Letter Sequence Request |
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TAC:ME4028, Steam Generator Tube Integrity (Approved, Closed) |
Results
Other: ML103620318, ML110270026, ML110280424, ML110970260, ML11280A045, ML11304A002, ML11304A109, ML12009A007, ML12164A756, ML12164A759, ML12214A607, ML12242A198, ML12264A648, ML13261A145, ML15149A280, ML15149A282, ML15183A020, ML15287A017, ML15307A022, ML15310A102, ML15337A047, ML15343A186, ML15349A918, ML19205A362, ML19205A365, ML19205A389, SBK-L-15073, Responses to Applicant/Licensee Action Items for the Inspection and Evaluation Guidelines for Pressurized Water Reactor Vessel Internals (MRP-227-A)
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MONTHYEARML1036203182010-01-21021 January 2010 Attachment 2, Document SEA-FLU-001-R-004, Rev 0, Non-Proprietary Version of Seabrook Station Reactor Pressure Vessel Fluence Evaluation at 55 EFPY Project stage: Other ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides Project stage: Meeting ML1025202222010-09-20020 September 2010 Summary of Public License Renewal Overview and Environmental Scoping Meeting Related to the Review of the Seabrook Station License Renewal Application (TAC No. ME3959 and ME4028) Project stage: Meeting ML11307A1392010-10-28028 October 2010 2010/10/28 Seabrook Lr - FW: Seabrook Station, Unit No. 1 - Fire Protection Request for Additional Information Regarding License Renewal Application Project stage: RAI SBK-L-10192, Supplement 2 to License Renewal Application2010-11-15015 November 2010 Supplement 2 to License Renewal Application Project stage: Supplement ML1030905582010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application - Aging Management Programs Project stage: RAI ML1030903082010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application Project stage: RAI ML1031301592010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1032605542010-12-14014 December 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application (TAC No. ME4028) Aging-Management Programs Project stage: RAI ML1034202732010-12-14014 December 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application (TAC No. ME4028) - Aging Management Programs Project stage: RAI SBK-L-10204, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs2010-12-17017 December 2010 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs Project stage: Response to RAI SBK-L-10203, Response to Request for Additional Information Set 2 Related to the Review of the License Renewal Application2010-12-22022 December 2010 Response to Request for Additional Information Set 2 Related to the Review of the License Renewal Application Project stage: Response to RAI ML1034205872011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1034205852011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1034205832011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11003, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 52011-01-13013 January 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 5 Project stage: Response to RAI SBK-L-11002, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 42011-01-13013 January 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 4 Project stage: Response to RAI ML1100701282011-01-21021 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11015, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 82011-02-0303 February 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8 Project stage: Response to RAI ML1102700262011-02-0404 February 2011 Scoping and Screening Audit Summary Regarding the Seabrook Station License Renewal Application (TAC Number ME4028) Project stage: Other SBK-L-11027, Response to Request for Additional Information, License Renewal Application, Request for Additional Information - Set 92011-02-18018 February 2011 Response to Request for Additional Information, License Renewal Application, Request for Additional Information - Set 9 Project stage: Response to RAI ML1102602662011-02-24024 February 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1105509202011-03-0707 March 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1103506302011-03-17017 March 2011 Letter Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1102804242011-03-21021 March 2011 Audit Report Regarding the Seabrook Station License Renewal Application Project stage: Other ML1109702602011-03-28028 March 2011 Nwt 817, Chemistry Control in the Seabrook Thermal Barrier Loop, Final Project stage: Other ML1107000182011-03-30030 March 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11062, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Request for Additional Information - Set 112011-04-0505 April 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Request for Additional Information - Set 11 Project stage: Response to RAI SBK-L-11069, Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes2011-04-22022 April 2011 Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes Project stage: Response to RAI ML11132A0072011-05-23023 May 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11123, Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application, Request for Additional Information - Set 142011-06-0202 June 2011 Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application, Request for Additional Information - Set 14 Project stage: Response to RAI ML11139A1462011-06-0909 June 2011 Summary of Telephone Conference Call Held Between the NRC and Nextera Energy Seabrook, LLC, to Clarify Responses to RAI and Draft Requests for Additional Information Pertaining to the Seabrook Station LRA Project stage: Draft RAI ML11143A1652011-06-15015 June 2011 5/18/11, Summary of Telephone Conference Call Held Between NRC and Nextera Energy Seabrook, LLC, Concerning the D-RAI Pertaining to the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11133, Response to Request for Additional Information - Set 14 RAI B.1.4-12011-06-24024 June 2011 Response to Request for Additional Information - Set 14 RAI B.1.4-1 Project stage: Response to RAI ML11178A3652011-07-12012 July 2011 Schedule Revision for the Safety Review of the Seabrook Station License Renewal Application Project stage: Approval ML11284A0202011-10-14014 October 2011 Summary of Telephone Conf Call Held on August 4, 2011 Between the USNRC and Nextera Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Response Project stage: RAI ML11280A0452011-10-17017 October 2011 Summary of Telephone Conference Call Held on May 5, 2011, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning Clarification of Information Pertaining to the Seabrook Station LRA Project stage: Other ML11304A0022011-11-0404 November 2011 Summary of Tele Conf Call Held on 3/18/11, Between the USNRC and NextEra Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook Station License Renewal Application Project stage: Other ML11304A1092011-11-0404 November 2011 Summary of Tele Conf Call Held on 5/31/11, Between the USNRC and Nextera Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook LRA Project stage: Other ML11304A1512011-11-0404 November 2011 Summary of Tele Conf Call Held on 4/8/11 Between USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses Project stage: RAI ML11304A1662011-11-0404 November 2011 Summary of Tele Conf Call Held on 3/3/11, Between the USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses Project stage: RAI ML12009A0072012-01-25025 January 2012 Project Manager Change for the License Renewal of Seabrook Station Project stage: Other ML12054A7662012-03-26026 March 2012 022312, Telecon Summary Between NRC and NextEra Seabrook, Discussing RAIs Response Project stage: RAI ML12160A3742012-06-0808 June 2012 Safety Evaluation Report with Open Items Related to the License Renewal of Seabrook Station Project stage: Approval ML12053A1922012-06-0808 June 2012 Safety Evaluation Report with Open Items Related to the License Renewal of Seabrook Station (TAC No. ME4028). Seabrook SER with Open Items Transmittal Letter Project stage: Approval ML12165A7422012-06-21021 June 2012 Summary of Telephone Conference Call Held on April 10, 2012, Between NRC and Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA Project stage: RAI ML12165A5952012-06-22022 June 2012 Summary of Telephone Conference Call Held on May 16, 2012, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA Project stage: RAI ML12164A9012012-06-22022 June 2012 Summary of Telephone Conference Call Held on 5/24/12, Between the NRC and NextEra Energy Seabrook, LLC Concerning the Drai Pertaining to the Seabrook Station LRA Project stage: RAI ML12164A7562012-06-22022 June 2012 Summary of Telephone Conference Call Between NRC and NextEra Seabrook Project stage: Other ML12164A7592012-07-0303 July 2012 041912, Telecon Summary Between NRC and NextEra Seabrook Project stage: Other 2011-02-04
[Table View] |
PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and AffidavitML15149A283 |
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Seabrook |
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05/26/2015 |
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From: |
PWR Owners Group, Westinghouse |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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Shared Package |
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ML15149A278 |
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References |
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CAW-15-4190, MRP-227-A, SBK-L-15073, TAC ME4028 PWROG-15042-P, Rev 0 |
Download: ML15149A283 (13) |
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Category:Legal-Affidavit
MONTHYEARL-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2023-034, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2023-02-24024 February 2023 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) ML18151A1442018-05-31031 May 2018 Hearing File Update ML15149A2832015-05-26026 May 2015 PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and Affidavit ML15072A0372015-03-0909 March 2015 Enclosures 1 and 2 - Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years and Affidavit SBK-L-12176, Response to Request for Additional Information Regarding Relief Request for Service Water Piping2012-09-0707 September 2012 Response to Request for Additional Information Regarding Relief Request for Service Water Piping SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2012-03-15015 March 2012 Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System2011-09-16016 September 2011 Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System ML11223A3772011-08-0808 August 2011 (Beyond Nuclear, Seacoast Antipollution League, Sierra Club of Nh) Declaration of Dr. Arjun Makhijani Safety and Environmental Significance of NRC Task Force Report Regarding Lessons Learned from Fukushima Daiichi Nuclear Power Station Acci ML11223A4462011-08-0808 August 2011 (Friends of the Coast, New England Coalition) Declaration of Dr. Arjun Makhijani Regarding Safety and Environmental Significance of NRC Task Force Report Regarding Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident ML1111000032011-04-20020 April 2011 Declaration and Cv of Dr. Arjun Makhijani in Support of Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned from Fukushima Daiichi Power Station Acc ML1111000052011-04-19019 April 2011 Letter to Commissioners Transmitting Declaration and Cv of Dr. Arjun Makhijani in Support of Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions . . ML1110504752011-04-15015 April 2011 Certificate of Service for Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident ML1106805352011-03-0909 March 2011 Certificate of Service for Commonwealth of Massachusetts' Request to Participate as an Interested State, and Notice of Appearance of Matthew Brock on Behalf of the Commonwealth of Massachusetts SBK-L-08039, License Amendment Request 08-01, Application for Change to the Technical Specification Surveillance Requirements for Nuclear Instrumentation2008-03-0707 March 2008 License Amendment Request 08-01, Application for Change to the Technical Specification Surveillance Requirements for Nuclear Instrumentation SBK-L-08005, License Amendment Request 07-04 Application for Amendment to Delete Post-Maintenance Testing Surveillance Requirement for Containment Isolation Valves2008-02-0808 February 2008 License Amendment Request 07-04 Application for Amendment to Delete Post-Maintenance Testing Surveillance Requirement for Containment Isolation Valves SBK-L-07112, License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.2007-07-17017 July 2007 License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process. SBK-L-07042, License Amendment Request 07-01 Setpoint Change for Reactor Trip System Interlock P-92007-03-29029 March 2007 License Amendment Request 07-01 Setpoint Change for Reactor Trip System Interlock P-9 SBK-L-06166, Proprietary Information to Support Response to Request for Additional Information Re License Amendment Request 05-08, Limited Inspection of Steam Generator Tube Portion within the Tubesheet.2006-08-0808 August 2006 Proprietary Information to Support Response to Request for Additional Information Re License Amendment Request 05-08, Limited Inspection of Steam Generator Tube Portion within the Tubesheet. ML0534903472005-12-12012 December 2005 Caldon Inc. Proprietary Information Package, INFO-18 SBK-L-05186, License Amendment Request 05-08, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet2005-09-29029 September 2005 License Amendment Request 05-08, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet SBK-L-04052, Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate2004-09-13013 September 2004 Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate 2024-02-28
[Table view] Category:Topical Report
MONTHYEARL-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2022-082, NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 282022-05-23023 May 2022 NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 28 L-2021-234, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update2021-12-15015 December 2021 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update L-2021-115, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 26 Annual Submittal and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 102021-05-24024 May 2021 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 26 Annual Submittal and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 10 L-2016-129, NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal2016-06-22022 June 2016 NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal ML15149A2822015-05-31031 May 2015 PWROG-15023-NP, Revision 1, Seabrook Station, Unit 1, Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability. ML15149A2802015-05-31031 May 2015 PWROG-14083-NP, Revision 1, NextEra Energy, Seabrook Unit 1, Summary Report for Applicant/Licensee Action Items 1, 2, and 7. ML15149A2832015-05-26026 May 2015 PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and Affidavit L-2013-208, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 132013-07-0101 July 2013 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 13 SBK-L-12256, WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation2011-10-31031 October 2011 WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation L-2010-138, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 72010-06-28028 June 2010 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 7 L-2009-134, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 42009-06-29029 June 2009 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 4 ML0913404382009-04-30030 April 2009 Westinghouse Electric Co., WCAP-17071-NP, Revision 0, H: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F) L-2008-150, Duane Arnold, and Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 22008-06-27027 June 2008 Duane Arnold, and Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 2 L-2006-246, Response to RAI Follow-Up Questions Regarding Fpl'S Common Quality Assurance Topical Report Request2006-11-15015 November 2006 Response to RAI Follow-Up Questions Regarding Fpl'S Common Quality Assurance Topical Report Request ML0615203362006-04-30030 April 2006 WCAP-16550-NP, Rev. 0, Stuctural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Opearation: Seabrook Station. L-2006-067, Request for Approval of FPL Quality Assurance Topical Report2006-03-31031 March 2006 Request for Approval of FPL Quality Assurance Topical Report ML0610300882006-03-31031 March 2006 WCAP-16526-NP, Rev. 0, Analysis of Capsule V from FPL Energy - Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. 2024-07-10
[Table view] |
Text
Enclosure 8 to SBK-L-15073Appendix A of Westinghouse Report (PWROG-15042-P, Revision 0)NextEra Energy, Seabrook Unit 1Summary Report for the Cold Work Assessment(Non-Proprietary)
WESTINGHOUSE NON-PROPRIETARY CLASS 3A-1APPENDIX ACOLD WORK ASSESSMENTWestinghouse Electric Company LLC1000 Westinghouse DriveCranberry Township, PA 16066, USA© 2015 Westinghouse Electric Company LLCAll Rights ReservedPWROG-1 5042-PMay 2015Revision 0-WESTINGHOUSE NON-PROPRIETARY CLASS 3A-2A.1 REACTOR INTERNALS COLD WORK ASSESSMENTAs a result of the review of the Applicant/Licensee Action Items (AILAI) 1, 2 and 7 responsessubmitted by the industry, the U.S. Nuclear Regulatory Commission (NRC) has requested thatadditional information on cold work in Reactor Vessel Internals (RVI) be provided to supportA/LAI 1 plant-specific demonstration of MRP-227-A [4] applicability. The issue of cold work instainless steel relates to the criteria in MRP-1 75 [3] for stress corrosion cracking (SCC). Thespecific NRC question is focused on whether the materials of original construction for thedomestic fleet RVI components contain "severe cold work" (greater than 20 percent). Aguideline template (MRP 2013-025 [1]) was completed by Westinghouse and the Electric PowerResearch Institute (EPRI) to define a process for evaluating cold work in the RVI componentmaterials. For the purposes of this evaluation, it is noted that the assessments are based onthe screening and binning process based exclusively on material specifications. Thisassessment did not specifically investigate any other avenues, such as field installation.The MRP-227-A [4] Applicability Template Guideline, as summarized in MRP 2013-025 [1], isfollowed to support this assessment and response to the NRC.A.2 SEABROOK UNIT 1 -REACTOR INTERNALS COLD WORK ASSESSMENTWestinghouse has evaluated the Seabrook Unit I reactor internals components according toindustry guideline MRP 2013-025 [1] and the MRP-191 [2] industry generic component listingsand screening criteria (including consideration of cold work as defined in MRP-175 [3], notingthe requirements of subsection 3.2.3). In addition to consideration of the material fabrication,forming and finishing process, a general screening definition of "severe cold work" as a resultingreduction in wall thickness of 20 percent was applied as an evaluation limit. It was confirmedthat all of Seabrook Unit 1 components, as applicable for the design, are included directly in theMRP-191 component lists, or have been evaluated accordingly.The evaluation included a review of all plant modifications affecting reactor internals and theplant operating history. The components were procured according to the American Society forTesting and Materials (ASTM) International or American Society of Mechanical Engineers(ASME) material specifications that were called out on the original plant construction drawings.Material and component procurement was through applicable quality-controlled protocols.Therefore, material identification based on the material call-outs and notes in the componentdrawings was an efficient and reasonable approach to identify the materials of construction forthe RVI components in Seabrook Unit 1.Based on the specifications called out on the Seabrook Unit 1 component drawings, theRVI components are binned into the five material categories identified in MRP 2013-025 [1].Cold work categories based on MRP 2013-025 include:* Cast austenitic stainless steel (CASS) (Category 1)* Hot-formed austenitic stainless steel (Category 2)PWROG-15042-P May 2015Revision 0 WESTINGHOUSE NON-PROPRIETARY CLASS 3A-3* Annealed austenitic stainless steel (Category 3)* Fasteners austenitic stainless steel (Category 4)Cold-formed austenitic stainless steel without subsequent solution annealing(Category 5)The potential for cold work is directly controlled by the materials specifications. Essentially all ofthe components that are binned (based on their specified materials) as Categories 1, 2 and 3are non-cold worked; therefore, they have less than 20 percent cold work according to theNRC criterion. Similarly, any component binned under Category 5 has the potential to containgreater than 20 percent cold work. Category 4 materials are fasteners that may have beenintentionally strain-hardened.During the fabrication of fasteners, the strain hardening was typically intentionally restricted toless than 20 percent. These restrictions, if present, were noted on engineering drawings. Arestriction or limitation on the material yield stress (e.g., a maximum of 90 ksi) would indicatethat the material cold work would be limited to be less than 20 percent. In the absence of arestriction on the maximum yield stress of strain-hardened material, a conservative approachhas been taken to assume the potential for greater than 20 percent cold work.Where multiple options existed for a component or assembly, the bounding condition of coldwork was taken as the option that had the greater potential to include greater than 20 percentcold work. This option was then employed in the assessment of the component, and wasselected for the purposes of the assessment. In some instances, sequential fabrication wouldappear to mitigate any potential for cold work; however, since the historical record was notdetailed the potential is noted, but a conservative approach was selected for this assessment.The evaluation, performed consistently with the industry guideline [1], concluded that the reactorinternals Category 1, 2 and 3 (non-bolting) components at Seabrook Unit 1 contain no cold workgreater than 20 percent as a result of material specification and controlled fabricationconstruction. No Seabrook Unit 1 components were binned as Category 5. Therefore, the onlymaterials with the potential for greater than 20 percent cold work for Seabrook werestrain-hardened fasteners binned as Category 4 components. For some Category 4components, the material drawing notes and Westinghouse purchasing specifications that wereemployed in addition to ASME and ASTM specifications for parts purchase were found to limitthe strength of the employed materials such that the use of greater than 20 percent cold workmaterial was precluded. In cases where additional specifications were not clearly identified, aconservative posture was selected to consider the component as being cold worked for thepurposes of this assessment. Category 4 components were already assumed to have thepotential for cold work in the MRP-1 91 generic assessments.The detailed evaluation for Seabrook Unit 1 cold work assessments concluded that theplant-specific material fabrication and design was consistent with the MRP-191 basis, and thatthe MRP-227-A sampling inspection aging management requirements as related to cold workare directly applicable to Seabrook Unit 1.PWROG-1 5042-P May 2015Revision 0 WESTINGHOUSE NON-PROPRIETARY CLASS 3A-4A.3 REFERENCES1. EPRI Letter, MRP 2013-025, "MRP-227-A Applicability Template Guideline,"October 14, 2013.2. Materials Reliability Program: Screening, Categorization, and Ranking of ReactorInternals Components for Westinghouse and Combustion Engineering PWR Design(MRP-19 1). EPRI, Palo Alto, CA: 2006. 1013234.3. Materials Reliability Program: PWR Internals Material Aging Degradation MechanismScreening and Threshold Values (MRP-175). EPRI, Palo Alto, CA: 2005. 1012081.4. Materials Reliability Program: Pressurized Water Reactor Internals Inspection andEvaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.PWROG-1 5042-PMay 2015Revision 0 to SBK-L-15073Application for Withholding Proprietary InformationFrom Public Disclosure and Affidavit
(*) WestinghouseU.S. Nuclear Regulatory CommissionDocument Control Desk11555 Rockville PikeRockville, MD 20852Westinghouse Electric CompanyEngineering, Equipment and Major Projects1000 Westinghouse Drive, Building 3Cranberry Township, Pennsylvania 16066USADirect tel:Direct fax:e-mail:(412) 374-4643(724) 940-8560greshaja@westinghouse.comCAW-15-4190May 20,2015APPLICATION FOR WITHHOLDING PROPRIETARYINFORMATION FROM PUBLIC DISCLOSURE
Subject:
PWROG-15023-P, Revision 1, "Seabrook Station Unit I Summary Report for the FuelDesign/Fuel Management Assessments to Demonstrate MRP-227-A Applicability"(Proprietary)The proprietary information for which withholding is being requested in the above-referenced report isfurther identified in Affidavit CAW-15-4190 signed by the owner of the proprietary information,Westinghouse Electric Company LLC. The Affidavit, which accompanies this letter, sets forth the basison which the information may be withheld from public disclosure by the Commission and addresses withspecificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission'sregulations.Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Pressurized WaterReactor Owners Group (PWROG).Correspondence with respect to the proprietary aspects of the Application for Withholding or theWestinghouse Affidavit should reference CAW- 15-4190 and should be addressed to James A. Gresham,Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive,Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.Very truly yours,ames A. Gresham, ManagerRegulatory Compliance CAW-15-4190May 20,2015AFFIDAVITCOMMONWEALTH OF PENNSYLVANIA:SSCOUNTY OF BUTLER:I, James A. Gresham, am authorized to execute this Affidavit on behalf of Westinghouse ElectricCompany LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true andcorrect to the best of my knowledge, information, and belief./James A. Gresham, ManagerRegulatory Compliance 2CAW-15-4190(1) I am Manager, Regulatory Compliance, Westinghouse Electric Company LLC (Westinghouse),and as such, I have been specifically delegated the function of reviewing the proprietaryinformation sought to be withheld from public disclosure in connection with nuclear power plantlicensing and rule making proceedings, and am authorized to apply for its withholding on behalfof Westinghouse.(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of theCommission's regulations and in conjunction with the Westinghouse Application for WithholdingProprietary Information from Public Disclosure accompanying this Affidavit.(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designatinginformation as a trade secret, privileged or as confidential commercial or financial information.(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations,the following is furnished for consideration by the Commission in determining whether theinformation sought to be withheld from public disclosure should be withheld.(i) The information sought to be withheld from public disclosure is owned and has been heldin confidence by Westinghouse.(ii) The information is of a type customarily held in confidence by Westinghouse and notcustomarily disclosed to the public. Westinghouse has a rational basis for determiningthe types of information customarily held in confidence by it and, in that connection,utilizes a system to determine when and whether to hold certain types of information inconfidence. The application of that system and the substance of that system constituteWestinghouse policy and provide the rational basis required.Under that system, information is held in confidence if it falls in one or more of severaltypes, the release of which might result in the loss of an existing or potential competitiveadvantage, as follows:(a) The information reveals the distinguishing aspects of a process (or component,structure, tool, method, etc.) where prevention of its use by any of 3CAW-15-4190Westinghouse's competitors without license from Westinghouse constitutes acompetitive economic advantage over other companies.(b) It consists of supporting data, including test data, relative to a process (orcomponent, structure, tool, method, etc.), the application of which data secures acompetitive economic advantage, e.g., by optimization or improvedmarketability.(c) Its use by a competitor would reduce his expenditure of resources or improve hiscompetitive position in the design, manufacture, shipment, installation, assuranceof quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, orcommercial strategies of Westinghouse, its customers or suppliers.(e) It reveals aspects of past, present, or future Westinghouse or customer fundeddevelopment plans and programs of potential commercial value to Westinghouse.(f) It contains patentable ideas, for which patent protection may be desirable.(iii) There are sound policy reasons behind the Westinghouse system which include thefollowing:(a) The use of such information by Westinghouse gives Westinghouse a competitiveadvantage over its competitors. It is, therefore, withheld from disclosure toprotect the Westinghouse competitive position.(b) It is information that is marketable in many ways. The extent to which suchinformation is available to competitors diminishes the Westinghouse ability tosell products and services involving the use of the information.(c) Use by our competitor would put Westinghouse at a competitive disadvantage byreducing his expenditure of resources at our expense.
4CAW-15-4190(d) Each component of proprietary information pertinent to a particular competitiveadvantage is potentially as valuable as the total competitive advantage. Ifcompetitors acquire components of proprietary information, any one componentmay be the key to the entire puzzle, thereby depriving Westinghouse of acompetitive advantage.(e) Unrestricted disclosure would jeopardize the position of prominence ofWestinghouse in the world market, and thereby give a market advantage to thecompetition of those countries.(f) The Westinghouse capacity to invest corporate assets in research anddevelopment depends upon the success in obtaining and maintaining acompetitive advantage.(iv) The information is being transmitted to the Commission in confidence and, under theprovisions of 10 CFR Section 2.390, it is to be received in confidence by theCommission.(v) The information sought to be protected is not available in public sources or availableinformation has not been previously employed in the same original manner or method tothe best of our knowledge and belief.(vi) The proprietary information sought to be withheld in this submittal is that which isappropriately marked in PWROG-15023-P, Revision 1, "Seabrook Station Unit 1 SummaryReport for the Fuel Design/Fuel Management Assessments to Demonstrate MRP-227-AApplicability" (Proprietary), for submittal to the Commission, being transmitted byPWROG letter OG-15-198 and Application for Withholding Proprietary Information fromPublic Disclosure, to the Document Control Desk. The proprietary information assubmitted by Westinghouse is that associated with the NRC Letter, "Request for AdditionalInformation Related to the Review of the Seabrook Station License Renewal Application -Set 21 (TAC NO. ME4028)," ML14101A324 April 25, 2014 and may be used only for thatpurpose.
5CAW-15-4190(a) This information is part of that which will enable Westinghouse to:(i) Support reactor vessel internals aging management.(b) Further this information has substantial commercial value as follows:(i) Westinghouse plans to sell the use of similar information to its customersfor the purpose of supporting reactor internals aging management(ii) Westinghouse can sell support and defense of industry guidelines andacceptance criteria for plant-specific applications.(iii) The information requested to be withheld reveals the distinguishingaspects of a methodology which was developed by Westinghouse.Public disclosure of this proprietary information is likely to cause substantial harm to thecompetitive position of Westinghouse because it would enhance the ability ofcompetitors to provide similar technical evaluation justifications and licensing defenseservices for commercial power reactors without commensurate expenses. Also, publicdisclosure of the information would enable others to use the information to meet NRCrequirements for licensing documentation without purchasing the right to use theinformation.The development of the technology described in part by the information is the result ofapplying the results of many years of experience in an intensive Westinghouse effort andthe expenditure of a considerable sum of money.In order for competitors of Westinghouse to duplicate this information, similar technicalprograms would have to be performed and a significant manpower effort, having therequisite talent and experience, would have to be expended.Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICETransmitted herewith is the proprietary and non-proprietary version of a document furnished to the NRCassociated with the NRC letter, "Request for Additional Information Related to the Review of theSeabrook Station License Renewal Application -Set 21 (TAC NO. ME4028)," ML14101A324 April 25,2014 and may be used only for that purpose.In order toconform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning theprotection of proprietary information so submitted to the NRC, the information which is proprietary in theproprietary versions is contained within brackets, and where the proprietary information has been deletedin the non-proprietary versions, only the brackets remain (the information that was contained within thebrackets in the proprietary versions having been deleted). The justification for claiming the informationso designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item of information beingidentified as proprietary or in the margin opposite such information. These lower case letters refer to thetypes of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a)through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).COPYRIGHT NOTICEThe reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted tomake the number of copies of the information contained in these reports which are necessary for itsinternal use in connection with generic and plant-specific reviews and approvals as well as the issuance,denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license,permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on publicdisclosure to the extent such information has been identified as proprietary by Westinghouse, copyrightprotection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC ispermitted to make the number of copies beyond those necessary for its internal use which are necessary inorder to have one copy available for public viewing in the appropriate docket files in the public documentroom in Washington, DC and in local public document rooms as may be. required by NRC regulations ifthe number of copies submitted is insufficient for this purpose. Copies made by the NRC must includethe copyright notice in all instances and the proprietary notice if the original was identified as proprietary.