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	Issue date	Title	Topic
ML23103A323	13 April 2023	Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89	Safe Shutdown Non-Destructive Examination Commercial Grade Dedication Aging Management Surveillance Frequency Control Program Open Phase Condition Open Phase Initiative
CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40	28 April 2022	Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40	Fitness for Duty Offsite Dose Calculation Manual Safe Shutdown Earthquake Coatings Nondestructive Examination Cyber Security B.5.b Process Control Program Subsequent License Renewal Fire Protection Program Grace period
ML20142A542	21 May 2020	4 to Updated Final Safety Analysis Report, Section 17, Quality Assurance
ML17157B265	9 May 2017	Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor	Safe Shutdown FLEX Aging Management Fire Protection Program GOTHIC
LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re	9 May 2017	Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor	Safe Shutdown FLEX Aging Management Fire Protection Program GOTHIC
ML17164A314	24 February 2017	Enclosures 1 & 2: PSEG Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86	Safe Shutdown Fitness for Duty Non-Destructive Examination Offsite Dose Calculation Manual Commercial Grade Dedication Safe Shutdown Earthquake Nondestructive Examination Temporary Modification Cyber Security Emergency Lighting Condition Adverse to Quality FLEX Aging Management Foreign Material Exclusion Process Control Program Operability Determination License Renewal Fire Protection Program
LR-N17-0088, Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86	24 February 2017	Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86	Safe Shutdown Fitness for Duty Non-Destructive Examination Offsite Dose Calculation Manual Commercial Grade Dedication Safe Shutdown Earthquake Nondestructive Examination Temporary Modification Cyber Security Emergency Lighting Condition Adverse to Quality FLEX Aging Management Foreign Material Exclusion Process Control Program Operability Determination License Renewal Fire Protection Program
ML17046A229	30 January 2017	Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85	Safe Shutdown Boric Acid Fitness for Duty Shutdown Margin High Radiation Area Ultimate heat sink Non-Destructive Examination Offsite Dose Calculation Manual Anticipated operational occurrence Safe Shutdown Earthquake Hydrostatic Coatings Nondestructive Examination Temporary Modification Cyber Security Emergency Lighting Condition Adverse to Quality FLEX Aging Management Missed surveillance Fukushima Dai-Ichi Surveillance Frequency Control Program Foreign Material Exclusion Process Control Program Operability Determination Spent Fuel Pool Instrumentation License Renewal Maintenance Rule Program Fuel cladding Pressure Boundary Leakage Offsite Circuit Fire Protection Program Power change Unidentified leakage
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85	30 January 2017	Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85	Safe Shutdown Boric Acid Fitness for Duty Shutdown Margin High Radiation Area Ultimate heat sink Non-Destructive Examination Offsite Dose Calculation Manual Anticipated operational occurrence Safe Shutdown Earthquake Hydrostatic Coatings Nondestructive Examination Temporary Modification Cyber Security Emergency Lighting Condition Adverse to Quality FLEX Aging Management Missed surveillance Fukushima Dai-Ichi Surveillance Frequency Control Program Foreign Material Exclusion Process Control Program Operability Determination Spent Fuel Pool Instrumentation License Renewal Maintenance Rule Program Fuel cladding Pressure Boundary Leakage Offsite Circuit Fire Protection Program Power change Unidentified leakage
LR-N12-0156, Submittal of Updated Final Safety Analysis Report, Revision 26, Salem Units 1 & 2 Technical Specification Bases Changes, 10 CFR 54.37(b) Review Results and PSEG Nuclear LLC Quality Assurance Topical Report, NO-AA-10, Revision 82	21 May 2012	Submittal of Updated Final Safety Analysis Report, Revision 26, Salem Units 1 & 2 Technical Specification Bases Changes, 10 CFR 54.37(b) Review Results and PSEG Nuclear LLC Quality Assurance Topical Report, NO-AA-10, Revision 82	Safe Shutdown Boric Acid Time of Discovery Shutdown Margin Packing leak High Radiation Area Ultimate heat sink Non-Destructive Examination Grab sample Offsite Dose Calculation Manual Anticipated operational occurrence Hydrostatic Operating Basis Earthquake Nondestructive Examination Cyber Security Incorporated by reference B.5.b Annual Radioactive Effluent Release Report Surveillance Frequency Control Program Design basis earthquake Annual Radiological Environmental Operating Report Process Control Program Safeguards Contingency Plan License Renewal Fuel cladding Pressure Boundary Leakage Offsite Circuit Fire Protection Program Power change Unidentified leakage
ML19031A381	18 January 1979	Response to Request for Additional Information on Quality Assurance & Subcompartment Analysis, Which Will Be Incorporated Into Fasr in Amendment to Application	Temporary Modification Earthquake

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