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Category:Letter type:PLA
MONTHYEARPLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) PLA-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-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) 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-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-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-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) 2024-09-18
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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-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-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-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-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-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-7979, Supplement to License Amendment to Revise Reactor Steam Dome Pressure Low Instrumentation Function Allowable Value2021-12-16016 December 2021 Supplement to License Amendment to Revise Reactor Steam Dome Pressure Low Instrumentation Function Allowable Value PLA-7950, Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-7950)2021-10-0505 October 2021 Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-7950) PLA-7897, Proprosed Amendment to Licenses NPF-14 and NPF-22: License Amendment Request to Revise Technical Specification to Adopt Risk Informed Completion Times TSTF-505, Rev 2, Provide Risk Informed Extended Completion.2021-04-0808 April 2021 Proprosed Amendment to Licenses NPF-14 and NPF-22: License Amendment Request to Revise Technical Specification to Adopt Risk Informed Completion Times TSTF-505, Rev 2, Provide Risk Informed Extended Completion. ML20245E1922020-09-0101 September 2020 Talen Energy - Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements PLA-7880 PLA-7866, Electric Station Proposed Amendment Licenses NPF-14 and - NPF-22: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules PLA-78662020-06-25025 June 2020 Electric Station Proposed Amendment Licenses NPF-14 and - NPF-22: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules PLA-7866 PLA-7842, Proposed Amendment to Licenses NPF-14 and NPF-22: Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit PLA-72482020-05-26026 May 2020 Proposed Amendment to Licenses NPF-14 and NPF-22: Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit PLA-7248 PLA-7823, Proposed Amendment to Licenses NPF-014 and NPF-022: Revision to the Dose Consequence Analysis for a Loss of Coolant Accident2020-01-0202 January 2020 Proposed Amendment to Licenses NPF-014 and NPF-022: Revision to the Dose Consequence Analysis for a Loss of Coolant Accident PLA-7783, Proposed Amendment to Licenses: Application of Advanced Framatome Methodologies and TSTF-535 PLA-77832019-07-15015 July 2019 Proposed Amendment to Licenses: Application of Advanced Framatome Methodologies and TSTF-535 PLA-7783 PLA-7772, Application to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2019-03-28028 March 2019 Application to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. 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 PLA-7729, Technical Specifications Task Force Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-12-0404 December 2018 Technical Specifications Task Force Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. PLA-7605, Change to Submittal Regarding License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-522-A2017-05-17017 May 2017 Change to Submittal Regarding License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-522-A PLA-7528, Supplemental Information for License Amendment Request to Address Secondary Containment Access Openings2016-09-13013 September 2016 Supplemental Information for License Amendment Request to Address Secondary Containment Access Openings PLA-7486, Proposed Amendment Request to Address Secondary Containment Access Openings2016-07-27027 July 2016 Proposed Amendment Request to Address Secondary Containment Access Openings ML16181A4172016-06-29029 June 2016 Projected Income Statement and Calculation of Six-Month Fixed Costs (Redacted) ML16181A4152016-06-29029 June 2016 Request for Order Approving Indirect Transfer of Control - PLA-7500 ML16181A4192016-06-29029 June 2016 Capacity Factor Assumptions (Redacted) PLA-7441, Supplemental Information on Technical Specification Changes to Adopt Traveler TSTF-4252016-01-29029 January 2016 Supplemental Information on Technical Specification Changes to Adopt Traveler TSTF-425 PLA-7384, Proposed Amendment No. 292, Temporary Change to Allow Replacement on Unit 1 480 V Ess Load Center Transformers in Unit 2 Technical Specifications 3.8.7 and 3.7.12016-01-28028 January 2016 Proposed Amendment No. 292, Temporary Change to Allow Replacement on Unit 1 480 V Ess Load Center Transformers in Unit 2 Technical Specifications 3.8.7 and 3.7.1 PLA-7378, Proposed Amendment No. 317 to License NPF-14 and Proposed Amendment No. 289 to License NPF-22: Supplement to Change Milestone 8 Date2015-08-28028 August 2015 Proposed Amendment No. 317 to License NPF-14 and Proposed Amendment No. 289 to License NPF-22: Supplement to Change Milestone 8 Date PLA-7360, Supplemental Information to License Amendment Request for Changes in RCS Pressure and Temperature (P/T) Limits2015-07-16016 July 2015 Supplemental Information to License Amendment Request for Changes in RCS Pressure and Temperature (P/T) Limits ML15091A6612015-03-19019 March 2015 Evaluation of Proposed Change Regarding Proposed License Amendment to Adopt Emergency Action Level Scheme NEI 99-01, Susquehanna, Units 1 and 2 - Proposed License Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2015-03-19019 March 2015 Susquehanna, Units 1 and 2 - Proposed License Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. NEI 99-01, Susquehanna, Units 1 and 2 - Evaluation of Proposed Change Regarding Proposed License Amendment to Adopt Emergency Action Level Scheme2015-03-19019 March 2015 Susquehanna, Units 1 and 2 - Evaluation of Proposed Change Regarding Proposed License Amendment to Adopt Emergency Action Level Scheme ML15091A6602015-03-19019 March 2015 Proposed License Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. 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. ML14195A1132014-07-11011 July 2014 Enclosure to PLA-7191 Application for Order Approving Indirect Transfer of Control of Facility Operating License Nos. NPF-14 and NPF-22 and Conforming Amendments ML14042A1152014-01-29029 January 2014 License Amendment Request - Increase of the Allowable Gas Treatment System Maximum Flow Rates from Secondary Containment PLA-6977, Proposed Amendment No. 313 to License NPF-14 and Proposed Amendment No. 285 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.5.1.122013-06-0606 June 2013 Proposed Amendment No. 313 to License NPF-14 and Proposed Amendment No. 285 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.5.1.12 PLA-6915, Proposed Amendment No. 312 to Unit 1, and Proposed Amendment No. 284 to Unit 2 Low Pressure Safety Limit and Reference Changes2012-12-19019 December 2012 Proposed Amendment No. 312 to Unit 1, and Proposed Amendment No. 284 to Unit 2 Low Pressure Safety Limit and Reference Changes PLA-6825, Proposed Amendment No. 310 to License NPF-14 and Proposed Amendment No. 282 to License NPF-22: Change to Tech Spec SR 3.8.1.9, 3.8.1.11, 3.8.1.12, and 3.8.1.19 to Increase Diesel Generator Minimum Steady State Voltage2012-09-18018 September 2012 Proposed Amendment No. 310 to License NPF-14 and Proposed Amendment No. 282 to License NPF-22: Change to Tech Spec SR 3.8.1.9, 3.8.1.11, 3.8.1.12, and 3.8.1.19 to Increase Diesel Generator Minimum Steady State Voltage PLA-6817, Temporary Change to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1 4160 V Buses Unit 2 Technical Specifications 3.8.7 and 3.7.1 PLA-68172012-03-0808 March 2012 Temporary Change to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1 4160 V Buses Unit 2 Technical Specifications 3.8.7 and 3.7.1 PLA-6817 ML11152A0092011-07-21021 July 2011 Issuance of Amendment Approval of the PPL Susquehanna, LLC Cyber Security Plan PLA-6695, Amend. Request No. 308 to License NPF-14 & Amend. Request No. 279 to License NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-514, Rev. 3, Revise BWR Operability Requirements & Actions RCS Leakage Instrumentation2011-04-0808 April 2011 Amend. Request No. 308 to License NPF-14 & Amend. Request No. 279 to License NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-514, Rev. 3, Revise BWR Operability Requirements & Actions RCS Leakage Instrumentation PLA-6628, Proposed Amendment No. 306 to License NPF-14 & Proposed Amendment No. 277 to License NPF-22: Withdrawal & Resubmittal of Request for Approval of the Cyber Security Plan2010-07-22022 July 2010 Proposed Amendment No. 306 to License NPF-14 & Proposed Amendment No. 277 to License NPF-22: Withdrawal & Resubmittal of Request for Approval of the Cyber Security Plan PLA-6606, Submittal of NRC Notification of NPDES Permit Renewal Application2010-03-26026 March 2010 Submittal of NRC Notification of NPDES Permit Renewal Application PLA-6556, License Renewal Application (LRA) Amendment to LRA Commitment 602009-09-0909 September 2009 License Renewal Application (LRA) Amendment to LRA Commitment #60 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-6520, Third Annual Amendment to the Application for Renewed Operating License Numbers NPF-14 and NPF-22 Pursuant to 10 CFR 54.21(b)2009-05-28028 May 2009 Third Annual Amendment to the Application for Renewed Operating License Numbers NPF-14 and NPF-22 Pursuant to 10 CFR 54.21(b) 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-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-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 2023-06-08
[Table view] |
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Bryce L. Shriver PPL Susquehanna, LLC Senior Vice President and 769 Salem Boulevard Chief Nuclear Officer Berwck, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 blshriver@pplweb com
'
- TM TM, OCT 23* 202 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT NO. 1 TO PROPOSED AMENDMENT NO. 247 TO UNIT 1 LICENSE NO. NPF-14 AND PROPOSED AMENDMENT NO. 212 TO UNIT 2 LICENSE NO. NPF-22: REVISION TO THE RPV MATERIAL SURVEILLANCE PROGRAM Docket Nos. 50-387 PLA-5528 and 50-388
Reference:
- 1) Letterfrom W. H. Bateman (USNRC) to C. Terry (BWR VIP Chairman)titled, "Safety EvaluationRegardingEPRI ProprietaryReport 'BWR Vessel and InternalsProject, B WR IntegratedSurveillanceProgramPlan (B WR VIP- 78) ' and 'B WI? VIP-86: B WIR Vessel and InternalsProject,BWR IntegratedSurveillanceProgramImplementation Plan,"' dated February1, 2002.
- 2) RegulatoryIssue Summary No. 2002-05, "NRC Approval ofBoiling Water Reactor Pressure Vessel IntegratedSurveillanceProgram," datedApril 8, 2002.
- 3) PLA-5498 from R. L. Anderson to USNRC Document ControlDesk titled, "Proposed Amendment No. 247 to Unit 1 License No. NPF-14 and ProposedAmendment No. 212 to Unit 2 License No. NPF-22: Revision to the RPV MaterialSurveillance Program," dated July 25, 2002.
The purpose of this letter is to respond to NRC Staff's questions on our proposed changes to the Susquehanna Steam Electric Station Final Safety Analysis Report (Susquehanna SES FSAR) for Unit 1 and Unit 2. This proposed change revises the Reactor Pressure Vessel Material Surveillance Program in accordance with References 1 and 2. This letter supercedes Reference 3.
Document Control Desk PLA-5528 At the request of the NRC staff, Supplement 1 revised the following:
"* The Technical Analysis in Attachment 1 was revised to clearly state that the methodology used to recalculate the fluence calculations will be in accordance with the requirements of Regulatory Guide 1.190.
"* FSAR Section 4.1.4.5 was revised to state that revisions to the fluence calculations will use NRC approved methodology that meets Regulatory Guide 1.190.
"* FSAR Section 5.3 and Tables 5.3-1b, 5.3-2b and 5.3-3 were revised to state that the Integrated Surveillance Program consists of BWRVIP-86, BWRVIP-78, the BWRVIP responses to NRC RAIs dated December 22, 2001 and May 30, 2001, and NRC's Safety Evaluation dated February 1, 2002.
Supplement 1 did not change the No Significant Hazards Considerations and Environmental Assessment from the previous submittal. to this letter is the "Safety Assessment" supporting this change. is the No Significant Hazards Considerations evaluation performed in accordance with the criteria of 10 CFR 50.92 and the Environmental Assessment. to this letter contains the applicable pages of the Susquehanna SES FSAR for Unit 1 and Unit 2, marked to show the proposed change.
Consistent with the process established between the NRC and the BWRVIP, this change is being processed as a license amendment to facilitate NRC review and approval.
PPL plans to implement the proposed changes in the Spring of 2003 to support deletion of work from the Unit 2 1 1 th Refueling and Inspection Outage. Therefore, we request NRC complete its review of this change by December 1, 2002 with the changes effective 30 days after approval.
Any questions regarding this request should be directed to Mr. Cornelius T. Coddington at (610) 774-4019.
Sincerely, L. Shriver
Document Control Desk PLA-5528 Attachments: Affidavits Attachment 1 - Safety Assessment - Revision to the Reactor Pressure Vessel Material Surveillance Program Attachment 2 - No Significant Hazards Considerations and Environmental Assessment Attachment 3 - Final Safety Analysis Report Mark-Ups copy: NRC Region I Mr. D. J. Allard, PA DEP Mr. S. L. Hansell, NRC Sr. Resident Inspector Mr. E. M. Thomas, NRC Project Manager Mr. R. Janati, DEP/BRP
BEFORE THE BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of PPL Susquehanna, LLC: Docket No. 50-387 SUPPLEMENT NO. 1 TO PROPOSED AMENDMENT NO. 247 TO LICENSE NPF-14:
REVISION TO THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM UNIT NO. 1 Licensee, PPL Susquehanna, LLC, hereby files a revision to its Facility Operating License No. NPF-14 dated July 17, 1982.
This amendment involves a revision to the Susquehanna SES Final Safety Analysis Report Specifications.
? *--- "--- PPL Susquehanna, LLC
- -. .- By:
B. 4. Shn'*er Sr. Vice-President and Chief Nuclear Officer Sworn to and subscribed before me Noctaial Seal this day of Ab.-', 2002. Laurie Minto, Notary Public Salem T'wp,. Luzem County My Commluion Expires July 24, 2006 Memrr ,m*wtmfAa=scWn tNoarWles Notary Public
BEFORE THE BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of PPL Susquehanna, LLC: Docket No. 50-388 SUPPLEMENT NO. 1 TO PROPOSED AMENDMENT NO. 212 TO LICENSE NPF-22:
REVISION TO THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM UNIT NO. 2 Licensee, PPL Susquehanna, LLC, hereby files a revision to its Facility Operating License No. NPF-22 dated March 23, 1984.
This amendment involves a revision to the Susquehanna SES Final Safety Analysis Report.
-,< -,'-. .. - .. . ./ f PPL Susquehanna, LLC Sr L.S V river Sr. Vice-President and Chief Nuclear Officer Sworn to and subscribed before me this A!) day of Oe.,4 o0e, 2002.
1 Notarial Seal laurie Minto, Notary Public Salem Twp.. Luzerne County My Commnilon Expires July 24, 2006 J
ier ,Ponnanqot atgon of NMoft Notary Public
Attachment I to PLA-5528 Safety Assessment Revision to the Reactor Pressure Vessel Material SSurveillance Program
Attachment 1 to PLA-5528 Page 1 of3 Safety Assessment Revision to the Reactor Pressure Vessel Material Surveillance Program The following provides the basis for the proposed revision to the reactor pressure vessel material surveillance program.
1.0 DESCRIPTION
OF THE PROPOSED CHANGE PPL Susquehanna, LLC (PPL) proposes to revise the licensing basis for Susquehanna Steam Electric Station Units 1 and 2 (SSES) by replacing the current plant-specific reactor pressure vessel (RPV) material surveillance program with the Boiling Water Reactor (BWR) Integrated Surveillance Program (ISP), which was approved by the NRC in its Safety Evaluation (SE) dated February 1, 2002 (Reference 1). The proposed revision to the SSES Final Safety Analysis Report reflecting this change is provided for information in Attachment 3.
2.0 REASON FOR THE PROPOSED CHANGE The BWR ISP was developed in response to an issue raised by the NRC staff regarding the potential lack of adequate unirradiated baseline Charpy V-notch (CVN) data for one or more materials in plant-specific RPV surveillance programs at several BWRs. The lack of baseline properties would inhibit a licensee's ability to effectively monitor changes in the fracture toughness properties of RPV materials in accordance with Appendix H to 10 CFR 50. The BWR ISP, as approved by the NRC, resolves this issue.
Implementation of the ISP will provide additional benefits. When the original surveillance materials were selected for plant-specific surveillance programs, the state of knowledge concerning RPV material response to irradiation and post irradiation fracture toughness was not the same as it is today. As a result, many facilities did not include what would be identified today as the plant's limiting RPV materials in their surveillance programs. Hence, this effort to identify and evaluate materials from other BWRs, which may better represent a facility's limiting materials, should improve the overall evaluation of BWR RPV embrittlement. Second, the inclusion of data from the testing of BWR Owners' Group (BWROG) Supplemental Surveillance Program (SSP) capsules will improve the overall quality of the data being used to evaluate BWR RPV
Attachment 1 to PLA-5528 Page 2 of 3 embrittlement. Finally, implementation of the ISP is also expected to reduce the cost of surveillance testing and analysis since surveillance materials that are of little or no value (either because they lack adequate unirradiated baseline CVN data or because they are not the best representative materials) will no longer be tested.
3.0 TECHNICAL ANALYSIS
Reference I concludes that the proposed ISP, if implemented in accordance with the conditions in the SE, has been determined to be an acceptable alternative to all existing BWR plant-specific RPV surveillance programs for the purpose of maintaining compliance with the requirements of Appendix H to 10 CFR Part 50 through the end of current facility 40 year operating licenses. Reference 1 requires that each licensee (1) provide information regarding what specific neutron fluence methodology will be implemented as part of participation in the ISP and (2) address the neutron fluence methodology compatibility issue as it applies to the comparison of neutron fluences calculated for its RPV versus the neutron fluences calculated for surveillance capsules in the ISP which are designated to represent its RPV. This information is provided in the following discussion.
The SSES Technical Specifications, as discussed in Amendment No. 200 to SSES Unit 1 Operating License (NPF-14) and Amendment No. 174 to SSES Unit 2 Operating License (NPF-22) require that new P-T curves be implemented based on updated fluence calculations by May 1, 2005 and May 1, 2006 (Unit 2 and Unit 1 respectiviely). See Reference 2 for additional information. The methodology used for the recalculation of the fluence will be in accordance with the requirements of Regulatory Guide 1.190.
PPL intends to use the BWRVIP RAMA code or other NRC approved methodology that meets Regulatory Guide 1.190 to revise the calculations for both Units 1 and 2. The RAMA code will perform a full 3D-neutron transport solution to determine fluence within the vessel. The analysis will use the BUGLE-96 data library as recommended by Regulatory Guide 1.190. It will perform a full uncertainty analysis to determine the accuracy of the calculation. The Susquehanna SES FSAR will be updated to include reference to the requirements of Regulatory Guide 1.190 when the new fluence calculation methodology is utilized.
Attachment 1 to PLA-5528 Page 3 of 3 The BWRVIP's anticipated schedule for completion of the BWRVIP RAMA code is December 2002. The BWRVIP intends to submit a topical report on the RAMA code to the NRC for review, with the objective of receiving a safety evaluation in 2003 approving use of the methodology.
The first surveillance capsule to be tested under the ISP is the River Bend 1830 capsule. The test report is scheduled to be submitted to the NRC by February 2003. Coincidentally, these capsules, according to the ISP, are the substitute capsules for SSES Unit 2. Thus in accordance with the ISP, the SSES Unit 2 capsule will not be removed and tested.
The ISP requires the Unit 1 surveillance capsules be removed in 2012 and tested in 2013. The Unit 1 fluence calculations will be reevaluated both in 2006 and after this ISP testing.
REFERENCES:
- 1. Letter, W. H. Bateman (USNRC) to C. Terry (BWRVIP Chairman), "Safety Evaluation Regarding EPRI Proprietary Report 'BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78)' and
'BWRVIP-86: BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan"', dated February 1, 2002.
- 2. Letter, D. S. Collins (USNRC) to R. G. Byram (PPL), "Susquehanna Steam Electric Station Units 1 and 2 - Issuance of Amendment RE: Reactor Pressure Vessel Pressure-Temperature Limit Curves", dated February 7, 2002.
Attachment 2 to PLA-5528 No Significant Hazards Considerations and Environmental Assessment
Attachment 2 to PLA-5528 Page 1 of 2 No Significant Hazards Considerations and Environmental Assessment The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
PPL proposes to revise the licensing basis for SSES by replacing the plant-specific RPV material surveillance program with the BWR ISP. This change is acceptable because the BWR ISP has been approved by the NRC staff as meeting the requirements of paragraph III.C of Appendix H to 10 CFR 50 for an integrated surveillance program.
In accordance with the criteria set forth in 10 CFR 50.92, PPL has evaluated the proposed TS change and determined it does not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the proposed change involve a significantincrease in the probabilityor consequences of an accidentpreviously evaluated?
No. The proposed change implements an integrated surveillance program that has been evaluated by the NRC staff as meeting the requirements of paragraph III.C of Appendix H to 10 CFR 50. Consequently, the proposed change does not significantly increase the probability of any accident previously evaluated. The proposed change provides the same assurance of RPV integrity. As a result, the consequences of any accident previously evaluated are not significantly increased.
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 accidentfrom any accidentpreviously evaluated?
No. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or changes in methods governing normal plant operation. The proposed change maintains an equivalent level of RPV material surveillance and does not introduce any new accident initiators. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Attachment 2 to PLA-5528 Page 2 of 2
- 3. Does the proposedchange involve a significantreduction in a margin ofsafety?
No. The proposed change has been evaluated as providing an acceptable alternative to the plant-specific RPV material surveillance program that meets the requirements of the regulations for RPV material surveillance. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
ENVIRONMENTAL CONSIDERATION 10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions, which are eligible for categorical exclusion from the requirement to perform an environmental assessment.
A proposed amendment to an operating license for a facility does not require an environmental assessment if operation of the facility in accordance with the proposed amendment would not (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (3) result in a significant increase in individual or cumulative occupational radiation exposure. PPL has evaluated the proposed change and has determined that the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Accordingly, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with issuance of the amendment. The basis for this determination, using the above criteria, follows:
Basis
- 1. As demonstrated in the No Significant Hazards Consideration Evaluation, the proposed amendment does not involve a significant hazards consideration.
- 2. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be installed) or change in methods governing normal plant operation.
There is no significant increase in individual or cumulative occupational radiation exposure. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be installed) or change in methods governing normal plant operation.