Letter Sequence Approval |
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MONTHYEARML0703902152007-02-28028 February 2007 Stean Electric Station, Units 1 & 2, License Amendment, Issuance of Amendment Standby Liquid Control System (TAC Nos. MD1424 & MD1425) Project stage: Approval ML0706005102007-02-28028 February 2007 Tech Spec Pages for Amendments 240 and 217 Regarding Standby Liquid Control System Project stage: Acceptance Review ML0708100702007-03-19019 March 2007 Tech Spec Pages, Correction to Amendment No. 217 (TAC No. MD1425), Technical Specifications, 3.1 Reactivity Control Systems Project stage: Other ML0707404332007-03-19019 March 2007 Public Steam Electric Station, Unit 2 - Correction to Amendment No. 217 Project stage: Other 2007-02-28
[Table View] |
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Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 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) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 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 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual 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) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 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 ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative 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 IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 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) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection 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 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) 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 IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses 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) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 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 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 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) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 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 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) 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 IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses ML23073A0712023-03-30030 March 2023 Enclosure 1 - Order - Susquehanna Steam Electric Station, Units 1 and 2 and Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments ML23073A0682023-03-30030 March 2023 Letter - Susquehanna Steam Electric Station, Units 1 and 2 and Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments ML23073A0822023-03-30030 March 2023 Enclosure 2 - Draft Conforming Amendments - Susquehanna Steam Electric Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation- Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L ML23073A1072023-03-30030 March 2023 Enclosure 4 - Safety Evaluation Nonproprietary Susquehanna Steam Electric Station,Units 1,2 & Associated Independent Spent Fuel Storage Installation-Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L- ML23010A1082023-01-15015 January 2023 Issuance of Amendment No. 268 Change to Control Rod Technical Specifications ML22294A1502022-11-17017 November 2022 Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program ML22299A1122022-11-0303 November 2022 Notice of Consideration of Approval of Indirect Transfer of Licenses & Conforming Amendments & Opportunity to Request Hearing - Susquehanna Steam Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation (EPID L-2022-LLM ML22256A0542022-10-28028 October 2022 Issuance of Amendment Nos. 283 and 266 Change to Reactor Steam Dome Pressure--Low Instrument Function Allowable Value in Technical Specifications ML22200A0622022-08-30030 August 2022 Issuance of Amendment Nos. 282 and 265 Regarding Risk-Informed Completion Times in Technical Specifications ML22146A2072022-07-15015 July 2022 Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY - ML21229A1572021-11-0404 November 2021 Issuance of Amendment No. 263 Temporary Change to Unit 2 Technical Specification 3.8.7 to Allow Replacement of Unit 1 480 Volt Load Center Transformers ML20317A3142021-03-10010 March 2021 Issuance of Amendment Nos. 280 and 262 Revise Technical Specification 3.8.1, AC Sources-Operating, to Create a New Condition for an Inoperable Manual Synchronization Circuit ML20342A2372021-02-18018 February 2021 Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements ML20168B0042021-01-21021 January 2021 Issuance of Amendment Nos. 278 and 260 to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2019-LLA-0153) (Redacted) ML20297A5642020-12-22022 December 2020 Issuance of Amendment Nos. 277 and 259 Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML20199G7492020-10-0808 October 2020 Issuance of Amendment Nos. 276 and 258 Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis ML19248A8442020-01-17017 January 2020 Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping ML19336D0642020-01-13013 January 2020 Issuance of Amendment Nos. 274 and 256 to Revise Shutdown Margin Definition to Address Advanced Fuel (TSTF-535, Revision 0) ML19155A2642019-07-16016 July 2019 Issuance of Amendment Nos. 273 and 255 Adoption of TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19154A0602019-06-24024 June 2019 Issuance of Amendment Nos. 272 and 254 Technical Specifications to Adopt TSTF-501, Revision 1, Relocated Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18284A4552018-11-0707 November 2018 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18222A2032018-09-26026 September 2018 Issuance of Amendment Nos. 271 and 253 Revising Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MG0269 and MG0270; EPID L-2017-LLA-0306) ML17187A2972017-07-28028 July 2017 Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Revising Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF9154 and MF9155) ML17067A4442017-03-27027 March 2017 Issuance of Amendments Secondary Containment Access Openings ML17004A2502017-01-26026 January 2017 Susquehanna Steam Electric Station, Unit 2 - Issuance of Amendment Re: Temporary Change of Technical Specifications to Allow Replacement of Engineered Safeguard System Load Center Transformers. (CAC No. MF7298) ML16005A2342016-05-20020 May 2016 Issuance of Amendments Adoption of TSTF-425 ML16062A2162016-03-28028 March 2016 Issuance of Amendments Emergency Action Level Scheme Change ML15267A3812015-11-0202 November 2015 Issuance of Amendments Approval of Cyber Security Plan Milestone 8 ML15243A1402015-09-30030 September 2015 Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits ML15054A0582015-04-10010 April 2015 Letter Forwarding Order Approving Transfer of Licenses and Conforming Amendments Related to Susquehanna Steam Electric Station, Units 1 and 2 (TAC MF4426 and MF4427) ML14111A0522014-05-14014 May 2014 Issuance of Amendments Regarding Change to Technical Specification Surveillance Requirement 3.5.1.12 ML14036A2572014-02-26026 February 2014 Issuance of Amendment Change to Allow Only One Manual Trip System to Be Operable for the Residual Heat Removal Shutdown Cooling System in Modes 4 and 5 ML12265A2982012-10-17017 October 2012 Issuance of Amendment Approval of Cyber Security Plan Milestones 3 and 6 ML1211701292012-04-27027 April 2012 Correction to Issuance of Amendment ML12096A1582012-04-19019 April 2012 Issuance of Amendment Temporary Change to Unit 2 Technical Specifications 3.8.7 and 3.7.1 to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1, 4160 V Buses PLA-4817, Amendment Request to Temporary Change to Allow Implementation of Multiple Spurious Operations Modifications on SSES, Unit 1 4160 V Buses, Unit 2 Technical Specifications2012-03-0808 March 2012 Amendment Request to Temporary Change to Allow Implementation of Multiple Spurious Operations Modifications on SSES, Unit 1 4160 V Buses, Unit 2 Technical Specifications ML11292A1372011-11-17017 November 2011 ME5050 & ME5051-Issuance of Amendments to Renewed FOLs Changes to TS SR 3.4.3.1, Safety Relief Valve Tolerances from -3% to -5% ML11221A2712011-09-0808 September 2011 License Amendment, Issuance of Amendment Adoption of TSTF-514, Revision 3 PLA-6642, Proposed Amendment Nos. 307 & 278, Change to Technical Specification Surveillance Requirement (SR) 3.4.3.1 to Revise the Lower Surveillance Tolerances2010-11-10010 November 2010 Proposed Amendment Nos. 307 & 278, Change to Technical Specification Surveillance Requirement (SR) 3.4.3.1 to Revise the Lower Surveillance Tolerances ML0931602762009-11-24024 November 2009 Renewed Operating License No. NPF-22 for Susquehanna Steam Electric Station, Unit 2 ML0931602402009-11-24024 November 2009 Renewed Operating License No. NPF-14 for Susquehanna Electric Steam Station, Unit 1 ML0929501102009-11-0909 November 2009 License Amendment, Changed Technical Specification Table 3.3.5.1-1 for ECCS Instrumentation for CST and Editorial Changes to TS 3.10.8.f ML0917305982009-07-13013 July 2009 License Amendment, Deleted Technical Specification (TS) Section 5.2.2.e, Which Is Superseded by Title 10 of the Code of Federal Regulations (10 CFR) Part 26, Fitness for Duty Programs, Subpart I, Managing... ML0912703662009-07-0606 July 2009 ME0693 & ME0694, Issuance of Amendment to Incorporate TSTF-448 Using CLIIP ML0905002332009-03-18018 March 2009 Issuance of Amendment Technical Specification Change to Technical Specification 3.6.1.3 to Increase the Maximum Allowable Secondary Containment Bypass Leakage Limit ML0903303912009-02-26026 February 2009 Issuance of Amendment Changes in MCPR Safety Limits ML0835004782009-01-0202 January 2009 Issuance of Amendments 249 & 228 Adoption of TSTF-460-A, Revision 0, Control Rod Scram Time Test Frequency Using Consolidated Line Item Improvement Process (TAC Nos. MD9301 and MD9302) ML0835203952009-01-0202 January 2009 Issuance of Amendment Adoption of TSTF-475, Revision 1, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action Using Consolidated Line Item Improvement Process ML0829702642008-12-11011 December 2008 Issuance of Amendment Revision of Technical Specifications (Tss) 3.8.4, DC Sources-Operating, 2023-05-17
[Table view] Category:Safety Evaluation
MONTHYEARML23257A1222023-09-19019 September 2023 Authorization and Safety Evaluation for Alternative Request for Valve 251130 ML23207A1762023-08-0101 August 2023 Authorization and Safety Evaluation for Relief Request 4RR-10 ML23073A0822023-03-30030 March 2023 Enclosure 2 - Draft Conforming Amendments - Susquehanna Steam Electric Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation- Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L ML23073A1072023-03-30030 March 2023 Enclosure 4 - Safety Evaluation Nonproprietary Susquehanna Steam Electric Station,Units 1,2 & Associated Independent Spent Fuel Storage Installation-Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L- ML23010A1082023-01-15015 January 2023 Issuance of Amendment No. 268 Change to Control Rod Technical Specifications ML22294A1502022-11-17017 November 2022 Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program ML22256A0542022-10-28028 October 2022 Issuance of Amendment Nos. 283 and 266 Change to Reactor Steam Dome Pressure--Low Instrument Function Allowable Value in Technical Specifications ML22200A0622022-08-30030 August 2022 Issuance of Amendment Nos. 282 and 265 Regarding Risk-Informed Completion Times in Technical Specifications ML22146A2072022-07-15015 July 2022 Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY - ML21229A1572021-11-0404 November 2021 Issuance of Amendment No. 263 Temporary Change to Unit 2 Technical Specification 3.8.7 to Allow Replacement of Unit 1 480 Volt Load Center Transformers ML21095A3042021-04-19019 April 2021 Relief Request 4RR-02 Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML20317A3142021-03-10010 March 2021 Issuance of Amendment Nos. 280 and 262 Revise Technical Specification 3.8.1, AC Sources-Operating, to Create a New Condition for an Inoperable Manual Synchronization Circuit ML20342A2372021-02-18018 February 2021 Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements ML20168B0042021-01-21021 January 2021 Issuance of Amendment Nos. 278 and 260 to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2019-LLA-0153) (Redacted) ML20297A5642020-12-22022 December 2020 Issuance of Amendment Nos. 277 and 259 Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML20199G7492020-10-0808 October 2020 Issuance of Amendment Nos. 276 and 258 Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis ML20028E8842020-02-10010 February 2020 Correction to Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of the Emergency Service Water System Piping ML19248A8442020-01-17017 January 2020 Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping ML19336D0642020-01-13013 January 2020 Issuance of Amendment Nos. 274 and 256 to Revise Shutdown Margin Definition to Address Advanced Fuel (TSTF-535, Revision 0) ML19155A2642019-07-16016 July 2019 Issuance of Amendment Nos. 273 and 255 Adoption of TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19154A0602019-06-24024 June 2019 Issuance of Amendment Nos. 272 and 254 Technical Specifications to Adopt TSTF-501, Revision 1, Relocated Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18302A3032019-01-0303 January 2019 SE Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order Ea-13-109 (CAC Nos. MF4364 and MF4365; EPID No. L-2014-JLD-0055 ML18284A4552018-11-0707 November 2018 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18222A2032018-09-26026 September 2018 Issuance of Amendment Nos. 271 and 253 Revising Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MG0269 and MG0270; EPID L-2017-LLA-0306) ML17187A2972017-07-28028 July 2017 Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Revising Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF9154 and MF9155) ML17067A4442017-03-27027 March 2017 Issuance of Amendments Secondary Containment Access Openings ML16320A0802016-11-30030 November 2016 NON-PROPRIETARY - Safety Evaluation by NRR Related to Indirect Transfer of Renewed Operating Licenses from Talen Energy Corporation to Riverstone Holdings, LLC for the Susquehanna Steam Electric Station, Units 1 and 2 ML16005A2342016-05-20020 May 2016 Issuance of Amendments Adoption of TSTF-425 ML16069A1992016-05-10010 May 2016 Relief Requests for the Third 10-Year Inservice Inspection Interval (CAC Nos. MF6302 Through MF6307) ML16062A2162016-03-28028 March 2016 Issuance of Amendments Emergency Action Level Scheme Change ML15267A3812015-11-0202 November 2015 Issuance of Amendments Approval of Cyber Security Plan Milestone 8 ML15243A1402015-09-30030 September 2015 Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits ML15098A4782015-04-28028 April 2015 Relief Requests 4RR-01: Use of a Risk-Informed Inservice Inspection Alternative for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF5097 and MF5098) ML15054A0582015-04-10010 April 2015 Letter Forwarding Order Approving Transfer of Licenses and Conforming Amendments Related to Susquehanna Steam Electric Station, Units 1 and 2 (TAC MF4426 and MF4427) ML14141A0732014-06-0909 June 2014 Relief Requests for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF2705 Through MF2714) ML14122A1972014-05-22022 May 2014 Relief Requests for the Fourth 10-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2912 and MF2915) ML14111A0522014-05-14014 May 2014 Issuance of Amendments Regarding Change to Technical Specification Surveillance Requirement 3.5.1.12 ML14028A3952014-03-12012 March 2014 Request for Relief 3RR-20 from the Requirements of the American Society of Mechanical Engineers Section XI ML14036A2572014-02-26026 February 2014 Issuance of Amendment Change to Allow Only One Manual Trip System to Be Operable for the Residual Heat Removal Shutdown Cooling System in Modes 4 and 5 ML12160A1942012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML1211701292012-04-27027 April 2012 Correction to Issuance of Amendment ML12096A1582012-04-19019 April 2012 Issuance of Amendment Temporary Change to Unit 2 Technical Specifications 3.8.7 and 3.7.1 to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1, 4160 V Buses ML12062A1332012-03-0606 March 2012 ME7902 & ME7903-Approval of RR-2012-001 Use of Later Edition of the ASME OM Code for Check Valve Condition Monitoring Program ML12046A0462012-02-23023 February 2012 Relief Request No. 3RR-18, Regarding Relief from the Requirements of the ASME Code for Successive Inspections ML11292A1372011-11-17017 November 2011 ME5050 & ME5051-Issuance of Amendments to Renewed FOLs Changes to TS SR 3.4.3.1, Safety Relief Valve Tolerances from -3% to -5% ML11221A2712011-09-0808 September 2011 License Amendment, Issuance of Amendment Adoption of TSTF-514, Revision 3 ML11152A0092011-07-21021 July 2011 Issuance of Amendment Approval of the PPL Susquehanna, LLC Cyber Security Plan ML1035600052011-01-0404 January 2011 Approval of Relief Request RR-02, Revision 1, to Allow 6 Month Extension for SRV IST ML1015204312010-06-16016 June 2010 Request for Alternative No. RR-07 Main Steam Safety Relief Valve Test Interval Extension ML0935201522010-01-0707 January 2010 Relief Requests RR-07 and RR-08 from the Requirements of the OM Code Inservice Testing of Safety Relief Valves 2023-09-19
[Table view] |
Text
February 28, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: STANDBY LIQUID CONTROL SYSTEM (TAC NOS. MD1424 AND MD1425)
Dear Mr. McKinney:
The Commission has issued the enclosed Amendment No. 240 to Facility Operating License No.
NPF-14 and Amendment No. 217 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 28, 2006.
These amendments revise the SSES 1 and 2 TSs 3.1.7, Standby Liquid Control (SLC) System, to modify the SLC system for single loop pump operation and the use of enriched sodium pentaborate solution.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 240 to License No. NPF-14
- 2. Amendment No. 217 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: See next page
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Robert A. Saccone Bryan A. Snapp, Esq General Manager - Nuclear Operations Assoc. General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Terry L. Harpster Supervisor - Document Control Services General Manager - Plant Support PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSA4 Allentown, PA 18101-1179 Berwick, PA 18603-0467 Richard W. Osborne Rocco R. Sgarro Allegheny Electric Cooperative, Inc.
Manager - Nuclear Regulatory Affairs 212 Locust Street PPL Susquehanna, LLC P.O. Box 1266 Two North Ninth Street, GENPL4 Harrisburg, PA 17108-1266 Allentown, PA 18101-1179 Director - Bureau of Radiation Protection Walter E. Morrissey Pennsylvania Department of Supervising Engineer Environmental Protection Nuclear Regulatory Affairs P.O. Box 8469 PPL Susquehanna, LLC Harrisburg, PA 17105-8469 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Senior Resident Inspector U.S. Nuclear Regulatory Commission Michael H. Crowthers P.O. Box 35, NUCSA4 Supervising Engineer Berwick, PA 18603-0035 Nuclear Regulatory Affairs PPL Susquehanna, LLC Regional Administrator, Region 1 Two North Ninth Street, GENPL4 U.S. Nuclear Regulatory Commission Allentown, PA 18101-1179 475 Allendale Road King of Prussia, PA 19406 Steven M. Cook Manager - Quality Assurance Board of Supervisors PPL Susquehanna, LLC Salem Township 769 Salem Blvd., NUCSB2 P.O. Box 405 Berwick, PA 18603-0467 Berwick, PA 18603-0035 Luis A. Ramos Dr. Judith Johnsrud Community Relations Manager, National Energy Committee Susquehanna Sierra Club PPL Susquehanna, LLC 443 Orlando Avenue 634 Salem Blvd., SSO State College, PA 16803 Berwick, PA 18603-0467
February 28, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: STANDBY LIQUID CONTROL SYSTEM (TAC NOS. MD1424 AND MD1425)
Dear Mr. McKinney:
The Commission has issued the enclosed Amendment No. 240 to Facility Operating License No.
NPF-14 and Amendment No. 217 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 28, 2006.
These amendments revise the SSES 1 and 2 TSs 3.1.7, Standby Liquid Control (SLC) System, to modify the SLC system for single loop pump operation and the use of enriched sodium pentaborate solution.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 240 to License No. NPF-14
- 2. Amendment No. 217 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-1 RidsNrrPMRGuzman RidsNrrDssSbwb LPLI-1/R/F RidsNrrDirsltsb RidsNrrLASLittle RidsOGCRp TFord ALewin GHill (4) RidsAcrsAcnwMailCenter ADAMS Accession Number: ML070390215
- SE inputs provided by memo. No substantive changes made.
OFFICE LPLI-1/PM LPLI-1/LA SBWB/BC ITSB/BC OGC LPLI-1/BC(A)
NAME RGuzman SLittle GCranston* TKobetz JMartin DPickett DATE 2/7/07 2/27/07 2/16/07 2/27/07 2/26/07 2/27/07 OFFICIAL RECORD COPY
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 240 License No. NPF-14
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A. The application for the amendment filed by PPL Susquehanna, LLC, dated April 28, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 240 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented prior to the startup following the SSES 1 spring 2008 15th refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Douglas V. Pickett, Acting Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: February 28, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 240 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.1-20 3.1-20 3.1-21 3.1-21 TS/3.1-22 TS/3.1-22 3.1-23 3.1-23
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. NPF-22
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A. The application for the amendment filed by PPL Susquehanna, LLC, dated April 28, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 217 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented prior to the startup following the SSES 2 spring 2007 13th refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Douglas V. Pickett, Acting Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: February 28, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 217 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.1-20 3.1-20 3.1-21 3.1-21 TS/3.1-22 TS/3.1-22 3.1-23 3.1-23
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 240 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 217 TO FACILITY OPERATING LICENSE NO. NPF-22 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 388
1.0 INTRODUCTION
By letter dated April 28, 2006, Agencywide Documents Access and Management System (ADAMS) Accession No. ML061250159, PPL Susquehanna, LLC (PPL, the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).
The proposed changes would revise the SSES 1 and 2 TSs 3.1.7, Standby Liquid Control (SLC)
System, to modify the SLC system for single loop pump operation and the use of enriched sodium pentaborate solution which would increase the operating margin. With the use of an enriched sodium pentaborate solution, a reduced solution weight-percent and reduced solution volume would be required. In addition, with the replacement of the existing SLC solution, system operation would change from operation requiring both pumps, to operation requiring only a single pump. This would allow a reduction in the required system flow and pump discharge pressure due to a reduced system back pressure.
The proposed changes would be needed to support the planned SSES 1 and 2 constant pressure power uprate, but are not dependent upon Nuclear Regulatory Commission (NRC) approval of the uprate. The analysis supporting these changes was performed based on operation at 3952 megawatt-thermal (MWt), which is the planned uprate power level.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) finds that PPL, in its April 28, 2006, submittal, identified the applicable regulatory requirements. The regulatory requirements and guidance which the NRC staff considered in its review of the application include the following:
- Title 10 of the Code of Federal Regulations (10 CFR) Part 50 establishes the fundamental regulatory requirements with respect to the reactivity control systems.
Specifically, General Design Criterion (GDC)-26, Reactivity control system redundancy and capability, in Appendix A to Part 50, "General Design Criteria for Nuclear Power
Plants," states, in part, that two independent reactivity control systems of different design principles shall be provided, and that one of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding the reactor core subcritical under cold conditions.
For SSES 1 and 2, these systems are the control rod drive system and the SLC system, which is the subject of the proposed TS changes being reviewed for this safety evaluation (SE). The evaluations performed in support of the amendment, discussed in Section 3.0 of this amendment, demonstrate that the SLC system continues to satisfy the provisions of this GDC.
- GDC-27, Combined reactivity control systems capability, states that the reactivity control system shall be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of reliably controlling reactivity changes to assure that under postulated accident conditions and with appropriate margin for stuck rods the capability to cool the core is maintained. The evaluations performed in support of the amendment, discussed in Section 3.0 of this SE, demonstrate that the SLC system continues to satisfy the provisions of this GDC.
- Section 50.62, Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants, states, in part, that each boiling-water reactor (BWR) must have an SLC system with the capability of injecting into the reactor pressure vessel a borated water solution at such a flow rate, level of boron concentration and boron-10 isotope enrichment, and accounting for reactor pressure vessel volume, that the resulting reactivity control is at least equivalent to that resulting from injection of 86 gallons per minute of 13 weight percent sodium pentaborate decahydrate solution at the natural boron-10 isotope abundance into a 251-inch inside diameter reactor pressure vessel for a given core design. In the NRC-approved licensing topical report, NEDE-31096P-A, Anticipated Transients Without Scram: Response to NRC ATWS Rule, 10 CFR 50.62," General Electric provides guidance on modifications to the SLC system to ensure licensee compliance with the ATWS rule. The NRC approved the methods presented in NEDE-31096P-A for use by BWR licensees to demonstrate compliance with the ATWS Rule. The application of this guidance demonstrates that the equivalency requirement of 10 CFR 50.62 are met.
In addition to the above regulatory requirements, the NRC staff also considered the following in its review of the licensing application:
- In response to variations in SLC system pressure due to changes made to SLC system operation, the NRC staff issued Information Notice (IN) 2001-13, Inadequate Standby Liquid Control System Relief Valve Margin, (ML012210146). NRC IN 2001-13 requested licensees to evaluate their SLC system to ensure that modifications made to the system would not cause the SLC relief valves to lift at required injection pressures, thus causing the borated water to discharge to SLC system pump recirculation, rather than to the reactor vessel.
3.0 TECHNICAL EVALUATION
3.1 Background The SLC system is designed to bring the reactor, at any time during the fuel cycle, from rated power conditions to a cold shutdown, without taking any credit for control rod motion following a scram. This manually operated system pumps a sodium pentaborate solution into the vessel, to provide neutron absorption and achieve a subcritical reactor condition. The SLC system is designed to inject over a wide range of reactor operating pressures and satisfies the requirements of 10 CFR 50.62, "Requirements for reduction of risk from ATWS events for light-water-cooled nuclear power plants."
The proposed changes to the SLC system are to support a planned power uprate at SSES 1 and 2. In addition, the ATWS analysis results for operation at 3952 MWt (includes planned uprated power level and operation in the Average Power Range Monitor/Rod Block Monitor/Technical Specifications/Maximum Load Line Limit Analysis (ARTS/MELLLA) operating domain) indicated the need for an increase in the SLC system boron injection rate to produce acceptable suppression pool temperature results. A new analysis was performed to determine the required boron weight-percent and enrichment, as well as the minimum pump flow rate required to safely shutdown the reactor from operation at 3952 MWt. Consistent with the requirements of 10 CFR 50.62, the analysis assumed no control rod movement and failure of the alternate rod insertion. The minimum solution concentration is reduced to 7 weight-percent and the SLC system neutron absorber solution boron enrichment is increased to 88 atom-percent.
PPL states that this also limits the reliance on tank and piping heat tracing, thus increasing system reliability. Due to the neutron absorber solution changes, the number of SLC system pumps required for injection may be reduced to one instead of two.
Based on these changes, a suppression pool temperature response of 206 degrees Fahrenheit (EF) has been achieved. The SSES 1 and 2 suppression pool design limit is 220 EF. Therefore, since the new maximum suppression pool temperature of 206 EF is less than the design limit of 220 EF, the NRC staff finds the suppression pool temperature response acceptable.
In addition to requiring acceptable peak suppression pool temperatures under ATWS conditions, 10 CFR 50.62(c)(4) requires that each BWR have an SLC system with a minimum flow capacity and boron content equivalent in control capacity to 86 gallons per minute (gpm) of 13 weight-percent sodium pentaborate solution. NEDE-31096-P-A provides guidance for boron equivalency determinations. Equation 1-1 of that document was used to demonstrate injection capacity equivalency as follows:
Q M 251 C E x x x 1 86 M 13 19.8 Where: Q = SLC system flow rate; M251 = Reference plant, with 251" diameter vessel, mass of water in the reactor and recirculation system at hot rated conditions (lbsm);
M = Mass of water in the reactor and recirculation system at hot rated conditions (lbs);
C = Sodium pentaborate solution concentration (weight-percent); and, E = Boron-10 isotope enrichment (19.8 atom-percent for natural boron).
Since SSES 1 and 2 have a 251-inch diameter vessel, the value of M251/M is equal to 1.
Applying the remainder parameters, which were assumed in the ATWS analysis, yields:
40 7 88 x x = 111
. 1 86 13 19.8 Based on the results of the injection capacity equivalency calculation, the NRC staff finds that PPL satisfies this requirement of 10 CFR 50.62.
As a result of the ATWS analysis, the maximum postulated reactor vessel lower plenum pressure at the SLC discharge sparger is 1220 pounds-per-square inch absolute (psia) at the time the SLC system is analyzed to be in operation. This is the peak predicted pressure following the limiting ATWS event. Due to the change to single-pump operation, the SLC system pump discharge pressure is reduced from the current value of 1395 pounds-per-square inch gauge (psig) to the proposed value of 1250 psig. The pressure margin for the SLC system pump discharge relief valves increases from 105 psig to 250 psig. PPL states that this value is above the minimum value needed to assure that the relief valves remain closed during SLC system injection. Therefore, there is adequate margin to prevent the SLC system relief valve from lifting during SLC system operation to meet the guidelines published in NRC IN 2001-13.
3.2 Conclusion Based on its review, the NRC staff concludes that the proposed TS changes are acceptable because the SLC system continues to meet the requirements contained in 10 CFR 50.62(c)(4) for SLC system injection capability for ATWS events. The combination of the neutron absorber boron enrichment of 88 atom-percent, minimum solution concentration of 7 weight-percent, and minimum SLC system pump flow rate of 40 gpm exceeds the equivalency in control capacity to 86 gpm of 13 weight-percent sodium pentaborate solution for a 251-inch inside diameter reactor vessel contained in 10 CFR 50.62(c)(4). The NRC staff determined that the predicted peak reactor vessel pressure calculation was acceptable and that the requested TS revisions are in support of modifications consistent with NRC guidance provided in NRC IN 2001-13.
Additionally, PPLs analysis supporting these changes was performed based on operation at 3952 MWt, which is the planned power uprate level. Operation at current licensed thermal power (CLTP) with the proposed changes is bounded by the analysis performed for operation at 3952 MWt and, therefore, is acceptable at CLTP conditions.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Pennsylvania State Official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 46936). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: T. Ford Date: February 28, 2007