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 ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
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-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 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 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 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 2023-02-24
[Table view] Category:Topical Report
MONTHYEARL-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. 2023-05-22
[Table view] |
Text
Enclosure 8 to SBK-L-15073 Appendix A of Westinghouse Report (PWROG-15042-P, Revision 0)
NextEra Energy, Seabrook Unit 1 Summary Report for the Cold Work Assessment (Non-Proprietary)
WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-1 APPENDIX A COLD WORK ASSESSMENT Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA
© 2015 Westinghouse Electric Company LLC All Rights Reserved PWROG-1 5042-P May 2015 Revision 0-
WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-2 A.1 REACTOR INTERNALS COLD WORK ASSESSMENT As a result of the review of the Applicant/Licensee Action Items (AILAI) 1, 2 and 7 responses submitted by the industry, the U.S. Nuclear Regulatory Commission (NRC) has requested that additional information on cold work in Reactor Vessel Internals (RVI) be provided to support A/LAI 1 plant-specific demonstration of MRP-227-A [4] applicability. The issue of cold work in stainless steel relates to the criteria in MRP-1 75 [3] for stress corrosion cracking (SCC). The specific NRC question is focused on whether the materials of original construction for the domestic fleet RVI components contain "severe cold work" (greater than 20 percent). A guideline template (MRP 2013-025 [1]) was completed by Westinghouse and the Electric Power Research Institute (EPRI) to define a process for evaluating cold work in the RVI component materials. For the purposes of this evaluation, it is noted that the assessments are based on the screening and binning process based exclusively on material specifications. This assessment 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], is followed to support this assessment and response to the NRC.
A.2 SEABROOK UNIT 1 - REACTOR INTERNALS COLD WORK ASSESSMENT Westinghouse has evaluated the Seabrook Unit I reactor internals components according to industry guideline MRP 2013-025 [1] and the MRP-191 [2] industry generic component listings and screening criteria (including consideration of cold work as defined in MRP-175 [3], noting the 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 resulting reduction in wall thickness of 20 percent was applied as an evaluation limit. It was confirmed that all of Seabrook Unit 1 components, as applicable for the design, are included directly in the MRP-191 component lists, or have been evaluated accordingly.
The evaluation included a review of all plant modifications affecting reactor internals and the plant operating history. The components were procured according to the American Society for Testing 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 component drawings was an efficient and reasonable approach to identify the materials of construction for the RVI components in Seabrook Unit 1.
Based on the specifications called out on the Seabrook Unit 1 component drawings, the RVI 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 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-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 of the components that are binned (based on their specified materials) as Categories 1, 2 and 3 are non-cold worked; therefore, they have less than 20 percent cold work according to the NRC criterion. Similarly, any component binned under Category 5 has the potential to contain greater than 20 percent cold work. Category 4 materials are fasteners that may have been intentionally strain-hardened.
During the fabrication of fasteners, the strain hardening was typically intentionally restricted to less than 20 percent. These restrictions, if present, were noted on engineering drawings. A restriction or limitation on the material yield stress (e.g., a maximum of 90 ksi) would indicate that the material cold work would be limited to be less than 20 percent. In the absence of a restriction on the maximum yield stress of strain-hardened material, a conservative approach has 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 cold work was taken as the option that had the greater potential to include greater than 20 percent cold work. This option was then employed in the assessment of the component, and was selected for the purposes of the assessment. In some instances, sequential fabrication would appear to mitigate any potential for cold work; however, since the historical record was not detailed 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 reactor internals Category 1, 2 and 3 (non-bolting) components at Seabrook Unit 1 contain no cold work greater than 20 percent as a result of material specification and controlled fabrication construction. No Seabrook Unit 1 components were binned as Category 5. Therefore, the only materials with the potential for greater than 20 percent cold work for Seabrook were strain-hardened fasteners binned as Category 4 components. For some Category 4 components, the material drawing notes and Westinghouse purchasing specifications that were employed in addition to ASME and ASTM specifications for parts purchase were found to limit the strength of the employed materials such that the use of greater than 20 percent cold work material was precluded. In cases where additional specifications were not clearly identified, a conservative posture was selected to consider the component as being cold worked for the purposes of this assessment. Category 4 components were already assumed to have the potential for cold work in the MRP-1 91 generic assessments.
The detailed evaluation for Seabrook Unit 1 cold work assessments concluded that the plant-specific material fabrication and design was consistent with the MRP-191 basis, and that the MRP-227-A sampling inspection aging management requirements as related to cold work are directly applicable to Seabrook Unit 1.
PWROG-1 5042-P May 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-4 A.3 REFERENCES
- 1. EPRI Letter, MRP 2013-025, "MRP-227-A Applicability Template Guideline,"
October 14, 2013.
- 2. MaterialsReliability Program:Screening, Categorization,and Ranking of Reactor Internals Components for Westinghouse and Combustion EngineeringPWR Design (MRP-19 1). EPRI, Palo Alto, CA: 2006. 1013234.
- 3. MaterialsReliability Program:PWR Internals MaterialAging DegradationMechanism Screening and Threshold Values (MRP-175). EPRI, Palo Alto, CA: 2005. 1012081.
- 4. MaterialsReliability Program:PressurizedWater Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.
PWROG-1 5042-P May 2015 Revision 0
Enclosure 9 to SBK-L-15073 Application for Withholding Proprietary Information From Public Disclosure and Affidavit
Westinghouse Electric Company
(*) Westinghouse Engineering, Equipment and Major Projects 1000 Westinghouse Drive, Building 3 Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Direct fax: (724) 940-8560 11555 Rockville Pike e-mail: greshaja@westinghouse.com Rockville, MD 20852 CAW-15-4190 May 20,2015 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
PWROG-15023-P, Revision 1, "Seabrook Station Unit I Summary Report for the Fuel Design/Fuel Management Assessments to Demonstrate MRP-227-A Applicability" (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced report is further 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 basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Pressurized Water Reactor Owners Group (PWROG).
Correspondence with respect to the proprietary aspects of the Application for Withholding or the Westinghouse 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, Manager Regulatory Compliance
CAW-15-4190 May 20,2015 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
SS COUNTY OF BUTLER:
I, James A. Gresham, am authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.
/James A. Gresham, Manager Regulatory Compliance
2 CAW-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 proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information 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 the information 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 held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the 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 in confidence. The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, 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
3 CAW-15-4190 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development 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 the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 CAW-15-4190 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iv) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.
(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(vi) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in PWROG-15023-P, Revision 1, "Seabrook Station Unit 1 Summary Report for the Fuel Design/Fuel Management Assessments to Demonstrate MRP-227-A Applicability" (Proprietary), for submittal to the Commission, being transmitted by PWROG letter OG-15-198 and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with the NRC Letter, "Request for Additional Information 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 that purpose.
5 CAW-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 customers for the purpose of supporting reactor internals aging management (ii) Westinghouse can sell support and defense of industry guidelines and acceptance criteria for plant-specific applications.
(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith is the proprietary and non-proprietary version of a document furnished to the NRC associated with the NRC letter, "Request for Additional Information 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 that purpose.
In order toconform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so 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 being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types 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 NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal 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 public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be. required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.