ML091490607
| ML091490607 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/29/2009 |
| From: | Doris Lewis Northern States Power Co, Pillsbury, Winthrop, Shaw, Pittman, LLP |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| 50-282-LR, 50-306-LR, ASLBP 08-871-01-LR-BD01, RAS 3930 | |
| Download: ML091490607 (10) | |
Text
May 29, 2009 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )
) Docket Nos. 50-282-LR Northern States Power Co. ) 50-306-LR
)
(Prairie Island Nuclear Generating Plant, ) ASLBP No. 08-871-01-LR Units 1 and 2) )
NSPMS THIRD SUPPLEMENTAL DISCLOSURE Pursuant to 10 C.F.R. § 2.336(d), Northern States Power Company - a Minnesota Corporation (NSPM) hereby supplements its initial disclosures as follows. A description by category and location of relevant, non-privileged documents and data compilations that have been identified as subsequently developed or obtained is provided in Attachment 1.
Arrangements for reviewing these documents at the Prairie Island Nuclear Generating Plant Training Center can be made by contacting Mr. Eugene Eckholt at 651-388-1121 ext. 4137.
Arrangements for reviewing these documents in Washington D.C. can be made by contacting Ms. Stefanie Nelson at 202-663-9382. A listing of documents that are proprietary is provided in .
Respectfully Submitted,
/Signed electronically by David R. Lewis/
David R. Lewis Matias F. Travieso-Diaz PILLSBURY WINTHROP SHAW PITTMAN LLP 2300 N Street, NW Washington, DC 20037-1128 Tel. (202) 663-8474 Dated: May 29, 2009 Counsel for Northern States Power Co.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )
) Docket Nos. 50-282-LR Northern States Power Co. ) 50-306-LR
)
(Prairie Island Nuclear Generating Plant, ) ASLBP No. 08-871-01-LR Units 1 and 2) )
CERTIFICATE OF SERVICE I hereby certify that copies of NSPMs Third Supplemental Disclosures, dated May 29, 2009, was provided to the Electronic Information Exchange for service on the individuals listed below, this 29th day of May, 2009.
Administrative Judge Administrative Judge William J. Froehlich, Esq., Chair Dr. Gary S. Arnold Atomic Safety and Licensing Board Atomic Safety and Licensing Board Mail Stop T-3 F23 Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Washington, D.C. 20555-0001 Email: wjf1@nrc.gov Email: gxa1@nrc.gov Administrative Judge Secretary Dr. Thomas J. Hirons Attn: Rulemakings and Adjudications Staff Atomic Safety and Licensing Board Mail Stop O-16 C1 Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Washington, D.C. 20555-0001 secy@nrc.gov; hearingdocket@nrc.gov Email: thomas.hirons@nrc.gov Office of Commission Appellate Adjudication Beth N. Mizuno, Esq.
Mail Stop O-16 C1 David E. Roth, Esq.
U.S. Nuclear Regulatory Commission Maxwell C. Smith, Esq, Washington, DC 20555-0001 Office of the General Counsel E-mail: ocaamail@nrc.gov Mail Stop O-15 D21 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 E-mail: beth.mizuno@nrc.gov; david.roth@nrc.gov; maxwell.smith@nrc.gov
Philip R. Mahowald, Esq.
General Counsel, Prairie Island Indian Community 5636 Sturgeon Lake Road Welch, MN 55089 pmahowald@piic.org
/Signed electronically by David R. Lewis/
David R. Lewis
ATTACHMENT 1 Northern States Power Co.
Prairie Island Nuclear Generating Plant, Units 1 and 2 License Renewal Proceeding Docket Nos. 50-282-LR, 50-306-LR; ASLBP No. 08-871-01-LR Production Log for NSPMs Third Supplemental Disclosures (May 29, 2009)
Document ID Description Contention PROD00006691 LRA supplement for PWR Vessel Internals Program 7 PROD00006692 LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006693 LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006694 Draft LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006695 Draft LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006696 Draft LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006697 Draft LRA supplement for PWR Vessel Internals AMP with handwritten notes 7 PROD00006698 Excerpt from LRA of Section 3.1.2.1.3 7, 8 PROD00006699 Addendum to License Renewal Report for Reactor Internals System 7 PROD00006700 Addendum to License Renewal Report regarding Reactor Internals system 7 PROD00006701 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006702 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006703 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006704 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006705 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006706 LRA Table 3.1.1 (Summary of Aging Management evaluations for reactor vessel, internals) 7, 8 PROD00006707 Table of Aging Management Requirements for Westinghouse Plants Primary Components 7, 8 PROD00006708 Excerpts from LRA regarding aging management for reactor vessel, internals 7, 8 PROD00006709 Excerpts from LRA regarding aging management for reactor vessel, internals 7, 8 PROD00006710 Excerpts from LRA regarding aging management for reactor vessel, internals 7, 8 PROD00006711 Table 3.1.2.3 excerpt from LRA regarding aging management for reactor vessel, internals 7, 8 PROD00006712 Appendix A USAR Supplement including statement of PWR Vessel Internals Program 7 PROD00006713 Draft PWR Vessel Internals Program (AMP) with handwritten notes 7 PROD00006714 LRA Aging Management Programs Correlation chart 7, 8 PROD00006715 LRA Integrated Plant Assessment Methodology Report draft regarding PWR Vessel Internals Program 7 PROD00006716 LRA excerpt regarding PWR Vessel Internals Program 7 PROD00006717 Exceprt from chart of PINGP License Renewal Commitments 7 PROD00006718 LRA change to incorporate PWR Vessel Internals Program 7 PROD00006719 LRA supplement for PWR Vessel Internals Program with handwritten notes 7 PROD00006720 LRA excerpts regarding PWR Vessel Internals Program 7 PROD00006721 Draft LRA supplement for PWR Vessel Internals Program with handwritten notes 7
Document ID Description Contention PROD00006722 March 10, 2008 PWR Owners Group Executive Management Group/NRC Meeting Presentation 7 PROD00006723 PWR Owners Group, October 2008 General Session, Materials Subcommittee Presentation 7 PROD00006724 March 9, 2009 PWR Owners Group Executive Management Group/NRC Meeting Presentation 7 PROD00006725 PWR Owners Group, February 2009 General Session, Materials Subcommittee Presentation 7 PROD00006726 Westinghouse Presentation: Recent Experience with Alloy 52 Welds 8 PROD00006727 Westinghouse Presentation: ASME Code Activities Update, December 2008 8 PROD00006728 Westinghouse Presentation: Comparison of Inspection Requirements of Code Case N-770 and MRP-139 8 Rev. 1 PROD00006729 EdF Bottom Nozzle Inspection Experience Presentation 8 PROD00006730 Internals LR-RVI-Progplan: Ginna Approach 7, 8 PROD00006731 PWR Owners Group Materials Subcommittee Mission Statement 7 PROD00006732 PWR Owners Group Materials Alignment Strategic Plan 7, 8 PROD00006733 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Reactor Vessel ISI 10 to 20 Year Interval 7 Extension - Plant Specific Work Presentation PROD00006734 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Proactive Program for Measurement of 7 Westinghouse Upper Internals Guide Tube Wear Project Review PROD00006735 PWR Owners Group, April 2009 Materials Subcommittee Meeting, PWSCC Crack Initiation Testing of Farley 8 Unit 2 Alloy 600 CRDM Penetrations PROD00006736 PWR Owners Group, April 2009 Materials Subcommittee Meeting, RV Primary Nozzle Weld Inlay PDI 8 Equivalency Testing and Process Qualification Presentation PROD00006737 PWR Owners Group, April 2009 Materials Subcommittee Meeting, B&W RV Internals Structural Bolt 7 Evaluations: Phase II Presentation PROD00006738 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Reactor Internals Material Issues Industry 7 Participation and Strategic Planning Support Presentation PROD00006739 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Technical Support to MRP and Other 8 Industry Groups for Alloy 600 Issues Presentation PROD00006740 PWR Owners Group, April 2009 Materials Subcommittee Meeting, RPV Integrity Industry Support and 7 Strategic Plan Presentation PROD00006741 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Reactor Internals Acceptance Criteria, 7 Methodology and Data Requirements Presentation PROD00006742 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Overview of MSC Activities Since 7 December 2008 PWROG MSC Meeting PROD00006743 Minutes from PWR Owners Group Materials Subcommittee Meeting, April 2008 Charleston 7, 8 PROD00006744 Minutes from PWR Owners Group Materials Subcommittee Meeting, April 2008 San Francisco 7, 8 PROD00006745 Minutes from PWR Owners Group Materials Subcommittee Meeting, April 2009 7, 8 PROD00006746 Minutes from PWR Owners Group Materials Subcommittee Meeting, December 2008 7, 8 2
Document ID Description Contention PROD00006747 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Reactor Internals Acceptance Criteria 7 Methodology and Data Requirement - Phase II Presentation PROD00006748 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Reactor Internals Operating Experience 7 Review, Risk Ranking and Contingency Planning Presentation PROD00006749 PWR Owners Group, April 2009 Materials Subcommittee Meeting, Alloy 600 Decision Advisor Overview 8 Presentation PROD00006750 Draft Settlement Agreement re: Contention 2 2 PROD00006751 Email from C. Koehler to L. Drenth et al. re: reactor vessel internals 7 PROD00006752 Email from L. Drenth to W. O'Brien and C. Koehler re: reactor vessel internals 7 PROD00006753 Email from C. Koehler to L. Drenth and W. O'Brien re: reactor vessel internals 7 PROD00006754 Email from C. Koehler to L. Drenth et al. re: reactor vessel internals 7 PROD00006755 Email from C. Koehler to L. Drenth and W. O'Brien re: reactor vessel internals 7 PROD00006756 License Renewal Aging Management Program Basis Document: Ginna Station: Reator Vessel Internals 7 Program: Revision 2 PROD00006757 Email from L. Drenth to R. Pearson et al. re: reactor vessel internals 7 PROD00006758 Email from R. Pearson to L. Drenth et al. re: reactor vessel internals 7 PROD00006759 Email from C. Koehler to R. Pearson et al. re: reactor vessel internals 7 PROD00006760 Email from L. Drenth to W. O'Brien re: reactor vessel internals 7 PROD00006761 Email from L. Drenth to W. O'Brien re: reactor vessel internals 7 PROD00006762 PINGP Replacement Steam Generator Report: Structural Evaluation Section 7 PROD00006763 Email from L. Drenth to R. Murray re: reactor vessel internals 7 PROD00006764 5/12/09 LRA Amendment Submittal re: Contention 7 7 PROD00006765 5/12/09 LRA Amendment Submittal re: Contention 7 7 PROD00006766 Letter from P. Glass to P. Mahowald, 4-24-09 5 PROD00006767 Email from A. Demme to C. Koehler et. al. re: reactor internals meeting with NRC 7 PROD00006768 Email from C. Koehler to R. Lott regarding reactor internals 7 PROD00006769 Email from C. Koehler to R. Lott regarding reactor internals 7 PROD00006770 Email from R. Lott to C. Koehler regarding reactor internals 7 PROD00006771 Email from C. Koehler to R. Lott regarding reactor internals 7 PROD00006772 Email from C. Boggess to C. Koehler regarding reactor internals 7 PROD00006773 Email from C. Koehler to J. Wren et al. regarding MRP-228 (Reactor Internals Inspection Standard) 7 PROD00006774 Email from C. Koehler to L. Drenth regarding Reactor Internals Inspections-Westinghouse capabilities 7 proposal PROD00006775 Email from C. Koehler to L. Drenth regarding Ginna Reactor Vessel Internals AMP 7 PROD00006776 Email from L. Drenth to R. Pearson regarding Baffle Former Bolt Inspection 7 PROD00006777 Email from R. Pearson to L. Drenth regarding Baffle Former Bolt Inspection 7 PROD00006778 Email from C. Koehler to A. Butcavage regarding MRP-227 7 3
Document ID Description Contention PROD00006779 Email from C. Koehler to A. Butcavage regarding MRP-227 7 PROD00006780 Email from C. Koehler to P. Lindberg regarding Reactor Vessel Internals AMP 7 PROD00006781 Email from W. O'Brien to C. Koehler regarding Reactor Vessel Internals AMP 7 PROD00006782 Email from A. Butcavage to C. Koehler regarding Ginna Reactor Vessel Internals AMP 7 PROD00006783 Email from C. Koehler to L. Drenth regarding baffle bolts 7 PROD00006784 Email from P. Lindberg to C. Koehler regarding Reactor Vessel Internals AMP 7 PROD00006785 Email from C. Koehler to P. Lindberg regarding Reactor Vessel Internals AMP 7 PROD00006786 Email from C. Koehler to C. Harrington et. al. re MRP-227 Advisory Panel Inquiry 7 PROD00006787 Email from C. Koehler to C. Harrington et. al. re MRP-227 Advisory Panel Inquiry 7 PROD00006788 Email from A. Demma to MRP Assessment group regarding meeting with NRC on MRP-227 7 PROD00006789 EPRI Report MRP-175 (regarding PWR Internals Material Aging Degradation Mechanism Screening and 7 Threshold Values)
PROD00006790 Ginna Reactor Vessel Internals AMP 7 PROD00006791 LRA Section 3.1.2.1.3 Draft 7 PROD00006792 Reactor Internals System Addendum to License Renewal Report 7 PROD00006793 Reactor Vessel Internals Addendum to License Renewal Report draft 7 PROD00006794 Email from P. Lindberg to G. Eckholt regarding Reactor Vessel Internals AMP 7 PROD00006795 Email from W. O'Brien to C. Koehler regarding Reactor Vessel Internals AMP 7 PROD00006796 Email from W. O'Brien to L. Drenth regarding Reactor Vessel Internals AMP 7 PROD00006797 Email from L. Drenth to W. O'Brien regarding baffle bolts 7, 8 PROD00006798 Email from L. Drenth to W. O'Brien regarding baffle bolts 7 PROD00006799 Email from L. Drenth to W. O'Brien regarding baffle bolts 7 PROD00006800 Email from L. Drenth to W. O'Brien regarding baffle bolts 7 PROD00006801 Email from P. Lindberg to L. Drenth regarding Reactor Vessel Internals AMP 7 PROD00006802 Email from P. Lindberg to L. Drenth regarding Reactor Vessel Internals AMP 7 PROD00006803 Email from P. Lindberg to W. O'Brien regarding Reactor Vessel Internals AMP 7 PROD00006804 Email from W. O'Brien to R. Vincent regarding baffle bolts 7 PROD00006805 Email from R. Vincent to M. Wadley regarding Reactor Vessel Internals AMP 7 PROD00006806 Email from R. Vincent to R. Plasse et al. regarding LRA supplement with Reactor Vessel Internals AMP 7 PROD00006807 LRA supplement with Reactor Vessel Internals AMP 7 PROD00006808 LRA supplement with Reactor Vessel Internals AMP 7 PROD00006809 LRA supplement with Reactor Vessel Internals AMP 7 PROD00006810 LRA supplement with Reactor Vessel Internals AMP 7 PROD00006811 Email from D. Lewis to P. Mahowald et al. regarding LRA supplement with Reactor Vessel Internals AMP 7 PROD00006812 LRA supplement with Reactor Vessel Internals AMP 7 4
ATTACHMENT 2 Northern States Power Co.
Prairie Island Nuclear Generating Plant, Units 1 and 2 License Renewal Proceeding Docket Nos. 50-282-LR, 50-306-LR; ASLBP No. 08-871-01-LR Proprietary Log for NSPMs Third Supplemental Disclosures (May 29, 2009)
Document ID Date Entity Claiming Description Contention Protected Status PROP00000447 5/10/2009 PIIC Handwritten notes on PIIC Replacement and Reconstruction Appraisal report 2 PROP00000448 4/22/2009 Westinghouse Westinghouse Presentation: Outage Services and Reactor Internals Aging 7 Management Meeting PROP00000449 4/23/2009 Westinghouse Westinghouse Baffle Bolting Generic Safety Assessment (WCAP-15328) 7 PROP00000450 4/9/2009 AREVA RV Primary Nozzle Weld Inlay PDI Equivalency Testing and Process 8 Qualification PROP00000451 11/2008 EPRI EPRI Draft Materials Reliability Program: Inspection Standard for PWR 7 Internals (MRP-228)
PROP00000452 5/7/2009 Westinghouse Email from L. Drenth to W. O'Brien quoting language from WCAP-15036 7 PROP00000453 5/7/2009 Westinghouse Email from W. O'Brien to L. Drenth quoting language from WCAP-15036 7 PROP00000454 5/7/2009 Westinghouse Email from L. Drenth to W. O'Brien quoting language from WCAP-15036 7 PROP00000455 5/8/2009 Westinghouse Email from W. O'Brien to L. Drenth quoting language from WCAP-15036 7 PROP00000456 5/8/2009 Westinghouse Email from P. Lindberg to W. O'Brien quoting language from WCAP-15036 7 PROP00000457 5/8/2009 Westinghouse Email from L. Drenth to P. Lindberg quoting language from WCAP-15036 7 PROP00000458 5/8/2009 Westinghouse Email from C. Koehler to L. Drenth quoting language from WCAP-15036 7 1