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MONTHYEARJAFP-15-0133, Notification of Permanent Cessation of Power Operations2015-11-18018 November 2015 Notification of Permanent Cessation of Power Operations Project stage: Request JAFP-15-0142, Request for Approval of a Certified Fuel Handler Training and Retraining Program2016-01-15015 January 2016 Request for Approval of a Certified Fuel Handler Training and Retraining Program Project stage: Request JAFP-15-0143, License Amendment Request Revision to Technical Specification Administrative Controls for Permanently Defueled Condition2016-01-15015 January 2016 License Amendment Request Revision to Technical Specification Administrative Controls for Permanently Defueled Condition Project stage: Request ML16035A3092016-02-0404 February 2016 License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition Project stage: Other JAFP-16-0012, Attachments 1 - 6: License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition2016-02-0404 February 2016 Attachments 1 - 6: License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition Project stage: Request 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 Project stage: Response to RAI 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 Project stage: Supplement 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 Project stage: Supplement 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 Project stage: Supplement 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 Project stage: Response to RAI 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 Project stage: Supplement ML16259A3472016-10-17017 October 2016 Approval of the Certified Fuel Handler Training and Retraining Program Project stage: Other JAFP-17-0004, Withdrawal of License Amendment Request to Revise Technical Specifications Administrative Controls and Request to Revise Emergency Plan to Address the Permanently Defuel Condition (CAC No. MF7280 & MF7347)2017-01-13013 January 2017 Withdrawal of License Amendment Request to Revise Technical Specifications Administrative Controls and Request to Revise Emergency Plan to Address the Permanently Defuel Condition (CAC No. MF7280 & MF7347) Project stage: Withdrawal PNP 2017-010, Program Approval - Certified Fuel Handler Training and Retraining Program2017-03-28028 March 2017 Program Approval - Certified Fuel Handler Training and Retraining Program Project stage: Other 2016-07-06
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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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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Brian R. Sullivan Site Vice President - JAF JAFP-16-0078 June 3, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Response to Request for Additional Information (RAI) Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program (CAC No. MF7282)
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
References:
- 1. Entergy letter, Notification of Permanent Cessation of Power Operations, JAFP-15-0133, dated November 18, 2015 (ML15322A273)
- 2. Entergy letter, Certification of Permanent Cessation of Power Operations, JAFP-16-0045, dated March 16, 2016 (ML16076A391)
- 3. Entergy Letter, Request for Approval of a Certified Fuel Handler Training and Retraining Program, JAFP-15-0142, dated January 15, 2016 (ML16015A455)
- 4. NRC correspondence, Request for Additional Information (RAI)
Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program, (ML16109A255; CAC No. MF7282), dated April 7, 2016
- 5. Entergy letter, License Amendment Request - Revision to Technical Specification Administrative Controls for Permanently Defueled Condition, JAFP-15-0143, dated January 15, 2016 (ML16015A456)
- 6. Entergy letter, 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-16-0077, dated June 3, 2016 (CAC No. MF7280)
On November 18, 2015, Entergy Nuclear Operations, Inc. (ENOI) provided formal notification to the Nuclear Regulatory Commission (NRC) of its intention to permanently cease power operations of James A. FitzPatrick Nuclear Power Plant (JAF) at the end of the current operating cycle [Reference 1]. On March 16, 2016, ENOI certified, pursuant to 10 CFR 50.82(a)(1)(i), that JAF would be permanently shut down on January 27, 2017 [Reference 2].
JAFP-16-0078 Page 2 of 2 By letter dated January 15, 2016 [Reference 3], ENOI requested approval of the Certified Fuel Handler Training and Retraining Program, which is needed to provide training to personnel who will facilitate activities associated with decommissioning and irradiated fuel handling and management. In processing the submittal, the NRC determined that additional information was required to complete the review [Reference 4]. The specific questions provided to JAF in the NRC request for additional information (RAI) are addressed in the attachment to this letter.
Note that the ENOl license amendment request regarding revision to Technical Specification Administrative Controls [Reference 5], and the respective RAI response [Reference 6], are topical to this transmittal.
There are no new regulatory commitments in this submittal. Should you have any questions please contact Mr. William C. Drews at 315-349-6562.
Sincerely, Brian R. Sullivan Site Vice President BRS/WCD/ds Attachments: 1. Response to Request for Additional Information cc: NRC Region 1 Administrator NRC NRR Project Manager NRC Resident Inspector NYSPSC NYSE RDA
JAFP-16-0078 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (6 Pages)
JAFP-16-0078 Attachment 1 Response to Request for Additional Information REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING REQUEST FOR APPROVAL OF A CERTIFIED FUEL HANDLER TRAINING AND RETRAINING PROGRAM JAMES A. FITZPATRICK NUCLEAR POWER PLANT ENTERGY NUCLEAR OPERATIONS, INC DOCKET NO. 50-333 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 By letter dated January 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16015A455), Entergy Nuclear Operations, Inc. (ENO or the licensee) submitted a request for U. S. Nuclear Regulatory Commission (NRC) approval of the James. A FitzPatrick (JAF) Certified Fuel Handler (CFH) Training and Retraining Program, pursuant to the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.2. On March 16, 2016, pursuant to 10 CFR 50.82(a)(1)(i), ENO provided a formal notification to the NRC of its intention to permanently cease power operations of JAF on January 27, 2017 (ADAMS Accession Number ML16076A391). Upon permanent cessation of operations and permanent removal of fuel from the reactor vessel, licensed senior reactor operators and reactor operators will no longer be required to support plant operating activities. Therefore, ENO is requesting approval of the CFH Training and Retraining Program, which is needed to provide training to personnel who will facilitate activities associated with decommissioning and irradiated fuel handling and management.
The NRC staff has determined that additional information is needed to continue the review as discussed below.
RAI-1 Title 10 of the Code of Federal Regulations (CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Section 50.120, Training and qualification of nuclear power plant personnel, states, in part: (b)(3) The training program must be periodically evaluated and revised as appropriate to reflect industry experience as well as changes to the facility, procedures, regulations, and quality assurance requirements.
Provide additional information regarding how the James A. FitzPatrick Nuclear Power Plant (JAF) Certified Fuel Handler (CFH) Training and Retraining Program provides for periodic evaluation and incorporation of changes to the program, as appropriate, to reflect industry experience, changes to the facility, procedures, regulations, and quality assurance requirements.
Response
As described in Section 1.3 of the JAF CFH Training and Retraining Program (CFH Program),
assessments of the effectiveness and accuracy of training are conducted by appropriate management personnel during and at the end of each two (2) year training cycle. Implementing program documents have yet to be finalized for the JAF CFH Program; however, ENOI will ensure that the JAF CFH Training and Retraining Program contains the guidance necessary to ensure compliance with the requirements of the systems approach to training (SAT) process in 10 CFR 50.120(b)(3). Specifically, the final approved CFH Program will provide for periodic evaluation and incorporation of changes to the program, as appropriate, to reflect industry experience, changes to the facility, procedures, regulations, and quality assurance requirements.
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JAFP-16-0078 Attachment 1 Response to Request for Additional Information RAI-2 The following questions apply to Section 1, Introduction, of the JAF CFH Training and Retraining Program:
- a. First paragraph on page 1 of the document refers to the training program to be implemented by the licensees.
Clarify if the licensees is in reference to JAF.
Response
Licensees refers to the holders of Renewed Facility Operating License No. DPR-059; ENOI and Entergy Nuclear FitzPatrick, LLC (ENF).
- b. Second paragraph on page 1 of the document states, in part: The program shall comply with facility Technical Specifications Further, the same paragraph states, in part: candidates in the training program shall meet minimum applicable operator experience requirements of the facility Technical Specifications. Changes to this program may be made <>
provided the program continues to comply with the Technical Specifications.
Provide additional information regarding which Technical Specifications are being referred to in the above mentioned paragraph. In your response, clarify why the CFH Training and Retraining Program does not explicitly reference American National Standards Institute (ANSI)/American Nuclear Society (ANS) 3.1-1978, American National Standard for Selection and Training of Nuclear Power Plant Personnel, which is referenced in the current JAF Technical Specifications (TS) 5.3, Plant Staff Qualifications.
Response
The abovementioned paragraph refers to JAF Technical Specification 5.3, Plant Staff Qualifications.
A generic reference to the TS is used in the CFH Program to avoid conflicts that may arise in the future if either TS 5.3.1 or 5.3.2 (as proposed in Reference 1) are revised or renumbered by a subsequent license amendment. For similar reasons, a specific reference to ANSI/ANS 3.1-1978 is not included in the CFH Program in the event that either the version of ANSI/ANS 3.1 applicable to JAF is changed by a future license amendment or exceptions to ANSI/ANS 3.1-1978 are added to, or removed from, the Quality Assurance Program Manual (QAPM). A generic reference to the TS in the CFH Program will therefore minimize the number of administrative revisions needed to maintain alignment with the TS and/or QAPM.
ENOI has administrative controls in place to ensure that potential impacts to training program documents are identified whenever changes to the JAF licensing basis, such as the TS or QAPM, are proposed.
Note that in Reference 1, ENOI proposed to revise the title of TS 5.3 to, Facility Staff Qualifications.
- c. Third paragraph, item 2 on page 1 of the document states, in part: If required, amendment to the facility license Clarify if the facility license is in reference to the JAF license. Further, clarify the reason for including the if required statement, considering the fact that Entergy Nuclear Operations (ENO) has already submitted a license Page 2 of 6
JAFP-16-0078 Attachment 1 Response to Request for Additional Information amendment request (LAR) for the NRC staffs review, proposing changes to the staffing and training requirements for JAF staff contained in Section 5.0, Administrative Controls, of the JAF TS, by letter dated January 15, 2016 (ADAMS Accession Number ML16015A456).
Response
The phrase facility license is in reference to Renewed Facility Operating License No. DPR-059. JAF TS 5.3.2 currently references requirements for NRC Licensed Senior Reactor Operators and Reactor Operators and 10 CFR 55. As discussed in Reference 1, TS 5.3.2 is proposed to be revised to replace the current language with a reference to the JAF CFH Training and Retraining Program. Although the JAF CFH Program may be approved by the NRC at any time, ENOI does not plan to fully implement the CFH Program until Reference 1 is approved and effective, which cannot occur sooner than the docketing of the certifications of permanent cessation of operations and permanent removal of fuel from the reactor vessel, pursuant to 10 CFR 50.82(a)(1).
- d. First paragraph on page 2 of the document states, in part: Such exemptions, including the basis, shall be documented. (Note that the same statement also appears in Section 1.1, Initial Training Program, subsection Exemption from Training Requirements, on page 3 of the document, and in Section 1.2, Retraining Program, subsection Exemption of Maintenance of Qualification Requirements, on page 7 of the document.)
Provide additional information regarding what process (or procedure) will be used for documenting exemptions from training requirements.
Response
Exemptions from training requirements, including the basis, shall be documented using a process similar to Entergy fleet training procedure EN-TQ-212, Conduct of Training and Qualification. Although the JAF CFH Training and Retraining Program documents have not been finalized, draft procedural requirements provide guidance on the exemption process and the form to be used. The draft procedure outlines the following criteria to be evaluated in consideration of any exemption/alternate qualifications:
Previous training, education, and experience records Knowledge based examination Skill based examination
- e. Clarify if the JAF CFH Training and Retraining Program adheres to the guidelines of NUREG-1220, Training Review Criteria and Procedures, Revision 1. If there are deviations from the guidance provided in NUREG-1220, Revision 1, describe how the training program complies with the requirements for systems approach to training (SAT)-based training.
Response
Although the JAF CFH Training and Retraining Program documents have not been finalized, the program will adhere to the guidelines of NUREG-1220, "Training Review Criteria and Procedures," Revision 1 that are applicable to a permanently defueled facility.
Procedure EN-TQ-201, Systematic Approach to Training Process, defines the requirements for the fleet to maintain a systematic approach to training. The JAF Page 3 of 6
JAFP-16-0078 Attachment 1 Response to Request for Additional Information CFH Training and Retraining Program will align with the provisions of 10 CFR 50.120 and 10 CFR 55.4 for SAT. The five key elements for a SAT are:
- 1. Systematic analysis of the jobs to be performed.
- 2. Learning objectives derived from the analyses which describe desired performance after training.
- 3. Training design and implementation based on the learning objectives.
- 4. Evaluation of trainee mastery of the objectives during training.
- 5. Evaluation and revision of the training based on the performance of trained personnel in the job setting.
RAI-3 The following questions apply to Section 1.1, Initial Training Program, of the JAF CFH Training and Retraining Program:
- a. Subsection Eligibility Requirements states, in part: Candidates for enrollment in the Certified Fuel Handler initial training program shall meet the applicable requirements of the facility Technical Specifications.
Provide additional information regarding which Technical Specifications are being referred to in the above statement. In your response, clarify what minimum education, experience, and other requirements a candidate for enrollment in the CFH initial training program has to meet.
Response
The above statement is in reference to JAF TS 5.3.1. The minimum education, experience, and other requirements a candidate for enrollment in the JAF CFH Program must meet are as follows (Reference ANSI/ANS 3.1-1978 Section 4.5.1):
- 1. High school diploma or equivalent
- 2. Two (2) years of power plant experience
- 3. One year of nuclear power plant experience; at least six (6) months of which shall be at JAF
- 4. Possess a high degree of manual dexterity and mature judgment
- b. Subsection Examination states, in part: Critical tasks for a JPM [Job Performance Measure] will be pre-identified as defined in Supplement 1 to NUREG-1021, Operator Licensing Examination Standards for Power Reactors. (Note that Section 1.2, Retraining Program, subsections Course Schedule, and Examinations, also invoke Supplement 1 to NUREG-1021.)
Clarify which revision of the abovementioned NUREG will be used. Confirm that the same revision of the document is being referred to in Sections 1.1 and 1.2.
Response
Procedure EN-TQ-105, NRC Initial License Examination, Development, and Administration, specifies that the NUREG-1021 revision in effect six (6) months prior to the exam administration date is to be used. NUREG-1021 Revision 10 is current at JAF. Revision 10, or later, will be used to identify critical tasks and is also the revision being referred to in Sections 1.1 and 1.2 of CFH Training and Retraining Program.
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JAFP-16-0078 Attachment 1 Response to Request for Additional Information
- c. Subsection Exemption from Training Requirements states, in part:
individuals who hold a current NRC issued Reactor Operator or Senior Reactor Operator license <> may be evaluated to determine if they satisfy all of the requirements of this training program.
Clarify if the abovementioned statement refers to licensed Reactor Operators and Senior Reactor Operators only at JAF or from any NRC-regulated commercial nuclear power reactor in the U.S.
Response
The statement refers to licensed Reactor Operators and Senior Reactor Operators only at JAF.
RAI-4 Section 1.2, Retraining Program, subsection Examination Failures, states, in part: Only those portions that were originally failed need to be successfully re-examined prior to restoring qualifications.
Clarify whether the above statement refers to the entire written or operating exam that would need to be re-taken, or just a portion of either written or operating exam that was failed during the examination.
Response
Written exam failures will require retake of the entire written exam; operating exam failures will require retake of the entire operating exam.
RAI-5 Section 1.5, Evaluating Changes to the CFH Training and Retraining Program, states, in part: changes may be made to the program elements without NRC approval as long as: <> (1) suitable proficiency in performance of the program activities is maintained; and (2) changes are documented in an accessible manner that will allow the NRC to verify the adequacy of the program in accordance with 10 CFR 50.120.
Clarify whether in addition to the above two requirements, changes to the program made without prior NRC approval must also be such that the program continues to comply with the pertinent Technical Specifications. (Note that a statement to that effect was included in the second paragraph of Section 1, Introduction. Also see question 1, item (b) above.)
Response
Changes to the JAF Training and Retraining Program made without prior NRC approval ensures that the program continues to comply with TS 5.3.1, which states the following:
Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the Quality Assurance Program Manual (QAPM)1.
In addition to the above two requirements, changes made to the CFH Training and Retraining Program without prior NRC approval will ensure that the program continues to comply with TS 5.3.1.
1 Note that ENOI proposed revision of TS 5.3.1 to remove the word Entergy from the title of the Quality Assurance Program Manual (QAPM) by letter dated January 15, 2016 (ML16015A456).
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JAFP-16-0078 Attachment 1 Response to Request for Additional Information RAI-6 For RAIs 1 through 5 above, consider revising the JAF CFH Training and Retraining Program, as appropriate, to make any necessary changes or include the information provided by your responses, if needed. In your response, state if such changes were or will be made, and identify which Section(s) of the document were or will be revised, as appropriate.
Response
Based on the RAI responses above, no revisions to the JAF CFH Training and Retraining Program are proposed. The responses provide clarification and do not represent a material change to the JAF CFH Program that was originally submitted.
REFERENCE
- 1. Entergy letter, License Amendment Request - Revision to Technical Specification Administrative Controls for Permanently Defueled Condition, JAFP-15-0143, dated January 15, 2016 (ML16015A456)
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