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 Issue dateTitleTopic
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..16 June 2022Response 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..Safe Shutdown
High winds
Probabilistic Risk Assessment
Reserve Station Service Transformer
Open Phase Condition
Large early release frequency
Offsite Circuit
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 Actuated23 February 2022Constellation, 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 PSurveillance Frequency Control Program
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 Repairs2 February 2022Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle RepairsNondestructive Examination
VT-2
Foreign Material Exclusion
Through-Wall Leakage
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 Primary14 January 2022Response 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 PrimaryReactor Vessel Water Level
JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments16 September 2021Response 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.9 August 2021Response 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.Stroke time
Weld Overlay
JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments11 June 2021Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
ML21138A01318 May 2021NRC 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. 05000333/2021090Backfit
JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting20 April 2021Response 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) 3.5.1.618 February 2021Supplement 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 Valves26 January 2021Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation ValvesLoop seal
ML20315A24510 November 2020Response to Request for Additional Information to Support Review of License Amendment Request - Application to Modify Technical Specifications 3.6.1.3 Primary Containment Isolation ValvesStroke time
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 Loads6 April 2020Response to Request for Additional Information in Support of License Amendment Request - Proposed Changes to the Technical Specifications to Primary Containment Hydrodynamic LoadsMELLLA
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 Isolation31 March 2020Response 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 IsolationReactor Vessel Water Level
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 Isolation21 February 2020Response 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 Consequences16 January 2020Response 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)...6 November 2019Response 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)...Safe Shutdown
Reactor Vessel Water Level
Earthquake
ML19279A0016 October 2019Response 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 ...Grace period
JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8804 June 2019Response 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 Plants1 May 2019Response 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) Interval15 January 2019End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) IntervalWeld Overlay
JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8808 January 2019Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880Commercial Grade Dedication
Nondestructive Examination
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 Reactors12 July 2018Response 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 ReactorsSafe Shutdown
High winds
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Operating Basis Earthquake
Earthquake
Fuel cladding
Pressure Boundary Leakage
RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-0129 May 2018Response to Request for Additional Information Regarding Generic Letter 2016-01Aging Management
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 219 April 2018Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2Water Inventory Control
Surveillance Frequency Control Program
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 Openings15 March 2018Response 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)2 March 2018Response 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)
ML18025A79925 January 2018Response to Request for Additional Information Regarding Generic Letter 2016-01Aging Management
JAFP-18-0012, Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 222 January 2018Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2Reactor Vessel Water Level
Water Inventory Control
ML17346A15311 December 2017Submittal of Response to Request for Additional Information on Relief Requests Associated with the Fifth Inservice Inspection (ISI) IntervalVT-2
Earthquake
EVT-1
Liquid penetrant
DM weld
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...27 April 2017Revision 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...Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Earthquake
Power-Operated Valves
Power Operated Valves
Hardened vent
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 Preparedness23 January 2017Response 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 PreparednessSafe Shutdown
High Radiation Area
Ultimate heat sink
FLEX
Fukushima Dai-Ichi
Severe Accident Management Guideline
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 Accident22 December 2016Spent 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 AccidentSafe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
ML16335A10429 November 2016Independent 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 AmendmentOpen House
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 121 November 2016Response 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 Pools3 November 2016Response 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 219 September 2016Revision 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 Program18 August 2016Response to Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining ProgramJob Performance Measure
JAFP-16-0130, License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 210 August 2016License 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 16 July 2016License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition - Supplement 1Severe Accident Management Guideline
Earthquake
Fuel cladding
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-2027 June 2016Response to Request for Additional Information for Proposed Inservice Inspection Program Alternative in Accordance with 10 CFR 50.55a(z)(2), RR-20Hydrostatic
VT-2
Pressure Boundary Leakage
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 13 June 2016Response 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 1Control of Heavy Loads
Fire Protection Program
Grace period
JAFP-16-0078, Response to Request for Additional Information (RAI) Regarding Request for Approval of Certified Fuel Handler Training and Retaining Program3 June 2016Response 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)2 June 2016Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)Weld Overlay
Nondestructive Examination
Incorporated by reference
ML16071A4417 March 2016Entergy 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)25 February 2016Response 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, Secti29 January 2016Entergy - 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,Liquid penetrant
CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 14 December 2015Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1Nondestructive Examination
Functionality Assessment
JAFP-15-0094, Response to Request for Additional Information for Expedited Seismic Evaluation Process Report4 August 2015Response to Request for Additional Information for Expedited Seismic Evaluation Process ReportFLEX
Fukushima Dai-Ichi
Hardened vent
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