Letter Sequence Request |
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MONTHYEARPLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version2008-10-30030 October 2008 Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version Project stage: Request PLA-6458, Revised Affidavit for Requested Amendment to Unit 2 License NPF-22: MCPR Safety Limits2008-11-21021 November 2008 Revised Affidavit for Requested Amendment to Unit 2 License NPF-22: MCPR Safety Limits Project stage: Request ML0835101402008-12-23023 December 2008 Request for Withholding Information from Public Disclosure Susquehanna Steam Electric Station, Unit 1 Project stage: Withholding Request Acceptance ML0902707992009-01-27027 January 2009 ME0067, Acceptance Review Letter to Licensee Project stage: Acceptance Review ML0903303912009-02-26026 February 2009 Issuance of Amendment Changes in MCPR Safety Limits Project stage: Approval 2008-12-23
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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] Category:Report
MONTHYEARPLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 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-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-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-7959, Owner'S Activity Report PLA-79592021-07-15015 July 2021 Owner'S Activity Report PLA-7959 PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 12018-11-27027 November 2018 Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents PLA-7559, Flooding Mitigating Strategies Assessment (MSA) Report2016-12-19019 December 2016 Flooding Mitigating Strategies Assessment (MSA) Report ML16231A5092016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents)(Cac Nos. MF4364 and MF4365) PLA-7491, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident2016-06-30030 June 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application ML15356A2472016-01-20020 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulation Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-08-20020 August 2015 Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 PLA-7311, Negative Blind Specimen Report, PLA-73112015-04-0909 April 2015 Negative Blind Specimen Report, PLA-7311 ML15090A3002015-04-0101 April 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC Nos. MF4364 & MF4365) PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 PLA-7175, (SSES)- 10 CFR 50.46 - Annual Report2014-06-20020 June 2014 (SSES)- 10 CFR 50.46 - Annual Report ML14156A2342014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0288 and MF0289) ML14056A4492014-05-0606 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tacs MF0183, MF0184) ML14113A5552014-04-23023 April 2014 Draft Staff Assessment of Seismic Walkdown Report Near-term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident; PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit 1. Docket No. 50-387 ML14085A3982014-03-26026 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident PLA-7145 ML14085A4262014-03-26026 March 2014 Apendix B IPEEE Adequacy Review ML14010A3712014-01-15015 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Susquehanna Steam Electric Station, Units 1 and 2, TAC Nos.: MF0888 and MF0889 PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-69382012-11-21021 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 PLA-6809, Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady.2012-09-18018 September 2012 Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady. ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML12068A1952012-02-23023 February 2012 Technical Requirements Manual Unit 2 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML13046A1372011-11-30030 November 2011 Enclosure 8 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1102504712011-01-14014 January 2011 Technical Requirements Manual PLA-6657, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments2010-10-0707 October 2010 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments ML1020401442010-05-12012 May 2010 Replacement Steam Dryer Report, Unit 1, Start-Up, 107% Power Test Plateau 05/11/10 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1004801852009-12-31031 December 2009 BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report PLA-6568, Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-65682009-10-0505 October 2009 Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-6568 PLA-6523, Fourteen Refueling Outage Owner'S Activity Report PLA-65232009-07-31031 July 2009 Fourteen Refueling Outage Owner'S Activity Report PLA-6523 ML0921703332009-07-31031 July 2009 Enclosure 2 to PLA-6542 - SSES Replacement Steam Dryer and Flow Induced Vibration Report Unit 2 Start-Up 107.0% Power Test Plateau. (Non-Proprietary) ML0918004602009-06-23023 June 2009 Submittal of Work Environment Improvement Plan, PLA-6528 PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 February 2009 Enclosure 5 to PLA-6484, Susquehanna Replacement Steam Dryer Updated Stress Analysis at Extended Power Uprate Conditions, Non-Proprietary Version Engineering Report 0000-0095-2113-NP-R0 ML0907704482009-02-27027 February 2009 Enclosures 6, 7, 8 and 9 to PLA-6484, Revised Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation, Non-Proprietary Version Engineering Report 0000-0096-5766-NP-R1 PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version2008-10-30030 October 2008 Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version 2024-07-23
[Table view] Category:Technical
MONTHYEARPLA-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-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-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 12018-11-27027 November 2018 Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents PLA-7491, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident2016-06-30030 June 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14010A3712014-01-15015 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Susquehanna Steam Electric Station, Units 1 and 2, TAC Nos.: MF0888 and MF0889 PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-69382012-11-21021 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML1102504712011-01-14014 January 2011 Technical Requirements Manual ML1004801852009-12-31031 December 2009 BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report ML0921703332009-07-31031 July 2009 Enclosure 2 to PLA-6542 - SSES Replacement Steam Dryer and Flow Induced Vibration Report Unit 2 Start-Up 107.0% Power Test Plateau. (Non-Proprietary) PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 February 2009 Enclosure 5 to PLA-6484, Susquehanna Replacement Steam Dryer Updated Stress Analysis at Extended Power Uprate Conditions, Non-Proprietary Version Engineering Report 0000-0095-2113-NP-R0 ML0907704482009-02-27027 February 2009 Enclosures 6, 7, 8 and 9 to PLA-6484, Revised Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation, Non-Proprietary Version Engineering Report 0000-0096-5766-NP-R1 PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version2008-10-30030 October 2008 Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0828300742008-07-31031 July 2008 GE-NE 0000-0085-2413 NP-R0, Susquehanna Unit 1, Replacement Steam Dryer Vibration Instrumentation Program NRC Summary Test Report ML0810105462008-04-0101 April 2008 Attachment 2 to PLA-6346, Non-Proprietary Version of Unit 1 Main Steam Line Limit Curves ML0806602552008-02-22022 February 2008 GE-NE-000-0080-2994-NP-R2, Revision 2, Susquehanna Replacement Steam Dryer Instrumentation Acceptance Criteria - Dryer Mounted Instrumentation. ML0803800892008-01-31031 January 2008 Engineering Report, GE-NE-0000-0079-2250-NP-R0, Susquehanna Replacement Steam Dryer Stress Analysis at Extended Power Uprate Conditions ML0728501222007-10-10010 October 2007 BWRVIP-145NP, BWR Vessel and Internals Project, Evaluation of Susquehanna Unit 2 Top Guide and Core Shroud Material Samples Using RAMA Fluence Methodology ML0720103642007-06-30030 June 2007 GE-Hitachi Nuclear Energy Americas LLC Report GE-NE-0000-0061-0595-NP-R1, Susquehanna Replacement Steam Dryer Fatigue Analysis. ML0700403832006-12-31031 December 2006 GE-NE-OOOO-0061-0595-NP-RO, Engineering Report: Susquehanna Replacement Steam Dryer Fatigue Analysis. PLA-6136, Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-61362006-11-29029 November 2006 Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-6136 PLA-5995, Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI)2005-12-15015 December 2005 Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI) PLA-5983, Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information2005-12-0101 December 2005 Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information PLA-6130, Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA).2005-10-31031 October 2005 Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA). ML0601203532005-10-13013 October 2005 Proposed Amendment No. 281 and Proposed Amendment No. 251: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67 ML0507504332005-03-11011 March 2005 PROJ0704 - BWRVIP-1 17NP: BWR Vessel and Internals Project, RAMA Fluence Methodology Plant Application - Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5 ML0710400422003-08-0101 August 2003 Environmental Studies in the Vicinity of the Susquehanna Steam Electric Station 2002 Water Quality and Fishes. PLA-5616, Annual Personnel Exposure Report PLA-56162003-04-28028 April 2003 Annual Personnel Exposure Report PLA-5616 ML18024A0561978-09-15015 September 1978 Letter Supplementing PP&L Letters Dated April 17, 1978 and July 14, 1978 and Attaching a Final Report of a Deficiency in Seismic Qualification of Medium Voltage, Metal Clad, Safeguards Switchgear ML18026A2181978-04-14014 April 1978 SSES Design Assessment Report, Revision 1 ML18025A6661978-02-28028 February 1978 Structural Integrity Test Report Containment Structure Unit 1 ML18025A6671977-12-30030 December 1977 Final Report on Shear Studs ML18025A1901977-06-22022 June 1977 Letter Enclosing an Interim Report of Reportable Deficiency Regarding Unsatisfied Field Welding and Inspection of Shear Studs ML18026A1191977-03-22022 March 1977 Results of Non-Nuclear Hot Test with the Relief System in the Philippsburg Nuclear Power Plant ML18025A0911976-05-31031 May 1976 Ecological Studies of the North Branch Susquehanna River in the Vicinity of the Susquehanna Steam Electric Station - Progress Report for the Period January-December 1974 ML18023A8811975-08-29029 August 1975 Letter Transmitting Report on Deficiency in Box Column Supports for the Susquehanna Nuclear Plant. ML18025A2011975-08-29029 August 1975 Definitive Report of Deficiencies in Fabricated Structural Steel Members (Box Column Supports) ML18023A8841975-07-25025 July 1975 Letter Regarding an Interim Report of Reportable Deficiency ML18023A8871975-04-0404 April 1975 Letter Attaching an Interim Report on a Potential Deficiency Which Was Discussed on March 6, 1975 ML18026A1181972-12-31031 December 1972 Formation and Oscillations of a Spherical Gas Bubble Under Water 2022-03-29
[Table view] |
Text
A Britt T. McKinney PPL Susquehanna, LLC Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com OCT 3 0 2008 pp, *TM U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 274 TO UNIT 2 LICENSE NPF-22: MCPR SAFETY LIMITS PLA-6438 Docket No. 50-388 In accordance with the provisions of 10 CFR 50.90, PPL Susquehanna, LLC (PPL) is submitting a request for an amendment to the Technical Specifications for Susquehanna Steam Electric Station (SSES) Unit 2.
The proposed change revises the Section 2.1.1.2 Minimum Critical Power Ratio Safety Limits (MCPRSLs) for two-loop and single-loop operation.
There are no new regulatory commitments associated with this change.
The enclosures to this letter contain PPL's evaluation of this proposed change. Included are a description of the proposed change, the technical analysis of the change, the regulatory analysis of the change (No Significant Hazards Consideration and the Applicable Regulatory Requirements), and the environmental considerations associated with the change.
Enclosure 1 contains AREVA NP, Inc. proprietary information. As such, AREVA NP, Inc. requests that the information be withheld from public disclosure in accordance with 10 CFR 2.390 (a) (4) and 9.17 (a) (4). An affidavit supporting this request is contained in Attachment 1. Enclosure 2 contains a non-proprietary version of the information.
Attachment 2 provides the applicable pages of SSES Unit 2 Technical Specifications, marked to show the proposed change.
Attachment 3 provides a description of the planned Unit 2 Cycle 15 (U2C 15) core composition to assist in your review.
Attachment 4 provides the planned U2C 15 Core Loading Pattern.
'Aoocf
i Document Control Desk PLA-6438 Attachment 5 provides descriptions of the planned reload fuel bundles for U2C 15.
Attachment 6 provides a diagram of the NRC approved MCPRSL Methodology.
The proposed changes have been reviewed by the SSES Plant Operations Review Committee and the Susquehanna Review Committee.
PPL plans to implement the proposed changes in the spring of 2009 to support the startup of U2C 15 operation. Therefore, we request NRC complete its review of this change by March 12, 2009 with the changes effective upon startup following the Unit 2 14 th Refueling and Inspection Outage.
Any questions regarding this request should be directed to Mr. Charlie Manges at (570)-542-3089.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: 0 S B. T. McKinney Enclosure 1: PPL Evaluation of the Proposed Changes - Unit 2 Minimum Critical Power Safety Limits - (PROPRIETARY)
Enclosure 2: PPL Evaluation of the Proposed Changes - Unit 2 Minimum Critical Power Safety Limits - (NON-PROPRIETARY)
Attachments:
Attachment 1 - AREVA NP, Inc. Affidavit for Proprietary Information Attachment 2 - Proposed Technical Specification Changes Unit 2, (Mark-ups)
Attachment 3 - Description of the Planned Unit 2 Cycle 15 Core Composition Attachment 4 - Planned Unit 2 Cycle 15 Core Loading Pattern Attachment 5 - Descriptions of the Planned Unit 2 Cycle 15 Reload Bundles Attachment 6 - Diagram of NRC Approved Minimum Critical Power Ratio Safety Limit Methodology cc: NRC Region I Mr. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager
ENCLOSURE 2 to PLA-6438 PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits (NON-PROPRIETARY)
- 1. DESCRIPTION
- 2. PROPOSED CHANGE
- 3. BACKGROUND
- 4. TECHNICAL ANALYSIS
- 5. REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
- 6. ENVIRONMENTAL CONSIDERATIONS
- 7. REFERENCES
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 1 of 15 PPL EVALUATION
Subject:
Unit 2 Cycle 15 MCPR Safety Limits
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-22 for PPL Susquehanna, LLC (PPL), Susquehanna Steam Electric Station (SSES) Unit 2.
The proposed changes would revise the SSES Unit 2 Technical Specifications (TS)
Section 2.1.1.2 Minimum Critical Power Ratio Safety Limits (MCPRSLs) for two-loop and single-loop operation. The change to Section 2.1.1.2 is necessary as a result of Unit 2 Cycle 15 (U2C 15) cycle specific calculations.
The calculations performed to support the proposed MCPRSLs utilize NRC approved methodology and comply with NRC required license condition (Reference 7.2, Section 3.4.3.2) on power distribution uncertainties for application to Extended Power Uprate (EPU) Conditions (Reference 7.2). The calculations also account for a Part 21.
notification regarding non-conservative SPCB Critical Power correlation additive constants (Reference 7.1). AREVA has submitted the corrected additive constants to the NRC in Reference 7.3.
The proposed changes are described in detail in Section 4.0.
The requested approval date (March 12, 2009) will allow time for the Core Operating Limits Report (COLR) to be prepared and reviewed by the Plant Operation Review Committee (PORC) prior to the Spring 2009 Unit 2 refueling outage.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 2 of 15
2.0 PROPOSED CHANGE
Specifically, the proposed changes would revise the following:
2.1 TS2.1.1.2 The MCPRSLs are revised from 1.11 (two-loop operation) and 1.14 (single-loop operation) to 1.08 (two-loop operation) and 1.11 (single-loop operation) to reflect results of the cycle specific MCPRSL analysis for U2C 15.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 3 of 15
3.0 BACKGROUND
3.1 MCPR SAFETY LIMIT CHANGE Excessive thermal overheating of the fuel rod cladding can result in cladding damage and release of fission products. In order to protect the cladding against thermal overheating due to boiling transition, MCPRSLs (Section 2.1.1.2 of the SSES Unit 2 Technical Specifications) were established.
NUREG-0800, Standard Review Plan, Section 4.4, specifies an acceptable, conservative approach to define the MCPRSLs. Specifically, a MCPR value is specified such that at least 99.9% of the fuel rods are expected to avoid boiling transition during normal operation or Anticipated Operational Occurrences (AOOs). Boiling transition is predicted using a correlation based on test data (i.e., a Critical Power Correlation). The MCPRSL calculation accounts for various uncertainties such as feedwater flow, feedwater temperature, pressure, power distribution uncertainties (including the effects of fuel channel bow), and uncertainty in the Critical Power Correlation.
Both two-loop and single-loop MCPRSL values have been calculated using NRC approved analytical methods with the SPCB critical power correlation for ATRIUMTM- 10 fuel. The AREVA methodology has been reviewed by the NRC for applicability to EPU Conditions (Reference 7.2). Corrected SPCB additive constants have been applied to address a non-conservatism reported by AREVA through Part 21 (Reference 7.1.)
AREVA has submitted the corrected additive constants to NRC in Reference 7.3. The proposed MCPRSL values (1.08 for two-loop operation and 1.11 for single-loop operation) assure that at least 99.9% of the fuel rods are expected to avoid boiling transition during normal operation or anticipated operational occurrences.
The MCPRSL analysis is the first in a series of analyses that assure the core loading is operated in a safe manner. Prior to startup, analyses are performed (using NRC approved methodologies referenced in TS Section 5.6.5.b) to determine changes in the Critical Power Ratio (CPR) as a result of anticipated operational occurrences. These results are combined with the MCPRSL values to generate the MCPR operating limits (MCPROLs) that are identified in the Core Operating Limits Report (COLR). The COLR operating limits assure that the MCPRSL will not be exceeded during normal operation or anticipated operational occurrences, providing the required protection for the fuel rod cladding. Postulated accidents are also analyzed prior to startup and the results shown to be within the NRC approved criteria.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 4 of 15
4.0 TECHNICAL ANALYSIS
4.1 MCPR SAFETY LIMIT CHANGE This TS change decreases the MCPRSL from the current Unit 2 limits of 1.11 for two-loop and 1.14 for single-loop to the proposed limits of 1.08 for two-loop and 1.11 for single-loop. Descriptions of the methodology, inputs, results, and the reasons for the decrease in the MCPRSL are provided in the following subsections.
Methodology The two-loop and single loop MCPRSL values are calculated using the following methods:
" ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
" EMF-2209(P)(A) Revision 2, SPCB Critical Power Correlation, Framatome ANP, September 2003.
These methods are included in TS 5.6.5.b.
In the MCPRSL methodology, a Monte Carlo procedure is used to evaluate reactor system measurement uncertainties and fuel related uncertainties so that during sustained operation at the MCPRSL, at least 99.9% of the fuel rods in the core would be expected to avoid boiling transition. The effects of channel bow were accounted for in the MCPRSL analysis using the ANF-524(P)(A) methodology.
MICROBURN-B2 (MB2) was used to design the cycle and MB2/POWERPLEX-III CMSS will be used for monitoring. The exposure-specific radial and axial power distribution inputs were generated using MB2. The exposure-specific local power distribution inputs were generated using CASMO-4 (C4). The C4/MB2 code system has been approved by the NRC and is described in EMF-2158(P)(A), Rev., 0 which is listed in TS 5.6.5.b. AREVA nuclear design methods including, C4/MB2, have been determined to be applicable to SSES EPU conditions. (Reference 7.2, Section 2.8.7.4.)
A depiction of the MCPRSL analysis process, including applicable methodology reports, is provided in Attachment 6. The AREVA MCPRSL methodology was found to be applicable to EPU conditions, subject to additional penalties on power distribution uncertainties (Reference 7.2). Uncertainties are described in the next section.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 5 of 15 AREVA notified the NRC of a non-conservatism in the SPCB CPR correlation additive constants (Reference 7.1). The U2C 15 MCPRSL analysis applied the corrected additive constants that have been submitted to the NRC in EMF-2209 (P), Revision 2, Addendum 1 (Reference 7.3).
Uncertainties The following uncertainties were applied for the U2C15 MCPRSL analysis. These uncertainties are applicable to EPU conditions (Reference 7.2, Section 2.8.7). Radial and local power distribution uncertainties conform to the license condition specified for EPU (Reference 7.2, Section 2.8.7.3.1, Page 185).
Parameter Standard Deviation Basis Reactor System Related Uncertainties Feedwater Flow Rate 1.76% ANF-524(P)(A), Table 5.1.
Feedwater Temperature 0.76% ANF-524(P)(A), Table 5.1.
Core Pressure 0.50% ANF-524(P)(A), Table 5.1.
Total Core Flow Rate Two-Loop 2.50% ANF-524(P)(A), Table 5.1.
Single-Loop 6.00% PLA-2520, SLO Report Transmittal, Section 15.C.2.
Fuel Related Uncertainties
[
I
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 6 of 15 Channel Bow NRC Bulletin 90-02 was issued to ensure that the effects of channel box bow on the CPR calculations are properly taken into account. In response to NRC Bulletin 90-02, AREVA issued Supplement 1 to their CPR Methodology, ANF-524(P)(A). The ANF-524(P)(A) methodology incorporates the effects of channel bow on CPR through the MCPRSL calculation.
Prior to Unit 2 Cycle 14 (U2C14), SSES experienced significant operational difficulty due to channel bow. PPL's root cause analysis identified shadow corrosion induced channel bow in Zr-2 fuel channels. Subsequently, PPL implemented a large scale channel replacement strategy by re-channeling suspect Zr-2 fuel channels with new Zr-4 fuel channels. During the U2-13RIO (Refueling and Inspection Outage), PPL completed re-channeling of all once burned fuel assemblies with new 100 mil Zr-4 fuel channels. Also during the outage, all fresh fuel assemblies received new 100 mil Zr-4 fuel channels. The re-channeling was performed to eliminate the effects of shadow corrosion induced channel bow for U2C14 and future operating cycles. New Zr-4 fuel channels will be placed on fresh fuel for U2C 15.
For U2C 15, PPL requested that AREVA use their standard, nominal mean channel bow assumptions based on the following: 1) All fuel channels to be used in the U2C15 core have had no more than one cycle's worth of irradiation prior to U2C15 due to the PPL rechanneling campaigns performed prior to U2C 14, and 2) All fuel channels used in the U2C15 core are first-lifetime, 100 mil Zr-4 channels. (U2C15 contains no Zr-2 fuel channels.) Based on these facts, all of the fuel channels to be used in U2C15 are within the assumptions of the AREVA channel bow experience base. AREVA channel bow data used in calculating two-loop and single-loop MCPRSL are shown below:
[
]
Fluence gradient channel bow is managed during core design per GE-SIL 320 Supplements 1, 2 and 3. All peripheral fuel assemblies in U2C14 will be discharged from the U2C 15 core. All U2C 15 fuel channels will experience no more than two cycles of irradiation due to the PPL rechanneling campaigns performed during U2-13RIO. As a result, U2C 15 fuel channel exposures at end of U2C 15 will be significantly below the threshold for breakaway fluence induced growth (approx. 40 GWD/MT), effectively
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 7 of 15 mitigating inward and outward fluence gradient induced bow.
PPL maintains a fuel channel monitoring program and will continue to monitor fuel channel performance during the operating cycle.
Design Basis Power Distributions The U2C15 core consists of a full core of AREVA's ATRIUM TM-10 fuel design. U2C15 has been designed for Extended Power Uprate operating conditions. The core composition is provided as Attachment 3 and the corresponding core loading pattern is provided as Attachment 4. The fresh fuel bundles for Unit 2 Cycle 15 are split into five different neutronic assembly types, according to their enrichment and gadolinia distributions, as described in Attachment 5. The descriptions of the previous U2C14 core loading and exposed fuel assemblies used in U2C15 can be found in the Susquehanna FSAR Section 4.3.
The design basis radial, local, and axial power distributions at each cycle exposure point were evaluated to determine potentially limiting conditions. These power distributions are conservative compared to power distributions that would exist during reactor operation when the core is at the MCPROL and the MCPRSL could be reached during an AOO (Reference ANF-524(P)(A), Section 5.0). Design basis power distributions are representative of operation within the approved EPU (ARTs/MELLLA) operating domain.
Results Summary A summary of the MCPRSL calculations performed by AREVA is provided in the following tables:
Percentage of Pins in Boiling Transition for Two-Loop Operation
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 8 of 15 Percentage of Pins in Boiling Transition for Single-Loop Operation I1.11 0.0592 The above tables demonstrate that MCPRSLs of 1.08 (two-loop) and 1.11 (single-loop) result in < 0.1% of pins in boiling transition. Therefore, MCPRSLs of 1.08 (two-loop) and 1.11 (single-loop) are proposed for U2C 15 operation.
Comparison to U2C 14 MCPRSL For U2C 14, AREVA analyses showed that MCPRSLs of 1.10 and 1.13 could be supported for two-loop and single-loop operation, respectively. To reduce the predicted number of pins in boiling transition, PPL conservatively added 0.01 to the MCPRSL values calculated by AREVA. Therefore, the U2C14 MCPRSLs were set to 1.11 and 1.14 for two-loop and single-loop operation, respectively (Reference 7.4).
For U2C 15, MCPRSLs of 1.08 and 1.11 are supported for two-loop and single-loop operation, respectively. This represents a 0.02 reduction in the calculated MCPRSL for both two-loop operation and single-loop operation. The reduction in MCPRSL is a result of changes in the core loading pattern and in the mean channel bow values used in the.
MCPRSL analyses.
Previous cycle sensitivity analyses have shown that cycle to cycle core loading pattern changes can affect the MCPRSL by +/-0.01 (Reference 7.5, page 3). In addition, previous cycle sensitivity analyses have shown that increasing the nominal channel bow assumption by a factor of two increased the MCPRSL by +0.01 to +0.02 (Reference 7.5, page 4).
For the U2C14 analyses, twice the mean channel bow values were used. For the U2C15 analyses, the standard, nominal mean channel bow values-were used (See Subsection "Channel Bow" for the basis.). Based on the above sensitivity analyses, a 0.01 to 0.02 reduction in the value of the MCPRSL is estimated by reducing the channel bow assumption by a factor of two. The U2C15 results for two-loop operation support the trends from the channel bow sensitivity analyses.
The U2C14 MCPRSL analyses were not performed using the increased local peaking and radial peaking uncertainties required for EPU conditions. The U2C15 MCPRSL analyses were performed using the increased local peaking and radial peaking uncertainties required for EPU conditions (Reference 7.2). Increasing the local peaking and radial
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 9 of 15 peaking uncertainties results in an increase in the number of rods in boiling transition and is estimated to have a 0.00 to +0.01 impact on the MCPR results (Reference 7.2 page 205).
The following table summarizes the changes from U2C 14:
Two Loop Single Loop Current TS value 1.11 1.14 Removal of PPL added conservatism for U2C14 -0.01 -0.01 (Reference 7.4)
Use of nominal channel bow -0.01 to -0.02 -0.01-0.02 Cycle to cycle variation -0.01 to +0.01 -0.01 to +0.01 Use of increased power distribution uncertainties for EPU 0.00 to +0.01 0.00 to +0.01 U2C15 Proposed TS value 1.08 1.11 From the above table, the reduction in the value of mean channel bow for U2C 15 has the largest overall effect on reducing the MCPRSL. Given the range of sensitivities provided in the table, it is reasonable that the resulting number of rods in BT (Boiling Transition) would be lower than that of U2C 14, thus reducing the value of the MCPRSL for U2C 15.
Additional Discussion for MCPRSL Change The proposed change to the MCPRSLs does not directly or indirectly affect any plant system, equipment, component, or change the processes used to operate the plant. As discussed above, the reload analyses performed prior to U2C 15 startup will meet all applicable acceptance criteria. Therefore, the proposed changes do not affect the failure modes of any systems or components. Thus, the proposed change does not create the possibility of a previously unevaluated operator error or a new single failure. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Since the proposed change does not alter any plant system, equipment, or component, the proposed change will not jeopardize or degrade the function or operation of any plant system or component governed by TS. The proposed MCPRSLs do not involve a significant reduction in the margin of safety as currently defined in the Bases of the applicable TS sections because the MCPRSLs calculated for U2C 15 preserve the required margin of safety.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 10 of 15 Operator performance and procedures are unaffected by these proposed changes since the changes are essentially transparent to the operators and plant procedures, and do not change the way in which the plant is operated. The MCPROLs to be incorporated in the COLR (determined from the MCPRSLs and U2C 15 transient analysis results) may be different from the previous Unit 2 limits. Following the use of the methodology to analyze the U2C15 core design and future Unit 2 reloads, the reload cycle specific results are incorporated into the FSAR via inclusion of the COLR in the Technical Requirements Manual (TRM).
4.2 CONCLUSION
The proposed change to the MCPRSL does not affect any plant system, equipment, or component. Therefore, the proposed change will not jeopardize or degrade the function or operation of any plant system or component governed by TS. The proposed MCPRSL change does not involve a significant reduction in the margin of safety as currently defined in the Bases of the applicable TS sections because the MCPRSLs calculated for U2C 15 preserve the required margin of safety.
Licensing analyses will be performed (using methodology referenced in TS Section 5.6.5.b) to determine changes in the CPR as a result of anticipated operational occurrences. These results are added to the MCPRSL values proposed herein to generate the MCPROLs in the U2C 15 COLR. Thus, the MCPROLs assure that the MCPRSLs will not be exceeded during normal operation or AOOs, providing the required protection for the fuel rod cladding. The proposed change to the MCPRSLs will have a negligible impact on the results of postulated accident analyses.
Therefore, the proposed action does not involve an increase in the probability or an increase in the consequences of an accident previously evaluated in the SAR. Thus, the proposed changes are in compliance with applicable regulations. The health and safety of the public are not adversely impacted by operation of SSES as proposed.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 11 of 15 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration The proposed changes would revise the following:
TS 2.1.1.2 The two-loop and single-loop Minimum Critical Power Ratio Safety Limits (MCPRSLs) are revised to reflect results of the cycle specific MCPRSL analysis for U2C 15. The two-loop MCPRSL decreases from 1.11 to 1.08. The single-loop MCPRSL decreases from 1.14 to 1.11.
PPL has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated?
Response: No.
The proposed change to the two-loop and single-loop MCPRSLs do not directly or indirectly affect any plant system, equipment, component, or change the processes used to operate the plant. Further, the proposed MCPRSLs were generated using NRC approved methodology and meet the applicable acceptance criteria. Thus, this proposed amendment does not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
Prior to the startup of U2C 15, licensing analyses are performed (using NRC approved methodology referenced in TS Section 5.6.5.b) to determine changes in the CPR as a result of anticipated operational occurrences. These results are added to the MCPRSL values to generate the MCPROLs in the COLR. These limits could be different from those specified for the previous Unit 2 COLR. The COLR operating limits thus assure that the MCPRSL will not be exceeded during normal operation or AOOs. Postulated accidents are also analyzed prior to the startup and the results shown to be within the NRC approved criteria.
Therefore, this proposed amendment does not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 12 of 15
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The changes to the two-loop and single-loop MCPRSLs do not directly or indirectly affect any plant system, equipment, or component and therefore does not affect the failure modes of any of these items. Thus, the proposed change does not create the possibility of a previously unevaluated operator error or a new single failure.
Therefore, this proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
- 4. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
Since the proposed changes do not alter any plant system, equipment, component, or processes used to operate the plant, the proposed change will not jeopardize or degrade the function or operation of any plant system or component governed by TS.
The proposed two-loop and single-loop MCPRSLs do not involve a significant reduction in the margin of safety as currently defined in the Bases of the applicable TS sections, because the proposed MCPRSLs preserve the required margin of safety.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based upon the above, PPL concludes that the proposed amendment presents no 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.
5.2 Applicable Regulatory Requirements/Criteria Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to reactivity control systems. Specifically, General Design Criterion 10 (GDC-10), "Reactor design," in Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 13 of 15 The proposed MCPRSL values in TS Section 2.1.1.2 will ensure that 99.9% of the fuel rods in the core are not expected to experience boiling transition. This satisfies the requirements of GDC- 10 regarding acceptable fuel design limits.
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 Commission's 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.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 14 of 15
6.0 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 Susquehanna, LLC has evaluated the proposed changes and has determined that the proposed changes meet 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 As demonstrated in the No Significant Hazards Consideration Evaluation, the proposed amendment does not involve a significant hazards consideration.
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.
Non-Proprietary Version of PPL Evaluation Enclosure 2 to PLA-6438 Page 15 of 15
7.0 REFERENCES
7.1. Part 21 Notification, "Notification of Potential Part 21 Report - AREVA Minimum Critical Power Ratio," dated October 8, 2007 (Adams ML072830334) 7.2 Letter from R.V. Guzman (USNRC) to B. T. McKinney (PPL), "Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendment Regarding the 13-Percent Extended Power Uprate (TAC NOS. MD3309 and MD33 10)," dated January 30, 2008.
7.3 Request for Review and Approval of EMF-2209(P), Revision 2, Addendum 1, "SPCB Additive Constants for ATRIUM-10 Fuel," dated May 1, 2008 (Adams ML081260442) 7.4 PLA-6132, B. T. McKinney (PPL) to USNRC, "Susquehanna Steam Electric Station Proposed Amendment No. 259 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes," dated November 16, 2006.
7.5 PLA-6156, B. T. McKinney (PPL) to USNRC, "Susquehanna Steam Electric Station Request for Additional Information Regarding Proposed Amendment No. 259 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes,"
dated February 15, 2007.
Attachment 1 to PLA-6438 AREVA NP, Inc., Affidavit for Proprietary Information
AFFIDAVIT COMMONWEALTH OF VIRGINIA )
) ss.
CITY OF LYNCHBURG )
- 1. My name is Gayle F. Elliott. I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA NP information contained in the enclosure to a letter to the U.S. Nuclear Regulatory Commission from Mr. Britt T. McKinney (PPL Susquehanna, LLC) entitled, "Susquehanna Steam Electric Station Proposed Amendment to Unit 2 License NPF-22: MCPR Safety Limits," dated October 2008 and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in
accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA NP's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.
(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b) and 6(c) above.
- 7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this
_ _O day of September 2008.
Sherry L. McFaden NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/10 Reg. # 7079129 SHERRY L.MCFAOUN
- . Notary Public Commonwealth of Virginia [
7079129 My Commission Expires Oct 31, 2010
Attachment 2 to PLA-6438 Proposed Technical Specification Changes Unit 2 (Mark-ups)
PPL Rev. 3 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow
< 10 million Ibm/hr:
THERMAL POWER shall be *25% RTP.
2.1.1.2 With the reactor steam dome pressure _>785 psig and core flow
> 10 million Ibm/hr:.
. 4.4 MCPR shall be k-f for two recirculation loop operation or >_144" for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be _<1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2.hours:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
SUSUQUEHANNA - UNIT 2 TS / 2.0-1 Amendment 1&1 1,64, 1.84,1UM 19*4, 218
Attachment 3 to PLA-6438 Description of the Planned Unit 2 Cycle 15 Core Composition
Attachment 3 to PLA-6438 Page 1 of 1 Unit 2 Cycle 15 Core Composition Assembly Type Operational Histry Number of Ass mblies AREVA ATRIUM TM-10 Fresh 316 AREVA ATRIUMT M-10 Once-burned 292 AREVA ATRIUM TM-10 Twice-burned 156
Attachment 4 to PLA-6438 Planned Unit 2 Cycle 15 Core Loading Pattern
Attachment 4 to PLA-6438 Page 1 of 1
. 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 26 33 27 33 28 32 26 33 27 29 28 31 28 23 25 22.7 0.0 23.5 0.0 22.0 0.0 22.3 0.0 24.1 0.0 22.2 0.0 23.7 35.4 41.2 33 28 32 27 32 27 32 28 32 27 32 30 28 28 24 0.0 22.2 0.0 23.6 0.0 24.3 0.0 22.2 0.0 21.7 0.0 0.0 21.8 19.3 41.4 27 32 27 32 28 32 27 32 27 33 27 33 28 23 24 23.3 0.0 23.1 0.0 23.3 0.0 23.1 0.0 22.2 0.0 20.6 0.0 22.2 34.5 42.2 33 27 32 27 33 27 32 28 33 27 31 29 30 28 24 0.0 23.6 0.0 23.5 0.0 24.2 0.0 23.9 0.0 23.6 0.0 0.0 0.0 20.2 41.4 28 32 28 33 26 32 27 32 27 32 28 33 26 23 24 22.0 0.0 23.3 0.0 24.3 0.0 22.5 0.0 24.1 0.0 21.0 0.0 22.7 35.4 42.4 32 27 32 27 32 27 32 28 32 27 31 30 30 28 24 0.0 24.3 0.0 24.2 0.0 23.6 0.0 23.8 0.0 22.6 0.0 0.0 0.0 20.1 42.7 26 32 27 32 27 32 27 32 27 33 27 30 28 24 24 21.8 0.0 23.1 0.0 22.6 0.0 20.9 0.0 21.1 0.0. 21.3 0.0 19.1 39.1 41.5 33 28 32 28 32 28 32 26 31 30 30 28 23 24 0.0 22.2 0.0 23.9 0.0 23.8 0.0 24.2 0.0 0.0 0.0 19.1 36.8 42.4 27 32 27 33 27 32 27 31 27 30 23 24 24 24 .1 0.0 22.2 0.0 24.1 0.0 21.1 0.0 20.3 0.0 33.5 40.1 40.7 29 27 33 27 32 27 33 30 30 30 23 24 24 0.0 21.7 0.0 23.5 0.0 22.8 0.0 0.0 0.0 0.0 34.7 40.7 41.3 28 32 27 31 28 31 27 30 23 23 24 22.2 0.0 20.7 0.0 21.0 0.0 21.3 0.0 33.4 34.6 42.9
@ 31 0.0 30 0.0 33 0.0 29 0.0 33 0.0 30 0.0 30 0.0 19.1 28 40.0 24 41.2 24 28 28 28 30 26 30 28 23 24 24 23.7 21.8 22.2 0.0 22.9 0.0 19.1 36.7 40.7 41.3 23 28 23 28 23 28 24 24 Nuclear Fuel Type 35.3 19.4 34.4 20.2 35.4 20.1 38.9 42.0 BOC Exposure (GWd/MTU) 25 24 24 24 24 24 24 40.5 41.2 42.5 41.3 42.3 43.1 41.7 No. Per Fuel Type Description Cycle Loaded Quarter Core 23 4.128-14GV7 13 12 24 4.12B-15GV8 13 25 25 3.90B-15GV7 13 2 26 3.674B-12GV7 14 7 27 4.057-14GV8 14 35 28 4.241B-14GV8 14 31 29 3.887B-14GV80a 15 4 30 4.215B-12GV80 15 17 31 4.207B-14GV80 15 8 32 4.204B-14GV80 15 32 33 3.887B-14GV80 15 18 Susquehanna Unit 2 Cycle 15 Lower Right Quarter Core Layout by Fuel Type
Attachment 5 to PLA-6438 Descriptions of the Planned Unit 2 Cycle 15 Reload Bundles
Attachment 5 to PLA-6438 Page 1 of 5 Assembly Type 29 Reload Bundle Description (ATRIUM-10, 100mil Channel)
Bundle Average Enrichment = 3.887%
TAF 149.45" 144" 96"1 72" 36" 6"
BAF 0V
@
Attachment 5 to PLA-6438 Page 2 of 5 Assembly Type 30 Reload Bundle Description (ATRIUM-10, 100mil Channel)
Bundle Average Enrichment = 4.215%
TAF Nat 149.45" End 144" 3.956 w/o U-235 12Gd4 132" 4.391 w/o U-235 12Gd7 96" 6"
BAF oil
a Attachment 5 to PLA-6438 Page 3 of 5 Assembly Type 31 Reload Bundle Description (ATRIUM-10, 100mil Channel)
Bundle Average Enrichment = 4.207%
TAF 149.45" 144" 132" 96" 6"1 BAF 0"
Attachment 5 to PLA-6438 Page 4 of 5 Assembly Type 32 Reload Bundle Description (ATRIUM-10, 100mil Channel)
Bundle Average Enrichment = 4.204%
TAF - Nat 149.45" End 144" 3.956 w/o U-235 12Gd4 132" 4.377 w/o U-235 14Gd8 96"'
4.584 wlo U-235 14Gd8
4 Attachment 5 to PLA-6438 Page 5 of 5 Assembly Type 33 Reload Bundle Description (ATRIUM-10, 100mil Channel)
Bundle Average Enrichment = 3.887%
TAF 149.45" 144" 0 132" 96" 72" 36" 6"
BAF 0"
Attachment 6 to PLA-6438 Diagram of NRC Approved Minimum Critical Power Ratio Safety Limit Methodology
'4,°I Attachment 6 to PLA-6438 Page 1 of 1 MCPR Safety Limit Methodology
MCPRSL To Be Supported Plant, Fuel &
CPR Correlation Uncertainties ANF-524 (P)(A), Rev. 2 & Supplement 1, Rev. 2 EMF-2209 (P)(A), Rev. 2, & Addendum I EMF-2158 (P)(A), Rev. 0 SSES EPU SER Statistical Analysis of Rods in Boiling Transition Steady State Core T/H-(XCOBRA) Bundle Flow vs LHGR ANF-524 (P)(A), Rev. 2 Conservative Power Profiles (MICROBURN-B32
/ CASMO-4) Radials, Axials, EMF-2158 (P)(A), Rev. 0 Locals
<<0. 1%?
Increase MCPRSL Yes Input MCPRSL is Supported