Letter Sequence Other |
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Results
Other: ML13317A950, ML15119A292, ML15254A135, RS-13-024, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049), RS-13-127, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (EA-12-049), RS-14-202, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-14-212, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-15-023, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049), RS-15-032, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-15-280, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), RS-16-026, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), RS-16-149, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049), RS-17-021, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events, RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
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MONTHYEARRS-13-024, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) Project stage: Other RS-13-127, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (EA-12-049) Project stage: Other ML13317A9502013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Peach Bottom Atomic Power Station, Units 2 and 3, TAC Nos.: MF0845 and MF0846 Project stage: Other ML13220A1052013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies Project stage: Acceptance Review RS-14-202, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other RS-14-212, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-15-023, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-15-032, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ML15119A2922015-05-0606 May 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML15254A1352015-09-23023 September 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other RS-15-280, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-12-15015 December 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other RS-16-026, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-16-149, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049) Project stage: Other RS-17-021, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events Project stage: Other RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other 2015-02-27
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Category:Letter type:RS
MONTHYEARRS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-028, Fitness for Duty Performance Data Reports - Annual 20202021-02-26026 February 2021 Fitness for Duty Performance Data Reports - Annual 2020 RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-21-002, Company - Update to Correspondence Addressees and Service Lists2021-01-0404 January 2021 Company - Update to Correspondence Addressees and Service Lists RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020 Proposed Changes to Decommissioning Trust Agreements RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 RS-20-110, Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-0202 September 2020 Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-20-111, Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-0202 September 2020 Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-20-056, Re. Ginna, Withdrawal of Relief Request for Alternative Frequency to Supplemental Indication2020-04-10010 April 2020 Re. Ginna, Withdrawal of Relief Request for Alternative Frequency to Supplemental Indication RS-20-037, Annual Property Insurance Status Report2020-04-0101 April 2020 Annual Property Insurance Status Report RS-20-039, Report on Status of Decommissioning Funding for Shutdown Reactors2020-03-31031 March 2020 Report on Status of Decommissioning Funding for Shutdown Reactors RS-20-041, Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-03-20020 March 2020 Response to NRC Regulatory Issue Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations RS-20-027, Advisement of Leadership Changes2020-03-0202 March 2020 Advisement of Leadership Changes RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) RS-20-023, Additional Information Regarding Request for Approval of Change to Exelon Generation Company, LLC, Quality Assurance Topical Report2020-02-24024 February 2020 Additional Information Regarding Request for Approval of Change to Exelon Generation Company, LLC, Quality Assurance Topical Report RS-19-075, Request for Approval of Change to Quality Assurance Topical Report2019-12-0505 December 2019 Request for Approval of Change to Quality Assurance Topical Report RS-19-111, Notice of Disbursement from Decommissioning Trusts2019-11-20020 November 2019 Notice of Disbursement from Decommissioning Trusts RS-19-102, Amended Nuclear Decommissioning Trust Agreements2019-10-0808 October 2019 Amended Nuclear Decommissioning Trust Agreements RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-085, Additional Information Regarding Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control for R.E. Ginna Nuclear Power Plant2019-08-22022 August 2019 Additional Information Regarding Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control for R.E. Ginna Nuclear Power Plant RS-19-073, Proposed Change to Decommissioning Trust Agreements2019-08-15015 August 2019 Proposed Change to Decommissioning Trust Agreements RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program 2023-08-04
[Table view] Category:Status Report
MONTHYEARWM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23090A0482023-03-31031 March 2023 (PBAPS) Unit 1 - Decommissioning Status Report - 2022 RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors LR-N21-0015, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-03-25025 March 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML20097C6472020-03-27027 March 2020 Decommissioning Status Report - 2019 LR-N19-0014, Stations - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-03-25025 March 2019 Stations - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-18-060, Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable ...2018-06-29029 June 2018 Eighth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable ... RS-17-155, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable ...2017-12-15015 December 2017 Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable ... RS-17-096, Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2017-08-28028 August 2017 Ninth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) RS-17-068, Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.2017-06-30030 June 2017 Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe. RS-17-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-30030 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-16-046, Annual Property Insurance Status Report2017-03-29029 March 2017 Annual Property Insurance Status Report LR-N17-0043, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-29029 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-17-021, Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events RS-16-235, Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.2016-12-15015 December 2016 Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe. RS-16-149, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049)2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (Order Number EA-12-049) RS-16-109, Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 6/6/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-06-30030 June 2016 Fourth Six-Month Status Report for Phases 1 & 2 Overall Integrated Plan in Response to 6/6/2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions RS-16-094, Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isl2016-04-25025 April 2016 Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isla RS-16-026, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-15-280, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-12-15015 December 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-15-214, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-15-032, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-14-305, First Six-Month Status Report Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...2014-12-19019 December 2014 First Six-Month Status Report Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... RS-14-212, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML14059A2222014-02-28028 February 2014 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-14-024, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-28028 February 2014 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-13-126, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-13-127, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events (EA-12-049) RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors RA-13-030, Annual Property Insurance Status Report2013-04-0101 April 2013 Annual Property Insurance Status Report ML13092A3312013-03-29029 March 2013 Decommissioning Status Report - 2012 LR-N13-0059, NRC Decommissioning Funding Status Report2013-03-26026 March 2013 NRC Decommissioning Funding Status Report ML12122A0712012-05-14014 May 2012 Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 RA-12-032, Annual Property Insurance Status Report2012-03-30030 March 2012 Annual Property Insurance Status Report ML12024A3762011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analyses, Current Status and Next Steps LR-N11-0086, NRC Decommissioning Funding Status Report2011-03-31031 March 2011 NRC Decommissioning Funding Status Report ML1009200492010-04-0101 April 2010 Annual Property Insurance Status Report RS-10-055, Report on Status of Decommissioning Funding for Shutdown Reactors2010-03-29029 March 2010 Report on Status of Decommissioning Funding for Shutdown Reactors ML0909202562009-04-0101 April 2009 Annual Property Insurance Status Report RS-09-041, Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC2009-03-31031 March 2009 Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC LR-N09-0074, Letter from Jeffrie Keenan of PSEG Nuclear L.L.C., NRC Decommissioning Funding Status Report for Salem, Hope Creek & Peach Bottom Generating Stations2009-03-31031 March 2009 Letter from Jeffrie Keenan of PSEG Nuclear L.L.C., NRC Decommissioning Funding Status Report for Salem, Hope Creek & Peach Bottom Generating Stations ML0814004882008-05-0909 May 2008 Decommissioning Status Report ML0613902022006-05-17017 May 2006 NRC Decommissioning Funding Status Report, Salem, Hope Creek, and Peach Bottom LR-N05-0140, Units 2 & 3, NRC Decommissioning Funding Status Report2005-03-30030 March 2005 Units 2 & 3, NRC Decommissioning Funding Status Report ML0508703272005-03-25025 March 2005 Annual Property Insurance Status Report RS-05-035, Report on Status of Decommissioning Funding for Reactors2005-03-24024 March 2005 Report on Status of Decommissioning Funding for Reactors 2023-05-10
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1 Exelon Generation ~
Order No. EA-12-049 RS-13-127 August 28, 2013 u.s. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
References:
- 1. NRC Order Number EA-12-049, " Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
- 3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"
Revision 0, dated August 2012
- 4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 25, 2012
- 5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-024)
- 6. NRC Order Number EA-12-050, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents," dated March 12,2012
- 7. NRC Order Number EA-13-109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6,2013
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 2 On March 12,2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGC). Reference 1 was immediately effective and directs EGC to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference 5 provided the Peach Bottom Atomic Power Station, Units 2 and 3 overall integrated plan.
Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.
As described in Reference 5, full implementation of NRC Order EA-12-049 required mitigation strategies is dependent upon implementation of reliable hardened containment venting capability established in accordance with NRC Order EA-12-050 (Reference 6). NRC Order EA-13-109 (Reference 7) issued by the NRC on June 6,2013, rescinded the requirements of Order EA-12-050 and established revised schedule timelines and implementation dates for reliable hardened containment vents capable of operation under severe accident conditions.
The revised schedule and implementation time line contained in Order EA-13-109 delays the ability to achieve full implementation of the mitigation strategy requirements of Order EA 049. This need for relaxation from the implementation requirements of Order EA-12-049 is described in Section 5 of the enclosed update report. The request for relaxation of the full implementation schedule requirements of Order EA-12-049 will be submitted separately.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
th I declare under penalty of perjury that the foregoing is true and correct. Executed on the 28 day of August 2013.
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28,2013 Page 3
Enclosure:
- 1. Peach Bottom Atomic Power Station, Units 2 and 3 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region I NRC Senior Resident Inspector - Peach Bottom Atomic Power Station, Units 2 and 3 NRC Project Manager, NRR - Peach Bottom Atomic Power Station, Units 2 and 3 Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Robert J. Fretz, Jr, NRR/JLD/PMB, NRC Mr. Robert L. Dennig, NRR/DSS/SCVB, NRC Mr. Eric E. Bowman, NRR/DPRlPGCB, NRC Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources S. T. Gray, State of Maryland R. R. Janati, Commonwealth of Pennsylvania
Enclosure Peach BoHom Atomic Power Station, Units 2 and 3 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (13 pages)
Enclosure Peach Bottom Atomic Power Station Units 2 and 3 First Six Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Peach Bottom Atomic Power Station, Units 2 and 3 developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
2 Milestone Accomplishments None 3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.
Target Revised Target Milestone Completion Activity Status Completion Date Date Submit 60 Day Status Report Oct 2012 Complete Submit Overall Integrated Plan Feb 2013 Complete Contract with RRC Complete Submit 6 Month Updates:
Complete with Update 1 Aug 2013 this submittal Update 2 Feb 2014 Not Started Update 3 Aug 2014 Not Started Update 4 Feb 2015 Not Started Page 1 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Milestone Completion Activity Status Completion Date Date Update 5 Aug 2015 Not Started Update 6 Feb 2016 Not Started Update 7 Aug 2016 Not Started Submit Completion Report Dec 2016 Not Started Perform Staffing Analysis May 2015 Not started Modifications:
Unit 2 Design Engineering May 2015 Started Unit 2 Implementation Outage Nov 2016 Not Started Unit 3 Design Engineering June 2014 Started Unit 3 Implementation Outage Oct 2015 Not Started Storage:
Storage Design Engineering Oct 2015 Not started Storage Implementation Oct 2015 Not started FLEX Equipment:
Procure On-Site Equipment Sept 2015 Started Develop Strategies with RRC Dec 2014 Started Procedures:
Create Site-Specific Procedures Sept 2015 Not started Validate Procedures (NEI-12.06, section Sept 2015 Not started 11.4.3)
Create Maintenance Procedures Sept 2015 Not started Training:
Page 2 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Milestone Completion Activity Status Completion Date Date Develop Training Plan March 2015 Not started Training Complete Oct 2015 Not started Unit 2 FLEX Implementation Oct 2016 Not started Unit 3 FLEX Implementation Oct 2015 Not started Full Site FLEX Implementation Oct 2016 Not started 4 Changes to Compliance Method General Integrated Plan Elements BWR-Change 1 Time Constraints- Action Item #14: Early Containment Venting. Early containment venting was to be initiated using the Torus Hardened Vent Line at approximately 4.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into the event to prevent Torus temperature from exceeding 230 F.
Reason for change: Modification of the Torus Hardened Vent to allow venting at pressures below 30 psig have been delayed due to the Severe Accident Capable Vent (SACV) Order EA-13-109, scheduled for completion at Peach Bottom Unit 2 in Fall 2016 and Unit 3 in Fall 2017.
Maintain Core Cooling: Determine baseline coping capability with installed coping modifications not induding FLEX modifications. Utilizing methods described in Table 3-1 of NEI12-06:
Reactor Level Control: Venting of containment was to be initiated such that peak Suppression Pool temperature was to remain below the maximum allowed for RCIC operation, at 230 deg F.
Modifications to the Peach Bottom Torus Hardened Vent required to perform early venting have been delayed due to the Severe Accident Capable Vent (SACV) Order EA-13-109, scheduled for completion at Peach Bottom Unit 2 in Fall 2016 and Unit 3 in Fall 2017. Venting of containment using the Torus Hardened Vent could only now begin at a minimum containment pressure of 30 psig with a saturation temperature of the torus of at least 278 deg F. Conceptual Sketch and the discussion section for Safety Function Support show modifications to install FLEX 480VAC generator connections. The primary strategy is being revised to install a 480VAC portable generator connection in each unit's 135' elevation reactor building railroad access bay with cable supplying transfer switches to the E124 and E134 Load Centers. The alternate Page 3 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 strategy is being revised to install a 480VAC portable generator connection at each unit's Outage Power area behind the Reactor Building on the west wall with cable supplying the E324 and E334 Load Centers.
Existing cabling between the E124 and E324, and the E134 and the E334 Load Centers will be used to crosstie power from the FLEX generators. The 480VAC motor control centers required for FLEX will be powered from the E124, E324, E134 and E334 Load Centers. No new cables or modifications will be required to the motor control centers.
This change reduces the number of 480VAC Load Centers and Motor Control Centers to be powered by the FLEX generators. On Unit 2 the E224 and E424 480VAC Load Centers and the E224-R-B and E424-T-B 480VAC Motor Control Centers will not be powered. On Unit 3 the E234 480VAC Load Center and the E234-R-B and E234-T-B Motor Control Centers will not be powered. The Division 2 "B" RHR MO-2(3)-
25B valve for vessel injection and the MO-2(3)-39B and MO-2(3)-34B valves for Torus makeup will not have power and will be unavailable for operation from the Control Room. The Division 2 "B" RHR MO-2(3)-25B valve for vessel injection and the MO-2(3)-39B and MO-2(3)-34B valves for Torus makeup are not required for compliance with Order EA-12-049.
Maintain Containment: EPG/SAG Rev 3 guidance to perform early containment venting at approximately 4.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into the event required modification to the existing Peach Bottom Torus Hardened Vent. These modifications have been delayed due to the Severe Accident Capable Vent (SACV) Order EA-13-109, scheduled for completion at Peach Bottom Unit 2 in Fall 2016 and Unit 3 in Fall 2017.
Change 2 Key Containment Parameters: Torus Wide Range Level Instruments LR/TR-8(9)123A is added to the Key Containment Parameters list of instrumentation.
Change 3 Conceptual Sketch and the SFP Makeup discussion section for the Maintain Spent Fuel Pool Cooling show water supply modifications to the Spent Fuel Pool by installing additional manual valves and hose connections downstream of HV-(3)-4457A and HV-2(3)-4457B. This is being revised to a single hose connection upstream of the HV-2(3)-4457A and HV-2(3)-4457B on 165' Reactor Building with sections of fire hose then routed to the 234' elevation of the Refuel Floor. Hoses will then be used to makeup to the Spent Fuel Pool or provide spray capability to the Spent Fuel Pool. The new hose connections will be installed on seismically rated piping.
Change 4 Conceptual Sketch and the discussion section for Safety Function Support show modifications to install FLEX 480VAC generator connections. The primary strategy is being revised to install a 480VAC portable generator connection in each unit's 135' elevation reactor building railroad access bay with cable supplying transfer switches to the E124 and E134 Load Centers. The alternate Page 4 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 strategy is being revised to install a 480VAC portable generator connection at each unit's Outage Power area behind the Reactor Building on the west wall with cable supplying the E324 and E334 Load Centers.
Existing cabling between the E124 and E324, and the E134 and the E334 Load Centers will be used to crosstie power from the FLEX generators. The 480VAC motor control centers required for FLEX will be powered from the E124, E324, E134 and E334 Load Centers. No new cables or modifications will be required to the motor control centers.
This change reduces the number of 480VAC Load Centers and Motor Control Centers to be powered by the FLEX generators. On Unit 2 the E224 and E424480VAC Load Centers and the E224-R-B and E424-T-B 480VAC Motor Control Centers will not be powered. On Unit 3 the E234 480VAC Load Center and the E234-R-B and E234-T-B Motor Control Centers will not be powered. The Division 2 "B" RHR MO-2(3)-
25B valve for vessel injection and the MO-2(3)-39B and MO-2(3)-34B valves for Torus makeup will not have power and will be unavailable for operation from the Control Room. The Division 2 "B" RHR MO-2(3)-25B valve for vessel injection and the MO-2(3)-39B and MO-2(3)-34B valves for Torus makeup are not required for compliance with Order EA-12-049.
The OAV030 Control Room Emergency Vent Supply Fan A, the OAV034 Emergency Switchgear and Battery Room Vent Supply Fan A and the OAV036 Battery Room Exhaust Fan A are powered from the E324-T-B Motor Control Center and will be available for operation.
5 Need for ReliefIRelaxation and Basis for the ReliefIRelaxation Relief /Relaxation is required due to the delay in the modifications to the Torus Hardened Vent due to the Severe Accident Capable Vent (SACV) Order EA-13-109 (Reference 3).
This section provides a summary of needed relief/relaxation only. The specific details will be submitted in a separate document at a later date.
NRC Order EA-12-049 requires implementation of Mitigation Strategies to include procedures, guidance, training, and acquisition, staging, or installing of equipment needed for the strategies. Reference 1 provided the Peach Bottom Atomic Power Station response to NRC Order EA-12-049. The cover letter identifies that delays in implementing the Hardened Containment Vent System as required by NRC order EA-12-050 (Reference 4) will also affect implementation of the Mitigation Strategies Order EA-12-049 actions.
The Reference 1 enclosure describes the Peach Bottom Atomic Power Station Mitigation Strategies that is based on venting the containment using the Hardened Containment Vent System. It also describes that a modification to install a Hardened Containment Vent System (HCVS) is required.
Thus, the Peach Bottom Atomic Power Station NRC Order EA-12-049 response provided in Reference 1 was premised on installation and use of a Hardened Containment Vent System as required by NRC Order Page 5 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 EA-12-0S0. Upon issuance of NRC Order EA-13-109, the NRC staff changed technical and schedule requirements applicable to the Hardened Containment Vent System and rescinded the requirements of NRC Order EA-12-0S0.
As a result, full compliance to the Mitigation Strategies required by NRC Order EA-12-049 and described in Reference 1 for Peach Bottom Atomic Power Station Units 2 and 3 will not be achieved until compliance to NRC Order EA-13-109 is achieved. Relief/relaxation from the NRC Order 12-049 IV.A.2 requirements is required.
Peach Bottom Atomic Power Station will be in compliance with the aspects of the Reference 1 Unit 2 and Unit 3 Mitigation Strategies that do not rely upon a Hardened Containment Vent System unless otherwise described.
6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following tables provide a summary of the open items documented in the Overall Integrated Plan or the Draft Safety Evaluation (SE) and the status of each item.
Section Reference Overall Integrated Plan Open Item Status Multiple Sections Item 1) Transportation routes will be Started developed from the equipment storage area to the FLEX staging areas. An administrative program will be developed to ensure pathways remain clear or compensatory actions will be implemented to ensure all strategies can be deployed during all modes of operation. The location of the storage areas, identification of the travel paths and creation of the administrative program are open items.
Programmatic Controls (p. 7) Item 2) An administrative program for FLEX Not started to establish responsibilities, testing and maintenance requirements will be implemented.
Describe Training Plan (p. 8) Item 3) Training materials for FLEX will be Not started developed for all station staff involved in implementing FLEX strategies.
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Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Maintain Spent Fuel pool Item 4) Complete an evaluation of the spent Not started Cooling (p. 30) fuel pool area for steam and condensation to determine vent path strategy requirements.
Safety Function Support (p. Item 5) ROC room temperature analysis is Started
- 38) still in progress.
Safety Function Support Item 6) Evaluate the habitability of the Main Not started (p.38) Control Room and develop a strategy to maintain habitability.
Safety Function Support (p. Item 7) Develop a procedure to prop open Not started
- 38) battery room doors and utilize portable fans or utilize installed room supply and exhaust fans upon energizing the battery chargers to prevent a buildup of hydrogen in the battery rooms.
Sequence of Events (p. 4) Item 8) Timeline walk through will be Not started completed for the FLEX generator installations when the detailed design and site strategy is finalized. The final timeline will be validated once the detailed designs are developed. The results will be provided in a future 6 month update.
Sequence of Events (pA) Item 9) Timeline walk through will be Not started completed for the FLEX pump installations when the detailed design and site strategy is finalized. The final time line will be validated once the detailed deSigns are developed.
The results will be provided in a future 6 month update.
Sequence of Events (p. 5) Item 10) Additional analysis will be Not started performed during detailed design development to ensure Suppression Pool temperature will support RCIC operation, in accordance with approved BWROG analysis, throughout the event.
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Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Sequence of Events (p. 5) Item 11) Analysis of deviations between Completed .
Exelon's engineering analyses and the Attachment 3 included in analyses contained in BWROG Document this six month update NEDC-33771P, "GEH Evaluation of FLEX Implementation Guidelines and documentation of results on Att. lB, "NSSS Significant Reference Analysis Deviation Table." Planned to be completed and submitted with August 2013 Six Month Update.
Draft Safety Evaluation Open Item Status N/A N/A 7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time.
8 References The following references support the updates to the Overall Integrated Plan described in this enclosure.
- 1. Peach Bottom Atomic Power Station Units 2 and 3, Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013.
- 2. NRC Order Number EA-12-049, "Order Modifying licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012.
- 3. NRC Order Number EA-13-109, "Order Modifying licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013.
- 4. NRC Order Number EA-12-050, "Order Modifying licenses with Regard to Reliable Hardened Containment Vents," dated March 12, 2012 Page 8 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 2013 9 Attachments
- 1. PBAPS Primary and Alternate Power Requirements Electrical Schematic
- 2. FLEX Simplified Design Mechanical Schematic
- 3. Peach Bottom Atomic Power Station FLEX Integrated Plan Analyses Reconciliation to NEDC-33771P, Rev 1 Page 9 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28,2013 Attachment 1 Note 1 Note 2 Note 2 50' via tray 2AD003 2CD003 3ADOO3 Battery Charger Battery Charger Battery Charger Unit 2 Unit3 PBAPS Primary and Alt Note 1 - Primary Connection in RB to support 1 Power Requirements Unit Specific Generator LoadUst Note 2 - Altemate connection west of RB to support 1 Battery Chargers - Input 45A Unit Specific Generator RCIC Control Power - 30A Baro Cond Vac Pp - 35A Vec Tank Cond Pp - 35A
'OY050 - 100A Page 10 of 13
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Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Attachment 3 Peach Bottom Atomic Power Station FLEX Integrated Plan Analyses Reconciliation to NEDC-33771P, Rev 1 (Attachment 1B in the Overall Integrated Plan Report)
NOTE: NEDC-33771P, Rev 1, Appendices Band D (BWR/4 Mark I with RCiC (No Venting, Suction From Suppression Pool, and Venting Starting at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Suction From CST)) are most similar to the Peach Bottom Atomic Power Station FLEX Plan strategy for maintaining Containment Integrity. Notable differences between the input parameters used in the Peach Bottom Atomic Power Station FLEX analyses and the NEDC-33771P, Rev 1, analyses are noted below in the Gap and Discussion column.
NEDC-Peach Bottom 33771P Design Item Parameter of Interest Analyses Applied Gap and Discussion Value (Page Value Value Reference)
Input Parameter Values 1 Core Thermal Power 17 3517 MWT 100% N/A 2 Reactor Dome Pressure 17 1050 psia N/A Initial RPV Water Level above 3 17 562.5 inches N/A vessel zero MAAP model configured with Recirc pump 4 Primary system Leakage 17 42gpm N/A leakage 18 gpm/pump, 5 gpm unidentified leakage and 1 gpm identified leakage 5 RPV Depressurization Time 17 20 minutes N/A 6 RPV Depressurization Rate 17 80 F / hour N/A 7 RPV Maintained Pressure 17 200 psig N/A Initial Wetwell Airspace 8 17 145 F N/A Temperature 9 Initial Wetwell Pressure 17 15.2 psia N/A 10 Suppression Pool Level 17 14.5 feet N/A Page 12 of 13
Peach Bottom Atomic Power Station, Units 2 and 3 First Six Month Status Report for the Implementation of FLEX August 28,2013 Attachment 3 NEDC-Peach Bottom 33771P Design Item Parameter of Interest Analyses Applied Gap and Discussion Value (Page Value Value Reference)
Initial Suppression Pool 11 17 95 F N/A Temperature 12 Drywell Free Volume 17 116,882.37 fe N/A MAAP Containment Venting starting when 13 Start of Venting 17 4.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> N/A torus temperature exceeds 200 F 14 Venting Flow Coefficient 17 0.75 N/A 15 Venting Pipe Size 17 16 inches N/A Resultant Parameter Values Maximum Suppression Pool Temperature (Venting, Torus 34 221 Fat 11.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 281°F Suction) The differences identified between the SHEX and MAAP analyses are due to the time in Maximum WetWell which containment venting was initiated.
Temperature (Venting, Torus 34 241 Fat 13.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 281°F Analyses of the containment pressures and Suction) temperature prior to initiation of the venting Maximum Wetwell Pressure 25.0 psi a at 4.7 action are approximately equal. The time for 34 56psig (Venting, Torus Suction) hours containment venting initiation in the MAAP analysis is based on Torus temperature Maximum Drywell exceeding 200 deg F.
Temperature (Venting, Torus 34 256 F at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 281°F Suction)
Maximum Drywell Pressure 24.9 psia at 4.7 34 56psig (Venting, Torus Suction) hours Page 13 of 13