ML102250477
| ML102250477 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/13/2010 |
| From: | NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| Shared Package | |
| ML102250464 | List: |
| References | |
| 50-282-LR, 50-306-LR, ASLBP 08-871-01-LR-BD01, RAS 18398 | |
| Download: ML102250477 (4) | |
Text
NRC STAFF EXHIBIT LIST August 13, 2010 Document Exhibit No.
Safety Evaluation Report Related to the License Renewal of Prairie Island 1 Nuclear Generating Plant, Units 1 and 2 (October 2009)
Safety Evaluation Report With Open Items Related to the License Renewal of 2 Prairie Island Nuclear Generating Plant Units 1 and 2 (June 2009)
Advisory Committee on Reactor Safeguards Report on Safety Aspects of the 3 License Renewal Application for the Prairie Island Nuclear Generating Plant, Units 1 & 2 (December 10, 2009)
NUREG-1800 Standard Review Plan for Review of License Renewal 4 Applications for Nuclear Power Plants (SRP-LR) (September 2005).
NUREG-1800 Standard Review Plan for Review of License Renewal 4A Applications for Nuclear Power Plants (SRP-LR) (September 2005) (Excerpt)
Corrected Prairie Island May 20, 2010 Annual Assessment Meeting Slides 5 Inspection Manual Chapter 308 Reactor Oversight Process (ROP) Basis 6 Document Inspection Manual Chapter 0308 Reactor Oversight Process (ROP) Basis 7 Document, Attachment 3 Significance Determination Process Basis Document Inspection Manual Chapter 2515 Light-Water Reactor Inspection Program- 8 Operations Phase Inspection Manual Chapter 2515 Appendix A, Risk Informed baseline 9 Inspection Program Inspection Manual Chapter 305 Operating Reactor Assessment Program 10 Inspection Manual Chapter 305 Operating Reactor Assessment Program 11 Exhibit 4-Action Matrix Inspection Manual Chapter 609 Significance Determination Process 12 Inspection Manual Chapter 0612 Power Reactor Inspection Reports 13 Inspection Manual Chapter 0608 Performance Indicator Program 14 Inspection Manual Chapter 0307 Reactor Oversight Process Self- 15 Assessment Program Inspection Manual Chapter 0307 Reactor Oversight Process Self- 16 Assessment Program Appendix A Inspection Manual Chapter 1245 Qualification Program for Operating Reactor 17 Programs Inspection Manual Chapter 0313 Industry Trends Program 18
Inspection Manual Chapter 0310 Components Within the Cross Cutting 19 Areas Inspection Manual Chapter 71003 Post Approval Site Inspection for License 20 Renewal Inspection Procedure 71152 Problem Identification and Resolution 21 Inspection Procedure 95001 Inspection for One or Two White Inputs in a 22 Strategic Performance Area Inspection Procedure 95002 Inspection for One Degraded Cornerstone or 23 Any Three White Inputs in a Strategic Performance Area Inspection Procedure 95003 Supplemental Inspection for Repetitive 24 Degraded Cornerstones, or Multiple Yellow Inputs, or One Red Input Inspection Procedure Attachment 95003.02 Guidance for Conducting an 25 Independent NRC Safety Culture Assessment F.W. Guldenmund, The Nature of Safety Culture: A Review of Theory and 26 Research Safety Science 34 (2000) pp. 215-257 Kathryn Mearns et al., Safety climate, Safety Management Practice and 27 Safety Performance in Offshore Environments Safety Science 41(2003) pp. 641-680 Benjamin Schneider et al., Creating a Climate and Culture for Sustainable 28 Organizational Change 1996 Institute for Nuclear Power Operations Principles for a Strong Nuclear Safety 29 Culture November 2004 Douglas A. Wiegmann, et al. A Synthesis of Safety Culture and Safety 30 Climate Research June 2002 Terry L. von Thaden & Alyssa M. Gibbons The Safety Culture Indicator Scale 31 Measurement System (SCISMS) July 2008 Safety Culture: A Report by the International 32 Nuclear Safety Advisory Group (INSAG). INSAG-4, International Atomic Energy Agency Vienna, Austria 1991 Safety Culture: A Report by the International 33 Nuclear Safety Advisory Group (INSAG). INSAG-10, International Atomic Energy Agency Vienna, Austria 1996 Management of Operational Safety at Nuclear 34 Power Plants: A Report by the International Nuclear Safety Advisory Group (INSAG), INSAG-13 International Atomic Energy Agency Vienna, Austria 1999 Policy Statement on the Conduct of Nuclear Power Plant Operations, 54 35 Fed. Reg. 3424 (January 24, 1989)
Freedom of Employees in the Nuclear Industry to Raise Safety Concerns 36 Without Fear of Retaliation, 61 Fed. Reg. 24336 (May 14, 1996)
SRM COMGBJ-08-0001 A Commission Policy Statement on Safety Culture, 37 (February 25, 2008)
SECY-09-0075 Safety Culture Policy Statement (March 18, 2009) 38 SRM-SECY-09-0075 Safety Culture Policy Statement (October 16, 2009) 39 Draft Safety Culture Policy Statement: Request for Public Comments, 74 40 Fed. Reg. 57525 (November 6, 2009)
Draft Safety Culture Policy Statement: Request for Public Comments; 41 Extension of Comment Period 75 Fed. Reg. 1656 (January 12, 2010)
SRM-SECY-04-0111 Recommended Staff Actions Regarding Agency 42 Guidance in the Areas of Safety Conscious Work Environment and Safety Culture (August 30, 2004)
SRM-SECY-05-0187 Status of Safety Culture Initiatives and Schedule for 43 Near-Term Deliverables (December 21, 2005)
Regulatory Information Summary 2006-13, Information on the Changes to the 44 Reactor Oversight Process to More Fully Address Safety Culture (July 31, 2006)
Palo Verde Nuclear Generating Station NRC Supplemental Inspection 95003 45 Inspection Report February 1, 2008 Prairie Island Nuclear Generating Plant Supplemental Inspection Report 46 0500282/200911 (October 15, 2009)
Prairie Island Nuclear Generating Plant Supplemental Inspection Report 47 0500282(306)/2009015 (January 12, 2009)
Mid-Cycle Performance Review and Inspection Plan- Prairie Island Nuclear 48 Generating Plant, Units 1 & 2 (September 1, 2009)
Biennial Problem Identification and Resolution Inspection Report 2009009 49 (September 25, 2009)
NRC Integrated Inspection Report No. 0500282/2010003; 05000306/2010003 50 (July 26, 2010)
Prairie Island Nuclear Generating Station Final Significance Determination 51 NRC Inspection Report No. 05000282/2008008 (January 27, 2009)
NRC Special Inspection Report 05000282/2008008; 05000306/2008008 52 Preliminary White Finding (November 7, 2008)
Final Significance Determination for White Finding and Notice of Violation; 53 NRC Inspection Report 05000282/2009008; 05000306/2009008 (May 6, 2009)
NRC Inspection Report 05000282/2008009; 05000306/2008009 Preliminary 54 Significance Determination for Yellow Finding (February 10, 2009)
Final Significance Determination for White Findings and Notice of Violation 55 NRC Inspection Report 05000306/2009013 (September 3, 2009)
NRC Inspection Report 05000282/2009010; 05000306/2009010 (August 5, 56 2009)
Reactor Containment Diagram 57
Steven Yule et al., The Role of Management and Safety Climate in 58 Preventing Risk-taking at Work, Int. J. Risk Assessment and Management, Vol. 7, No. 2 (2007)
Biennial Problem Identification and Resolution Inspection Report 59 05000282/2007006 AND 05000306/2007006 (December 27, 2009)
SECY 06-0122 Safety Culture Initiative Activities to Enhance the Reactor 60 Oversight Process and Outcomes of the Initiatives (May 24, 2006)
NRC Staff Slide from Public Meeting with the Nuclear Energy Institute and 61 Industry Representatives Re: Nuclear Safety Culture Assessment Pilot (February 24, 2010)
Summary of July 28, 2010 Public Meeting to Discuss Observations and 62 Lessons Learned During the Pilot Application of the Nuclear Energy Institutes Nuclear Safety Culture Assessment Process (August 4, 2010)
Boric Acid Corrosion Guidebook, Revision 1: Managing Boric Acid Corrosion 63 Issues at PWR Power Stations, EPRI, Palo Alto, CA (2001) 1000975 (Pages 4-25 & 4-26)