for Strategic Energy Analysis (JISEA) co-sponsored an international workshop to identify research topics important in advancing the potential use of hybrid systems with a specific focus on nuclear-renewable hybrid systems. The workshop included presentations ranging from energy challenges and research and development directions being pursued by nations to multiple options for hybrid systems. Those options include one that is being commercialized to other opportunities and analysis results quantifying them. The workshop also involved two breakout sessions--one focused on thermal energy management issues especially at unit-operation scale and the second focused on system operations issues including system controls, regulatory issues, technical and economic analysis, and market challenges. A discussion involving the full group focused on more general issues such as societal involvement and participation. Key criteria for selecting hybrid energy system projects and metrics for comparing them were also identified by the full group.

Antkowiak, M.; Ruth, M.; Boardman, R.; Bragg-Sitton, S.; Cherry, R.; Shunn, L.

2012-07-01T23:59:59.000Z

266

REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS  

Science Conference Proceedings (OSTI)

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEAs Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facilitys general character, purpose, capacity, and location; (2) Description of the facilitys layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

Richard Metcalf; Robert Bean

2009-10-01T23:59:59.000Z

267

A Web-Based Nuclear Criticality Safety Bibliographic Database  

SciTech Connect

A bibliographic criticality safety database of over 13,000 records is available on the Internet as part of the U.S. Department of Energy's (DOE) Nuclear Criticality Safety Program (NCSP) website. This database is easy to access via the Internet and gets substantial daily usage. This database and other criticality safety resources are available at ncsp.llnl.gov. The web database has evolved from more than thirty years of effort at Lawrence Livermore National Laboratory (LLNL), beginning with compilations of critical experiment reports and American Nuclear Society Transactions.

Koponen, B L; Huang, S

2007-02-22T23:59:59.000Z

268

Environment, Safety & Health | National Nuclear Security Administratio...  

National Nuclear Security Administration (NNSA)

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

269

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis |  

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

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and

270

Department of Energy Office of Nuclear Safety and Environmental Policy  

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

Department of Energy Office of Nuclear Safety and Environmental Department of Energy Office of Nuclear Safety and Environmental Policy Technical Position NSEP-TP-2007- 1, Technical Position on the Requirement in DOE 0 420.1B to Use National Consensus Industry Standards and the Model Building CodesTechnical Position NS Department of Energy Office of Nuclear Safety and Environmental Policy Technical Position NSEP-TP-2007- 1, Technical Position on the Requirement in DOE 0 420.1B to Use National Consensus Industry Standards and the Model Building CodesTechnical Position NS All new construction required to follow the provisions of Department of Energy (DOE) Order 420. lB, Facility Safety, must comply with national consensus industry standards and the model building codes applicable for the state or region in which the facility is located. Certain individuals in the fire community requested

271

Nuclear Safety Research and Development (NSR&D) Program | Department of  

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

Nuclear Safety » Nuclear Safety Research and Nuclear Safety » Nuclear Safety Research and Development (NSR&D) Program Nuclear Safety Research and Development (NSR&D) Program In 2011, the Office of Health, Safety and Security (HSS) created the Nuclear Safety Research and Development (NSR&D) Program within the Office of Nuclear Safety to provide corporate-level leadership supporting nuclear safety research and development throughout the Department of Energy (DOE). The NSR&D Program solicits input from the Nuclear Safety Council which includes membership of senior management from each program office. NSR&D Program Objectives: To establish an enduring Departmental commitment and capability to utilize NSR&D in preventing and reducing the hazards and risks posed by DOE/NNSA nuclear facilities;

272

Nuclear Criticality Technology and Safety Project parameter study database  

SciTech Connect

A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst.

Toffer, H.; Erickson, D.G.; Samuel, T.J. [Westinghouse Hanford Co., Richland, WA (United States); Pearson, J.S. [Lawrence Livermore National Lab., CA (United States)

1993-03-01T23:59:59.000Z

273

Proceedings: 2005 EPRI Topical Workshop-Groundwater Contamination Assessment and License Termination Activities  

Science Conference Proceedings (OSTI)

The EPRI Groundwater Workshop focused on the subject of groundwater monitoring related to both operating and decommissioning nuclear plant sites. Groundwater monitoring can have an impact in terms of the time and resources needed to quantify the groundwater contamination and to assure the maintenance of public health and safety. EPRI held this workshop to aid nuclear plant operators in developing robust groundwater monitoring programs. The Workshop presented the latest information on groundwater assessme...

2006-06-01T23:59:59.000Z

274

Safety - Vulnerability Assessment Team - Nuclear Engineering Division  

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

Safety Safety VAT Projects Introducing the VAT Adversarial Vulnerability Assessments Safety Tags & Product Counterfeiting Election Security Spoofing GPS Defeating Existing Tamper-Indicating Seals Specialty Field Tools & Sampling Tools Insider Threat Mitigation Drug Testing Security Microprocessor Prototypes The Journal of Physical Security Vulnerability Assessments Vulnerability Assessments Insanely Fast µProcessor Shop Insanely Fast µProcessor Shop Seals About Seals Applications of Seals Common Myths about Tamper Indicating Seals Definitions Findings and Lessons Learned New Seals Types of Seals Seals References Selected VAT Papers Selected VAT Papers Selected Invited Talks Self-Assessment Survey Security Maxims Devil's Dictionary of Security Terms Argonne's VAT (brochure)

275

Aerospace nuclear safety: An introduction and historical overview  

SciTech Connect

This paper provides an introduction and overview on the topical area of aerospace nuclear safety. Emphasis is on the history of the use of nuclear power sources in space, operational experience with these nuclear sources, a review of previous accidents associated with both U.S. and Russian launches, and the safety issues associated with the entire life cycle of space reactors. There are several potential missions to include near earth orbit, orbit-raising, lunar bases, and propulsion to such solar system locations as Mars, which are suitable for the use of space reactors. The process by which approval is obtained to launch these nuclear materials to space is also presented as well as the role of nuclear safety policy and requirements in a space program using nuclear power sources. Important differences in safety concerns for the Radioisotope Thermoelectric Generators (RTGs) now used, and space reactors are presented. The role and purpose of independent safety evaluation and assessment in ensuring safe launch and operation is also discussed. In summary, this paper provides the requisite framework in this topical area for the remaining papers of this session.

Lee, J.H.; Buden, D.

1994-04-01T23:59:59.000Z

276

Energy Department and Catholic University Improve Safety of Nuclear Waste |  

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

Catholic University Improve Safety of Nuclear Catholic University Improve Safety of Nuclear Waste Energy Department and Catholic University Improve Safety of Nuclear Waste January 30, 2013 - 12:51pm Addthis Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. David Sheeley David Sheeley Editor/Writer What does this project do? Hanford treats and immobilizes significant quantities of legacy nuclear waste left from the manufacture of plutonium during World War II and the Cold War. Secretary Steven Chu recently visited Catholic University's Vitreous

277

14th Annual Joint DOE/EFCOG Chemical Safety and Worker Safety and Health  

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

4th Annual Joint DOE/EFCOG Chemical Safety and Worker Safety and 4th Annual Joint DOE/EFCOG Chemical Safety and Worker Safety and Health Program (10 CFR 851) Workshop 14th Annual Joint DOE/EFCOG Chemical Safety and Worker Safety and Health Program (10 CFR 851) Workshop Workshop Dates: March 13-15, 2012 The workshop served to promote continuous improvement in the implementation of 851 through the shared experiences and enhancements of a variety of DOE stakeholder communities. Panel members from Savannah River Nuclear Solutions, the United Steel Workers, the DOE Offices of Environmental Management and the National Nuclear Security Administration, and the HSS Offices of Worker Safety and Health Policy and Enforcement and Oversight, provided 851 implementation perspectives and an opportunity for interactive discussion and exchange with attendees.

278

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

SciTech Connect

A panel of experts in the fields of process engineering, process chemistry, and safety analysis met together on January 26, 1993, and February 19, 1993, to discuss nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility (DWPF) processes. Nuclear safety issues and possibilities of nuclear criticality incidents in the DWPF were examined in depth. The discussion started at the receipt of slurry feeds: The Low Point Pump Pit Precipitate Tank (LPPPPT) and the Low Point Pump Pit Sludge Tank (LPPPST), and went into detail the whole DWPF processes. This report provides discussion of each of the areas and processes of the DWPF in terms of potential nuclear safety issues and nuclear criticality concerns.

Ha, B.C.

1993-05-10T23:59:59.000Z

279

Nuclear safety | Princeton Plasma Physics Lab  

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

to prevent nuclear and radiation accidents or to limit their consequences. PPPL and ITER: Lab teams support the world's largest fusion experiment with leading-edge ideas and...

280

Safety/safeguards interactions during safety-related emergencies at Nuclear Power Reactor Facilities  

Science Conference Proceedings (OSTI)

This report contains an analysis of the safety/safeguards interactions that could occur during safety-related emergencies at licensed nuclear power reactors, and the extent to which these interactions are addressed in existing or proposed NRC guidance. The safety/safeguards interaction during a series of postulated emergencies was systematically examined to identify any potential performance deficiencies or conflicts between the Operations (safety) and Security (safeguards) organizations. This examination included the impacts of coordination with off-site emergency response personnel. Duties, responsibilities, optimal methods, and procedural actions inherent in these interactions were explored.

Moul, D.A.; Pilgrim, M.K.; Schweizer, R.L.; McEwen, J.E. Jr.

1985-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear safety workshop" 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.


281

Materials characterization center workshop on the irradiation effects in nuclear waste forms  

SciTech Connect

The Workshop on Irradiation Effects in Nuclear Waste Forms sponsored by the Materials Characterization Center (MCC) brought together experts in radiation damage in materials and waste-management technology to review the problems associated with irradiation effects on waste-form integrity and to evaluate standard methods for generating data to be included in the Nuclear Waste Materials Handbook. The workshop reached the following conclusions: the concept of Standard Test for the Effects of Alpha-Decay in Nuclear Waste Solids, (MCC-6) for evaluating the effects of alpha decay is valid and useful, and as a result of the workshop, modifications to the proposed procedure will be incorpoated in a revised version of MCC-6; the MCC-6 test is not applicable to the evaluation of radiation damage in spent fuel; plutonium-238 is recommended as the dopant for transuranic and defense high-level waste forms, and when high doses are required, as in the case of commercial high-level waste forms, /sup 244/Cm can be used; among the important property changes caused by irradiation are those that lead to greater leachability, and additionally, radiolysis of the leachant may increase leach rates; research is needed in this area; ionization-induced changes in physical properties can be as important as displacement damage in some materials, and a synergism is also likely to exist from the combined effects of ionization and displacement damage; and the effect of changing the temperature and dose rates on property changes induced by radiation damage needs to be determined.

Roberts, F.P.; Turcotte, R.P.; Weber, W.J.

1981-01-01T23:59:59.000Z

282

Western University Nuclear Radiation Safety Inspection Checklist  

E-Print Network (OSTI)

of Understanding (MOU) between USACE and the Nuclear Regulatory Commission (NRC) dated July 5, 2001, and subject for interagency consultation if the decommissioning criteria at 10 CFR Section 20.1402 are determined, resulting from the disposal of radiologically contaminated waste from the nearby Apollo Nuclear Fuel

Sinnamon, Gordon J.

283

Nuclear safety criteria and specifications for space nuclear reactors  

SciTech Connect

The purpose of this document is to define safety criteria which must be met to implement US safety policy for space fission reactors. These criteria provide the bases for decisions on the acceptability of specific mission and reactor design proposals. (JDH)

1982-08-01T23:59:59.000Z

284

Aerospace nuclear safety report for August 1967  

SciTech Connect

The AEC Safety Branch advised that the present outlook for a potential mission using four modified SNAP-3 type generators is rather negative. Drop tests of four SNAP-19 intact reentry heat source capsules were conducted at the Tonopah Test Range. A preliminary GE SNAP-27 safety analysis was reviewed. Three arc tunnel tests were conducted at low heat fluxes. Debris were collected on downrange impactors from all tests. The rapid helium depressurization test on fuel microspheres was conducted by Battelle; preliminary examination of the fuel revealed no obvious change in microsphere characteristics.

Illing, R.G. (comp.)

1967-09-01T23:59:59.000Z

285

Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

286

Web-based nuclear criticality safety bibliographic database  

SciTech Connect

The Lawrence Livermore National Laboratory has prepared a Nuclear Criticality Safety Bibliographic Database that is now available via the Internet. This database is a component of the U.S. DOE Nuclear Criticality Safety Program (NCSP) Web site. This WWW resource was developed as part of the DOE response to the DNFSB Recommendation 97-2, which reflected the need to make criticality safety information available to a wide audience. To the extent possible, the hyperlinks on the Web pages direct the user to original source of the reference material in order to ensure accuracy and access to the latest versions. A master index is in place for simple navigation through the site. A search capability is available to assist in locating the on-line reference materials. Among the features included are: A user-friendly site map for ease of use; A personnel registry; Links to all major laboratories and organizations involved in the many aspects of criticality safety; General help for new criticality safety practitioners, including basic technical references and training modules; A discussion of computational methods; An interactive question and answer forum for the criticality safety community; and Collections of bibliographic references mdvahdation experiments. This paper will focus on the bibliographic database. This database evolved from earlier work done by the DOE's Nuclear Criticality Information System (NCIS) maintained at LLNL during the 1980s. The bibliographic database at the time of the termination of NCIS were composed principally of three parts: (1) A critical experiment bibliography of 1067 citations (reported in UCRL-52769); (2) A compilation of criticality safety papers from Volumes 1 through 41 of the Transactions of the American Nuclear Society (reported in UCRL-53369); and (3) A general criticality bibliography of several thousand citations (unpublished). When the NCIS project was terminated the database was nearly lost but, fortunately, several years later most of the data were restored from backup tapes that had been archived by LLNL's ICNC conferences and American Nuclear Society publications, Nuclear Science and Engineering and Nuclear Technology. Since the Rocky Flats facility is heading for closure maintenance of the database was again threatened. This has now been avoided since LLNL was selected in 1999 to fulfill part of the ''Information Preservation and Dissemination'' task of the DOE's Nuclear Criticality Safety Program Five-Year Plan. This effort will ''collect, preserve and make readily available criticality safety information'' and make the information available via the Internet.

Koponen, B L; Huang, S T

2000-06-21T23:59:59.000Z

287

Guidance for identifying, reporting and tracking nuclear safety noncompliances  

SciTech Connect

This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

NONE

1995-12-01T23:59:59.000Z

288

Facility Representative Program: 2007 Facility Representative Workshop  

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

7 Facility Representative Workshop 7 Facility Representative Workshop May 15 - 17, 2007 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Final Day 1: Tuesday, May 15, 2007 8:00 a.m. Opening Remarks Joanne Lorence, Facility Representative Program Manager 8:15 a.m. Welcome from the Nevada Site Office Gerald Talbot, Manager, Nevada Site Office 8:30 a.m. Videotaped Remarks from the Deputy Secretary The Honorable Clay Sell, Deputy Secretary of Energy 8:45 a.m. Keynote Address - Safety Oversight Perspective and Expectations Glenn Podonsky, Chief Health, Safety and Security Officer, Office of Health, Safety and Security 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board,

289

Program on Technology Innovation: Summary of 2013 EPRI Nuclear Fuel Cycle Assessment Workshop - Vanderbilt University, Nashville, Tennessee, July 23 24, 2013  

Science Conference Proceedings (OSTI)

Government, industry, and academic stakeholders assembled at the second EPRI Nuclear Fuel Cycle Assessment Workshophosted and co-organized by Vanderbilt University and held July 2324, 2013to review ongoing efforts and opportunities for improving sustainability of nuclear fuel cycle (NFC) assessment related knowledge and tools through expanded collaboration. The workshop emphasized three topics addressing the development, maintenance, and application ...

2013-11-26T23:59:59.000Z

290

Nuclear Safeguards Infrastructure Development and Integration with Safety and Security  

SciTech Connect

Faced with increasing global energy demands, many developing countries are considering building their first nuclear power plant. As a country embarks upon or expands its nuclear power program, it should consider how it will address the 19 issues laid out in the International Atomic Energy Agency (IAEA) document Milestones in Development of a National Infrastructure for Nuclear Power. One of those issues specifically addresses the international nonproliferation treaties and commitments and the implementation of safeguards to prevent diversion of nuclear material from peaceful purposes to nuclear weapons. Given the many legislative, economic, financial, environmental, operational, and other considerations preoccupying their planners, it is often difficult for countries to focus on developing the core strengths needed for effective safeguards implementation. Typically, these countries either have no nuclear experience or it is limited to the operation of research reactors used for radioisotope development and scientific research. As a result, their capacity to apply safeguards and manage fuel operations for a nuclear power program is limited. This paper argues that to address the safeguards issue effectively, a holistic approach must be taken to integrate safeguards with the other IAEA issues including safety and security - sometimes referred to as the '3S' concept. Taking a holistic approach means that a country must consider safeguards within the context of its entire nuclear power program, including operations best practices, safety, and security as well as integration with its larger nonproliferation commitments. The Department of Energy/National Nuclear Security Administration's International Nuclear Safeguards and Engagement Program (INSEP) has been involved in bilateral technical cooperation programs for over 20 years to promote nonproliferation and the peaceful uses of nuclear energy. INSEP is currently spearheading efforts to promote the development of nuclear safeguards infrastructure in countries with credible plans for nuclear energy as part of the Next Generation Safeguards Initiative. Developing an adequate safeguards infrastructure is critical to becoming a responsible 'owner' of nuclear power. The 3S concept is the optimal path forward to achieving this goal.

Kovacic, Donald N [ORNL; Raffo-Caiado, Ana Claudia [ORNL; McClelland-Kerr, John [U.S. Department of Energy; Van sickle, Matthew [U.S. National Nuclear Security Administration; Bissani, Mo [Lawrence Livermore National Laboratory (LLNL)

2009-01-01T23:59:59.000Z

291

Nuclear criticality safety training: guidelines for DOE contractors  

SciTech Connect

The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, training program evaluations, and training program records. It also suggests appropriate feedback mechanisms for criticality safety training program improvement. The emphasis is on academic rather than hands-on training. This allows a decoupling of these guidelines from specific facilities. It would be unrealistic to dictate a universal program of training because of the wide variation of operations, levels of experience, and work environments among DOE contractors and facilities. Hence, these guidelines do not address the actual implementation of a nuclear criticality safety training program, but rather they outline the general characteristics that should be included.

Crowell, M.R.

1983-09-01T23:59:59.000Z

292

Safety Standards  

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

US DOE Workshop US DOE Workshop September 19-20, 2012 International perspective on Fukushima accident Miroslav Lipár Head, Operational Safety Section M.Lipar@iaea.org +43 1 2600 22691 2 Content * The IAEA before Fukushima -Severe accidents management * The IAEA actions after Fukushima * The IAEA Action plan on nuclear safety * Measures to improve operational safety * Conclusions THE IAEA BEFORE FUKUSHIMA 4 IAEA Safety Standards IAEA Safety Standards F undamental S afety Principles Safety Fundamentals f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Regulations for the Safe Transport of Radioactive Material 2005 E dit ion Safety Requirements No. T S-R-1 f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Design of the Reactor Core for Nuclear Power Plants

293

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Charges Relating to Nuclear Reactor Safety," 1976, availableissues impor tant to nuclear reactor safety. This report wasstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

294

License Application Chapter 5 Nuclear Criticality Safety  

E-Print Network (OSTI)

uranium or other fissile material outside of check-sources and various standards for radiological measurement calibration. As such, no criticality safety programs or procedures are maintained or implemented at the facility; however, the IIFP Integrated Safety Analysis (ISA), as documented in the ISA Summary, did evaluate the potential for a criticality accident at the IIFP Site. The only potential method of having a criticality accident at the facility involves the inadvertent receipt and processing of fissile materials, which is addressed in the ISA. Controls are established to verify that no enriched uranium hexafluoride (UF6) is received and processed at the facility. The cylinders processed at the IIFP Facility are the large, 14-ton or 10-ton UF6 tails cylinders, not the 2 -ton enriched product cylinders. Processing equipment at the plant, namely the autoclaves, is not sized to handle these smaller cylinders, so there is no method to feed enriched material into the processing plants. Additionally, each cylinder will be scanned with a detector to verify that the incoming cylinders do not contain fissile materials. The scan does not determine the shippers assay exactness for the cylinder contents, but does provide a reasonable indication if the cylinder is depleted or enriched. Both the receipt inspection and the scan for the assay at the Facility Site are maintained as Items Relied on for Safety (IROFS) controls. Also, feed suppliers (UF6 enrichment plants) have redundant and

Uranium De-conversion; Revision B

2011-01-01T23:59:59.000Z

295

Processing Exemptions to Nuclear Safety Rules and Approval of Alternative Methods for Documented Safety Analysis  

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

STD-1083-2009 STD-1083-2009 June 2009 DOE STANDARD PROCESSING EXEMPTIONS TO NUCLEAR SAFETY RULES AND APPROVAL OF ALTERNATIVE METHODS FOR DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/techstds DOE-STD-1083-2009 iii FOREWORD 1. This Department of Energy (DOE) Standard has been prepared by the Office of Quality Assurance Policy and Assistance to provide acceptable processes for: a. requesting and granting exemptions to DOE nuclear safety rules and b. requesting and approving alternate methodologies for documented safety analyses

296

Space Nuclear Safety Program. Progress report  

DOE Green Energy (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.

Bronisz, S.E. (comp.)

1984-01-01T23:59:59.000Z

297

Method for quantitative assessment of nuclear safety computer codes. [PWR  

SciTech Connect

A procedure has been developed for the quantitative assessment of nuclear safety computer codes and tested by comparison of RELAP4/MOD6 predictions with results from two Semiscale tests. This paper describes the developed procedure, the application of the procedure to the Semiscale tests, and the results obtained from the comparison.

Dearien, J.A.; Davis, C.B.; Matthews, L.J.

1979-01-01T23:59:59.000Z

298

Materials Characterization Center. Second workshop on irradiation effects in nuclear waste forms. Summary report  

SciTech Connect

The purpose of this second workshop on irradiations effects was to continue the discussions initiated at the first workshop and to obtain guidance for the Materials Characterization Center in developing test methods. The following major conclusions were reached: Ion or neutron irradiations are not substitutes for the actinide-doping technique, as described by the MCC-6 Method for Preparation and Characterization of Actinide-Doped Waste Forms, in the final evaluation of any waste form with respect to the radiation effects from actinide decay. Ion or neutron irradiations may be useful for screening tests or more fundamental studies. The use of these simulation techniques as screening tests for actinide decay requires that a correlation between ion or neutron irradiations and actinide decay be established. Such a correlation has not yet been established and experimental programs in this area are highly recommended. There is a need for more fundamental studies on dose-rate effects, temperature dependence, and the nature and importance of alpha-particle effects relative to the recoil nucleus in actinide decay. There are insufficient data presently available to evaluate the potential for damage from ionizing radiation in nuclear waste forms. No additional test methods were recommended for using ion or neutron irradiations to simulate actinide decay or for testing ionization damage in nuclear waste forms. It was recognized that additional test methods may be required and developed as more data become available. An American Society for Testing and Materials (ASTM) Task Group on the Simulation of Radiation Effects in Nuclear Waste Forms (E 10.08.03) was organized to act as a continuing vehicle for discussions and development of procedures, particularly with regard to ion irradiations.

Weber, W.J.; Turcotte, R.P.

1982-01-01T23:59:59.000Z

299

Software reliability and safety in nuclear reactor protection systems  

SciTech Connect

Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the report, First, software considerations cannot be fully understood in isolation from computer hardware and application considerations. Second, the process of engineering reliability and safety into a computer system requires activities to be carried out throughout the software life cycle. The report discusses the many activities that can be carried out during the software life cycle to improve the safety and reliability of the resulting product. The viewpoint is primarily that of the assessor, or auditor.

Lawrence, J.D. [Lawrence Livermore National Lab., CA (United States)

1993-11-01T23:59:59.000Z

300

Proceedings of the nuclear criticality technology safety project  

SciTech Connect

This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

Sanchez, R.G. [comp.

1997-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear safety workshop" 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.


301

DOE O 452.2D Admin Chg 1, Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and ...

2009-04-14T23:59:59.000Z

302

DOE P 420.1 Department of Energy Nuclear Safety Policy  

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

POLICY Washington, D.C. Approved: 2-08-2011 SUBJECT: DEPARTMENT OF ENERGY NUCLEAR SAFETY POLICY PURPOSE: To document the Department of Energy's (DOE) nuclear safety policy. SCOPE:...

303

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice,  

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

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of risk assessment. Working with the Chief of Defense Nuclear Safety and the Chief of Nuclear Safety, staff from the Office of Health,

304

N reactor individual risk comparison to quantitative nuclear safety goals  

Science Conference Proceedings (OSTI)

A full-scope level III probabilistic risk assessment (PRA) has been completed for N reactor, a US Department of Energy (DOE) production reactor located on the Hanford Reservation in the state of Washington. Sandia National Laboratories (SNL) provided the technical leadership for this work, using the state-of-the-art NUREG-1150 methodology developed for the US Nuclear Regulatory Commission (NRC). The main objectives of this effort were to assess the risks to the public and to the on-site workers posed by the operation of N reactor, to identify changes to the plant that could reduce the overall risk, and to compare those risks to the proposed NRC and DOE quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford Company (WHC) and SNL for individual health risk evaluation, its results, and a comparison to the NRC safety objectives and the DOE nuclear safety guidelines. The N reactor results, are also compared with the five NUREG-1150 nuclear plants. Only internal events are compared here because external events are not yet reported in the current draft NUREG-1150. This is the first full-scope level III PRA study with a detailed quantitative safety goal comparison performed for DOE production reactors.

Wang, O.S.; Rainey, T.E.; Zentner, M.D.

1990-01-01T23:59:59.000Z

305

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

306

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

307

Systems Analysis Workshop Purpose  

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

National Renewable Energy Laboratory National Renewable Energy Laboratory DOE Hydrogen Program DOE Hydrogen Program Systems Analysis Workshop Systems Analysis Workshop Systems Integration Production Delivery Conversion Application Education Codes & Standards Safety Tech Validation Storage Systems Integration Production Delivery Conversion Application Education Codes & Standards Safety Tech Validation Storage Washington D.C. 28-29 Jul 04 Dale Gardner Systems Integration Operated for the U.S. Department of Energy by Midwest Research Institute * Battelle 2 Systems Analysis Workshop Topics * Meeting Goals * Systems Integration * Roles/Responsibilities of Analysis Participants * Systems Analysis * From this Workshop * Capability Presentations 3 Systems Analysis Workshop Meeting Goals 1) Understand the roles and activities of the DOE Technology Analyst,

308

Nuclear Explosives Safety Study Functional Area Qualification Standard  

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

85-2007 85-2007 September 2007 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DRAFT DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DRAFT DOE-STD-1185-2007 iv INTENTIONALLY BLANK DRAFT DOE-STD-1185-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................1

309

Nuclear reactor safety. Progress report, January 1-March 31, 1982  

SciTech Connect

The work that is highlighted here represents accomplishments for the period January 1-March 31, 1982 by the groups at Los Alamos involved in reactor safety research for the Division of Accident Evaluation, Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission. Presented are brief overviews compiled by project, along with a bibliography of Technical Notes and publications written during this quarter. Information is presented concerning the TRAC code development; thermal-hydraulic analysis for PWR after ECCS operation; failure criteria for graphites used in HTGR type reactors; upper structure dynamics experiments; CRBR loss-of-flow accident analysis; and LWR severe accident analysis.

Stevenson, M.G. (comp.)

1982-08-01T23:59:59.000Z

310

Nuclear safety as applied to space power reactor systems  

SciTech Connect

To develop a strategy for incorporating and demonstrating safety, it is necessary to enumerate the unique aspects of space power reactor systems from a safety standpoint. These features must be differentiated from terrestrial nuclear power plants so that our experience can be applied properly. Some ideas can then be developed on how safe designs can be achieved so that they are safe and perceived to be safe by the public. These ideas include operating only after achieving a stable orbit, developing an inherently safe design, ''designing'' in safety from the start and managing the system development (design) so that it is perceived safe. These and other ideas are explored further in this paper.

Cummings, G.E.

1987-01-01T23:59:59.000Z

311

Double-clad nuclear-fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, W.H.; Atcheson, D.B.

1981-12-30T23:59:59.000Z

312

Nuclear Criticality Safety Requirements Implementation Matrix for Tank Farms  

SciTech Connect

This document provides a detailed matrix of specific Tank Farms nuclear criticality safety program elements indexed to primary requirements documents. These requirements are collected at a higher level in HNF-SO-MP-SRID-001, ''Tank Waste Remediation System Standards/Requirements Identification Document.'' The intended use of this document is to provide a roadmap for implementing procedures and assessments.

WEISS, E.V.

2000-05-17T23:59:59.000Z

313

Merger of Nuclear Data with Criticality Safety Calculations  

SciTech Connect

In this paper we report on current activities related to the merger of differential/integral data (especially in the resolved-resonance region) with nuclear criticality safety computations. Techniques are outlined for closer coupling of many processes ? measurement, data reduction, differential-data analysis, integral-data analysis, generating multigroup cross sections, data-testing, criticality computations ? which in the past have been treated independently.

Derrien, H.; Larson, N.M.; Leal, L.C.

1999-09-20T23:59:59.000Z

314

Space Nuclear Safety Program. Progress report, November 1983  

DOE Green Energy (OSTI)

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Topics discussed include: safety-verification impact tests; explosion test; fragment test; leaking fueled clads; effects of fresh water and seawater or PuO/sub 2/ pellets; and impact tests of 5 watt radioisotope thermoelectric generator.

Bronisz, S.E. (comp.)

1984-06-01T23:59:59.000Z

315

Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents  

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

SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD .................................................................................................................................. v INTRODUCTION ..........................................................................................................................

316

Teacher Resource Center: Customized Workshops  

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

Customized Workshops Customized Workshops TRC Home TRC Fact Sheet Library Curricular Resources Science Fair Resources Bibliographies sciencelines The Best of sciencelines Archives Annotated List of URLs Catalog Teacher's Lounge Full Workshop Catalog Customized Workshops Scheduled Workshops Special Opportunities Teacher Networks Science Lab Fermilab Science Materials Samplers Order Form Science Safety Issues Tech Room Fermilab Web Resources From time to time we receive requests for information about workshops offered through the Fermilab Teacher Resource Center. We have conducted workshops for schools, districts and intermediate service agencies. We work closely with organizers to customize the workshops to their needs—the discussion and collaboration is essential. We receive many requests for

317

Worker Safety and Health and Nuclear Safety Quarterly Performance Analysis (January - March 2008)  

Science Conference Proceedings (OSTI)

The DOE Office of Enforcement expects LLNL to 'implement comprehensive management and independent assessments that are effective in identifying deficiencies and broader problems in safety and security programs, as well as opportunities for continuous improvement within the organization' and to 'regularly perform assessments to evaluate implementation of the contractor's processes for screening and internal reporting.' LLNL has a self-assessment program, described in ES&H Manual Document 4.1, that includes line, management and independent assessments. LLNL also has in place a process to identify and report deficiencies of nuclear, worker safety and health and security requirements. In addition, the DOE Office of Enforcement expects LLNL to evaluate 'issues management databases to identify adverse trends, dominant problem areas, and potential repetitive events or conditions' (page 14, DOE Enforcement Process Overview, December 2007). LLNL requires that all worker safety and health and nuclear safety noncompliances be tracked as 'deficiencies' in the LLNL Issues Tracking System (ITS). Data from the ITS are analyzed for worker safety and health (WSH) and nuclear safety noncompliances that may meet the threshold for reporting to the DOE Noncompliance Tracking System (NTS). This report meets the expectations defined by the DOE Office of Enforcement to review the assessments conducted by LLNL, analyze the issues and noncompliances found in these assessments, and evaluate the data in the ITS database to identify adverse trends, dominant problem areas, and potential repetitive events or conditions. The report attempts to answer three questions: (1) Is LLNL evaluating its programs and state of compliance? (2) What is LLNL finding? (3) Is LLNL appropriately managing what it finds? The analysis in this report focuses on data from the first quarter of 2008 (January through March). This quarter is analyzed within the context of information identified in previous quarters to include April 2007 through March 2008. The results from analyzing the deficiencies are presented in accordance with the two primary NTS reporting thresholds for WSH and nuclear safety noncompliances: (1) those related to certain events or conditions and (2) those that are management issues. In addition, WSH noncompliances were also analyzed to determine if any fell under the 'other significant condition' threshold. This report also identifies noncompliance topical areas that may have issues that do not meet the NTS reporting threshold but should remain under observation. These are placed on the 'watch list' for continued analysis.

Kerr, C E

2009-10-07T23:59:59.000Z

318

2011 Project Management Workshop | Department of Energy  

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

Project Management Workshop Project Management Workshop 2011 Project Management Workshop 2011 DOE Project Management Workshop Paul Bosco, The New DOE O 413.3B Jeff Baker, EERE's Research Support Facility Patrick Ferraro, Contract Management/ Project Management Summit Outbrief Anirban Basu, Construction Economic Forecast John Curran, LED Lighting Michael Deane, Construction and Demolition Debris Recycle Mark Fallon, Leadership & Safety Cost Estimating Panel, The Science and Art of Cost Estimating Tom Fox, Leading in Tough Times Bob Raines, Project Management Update Tony Cannon, Nuclear Quality Assurance Issues Peer Review Panel, Peer Reviews 101 Terry Cooke-Davies, Project Complexity Rod Rimando, EM Project Management Framework PMCDP Panel, PMCDP CRB CRB Panel Questions & Answers Chad Henderson, FPD's Perspective

319

Nuclear Facility Safety Basis Fundamentals Self-Study Guide - November 2002  

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

Oak Ridge Operations Office Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] November 2002 Nuclear Facility Safety Basis Fundamentals Self-Study Guide TABLE OF CONTENTS Acronyms and Abbreviations ......................................................................................... iii List of Figures ....................................................................................................................iv List of Tables......................................................................................................................iv INTRODUCTION..............................................................................................................1

320

Workshop introduction  

Science Conference Proceedings (OSTI)

The Department of Energy's National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI) has three subprograms that directly reduce the nuclear/radiological threat; Convert (Highly Enriched Uranium), Protect (Facilities), and Remove (Materials). The primary mission of the Off-Site Source Recovery Project (OSRP) falls under the 'Remove' subset. The purpose of this workshop is to provide a venue for joint-technical collaboration between the OSRP and the Nuclear Radiation Safety Service (NRSS). Eisenhower's Atoms for Peace initiative and the Soviet equivalent both promoted the spread of the paradoxical (peaceful and harmful) properties of the atom. The focus of nonproliferation efforts has been rightly dedicated to fissile materials and the threat they pose. Continued emphasis on radioactive materials must also be encouraged. An unquantifiable threat still exists in the prolific quantity of sealed radioactive sources (sources) spread worldwide. It does not appear that the momentum of the evolution in the numerous beneficial applications of radioactive sources will subside in the near future. Numerous expert studies have demonstrated the potentially devastating economic and psychological impacts of terrorist use of a radiological dispersal or emitting device. The development of such a weapon, from the acquisition of the material to the technical knowledge needed to develop and use it, is straightforward. There are many documented accounts worldwide of accidental and purposeful diversions of radioactive materials from regulatory control. The burden of securing sealed sources often falls upon the source owner, who may not have a disposal pathway once the source reaches the end of its useful life. This disposal problem is exacerbated by some source owners not having the resources to safely and compliantly store them. US Nuclear Regulatory Commission (NRC) data suggests that, in the US alone, there are tens of thousands of high-activity (IAEA Category I and II) sources in thousands of devices; and there are many more tens of thousands of smaller sources scattered among thousands of other NRC licensees. As a result of the ubiquitous nature and undeterminable number of current and legacy sources, even in developed countries they can be abandoned, disposed of in a haphazard manner, lost, stolen, and/or otherwise fallout of regulatory control. Supply and demand of sources, being market based, is more or less fluid. Normative security of radioactive sources exists, but varies in each country, and is loosely implemented through non-legally binding recommendations and standards provided by International Atomic Energy Agency technical documents and cooperation and through bilateral efforts such as this workshop where we share best-practices with one another. Much of the reason for the difficulty in securing sealed sources rests in the enormous need for their beneficial applications in the medical, industrial, and agricultural sectors. Alternative technologies to replace high-risk sources continue to be explored, but very few of these alternative solutions have reached the development stage for common usage and distribution. The beneficial uses of sources must be allowed to continue; however, to minimize the potential for their misuse, current controls and regulating mechanisms must be constantly evaluated to ensure the benefits gained outweigh potential risks. From a global perspective, an evaluation and modification of requirements over the entire life cycle of sources from their manufacture to their final disposition is required. The proper removal and disposal of vulnerable disused or orphan sources is essential to maintaining a safe operating environment. One of our goals in this workshop is to share our methodologies for recovering sources and learn how they differ or are similar to the challenges faced in recovering, storing, and disposing of sources in the Republic of Georgia . The suggestions we will make are flexible in allowing for the imperfect situations and capabilities we have all encountered in sour

Streeper, Charles [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear safety workshop" 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.


321

PRELIMINARY NUCLEAR CRITICALITY NUCLEAR SAFETY EVLAUATION FOR THE CONTAINER SURVEILLANCE AND STORAGE CAPABILITY PROJECT  

SciTech Connect

Washington Safety Management Solutions (WSMS) provides criticality safety services to Washington Savannah River Company (WSRC) at the Savannah River Site. One activity at SRS is the Container Surveillance and Storage Capability (CSSC) Project, which will perform surveillances on 3013 containers (hereafter referred to as 3013s) to verify that they meet the Department of Energy (DOE) Standard (STD) 3013 for plutonium storage. The project will handle quantities of material that are greater than ANS/ANSI-8.1 single parameter mass limits, and thus required a Nuclear Criticality Safety Evaluation (NCSE). The WSMS methodology for conducting an NCSE is outlined in the WSMS methods manual. The WSMS methods manual currently follows the requirements of DOE-O-420.1B, DOE-STD-3007-2007, and the Washington Savannah River Company (WSRC) SCD-3 manual. DOE-STD-3007-2007 describes how a NCSE should be performed, while DOE-O-420.1B outlines the requirements for a Criticality Safety Program (CSP). The WSRC SCD-3 manual implements DOE requirements and ANS standards. NCSEs do not address the Nuclear Criticality Safety (NCS) of non-reactor nuclear facilities that may be affected by overt or covert activities of sabotage, espionage, terrorism or other security malevolence. Events which are beyond the Design Basis Accidents (DBAs) are outside the scope of a double contingency analysis.

Low, M; Matthew02 Miller, M; Thomas Reilly, T

2007-04-30T23:59:59.000Z

322

NUCLEAR SUBSTANCE LABORATORY SELF-AUDIT CHECKLIST Office of Environmental Health and Safety Title: Radiation Safety Self-Audit Checklist  

E-Print Network (OSTI)

NUCLEAR SUBSTANCE LABORATORY SELF-AUDIT CHECKLIST Office of Environmental Health and Safety Title for Handling Packages Containing Nuclear Substances" posters posted. Storage area signed, included 24 hour contact information Nuclear Substance Permit and all attachments posted (eg. Conditions ­ general, special

Beaumont, Christopher

323

Foundational development of an advanced nuclear reactor integrated safety code.  

SciTech Connect

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

2010-02-01T23:59:59.000Z

324

Report of a workshop on nuclear forces and nonproliferation Woodrow Wilson international center for scholars, Washington, DC October 28, 2010  

Science Conference Proceedings (OSTI)

A workshop sponsored by the Los Alamos National Laboratory in cooperation with the Woodrow Wilson International Center for Scholars was held at the Wilson Center in Washington, DC, on October 28, 2010. The workshop addressed evolving nuclear forces and their impacts on nonproliferation in the context of the new strategic environment, the Obama Administration's Nuclear Posture Review and the 2010 NPT Review Conference. The discussions reflected the importance of the NPR for defining the role of US nuclear forces in dealing with 21st century threats and providing guidance for National Nuclear Security Administration (NNSA) and Department of Defense (DoD) programs and, for many but not all participants, highlighted its role in the successful outcome of the NPT RevCon. There was widespread support for the NPR and its role in developing the foundations for a sustainable nuclear-weapon program that addresses nuclear weapons, infrastructure and expertise in the broader nonproliferation, disarmament and international security contexts. However, some participants raised concerns about its implementation and its long-term effectiveness and sustainability.

Pilat, Joseph F [Los Alamos National Laboratory

2010-12-08T23:59:59.000Z

325

Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report  

SciTech Connect

This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV`s) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG and G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin).

NONE

1998-01-01T23:59:59.000Z

326

Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis  

SciTech Connect

The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP.

Fisk, Patricia; Rutherford, Lavon

2003-06-01T23:59:59.000Z

327

Safety and Security Enforcement Program  

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

Enforcement Enforcement Enforcement Home Worker Safety and Health Enforcement Office of Nuclear Safety Enforcement Security Enforcement Notices of Violation Consent Orders / Settlement Agreements Compliance Orders Special Report Orders Enforcement Letters Regulatory Assistance Reviews Enforcement Program and Process Guidance and Information Non-Compliance Tracking System (NTS) Non-Compliance Reporting Thresholds Regulations and Directives Enforcement Staff Enforcement Coordinator Contact Information 2013 DOE Safety and Security Enforcement Workshop Request for Investigation or Inspection of Safety or Security Violations Archived Documents HSS Logo Safety and Security Enforcement Program Office of Enforcement and Oversight What's New: » Worker Safety and Health Enforcement Preliminary Notice of Violation issued to Brookhaven Science Associates, LLC

328

DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011  

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

DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011 DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011 PURPOSE: To document the Department of Energy's (DOE) nuclear safety policy. SCOPE: The provisions of this policy apply to all Departmental elements with responsibility for a nuclear facility, except the Naval Nuclear Propulsion Program, which is separately covered under Executive Order 12344, Title 50 United States Code, sections 2406 and 2511. This Policy cancels Secretary of Energy Notice 35-91, Nuclear Safety Policy, dated 9-9-91. POLICY: It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

329

THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER: A RESOURCE FOR REACTOR DOSIMETRY SOFTWARE AND NUCLEAR DATA  

Science Conference Proceedings (OSTI)

The Radiation Safety Information Computational Center (RSICC) was established in 1963 to collect and disseminate computational nuclear technology in the form of radiation transport, shielding and safety software and corresponding nuclear cross sections. Approximately 1700 nuclear software and data packages are in the RSICC collection, and the majority are applicable to reactor dosimetry.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

330

RADIOACTIVE MATERIALS LABORATORY SAFETY REPORT, MARTIN NUCLEAR FACILITY, QUEHANNA SITE  

SciTech Connect

A description is given of the safety features and the major alterations to be performed prior to occupancy. The evaluation was made in support of fubrication work on the production of safe isotopic power sources from Cm/sup 242/ and Sr/sup 90/. The chemical, nuclear, and radiobiological properties of Cm/sup 242/ and Sr/sup 90/ are outlined. The projected physical fiow of materials for production of the isotopic power souroes is schematically given. An evaluation of the malfunctions, operational hazards, and remedial health physics procedures is presented. The analysis and evaluation of postulated maximum credible incidents are demonstrated. (B.O.G.)

1960-09-01T23:59:59.000Z

331

Nuclear Explosive Safety Study Functional Area Qualification Standard  

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

NOT MEASUREMENT SENSITIVE DOE-STD-1185-2007 CHANGE NOTICE No.1 April 2010 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/ns/techstds DOE-STD-1185-2007 iii APPROVAL The Federal Technical Capability Panel consists of senior U.S. Department of Energy (DOE) managers responsible for overseeing the Federal Technical Capability Program. This Panel is

332

(Safety and reliability of nuclear power plant technology)  

SciTech Connect

The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

Dickson, T.L.

1990-10-22T23:59:59.000Z

333

Safety culture in the nuclear power industry : attributes for regulatory assessment  

E-Print Network (OSTI)

Safety culture refers to the attitudes, behaviors, and conditions that affect safety performance and often arises in discussions following incidents at nuclear power plants. As it involves both operational and management ...

Alexander, Erin L

2004-01-01T23:59:59.000Z

334

Status and Value of International Standards for Nuclear Criticality Safety  

SciTech Connect

This presentation provides an update to the author's standards report provided at the ICNC-2007 meeting. It includes a discussion about the difference between, and the value of participating in, the development of international 'consensus' standards as opposed to nonconsensus standards. Standards are developed for a myriad of reasons. Generally, standards represent an agreed upon, repeatable way of doing something as defined by an individual or group of people. They come in various types. Examples include personal, family, business, industrial, commercial, and regulatory such as military, community, state, federal, and international standards. Typically, national and international 'consensus' standards are developed by individuals and organizations of diverse backgrounds representing the subject matter users and developers of a service or product and other interested parties or organizations. Within the International Organization for Standardization (ISO), Technical Committee 85 (TC85) on nuclear energy, Subcommittee 5 (SC5) on nuclear fuel technology, there is a Working Group 8 (WG8) on standardization of calculations, procedures, and practices related to criticality safety. WG8 has developed, and is developing, ISO standards within the category of nuclear criticality safety of fissionable materials outside of reactors (i.e., nonreactor fissionable material nuclear fuel cycle facilities). Since the presentation of the ICNC-2007 report, WG8 has issued three new finalized international standards and is developing two more new standards. Nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards. The progression of consensus standards development among international partners in a collegial environment establishes a synergy of different concepts that broadens the perspectives of the members. This breadth of perspectives benefits the working group members in their considerations of consensus standards developments in their own countries. A testament to the value of the international standards efforts is that nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards and are mainly consistent with international ISO member domestic standards.

Hopper, Calvin Mitchell [ORNL

2011-01-01T23:59:59.000Z

335

Facility Representative Program: 2001 Facility Representative Workshop  

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

1 Facility Representative Workshop 1 Facility Representative Workshop May 15 - 17, 2001 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 15, 2001 Theme: Program Successes and Challenges 8:00 a.m. - Logistics Announcements & Opening Remarks - Joe Arango, Facility Representative Program Manager 8:15 a.m. - Welcome - Debbie Monette, Assistant Manager for National Security, Nevada Operations Office 8:30 a.m. - Keynote Address - Ralph Erickson, National Nuclear Security Administration 9:00 a.m.- DOE Facility Representative of the Year Presentation - Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board 9:30 a.m. - Break 9:50 a.m. - Program Summary - Joe Arango 10:10 a.m. - Management Panel/Questions and Answers

336

GRI workshop on LNG vehicle technology, economics, and safety issues: Focus-group recommendations summary. Topical report, April 29 and 30, 1992  

Science Conference Proceedings (OSTI)

GRI organized and conducted the Workshop on LNG Vehicle Technology, Economics, and Safety Issues on April 29 and 30, 1992, in Houston, Texas. The workshop included various presentations, a tour of Houston Metro (LNG bus project) facilities, and focus group discussions. The report documents the recommendations generated by the focus group. There were five separate focus groups with an average of ten members each. They met for 2-1/2 hours to discuss LNG vehicle issues and evolve recommendations for GRI R and D. Fifty-three recommendations were generated and prioritized (through voting) by the focus groups. The report consolidates these recommendations. Recommendations relative to the LNG fuel composition issue received the most votes, followed by consolidated recommendations pertaining to gas venting elimination, safety codes, and odorants or leak detectors. Component development recommendations (in order of votes) included the refueling nozzle, fuel level gage, refueling pump and meter, vehicle pump/regulator/vaporizer, and vehicle tank.

Not Available

1992-07-07T23:59:59.000Z

337

Applied antineutrino physics workshop.  

Science Conference Proceedings (OSTI)

This workshop is the fourth one of a series that includes the Neutrino Geophysics Conference at Honolulu, Hawaii, which I attended in 2005. This workshop was organized by the Astro-Particle and Cosmology laboratory in the recently opened Condoret building of the University of Paris. More information, including copies of the presentations, on the workshop is available on the website: www.apc.univ-paris7.fr/AAP2007/. The workshop aims at opening neutrino physics to various fields such that it can be applied in geosciences, nuclear industry (reactor and spent fuel monitoring) and non-proliferation. The workshop was attended by over 60 people from Europe, USA, Asia and Brazil. The meeting was also attended by representatives of the Comprehensive nuclear-Test Ban Treaty (CTBT) and the International Atomic Energy Agency (IAEA). The workshop also included a workshop dinner on board of a river boat sailing the Seine river.

Lund, James C.

2008-01-01T23:59:59.000Z

338

DOE M 140.1-1B, Interface with the Defense Nuclear Facilities Safety Board  

Directives, Delegations, and Requirements

This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels ...

2001-03-30T23:59:59.000Z

339

Survey on the Use of Configuration Risk and Safety Management Tools at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A joint project of Electricite de France (EDF) and EPRI, this project analyzed use of configuration safety and risk management tools at nuclear power plants.

1998-09-24T23:59:59.000Z

340

Assessment of Nuclear Safety Culture at the Y-12 National Security...  

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

like to increase federal staff in the areas of nuclear safety engineering, project controls for reviewing base line management for schedule and cost, and procurement quality...

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


341

DOE M 452.2-2 Admin Chg 1, Nuclear Explosive Safety Evaluation Processes  

Directives, Delegations, and Requirements

This Manual provides supplemental details to support the nuclear explosive safety (NES) evaluation requirement of Department of Energy (DOE) Order (O) 452.2D, ...

2009-04-14T23:59:59.000Z

342

DOE M 452.2-1A Admin Chg 1, Nuclear Explosive Safety Manual  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Manual provides supplemental details on selected topics to support the requirements of DOE O 452.2D, Nuclear Explosive Safety, ...

2009-04-14T23:59:59.000Z

343

Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant  

SciTech Connect

The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

2006-07-01T23:59:59.000Z

344

NEET WORKSHOP REPORT  

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

NEET WORKSHOP REPORT Table of Contents Acronyms and Initialisms ................................................................................................... iii 1. Introduction .................................................................................................................... 1 1.1 Key Challenges Facing Nuclear Energy ........................................................................... 1 1.2 DOE Nuclear R&D Objectives ......................................................................................... 2 1.3 NEET Program Workshop Objectives .............................................................................. 3 2. Discussion of Crosscutting Technologies ...................................................................... 5

345

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE  

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

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1 This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE's operation of nuclear facilities. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear Safety Policy (Secretary of Energy Notice [SEN] 35-91, Nuclear Safety Policy) and safety policies established by other safety

346

SUMMARY (SUMMARY TALK AT THE QUARKONIUM PRODUCTION IN NUCLEAR COLLISIONS WORKSHOP).  

SciTech Connect

This summary is an attempt to overview the wealth of new results and ideas in quarkonium physics presented at the Seattle Workshop. The Workshop in Seattle has shown that the physics of heavy quarkonium continues to develop at a fast pace; moreover, we have every reason to believe that the next year, with RHIC turning on, will mark the beginning of the new exciting era in this field.

KHARZEEV,D.

1998-05-11T23:59:59.000Z

347

Investigation on the Benefits of Safety Margin Improvement in CANDU Nuclear Power Plant Using an FPGA-based Shutdown System.  

E-Print Network (OSTI)

??The relationship between response time and safety margin of CANadian Deuterium Uranium (CANDU) nuclear power plant (NPP) is investigated in this thesis. Implementation of safety (more)

She, Jingke

2012-01-01T23:59:59.000Z

348

Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

Not Available

1994-06-01T23:59:59.000Z

349

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

350

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

351

Joint EFCOG/DOE Chemical Management 2013 Workshop - March 19...  

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

3 Workshop Information Health and Safety POSTPONED. Future events will be announced. Joint EFCOGDOE Chemical Management 2013 Workshop March 19-21, 2013 DOE Forrestal...

352

Status and Value of International Standards for Nuclear Criticality Safety  

SciTech Connect

This presentation provides an update to the author's standards report provided at the ICNC-2007 meeting. It includes a discussion about the difference between, and the value of participating in, the development of international 'consensus' standards as opposed to nonconsensus standards. Standards are developed for a myriad of reasons. Generally, standards represent an agreed upon, repeatable way of doing something as defined by an individual or group of people. They come in various types. Examples include personal, family, business, industrial, commercial, and regulatory such as military, community, state, federal, and international standards. Typically, national and international 'consensus' standards are developed by individuals and organizations of diverse backgrounds representing the subject matter users and developers of a service or product and other interested parties or organizations. Within the International Organization for Standardization (ISO), Technical Committee 85 (TC85) on nuclear energy, Subcommittee 5 (SC5) on nuclear fuel technology, there is a Working Group 8 (WG8) on standardization of calculations, procedures, and practices related to criticality safety. WG8 has developed, and is developing, ISO standards within the category of nuclear criticality safety of fissionable materials outside of reactors (i.e., nonreactor fissionable material nuclear fuel cycle facilities). Since the presentation of the ICNC-2007 report, WG8 has issued three new finalized international standards and is developing two more new standards. Nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards. The progression of consensus standards development among international partners in a collegial environment establishes a synergy of different concepts that broadens the perspectives of the members. This breadth of perspectives benefits the working group members in their considerations of consensus standards developments in their own countries. A testament to the value of the international standards efforts is that nearly all elements of the published WG8 ISO standards have been incorporated into IAEA nonconsensus guides and standards and are mainly consistent with international ISO member domestic standards.

Hopper, Calvin Mitchell [ORNL

2011-01-01T23:59:59.000Z

353

Nuclear Safety Regulatory Assistance Reviews | Department of Energy  

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

August 14, 2002 August 14, 2002 Preliminary Notice of Violation, Fluor Hanford, Incorporated - EA-2002-03 Preliminary Notice of Violation issued to Fluor Hanford, Incorporated, related to Quality Assurance issues at the Hanford Site. June 19, 2002 Enforcement Letter, Kaiser-Hill Company, L.L.C. - June 19, 2002 Enforcement Letter issued to Kaiser-Hill Company, LLC related to Unplanned Radioactive Material Uptakes at the Rocky Flats Environmental Technology Site October 22, 2001 Special Report Order, CH2M Hill Hanford Group, Inc. - October 22, 2001 Special Report Order issued to CH2M Hill Hanford Group, Inc., related to Multiple Nuclear Safety Issues at the Hanford Site October 9, 2001 Enforcement Letter, LANL - October 9, 2001 Enforcement Letter issued to Los Alamos National Laboratory related to

354

Training and qualification program for nuclear criticality safety technical staff  

SciTech Connect

A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. The program is compliant with requirements and provides evidence that a systematic approach has been taken to indoctrinate new technical staff. Development involved task analysis to determine activities where training was necessary and the standard which must be attained to qualify. Structured mentoring is used where experienced personnel interact with candidates using checksheets to guide candidates through various steps and to provide evidence that steps have been accomplished. Credit can be taken for the previous experience of personnel by means of evaluation boards which can credit or modify checksheet steps. Considering just the wealth of business practice and site specific information a new person at a facility needs to assimilate, the program has been effective in indoctrinating new technical staff personnel and integrating them into a productive role. The program includes continuing training.

Taylor, R.G.; Worley, C.A.

1996-10-22T23:59:59.000Z

355

Reviewing real-time performance of nuclear reactor safety systems  

SciTech Connect

The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems.

Preckshot, G.G. [Lawrence Livermore National Lab., CA (United States)

1993-08-01T23:59:59.000Z

356

Scale 6.1 Enhancements for Nuclear Criticality Safety  

SciTech Connect

The Scale code system developed at Oak Ridge National Laboratory provides a comprehensive, verified and validated, user-friendly tool set for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. For more than 30 years, regulators, licensees, and research institutions around the world have used Scale for safety analysis and design. Scale provides a 'plug-and-play' framework with 89 computational modules, including three deterministic and three Monte Carlo radiation transport solvers that are selected based on the desired solution. Scale's graphical user interfaces assist with accurate system modeling and convenient access to desired results. Scale 6.1 builds on the existing capabilities and ease-of-use of Scale and provides several new features such as improved options and capabilities for sensitivity and uncertainty analysis calculations, improved flexibility in shielding and criticality accident alarm system calculations with automated variance reduction, and new options for the definition of group structures for depletion calculations. The Scale 6.1 development team has focused on improved robustness via substantial additional regression testing and verification for new and existing features, providing improved performance relative to Scale 6.0, especially in reactor physics calculations and in the nuclear data used for source term characterization and shielding calculations.

Rearden, Bradley T [ORNL; Petrie Jr, Lester M [ORNL; Peplow, Douglas E. [ORNL; Jessee, Matthew Anderson [ORNL; Wiarda, Dorothea [ORNL; Williams, Mark L [ORNL; Lefebvre, Robert A [ORNL; Lefebvre, Jordan P [ORNL; Gauld, Ian C [ORNL; Goluoglu, Sedat [ORNL

2011-01-01T23:59:59.000Z

357

Enforcement handbook: Enforcement of DOE nuclear safety requirements  

SciTech Connect

This Handbook provides detailed guidance and procedures to implement the General Statement of DOE Enforcement Policy (Enforcement Policy or Policy). A copy of this Enforcement Policy is included for ready reference in Appendix D. The guidance provided in this Handbook is qualified, however, by the admonishment to exercise discretion in determining the proper disposition of each potential enforcement action. As discussed in subsequent chapters, the Enforcement and Investigation Staff will apply a number of factors in assessing each potential enforcement situation. Enforcement sanctions are imposed in accordance with the Enforcement Policy for the purpose of promoting public and worker health and safety in the performance of activities at DOE facilities by DOE contractors (and their subcontractors and suppliers) who are indemnified under the Price-Anderson Amendments Act. These indemnified contractors, and their suppliers and subcontractors, will be referred to in this Handbook collectively as DOE contractors. It should be remembered that the purpose of the Department`s enforcement policy is to improve nuclear safety for the workers and the public, and this goal should be the prime consideration in exercising enforcement discretion.

NONE

1995-06-01T23:59:59.000Z

358

Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications (NCIG-07)  

Science Conference Proceedings (OSTI)

The reduced availability of spare and replacement parts designed specifically for nuclear safety related components has made it necessary for utilities to purchase commercial grade parts. This study, the seventh in a series cosponsored by the Nuclear Construction Issues Group (NCIG), outlines an acceptance procedure for ensuring that commercial grade items conform with requirements for their use in safety related applications.

1988-06-01T23:59:59.000Z

359

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24.

1993-11-01T23:59:59.000Z

360

CY 2012 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

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

2 2 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

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


361

CY 2011 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

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

1 1 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

362

Assessment of Nuclear Safety Culture at the Los Alamos National...  

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

Project May 2011 April 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of...

363

Review and Approval of Nuclear Facility Safety Basis Documents...  

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

institutional programs in Integrated Safety Management System documents and site-wide manuals was added. p. 13 Sect. 3 Approval Bases for Technical Safety Requirements New...

364

Nondestructive Evaluation: Recommended Practices for Maintaining Radiation Safety of Radiographic Operations at a Nuclear Plant  

Science Conference Proceedings (OSTI)

Radiation safety programs for radiographic operations at nuclear power plants are more complex than for those operations at other types of industrial and commercial facilities. This level of complexity arises because of the numerous challenges to maintenance of excellence in radiation safety at nuclear power facilities where sources of radiation may be found at various locations in the facility and multiple safety functions must be considered at all times. The facilities themselves are also large with mu...

2010-12-23T23:59:59.000Z

365

Nuclear Safety. Technical Progress Journal, October--December 1991: Volume 32, No. 4  

SciTech Connect

This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

Not Available

1991-01-01T23:59:59.000Z

366

BOOK: Safety Related Issues of Spent Nuclear Fuel Storage  

Science Conference Proceedings (OSTI)

Sep 26, 2007... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science ... Fifteen papers cover aluminum-clad fuel discharged from research...

367

DOE Workshop - Deposition Velocity Status  

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

Delivering DOE's Vision for the Delivering DOE's Vision for the East Tennessee Technology Park Mission Safely Delivering the Department of Energy's Vision for the East Tennessee Technology Park Mission DOE Workshop Deposition Velocity Status Mike Hitchler, Manager Nuclear Facility Safety June 5, 2012 Safely Delivering DOE's Vision for the East Tennessee Technology Park Mission Existing UCOR Analyses * UCOR facilities at East Tennessee Technology Park (ETTP) and Oak Ridge National Laboratory (ORNL) use various plume models depending on when they were developed and by whom. - Some use MACCS or MACCS2 for dispersion evaluation. (~5 locations) - LLLW uses ingestion modeling (multiple locations)

368

AFC Workshop on "Decay Spectroscopy at CARIBU: Advanced Fuel...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

369

Program - AFC Workshop (April 2011) - Argonne National Laboratory  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

370

Safety System Oversight  

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

Safety System Oversight Safety System Oversight Office of Nuclear Safety Home Safety System Oversight Home Annual SSO/FR Workshop DOE Safety Links › ORPS Info › Operating Experience Summary › DOE Lessons Learned › Accident Investigation Program Assessment Tools › SSO CRADS Subject Matter Links General Program Information › Program Mission Statement › SSO Program Description › SSO Annual Award Program › SSO Annual Award › SSO Steering Committee › SSO Program Assessment CRAD SSO Logo Items Site Leads and Steering Committee Archive Facility Representative Contact Us HSS Logo SSO SSO Program News Congratulations to Ronnie L. Alderson of Nevada Field Office, the Winner of the 2012 Safety System Oversight Annual Award! 2012 Safety System Oversight Annual Award Nominees SSO Staffing Analysis

371

Safety System Oversight: Steering Committee  

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

Safety Home Safety System Oversight Home Annual SSOFR Workshop DOE Safety Links ORPS Info Operating Experience Summary DOE Lessons Learned Accident...

372

Facility Representative Program: 2003 Facility Representative Workshop  

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

3 Facility Representative Workshop 3 Facility Representative Workshop May 13 - 15, 2003 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 13, 2003 Theme: Program Successes and Challenges 8:00 a.m. John Evans, Facility Representative Program Manager 8:15 a.m. Welcome Kathleen Carlson Manager, Nevada Site Office 8:30 a.m. Keynote Address Savannah River Site and Facility Reps - A Shared History and Common Future Jeffrey M. Allison Manager, Savannah River Operations Office 9:00 a.m. Videotaped Remarks from the Deputy Secretary Kyle E. McSlarrow, Deputy Secretary of Energy 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board

373

Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels  

E-Print Network (OSTI)

in this paper. Keywords: Remote inspection, Service robot, Non-destructive test, Nuclear, Climbing robotWalking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels B of Electronics and Computer Science, University of Southampton, Southampton, UK Abstract: Nuclear reactor

Chen, Sheng

374

September 10, 2010 HSS Briefing to the Defense Nuclear Facilities Safety Board (DNFSB) on Union Activities  

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

Labor Union and Stakeholder Labor Union and Stakeholder Outreach and Collaboration Office of Health, Safety and Security Briefing to the Defense Nuclear Facilities Safety Board Briefing to the Defense Nuclear Facilities Safety Board Leadership Commitment Leadership Commitment " h "It is imperative that we communicate and establish relationships with those elements that train manage and elements that train, manage and represent our workforce to improve the safety culture at DOE sites." safety culture at DOE sites. Glenn S. Podonsky Chief Health, Safety and Security Officer 2 History History History History October 2006: Formation of HSS to provide an integrated DOE HQ-level function for health, safety, environment, and security into one unified office. February 2007: Established HSS Focus Group -

375

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC  

SciTech Connect

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a ``Deliberate Operating`` mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a ``Use Every Time`` (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points.

Boler-Melton, C.; Holland, M.K.

1991-12-31T23:59:59.000Z

376

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC  

SciTech Connect

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points.

Boler-Melton, C.; Holland, M.K.

1991-01-01T23:59:59.000Z

377

Nuclear criticality safety modeling of an LEU deposit  

DOE Green Energy (OSTI)

The construction of the Oak Ridge Gaseous Diffusion Plant (now known as the K-25 Site) began during World War H and eventually consisted of five major process buildings: K-25, K-27, K-29, K-31, and K-33. The plant took natural (0.711% {sup 231}U) uranium as feed and processed it into both low-enriched uranium (LEU) and high-enriched uranium (HEU) with concentrations up to {approximately}93% {sup 231}U. The K-25 and K-27 buildings were shut down in 1964, but the rest of the plant produced LEU until 1985. During operation, inleakage of humid air into process piping and equipment caused reactions with gaseous uranium hexafluoride (UF{sub 6}) that produced nonvolatile uranyl fluoride (UO{sub 2}F{sub 2}) deposits. As part of shutdown, most of the uranium was evacuated as volatile UF{sub 6}. The UO{sub 2}F{sub 2} deposits remained. The U.S. Department of Energy has mitiated a program to unprove nuclear criticality safety by removing the larger enriched uranium deposits.

Haire, M.J.; Elam, K.R.; Jordan, W.C.; Dahl, T.L.

1996-11-01T23:59:59.000Z

378

Nuclear criticality safety program for environmental restoration projects  

SciTech Connect

The Fernald Environmental Management Project (FEMP), formerly known as the Feed Materials Production Center (FMPC), is located on a 1050 acre site approximately twenty miles northwest of Cincinnati, Ohio. The production area of the site covers approximately 136 acres in the central portion of the site. Surrounding the core production area is a buffer consisting of leased grazing land, reforested land, and unused areas. The uranium processing facility was designed and constructed in the early 1950s. During the period from 1952 to 1989 the site produced uranium feed material and uranium products used in the United States weapons complex. Production at the site ended in 1989, when the site was shut down for what was expected to be a short period of time. However, the FUTC was permanently shut down in 1991, and the site`s mission was changed from production to environmental restoration. The objective of this paper is to give an update on activities at the Fernald Site and to describe the Nuclear Criticality Safety issues that are currently being addressed.

Marble, R.C.; Brown, T.D.

1994-05-01T23:59:59.000Z

379

Training and qualification program for nuclear criticality safety technical staff. Revision 1  

SciTech Connect

A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification.

Taylor, R.G.; Worley, C.A.

1997-03-05T23:59:59.000Z

380

Pantex receives two safety awards | National Nuclear Security...  

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

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Pantex receives two safety awards Pantex receives two safety awards Posted By Office of...

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


381

1ST. WORKSHOP ON ULTRA-RELATIVISTIC NUCLEAR COLLISIONS. MAY 21-24, 1979  

E-Print Network (OSTI)

developed in the nuclear context ve find the self-consiof the nuclear fluid dynamical model which ve use later onI the sound ve which for groundst cice nuclear matter (p

Wenzel, W.

2010-01-01T23:59:59.000Z

382

DOE P 420.1 Department of Energy Nuclear Safety Policy  

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

POLICY POLICY Washington, D.C. Approved: 2-08-2011 SUBJECT: DEPARTMENT OF ENERGY NUCLEAR SAFETY POLICY PURPOSE: To document the Department of Energy's (DOE) nuclear safety policy. SCOPE: The provisions of this policy apply to all Departmental elements with responsibility for a nuclear facility, except the Naval Nuclear Propulsion Program, which is separately covered under Executive Order 12344, Title 50 United States Code, sections 2406 and 2511. This Policy cancels Secretary of Energy Notice 35-91, Nuclear Safety Policy, dated 9-9-91. POLICY: It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the

383

The Defense Nuclear Facilities Safety Board - Strategic Plan...  

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

all of its defense nuclear facilities. Message from the Board Peter S. Winokur, Chariman Jessie H. Roberson, Vice Chariman John E. Mansfield Joseph F. Bader DEFENSE NUCLEAR...

384

Status report of the US Department of Energy`s International Nuclear Safety Program  

SciTech Connect

The US Department of Energy (DOE) implements the US Government`s International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program`s activities that have been completed as of September 1994 and discusses those activities currently in progress.

NONE

1994-12-01T23:59:59.000Z

385

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

2007-08-01T23:59:59.000Z

386

DOE G 420.1-1A, Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety  

Directives, Delegations, and Requirements

This Guide provides an acceptable approach for safety design of DOE hazard category 1, 2 and 3 nuclear facilities for satisfying the requirements of DOE O ...

2012-12-04T23:59:59.000Z

387

Development of a safety assessment approach for decontamination and decommissioning operations at nuclear facilities  

SciTech Connect

The US Department of Energy (DOE) is responsible for nearly 1000 nuclear facilities which will eventually be decommissioned. In order to ensure that the health and safety of the workers, other personnel on site and the public in general is maintained during decontamination and decommissioning (D&D) operations, a methodology specifically for use in evaluating the nuclear safety of the associated activities is being developed within the Department. This methodology represents not so much a departure from that currently fish in the DOE when conducting safety assessments of operations at nuclear facilities but, rather, a formalization of those methods specifically adapted to the D&D activities. As such, it is intended to provide the safety assessment personnel with a framework on which they can base their technical judgement, to assure a consistent approach to safety assessment of D&D operations and to facilitate the systematic collection of data from facilities in the post-operational part of the life cycle.

Worthington, P.R. [USDOE, Washington, DC (United States); Cowgill, M.G. [Brookhaven National Lab., Upton, NY (United States)

1994-12-31T23:59:59.000Z

388

6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety  

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

6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety 6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety Management, AGENCY: Department of Energy (DOE). 6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety Management, AGENCY: Department of Energy (DOE). The Department of Energy (DOE) has issued Ruling 1995-1 which interprets certain regulatory provisions relating to DOE's nuclear safety requirements. This Ruling is intended to be a generally applicable clarification that addresses questions concerning the applicability and effect of these provisions. Ruling 1995-1; Ruling concerning 10 CFR Parts 830 and 835 More Documents & Publications Appendix A. Notice of Inquiry: Preparation of Report to Congress on Price-Anderson Act. 62 Federal Register 68,272 (December 31, 1997) Report to Congress on the Price-Anderson Act

389

Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR  

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

Nuclear Safety Management, Final Rule; Delay of Effective Date (66 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 In accordance with the memorandum of January 20, 2001, from the Assistant to the President and Chief of Staff, entitled ''Regulatory Review Plan,'' published in the Federal Register on January 24, 2001 (66 FR 7702), this action temporarily delays for 60 days the effective date of the rule entitled ''Alternate Fuel Transportation Program; Biodiesel Fuel Use Credit'' published in the Federal Register on January 11, 2001 (66 FR 2207). DATES: The effective date of the rule amending 10 CFR part 490

390

Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg  

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

Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg 4/17/01 Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg 4/17/01 In accordance with the memorandum of January 20, 2001, from the Assistant to the President and Chief of Staff, entitled ''Regulatory Review Plan,'' published in the Federal Register on January 24, 2001 (66 FR 7702), DOE temporarily delayed for 60 days (66 FR 8746, February 2, 2001) the effective date of the rule entitled ''Nuclear Safety Management'' published in the Federal Register on January 10, 2001 (66 FR 1810). DOE has now completed its review of that regulation, and does not intend to initiate any further rulemaking action to modify its provisions and confirms the effective date of April 10,

391

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

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

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

392

Role of criticality models in ANSI standards for nuclear criticality safety  

SciTech Connect

Two methods used in nuclear criticality safety evaluations in the area of neutron interaction among subcritical components of fissile materials are the solid angle and surface density techniques. The accuracy and use of these models are briefly discussed. (TFD)

Thomas, J.T.

1976-01-01T23:59:59.000Z

393

Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2  

Science Conference Proceedings (OSTI)

The FAR Manual is a convenient easy-to-use collection of the functions, assignments, and responsibilities (FARs) of DOE nuclear safety personnel. Current DOE directives, including Orders, Secretary of Energy Notices, and other assorted policy memoranda, are the source of this information and form the basis of the FAR Manual. Today, the majority of FARs for DOE personnel are contained in DOE`s nuclear safety Orders. As these Orders are converted to rules in the Code of Federal Regulations, the FAR Manual will become the sole source for information relating to the functions, assignments, responsibilities of DOE nuclear safety personnel. The FAR Manual identifies DOE directives that relate to nuclear safety and the specific DOE personnel who are responsible for implementing them. The manual includes only FARs that have been extracted from active directives that have been approved in accordance with the procedures contained in DOE Order 1321.1B.

Not Available

1994-10-15T23:59:59.000Z

394

DOE Cites CH2M Hill Hanford for Violating Nuclear Safety Rules | Department  

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

for Violating Nuclear Safety Rules for Violating Nuclear Safety Rules DOE Cites CH2M Hill Hanford for Violating Nuclear Safety Rules March 10, 2005 - 10:44am Addthis Hanford Tank Farm Contractor Faces Fine of more than $300,000 WASHINGTON, DC - The Department of Energy (DOE) today notified the CH2M Hill Hanford Group, Inc. (CH2M Hill) - that it will fine the company $316,250 for violations of the department's nuclear safety requirements. CH2M Hill is the department's contractor responsible for storage of highly radioactive and hazardous liquid waste at the Hanford Tank Farms near Richland, Wash. The Preliminary Notice of Violation (PNOV) issued today, cites four events that took place in 2003 and 2004. These events include the contamination of several workers while removing equipment from a valve pit

395

Workshop Registration  

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

Workshop Registration Workshop Registration Workshop Registration If you had previously registered for the cancelled October 2013 event, you must submit a new registration for the July 2014 event. Registration Form Last Name: First Name: Institution: Position: Mailing Address: Office Phone Number: Fax: Mobile Number: Email Address: Badging: I have a regular DOE Badge I do not have a regular DOE Badge and will need a Visitor Badge If you are a US citizen and do not have a DOE badge, bring a photo ID. If you are not a US citizen, contact Heath Garrison for more information. EFCOG Member: Is your company a member of EFCOG? If you are not sure, check the website. Yes No If you answered No to the above, were you invited by the Electrical Safety Subgroup Chair? Yes No Note: If you were not invited by the Subgroup Chair, do not submit your registration until you contact Greg Christensen, Idaho - Chair (208-526-5380) for approval to attend.

396

Nuclear Safety Component and Services Procurement, June 29, 2011 (HSS CRAD 45-12, Rev. 1)  

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

Office Office of Enforcement and Oversight Criteria Review and Approach Document Subject: Nuclear Safety Component and Services Procurement Inspection Criteria, Inspection Activities, and Lines of Inquiry HS: HSSCRAD 45-12 Rev.: 1 Eff.Date: 06/29/2011 Page 1 of 15 Acting Director, Office of Safety and Emergency Management Evaluations Date: G> |W ^ Criteria Lead, Nuclear Safety Component Procurement Date: G>/z9/z<>// 1.0 PURPOSE Within the Office of Enforcement and Oversight, the Office of Safety and Emergency Management Evaluations' mission is to assess the effectiveness of those environment, safety, and health systems and practices used by line and contractor organizations in implementing Integrated Safety Management; and to provide clear, concise, and independent evaluations of performance in protecting our workers, the public, and the environment from

397

Passive and inherent safety technologies for light-water nuclear reactors  

SciTech Connect

Passive/inherent safety implies a technical revolution in our approach to nuclear power safety. This direction is discussed herein for light-water reactors (LWRs) -- the predominant type of power reactor used in the world today. At Oak Ridge National Laboratory (ORNL) the approach to the development of passive/inherent safety for LWRs consists of four steps: identify and quantify safety requirements and goals; identify and quantify the technical functional requirements needed for safety; identify, invent, develop, and quantify technical options that meet both of the above requirements; and integrate safety systems into designs of economic and reliable nuclear power plants. Significant progress has been achieved in the first three steps of this program. The last step involves primarily the reactor vendors. These activities, as well as related activities worldwide, are described here. 27 refs., 7 tabs.

Forsberg, C.W.

1990-07-01T23:59:59.000Z

398

Assessment of Nuclear Safety Culture at the Pantex Plant, November 2012  

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

Pantex Plant Pantex Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Pantex Plant Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2 3.0 Results and Conclusions ....................................................................................................................... 3 4.0 Recommendations................................................................................................................................. 5

399

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices  

Science Conference Proceedings (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

400

PROCEEDINGS OF AEROSPACE NUCLEAR SAFETY, OCTOBER 1-4, 1963, ALBUQUERQUE, NEW MEXICO  

SciTech Connect

Separate abstracts were prepared for 18 of the 28 papers presented; 8 were previously abstracted in NSA. Topics covered include safety programs and philosophy, nuclear safety aspects of SNAP desigu and of propulsion reactor design, environmental factors, and re-entry and postmission disposal. (R.E.U.)

Dunlap, R.E. ed.

1964-10-31T23:59:59.000Z

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


401

Nuclear nonproliferation and safety: Challenges facing the International Atomic Energy Agency  

SciTech Connect

The Chairman of the Senate Committee on Govermental Affairs asked the United States General Accounting Office (GAO) to review the safeguards and nuclear power plant safety programs of the International Atomic Energy Agency (IAEA). This report examines (1) the effectiveness of IAEA`s safeguards program and the adequacy of program funding, (2) the management of U.S. technical assistance to the IAEA`s safeguards program, and (3) the effectiveness of IAEA`s program for advising United Nations (UN) member states about nuclear power plant safety and the adequacy of program funding. Under its statute and the Treaty on the Non-Proliferation of Nuclear Weapons, IAEA is mandated to administer safeguards to detect diversions of significant quantities of nuclear material from peaceful uses. Because of limits on budget growth and unpaid contributions, IAEA has had difficulty funding the safeguards program. IAEA also conducts inspections of facilities or locations containing declared nuclear material, and manages a program for reviewing the operational safety of designated nuclear power plants. The U.S. technical assistance program for IAEA safeguards, overseen by an interagency coordinating committee, has enhanced the agency`s inspection capabilities, however, some weaknesses still exist. Despite financial limitations, IAEA is meeting its basic safety advisory responsibilities for advising UN member states on nuclear safety and providing requested safety services. However, IAEA`s program for reviewing the operational safety of nuclear power plants has not been fully effective because the program is voluntary and UN member states have not requested IAEA`s review of all nuclear reactors with serious problems. GAO believes that IAEA should have more discretion in selecting reactors for review.

Not Available

1993-09-01T23:59:59.000Z

402

U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety  

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

U.S. Department of Energy Oak Ridge Operations Nuclear Facility U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions More Documents & Publications Requirements in DOE O 5480.19, Conduct of Operations Requirements for DOE Facilities Cross-referenced to DOE O 422.1, Conduct of Operations. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility

403

Assessment of Nuclear Safety Culture at the Pantex Plant, November...  

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

the Plant. Human Performance Improvement Coordinator works with the Safety Team and Human Error team from BBS to conduct human performance evaluations. B-12 Data on the...

404

Resolution of the nuclear criticality safety issue for the Hanford site high-level waste tanks  

SciTech Connect

This paper describes the approach used to resolve the Nuclear Criticality Safety Issue for the Hanford Site high-level waste tanks. Although operational controls have been in place at the Hanford Site throughout its operating life to minimize the amount of fissile material discarded as waste, estimates of the total amount of plutonium that entered the waste tanks range from 500 to 1,000 kg. Nuclear criticality safety concerns were heightened in 1991 based on a review of waste analysis results and a subsequent U.S. Department of Energy 1399 review of the nuclear criticality program. Although the DOE review team concluded that there was no imminent risk of a criticality at the Hanford Site tank farms, the team also stated its concern regarding the lack of definitive knowledge of the fissile material inventory and distribution within the waste tanks and the lack of sufficient management support for the overall criticality safety program. An in-depth technical review of the nuclear criticality safety of the waste tanks was conducted to develop a defensible technical basis to ensure that waste tanks are subcritical. The review covered all relevant aspects of nuclear criticality safety including neutronics and chemical and physical phenomena of the waste form under aging waste conditions as well as during routine waste management operations. This paper provides a review of the technical basis to support the conclusion that given current plutonium inventories and operating conditions, a nuclear criticality is incredible. The DOE has been requested to close the Nuclear Criticality Safety Issue. The Defense Nuclear Facilities Safety Board is currently reviewing the technicalbasis.

Bratzel, D.R.

1997-01-07T23:59:59.000Z

405

Related Resources - Nuclear Data Program, Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

406

Publications: Other Resources - Nuclear Data Program - Nuclear...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

407

Publications 2005 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

408

Publications 2003 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

409

Contacts - Nuclear Data Program, Nuclear Engineering Division...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

410

Publications 2001 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

411

Publications 2004 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

412

Publications 2009 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

413

Nuclear Systems Analysis - Nuclear Engineering Division (Argonne...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

414

Publications 2011 - Nuclear Data Program - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

415

Qualification of safety-critical systems in TVO nuclear power plants  

Science Conference Proceedings (OSTI)

Teollisuuden Voima Oy (TVO) operates two nuclear power plant units in Finland and has started to build a third one. The current nuclear power units have to continuously maintain and update existing instrumentation and control systems (I&C). Each new ... Keywords: FMECA, SPICE, instrumentation and control, qualification, safety-critical systems

Juha Halminen; Risto Nevalainen

2007-11-01T23:59:59.000Z

416

National Postirradiation Examination Workshop Report  

SciTech Connect

A National Post-Irradiation-Examination (PIE) Workshop was held March 29-30, 2011, in Washington D.C., stimulated by the DOE Acting Assistant Secretary for Nuclear Energy approval on January 31, 2011 of the Mission Need Statement for Advanced Post-Irradiation Examination Capability. As stated in the Mission Need, A better understanding of nuclear fuels and material performance in the nuclear environment, at the nanoscale and lower, is critical to the development of innovative fuels and materials required for tomorrows nuclear energy systems. (2011) Developing an advanced post-irradiation capability is the most important thing we can do to advance nuclear energy as an option to meeting national energy goals. Understanding the behavior of fuels and materials in a nuclear reactor irradiation environment is the limiting factor in nuclear plant safety, longevity, efficiency, and economics. The National PIE Workshop is part of fulfilling or addressing Department of Energy (DOE) missions in safe and publically acceptable nuclear energy. Several presentations were given during the opening of the workshop. Generally speaking, these presentations established that we cannot continue to rely on others in the world to provide the capabilities we need to move forward with nuclear energy technology. These presentations also generally identified the need for increased microstructural understanding of fuels and materials to be coupled with modeling and simulation, and increased accessibility and infrastructure to facilitate the interaction between national laboratories and participating organizations. The overall results of the work of the presenters and panels was distilled into four primary needs 1. Understanding material changes in the extreme nuclear environment at the nanoscale. Nanoscale studies have significant importance due to the mechanisms that cause materials to degrade, which actually occur on the nanoscale. 2. Enabling additional proficiency in experimentation and analysis through robust modeling coupled with advanced characterization. 3. Advancing the infrastructure and accessibility of physical and administrative systems needed to meet the needs of participating organizations that are subject to different time cycles and constraints that make working and collaborating the national laboratories challenging. 4. Pursuing in-situ analysis and instrumentation to support the examination of dynamic changes to materials microstructure, deformation, and surface effects as they occur with time scales rather than the static comparison offered by current PIE methods. This Workshop Report responds to the research challenges for advanced/future PIE needs for nuclear materials development outlined by Energy Secretary Chu and the DOE-NE Research and Development Roadmap report, which was delivered to Congress in April 2010, (DOE-NE, 2010) by identifying the technial needs for fuel and material development specifically related to PIE. The information from the panels address these research challenges by identifying specific needs related to each of the topical areas. The focus of the Workshop was to identify gaps in the enabling capabilities for nuclear energy research and to identify high-priority fundamental capabilities to enable research to be completed that would likely have high impact on enabling nuclear energy as a significant contributor to energy production portfolios.

Schulthess, Jason L

2011-06-01T23:59:59.000Z

417

Plant Modernization with Digital Reactor Protection System Safety System Upgrades at US Nuclear Power Stations  

SciTech Connect

As the current fleet of nuclear power plants in the US reaches 25+ years of operation, obsolescence is driving many utilities to implement upgrades to both their safety and non-safety-related Instrumentation and Control (I and C) Systems. Digital technology is the predominant replacement technology for these upgrades. Within the last 15 years, digital control systems have been deployed in non-safety- related control applications at many utilities. In addition, a few utilities have replaced small safety-related systems utilizing digital technology. These systems have shown digital technology to be robust, reliable and simpler to maintain. Based upon this success, acceptance of digital technology has gained momentum with both utilities and regulatory agencies. Today, in an effort to extend the operating lives of their nuclear stations and resolve obsolescence of critical components, utilities are now pursuing digital technology for replacement of their primary safety systems. AREVA is leading this effort in the United States with the first significant digital upgrade of a major safety system. AREVA has previously completed upgrades to safety-related control systems emergency diesel engine controls and governor control systems for a hydro station which serves as the emergency power source for a nuclear station. Currently, AREVA is implementing the replacement of both the Reactor Protection System (RPS) and the Engineered Safety Features Actuation System (ESFAS) on all three units at a US PWR site. (authors)

Heckle, Wm. Lloyd; Bolian, Tricia W. [AREVA NP, an AREVA and Siemens Company, 1345 Ridgeland Parkway, Suite 130 (United States)

2006-07-01T23:59:59.000Z

418

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy  

Science Conference Proceedings (OSTI)

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system.

TRAWINSKI, B.J.

2000-02-08T23:59:59.000Z

419

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications  

Science Conference Proceedings (OSTI)

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

420

New Research Center to Increase Safety and Power Output of U.S. Nuclear  

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

New Research Center to Increase Safety and Power Output of U.S. New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors May 3, 2011 - 3:41pm Addthis Oak Ridge, Tenn. - Today the Department of Energy dedicated the Consortium for Advanced Simulation of Light Water Reactors (CASL), an advanced research facility that will accelerate the advancement of nuclear reactor technology. CASL researchers are using supercomputers to study the performance of light water reactors and to develop highly sophisticated modeling that will help accelerate upgrades at existing U.S. nuclear plants. These upgrades could improve the energy output of our existing reactor fleet by as much as seven reactors' worth at a fraction of the cost of building new reactors, while providing continued improvements in

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


421

Defense Nuclear Facilities Safety Board Public Meeting on the...  

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

HSS Independent Activity Report - Rev. 0 Report Number: HIAR-Y-12-2012-10-02 Site: Y-12 UPF Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management...

422

Nuclear criticality safety staff training and qualifications at Los Alamos National Laboratory  

SciTech Connect

Operations involving significant quantities of fissile material have been conducted at Los Alamos National Laboratory continuously since 1943. Until the advent of the Laboratory`s Nuclear Criticality Safety Committee (NCSC) in 1957, line management had sole responsibility for controlling criticality risks. From 1957 until 1961, the NCSC was the Laboratory body which promulgated policy guidance as well as some technical guidance for specific operations. In 1961 the Laboratory created the position of Nuclear Criticality Safety Office (in addition to the NCSC). In 1980, Laboratory management moved the Criticality Safety Officer (and one other LACEF staff member who, by that time, was also working nearly full-time on criticality safety issues) into the Health Division office. Later that same year the Criticality Safety Group, H-6 (at that time) was created within H-Division, and staffed by these two individuals. The training and education of these individuals in the art of criticality safety was almost entirely self-regulated, depending heavily on technical interactions between each other, as well as NCSC, LACEF, operations, other facility, and broader criticality safety community personnel. Although the Los Alamos criticality safety group has grown both in size and formality of operations since 1980, the basic philosophy that a criticality specialist must be developed through mentoring and self motivation remains the same. Formally, this philosophy has been captured in an internal policy, document ``Conduct of Business in the Nuclear Criticality Safety Group.`` There are no short cuts or substitutes in the development of a criticality safety specialist. A person must have a self-motivated personality, excellent communications skills, a thorough understanding of the principals of neutron physics, a safety-conscious and helpful attitude, a good perspective of real risk, as well as a detailed understanding of process operations and credible upsets.

Monahan, S.P.; McLaughlin, T.P.

1997-05-01T23:59:59.000Z

423

Nuclear Safety Component and Services Procurement, June 29, 2011...  

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

integrated with the DOE-approved Nuclear Maintenance Management Program, per DOE O 433.IB, Attachment 2, Requirement 2b(i), to ensure the availability of parts,...

424

Preliminary nuclear safety assessment of the NEPST (Topaz II) space reactor program  

SciTech Connect

The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz II space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as; neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz II system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway.

Marshall, A.C.

1993-01-01T23:59:59.000Z

425

Planning Workshop  

Science Conference Proceedings (OSTI)

Planning Workshop on Renewable Energy and Climate Science for the Americas: Metrology and Technology Challenges. ...

2013-12-05T23:59:59.000Z

426

MN Workshop  

Science Conference Proceedings (OSTI)

Page 1. NIST Special Publication 1093 Mass Notification Messages: Workshop Proceedings Erica D. Kuligowski Richard ...

2009-03-24T23:59:59.000Z

427

.Dear Secretary Bodman: In its response to the Defense Nuclear Facilities Safety Board's (Board)  

E-Print Network (OSTI)

of Energy (DOE) committed to revitalizing Integrated Safety Management (ISM) with "a set of actions the Department will pursue to re-confirm that ISM will be the foundation of the Department's safety management approach and to address identified weaknesses in implementation. " The enclosed technical report, DNFSB/TECH-36, Integrated Safety Management: The Foundation for an Effective Safety Culture, provides an assessment of the strengths and weaknesses of the current state of ISM implementation at the National Nuclear Security Administration's (NNSA) production plants and laboratories. ISM was established 10 years ago as a new approach to integrating work and safety. The concept was adopted by DOE to enhance safety awareness, upgrade formality of operations, and improve safety performance. However, the potential for this practical safety system to achieve operational excellence and instill a sustainable safety culture has not been fully realized. From the broadest perspective, requirements and mechanisms to implement ISM are established, but implementation of safety management systems varies from site to site. This report examines the current status of the effectiveness of ISM systems at the seven NNSA weapons sites, summarizes

Joseph F. Bader; John E Mansfield; The Honorable; Samuel W. Bodman; Oversight Of Complex; High-hazard Organizations; The Department; A J. Eggenberger; Ms Patty Wagner

2006-01-01T23:59:59.000Z

428

Group Differences in Safety Climate Among Workers in the Nuclear Decommissioning and Demolition Industry in the United States.  

E-Print Network (OSTI)

??This study investigated group differences in safety climate among workers in the nuclear decommissioning and demolition (D&D) industry in the United States. The study population (more)

Findley, Michael Everett

2004-01-01T23:59:59.000Z

429

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)  

SciTech Connect

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the software. The discussion provided herein illustrates benefits of applying the Safety Software Guide to work activities dependent on software applications and directed toward the design of new nuclear facilities. In particular, the Guide-based systematic approach with software enables design processes to effectively proceed and reduce the likelihood of rework activities. Several application examples are provided for the new facility.

VINCENT, Andrew

2005-07-14T23:59:59.000Z

430

Proceedings: Radioactive Low Level Waste Management Workshop  

Science Conference Proceedings (OSTI)

This report presents the proceedings of an EPRI workshop on low level waste management. The workshop was the fifth in a series to aid utility personnel in assessing technologies for decommissioning nuclear power plants. This workshop focused on specific aspects of low level waste management as they relate to nuclear plant decommissioning. Workshop information will help utilities assess benefits of waste management, select technologies for their individual projects, and reduce decommissioning costs.

2000-05-25T23:59:59.000Z

431

Defense Nuclear Facilities Safety Board Review at the Nevada National Security Site  

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

NNSS-2011-001 NNSS-2011-001 Site: Nevada National Security Site Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Defense Nuclear Facilities Safety Board Review at the Nevada National Security Site Dates of Activity 02/14/2011 - 02/17/2011 Report Preparer William Macon Activity Description/Purpose: The U.S. Department of Energy Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), visited the Nevada Site Office (NSO) and the Nevada National Security Site (NNSS) from February 14-17, 2011. The purpose of the visit was to observe the Defense Nuclear Facilities Safety Board (DNFSB) review and maintain operational awareness of NNSS activities. Result:

432

Safety Aspects of Wet Storage of Spent Nuclear Fuel, OAS-L-13-11  

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

Safety Aspects of Wet Storage of Safety Aspects of Wet Storage of Spent Nuclear Fuel OAS-L-13-11 July 2013 Department of Energy Washington, DC 20585 July 10, 2013 MEMORANDUM FOR THE SENIOR ADVISOR FOR ENVIRONMENTAL MANAGEMENT FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Safety Aspects of Wet Storage of Spent Nuclear Fuel" BACKGROUND The Department of Energy (Department) is responsible for managing and storing spent nuclear fuel (SNF) generated by weapons and research programs and recovered through nonproliferation programs. The SNF consists of irradiated reactor fuel and cut up assemblies containing uranium, thorium and/or plutonium. The Department stores 34 metric tons of heavy metal SNF primarily

433

Nuclear Safety Management, Final Rule amending 10 CFR Part 830 (66 FR  

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

Management, Final Rule amending 10 CFR Part 830 (66 Management, Final Rule amending 10 CFR Part 830 (66 FR 1810), Federal Register (Fed Reg), 1/10/2001 Nuclear Safety Management, Final Rule amending 10 CFR Part 830 (66 FR 1810), Federal Register (Fed Reg), 1/10/2001 SUMMARY: The Department of Energy (DOE) adopts, with minor changes, the interim final rule published on October 10, 2000, to amend the DOE Nuclear Safety Management regulations. EFFECTIVE DATE: This final rule is effective on February 9, 2001. FOR FURTHER INFORMATION CONTACT: Richard Black, Director, Office of Nuclear and Facility Safety Policy, 270CC, Department of Energy, 19901 Germantown Road, Germantown, MD 20874; telephone: 301-903-3465; email: Richard.Black@eh.doe.gov SUPPLEMENTARY INFORMATION: I. Introduction and Summary On October 10, 2000, the Department of Energy (DOE) published an

434

Safety Related Applications (Sensors and Instrumentation and...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

435

AGENCY: Defense Nuclear Facilities Safety Board, ACTION: Notice...  

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

upon to accomplish the mission assigned to DOE and NNSA under the Atomic Energy Act of 1954, as amended, at defense nuclear facilities . We will focus on what impact DOE's and...

436

Fundamentals of Nuclear Safety and Their Application in Design...  

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

The success or failure of these measures can be assessed with reference to the Three-mile Island, Chernobyl and Fukushima nuclear power plant accidents. Rev 1, 25 May 2011...

437

The uses and benefits of probabilistic risk assessment in nuclear reactor safety  

SciTech Connect

Probabilistic risk assessment (PRA) has proven to be an important tool in the safety assessment of nuclear reactors throughout the world. Decision making with regard to many safety issues has been facilitated by both general insights from and direct application of this technology. Key uses of PRA are discussed and some examples of successful applications are cited. The benefits and limitations of PRA are also discussed as well as the broader outlook for applications of PRA. 9 refs.

Bari, R.A.; Speis, T.P. (Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research)

1989-01-01T23:59:59.000Z

438

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

439

Report on the workshop "Decay spectroscopy at CARIBU: advanced fuel cycle applications, nuclear structure and astrophysics". 14-16 April 2011, Argonne National Laboratory, USA.  

SciTech Connect

A workshop on 'Decay Spectroscopy at CARIBU: Advanced Fuel Cycle Applications, Nuclear Structure and Astrophysics' will be held at Argonne National Laboratory on April 14-16, 2011. The aim of the workshop is to discuss opportunities for decay studies at the Californium Rare Isotope Breeder Upgrade (CARIBU) of the ATLAS facility with emphasis on advanced fuel cycle (AFC) applications, nuclear structure and astrophysics research. The workshop will consist of review and contributed talks. Presentations by members of the local groups, outlining the status of relevant in-house projects and availabile equipment, will also be organized. time will also be set aside to discuss and develop working collaborations for future decay studies at CARIBU. Topics of interest include: (1) Decay data of relevance to AFC applications with emphasis on reactor decay heat; (2) Discrete high-resolution gamma-ray spectroscopy following radioactive decya and related topics; (3) Calorimetric studies of neutron-rich fission framgents using Total ABsorption Gamma-Ray Spectrometry (TAGS) technique; (4) Beta-delayed neutron emissions and related topics; and (5) Decay data needs for nuclear astrophysics.

Kondev, F.; Carpenter, M.P.; Chowdhury, P.; Clark, J.A.; Lister, C.J.; Nichols, A.L.; Swewryniak, D. (Nuclear Engineering Division); (Univ. of Massachusetts); (Univ. of Surrey)

2011-10-06T23:59:59.000Z

440

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR  

SciTech Connect

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

1983-08-01T23:59:59.000Z

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


441

Nuclear Criticality Safety Organization guidance for the development of continuing technical training. Revision 1  

SciTech Connect

The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in nuclear criticality safety at the Oak Ridge Y-12 Plant and throughout the DOE complex. Continuing technical training is training outside of the initial qualification program to address identified organization-wide needs. Typically, this training is used to improve organization performance in the conduct of business. This document provides guidelines for the development of the technical portions of the Continuing Training Program. It is not a step-by-step procedure, but a collection of considerations to be used during the development process.

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1997-05-20T23:59:59.000Z

442

2002 DOE/DNFSB Interface Workshop - Participants  

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

DOE/DNFSB Interface Workshop DOE/DNFSB Interface Workshop PARTICIPANTS Amerine, Dave CH2M HILL Hanford Group, Hanford P. O. Box 1500 MSIN: H6-63 Richland, WA 99352 509-376-5107 509-372-1664 (Fax) David_B_Amerine@rl.gov Bailey, Nolan Board Point of Conact, Nevada Operations Office 232 Energy Way North Las Vegas, NA 89030 702-295-4601 702-295-2261 (Fax) bailey@nv.doe.gov Bartlett, William Carlsbad Technical Assistance Contractor, WIPP 4021 National Parks Hwy Carlsbad, NM 88220 505-234-7160 505-234-7198 (Fax) bill.bartlett@wipp.ws Beck, Dave NNSA Assistant Deputy Administrator for Military Application and Stockpile Operations, NA-12 1000 Independence Ave Washington, DC 20585 202-586-4879 Black, Dick Director, EH Office of Nuclear and Facility Safety Policy, EH-53 1000 Independence Ave

443

Nuclear criticality safety evaluation of SRS 9971 shipping package  

SciTech Connect

This evaluation is requested to revise the criticality evaluation used to generate Chapter 6 (Criticality Evaluation) of the Safety Analysis Report for Packaging (SARP) for shipment Of UO{sub 3} product from the Uranium Solidification Facility (USF) in the SRS 9971 shipping package. The pertinent document requesting this evaluation is included as Attachment I. The results of the evaluation are given in Attachment II which is written as Chapter 6 of a NRC format SARP.

Vescovi, P.J.

1993-02-01T23:59:59.000Z

444

THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER (RSICC) - A RESOURCE FOR COMPUTATIONAL TOOLS FOR NUCLEAR APPLICATIONS  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC), which has been in existence since 1963, is the principal source and repository in the United States for computational tools for nuclear applications. RSICC collects, organizes, evaluates and distributes nuclear software and data involving the transport of neutral and charged particle radiation, and shielding and protection from radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste. RSICC serves over 12,000 scientists and engineers from 94 countries. RSICC software provides in-depth coverage of radiation related topics: the physics of the interaction of radiation with matter, radiation production and sources, criticality safety, radiation protection and shielding, radiation detectors and measurements, shielding materials properties, radiation waste management, atmospheric dispersion and environmental dose, medical applications, macro- and micro-dosimetry calculations.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

445

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01T23:59:59.000Z

446

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)  

Science Conference Proceedings (OSTI)

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Cottrell, W.B.; Passiakos, M.

1982-06-01T23:59:59.000Z

447

Space nuclear safety program: Progress report, July--September 1987  

SciTech Connect

This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. The studies discussed are ongoing; the results and conclusions described may change as the work progresses. 20 figs., 4 tabs.

George, T.G. (comp.)

1989-02-01T23:59:59.000Z

448

March 7, 2012, USW Health Safety and Environment Conference Presentations - Improving Safety Culture at DOE Sites  

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

Improving Safety Culture Improving Safety Culture at DOE Sites William Eckroade Principal Deputy Chief for Mission Support Operations Office of Health, Safety and Security U.S. Department of Energy USW Health, Safety and Environment Conference HSS Workshop March 7, 2012 2 BACKGROUND WHAT IS SAFETY CULTURE? * Safety Culture: An organization's values and behaviors modeled by its leaders and internalized by its members, which serve to make safe performance of work the overriding priority to protect workers, the public, and the environment. KEY REGUALTORY DRIVERS: * DOE Policy 420.1, Department of Energy Nuclear Safety Policy * DOE Order 450.2, Integrated Safety Management * DOE Guide 450.4-1C, Integrated Safety Management System

449

SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing  

SciTech Connect

Review of NMP-NCS-94-0087, ``Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,`` was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion.

Rathbun, R. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-26T23:59:59.000Z

450

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

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

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

451

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

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

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

452

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who  

SciTech Connect

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

Forsberg, C.W.; Reich, W.J.

1991-09-01T23:59:59.000Z

453

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who  

SciTech Connect

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

Forsberg, C.W.; Reich, W.J.

1991-09-01T23:59:59.000Z

454

Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper  

SciTech Connect

This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

Pete Jordan

2010-09-01T23:59:59.000Z

455

Safety Aspects of Nuclear Desalination with Innovative Systems; the EURODESAL Project  

SciTech Connect

The proposed paper reports the results of a preliminary investigation on safety impact deriving from the coupling of a desalination plant with a 600 MWe Passive Design PWR like the AP600 Nuclear Power Plant. This evaluation was performed in the frame of the EURODESAL Project of the 5. EURATOM Framework Programme. (authors)

Alessandroni, C.; Cinotti, L.; Mini, G. [Ansaldo Nucleare, C.so Perrone, 25 - Genova (Italy); Nisan, S. [CEA-CEN Cadarache, F-13108 Saint Paul-lez-Durance (France)

2002-07-01T23:59:59.000Z

456

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

457

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

458

Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities  

E-Print Network (OSTI)

One of the strong motivations for pursuing the development of fusion energy is its potentially low environmental impact and very good safety performance. But this safety and environmental potential can only be fully realized by careful design choices. For DEMO and other fusion facilities that will require nuclear licensing, S&E objectives and criteria should be set at an early stage and taken into account when choosing basic design options and throughout the design process. Studies in recent decades of the safety of fusion power plant concepts give a useful basis on which to build the S&E approach and to assess the impact of design choices. The experience of licensing ITER is of particular value, even though there are some important differences between ITER and DEMO. The ITER project has developed a safety case, produced a preliminary safety report and had it examined by the French nuclear safety authorities, leading to the licence to construct the facility. The key technical issues that arose during ...

Taylor, Neill

2013-01-01T23:59:59.000Z

459

Advanced reactors, passive safety, and acceptance of nuclear energy  

SciTech Connect

If nuclear power is to make a serious impact on CO{sub 2} emission, the industry will have to be very large. A 1000-MWe coal-fired power plant releases about 1.4 {times} 10{sup {minus}3} gigatons of carbon per year in the form of CO{sub 2}. The total of 6 GTC/yr of carbon released by human use of 300 quads/yr of energy worldwide then corresponds to the equivalent of about 4000 one-gigawatt power plants. By the middle of the next century, the world's energy demand might grow to about 500 quads/yr. One might halve the implied 10 GTC/yr by deploying 3500 1000-megawatt large reactors. Now the median core melt probability of today's fleet of reactors is according to Rasmussen 5 {times} 10{sup {minus}5} per reactor year which corresponds to a core melt frequency in such a large nuclear system of 0.18/yr - one accident equivalent to that at Three Mile Island Unit 2 every six years. This is almost surely unacceptable. Thus one concludes that a necessary condition for deployment of nuclear reactors on a scale sufficient to contribute significantly to mitigation of the greenhouse effect is reduction of the core melt probability considerably below Rasmussen's fiducial figure. In this paper, the authors summarize developments, both institutional and technical, since 1985 in the development of safer, if not inherently safe, reactors.

Forsberg, C.W. (Chemical Technology Div., Oak Ridge National Lab., Oak Ridge, TN (US)); Weinberg, A.M. (Oak Ridge Associated Univ., Oak Ridge, TN (US))

1990-01-01T23:59:59.000Z

460

NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations, Fact Sheet  

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

Sheet Sheet NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations On August 22, 2011, the National Nuclear Security Administration (NNSA) issued a Preliminary Notice of Violation (PNOV) to National Security Technologies, LLC (NSTec) for violations of Department of Energy's (DOE) nuclear safety regulations. NSTec is the operating contractor of NNSA's Nevada National Security Site (NNSS) located 65 miles northwest of Las Vegas, Nevada. The PNOV cites four violations of DOE regulations governing nuclear safety management. The violations are associated with quality assurance (QA) related deficiencies in the inspection and installation of penetration fire seals and other components at the Criticality Experiments Facility