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| {{#Wiki_filter:September 16, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)-NFPA 805 | | {{#Wiki_filter:NEXTera*** |
| | ENERGY~ |
| | POINT BEACH September 16, 2013 NRC 2013-0092 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805 |
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| ==References:== | | ==References:== |
| | | : 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)- NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition ." (ML13182A350 & 353) |
| NEXT era*** POINT BEACH NRC 2013-0092 10 CFR 50.90 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)-NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition." (ML13182A350
| | : 2. NRC to NextEra Energy Point Beach, LLC electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2- Acceptance Review Regarding the NFPA-805 License Amendment Request- Opportunity to Supplement (TAC Nos. MF2372 and NF2373)." (ML13256A197) |
| & 353) 2. NRC to NextEra Energy Point Beach, LLC electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2-Acceptance Review Regarding the NFPA-805 License Amendment Request-Opportunity to Supplement (TAC Nos. MF2372 and NF2373)." (ML13256A197) Pursuant to 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra) hereby submits a supplement to License Amendment Request (LAR) 271 (Reference | | Pursuant to 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra) hereby submits a supplement to License Amendment Request (LAR) 271 (Reference 1) for Point Beach Nuclear Plant (PBNP) Units 1 and 2. This supplement (see Enclosure) provides the NextEra response to the NRC LAR 271 acceptance review question transmitted on September 9, 2013 (Reference 2). NextEra requests approval of this supplement on the same schedule as LAR 271. The supplement will be implemented on the same schedule as that of LAR 271. |
| : 1) for Point Beach Nuclear Plant (PBNP) Units 1 and 2. This supplement (see Enclosure) provides the NextEra response to the NRC LAR 271 acceptance review question transmitted on September 9, 2013 (Reference 2). NextEra requests approval of this supplement on the same schedule as LAR 271. The supplement will be implemented on the same schedule as that of LAR 271. This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.
| | This letter contains no new regulatory commitments and no revisions to existing regulatory commitments. |
| In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official. | | In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official. |
| If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845. | | If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on September 16, 2013. . Very truly yours, NextEra Energy Point Beach, LLC Enclosure cc: Administrator, Region Ill, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC PSCW Introduction ENCLOSUR E LICENSE AMENDMENT REQUEST 271, SUPPLEMENT 1 TRANSITION TO 10 CFR 50.48(c)-NFPA 805 NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 271 (Reference | | |
| : 1) to NRC dated June 26, 2013, requesting transition of the Point Beach Nuclear Plant (PBNP) fire protection program to NFPA 805, "Performance
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on September 16, 2013. . |
| -Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition. The NRC staff transmitted a LAR 271 acceptance review question to NextEra via electronic mail dated September 9, 2013 (Reference 2). The following information is provided by NextEra in response to NRCs staff's question. NextEra Response to NRC LAR 271 Acceptance Question Question 1 Table S-2 of the June 26, 2013, application identifies modification MOD-3 to be an upgrade of the reactor coolant pump (RCP) seals, which includes installation of Westinghouse SHIELDŽ low leakage RCP seals. Given recent concerns about the performance of the new Westinghouse RCP seals, the risk reduction credit taken in your application for this modification may be optimistic. | | Very truly yours, NextEra Energy Point Beach, LLC Enclosure cc: Administrator, Region Ill, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC PSCW |
| During a September 4, 2013, phone call, NextEra stated that based on a sensitivity analysis recently performed, the Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment | | |
| [PRA] in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," risk acceptance guidelines would be exceeded if the new Westinghouse SHIELDŽ RCP seals are not credited in the PRA. Please discuss which RG 1.174 acceptance guidelines are exceeded (CDF, LERF, !J.CDF, !J.LERF) for each unit at Point Beach, and the magnitude of the exceedance. | | ENCLOSURE LICENSE AMENDMENT REQUEST 271, SUPPLEMENT 1 TRANSITION TO 10 CFR 50.48(c) - NFPA 805 Introduction NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 271 (Reference 1) to NRC dated June 26, 2013, requesting transition of the Point Beach Nuclear Plant (PBNP) fire protection program to NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition. The NRC staff transmitted a LAR 271 acceptance review question to NextEra via electronic mail dated September 9, 2013 (Reference 2). The following information is provided by NextEra in response to NRCs staff's question . |
| NextEra Response NextEra committed in PBNP LAR 271 (Enclosure, AttachmentS, Table S-2, Item MOD-3) to install the Westinghouse Electric Company (WEC) SHIELDŽ Passive Thermal Shutdown Seal (SDS) into the existing WEC reactor coolant pump (RCP) seals of each Unit to provide a more controllable leak rate, if cooling flow is lost to the RCP seals due to a fire. With the recent failure of the Beaver Valley SDS to actuate when tested following one reactor fuel cycle of operation, NextEra is tracking the Westinghouse redesign and qualification testing of their SDS. Next E ra plans to install the redesigned SDS into the RCP seals in both units with the first installation tentatively planned for one RCP on Unit 2 during the U2R33 spring 2014 refueling outage. Alternatives to the SDS are also being evaluated as contingency plans in the event that the SDS redesign is not acceptable. | | NextEra Response to NRC LAR 271 Acceptance Question Question 1 Table S-2 of the June 26, 2013, application identifies modification MOD-3 to be an upgrade of the reactor coolant pump (RCP) seals, which includes installation of Westinghouse SHIELD' low leakage RCP seals. Given recent concerns about the performance of the new Westinghouse RCP seals, the risk reduction credit taken in your application for this modification may be optimistic. |
| Regarding exceeding the RG 1.17 4 acceptance guidelines for each unit at Point Beach without credit for the SDS, two sensitivity analyses were performed on the fire PRA model utilized for the results reported in LAR 271. The sensitivity results (see Tables 1 and 2 below) show the fire Page 1 of 3 PRA core damage frequency (CD F) and la r ge early release frequency (L E RF) for the Post NFPA 805 Transition and the Appendix R Compliant cases with the associated | | During a September 4, 2013, phone call, NextEra stated that based on a sensitivity analysis recently performed, the Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment [PRA] in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," risk acceptance guidelines would be exceeded if the new Westinghouse SHIELD' RCP seals are not credited in the PRA. |
| .!lCDF and ilL E RF for each PBNP Unit. Comparing the Table 1 values to the Regulatory Guide (RG) 1.17 4 acceptance guidelines in Figure 4 (Acceptance guidelines for core damage frequency) and Figure 5 (Acceptance guidelines for large early release frequency) lead to the following results: | | Please discuss which RG 1.174 acceptance guidelines are exceeded (CDF, LERF, !J.CDF, |
| | !J.LERF) for each unit at Point Beach, and the magnitude of the exceedance. |
| | NextEra Response NextEra committed in PBNP LAR 271 (Enclosure, AttachmentS, Table S-2, Item MOD-3) to install the Westinghouse Electric Company (WEC) SHIELD' Passive Thermal Shutdown Seal (SDS) into the existing WEC reactor coolant pump (RCP) seals of each Unit to provide a more controllable leak rate, if cooling flow is lost to the RCP seals due to a fire. With the recent failure of the Beaver Valley SDS to actuate when tested following one reactor fuel cycle of operation, NextEra is tracking the Westinghouse redesign and qualification testing of their SDS. NextEra plans to install the redesigned SDS into the RCP seals in both units with the first installation tentatively planned for one RCP on Unit 2 during the U2R33 spring 2014 refueling outage. |
| | Alternatives to the SDS are also being evaluated as contingency plans in the event that the SDS redesign is not acceptable. |
| | Regarding exceeding the RG 1.174 acceptance guidelines for each unit at Point Beach without credit for the SDS, two sensitivity analyses were performed on the fire PRA model utilized for the results reported in LAR 271. The sensitivity results (see Tables 1 and 2 below) show the fire Page 1 of 3 |
| | |
| | PRA core damage frequency (CD F) and large early release frequency (L ERF) for the Post NFPA 805 Transition and the Appendix R Compliant cases with the associated .!lCDF and ilL ERF for each PBNP Unit. Comparing the Table 1 values to the Regulatory Guide (RG) 1.174 acceptance guidelines in Figure 4 (Acceptance guidelines for core damage frequency) and Figure 5 (Acceptance guidelines for large early release frequency) lead to the following results: |
| * Unit 1 Post-Transition CDF of 7.96E-04 is> 1.0E-4 and .!lCDF of 6.14E-4 is> 1.0E-5 | | * Unit 1 Post-Transition CDF of 7.96E-04 is> 1.0E-4 and .!lCDF of 6.14E-4 is> 1.0E-5 |
| * Unit 2 Post-Transition CD F of 4.80E-04 is> 1.0 E-4. However, the .!lCDF is -2.80E-5 (a decrease in CDF) | | * Unit 2 Post-Transition CD F of 4.80E-04 is> 1.0E-4. However, the .!lCDF is -2 .80E-5 (a decrease in CDF) |
| * Unit 1 Post-Transition LERF of 2.61 E-5 is> 1.0E-5 and ilLERF of 2.42E-5 is> 1.0E-6 | | * Unit 1 Post-Transition LERF of 2.61 E-5 is> 1.0E-5 and ilLERF of 2.42E-5 is> 1.0E-6 |
| * Unit 2 Post-Transition LERF of 1.10E-5 is> 1.0E-5 and ilLERF of 7.58E-6 is> 1.0E-6 Table 2 presents more realistic risk results for removal of credit for SDS modifications, but with a revision of the PRA assumptions for RCP seal leakage split fraction upon a loss of seal cooling in a fire, in accordance with Westinghouse WCAP 16141. Table 1: Post-Transition and Compliant Model Results without Credit for the SDS Modification Unit 1 Unit 2 Post-Transition Fire CDF 7.96E-04 Post-Transition Fire CDF 4.80E-04 NFPA 805 Compliant Fire CDF 1.82E-04 NFPA 805 Compliant Fire CDF 5.08E-04 ilCDF 6.14E-04 .!lCDF -2.80E-05 Post-Transition Fire LERF 2.61 E-05 Post-T ransition Fire LERF 1.10E-05 NFPA 805 Compliant Fire LERF 1.92E-06 NFPA 805 Compliant Fire LERF 3.42E-06 b.LERF 2.42E-05 ilLERF 7.58E-06 Table 2: Post-Transition and Compliant Model Results without Credit for the SDS Modification and Refined RCP Seal Leakage Split Fraction Unit 1 Unit 2 Post-Transition Fire CDF 2.41 E-04 Post-Transition Fire CDF 1.42E-04 NFPA 805 Compliant Fire CDF 8.88 E-05 NFPA 805 Compliant Fire CDF 4.06E-04 .!lCDF 1.52E-04 ilCDF -2.64E-04 Post-Transition Fire LERF 6.27E-06 Post-Transition Fire LERF 3.07E-06 NFPA 805 Compliant Fire LERF 7.83E-07 NFPA 805 Compliant Fire LERF 1.96E-06 ilLERF 5.49E-06 ilLERF 1.11 E-06 In conclusion, the PBNP NFPA 805 strategy is to install qualified SDSs consistent with the PRA results previously documented in LAR 271, however, PBNP is evaluating alternatives should this SDS fail to meet requirements. | | * Unit 2 Post-Transition LERF of 1.10E-5 is> 1.0E-5 and ilLERF of 7.58E-6 is> 1.0E-6 Table 2 presents more realistic risk results for removal of credit for SDS modifications, but with a revision of the PRA assumptions for RCP seal leakage split fraction upon a loss of seal cooling in a fire, in accordance with Westinghouse WCAP 16141 . |
| PBNP has implemented interim compensatory measures to address the current fire risk until NRC approval of LAR 271 and installation of the committed modifications, as discussed in the attachment toLAR 271. Page 2 of 3 References | | Table 1: Post-Transition and Compliant Model Results without Credit for the SDS Modification Unit 1 Unit 2 Post-Transition Fire CDF 7.96E-04 Post-Transition Fire CDF 4 .80E-04 NFPA 805 Compliant Fire CDF 1.82E-04 NFPA 805 Compliant Fire CDF 5.08E-04 ilCDF 6.14E-04 .!lCDF -2.80E-05 Post-Transition Fire LERF 2.61 E-05 Post-Transition Fire LERF 1.10E-05 NFPA 805 Compliant Fire LERF 1.92E-06 NFPA 805 Compliant Fire LERF 3.42E-06 b.LERF 2.42E-05 ilLERF 7.58E-06 Table 2: Post-Transition and Compliant Model Results without Credit for the SDS Modification and Refined RCP Seal Leakage Split Fraction Unit 1 Unit 2 Post-Transition Fire CDF 2.41 E-04 Post-Transition Fire CDF 1.42E-04 NFPA 805 Compliant Fire CDF 8.88E-05 NFPA 805 Compliant Fire CDF 4.06E-04 |
| : 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)-NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition." (ML13182A350 | | .!lCDF 1.52E-04 ilCDF -2.64E-04 Post-Transition Fire LERF 6.27E-06 Post-Transition Fire LERF 3.07E-06 NFPA 805 Compliant Fire LERF 7.83E-07 NFPA 805 Compliant Fire LERF 1.96E-06 ilLERF 5.49E-06 ilLERF 1.11 E-06 In conclusion, the PBNP NFPA 805 strategy is to install qualified SDSs consistent with the PRA results previously documented in LAR 271, however, PBNP is evaluating alternatives should this SDS fail to meet requirements. PBNP has implemented interim compensatory measures to address the current fire risk until NRC approval of LAR 271 and installation of the committed modifications, as discussed in the attachment toLAR 271. |
| & 353) 2. NRC to NextEra Energy electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2-Acceptance Review Regarding the NFPA-805 License Amendment Request-Opportunity to Supplement (TAC Nos. MF2372 and NF2373)." Page 3 of 3}} | | Page 2 of 3 |
| | |
| | References |
| | : 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)- NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition." (ML13182A350 & 353) |
| | : 2. NRC to NextEra Energy electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2- Acceptance Review Regarding the NFPA-805 License Amendment Request- Opportunity to Supplement (TAC Nos. MF2372 and NF2373)." |
| | Page 3 of 3}} |
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MONTHYEARML13182A3502013-06-26026 June 2013 License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3 Project stage: Other ML13256A1972013-09-0909 September 2013 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 Acceptance Review Regarding the NFPA 805 License Amendment Request - Opportunity to Supplement Project stage: Acceptance Review NRC 2013-0092, License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 8052013-09-16016 September 2013 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805 Project stage: Supplement ML13267A0372013-09-25025 September 2013 Acceptance Review of Licensing Action License Amendment Request to Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants Project stage: Acceptance Review ML14127A2942014-05-0909 May 2014 Regulatory Audit in Support of License Amendment Request to Implement NFPA 805, as Incorporated Into 10 CFR 50.48(c) Project stage: Other ML14153A3902014-05-27027 May 2014 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 Final Requests for Additional Information License Amendment Request Associated with NFPA 805 (TAC Nos. MF2372 and MF2373) Project stage: RAI ML14189A3652014-07-0808 July 2014 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 Final (Revised) Requests for Additional Information License Amendment Request Associated with NFPA 805 Project stage: RAI NRC-2014-0043, Response (60 Day) to Request for Additional Information License Amendment Request Associated with NFPA 8052014-07-29029 July 2014 Response (60 Day) to Request for Additional Information License Amendment Request Associated with NFPA 805 Project stage: Request NRC 2014-0054, Response (90 Day) to Request for Additional Information License Amendment Request Associated with NFPA 8052014-08-28028 August 2014 Response (90 Day) to Request for Additional Information License Amendment Request Associated with NFPA 805 Project stage: Request NRC 2014-0056, Response (120 Day) to Request for Additional Information and Revision to 60 Day Response License Amendment Request 271 Associated with NFPA 8052014-09-25025 September 2014 Response (120 Day) to Request for Additional Information and Revision to 60 Day Response License Amendment Request 271 Associated with NFPA 805 Project stage: Request ML14325A5412014-11-14014 November 2014 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Follow-up Requests for Additional Information (Afpb) NFPA 805 License Amendment Request Review Project stage: RAI NRC 2014-0073, Response to Request for Additional Information (Radiation Release) License Amendment Request 271 Associated with NFPA 8052014-11-14014 November 2014 Response to Request for Additional Information (Radiation Release) License Amendment Request 271 Associated with NFPA 805 Project stage: Response to RAI ML14325A5402014-11-19019 November 2014 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Follow-up Requests for Additional Information (Afpb) NFPA 805 License Amendment Request Review Project stage: RAI ML15091A5172015-04-0606 April 2015 4/6/2015, Meeting Slide for Public Teleconference on Point Beach MCR Abandonment Analysis for Loss of Control Scenarios Project stage: Request ML15106A5932015-04-14014 April 2015 NRR E-mail Capture - Request for Additional Information - Point Beach Nuclear Plant, Unit 1 and 2 - MF2372 and MF2373 Project stage: RAI ML15106A7122015-04-23023 April 2015 Summary of April 6, 2015, Meeting with NextEra Energy Point Beach, LLC, to Discuss License Amendment Request to Transition to NFPA 805 Project stage: Meeting ML15121A0572015-05-15015 May 2015 June 9 - 12, 2014 Summary of Audit at Point Beach Nuclear Plant, Unit Nos. 1 and 2, Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 Project stage: Other NRC 2016-0012, Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 8052016-04-0707 April 2016 Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 805 Project stage: Response to RAI 2014-07-29
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Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2022-177, Subsequent License Renewal Application - Second Annual Update2022-11-28028 November 2022 Subsequent License Renewal Application - Second Annual Update L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 L-2021-147, Subsequent License Renewal Application - Aging Management Supplement 3 Revision 12021-07-26026 July 2021 Subsequent License Renewal Application - Aging Management Supplement 3 Revision 1 L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021 Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses L-2021-113, Subsequent License Renewal Application - Aging Management Supplement 32021-05-27027 May 2021 Subsequent License Renewal Application - Aging Management Supplement 3 NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses ML20329A2142020-11-16016 November 2020 Enclosure 1, Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application Enclosures Summary ML20329A2642020-11-16016 November 2020 Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) ML20329A2192020-11-16016 November 2020 Enclosure 2, Affidavits Supporting Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 ML20329A2482020-11-16016 November 2020 Enclosure 3, Attachment 2, Appendix E Applicant'S Environmental Report Subsequent Operating License Renewal Point Beach Nuclear Plant Units 1 and 2 NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2018-0028, NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2018-07-30030 July 2018 NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements NRC 2018-0001, Transmittal of Construction Truss License Amendment Request Document2018-04-12012 April 2018 Transmittal of Construction Truss License Amendment Request Document NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency2018-03-30030 March 2018 License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency NRC 2017-0043, License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants2017-08-31031 August 2017 License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants NRC 2017-0028, License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2017-06-23023 June 2017 License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances2017-03-31031 March 2017 License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2016-07-29029 July 2016 License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC-2016-0009, License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves2016-03-10010 March 2016 License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-02-12012 February 2016 License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2015-0075, License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation2016-01-15015 January 2016 License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-27027 March 2015 LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process NRC 2014-0075, Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog2014-12-0808 December 2014 Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog NRC 2014-0003, License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2014-07-0303 July 2014 License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0202 July 2014 License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process NRC 2013-0092, License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 8052013-09-16016 September 2013 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805 NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 22013-06-26026 June 2013 Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3 ML13182A3502013-06-26026 June 2013 License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3 NRC 2013-0028, License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 32013-06-26026 June 2013 License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 3 NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding2013-06-0404 June 2013 License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013 Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013 License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) NRC 2012-0073, License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change2012-09-17017 September 2012 License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012 License Amendment Request 270, Operations Manager Qualification Requirements NRC 2012-0040, License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change2012-06-18018 June 2012 License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change NRC 2011-0066, License Amendment Request 254, Removal of the Table of Contents from Technical Specifications2011-06-23023 June 2011 License Amendment Request 254, Removal of the Table of Contents from Technical Specifications NRC 2010-0189, License Amendment Request 261, Extended Power Uprate Response to Request for Clarification2010-12-21021 December 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Clarification NRC 2010-0154, License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information2010-09-28028 September 2010 License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information NRC 2010-0146, License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-09-28028 September 2010 License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate NRC 2010-0145, License Amendment Request 261, Supplement 9 Extended Power Uprate2010-09-21021 September 2010 License Amendment Request 261, Supplement 9 Extended Power Uprate NRC 2010-0132, License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information2010-09-0101 September 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information NRC 2010-0133, License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change2010-08-12012 August 2010 License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010 License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate NRC 2010-0084, License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan2010-07-0808 July 2010 License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan 2023-09-19
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NEXTera***
ENERGY~
POINT BEACH September 16, 2013 NRC 2013-0092 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805
References:
- 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)- NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition ." (ML13182A350 & 353)
- 2. NRC to NextEra Energy Point Beach, LLC electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2- Acceptance Review Regarding the NFPA-805 License Amendment Request- Opportunity to Supplement (TAC Nos. MF2372 and NF2373)." (ML13256A197)
Pursuant to 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra) hereby submits a supplement to License Amendment Request (LAR) 271 (Reference 1) for Point Beach Nuclear Plant (PBNP) Units 1 and 2. This supplement (see Enclosure) provides the NextEra response to the NRC LAR 271 acceptance review question transmitted on September 9, 2013 (Reference 2). NextEra requests approval of this supplement on the same schedule as LAR 271. The supplement will be implemented on the same schedule as that of LAR 271.
This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.
In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official.
If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 16, 2013. .
Very truly yours, NextEra Energy Point Beach, LLC Enclosure cc: Administrator, Region Ill, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC PSCW
ENCLOSURE LICENSE AMENDMENT REQUEST 271, SUPPLEMENT 1 TRANSITION TO 10 CFR 50.48(c) - NFPA 805 Introduction NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 271 (Reference 1) to NRC dated June 26, 2013, requesting transition of the Point Beach Nuclear Plant (PBNP) fire protection program to NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition. The NRC staff transmitted a LAR 271 acceptance review question to NextEra via electronic mail dated September 9, 2013 (Reference 2). The following information is provided by NextEra in response to NRCs staff's question .
NextEra Response to NRC LAR 271 Acceptance Question Question 1 Table S-2 of the June 26, 2013, application identifies modification MOD-3 to be an upgrade of the reactor coolant pump (RCP) seals, which includes installation of Westinghouse SHIELD' low leakage RCP seals. Given recent concerns about the performance of the new Westinghouse RCP seals, the risk reduction credit taken in your application for this modification may be optimistic.
During a September 4, 2013, phone call, NextEra stated that based on a sensitivity analysis recently performed, the Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment [PRA] in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," risk acceptance guidelines would be exceeded if the new Westinghouse SHIELD' RCP seals are not credited in the PRA.
Please discuss which RG 1.174 acceptance guidelines are exceeded (CDF, LERF, !J.CDF,
!J.LERF) for each unit at Point Beach, and the magnitude of the exceedance.
NextEra Response NextEra committed in PBNP LAR 271 (Enclosure, AttachmentS, Table S-2, Item MOD-3) to install the Westinghouse Electric Company (WEC) SHIELD' Passive Thermal Shutdown Seal (SDS) into the existing WEC reactor coolant pump (RCP) seals of each Unit to provide a more controllable leak rate, if cooling flow is lost to the RCP seals due to a fire. With the recent failure of the Beaver Valley SDS to actuate when tested following one reactor fuel cycle of operation, NextEra is tracking the Westinghouse redesign and qualification testing of their SDS. NextEra plans to install the redesigned SDS into the RCP seals in both units with the first installation tentatively planned for one RCP on Unit 2 during the U2R33 spring 2014 refueling outage.
Alternatives to the SDS are also being evaluated as contingency plans in the event that the SDS redesign is not acceptable.
Regarding exceeding the RG 1.174 acceptance guidelines for each unit at Point Beach without credit for the SDS, two sensitivity analyses were performed on the fire PRA model utilized for the results reported in LAR 271. The sensitivity results (see Tables 1 and 2 below) show the fire Page 1 of 3
PRA core damage frequency (CD F) and large early release frequency (L ERF) for the Post NFPA 805 Transition and the Appendix R Compliant cases with the associated .!lCDF and ilL ERF for each PBNP Unit. Comparing the Table 1 values to the Regulatory Guide (RG) 1.174 acceptance guidelines in Figure 4 (Acceptance guidelines for core damage frequency) and Figure 5 (Acceptance guidelines for large early release frequency) lead to the following results:
- Unit 1 Post-Transition CDF of 7.96E-04 is> 1.0E-4 and .!lCDF of 6.14E-4 is> 1.0E-5
- Unit 2 Post-Transition CD F of 4.80E-04 is> 1.0E-4. However, the .!lCDF is -2 .80E-5 (a decrease in CDF)
- Unit 1 Post-Transition LERF of 2.61 E-5 is> 1.0E-5 and ilLERF of 2.42E-5 is> 1.0E-6
- Unit 2 Post-Transition LERF of 1.10E-5 is> 1.0E-5 and ilLERF of 7.58E-6 is> 1.0E-6 Table 2 presents more realistic risk results for removal of credit for SDS modifications, but with a revision of the PRA assumptions for RCP seal leakage split fraction upon a loss of seal cooling in a fire, in accordance with Westinghouse WCAP 16141 .
Table 1: Post-Transition and Compliant Model Results without Credit for the SDS Modification Unit 1 Unit 2 Post-Transition Fire CDF 7.96E-04 Post-Transition Fire CDF 4 .80E-04 NFPA 805 Compliant Fire CDF 1.82E-04 NFPA 805 Compliant Fire CDF 5.08E-04 ilCDF 6.14E-04 .!lCDF -2.80E-05 Post-Transition Fire LERF 2.61 E-05 Post-Transition Fire LERF 1.10E-05 NFPA 805 Compliant Fire LERF 1.92E-06 NFPA 805 Compliant Fire LERF 3.42E-06 b.LERF 2.42E-05 ilLERF 7.58E-06 Table 2: Post-Transition and Compliant Model Results without Credit for the SDS Modification and Refined RCP Seal Leakage Split Fraction Unit 1 Unit 2 Post-Transition Fire CDF 2.41 E-04 Post-Transition Fire CDF 1.42E-04 NFPA 805 Compliant Fire CDF 8.88E-05 NFPA 805 Compliant Fire CDF 4.06E-04
.!lCDF 1.52E-04 ilCDF -2.64E-04 Post-Transition Fire LERF 6.27E-06 Post-Transition Fire LERF 3.07E-06 NFPA 805 Compliant Fire LERF 7.83E-07 NFPA 805 Compliant Fire LERF 1.96E-06 ilLERF 5.49E-06 ilLERF 1.11 E-06 In conclusion, the PBNP NFPA 805 strategy is to install qualified SDSs consistent with the PRA results previously documented in LAR 271, however, PBNP is evaluating alternatives should this SDS fail to meet requirements. PBNP has implemented interim compensatory measures to address the current fire risk until NRC approval of LAR 271 and installation of the committed modifications, as discussed in the attachment toLAR 271.
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References
- 1. NextEra Energy Point Beach, LLC, letter to NRC dated June 26, 2013, "Transition to 10 CFR 50.48(c)- NFPA 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,' 2001 Edition." (ML13182A350 & 353)
- 2. NRC to NextEra Energy electronic mail dated September 9, 2013, "Point Beach Nuclear Plant, Units 1 and 2- Acceptance Review Regarding the NFPA-805 License Amendment Request- Opportunity to Supplement (TAC Nos. MF2372 and NF2373)."
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