Letter Sequence Other |
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Results
Other: ET 13-0027, Operating Corporation'S 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, ET 14-0011, Second 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, ET 14-0024, Third 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, ET 15-0005, Operating Corporation'S Fourth 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, ET 15-0020, Operating Corporation'S Fifth 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, ET 16-0008, Sixth 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., ET 16-0018, Seventh 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., ET 17-0003, Operating Corporation'S Compliance 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 and Final Integrated Plan, ML13070A026, ML16168A254
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MONTHYEARML13070A0262013-02-28028 February 2013 Operating Corporation 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) Project stage: Other ET 13-0027, Operating Corporation'S 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 Events2013-08-28028 August 2013 Operating Corporation'S 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 Project stage: Other ET 14-0011, Second 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 Events2014-02-26026 February 2014 Second 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 Project stage: Other WO 14-0023, Request for Schedule Relaxation of NRC Order EA-12-049, Requirement IV.A.22014-03-31031 March 2014 Request for Schedule Relaxation of NRC Order EA-12-049, Requirement IV.A.2 Project stage: Request ET 14-0024, Third 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 Events2014-08-28028 August 2014 Third 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 Project stage: Other ET 15-0005, Operating Corporation'S Fourth 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 Events2015-02-24024 February 2015 Operating Corporation'S Fourth 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 Project stage: Other ET 15-0020, Operating Corporation'S Fifth 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 Events2015-08-25025 August 2015 Operating Corporation'S Fifth 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 Project stage: Other ET 16-0008, Sixth 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.2016-02-17017 February 2016 Sixth 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. Project stage: Other ML16168A2542016-07-0606 July 2016 Report for the Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 Project stage: Other ET 16-0018, Seventh 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.2016-08-18018 August 2016 Seventh 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. Project stage: Other ET 17-0003, Operating Corporation'S Compliance 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 and Final Integrated Plan2017-01-19019 January 2017 Operating Corporation'S Compliance 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 and Final Integrated Plan Project stage: Other ML17171A2332017-06-12012 June 2017 Response to Request for FLEX Audit Documentation Project stage: Request ML17144A0092017-08-0202 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Approval 2015-08-25
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Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
[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) ML17361A0732017-12-20020 December 2017 Submittal of Anchor Darling Double Disc Gate Valve Information and Status ET 16-0018, Seventh 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.2016-08-18018 August 2016 Seventh 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. ET 16-0008, Sixth 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.2016-02-17017 February 2016 Sixth 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. ET 15-0006, Operating Corporation, Fourth Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.2015-02-24024 February 2015 Operating Corporation, Fourth Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. ET 15-0005, Operating Corporation'S Fourth 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 Events2015-02-24024 February 2015 Operating Corporation'S Fourth 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 ET 14-0025, Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.2014-08-21021 August 2014 Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. ET 14-0010, Operating Corporation'S Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation2014-02-26026 February 2014 Operating Corporation'S Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ET 13-0026, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order 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 EA-12-051) ML13102A3012013-03-29029 March 2013 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(0)(1) ML11181A1492011-06-23023 June 2011 Revision of Information Provided in 10 CFR 50.75 Report on Status of Decommissioning Funding ML1109506592011-03-29029 March 2011 CFR 50.75 Report on Status of Decommissioning Funding ML0910002882009-03-31031 March 2009 CFR 50.75 Report on Status of Decommissioning Funding ML0807300242008-02-22022 February 2008 Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1 ML0709900532007-03-29029 March 2007 CFR 50.75 Report on Status of Decommissioning Funding ML0509603662005-03-30030 March 2005 10 CFR 50.75 Report on Status of Decommissioning Funding ML0224007812002-01-18018 January 2002 E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report 2023-05-10
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~LFCREEK 'NUCLEAR OPERATING CORPORATION August 18, 2016 Jaime H. McCoy Vice President Engineering ET 16-0018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
- 1) Letter dated March 12, 2012, from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events"
- 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, August 29, 2012
- 3) NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX)
Implementation Guide," Revision 0, August 2012
- 4) Letter ET 12-0029, dated October 29, 2012, from J. P. Broschak, WCNOC, to USNRC
- 5) Letter WO 13-0014, dated February 28, 2013, from R. A. Smith, WCNOC, to USNRC
- 6) Letter ET 13-0027, dated August 28, 2013, from J. P. Broschak, WCNOC, to USNRC
- 7) Letter ET 14-0011, dated February 26, 2014, from J. P. Broschak, WCNOC, to USNRC
- 8) Letter ET 14-0024, dated August 28, 2014, from C. 0. Reasoner, WCNOC, to USNRC
- 9) Letter ET 15-0005, dated February 24, 2015, from J. H. McCoy, WCNOC, to USNRC
- 10) Letter ET 15-0020, dated August 25, 2015, from J. H. McCoy, WCNOC, to USNRC
- 11) Letter ET 16-0008, dated February 17, 2016, from J. H. McCoy, WCNOC, to USNRC P.O. Box 411 I Burlington, KS 66839 I Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 16-0018 Page 2 of 3
Subject:
Docket No. 50-482: Wolf Creek Nuclear Operating Corporation's Seventh 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" Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049 (Reference 1) to Wolf Creek Nuclear Operating Corporation (WCNOC). Reference 1 was immediately effective and directs WCNOC 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 Attachment 2 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 (OIP) pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document Nuclear Energy Institute (NEI) 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"
(Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the WCNOC initial status report regarding mitigation strategies. Reference 5 provided the WCNOC OIP. References 6, 7, 8, 9, 10, and 11 provided the first, second, third, fourth, fifth, and sixth six-month status reports for the implementation of Order EA-12-049, respectively.
Reference 1 requires submission of a status report at six-month intervals following. submittal of the OIP. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the seventh 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 attached report provides an update of milestone accomplishments since submittal of Reference 11, including any changes to the compliance method, schedule, or need for relief and the basis, if any.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Cynthia R. Hafenstine (620) 364-4204.
Sincerely, r711&-
Jaime H. McCoy JHM/rlt Attachment cc: K. M. Kennedy (NRC), w/a C. F. Lyon (NRC), w/a N. H. Taylor (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 16-0018 Page 3 of 3 STATE OF KANSAS )
) SS COUNTY OF COFFEY )
Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
. McCoy resident Engineering SUBSCRIBED and sworn to before me this I~ day of ~ , 2016.
GAYLE SHEPHEARD My Appointment Expires July 24, 2019
Expiration Date 7/d.. Y /d cJ 19
Attachment to ET 16-0018 Page 1 of 8 Wolf Creek Nuclear Operating Corporation's (WCNOC) Seventh Six-Month Status Report for the Implementation of Order EA-12-049, "Order to Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events"
- 1. Introduction WCNOC developed an Overall Integrated Plan (OIP) (Reference 1), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This attachment provides an update of milestone accomplishments since submittal of the OIP, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
- 2. Milestone Accomplishments As of August 01, 2016, the following milestones have been completed since the submittal of the last six-month status report (Reference 3).
- Submittal of the seventh six-month status report (this submittal)
- Procure On-Site FLEX Equipment.
- 3. Milestone Schedule Status The following provides an update to Attachment 2 of the OIP. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates and are subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the order implementation outage.
lt~licized text denotes that a Milestone was updated since the sixth six-month status update.
Revised Target Target Milestone Completion Activity Status Completion Date Date Submit 60-Day Status Report Oct 2012 Complete -
Submit Overall Integrated Plan Feb 2013 Complete -
Submit 6-Month Updates:
Update 1 Aug 2013 *Complete -
Update 2 Feb 2014 Complete -
Update 3 Aug 2014 Complete -
Update 4 Feb 2015 Complete -
Update 5 Aug 2015 Complete -
Update f3 Feb 2016 Complete -
Update 7 Aug 2016 Complete -
FLEX Strategy Evaluation Apr 2013 Complete -
Walk- Throughs or Demonstrations Sep 2014 On-Going Sep 2016
Attachment to ET 16-0018 Page 2 of 8 Revised Target Target Milestone Completion Activity Status Completion Date Date Perform Staffing Analysis Dec 2013 Complete -
Modifications:
Modifications Evaluation Apr2013 Complete -
N-1 Walkdown Apr 2014 Complete -
Design Engineering Jan 2014 Complete -
Condensate Storage Tank (CST)
Oct 2015 On-Going Oct 2016 Reinforcement - Design Engineering Implementation Outage Feb 2015 As Scheduled Sep 2016 FLEX Equipment:
Procure On-Site Equipment Dec 2014 Complete -
Develop Strategies with Regional Nov 2013 Complete -
Response Center (RRC)
Install Off-Site Delivery Station (if Sep 2014 On-Going Nov 2016 necessary)
Procedures:
Pressurized Water Reactor Owners Group (PWROG) issues NSSS- Jun 2013 Complete -
specific guidelines Create WCGS FLEX Support Jun 2014 Complete -
Guidelines (FSG)
Create Maintenance Procedures Jul2014 Started Oct 2016 Training:
Develop Training Plan Jul2014 Complete -
Training Complete Feb 2015 On-Going Sep 2016 Submit Completion Report* Mar 2015 Started Jan 2017
- The report will be submitted 90 days after the completion of Refueling Outage 21.
- 4. Changes to Compliance Method Since the submittal of Reference 3, WCNOC has completed an evaluation for compliance to NEI 12-06, Revision 2 (Reference 18) and will be in compliance upon completion of FLEX implementation activities.
- 5. Need for Relief/Relaxation and Basis for the Relief/Relaxation WCNOC requested (Reference 4) relaxation for the implementation of Order EA-12-049. The Wolf Creek Generating Station (WCGS) FLEX strategies rely on the low leakage Reactor Coolant Pump (RCP) seals and a seismic and missile protected Condensate Storage Tank
Attachment to ET 16-0018 Page 3 of 8.
(CST). Compliance with the original Order EA-12-049 schedule requirement for full completion and implementation of mitigation strategies would have resulted in hardship or unusual difficulty without a compensating increase in the level of safety.
An extension of one additional refueling cycle was requested in Reference 4. Reference 10 approved the relaxation of the order implementation date. This moves the implementation date to completion of the fall 2016 refueling outage, which is still within the maximum allowed timeframe of December 2016.
- 6. Open Items from Overall Integrated Plan and Interim Staff Evaluation The following table provides a summary of the open items documented in the OIP and the status of each item. Italicized text denotes that an Open Item was updated since the sixth six-month status update.
Open Overall Integrated Plan Open Item Status Item#
Finalize the location of the FLEX Closed - The locations of the two FLEX storage building. The deployment storage buildings have been selected.
routes, distances, and times provided Construction of both buildings has been in this report are bounded for the completed and the deployment routes currently proposed locations but will and distances have been confirmed.
011 be updated as necessary. The verification and validation process (Milestone: Walk-Throughs or Demonstrations) will confirm that deployment times are consistent with analysis values.
Perform containment evaluation, Closed - The Generation of Thermal using GOTHIC, based on the Hydraulic Information for Containment boundary conditions described in (GOTHIC) analysis has been completed.
Section 2 of NEI 12-06. Based on the The containment structure and 012 results of this evaluation, required instrumentation inside containment actions to ensure maintenance of critical to coping with an Extended Loss containment integrity and required of ac Power (ELAP) event are shown to instrument function will be developed. be acceptable following a 7-day duration (Reference 5).
Attachment to ET 16-0018 Page 4 of 8 Open Overall Integrated Plan Open Item Status Item#
The current CST and CST pipe chase Ongoing - An evaluation was performed are non-seismic. Therefore, WCNOC to show that the existing CST meets is currently pursuing two options; the current licensing basis for seismic and qualification and hardening of the tornado missile hazards (References 6, existing CST, or the construction of a 7, 8, and 9).
new 670, 000 gallon seismically Design Change Package (DCP) 14277 is qualified and missile protected CST.
being implemented to harden the CST by One of these options must be welding a layer of plating around the tank completed before the volume of the in order to withstand a Safe Shutdown CST can be credited.
Earthquake. Necessary modification work will be complete by the end of Refuel Outage 21.
013 The CST pipe chase has been evaluated and can withstand the current licensing basis for seismic and tornado missile hazards (Reference 12).
DCP 14864 is being implemented to harden the CST Valve House. The valve house will be replaced with a metal frame steel structure built to withstand missile hazards and Safe Shutdown Earthquake. Necessary modification work will be complete by the end of Refuel Outage 21.
Modify the RWST to protect it from Closed - Identified an alternate source tornado missiles or identify a borated strategy using the Boric Acid Tanks in source that is protected for tornados the Auxiliary Building as the primary 014 and can be utilized to provide core source and Refueling Water Storage cooling when steam generators are Tank (RWST) as the alternate source.
not available.
For non-Class 1E instrumentation that Closed - The final plant strategies do not will be repowered using a temporary rely on any equipment that is not 015 battery, an analysis will need to be powered by a Class 1E source.
performed to determine battery life and frequency of replacing battery.
Attachment to ET 16-0018 Page 5 of 8 The method for isolating Closed - It was confirmed that the accumulators during Reactor Coolant accumulator isolation valves are on a System [RCS] inventory control has bus that is being re-powered for the 016 not been finalized. primary electrical FLEX strategy.
For the alternate electrical FLEX strategy, nitrogen injection will be prevented by venting the accumulators.
The method for repowering the SFP Closed - Powering a Spent Fuel Pool cooling pumps has not been finalized. (SFP) cooling pump is a Phase 3 017 action. The pump will be re-powered by a 4160V generator provided by the RRC.
The following table provides a summary of the open items documented in the Interim Staff Evaluation Report (Reference 15) and the status of each item. Italicized text denotes that an Open lt~m was updated since the sixth six-month status update.
Open ISE Open Item Status Item#
Verify that the potential for Closed - A recent re-evaluation of the liquefaction considerations to impede WCNOC seismic Probabilistic Risk
-- movement of FLEX equipment Assessment (PRA) analysis has following a severe seismic event at confirmed that liquefaction is not an 3.1.1.2.A Wolf Creek are evaluated. issue on-site (References 16 and. 17).
Thus, there will be no liquefaction concerns for impeding the movement of FLEX equipment on-site following a severe seismic event.
Verify that power that might be Closed - The deployment of FLEX required to deploy equipment, such equipment will not require external 3.1.1,2.B as power to open roll up doors at a power. Equipment such as roll up doors storage location, is evaluated. will have provisions to be opened manually.
Verify resolution of the generic Closed - WCNOC will conform to the concern associated with the modeling position expressed by the NRC staff in
\ of the timing and uniformity of the the letter dated January 8, 2014 to the mixing of a liquid boric acid solution PWROG (Reference 13). The NRC injected into the RCS under natural letter states that the NRC staff has 3.2.1.8.A conditions potentially involving two- reviewed the information submitted to
. phase flow. date and concluded that use of the industry approach in PWROG letter OG-13-284 dated August 19, 2013, (Reference 14) is acceptable with clarifications listed in the letter.
Attachment to ET 16-0018 Page 6 of 8 Closed - The FLEX 500kW generator Verify that instrumentation that will be used to power 480 Vac Load Centers used to monitor portable/FLEX NG001 and NG002 are provided with electrical power equipment ensures complete protection. The generators that: 1) the electrical equipment built in voltage regulator provides voltage remains protected (from an electrical control and generator protection.
power standpoint- e.g., power Protection consists of but is not limited fluctuations) and, 2) the operator is to: Generator Over and Undervoltage, provided with accurate information to Loss of Excitation, Instantaneous Field maintain core cooling, containment, Overcurrent, Over Excitation and Under and spent fuel cooling strategies.
Frequency.
The FLEX 500kW generator also includes a separate Electronic Modular Control Panel (EMCP) 4.4 Generator Controller. This unit provides additional protection including but not limited to:
Generator phase sequence, Over/Under voltage (27159), Over/Under Frequency (81 O/U), Reverse power (32),
Overcurrent (50151), and Current Balance (46).
The protections from these two (2) mdependent devices are active at all times and prevent the generator set from 3.2.4.8.B generating power that fluctuates in amplitude or is low or high frequency.
The generic FLEX Support Guidelines (FSGs) developed via the PWROG contain sufficient guidance to control the plant using installed and/or portable FLEX equipment based on the requirement to monitor actual plant processes. The DRAFT FSGs conform to the requirements detailed in the generic FSGs by monitoring installed plant instruments required for FLEX coping via Draft EMG C-0, Loss of All AC Power- Attachment H, Assessment Of Vital Instruments.
Additionally, Draft Procedure EMG C-0 Attachment H directs initiation of FSG-l Loss Of Vital Instrumentation Or Controi Power, if minimum plant instruments are not available. Draft FSG-7 provides guidance for plant control when certain instruments are lost. FSG-7 also provides a primary and backup method for obtaining process readings using oortable instruments.
Attachment to ET 16-0018 Page 7 of 8 Verify the licensee has fully Closed - Our National SAFER Response addressed considerations (2) through Center (NSRC) playbook is complete (10) of NEI 12-06, Section 12.2, and was loaded onto the STARS E-Minimum Capability of Off-Site portal.
3.4.A Resources, which requires each site to establish a means to ensure the necessary resources will be available from off-site.
References
- 1. WCNOC Letter WO 13-0014, "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," February 28, 2013. ADAMS Accession No. ML13070A026.
- 2. Letter from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Issuance of Order to Modify Licenses with Regard to Requirements For Mitigation Strategies for Beyond-Design-Basis External Events," March 12, 2012. ADAMS Accession No. ML12054A735.
- 3. WCNOC Letter ET 16-0008, "Wolf Creek Nuclear Operating Corporation's Sixth 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'," February 17, 2016. ADAMS Accession No. ML16055A113.
- 4. WCNOC Letter WO 14-0023, "Request for Schedule Relaxation of NRC Order EA-12-049, Requirement IV.A.2, at Wolf Creek Generating Station," March 31, 2014. ADAMS Accession No. ML14097A072.
- 5. CN-OA-13-7, Revision 1, "Wolf Creek ELAP Containment Heat-Up," June 16, 2014.
- 6. 020542.13.01-C-001, Revision 0, "Condensate Storage Tank and Refueling Water Storage Tanks Tornado Missile Impact Analy~es," November 2013.
- 7. 020542.13.01-C-002, Revision 0, "Structural Analysis of Condensate Storage Tank,"
November 2013.
- 8. 020542.13.01-C-003, Revision 0, "Condensate Storage Tank Valve House and Refueling Water Storage Tank Valve House Missile Impact and Seismic Analysis," December 2013.
- 9. 020542.13.01-C-004, Revision 0, "Condensate Storage Tank Pipe Stress Analysis,"
December 2013.
Attachment to ET 16-0018 Page 8 of 8
- 10. Letter from E. J. Leeds, USN RC, to A. C. Heflin, WCNOC, "Wolf Creek Generating Station, Unit 1 - Relaxation of the Schedule Requirements for Order EA-12-049 'Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events'," May 20,
- 11. 020542.13.01-C-008, Revision 0, "Refueling Water Storage Tank Pipe Stress Analysis,"
December 2013.
- 12. 020542.13.01-C-009, Revision 0, "Condensate Storage Tank Pipe Tunnel Evaluation,"
December 2013.
- 13. Letter from J. Davis, USNRC, to N. J. Stringfellow, PWROG, January 8, 2013. ADAMS Accession No. ML13276A183.
- 14. PWROG Letter OG 13-284, "Submittal of LTR-FSE-13-46, Revision 0, P-Attachment, "Westinghouse Response to NRC Generic Request for Additional Information (RAI) on Boron Mixing in Support of the Pressurized Water Reactor Owners Group (PWROG)"
(Proprietary) (PA-ASC-1184)," August 19, 2013.
- 15. Letter from J. S. Bowen, USNRC, to A. C.- Heflin, WCNOC 1 "Wolf Creek Generating Station, Unit 1 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)(TAC NO. MF0788)," February 6, 2014.
ADAMS Accession No. ML14002A190.
- 16. GEi Consultants for Stevenson & Associates, "Liquefaction Evaluation - Power Block Structures Wolf Creek Nuclear Generating Station," July 9, 2015.
- 17. GEi Consultants for Stevenson & Associates, "Liquefaction Evaluation - ESW Pumphouse and Marine Discharge Structure Wolf Creek Nuclear Generating Station," July 15, 2015.
- 18. NEI 12-06, Revision 2, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," December 2015.