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EPID:L-2022-LLA-0046, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) (Approved, Closed) |
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Category:Letter type:PLA
MONTHYEARPLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) PLA-8036, Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-80362022-11-30030 November 2022 Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-8036 PLA-8035, Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-80352022-11-0808 November 2022 Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-8035 PLA-8031, Emergency Plan Revision 66 (PLA-8031)2022-11-0707 November 2022 Emergency Plan Revision 66 (PLA-8031) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-8019, Nd Refueling Outage Owner'S Activity Report, PLA-80192022-07-13013 July 2022 Nd Refueling Outage Owner'S Activity Report, PLA-8019 PLA-8013, Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-80132022-06-27027 June 2022 Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-8013 PLA-8012, 10 CFR 50.46 Annual Report2022-06-10010 June 2022 10 CFR 50.46 Annual Report PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)2022-05-23023 May 2022 Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005) PLA-8001, Radiation Exposure Information and Reporting System - PLA-80012022-04-28028 April 2022 Radiation Exposure Information and Reporting System - PLA-8001 PLA-7986, 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-79862022-04-26026 April 2022 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-7986 PLA-7987, Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987)2022-04-26026 April 2022 Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987) PLA-7985, Annual Radiological Environmental Operating Report2022-04-22022 April 2022 Annual Radiological Environmental Operating Report PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7995, Property Insurance Program (PLA-7995)2022-03-30030 March 2022 Property Insurance Program (PLA-7995) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7991, Proof of Financial Protection and Guarantee of Payment of Deferred Premium2022-03-24024 March 2022 Proof of Financial Protection and Guarantee of Payment of Deferred Premium PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 2024-01-04
[Table view] Category:Technical Specification
MONTHYEARPLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 PLA-7892, Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-78922020-11-0505 November 2020 Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-7892 ML20129J9132020-04-23023 April 2020 Technical Specification Bases, Unit 1, Manual ML20036C9682020-01-29029 January 2020 Technical Specifications Bases, Manual ML20036C9732020-01-29029 January 2020 Technical Specification Bases, Manual ML19161A1372019-05-15015 May 2019 Technical Specification Bases Manual ML19078A1332019-03-0606 March 2019 Technical Requirements Manual ML19078A1342019-03-0606 March 2019 Technical Requirements Manual ML19078A2102019-03-0606 March 2019 Technical Specification Bases, Manual ML19078A2112019-03-0606 March 2019 Technical Specifications Bases, Manual PLA-7751, Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping2019-01-0909 January 2019 Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping ML19011A0572019-01-0707 January 2019 Technical Requirements Manual ML19011A0592019-01-0404 January 2019 Technical Specification Bases Manual ML19011A0582019-01-0404 January 2019 Technical Specifications Bases Manual ML18306A4882018-10-25025 October 2018 Revised Technical Specifications Manual ML18267A3792018-10-0303 October 2018 Correction to Technical Specification Page 3.6-37 for Error Introduced During the Issuance of Amendment Nos. 266 and 247 ML18201A1992018-07-11011 July 2018 Technical Specifications Bases, Manual ML18197A0782018-07-0909 July 2018 Revision 15 to Technical Specifications Bases Manual ML18128A2022018-04-25025 April 2018 Revision to Technical Specifications Bases Manual ML18128A2032018-04-25025 April 2018 Revision to Technical Specification Bases, Manual ML18072A1002018-02-28028 February 2018 Revision 11 to Technical Specifications Bases Manual ML18072A0992018-02-28028 February 2018 Technical Specification Bases Manual ML18033A3312018-01-24024 January 2018 Technical Specification Bases Manual ML18033A3342018-01-24024 January 2018 Technical Specifications Bases Manual PLA-7644, Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644)2017-12-14014 December 2017 Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644) ML17284A1772017-10-0202 October 2017 Technical Specification Bases Manual ML17265A4432017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 3 of 3) ML17265A4412017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 2 of 3) ML17270A0632017-09-18018 September 2017 Technical Specifications Bases, Manual ML17164A1772017-06-0101 June 2017 Revision to Technical Specifications Bases Manual ML17118A0762017-04-20020 April 2017 Revisions to Technical Specifications Bases Unit 2 Manual ML17118A0752017-04-20020 April 2017 Revision to Technical Specification Bases Manual PLA-7444, Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To...2017-02-0101 February 2017 Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To... ML16334A2652016-11-17017 November 2016 Technical Specification Bases Manual ML16110A3162016-04-14014 April 2016 Technical Specification Bases Manual ML16040A2032016-02-0303 February 2016 Technical Specification Bases Manual ML15329A1662015-11-11011 November 2015 Technical Requirements Manual ML15329A1652015-11-11011 November 2015 Technical Requirements Manual ML15317A0102015-11-0505 November 2015 Technical Specifications Bases Manual ML15317A0092015-11-0505 November 2015 Technical Specifications Bases Manual ML15077A4562015-03-0606 March 2015 Technical Requirements Manual ML15034A3102015-01-23023 January 2015 Technical Specification Bases Unit 1 Manual ML15034A3112015-01-23023 January 2015 Technical Specifications Bases, Unit 2 Manual PLA-7181, Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits.2014-08-11011 August 2014 Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits. ML14205A0132014-07-17017 July 2014 Technical Specification Bases, Manual, Revisions ML14196A0412014-07-0303 July 2014 Technical Specifications Bases, Manual 2023-11-02
[Table view] Category:Amendment
MONTHYEARPLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) ML18267A3792018-10-0303 October 2018 Correction to Technical Specification Page 3.6-37 for Error Introduced During the Issuance of Amendment Nos. 266 and 247 PLA-7644, Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644)2017-12-14014 December 2017 Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644) ML17265A4412017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 2 of 3) ML17265A4432017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 3 of 3) PLA-7444, Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To...2017-02-0101 February 2017 Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To... ML12242A2442012-08-14014 August 2012 Technical Specifications Bases Unit 2 Manual PLA-6539, Amendment Request No. 305 to Unit 1 License NPF-14 and Amendment Request No. 276 to Unit 2 License NPF-22: One-Time Extension of Tech Spec 3.8.1 Supplemental PRA Information2009-07-10010 July 2009 Amendment Request No. 305 to Unit 1 License NPF-14 and Amendment Request No. 276 to Unit 2 License NPF-22: One-Time Extension of Tech Spec 3.8.1 Supplemental PRA Information PLA-6509, Supplemental Electrical Information to License Amendment Request on the Technical Specifications2009-05-12012 May 2009 Supplemental Electrical Information to License Amendment Request on the Technical Specifications PLA-6505, Amendment Request No. 305 to Unit 1 License NPF-14 and Amendment Request No. 276 to Unit 2 License NPF-22: One-Time Extension of Technical Specification 3.8.1 PRA Supplemental Information2009-04-30030 April 2009 Amendment Request No. 305 to Unit 1 License NPF-14 and Amendment Request No. 276 to Unit 2 License NPF-22: One-Time Extension of Technical Specification 3.8.1 PRA Supplemental Information PLA-6235, Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1+1 and Editorial Change to TS 3.10.8.f2009-03-24024 March 2009 Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1+1 and Editorial Change to TS 3.10.8.f PLA-6480, One-Time Extension to Technical Specification 3.8.1 Allowable Completion Time for Offsite AC Circuits, PLA-64802009-03-24024 March 2009 One-Time Extension to Technical Specification 3.8.1 Allowable Completion Time for Offsite AC Circuits, PLA-6480 PLA-6474, Amendment Request No. 304 and 275, Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 262009-03-24024 March 2009 Amendment Request No. 304 and 275, Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 PLA-6359, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process (CLIIP) PLA-63592009-02-20020 February 2009 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process (CLIIP) PLA-6359 PLA-5604, Proposed Amendment No. 253 to License NPF-14 and Proposed Amendment No. 218 to License NPF-22: Request for Adoption of TSTF-460-A, Rev. 0, Control Rod Scram Time Test Frequency Using the CLIIP2008-07-0707 July 2008 Proposed Amendment No. 253 to License NPF-14 and Proposed Amendment No. 218 to License NPF-22: Request for Adoption of TSTF-460-A, Rev. 0, Control Rod Scram Time Test Frequency Using the CLIIP PLA-6304, Proposed Amendment No. 298 to Unit 1 License NPF-14 and Amendment No. 268 to Unit 2 License NPF-22: DC Electrical Power Systems Technical Specification 3.8.42008-03-28028 March 2008 Proposed Amendment No. 298 to Unit 1 License NPF-14 and Amendment No. 268 to Unit 2 License NPF-22: DC Electrical Power Systems Technical Specification 3.8.4 PLA-6306, Proposed License Amendments 285 and 253 - Constant Pressure Power Uprate Application - Supplement2007-11-30030 November 2007 Proposed License Amendments 285 and 253 - Constant Pressure Power Uprate Application - Supplement PLA-6266, Proposed License Amendment No. 285 for Unit 1, License No. NPF-14 & Proposed License Amendment No. 253 for Unit 2, License No. NPF-22, Extended Power Uprate Application Regarding Change to Technical Specification SR 3.7.1 - RHRSW and UHS2007-08-28028 August 2007 Proposed License Amendment No. 285 for Unit 1, License No. NPF-14 & Proposed License Amendment No. 253 for Unit 2, License No. NPF-22, Extended Power Uprate Application Regarding Change to Technical Specification SR 3.7.1 - RHRSW and UHS PLA-6172, Proposed License Amendment for Constant Pressure Power Uprate - Supplement PLA-61722007-03-22022 March 2007 Proposed License Amendment for Constant Pressure Power Uprate - Supplement PLA-6172 PLA-6114, Proposed Amendment Nos. 281 and 251 to Licenses NPF-22 and NPF-22, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67...2006-09-15015 September 2006 Proposed Amendment Nos. 281 and 251 to Licenses NPF-22 and NPF-22, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67... ML0619100912006-07-0707 July 2006 Technical Specifications Pages Re 3.0 Limiting Condition for Operation (LCO) Applicability PLA-6049, Proposed License Amendment Nos. 289 and 257, Standby Liquid Control System2006-04-28028 April 2006 Proposed License Amendment Nos. 289 and 257, Standby Liquid Control System ML0609603342006-03-31031 March 2006 Susquehanna - Proposed License Amendment Numbers 285 for Unit 1 and 253 for Unit 2, Constant Pressure Power Uprate, PLA-6002 ML0609004652006-03-30030 March 2006 Technical Specification 3.4.10 RCS Pressure and Temperature (P/T) Limits, October 5, 2005 ML0608007312006-03-20020 March 2006 Tech Spec for Susquehanna, Unit 1 - Issuance of Amendment Regarding Minimum Critical Power Ratio Safety Limit and Reference Changes ML0603306392006-02-0202 February 2006 Tech Spec Susquehanna Steam Electric Station, Unites 1 and 2 - Issuance of Amendment Revision to Specification Surveillance Requirement 3.6.4.1.4 and 3.6.4.1.5, Secondary Containment and Draw Down Testing PLA-5993, Proposed Amendment No. 284 to License NPF-14 & Proposed Amendment No. 252 to License NPF-22 to Revise Technical Specification 3.1.4, Control Rod Scram Times.2006-02-0101 February 2006 Proposed Amendment No. 284 to License NPF-14 & Proposed Amendment No. 252 to License NPF-22 to Revise Technical Specification 3.1.4, Control Rod Scram Times. ML0531803282005-11-10010 November 2005 Technical Specification Page Regarding Minimum Critical Power Ratio Safety Limit PLA-5967, Proposed Amendment No. 282 to Facility Operating License NPF-14: Proposed Change to Technical Specification 2.1.1.2 MCPR Safety Limit2005-10-14014 October 2005 Proposed Amendment No. 282 to Facility Operating License NPF-14: Proposed Change to Technical Specification 2.1.1.2 MCPR Safety Limit PLA-5888, Proposed Amendment Nos. 274 and 243 to License Nos. NPF-14 and NPF-22, Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Monthly Operating Reports.2005-10-0505 October 2005 Proposed Amendment Nos. 274 and 243 to License Nos. NPF-14 and NPF-22, Application for Technical Specification Improvement to Revise Technical Specifications to Eliminate Requirements for Monthly Operating Reports. ML0521700382005-08-0404 August 2005 Technical Specification Pages Re Containment Purge Value Leak Rate Test Frequency PLA-5880, Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NTF-14 and 241 for Unit 2 Operating License No. NPF-22, Power Range Neutron Monitor System Digital Upgrade PLA-58802005-06-27027 June 2005 Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NTF-14 and 241 for Unit 2 Operating License No. NPF-22, Power Range Neutron Monitor System Digital Upgrade PLA-5880 PLA-5891, Proposed Amendment No. 275 to Unit 1 Facility Operating License NPF-14 and Proposed Amendment No. 244 to Unit 2 Facility Operating License NPF-22: Exigent Change to Technical Specification 3.8.4, PLA-58912005-04-27027 April 2005 Proposed Amendment No. 275 to Unit 1 Facility Operating License NPF-14 and Proposed Amendment No. 244 to Unit 2 Facility Operating License NPF-22: Exigent Change to Technical Specification 3.8.4, PLA-5891 ML0509000432005-03-29029 March 2005 Technical Specification Pages Re ADS-LPCI Discharge Pressure PLA-5869, Proposed Amendment No. 240 to License No. NPF-22 Regarding Revision to Technical Specifications 3.3.8.1 and 3.8.72005-03-18018 March 2005 Proposed Amendment No. 240 to License No. NPF-22 Regarding Revision to Technical Specifications 3.3.8.1 and 3.8.7 PLA-5850, Proposed Amendment No. 238 to Unit 2 License NFP-22: Editorial Change to Technical Specification Table 3.3.5.1-1 PLA-58502005-01-28028 January 2005 Proposed Amendment No. 238 to Unit 2 License NFP-22: Editorial Change to Technical Specification Table 3.3.5.1-1 PLA-5850 PLA-5840, Proposed Amendment: Revision to Technical Specification 5.5.6., PLA-58402005-01-28028 January 2005 Proposed Amendment: Revision to Technical Specification 5.5.6., PLA-5840 PLA-5825, Proposed Amendment No. 269 to Unit 1 License NPF-14 and Amendment No. 236 to Unit 2 License NPF-22: DC Electrical Power Systems Technical Specifications Rewrite PLA-58252004-11-0909 November 2004 Proposed Amendment No. 269 to Unit 1 License NPF-14 and Amendment No. 236 to Unit 2 License NPF-22: DC Electrical Power Systems Technical Specifications Rewrite PLA-5825 PLA-5764, Proposed License Amendment Numbers 267 for Unit 1 and 232 for Unit 2 Mode Change Limitations Using the Consolidated Line Item Improvement (CLIIP) Process PLA-57642004-09-22022 September 2004 Proposed License Amendment Numbers 267 for Unit 1 and 232 for Unit 2 Mode Change Limitations Using the Consolidated Line Item Improvement (CLIIP) Process PLA-5764 PLA-5811, Proposed Amendment No. 235 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-temperature (P-T) Limits PLA-58112004-09-22022 September 2004 Proposed Amendment No. 235 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-temperature (P-T) Limits PLA-5811 PLA-5755, Proposed Amendment No. 265 to License NPF-14 & Proposed Amendment No. 230 to License NPF-22: Application for Technical Specification Improvement to Revise Technical Specification 3.1.8 Scram Discharge Volume.2004-09-0808 September 2004 Proposed Amendment No. 265 to License NPF-14 & Proposed Amendment No. 230 to License NPF-22: Application for Technical Specification Improvement to Revise Technical Specification 3.1.8 Scram Discharge Volume. PLA-5785, Table of Contents Revisions Proposed Amendment No. 259 and Proposed Amendment No. 224 Revised Response to GL 94-02: Long-Term Stability Solution PLA-57852004-07-15015 July 2004 Table of Contents Revisions Proposed Amendment No. 259 and Proposed Amendment No. 224 Revised Response to GL 94-02: Long-Term Stability Solution PLA-5785 PLA-5739, Proposed Amendment Nos. 264 and 229, Respectively Regarding Resolution of URI 2001-04-03 Standby Liquid Control/Atws2004-05-11011 May 2004 Proposed Amendment Nos. 264 and 229, Respectively Regarding Resolution of URI 2001-04-03 Standby Liquid Control/Atws PLA-5726, Proposed License Amendment Regarding Secondary Containment Access Doors Surveillance Requirements 3.6.4.1.32004-03-0505 March 2004 Proposed License Amendment Regarding Secondary Containment Access Doors Surveillance Requirements 3.6.4.1.3 PLA-5722, Proposed License Amendments Regarding ADS-LPCI Discharge Pressure, TS 3.3.5.1-1, Function 4.f and 5.f2004-03-0404 March 2004 Proposed License Amendments Regarding ADS-LPCI Discharge Pressure, TS 3.3.5.1-1, Function 4.f and 5.f PLA-5686, Proposed Amendment No. 259 to License NPF-14, and Proposed Amendment No. 224 to License NPF-22, Revised Response to Gl 94-02: Long-term Stability Solution2003-12-22022 December 2003 Proposed Amendment No. 259 to License NPF-14, and Proposed Amendment No. 224 to License NPF-22, Revised Response to Gl 94-02: Long-term Stability Solution PLA-5694, Proposed Amendment Regarding Revised Main Turbine Bypass System Requirements2003-12-0505 December 2003 Proposed Amendment Regarding Revised Main Turbine Bypass System Requirements ML0330904032003-10-29029 October 2003 Tech Spec Pages for Amendments 215 & 190 Revised Response to Generic Letter 94-02 Long-Term Stability Solution 2023-11-02
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Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com March 31, 2022 Attn: Document Control Desk 10 CFR 50.90 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT TO LICENSES NPF-14 AND NPF-22: RELOCATE TECHNICAL SPECIFICATION UNIT STAFF QUALIFICATION REQUIREMENTS TO SUSQUEHANNA QUALITY ASSURANCE PROGRAM Docket No. 50-387 PLA-7883 and 50-388
Reference:
NRC Administrative Letter 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, dated December 12, 1995 (ADAMS Accession No. ML031110271).
Pursuant to 10 CFR 50.90, Susquehanna Nuclear, LLC (Susquehanna), is submitting a request for an amendment to the Technical Specifications (TS) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2, Facility Operating License numbers NPF-14 and NPF-22. The proposed amendment would modify TS 5.3.1, Unit Staff Qualifications.
The proposed amendment would relocate the TS Unit Staff Qualification Requirements to the Susquehanna Quality Assurance Program, which is located in Sections 13.4 and 17.2 of the Susquehanna Updated Final Safety Analysis Report (FSAR), consistent with NRC Administrative Letter 95-06 (Reference 1) guidance. provides a description and assessment of the proposed changes along with Susquehanna's determination that the proposed changes do not involve a significant hazard consideration. Enclosure 2 provides the existing TS pages marked to show the proposed changes. Enclosure 3 provides revised (clean) TS pages. Enclosure 4 provides an excerpt of FSAR Table 17.2-1, which already reproduces the TS requirements and is provided for information only.
While this request is submitted under neither exigent nor emergent circumstances, Susquehanna requests NRC approval of the proposed changes and issuance of the requested license
Document Control Desk PLA-7883 amendment by February 28, 2023 . Once approved, the amendment shall be implemented within 60 days.
In accordance with 10 CFR 50.91, Susquehanna is providing a copy of this application, with enclosures, to the designated Commonwealth of Pennsylvania state official.
Both the Plant Operations Review Committee and the Nuclear Safety Review Board have reviewed the proposed changes.
There are no new or revised regulatory commitments contained in this submittal.
Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager-Nuclear Regulatory Affairs, at (570) 542-1818.
I declare under penalty of perjury that the foregoing is true and correct.
K. Cimorelli
Enclosures:
- 1. Description and Assessment
- 2. Marked-Up Technical Specification Pages
- 3. Revised (Clean) Technical Specification Pages
- 4. FSAR Table 17.2-1 Excerpt (Submitted for Information Only)
Copy: NRC Region I Mr. C. Highley, NRC Sr. Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Enclosure 1 to PLA-7883 Description and Assessment
- 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION 2.1 Current Technical Specifications Requirements 2.2 Reason for the Proposed Change 2.3 Description of the Proposed Change
- 3. TECHNICAL EVALUATION 3.1 Technical Analysis 3.2 Conclusions
- 4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration Analysis 4.4 Conclusions
- 5. ENVIRONMENTAL CONSIDERATION
- 6. REFERENCES
Enclosure 1 to PLA-7883 Page 1 of 7 SUSQUEHANNA ASSESSMENT
- 1. Summary Description Pursuant to 10 CFR 50.90, Susquehanna Nuclear, LLC (Susquehanna), is submitting a request for an amendment to the Technical Specifications (TS) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2, Facility Operating License numbers NPF-14 and NPF-22. The proposed amendment would modify TS 5.3.1, Unit Staff Qualifications. Specifically, the proposed amendment would permit the relocation of the Unit Staff Qualifications from the TS to the Susquehanna Quality Assurance Program (QAP), which is located in the Updated Final Safety Analysis Report (FSAR).
- 2. Detailed Description 2.1 Current Technical Specifications Requirements TS 5.3.1 currently requires:
- 1) Licensed Operators and Shift Technical Advisors shall meet the supplemental requirements in Regulatory Guide (RG) 1.8, Revision 2 (Reference 1);
- 2) Supervisor - Health Physics shall meet or exceed the qualification of RG 1.8, September 1975 (Reference 2); and
- 3) All other members of the unit staff shall meet or exceed the minimum qualifications of American National Standards Institute (ANSI) Standard ANSI N18.1-1971 (Reference 3) for comparable positions.
2.2 Reason for the Proposed Change The existing TS requirements for unit staff qualifications are based on NRC endorsed industry standards to ensure that a licensees staff is appropriately qualified for their respective positions.
Susquehanna desires to relocate these TS requirements for unit staff qualifications to the QAP to provide flexibility in adopting updated NRC-endorsed standards, and to eliminate the need for future amendment requests due only to upgrades to future revisions to the ANSI/ANS 3.1 standard, ANSI N18.1 Standard, or RG 1.8.
Enclosure 1 to PLA-7883 Page 2 of 7 2.3 Description of the Proposed Change TS 5.3.1 is revised to state, Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program. The unit staff qualification requirements are already reproduced in FSAR Table 17.2-1.1, 2
- 3. Technical Evaluation 3.1 Technical Analysis The proposed change will relocate the TS requirements for unit staff qualifications to the SSES QAP. This amendment will not change any current staff qualification requirements at SSES and is only an administrative TS change.
10 CFR 50.36(c)(5) requires TS to include items in the administrative controls category. Items include provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. In 1995, the NRC acknowledged that many license amendments were being processed (e.g., organizational changes, position title changes, organization description changes, procedure review process) to relocate TS items to the licensees QAP. The items being relocated from TS did not satisfy the criteria of 10 CFR 50.36 for inclusion as a limiting condition for operation and were adequately controlled by other regulations and related licensee programs. The NRC issued Administrative Letter (AL) 95-06 (Reference 4), to address this issue and to provide additional guidance for relocating TS administrative controls to the licensees QAP. The proposed change is consistent with the guidance in AL 95-06 for relocating a licensees TS requirements to its QAP.
The unit staff qualifications do not satisfy the criteria of 10 CFR 50.36 for inclusion in the TS as a limiting condition for operation and are adequately controlled by other regulations and Susquehanna training programs. Susquehanna meets the training requirements specified in 10 CFR 55 and NUREG-1021 (Reference 5). In addition, on March 20, 1985, the NRC issued the Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel (Reference 6), which endorsed the training accreditation program developed by the Institute of Nuclear Power Operations (INPO), in association with the National Academy for 1
FSAR Table 17.2-1 requires that, for all positions not otherwise stated in the table, individuals meet the minimum qualification requirements in ANSI N18.1-1978 rather than the 1971 version stated in TS 5.3.1. The qualification requirements in ANSI N18.1-1978 meet or exceed the qualification requirements of ANSI N18.1-1971 for all unit staff positions as is required by TS 5.3.1. Therefore, no changes are required to the qualification requirements delineated in FSAR Table 17.2-1. To aid the NRCs review, Page 1 of Table 17.2-1 is included in Enclosure 4 for information only.
2 TS 5.3.1 currently uses the position title supervisor - health physics. In FSAR Table 17.2-1, this is equated to the position Radiation Protection (Manager) as described in Section 4.4.4 of ANSI N18.1-1971.
Enclosure 1 to PLA-7883 Page 3 of 7 Nuclear Training (NANT). The NRC has documented discussion, approval, and acceptance of NANT guidelines in Regulatory Issue Summary 2001-01 (Reference 7). Susquehanna training programs employ the systems approach to training (SAT) required by 10 CFR 50.120 as embodied in the INPO NANT standards for plant staff personnel and their qualifications.
Consistent with the guidance in AL 95-06, future changes to the QAP staff qualification requirements will be evaluated under the 10 CFR 50.54(a) evaluation process.
3.2 Conclusions The proposed change does not change current staff qualification requirements. The unit staff qualification requirements in the TS remain unchanged. Future changes to the QAP, as contained in the FSAR, are controlled by the 10 CFR 50.54(a) evaluation processes.
- 4. Regulatory Evaluation 4.1 Applicable Regulatory Requirements/Criteria Title 10 Code of Federal Regulations (10 CFR) 50.36 10 CFR 50.36(c)(5) requires provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting to be included in the TS that are necessary to assure operation of the facility in a safe manner. The proposed change conforms to the 10 CFR 50.36(c)(5) requirements.
10 CFR 50.120 10 CFR 50.120 requires that each nuclear power plant licensee establish, implement, and maintain the training and qualification programs that are derived from a systems approach to training as defined in 10 CFR 55.4. The proposed change conforms to the 10 CFR 50.120 requirements.
10 CFR 55 10 CFR 55, Subpart D, Applications, requires that operator license applications include information concerning an individuals education, experience, and other related matters to provide evidence and certification that the applicant has successfully completed the facility licensees training program that is based on a systems approach to training. The proposed change conforms to the 10 CFR 55 requirements.
Enclosure 1 to PLA-7883 Page 4 of 7 NUREG-1021 NUREG-1021 establishes the policies, procedures, and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at nuclear power reactor facilities under 10 CFR 55. The Susquehanna operator training program meets the current requirements of NANT Academy Document ACAD 10-001. The proposed change conforms to the NUREG-1021 requirements.
Regulatory Guide 1.8 RG 1.8 describes a method that the NRC staff finds acceptable for complying with the NRCs regulations regarding training and qualification of nuclear plant personnel. The proposed change maintains the current commitments to RG 1.8 (Revisions 1 and 2) as identified in the current TS staff qualification requirements and relocates the requirements to the QAP.
Administrative Letter 95-06 AL 95-06 discusses relocation of administrative controls related to quality assurance from the TS to licensee-controlled documents and programs. The proposed change to relocate TS unit staff qualifications is consistent with the guidance in AL 95-06, as discussed in Section 3.1.
Conclusion Susquehanna has evaluated the proposed change against the applicable regulatory requirements and acceptance criteria. Susquehanna has determined that the applicable regulatory requirements continue to be met.
4.2 Precedent The NRC has approved multiple similar amendment requests to allow relocation of unit staff qualification requirements from the TS to the QAP. Specifically, the NRC has issued such an amendment to Duke Energy Corporation (Duke) for the Brunswick, Catawba, McGuire, Oconee, Shearon Harris, and H. B. Robinson Plants in 2020 (Reference 8) and to Exelon for all its nuclear units in 2018 (Reference 9). As the proposed change is administrative in nature, the differences in design between SSES and the Duke and Exelon plants are irrelevant, and the NRCs prior approvals are applicable to Susquehannas request for SSES.
4.3 No Significant Hazards Considerations Analysis In accordance with the requirements of 10 CFR 50.90, Susquehanna Nuclear, LLC (Susquehanna), requests an amendment to the Technical Specifications (TS) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. The proposed amendment would
Enclosure 1 to PLA-7883 Page 5 of 7 relocate the specific unit staff qualification requirements from TS 5.3.1 to the Quality Assurance Program (QAP), which is located within the SSES Updated Final Safety Analysis Report (FSAR).
Susquehanna has evaluated the proposed amendment against the standards in 10 CFR 50.92 and has determined that the operation of the SSES in accordance with the proposed amendment presents no significant hazards. Susquehannas evaluation against each of the criteria in 10 CFR 50.92 follows.
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change is administrative in nature. The unit staff qualification requirements remain the same and are being relocated from the TS to the QAP. It does not make any physical changes to the plant, and does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, tested, or inspected. The proposed change does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change is administrative in nature. The unit staff qualification requirements remain the same and are being relocated from the TS to the QAP. It does not involve changes to unit staff selection, qualification, and training programs. The proposed change does not impact the accident analysis. The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a change in the method of plant operation, or new operator actions. The proposed change does not introduce failure modes that could result in a new accident, and the change does not alter assumptions made in the safety analysis. The proposed change does not alter or prevent the ability of the operators to perform their intended functions to mitigate the consequences of an accident or event.
Enclosure 1 to PLA-7883 Page 6 of 7 Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change is administrative in nature. The unit staff qualification requirements remain the same and are being relocated from the TS to the QAP. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed change does not impact operation of the plant or its response to transients or accidents. The proposed change does not involve a change in the method of plant operation, and no accident analyses will be affected by the proposed change.
Safety analysis acceptance criteria are not affected by this proposed change.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above evaluation, Susquehanna concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
- 5. Environmental Consideration The proposed amendment is confined to changes to recordkeeping, reporting, or administrative procedures or requirement. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10)(ii). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Enclosure 1 to PLA-7883 Page 7 of 7
- 6. References
- 1. NRC Regulatory Guide 1.8, Qualification and Training of Personnel for Nuclear Power Plants, Revision 2, dated April 1987 (ADAMS Accession No. ML003739928).
- 2. NRC Regulatory Guide 1.8, Personnel Selection and Training, Revision 1, dated September 1975 (ADAMS Accession No. ML12305A250).
- 3. ANSI Standard N18.1-1971, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971.
- 4. NRC Administrative Letter 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, dated December 12, 1995 (ADAMS Accession No. ML031110271).
- 5. NRC NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 12, dated September 2021 (ADAMS Accession No. ML21256A276).
- 6. NRC Policy Statement, Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel, dated March 20, 1985 (50 FR 11147).
- 7. NRC Regulatory Issue Summary 2001-01, Eligibility of Operator License Applications, dated January 18, 2001 (ADAMS Accession No. ML003733003).
- 8. NRC letter to Duke Energy Corporation, Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description (EPID L-2019-LLA-0142), dated August 12, 2020 (ADAMS Accession No. ML20083F927).
- 9. NRC letter to Exelon, Issuance of Amendments to Relocate the Staff Qualification Requirements (EPID L-2018-LLA-0053), dated August 2, 2018 (ADAMS Accession No. ML18206A282).
Enclosure 2 of PLA-7883 Marked-Up Technical Specification Pages Revised Technical Specifications Pages Unit 1 TS Page 5.0-5 Unit 2 TS Page 5.0-5
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program of ANSI N18.1-1971 for comparable positions except licensed operators and Shift Technical Advisors who shall meet the supplemental requirements in Reg Guide 1.8 Rev. 2 and the supervisor-health physics who shall meet or exceed the qualification of Regulatory Guide 1.8 September 1975.
SUSQUEHANNA - UNIT 1 5.0-5 Amendment 178, XXX
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program of ANSI N18.1-1971 for comparable positions except licensed operators and Shift Technical Advisors who shall meet the supplemental requirements in Reg Guide 1.8 Rev. 2 and the supervisor-health physics who shall meet or exceed the qualification of Regulatory Guide 1.8 September 1975.
SUSQUEHANNA - UNIT 2 5.0-5 Amendment 151, XXX
Enclosure 3 of PLA-7883 Revised (Clean) Technical Specification Pages Revised Technical Specifications Pages Unit 1 TS Page 5.0-5 Unit 2 TS Page 5.0-5
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program.
SUSQUEHANNA - UNIT 1 5.0-5 Amendment 178, XXX
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Susquehanna Steam Electric Station Quality Assurance Program.
SUSQUEHANNA - UNIT 2 5.0-5 Amendment 151, XXX
Enclosure 4 of PLA-7883 FSAR Table 17.2-1 Excerpt FSAR Table 17.2-1, Page 1 of 3 (Provided for Information Only)
NO CHANGES - INCLUDED FOR INFORMATION ONLY SSES-FSAR Table Rev. 69 TABLE 17.2-1 QUALITY ASSURANCE PROGRAM DESCRIPTION COMPLIANCE MATRIX NRC Reg. Guide ANSI Standard Subject Clarifications & Exceptions 1.8, Rev. 4 ANS/ANS 3.1- Personnel Selection & Training Commitment to the following section of ANSI/ANS 3.1-2014, as (June 2019) 2014 modified by RG 1.8, Rev. 4:
4.2.4, [Senior Manager] Engineering 1.8, Rev. 3 ANSI/ANS 3.1- Personnel Selection & Training Commitment to the following section of ANSI/ANS 3.1-1993, (May 2000) 1993 as modified by RG 1.8, Rev. 3: 4.3.7, Quality Assurance (Manager)
The allowance contained in Regulatory Position 2.1.1 of RG 1.8, Rev. 3, has been expanded to include approval and documentation by the responsible executive in addition to the plant manager.
The term Quality Verification is defined as The act of reviewing, inspecting, testing, checking, auditing, or otherwise determining and documenting whether items, processes, services, or documents conform to specified requirements integral to the QA Program. (LDCN 4894) 1.8, Rev. 2 ANSI/ANS 3.1- Personnel Selection & Training Commitment to the following sections of ANSI/ANS 3.1-1981, (April 1987) 1981 as modified by RG 1.8, Rev. 2:
4.3.1.1, Shift Supervisor; 4.3.1.2, Senior Operator; 4.4.8, Shift Technical Advisor; 4.5.1.2, Licensed Operators 4.7.1, Supervisor of Organization Unit Responsible for Independent Review ; 4.7.2, [Independent Review] Staff Specialist.
1.8, Rev. 1-R ANSI N18.1- Personnel Selection & Training Commitment to the following section of ANSI N18.1-1971, (Sept. 1975) 1971 as modified by RG 1.8, Rev. 1-R:
4.4.4, Radiation Protection (Manager).
None ANSI/ANS 3.1- Personnel Selection & Training 1. Commitment to ANSI/ANS 3.1-1978 for all positions 1978 addressed therein, except those listed above.
- 2. SSES TS 5.2.2.f states that the operations manager or the assistant operations manager shall hold an SRO license.
1.28, Rev. 1 N45.2-1977 QA Program Requirements For Full compliance.
Nuclear Facilities 1.30, 8/72 N45.2.4-1972 Electrical Installation, Inspection & Commitment to the extent required by ANSI N18.7-1976.
Testing Calibration status of installed plant instrumentation is maintained via a computer information system.
1.33, Rev. 2 N18.7-1976 Administrative Controls & Full compliance except for:
Operational QA 1) Review frequency of procedures that comply with NRC Safety Evaluation dated July 27, 2001, performed for Vermont Yankee and frequency of program audits. See Section 17.2.2 for details. (LDCNs 3353 and 3466)
- 2) Allowance of up to 25% Grace for audits except for audits controlled by 10CFR requirements. See Section 17.2.18 for details. (LDCN 5552)
- 3) Alternative requirements may be implemented in lieu of imposing a quality assurance program consistent with ANSI N45.2 for NVLAP & A2LA accredited commercial-grade calibration services. See Section 17.2.4 and 17.2.7 for details (LDCN 3957)
- 4) Procurement documents do not need to require a quality assurance program consistent with 10CFR50, Appendix B and ANSI N45.2-1971 and a pre-award evaluation and post-award audits are not required for work performed at the National Institute of Standards and Technology. See Section 17.2.4 & 17.2.7 for details. (LDCN 3957) 1.37, 3/73 N45.2.1-1973 Cleaning Fluid Systems & Commitment to the extent required by ANSI N18.7-1976.
Components FSAR Rev. 70 Page 1 of 3