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MONTHYEARJAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-10-0202 October 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 Project stage: Request 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 Project stage: Supplement ML18085A6912018-03-23023 March 2018 NRR E-mail Capture - Draft Request for Information (RAI) for JAFNPP Traveler TSTF-542, RPV Water Inventory Control Project stage: Draft RAI ML18085A6922018-03-26026 March 2018 NRR E-mail Capture - James A. FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542, RPV Water Inventory Control Project stage: RAI 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 Project stage: Response to RAI ML18194A8822018-08-24024 August 2018 Issuance of Amendment No. 321 Re: Revision to Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control (EPID L-2017-LLA-0311) Project stage: Approval 2018-03-23
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Category:Letter type:JAFP
MONTHYEARJAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for 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-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-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-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 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-23-0047, 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 2024-09-25
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARJAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24085A2362024-03-25025 March 2024 Response to Request for Additional Information JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis 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.. 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) 2024-08-09
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200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.90 JAFP-18-0038 April 19, 2018 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-59 NRC Docket No. 50-333
Subject:
Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2 (EPID: L-2017-LLA-0311)
References:
- 1. Letter from James Barstow (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2," JAFP-19-0093, dated October 2, 2017 (ML17275A520)
- 2. Electronic mail from R. Haskell II, U.S. Nuclear Regulatory Commission, to Christian Williams, Exelon Generation Company, LLC, "James A.
FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542 RPV Water Inventory Control (EPID: L-2017-LLA-0311), dated March 26, 2018 (ML18085A692)
By letter dated October 2, 2017 (ADAMS Accession No. ML17275A520) (Reference 1),
Exelon Generation Company, LLC (Exelon), requested approval to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2, which changes the Technical Specifications (TSs) for James A. FitzPatrick Nuclear Power Plant (JAFNPP).
The NRC staff reviewed the information provided that supports the proposed amendment and identified the need for additional information in order to complete their evaluation of the amendment request. The request for additional information (RAI) was sent from the NRC to Exelon by electronic mail on March 26, 2018 (Reference 2). The NRC requested a response by April 23, 2018. to this letter provides a restatement of the RAI question followed by our response. Attachment 2 provides the revised TS markup as a result of the RAI. In addition to responding to this RAI Exelon is providing corrected marked up TS pages to address markup discrepancies identified during the review. A summary of the discrepancies is included in Attachment 3 and the corrected TS pages are included in Attachment 4.
U.S. Nuclear Regulatory Commission Response to Request for Additional Information Application to Revise TS to Adopt TSTF-542 Docket No. 50-333 April 19, 2018 Page2 Exelon has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of the Reference 1 letter. Exelon has concluded that the information provided in this response does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition , Exelon has concluded that the information in this response 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 in this response.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), Exelon is notifying the State of New York of this RAI response by transmitting a copy of this letter and its attachments to the designated State Official.
If you have any questions or require additional information, please contact Christian Williams at 610-765-5729.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 191h day of April 2018.
Respectfully,
~*~ 'J T j_.. Jr--
David T. Gudger Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments:
- 1. Response to Request for Additional Information
- 2. Revised Markup of Proposed Technical Specification Page 3.3.5.2-2
- 3. Summary of Additional Markup Discrepancies and Corrections
- 4. Revised Markup of Technical Specifications Pages 3.5.2-1 thru 3.5.2-4 and 3.5.2-6 cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector- JAFNPP NRC Project Manager, NRR - JAFNPP NYSPSC NYSE RDA
JAFP-18-0038 ATTACHMENT 1 Response to Request for Additional Information
Response to Request for Additional Information Attachment 1 Application to Revise TS to Adopt TSTF-542 Page 1 of 1 Docket No. 50-333 By letter dated October 2, 2017 (ADAMS Accession No. ML17275A520), Exelon Generation Company, LLC (Exelon), requested approval to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2, which changes the Technical Specifications (TSs) for James A. FitzPatrick Nuclear Power Plant (JAFNPP).
The NRC staff reviewed the information provided that supports the proposed amendment and identified the need for additional information in order to complete their evaluation of the amendment request. The request for additional information (RAI) was sent from the NRC to Exelon by electronic mail message on March 26, 2018. Below is a restatement of the question followed by our response.
Question 1 (JAFNPP-RAI-01):
Background:
In Attachment 1 (of the LAR), for Variation 2.2.6, the licensee states that Surveillance Requirement (SR) SR 3.3.5.2.3, Perform LOGIC SYSTEM FUNCTIONAL TEST, is not applicable because the manual initiation logic does not exist in the JAFNPP design. However, in Attachment 2 (of the LAR), on proposed TS markup page 3.3.5.2-2, SR 3.3.5.2.3 was included. Furthermore, proposed TS Table 3.3.5.2-1, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation, has no reference to SR 3.3.5.2.3.
Request:
Since this appears to indicate the proposed markups for the SR (page 3.3.5.2-2) and TS Table 3.3.5.2-1 (page 3.3.5.2-3) do not align, either provide clarification or correct the proposed TS markup page(s) as appropriate.
Response
SR 3.3.5.2.3 was included in error on page 3.3.5.2-2. SR 3.3.5.2.3 has been removed from page 3.3.5.2-2. See revised TS markup (Attachment 2).
References:
- 1. Letter from James Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2," dated October 2, 2017 (ML17275A520).
- 2. Electronic mail from R. Haskell II, U.S. Nuclear Regulatory Commission, to Christian Williams, Exelon Generation Company, LLC, "James A. FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542 RPV Water Inventory Control (EPID: L-2017-LLA-0311) dated March 26, 2018 (ML18085A692)
JAFP-18-0038 ATTACHMENT 2 Revised Markup of Proposed Technical Specifications Page 3.3.5.2-2 TS Page 3.3.5.2-2
RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Declare associated low Immediately associated Completion pressure ECCS Time of Condition C or D injection/spray subsystem not met. inoperable.
SURVEILLANCE REQUIREMENTS
NOTE-----------------------------------------------------------
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program JAFNPP 3.3.5.2-2 Amendment XXX
JAFP-18-0038 ATTACHMENT 3 Summary of Additional Markup Discrepancies and Corrections
Response to Request for Additional Information Attachment 3 Application to Revise TS to Adopt TSTF-542 Page 1 of 1 Docket Nos. 50-333 The following discrepancies were identified during the review of the markup pages for TS 3.5.2:
DISCREPANCY 1 (pg 3.5.2-1): In Attachment 2 of Reference 1, in the LCO 3.5.2 statement, the greater than or equal to symbol (>) and the TS Logical Connector term AND both include strikeouts (crossed out).
CORRECTION 1: Neither the symbol nor the logical connector should have been crossed out.
The strikeouts have been removed.
DISCREPANCY 2 (pg 3.5.2-2): The proposed markup for CONDITION C does not conform with the Traveler TSTF-542, Rev. 2. CONDITION C states, DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and > 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while the Traveler TSTF-542, Revision 2, states DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
CORRECTION 2: CONDITION C on the markup has been revised to be consistent with the TSTF-542 traveler as follows: DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> DISCREPANCY 3 (pg 3.5.2-2): The proposed markup for the TS Logical Connector term AND, located between REQUIRED ACTIONs C.2 and C.3, includes strikeout.
CORRECTION 3: This term should NOT have been crossed out. The strikeout has been removed.
DISCREPANCY 4 (pg 3.5.2-2): The proposed markup for REQUIRED ACTION C.3 states, Verify one standby gas treatment subsystem is capable of operation in less than the DRAIN TIME. Versus the Traveler TSTF-542, Revision 2, which states, Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
CORRECTION 4: REQUIRED ACTION C.3 on the markup has been revised to be consistent with the TSTF-542 traveler as follows: Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
DISCREPANCY 5 (pg 3.5.2-3): The proposed markup for REQUIRED ACTION D.1 includes a strikeout in the symbol for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
CORRECTION 5: The symbol should NOT have been crossed out. The strikeout has been removed.
DISCREPANCY 6 (pg 3.5.2-4): The proposed markup for CONDITION E includes a strikeout in the TS Logical Connector term OR. Additionally, for REQUIRED ACTION E.1 the DRAIN TIME requirement includes the > symbol vs. > for the 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> parameter.
CORRECTION 6: The symbol should NOT have been crossed out. The strikeout has been removed.
DISCREPANCY 7 (pg 3.5.2-4): The proposed markup for SR 3.5.2.1 includes the > symbol vs.
> for the 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> parameter.
CORRECTION 7: SR 3.5.2.1 should be > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. This has been corrected in the attached markup.
DISCREPANCY 8 (pg 3.5.2-6): The proposed markup for SR 3.5.2.6 includes a strikeout for the symbol.
CORRECTION 8: The symbol should NOT have been crossed out. The strikeout has been removed.
JAFP-18-0038 ATTACHMENT 4 Revised Markup of Technical Specifications Pages 3.5.2-1 thru 3.5.2-4 and 3.5.2-6 TS Pages 3.5.2-1 3.5.2-2 3.5.2-3 3.5.2-4 3.5.2-6
ECCS - ShutdownRPV Water Inventory Control 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS - ShutdownReactor Pressure Vessel (RPV) Water Inventory Control LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> AND One Two low pressure ECCS injection/spray subsystems shall be OPERABLE.
- - - - - - - - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - -
A Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY: MODES 4, and 5 MODE 5, except with the spent fuel storage pool gates removed and water level 22 ft 2 inches over the top of the reactor pressure vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rRequired low A.1 Restore required low 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> pressure ECCS pressure ECCS injection/spray injection/spray subsystem inoperable. subsystem to OPERABLE status.
B. Required Action and B.1 Initiate action to Immediately associated Completion establish a method of Time of Condition A water injection capable not met. of operating without offsite electrical power.suspend operations with a potential for draining the reactor vessel (OPDRVs).
JAFNPP 3.5.2-1 Amendment 274XXX
ECCS - ShutdownRPV Water Inventory Control 3.5.2 C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.1 Verify secondary Immediately4 hours and > 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Two containment boundary is required low capable of being pressure ECCS established in less than injection/spray the DRAIN TIMEInitiate subsystems inoperable. action to suspend C. OPDRVs.
AND (continued)
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2 Verify each secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> containment penetration flow path is capable of being isolated in less than the DRAIN TIME.Restore one required low pressure ECCS injection/spray subsystem to OPERBLE status.
AND C.3 Verify one standby gas 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> treatment subsystem is capable of being placed in operation in less than the DRAIN TIME (continued)
JAFNPP 3.5.2-2 Amendment 274XXX
ECCS - ShutdownRPV Water Inventory Control 3.5.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 ---------NOTE------------ Immediately associated Completion Required ECCS Time not met.DRAIN TIME injection/spray subsystem
< 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or additional method of water injection shall be capable of operating without offsite electrical power.
Initiate action to restore secondary containment to OPERABLE status.establish an additional method of water injection with water sources capable of maintaining RPV water level
> TAF for > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
AND D.2 Initiate action to establish Immediately secondary containment boundary restore one standby gas treatment subsystem to OPERABLE status.
AND D.3 Initiate action to isolate Immediately each secondary containment penetration flow path or verify it can be manually isolated from the control room.restore Isolation capability in each required secondary containment penetration flow path not isolated.
AND D.4 Initiate action to verify one Immediately standby gas treatment JAFNPP 3.5.2-32 Amendment XXX
ECCS - ShutdownRPV Water Inventory Control 3.5.2 subsystem is capable of being placed in operation E. Required Action and E.1 Initiate action to restore Immediately associated Completion DRAIN TIME to > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Time of Condition C or D not met.
OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SURVEILLANCE REQUIREMENTS SURVELLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> In accordance with the Surveillance Frequency Control Program SR 3.5.2.21 Verify, for each a required low pressure coolant injection In accordance with (LPCI) subsystem, the suppression pool water level is the Surveillance 10.33 ft. Frequency Control Program (continued)
JAFNPP 3.5.2-42 Amendment XXX
ECCS - ShutdownRPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVELLANCE FREQUENCY SR 3.5.2.65 Operate the required ECCS injection/spray subsystem In accordance with through the recirculation line for > 10 minutesVerify the Inservice Testing each required ECCS pump develops the ProgramSurveillance specified flow rate against a system head Frequency Control Program corresponding to the specified reactor pressure above primary containment pressure.
SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE NO. ABOVE PRIMARY OF CONTAINMENT SYSTEM FLOW RATE PUMPS PRESSURE OF CS 4265 gpm 1 113 psi LPCI 7700 gpm 1 20 psi SR 3.5.2.7 Verify each valve credited for automatically In accordance with isolating a penetration flow path actuates to the the Surveillance isolation position on an actual or simulated isolation Frequency Control signal. Program SR 3.5.2.86 - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - -
Vessel injection/spray may be excluded.
Verify each the required ECCS injection/spray subsystem In accordance with can be manually operated. actuates on an actual or the Surveillance simulated automatic Frequency Control initiation signal. Program JAFNPP 3.5.2-62 Amendment XXX