Letter Sequence Response to RAI |
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EPID:L-2019-LLA-0190, JAF-CALC-NBI-00206 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-58A,B and 02-3STU-259A,B) (Withdrawn, Closed) |
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MONTHYEARML19301A5052019-08-13013 August 2019 JAF-CALC-NBI-00205 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-57A,B and 02-3STU-258A,B) Project stage: Request ML19301A5042019-08-13013 August 2019 JAF-CALC-NBI-00206 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-58A,B and 02-3STU-259A,B) Project stage: Request ML19291A0352019-10-18018 October 2019 NRR E-mail Capture - FitzPatrick Supplemental Information Needed for Acceptance: Revise Allowable Value for Reactor Water Cleanup System Primary Containment Isolation Project stage: Other ML19302F8772019-11-0404 November 2019 Summary of the October 28, 2019, Meeting with Exelon Generation Company, LLC, Regarding a Planned Supplement to a License Amendment Request Regarding Revising the Allowable Value for Reactor Water Cleanup System Isolation Project stage: Meeting JAFP-19-0105, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...2019-11-0606 November 2019 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)... Project stage: Supplement ML19301A5022019-11-0707 November 2019 Draft Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Is ML19319C3582019-11-15015 November 2019 NRR E-mail Capture - Accepted for Review - FitzPatrick License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation Project stage: Acceptance Review ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation Project stage: RAI JAFP-20-0020, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-02-21021 February 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation Project stage: Response to RAI ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Project stage: RAI JAFP-20-0026, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-03-31031 March 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation Project stage: Response to RAI JAFP-20-0064, Withdrawal of License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-07-28028 July 2020 Withdrawal of License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation Project stage: Withdrawal ML20216A3742020-08-0505 August 2020 Letter with Withdrawal of an Amendment Request Project stage: Withdrawal 2019-08-13
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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARJAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. 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 NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21138A0132021-05-18018 May 2021 NRC Response to Request for Additional Time to Respond to James A. Fitzpatrick Nuclear Power Plant: Final Significance Determination of a White Finding with Assessment Follow Up and Notice of Violation-Inspection No. 05000333/2021090 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0008, Supplement to Application to Revise Surveillance Requirement (SR) 3.5.1.62021-02-18018 February 2021 Supplement to Application to Revise Surveillance Requirement (SR) 3.5.1.6 JAFP-21-0005, Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves2021-01-26026 January 2021 Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves ML20315A2452020-11-10010 November 2020 Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation Valves JAFP-20-0030, Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads2020-04-0606 April 2020 Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic Loads JAFP-20-0026, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-03-31031 March 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation JAFP-20-0020, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2020-02-21021 February 2020 Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation JAFP-20-0008, Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences2020-01-16016 January 2020 Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences JAFP-19-0105, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...2019-11-0606 November 2019 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)... ML19279A0012019-10-0606 October 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to the TS 3.8.1 Action ... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0009, End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval2019-01-15015 January 2019 End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0068, Response to Request for Additional Information: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2018-07-12012 July 2018 Response to Request for Additional Information: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-29029 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 JAFP-18-0038, Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-04-19019 April 2018 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 JAFP-18-0029, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of James A. FitzPatrick Nuclear Power Plant to Address Secondary Containment Personnel Access Door Openings2018-03-15015 March 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of James A. FitzPatrick Nuclear Power Plant to Address Secondary Containment Personnel Access Door Openings JAFP-18-0014, Response to Request for Additional Information on Submittal of Relief Request JAF-15R-05 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2018-03-0202 March 2018 Response to Request for Additional Information on Submittal of Relief Request JAF-15R-05 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 JAFP-18-0012, Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-22022 January 2018 Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17346A1532017-12-11011 December 2017 Submittal of Response to Request for Additional Information on Relief Requests Associated with the Fifth Inservice Inspection (ISI) Interval JAFP-17-0029, Revision to Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights...2017-04-27027 April 2017 Revision to Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights... JAFP-17-0005, Response to 03/12/2012 Request for Information Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident, Recommendation 9.3 for Emergency Preparedness2017-01-23023 January 2017 Response to 03/12/2012 Request for Information Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident, Recommendation 9.3 for Emergency Preparedness JAFP-16-0182, Spent Fuel Pool Evaluation, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-22022 December 2016 Spent Fuel Pool Evaluation, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16335A1042016-11-29029 November 2016 Independent Spent Fuel Storage Installation, Response to Request for Additional Information Regarding Application for Order Approving Transfer F Renewed Facility Operating License and Proposed Conforming License Amendment JAFP-16-0170, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies - Supplement 12016-11-21021 November 2016 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies - Supplement 1 JAFP-16-0165, Response to Generic Letter 2016-01 - Monitoring of Neutron Absorbing Materials in Spent Fuel Pools2016-11-0303 November 2016 Response to Generic Letter 2016-01 - Monitoring of Neutron Absorbing Materials in Spent Fuel Pools JAFP-16-0142, Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 22016-09-19019 September 2016 Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 2 JAFP-16-0131, Response to Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program2016-08-18018 August 2016 Response to Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program JAFP-16-0130, License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 22016-08-10010 August 2016 License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 2 JAFP-16-0113, License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 12016-07-0606 July 2016 License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 1 JAFP-16-0114, Response to Request for Additional Information for Proposed Inservice Inspection Program Alternative in Accordance with 10 CFR 50.55a(z)(2), RR-202016-06-27027 June 2016 Response to Request for Additional Information for Proposed Inservice Inspection Program Alternative in Accordance with 10 CFR 50.55a(z)(2), RR-20 JAFP-16-0077, Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 12016-06-0303 June 2016 Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 1 JAFP-16-0078, Response to Request for Additional Information (RAI) Regarding Request for Approval of Certified Fuel Handler Training and Retaining Program2016-06-0303 June 2016 Response to Request for Additional Information (RAI) Regarding Request for Approval of Certified Fuel Handler Training and Retaining Program CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 JAFP-15-0094, Response to Request for Additional Information for Expedited Seismic Evaluation Process Report2015-08-0404 August 2015 Response to Request for Additional Information for Expedited Seismic Evaluation Process Report 2022-06-16
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Exelon Generation ~ 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 JAFP-20-0020 February 21, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-059 NRC Docket No. 50-333
Subject:
Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU} System Primary Containment Isolation
References:
- 1. Letter from J. Barstow (Exelon Generation Company, LLC} to U.S. Nuclear Regulatory Commission (NRC}, License Amendment Request - Proposed Change to Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU} System Primary Containment Isolation, (ML192488085} dated September 5, 2019.
- 2. Email from NRC S. Lee, FitzPatrick Supplemental Information Needed for Acceptance: Revise Allowable Value for Reactor Water Cleanup System Primary Containment Isolation (EPID L-2019- LLA-0190), ML19291A035, dated October 18, 2019.
- 3. Letter from Exelon D. Gudger, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU} System Primary Containment Isolation. Letter dated November 6, 2019.
- 4. Email from NRC S. Lee, "FitzPatrick request for additional information:
License Amendment request for Change to the Technical Specifications to Revise the Allowable Value for Reactor water Cleanup (RWCU}
System Primary Containment Isolation" (EPID: L2019-LLA-0190}. Email dated January 23, 2020.
By letter dated September 5, 2019, (Reference 1} and supplemented by letter dated November 6, 2019, (Reference 3) Exelon Generation Company, LLC (Exelon) requested a change to the James A. FitzPatrick Nuclear Power Plant (JAF) Technical Specifications (TS) in accordance with 10 CFR 50.90. The proposed amendment
Response to RAI to Support Review of LAR to Revise RWCU Setpoint February 21, 2020 Page 2 request would revise the TS Allowable Value for Reactor Water Clean Up (RWCU) isolation on low Reactor Pressure Vessel (RPV) water level from Level 3 (<::177 inches) to Level 2 (~107 inches).
By electronic mail dated January 23, 2020 (Reference 4), the NRC identified areas where additional information was necessary. These additional RAls were discussed with the NRC Staff in a clarification call held on January 21, 2020, and it was agreed to a response by February 24, 2020.
Attachment to this letter contains the NRC's request for additional information immediately followed by Exelon's response.
Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1.
The information attached to this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.
Furthermore, the information attached to this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no new regulatory commitments contained in this response.
If you should have any questions regarding this submittal, please contact Enrique Villar at 610-765-5736.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21st day of February 2020.
Respectfully,
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David T. Gudger Senior Manager, Licensing Exelon Generation Company, LLC Attachments: Response to Request for Additional Information cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector- JAF NRC Project Manager, NRR - JAF A. L. Peterson, NYSERDA
ATTACHMENT Response to Request for Additional Information By letter dated September 5, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19248B085), as supplemented by letter dated November 6, 2019 (ADAMS Accession No. ML19310D579), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request (LAR) proposing changes to the technical specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF). The proposed changes revise the JAF TS Allowable Value for Reactor Water Cleanup (RWCU) System isolation on low Reactor Pressure Vessel (RPV) water level from Level 3 ( 177 inches) to Level 2 ( 107 inches) in Tables 3.3.6.1-1 and 3.3.5.2-1. The NRC staff has reviewed the LAR and determined that additional information is required to complete the review. The NRC staffs requests for additional information (RAIs) are listed below. These RAIs are in the human factors engineering areas. The staff may have additional RAIs in other review areas. A clarification call was held on January 21, 2020. The Exelon staff indicated that there was no proprietary or sensitive information. The Exelon staff requested, and NRC agreed, to a RAI response by February 24, 2020.
Human Factors Engineering RAI-IOLB-1 Title 10 of the Code of Federal Regulations (10 CFR), Section 50.34(f)(2)(iii) requires, in part, that the licensee or applicant provide, for Commission review, a control room design that reflects state-of-the-art human factor principles.
Chapter 18, "Human Factors Engineering," Revision 3, of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," provides guidance for the review of Human Factors Engineering (HFE) considerations of plant modifications and important human actions (HAs). Specifically,Section I, "Areas of Review,"
Subsection 5, "Important Human Actions," states, in part, that this document is used to review changes or modification to licenses for nuclear power plants that include or result in changes to human actions. An HFE review is also conducted if such a modification affects the role of personnel or the tasks they perform, the sequence of actions, the timing, or the overall workload, and is potentially significant to plant safety.
Provide additional information regarding whether the proposed change would result in any changes to the existing manual operator actions or introduce any new manual operator actions associated with the action to isolate Primary Containment. If there are any changes to the existing manual operator actions, describe the extent to which the changes affect personnel tasks, the sequence of actions, the amount of time required and/or available to perform such actions, and/or any impact on the operator workload.
Exelons Response to RAI-IOLB-1 The proposed change to revise the James A. FitzPatrick Nuclear Power Plant (JAF) Technical Specification (TS) Allowable Value for Reactor Water Cleanup (RWCU) system isolation on low Reactor Pressure Vessel (RPV) water level does not result in any changes to the existing manual operator actions and does not introduce any new manual operator actions associated with the action to isolate Primary Containment.
Attachment Response to Request for Additional Information Page 2 of 5 Existing Emergency Operating Procedures (EOP) require a Licensed Operator to verify system isolations occur as designed.
Specifically, for Reactor Water Clean Up (RWCU), a Licensed Operator will verify proper isolation of the system utilizing available control room instrumentation. If the RWCU system fails to isolate (on low RPV water level), the licensed operator will manually close, by switch from the Control Room, any RWCU isolation valve(s) that failed to close.
Furthermore, procedure for Operator Response Time Program at JAF does not include any time critical or time sensitive actions for verifying or manually isolating RWCU.
All other RWCU isolations setpoints remain the same.
RAI-IOLB-2 Section 50.34(f)(3)(i) of 10 CFR 50 requires that the licensee or applicant provide administrative procedures for evaluating operating, design, and construction experience and for ensuring that applicable important industry experiences will be provided in a timely manner to those designing and constructing the plant. NUREG-0711, "Human Factors Engineering," Revision 3, provides guidance for the staffs review of HFE programs, to ensure that HFE practices and guidelines were appropriately considered and incorporated in the plant design and modifications. NUREG-0711, Review Element 3, "Operating Experience Review," provides guidance for the NRC staffs evaluation of the operating experience review (OER) that would be performed by a licensee, as part of the HFE program, to identify HFE-related safety issues. Section 3.4, "Review Criteria," states, in part, that the applicants OER should include information about relevant human factors issues in the predecessor plant(s) or highly similar plants, systems, and human-system interfaces (HSIs), recognized industry HFE issues, related HSI technology, issues identified by plant personnel, and important HAs. Further, Section 3.4.3, "Plant Modifications," states that, in addition to other considerations, the applicants OER should provide information on the plants systems, HSIs, procedures, or training that are being modified, and account for the operating experience of the plant that will be modified, including experiences with the systems that will be changed.
Provide additional information regarding the OER that was performed by Exelon, as it relates to the proposed change revising the JAF TS Allowable Value for RWCU System isolation on low RPV water level from Level 3 to Level 2. In your response, describe whether the review identified any human performance issues associated with the existing procedural guidance, training, and any human performance issues associated with the operator actions required for RWCU System isolation, by reviewing operating experience at JAF and applicable industry experience, as appropriate.
Exelons Response to RAI-IOLB-2 A JAF and industry operating experience review was conducted on RWCU isolations to identify any lessons learned for human performance issues associated with existing procedural guidance, training, and any human performance issues associated with operator actions required for RWCU system isolation.
Attachment Response to Request for Additional Information Page 3 of 5 Operating experience review at JAF identified three (3) events, which resulted in either a manual or automatic RWCU system isolation. In December 2012, operators manually isolated RWCU due to rising temperatures and local report of a steam leak in the RWCU Heat Exchanger Room. In December 2011, operators removed RWCU system from service in order to repair a cracked pipe upstream of 12MOV-68. And finally, in March 2007, the RWCU system automatically isolated due to a seal failure on "B" RWCU pump. No procedural, training, equipment or human performance issues were noted with the review of these events.
Several industry operating experience events reviewed included inadvertent RWCU isolations caused by human performance errors or equipment challenges. For example, on May 27, 2018, at Fermi Unit 2, an inadvertent RWCU isolation occurred when a RWCU system flow differential flow indicator failed downscale. At JAF, RWCU does not have a differential flow isolation signal.
On June 29, 2019, at Cooper Nuclear Power Station, an inadvertent RWCU isolation occurred due to the failure of a temperature switch. On April 11, 2014, at Brunswick Unit 2, a RWCU isolation occurred when a jumper was inadvertently removed during surveillance testing.
The operating experience did not identify any instances of a failure of RWCU to isolate either manually or automatically at JAF or other nuclear power plants.
The operating experience review did not identify any further lessons learned on human performance issues associated with existing procedural guidance, training, and any human performance issues associated with operator actions required for RWCU system isolation.
RAI-IOLB-3 Title 10 of the Code of Federal Regulations (10 CFR), Section 50.34(f)(2)(iii) requires, in part, that the licensee or applicant provide, for Commission review, a control room design that reflects state-of-the-art human factor principles. NUREG-0711, "Human Factors Engineering,"
Revision 3, provides guidance for the staffs review of HFE programs, to ensure that HFE practices and guidelines were appropriately considered and incorporated in the plant design and modifications.
a) NUREG-0711, Review Element 9, Procedure Development, provides guidance for the staffs evaluation of the licensees procedure development program. Section 9.4, Review Criteria, states, in part, that the licensee should have a plan for maintaining procedures and controlling updates. It further states that procedure modifications should be integrated across the full set of procedures and that changes in particular parts of the procedures should not conflict with other parts nor be inconsistent with them.
Provide additional information describing the impact, if any, that the proposed change will have on plant procedures, including any affected emergency operating procedures, plant and system operations, abnormal and emergency operations, and alarm response.
In your response, identify the affected procedures and describe the scope of changes those documents.
Exelons Response to RAI-IOLB-3 a)
As stated in response to RAI-IOLB-1, the proposed change to revise the JAF TS Allowable Value for RWCU System isolation on low RPV water level does not result in any changes to the existing manual operator actions and does not introduce any new manual operator actions associated with the action to isolate Primary Containment.
Attachment Response to Request for Additional Information Page 4 of 5 The only changes required by this License amendment involve changes that are necessary to update those procedure with the new TS Allowable Value for RWCU System isolation on low RPV level.
However, since the RWCU system will now isolate at a lower setpoint, the AOP-15 Follow Up actions for Group 2 system restoration will require minor changes to remove the RWCU isolation reset and system restoration and make it a standalone procedure section.
Additionally, Operating Procedure for RWCU, OP-28, requires minor changes to update the system description section and a procedure section for Recovery from Manual or Automatic Isolation with the new RPV water level isolation setpoint. However, the specific operator actions for manual and automatic isolation and recovery remain unchanged.
The Annunciator Response Procedures (ARP) do not require any changes.
b) NUREG-0711, Review Element 10, "Training Program Development," provides guidance for the staffs evaluation of the licensees training program. Section 10.4.6, "Evaluation and Modification of Training," states, in part, that the licensee should define the methods for verifying the accuracy and completeness of the training course materials. It further states that the licensee should establish procedures for refining and updating the content and conduct of training, including procedures for tracking modifications in the training courses.
c)
Provide additional information describing the impact, if any, that the proposed change will have on Exelons training program for licensed and non-licensed personnel.
Exelons Response to RAI-IOLB-3 b)
The overall learning objectives for licensed and non-licensed personnel, purpose, function, and operation of RWCU System components remain unchanged as a result of the proposed change to revise the JAF TS Allowable Value for RWCU system isolation on low RPV water level.
Non-Licensed Operators are currently trained on the RWCU isolation function on low RPV water level. The specific level setpoint is not an enabling objective in the Non-Licensed Operators training.
Licensed Operators are also trained on the RWCU isolation function, including the specific setpoint at which it occurs. The new low RPV water level setpoint is an enabling objective in the License Operator training; and therefore, the RWCU lesson plan will require a minor update to incorporate the new RWCU isolation setpoint.
d) NUREG-0711, Review Element 11, "Human Factors Verification and Validation,"
provides guidance for the staffs evaluation of the verification and validation (V&V) activities, which comprehensively determine that the HFE design conforms to HFE design principles and that it enables plant personnel to successfully perform their tasks to assure plant safety and operational goals. Section 11.4.3, "Integrated System Validation," states, in part, that the objective of the Integrated System Validation (ISV) review is to verify that the applicant validated, using performance-based tests, that the integrated system design supports the safe operation of the plant.
Attachment Response to Request for Additional Information Page 5 of 5 Provide additional information regarding the V&V activities that have been, or will be conducted to provide reasonable assurance that following the implementation of the proposed changes, operator actions required for RWCU System isolation can continue to be performed safely and reliably within the established time and performance criteria, with effective situational awareness, and acceptable workload levels. In your response, provide information that addresses the applicable criteria described in Section 11.4.3 of NUREG-0711.
Exelons Response to RAI-IOLB-3 c)
The specific minor procedure revisions for AOP-15 and OP-28 have not been drafted to date.
Once the procedures are drafted, they will be evaluated in accordance with Exelon established process, which includes an evaluation of the Consequence Risk Factors.
If High or Medium Risk Factors exist, then procedure validation is required, and the methods of validation may include Mockup / Simulator, Field Walkdown, and Benchtop Review.