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Category:Letter type:PLA
MONTHYEARPLA-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-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-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) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 2024-07-23
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods 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 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 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- 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 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 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 2024-05-29
[Table view] Category:Technical Specification
MONTHYEARML24183A2622024-06-19019 June 2024 Unit, Technical Specification Bases, Manual ML24183A2682024-06-19019 June 2024 Technical Specifications Bases, Manual ML24103A2152024-04-0505 April 2024 Revision to Technical Bases Manual 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-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 PLA-7892, Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-78922020-11-0505 November 2020 Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-7892 ML20129J9132020-04-23023 April 2020 Technical Specification Bases, Unit 1, Manual ML20036C9682020-01-29029 January 2020 Technical Specifications Bases, Manual ML20036C9732020-01-29029 January 2020 Technical Specification Bases, Manual ML19161A1372019-05-15015 May 2019 Technical Specification Bases Manual ML19078A1332019-03-0606 March 2019 Technical Requirements Manual ML19078A1342019-03-0606 March 2019 Technical Requirements Manual ML19078A2102019-03-0606 March 2019 Technical Specification Bases, Manual ML19078A2112019-03-0606 March 2019 Technical Specifications Bases, Manual PLA-7751, Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping2019-01-0909 January 2019 Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping ML19011A0572019-01-0707 January 2019 Technical Requirements Manual ML19011A0582019-01-0404 January 2019 Technical Specifications Bases Manual ML19011A0592019-01-0404 January 2019 Technical Specification Bases Manual ML18306A4882018-10-25025 October 2018 Revised Technical Specifications Manual ML18267A3792018-10-0303 October 2018 Correction to Technical Specification Page 3.6-37 for Error Introduced During the Issuance of Amendment Nos. 266 and 247 ML18201A1992018-07-11011 July 2018 Technical Specifications Bases, Manual ML18197A0782018-07-0909 July 2018 Revision 15 to Technical Specifications Bases Manual ML18128A2022018-04-25025 April 2018 Revision to Technical Specifications Bases Manual ML18128A2032018-04-25025 April 2018 Revision to Technical Specification Bases, Manual ML18072A0992018-02-28028 February 2018 Technical Specification Bases Manual ML18072A1002018-02-28028 February 2018 Revision 11 to Technical Specifications Bases Manual ML18033A3342018-01-24024 January 2018 Technical Specifications Bases Manual ML18033A3312018-01-24024 January 2018 Technical Specification Bases Manual PLA-7644, Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644)2017-12-14014 December 2017 Proposed Amendments to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements (PLA-7644) ML17284A1772017-10-0202 October 2017 Technical Specification Bases Manual ML17265A4412017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 2 of 3) ML17265A4432017-09-20020 September 2017 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7625 (Part 3 of 3) ML17270A0632017-09-18018 September 2017 Technical Specifications Bases, Manual ML17164A1772017-06-0101 June 2017 Revision to Technical Specifications Bases Manual ML17118A0752017-04-20020 April 2017 Revision to Technical Specification Bases Manual ML17118A0762017-04-20020 April 2017 Revisions to Technical Specifications Bases Unit 2 Manual PLA-7444, Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To...2017-02-0101 February 2017 Proposed Amendment Requests to License No. NPF-14 and License No. NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revise Ventilation System Surveillance Requirements To... ML16334A2652016-11-17017 November 2016 Technical Specification Bases Manual ML16110A3162016-04-14014 April 2016 Technical Specification Bases Manual ML16040A2032016-02-0303 February 2016 Technical Specification Bases Manual ML15329A1652015-11-11011 November 2015 Technical Requirements Manual ML15329A1662015-11-11011 November 2015 Technical Requirements Manual ML15317A0092015-11-0505 November 2015 Technical Specifications Bases Manual ML15317A0102015-11-0505 November 2015 Technical Specifications Bases Manual ML15077A4562015-03-0606 March 2015 Technical Requirements Manual ML15034A3112015-01-23023 January 2015 Technical Specifications Bases, Unit 2 Manual ML15034A3102015-01-23023 January 2015 Technical Specification Bases Unit 1 Manual 2024-06-19
[Table view] Category:Bases Change
MONTHYEARML24183A2622024-06-19019 June 2024 Unit, Technical Specification Bases, Manual ML24183A2682024-06-19019 June 2024 Technical Specifications Bases, Manual ML24103A2152024-04-0505 April 2024 Revision to Technical Bases Manual 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-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-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 PLA-7892, Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-78922020-11-0505 November 2020 Temporary Change to the Technical Specifications to Allow Replacement of Transformers 1X230 and 1X240 PLA-7892 ML20129J9132020-04-23023 April 2020 Technical Specification Bases, Unit 1, Manual ML20036C9682020-01-29029 January 2020 Technical Specifications Bases, Manual ML20036C9732020-01-29029 January 2020 Technical Specification Bases, Manual ML19161A1372019-05-15015 May 2019 Technical Specification Bases Manual ML19078A2112019-03-0606 March 2019 Technical Specifications Bases, Manual ML19078A1332019-03-0606 March 2019 Technical Requirements Manual ML19078A1342019-03-0606 March 2019 Technical Requirements Manual ML19078A2102019-03-0606 March 2019 Technical Specification Bases, Manual PLA-7751, Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping2019-01-0909 January 2019 Proposed Amendment to Licenses NPF-14 and NPF-22: Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping ML19011A0572019-01-0707 January 2019 Technical Requirements Manual ML19011A0582019-01-0404 January 2019 Technical Specifications Bases Manual ML19011A0592019-01-0404 January 2019 Technical Specification Bases Manual ML18306A4882018-10-25025 October 2018 Revised Technical Specifications Manual ML18201A1992018-07-11011 July 2018 Technical Specifications Bases, Manual ML18197A0782018-07-0909 July 2018 Revision 15 to Technical Specifications Bases Manual ML18128A2032018-04-25025 April 2018 Revision to Technical Specification Bases, Manual ML18128A2022018-04-25025 April 2018 Revision to Technical Specifications Bases Manual ML18072A0992018-02-28028 February 2018 Technical Specification Bases Manual ML18072A1002018-02-28028 February 2018 Revision 11 to Technical Specifications Bases Manual ML18033A3312018-01-24024 January 2018 Technical Specification Bases Manual ML18033A3342018-01-24024 January 2018 Technical Specifications Bases Manual ML17284A1772017-10-0202 October 2017 Technical Specification Bases Manual ML17270A0632017-09-18018 September 2017 Technical Specifications Bases, Manual ML17164A1772017-06-0101 June 2017 Revision to Technical Specifications Bases Manual ML17118A0762017-04-20020 April 2017 Revisions to Technical Specifications Bases Unit 2 Manual ML17118A0752017-04-20020 April 2017 Revision to Technical Specification Bases Manual ML16334A2652016-11-17017 November 2016 Technical Specification Bases Manual ML16110A3162016-04-14014 April 2016 Technical Specification Bases Manual ML16040A2032016-02-0303 February 2016 Technical Specification Bases Manual ML15329A1662015-11-11011 November 2015 Technical Requirements Manual ML15329A1652015-11-11011 November 2015 Technical Requirements Manual ML15317A0102015-11-0505 November 2015 Technical Specifications Bases Manual ML15317A0092015-11-0505 November 2015 Technical Specifications Bases Manual ML15077A4562015-03-0606 March 2015 Technical Requirements Manual ML15034A3112015-01-23023 January 2015 Technical Specifications Bases, Unit 2 Manual ML15034A3102015-01-23023 January 2015 Technical Specification Bases Unit 1 Manual PLA-7181, Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits.2014-08-11011 August 2014 Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits. ML14205A0132014-07-17017 July 2014 Technical Specification Bases, Manual, Revisions ML14196A0412014-07-0303 July 2014 Technical Specifications Bases, Manual ML14196A0402014-07-0303 July 2014 Technical Specification Bases, Manual ML14122A0152014-04-26026 April 2014 Technical Specifications Bases Unit 2 Manual ML14122A0142014-04-26026 April 2014 Technical Specification Bases Unit 1 Manual ML14072A0212014-02-25025 February 2014 Technical Specification Base, Manual 2024-06-19
[Table view] Category:Technical Specifications
MONTHYEARML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods 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 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 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 ML23010A1082023-01-15015 January 2023 Issuance of Amendment No. 268 Change to Control Rod Technical Specifications 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 ML22294A1502022-11-17017 November 2022 Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program ML22146A2072022-07-15015 July 2022 Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY - ML22101A0282022-03-30030 March 2022 Revised Technical Specification Bases Unit 1 Manual ML20342A2372021-02-18018 February 2021 Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements 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 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 ML19248A8442020-01-17017 January 2020 Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping ML19232A0692019-08-0808 August 2019 Technical Specification Bases Unit 2 Manual ML19232A0682019-08-0808 August 2019 Technical Specification Bases Manual 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 ML19052A0082019-03-0505 March 2019 Correction to Technical Specifications Page 3.3-45 (Unit 1) and Page 3.6-11 (Unit 2) for Administrative Errors Introduced During the Issuance of Amendment Nos. 271 and 253 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) PLA-7733, Correction of Technical Specification Typographical Error for TS 3.6.4.1 (PLA-7733)2018-09-11011 September 2018 Correction of Technical Specification Typographical Error for TS 3.6.4.1 (PLA-7733) ML18017A2272017-12-15015 December 2017 Technical Specification Bases Manual ML18017A2282017-12-15015 December 2017 Technical Specifications Bases Manual ML17221A2892017-08-0909 August 2017 Draft TSTF-542-Variations 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) 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 ML17067A4442017-03-27027 March 2017 Issuance of Amendments Secondary Containment Access Openings 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 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-7406, Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-4252015-11-11011 November 2015 Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425 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 PLA-7334, Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-4252015-07-0202 July 2015 Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425 PLA-7299, Response to Request for Additional Information on Technical Specification Changes to RCS Pressure and Temperature (P/T) Limits2015-04-0606 April 2015 Response to Request for Additional Information on Technical Specification Changes to RCS Pressure and Temperature (P/T) Limits PLA-7119, PPL Susquehanna, LLC, Unit 1 & Unit 2 Proposed Technical Specification Amendment for Adoption of Task Force Traveler TSTF-425, Rev. 3, Relocate Surveillance Frequencies to Licensee Control Risk Informed Technical Specification Task Force...2014-10-27027 October 2014 PPL Susquehanna, LLC, Unit 1 & Unit 2 Proposed Technical Specification Amendment for Adoption of Task Force Traveler TSTF-425, Rev. 3, Relocate Surveillance Frequencies to Licensee Control Risk Informed Technical Specification Task Force... ML14316A6062014-10-27027 October 2014 PPL Susquehanna, LLC, Unit 1 & Unit 2 Proposed Technical Specification Amendment for Adoption of Task Force Traveler TSTF-425, Rev. 3, Relocate Surveillance Frequencies to Licensee Control Risk Informed Technical Specification Task Force... 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 ML14042A1152014-01-29029 January 2014 License Amendment Request - Increase of the Allowable Gas Treatment System Maximum Flow Rates from Secondary Containment ML13361A0872013-12-11011 December 2013 Revision 112 to Technical Specification Bases Manual 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 ML11221A2712011-09-0808 September 2011 License Amendment, Issuance of Amendment Adoption of TSTF-514, Revision 3 ML11251A1532011-08-24024 August 2011 Technical Requirements Manual, Rev. 69 and Table of Contents, Rev. 20 ML11251A1522011-08-24024 August 2011 Revision 68 to Technical Requirements Manual 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 ML1020103852010-07-12012 July 2010 Revision 100 to Technical Specifications Bases Unit 2 Manual ML1020104112010-07-12012 July 2010 Revisions to Technical Specification Bases Manual ML1012605332010-04-28028 April 2010 Technical Specification Bases Manual ML1011003942010-04-0606 April 2010 Technical Specifications Bases Unit 2 Manual, Rev. 98 ML0932901772009-11-24024 November 2009 Technical Specifications for Susquehanna Steam Electric Station, Unit 2 2024-02-27
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Timothy S. Rausch PPL Susquehanna, LLC Sr. Vice Pres~dent& Chief Nuclear Officer 769 Salem Boulevard Bewick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 tsrausch@pplweb.com tdmr -
NOV I 0 2060 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1- 17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 307 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 278 TO LICENSE NPF-22:
CHANGE TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT (SR) 3.4.3.1 TO REVISE THE LOWER SURVEILLANCE TOLEFUNCES Docket Nos. 50-387 PLA-6642 and 50-388 Pursuant to 10 CFR 50.90, PPL Susquehanna, LLC (PPL), hereby requests approval of the following proposed amendments to the Susquehanna Steam Electric Station (SSES)
Unit 1 and Unit 2 Technical Specifications (TS), as described in the Enclosure. The proposed amendments would change Surveillance Requirement 3.4.3.1 in Technical Specification 3.4.3 "SafetyRelief Valves (SIRVs)." Specifically, the proposed amendments will change the allowable lower S/RV tolerances.
The change is proposed in order to reduce an unnecessarily restrictive Surveillance Requirement. The proposed change will not impact the reliability of the SIRVs or adversely impact their ability to perform their safety function. This change will limit the number of TS S/RV surveillance test failures in the low direction and preclude the submittal of unnecessary License Event Reports (LERs) to the NRG.
Justification for the change to the Unit 1 and Unit 2 Safety/Relief Valves (S/RVs)
Surveillance Requirement 3.4.3.1 is based upon the evaluation presented in the Enclosure. As demonstrated in the enclosed evaluation, the proposed amendment does not involve a significant hazard consideration.
PPL requests approval of the proposed change to the Unit 1 and Unit 2 Technical Specificationsby November 30,201 1. PPL further requests that the approved amendment be issued to be effective immediately upon approval with the implementation to be completed within 60 days.
Attachments 1 and 2 contain the Technical Specification and the Technical Specification Bases Mark-ups reflecting the proposed change.
Document Control Desk PLA-6642 This change has been discussed with the SSES NRC Project Manager. The change is similar to a change approved by the NRC for Entergy Nuclear - South, River Bend Station in a letter dated 02/13/2003, titled "River Bend Station Unit 1 - Issuance of Amendment RE: Modification of the Technical Specifications Surveillance Requirements for the Safety/Relief Valves (TAC No. MB5090)." [ADAMS Accession No.
ML030450307J. The change has also been reviewed by the SSES Plant Operations Review Committee and by the Susquehanna Review Committee. In accordance with 10 CFR 50.9 1(b), PPL Susquehanna, LLC is providing the Commonwealth of Pennsylvania with a copy of this proposed License Amendment request.
There are no regulatory commitments associated with the proposed changes.
If you have any questions or require additional information, please contact Mr. C. T. Coddington at 6 10-774-4019.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: // )B - /c T. S. Rausch
Enclosure:
PPL Susquehanna, LLC Evaluation of Proposed Change to the Unit 1 and Unit 2 TS SR 3.4.3.1 "REACTOR COOLANT SYSTEM (RCS) SafetyRelief Valves (SRVs)" and the corresponding TS Bases Attachments: Proposed Unit 1 and Unit 2 Technical Specification Changes (Mark-ups) Proposed Unit 1 and Unit 2 Technical Specification Bases Changes Mark-ups)
Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEPBRP Mr. B. K. Vaidya, NRC Project Manager
Enclosure to PLA-6642 PPL Susquehanna, LLC Evaluation of Proposed Change to the Unit 1 and Unit 2 TS SR 3.4.3.1 "REACTOR COOLANT SYSTEM (RCS)
SafetylRelief Valves (SiRVs)"
and the Corresponding TS Bases DESCRIPTION PROPOSED CHANGE BACKGROUND TECHNICAT, ANALYSIS 4.1 Operating Margin 4.2 Surveillance Test History REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Reguf atory Requirementsfcriteria ENVlRONMENTAL CONSIDERATIONS REFERENCES
Enclosure to PLA-6642 Page 1 of 9 PPL EVALUATION r
Subiect: PPL Susquehanna, LLC Evaluation of Proposed Change to the Unit 1 and Unit 2 Technical Specifications (TS) Surveillance Requirements SR 3.4.3.1, SafetyIRelief Valves (S/RVs), and the associated TS Basis TS / B SR 3.4.3.1.
- 1. DESCRIPTION The change to the PPL Susquehanna, LLC (PPL) Unit 1 and Unit 2 Technical Specification SR 3.4.3.1 "SafetyfRelief Valves (SAWS)" proposes a new safety function lift setpoint lower tolerance for the Safemelief Valves (SIRVs). The proposed change will revise the lower tolerances from -3% to -5%. This change would be limited to the lower tolerances and does not affect the upper tolerances. This change only applies to the lower as-found tolerance and not to the as-left tolerance, which will remain unchanged at
+1% of the safety lift setpoint. The as-found tolerances are used for determining past
-
operability and to increase sample sizes for SIRV testing should the upper tolerance be exceeded. There will be no revision to the actual setpoints of the valves installed in the plant due to this change.
If approved, PPL plans to implement the proposed Unit 1 and Unit 2 TS amendments within 60 days. Accordingly, an accelerated acceptance review by the NRC is requested to support the implementation plan.
Mark-ups of the proposed change to the Unit 1 and Unit 2 Technical Specifications (TS) and Bases are included in Attachments 1 and 2.
- 2. PROPOSED CHANGE The proposed technical change to the Unit 1 and Unit 2 Technical Specification SR 3.4.3.1 revises the lower setpoint tolerances for the following setpoints:
Setpoint Lower Tolerance 1175 2 1140 to? 1117 1195 2 1160 to? 1136 f 196 2 1169 t o 1 1145 The proposed change reduces an unnecessarily restrictive Surveillance Requirement. The proposed change will not impact the reliability of the S W s or adversely impact their ability to perform their safety function. The S W s are required to meet ASME limits based
Enclosure to PLA-6642 Page 2 of 9 on valve type and size to ensure acceptable valve performance. These limits are not being changed. This change will preclude the submittal of ~~nnecessary LERs to the NRC due to set point drift in the low (conservative) direction.
Corresponding changes are required to the TS Bases Sections B 3.4.3.1.
- 3. BACKGROUND The purpose of the Nuclear Pressure Relief System is to prevent over-pressurization of the Reactor Vessel boiler system during abnormal operational transients. This protects the primary system process barrier from failure, which could result in the release of fission products.
The ASME Boiler and Pressure Vessel Code requires the reactor pressure vessel to be protected from overpressure during upset conditions by self-actuated safety valves. As part of the Nuclear Pressure Relief System, the size and number of Main Steam SfRVs are selected such that the peak pressure in the nuclear system will not exceed the ASME Code limits for the Reactor Coolant Pressure Boundary (RCPB).
There are a total of 16 S/RVs, of which 14 are required to be operable. The SRVs provide three main protection functions, which are:
- 1) the overpressure relief mode,
- 2) the overpressure safety mode, and
- 3) the automatic depressurization operation.
In the safety mode (or the spring mode of operation) the valves open when steam pressure at the valve inlet overcomes the spring force holding the valve closed. This mode satisfies the ASME code requirements. It is this mode of operation for which the lower surveillmce tolerances for the safety function lift setpoints will be relaxed from
-3% to -5%. The upper surveillance tolerances will remain at +3%. The relief and automatic depressurization modes rely upon solenoid actuation to open the valves and are not affected by this proposed change.
The SSES S N s are Crosby Style GxRxXO HB-65-BP SIRVs. A review of as-found test data for the SSES S/RVs indicates a tendency for minor setpoint drift in the negative direction. Industry experience shows that it is the nature of these valves to have a driftlvariance with an initial as-found low lift pressure. It is typical for two or three S/RVs out of a sample size of six to lift between -5% to -3%. The second, third and fourth test lifts following the initial test lift will typically be within the 23% band. The valve manufacturer attributes these variances to no cause other than setpoint driftlvariance.
Enclosure to PLA-6642 Page 3 of 9 Currently, at least four S/RVs are removed during each refueling outage, bench tested for safety set pressure and replaced with valves certified to have zero seat-to-disk leakage and to have safety lift setpoint tolerances within 21% of the setpoint as specified in the TS SR 3.4.3.1. If the as-found lift is greater than the +3% tolerance for one of the S/RVs tested from the sample size, the sample size will be increased by two S/RVs, in accordance with the IST program requirements.
- 4. TECHNICAL ANALYSIS The SSES S/RVs were originally purchased to the ASME Boiler and Pressure Vessel Code, Section 111, Nuclear Vessels, up to and including Summer 1970 Addenda. The designed setpoint tolerance of the safety setting was 21%for construction based upon ASME Section 111, Summer 1971, Article NB-7000. The original TS testing requirements were based upon this design code.
The NRC Staff issued an SER on the BWROG Licensing Topical Report NEDC-31753P (LTR) (Reference 7.1). In the SER, the NRC stated that a generic change of setpoint tolerance to 23% is acceptable provided that it is evaluated in the analytical bases. The required analysis was completed for SSES and the change was approved by the NRC (References 7.2 and 7.3).
The Operability of the SIRVs is based on the TS SR acceptance criteria with a setpoint tolerance of +/- 3%. If any S/RV exceeds the tolerance, a Condition Report for each S R V that exceeds the tolerance is entered into our Corrective Action Program to evaluate the test failure. If more than two (2) SRVs exceed the tolerance a License Event Report (LER) would be required. In addition, test failures above +3% would result in testing additional valves to comply with Code requirements.
The proposed lower setpoint tolerance change from -3% to -5%, was evaluated using the previously accepted methodology of the LTR and the associated SER. Since the evaluation done in detail to support the current upper and lower tolerances of 23%, and the conclusions of the evaluation have not changed, only those areas not previously reviewed by the NRC wilt be discussed here.
Plant behavior is cunently expected to lead to a less severe transient than is analyzed in FSAR Section 15.1, and will continue to be less severe after this change is made.
The inadvertent SlRV opening event has been identified as non-limiting, and therefore, it is not explicitly analyzed each cycle.
Enclosure to PLA-6642 Page 4 of 9 4.1. Operating Margin The purpose of the lower setpoint tolerance is to ensure sufficient margin exists between the normal operating pressure of the system and the point at which the S W s actuate in the overpressure safety mode. The nominal operating pressure of the reactor pressure vessel at power is 1050 psig. A lower setpoint tolerance value of -5%, applied to the lowest nominal S R V (1 175 psig) would allow it to lift at 1117 psig. The lowest potential margin between the nominal reactor pressure and the S/RV lift pressure of the valves with the lowest overpressure safety setpoint is 67 psig. Also, the relief mode for two S/RVs are set at 1106 psig. The relief mode on these two SIRVs would actuate before the above stated 1117 psig lowest allowable lift. The potential margin is sufficient to prevent unwanted actuation of the SiRVs, since the relief mode setpoint of 1106 psig ensures that pressure transients will still cause the valves to open in the relief mode prior to the safety mode. Therefore, there will be no additional inadvertent SRV lifts.
The valves removed for testing are returned to a tolerance of +l%prior to being installed for service, thereby returning the margin to the original levels. Therefore, the margin is considered adequate and will not impact normal plant operation.
4.2 Surveillance Test History Test results for SSES S/RVs have shown that the majority of SRVs experience minor setpoint drift in the negative direction over time. Based on a review of the 295 previous test results for the SSES valves, the average drift was -0.78% from bench test to bench test with a Standard Deviation of 1.56%. There were 22 valve tests that failed below the
-3% tolerance. There were 3 valves that tested below -5%. The database includes tests for valves that span more than 6 years between bench tests. Therefore, excessive drift over multiple operating cycles is not anticipated for the S/RVs. The S/RV leakage is monitored and determined by the S R V tailpipe temperatures recorded in the main control room. If a valve's tailpipe temperature reaches a specified temperature, the SlRV is considered to be leaking and will typically be replaced at the next refueling outage.
- 5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Amendments are proposed to the Unit 1 and Unit 2 Technical Specification SR 3.4.3.1 "Safety/Refief Valves (SRVs)" to change the lower surveillance lift setpoint tolerance for the SafetyRelief Valves (SRVs). The current tolerance is based on 23%. The proposed change will revise the lower setpoint surveillance tolerances from -3% to -5%. This change only applies to the as-found tolerance and not to the as-left tolerance, which will remain unchanged at +I%, as specified in TS SR 3.4.3.1, of the safety lift setpoint. The as-found tolerances are used for determining past operability and to increase sample sizes
Enclosure to PLA-6642 Page 5 of 9 for S/RV testing. No changes to the actual safety fknction lift setpoints are required for the valves installed in the plant. There will be no physical modifications to the valves.
PPL Susquehanna, LLC (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. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No This change has no influence on the probability or consequences of any accident previously evaluated. The lower setpoint tolerance change does not affect the operation of the valves and it does not change the as-left setpoint tolerance. The change only affects the lower tolerance for opening the valve and does not change the upper tolerance, which is the limit that protects from overpressurization.
The proposed action does not involve physical changes to the valves, nor does it change the safety function of the valves. The proposed TS revision involves no significant changes to the operation of any systems or components in normal or accident operating conditions and no changes to existing structures, systems, or components.
The proposed action does not change any other behavior or operation of any S/RVs, and, therefore, has no significant impact on reactor operation. It also has no significant impact on response to any perturbation of reactor operation including transients and accidents previously analyzed in the Final Safety Analysis Report (FSAR).
Therefore, the proposed amendment does not result in a significant increase in the probability or consequences of any previously evaluated accident
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed lower setpoint tolerance change only affects the criteria to determine when an as-found S/RV test is considered to be acceptable. This change does not affect the criteria for the upper setpoint tolerance.
The proposed lower setpoint tolerance change does not adversely affect the operation of any safety-related components or equipment. Since the proposed action does not involve hardware changes, significant changes to the operation of any systems or components,
Enclosure to PLA-6642 Page 6 of 9 nor change to existing structures, systems, or components, there is no possibility that a new or different kind of accident is created.
The proposed change does not involve physical changes to the SIRVs, nor does it change the safety function of the SRVs. The proposed change does not require any physical change or alteration of any existing plant equipment. No new or different equipment is being installed, and installed equipment is not being operated in a new or different manner. There is no alteration to the parameters within which the plant is normally operated. This change does not alter the manner in which equipment operation is initiated, nor will the hnctional demands on credited equipment be changed. No alterations in the procedures that ensure the plant remains within analyzed limits are being proposed, and no changes are being made to the procedures relied upon to respond to an off-normal event as described in the FSAR. As such, no new failure modes are being introduced. The change does not alter assumptions made in the safety analysis and licensing basis.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?
Response: No The proposed lower setpoint tolerance change only affects the criteria to determine when an as-found S/RV test is considered to be acceptable. This change does not affect the criteria for the upper setpoint tolerance. The TS setpoints for the SRVs are not changed.
The as-Ieft setpoint tolerances are not changed by this proposed change.
The margin of safety is established through the design of the plant structures, systems, and components, the parameters within which the plant is operated, and the establishment of the setpoints for the actuation of equipment relied upon to respond to an event. The proposed change does not significantly impact the condition or performance of structures, systems, and components relied upon for accident mitigation.
Therefore, the proposed change does not involve a siMkicmt reduction in a margin of safety.
Based on the above, PPL concludes that the proposed change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.
Enclosure to PLA-6642 Page 7 of 9 5.2 Applicable Regulatorv Requirements/Criteria SSES FSAR Sections 3.1 and 3.13 provide detailed discussion of SSES compliance with the applicable regulatory requirements and guidance.
The proposed TS amendments:
(a) Do not alter the design or function of any system; (b) Do not result in any change in the qualifications of any component; and (c) Do not result in the reclassification of any component's status in the areas of shared, safety-related, independent, redundant, and physically or electrically separated.
5.2.1 General Design Criteria The following applicable General Design Criteria (GDC) for the Reactor Coolant System require that the system be protected from overpressurization.
GDC 15-Reactor Coolant System Design (Criterion 15)
The reactor coolant system and associated auxiliary, control, and protection systems shall be designed with sufficient margin to assure that the design conditions of the RCPB are not exceeded during any condition of normal operation, including anticipated operational occurrences.
An example of the integrated protective action scheme, which provides sufficient margin to ensure that the design conditions of the RCPB are not exceeded, is the automatic initiation of the nuclear system pressure relief system upon receipt of an overpressure signal. To accomplish overpressure protection, a number of pressure-operated relief valves are provided to discharge steam from the nuclear system to the suppression pool.
The nuclear system pressure relief system also provides for automatic depressurization of the nuclear system in the event of a LOCA in which the vessel is not depressurized by the accident. The depressurization of the nuclear system in this situation allows operation of the low pressure Emergency Core Cooling Systems (ECCS) to supply enough cooling water to adequately cool the core. Criterion 15 is not affected by this proposed change.
GDC 35- Emergency Core Coolinp (Criterion 35)
The Automatic Depressurization System functions to reduce the reactor pressure so that flow from LPG1 and GS enters the reactor vessel in time to cool the core and prevent excessive fuel clad temperature. The Automatic Depressurization System uses several of
Enclosure to PLA-6642 Page 8 of 9 the nuclear system pressure relief valves to relieve the high pressure steam to the suppression pool. Criterion 35 is not affected by this proposed change.
Thus, the proposed changes do not change the conformance with the above General Design Criteria.
5.2.2 Applicable ASME Code Requirements The proposed changes have been evaluated to determine whether applicable regulations and requirements continue to be met.
The SSES In-Service Testing @ST)program is currently implemented in accordance with the requirements of the ASME Operation and Maintenance (OM) Code 1998 Edition through OMb-2000 Addenda. The SIRVs at SSES are Class 1 Category C valves in accordance with the SSES IST Program.
PPL Susquehanna Relief Request RR-02 (Reference 7.4) provides an alternative to ASME Code 1998 Edition through OMb-2000 Addenda, section 1-1330, "Test Frequencies, Class 1 Pressure Relief Valves." The alternative requires that SSES remove at least 20% of the 16 Main Steam S N s plus weeping valves detected during the previous operating cycle and any valves required to be removed to access scheduled or weeping valves up to a maximum of 8 valves during each refueling outage.
Additional valves above the Code required minimum 20% will be tested if the as-found setpoint exceeds +3% of the nameplate. No additional valves will be tested if the as-found setpoint is below the nameplate setpoint. The additional valves tested will be from the initial population removed that are in excess of the 20% Code required minimum. If one of these valves fails, then all the MSRVs would be removed and tested.
Completion of Code testing will be accomplished over a period of 3 refire1 cycles or 6 years. The SSES S / W s will continue to be tested in accordance with these requirements.
The ASME ON Code Appendix I, Section 1-13 10(e) allows the owner to establish setpoint acceptance criteria for relief valves tested under the IST program Therefore, no relief wilt be required with regard to the setpoint tolerance change. However, a change to the TS will be required.
Conclusion Based on the analysis provided in Section 5: (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
Enclosure to PLA-6642 Page 9 of 9 regulations, and (3) the issuance of the amendment will not be adverse to the common defense and security or to the health and safety of the public.
- 6. ENVIRONMENTAL CONSIDERATION 10 CFR 5 1.22(~)(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 change and has determined that the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 5 1.22(~)(9).Accordingly, pursuant to 10 CFR 5 1.22(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 operational transients. 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.
7.1 m D C - 3 1753P, "BWROG In-Service Pressure Relief Technical Specification Revision Licensing Technical Report" 7.2 PLA-5377, "Proposed Amendment No. 244 To License NPF- 14 And Proposed Amendment No. 208 To License NPF-22: Revise Main Steam Relief Valve Steam Setpoint Tolerance And Requests For Relief from IST And ASME Code Requirements" 7.3 PLA-5430, "Supplement to Proposed Amendment No. 244 To License NPF-14 And Proposed Amendment No. 208 To License NPF-22: Revise Main Steam Relief Valve Steam Setpoint Tolerance And Requests For Relief from IST And ASME Code Requirements" 7.4 PPL Susquehanna Relief Request RR-02, Approved by the NRC March 10,2005.
Attachment 1 to PLA-6642 Technical Specification Markups (Unit 1 and 2)
PPL Rev. 1 S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SR 3.4.3.1 Verify the safety function lift setpoints of the In accordance with the required S/RVs are as follows: Inservice Testing Program
NOTE.........................
Up to two inoperable required S/RVs may be replaced with spare OPERABLE S/RVs having lower setpoints until the next refueling outage.
.............................................................
Number of Setpoint SIRVs (psis) 2 1175 2 1117and I121 6 1195 2 1136 and I123 8 1205 1 1145 and 5 1241)
Following testing, lift settings shall be within 51 %.
SUSQUEHANNA - UNIT 1 -
TS / 3.4-9 Amendment 2911-
PPL Rev.X SIRVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the In accordance with the required S/RVs are as follows: Inservice Testing Program
............................ NOTE --------------ma---------
Up to two inoperable required SIRVs may be replaced with spare OPERABLE SIRVs having lower setpoints until the next refueling outage.
.............................................................
Number of Setpoint SIRVs (psin) 2 1175 (2-4-4021117and 51210) 6 1195 (M46021136 and 5 1230) 8 1205 ( 2 7 145 and 2 1241)
Following testing, lift settings shall be within 21%.
SUSQUEHANNA - UNIT 2 Amendment 4-75
Attachment 2 to PLA-6642 Technical Specification Bases Markups (Unit 1 and 2)
PPL Rev. 2 SIRVs B 3.4.3 BASES APPLICABLE From an overpressure standpoint, the design basis events are bounded by SAFETY the MSlV closure with flux scram event described above. Reference 2 ANALYSES discusses additional events that are expected to actuate the SIRVs.
(continued)
S/RVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 4).
The safety function of 14 of the 16 S/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. 1 and 2). The requirements of this LC0 are applicable only to the capability of the SIRVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function).
The SIRV setpoints are established to ensure that the ASME Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the FSAR are based on these setpoints, but also include the additional uncertainty of
+ 3%,- 5% of the nominal setpoint to provide an added degree of conservatism.
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
APPLICABlLlT\f In MODES 1,2, and 3, all required S/RVs must be OPERABLE, since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Heat Removal (RHR) System is capable of dissipating the core heat.
In MODE 4 reactor pressure is low enough that the overpressure limit is unlikely to be approached by assumed (continued)
SUSQUEHANNA - UNIT 1 TS II3 3.4-16 Revision 3
PPL Rev. 2 S/RVs B 3.4.3 BASES APPLICABILITY operational transients or accidents. In MODE 5, the reactor vessel head is (continued) unbolted or removed and the reactor is at atmospheric pressure. The S/RV function is not needed during these conditions.
ACTIONS A.l and A.2 With less than the minimum number of required S/RVs OPERABLE, a transient may result in the violation of the ASME Code limit on reactor pressure. If the safety function of one or more required S/RVs is inoperable, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3,4,3.1 REQUIREMENT The Surveillance requires that the required S/RVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the S/RV safe lift settings must be performed during shutdown, since this is a bench test, to be done in accordance with the lnservice Testing Program.
The lift setting pressure shalt correspond to ambient conditions of the valves at nominal operating temperatures and pressures. The S/RV setpoint is
+ 3%. - 5% of the nominal setpoint for OPERABILITY. Requirements for accelerated testing are established in accordance with the Inservice Test Program. Any of the 46 S/RVs, identified in this Surveillance Requirement, with their associated setpoints, can be designated as the 14 required S/RVs.
This maintains the assumptions in the overpressure analysis.
A Note is provided to aftow up to two of the required 14 S/RVs to be physically replaced with SRVs with lower setpoints until the next refueling outage. This provides operational flexibility which maintains the assumptions in the over-pressure analysis.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.4-17 Revision 8
PPL Rev. 2 S/RVs B 3.4.3 BASES APPLICABLE From an overpressure standpoint, the design basis events are bounded by SAFETY the MSlV closure with flux scram event described above. Reference 2 ANALYSES discusses additional events that are expected to actuate the S/RVs.
(continued)
S/RVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 4).
The safety function of 14 of the 16 S/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. 1 and 2). The requirements of this LC0 are applicable only to the capability of the S/RVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function).
The S/RV setpoints are established to ensure that the ASME Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the FSAR are based on these setpoints, but also include the additional uncertainty of 1- 3%. - 5% of the nominal setpoint to provide an added degree of I conservatism.
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
APPblCABlLlTY In MODES 1, 2, and 3, all required S/RVs must be OPERABLE, since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Meat Removal (RHR) System is capable of dissipating the core heat.
In MODE 4 reactor pressure is low enough that the overpressure limit is unlikely to be approached by assumed (continued)
SUSQUEHANNA - UNIT 2 TS / 5 3.4-16 Revision 8
PPL Rev. 2 S/RVs B 3.4.3 BASES APPLICABILITY operational transients or accidents. In MODE 5, the reactor vessel head is (continued) unbolted or removed and the reactor is at atmospheric pressure. The SIRV function is not needed during these conditions.
ACTIONS A.l and A.2 With less than the minimum number of required S/RVs OPERABLE, a transient may result in the violation of the ASME Code limit on reactor pressure. If the safety function of one or more required S/RVs is inoperable, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.4.3.1 REQUIREMENT The Surveillance requires that the required S/RVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the S/RV safe lift settings must be performed during shutdown, since this is a bench test, to be done in accordance with the lnservice Testing Program.
The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures. The S/RV setpoint is
+ 3% - 5% of the nominal setpoint for OPERABILITY. Requirements for accelerated testing are established in accordance with the lnservice Test Program. Any of the 16 SIRVs, identified in this Surveillance Requirement, with their associated setpoints, can be designated as the 14 required SIRVs.
This maintains the assumptions in the overpressure analysis.
A Note is provided to altow up to two of the required 14 S/RVs to be physically replaced with S/RVs with lower setpoints until the next refueling outage. This provides operational flexibility which maintains the assumptions in the over-pressure analysis.
(continued]
SUSQUEHANNA - UNIT 2 TS IB 3.4-17 Revision 3