Similar Documents at Perry |
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Category:Letter type:L
MONTHYEARL-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023 Core Operating Limits Report for Operating Cycle 20 L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-085, 1 to Emergency Plan2023-03-10010 March 2023 1 to Emergency Plan L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-23-017, Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 192023-01-31031 January 2023 Mid-Cycle Revisions to the Core Operating Limits Report for Operating Cycle 19 L-22-271, Emergency Plan2022-12-20020 December 2022 Emergency Plan L-22-272, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)2022-12-16016 December 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023) L-22-263, Spent Fuel Storage Cask Registration2022-12-12012 December 2022 Spent Fuel Storage Cask Registration L-22-254, Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 222022-11-18018 November 2022 Emergency Plan for Perry Nuclear Power Plant, Including EAL Matrix Revision 22 L-22-250, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 192022-11-0808 November 2022 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 19 L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-10-18018 October 2022 Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-201, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022 Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-0632022-07-14014 July 2022 Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063 L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis L-22-104, Annual Radiological Environmental Operating Report2022-04-28028 April 2022 Annual Radiological Environmental Operating Report L-22-110, Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement2022-04-28028 April 2022 Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement L-22-105, Annual Radiological Effluent Release Report2022-04-27027 April 2022 Annual Radiological Effluent Release Report L-22-082, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-23023 March 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022 Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage L-22-052, Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines2022-03-16016 March 2022 Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines L-22-073, Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant2022-03-16016 March 2022 Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022 Retrospective Premium Guarantee L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements2022-01-0505 January 2022 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements L-21-282, Proposed Inservice Inspection Alternative IR-0632022-01-0505 January 2022 Proposed Inservice Inspection Alternative IR-063 L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing2021-12-28028 December 2021 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing L-21-287, Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)2021-12-20020 December 2021 Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter) 2024-01-24
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4412023-09-29029 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Federal Register Notice, Direct and Indirect License Transfer Issuance Order ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML20030A4402020-02-27027 February 2020 Issuance of Amendment Nos. 304, 194, 299, and 187; Order Approving Transfers of Facility Operating Licenses and Independent Spent Fuel Storage Installation General Licenses and Conforming Amendments ML19326A7592019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Non-Proprietary, Letter & Encl 2-5, Order Approving Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18214A6672018-08-22022 August 2018 FENOC Fleet - Perry Nuclear Power Plant, Unit No. 1 - Correction to the Issuance of Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules (CAC No. MG0136; EPID L-2017-LLA-0259) ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML17033A0142017-02-16016 February 2017 Issuance of Amendment Concerning Revision to Technical Specifications to Permit Installation of Upper Containment Pool Gate During Modes 1, 2, and 3 (CAC No. MF7476) (L-16-083) ML16158A3312016-09-14014 September 2016 Issuance of Amendment Concerning Revision to the Perry Nuclear Power Plant Emergency Plan ML16130A5362016-05-31031 May 2016 Issuance of Conforming Amendment Related to the Direct License Transfer of the Facility Operating License NPF-58 ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) ML15075A1392015-03-30030 March 2015 Issuance of Amendment Concerning Full Implementation of Alternative Source Term (TAC No. MF3197) (L-13-306) L-14-325, Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325)2015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML15075A0912015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML14205A6192014-08-29029 August 2014 Amendments to Indemnity Agreements (TAC MF0701, MF0702, MF0703, and MF0704) ML13136A1432013-05-16016 May 2013 Nucelar Power Plant, Unit 1 - Re-Issuance of Amendment Regarding Adoption of TSTF-275 and TSTF-300 ML13051B1442013-05-0606 May 2013 Issuance of Amendment Regarding Adoption of TSTF-275, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-Up, and TSTF-300 ML13017A4312013-04-18018 April 2013 Issuance of Amendment Revise Technical Specification 3.10.1, Inservice Leak, and Hydrostatic Testing Operation ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC ML1128602452011-10-17017 October 2011 Issuance of Amendment No. 160, Revise Technical Specification 3.8.1, AC Sources - Operating, Regarding Use of a Delayed Circuit as a Required Offsite Circuit (Emergency Circumstances) ML1125211222011-10-0404 October 2011 Issuance of Amendment Adoption of TSTF - 514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML1119203822011-08-29029 August 2011 Issuance of Amendment Cyber Security Plan 2023-09-29
[Table view] Category:Safety Evaluation
MONTHYEARML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) ML21063A1572021-03-0404 March 2021 Safety Evaluation for Alternative Request SR-2, Revision 0 Related to one-time Extension Snubbers Testing to ASME OM Code for the Fourth 10-year Inservice Interval at Perry Nuclear Power Plant Unit 1, Docket Nos. 50-440 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML19072A0122019-03-15015 March 2019 Correction to License Amendment No. 184 Related to Adoption of Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML17193A3822017-07-18018 July 2017 Correction to Safety Evaluation for License Amendment No. 177 ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) 2023-09-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 27, 2015 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -ISSUANCE OF AMENDMENT CONCERNING SAFETY LIMIT CRITICAL POWER RATIO VALUES (TAC NO. MF5007)(L-14-325)
Dear Mr. Harkness:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 165 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1. This amendment revises the technical specifications (TS) in response to your application dated October 8, 2014, as supplemented by a letter dated February 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 14289A 117 and ML 15043A478, respectively).
This amendment revises the TS safety limit minimum critical power ratio (SLMCPR) value during single-recirculation-loop operation to support the use of Global Nuclear Fuel-2 fuel starting at the next operating cycle. A copy of the Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-440
Enclosures:
- 1. Amendment No. 165 to NPF-58 2. Safety Evaluation cc w/encls: Listserv Sincerely, !RAJ Eva A Brown, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 License No. NPF-58 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee, FENOC) dated October 8, 2014, as supplemented by a letter dated February 12, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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; 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 1 O 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 Facility Operating License No. NPF-58 is hereby amended to read as follows: Enclosure 1 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 165 are hereby incorporated into this license. FENOC 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 its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
Mm::h 27, 2015 Enclosure 1
ATTACHMENT TO LICENSE AMENDMENT NO. 165 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Facility Operating License and 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 License NPF-58 Page 4 TSs 2.0-1 License NPF-58 Page 4 2.0-1 renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions.
Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 1 O CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license. (b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein. (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 165 are hereby incorporated into the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Antitrust Conditions
- a. FirstEnergy Nuclear Generation Corp. and Ohio Edison Company Amendment No.165
2.0 SAFETY
LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure<
785 psig or core flow < 10% rated core flow: THERMAL POWER shall 23.8% RTP. SLs 2.0 2.1.1.2 With the reactor steam dome 785 psig and core flow 10% rated core flow: The Minimum Critical Power Ratio (MCPR) shall 1.10 for two recirculation loop operation 1.13 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater.than the top of active irradiated fuel. 2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall 1325 psig. 2.2 SL Violations With any SL violation.
the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance with all Sls: and 2.2.2 Insert all insertable control rods. PERRY -UN IT 1 2.0-1 Amendment Nn. 165 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 165 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
1.0 INTRODUCTION
OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440 By application to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated October 8, 2014, as supplemented by a letter dated February 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 14289A 117 and ML 15043A478, respectively).
FirstEnergy Nuclear Operating Company (the licensee or FENOC) requested changes to the technical specifications (TSs) for the Perry Nuclear Power Plant, Unit 1 (PNPP or Perry). The amendment request proposes to revise the TS safety limit minimum critical power ratio (SLMCPR) values to reflect the change to Global Nuclear Fuel (GNF)-2 fuel. More specifically, the licensee proposes to change the SLMCPR value in TS 2.1.1.2 from 1.11 to 1.13 for single-recirculation-loop operation (SLO). The February 12, 2015, supplement, contained clarifying information and did not change the NRC staff's initial proposed finding of no significant hazards consideration.
2.0 REGULATORY EVALUATION
2.1 Background
Perry is a boiling-water reactor (BWR)/6 with a Mark Ill containment design which has two recirculation loops. Perry Cycle 16 core loading consists of 280 fresh GNF-2 fuel bundles, 280 once-burnt General Electric (GE)14 fuel bundles, 184 twice-burnt GE14 fuel bundles, and 4 thrice-burnt GE14 fuel bundles. The SLMCPR value for two recirculation loop operation (TLO) is not changing.
This amendment supports the Perry Operating Cycle 16 core design. Enclosure 2 2.1.1 Methodology The Perry Cycle 16 SLMCPR values were developed using the following NRG-approved methodologies and uncertainties:
- NEDC-32601 P-A "Methodology and Uncertainties for Safety Limit MCPR [minimum critical power ratio] Evaluations,"
- NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel," and
- NEDC-32505P-A "A-Factor Calculation Method for GE11, GE12 and GE13 Fuel." No departures from NRG-approved methodologies were identified in the Perry Cycle 16 SLMCPR calculations.
Plant-specific use of these methodologies must adhere to certain restrictions.
Based on a review of the applicable topical reports (i.e., NEDC-32601 P-A, NEDC-32694P-A) as well as the Office of Nuclear Reactor Regulation's Amendment 25 to NEDE-24011-P-A (GESTAR II), the following guidance should be considered when using the associated topical reports: 1. The TGBLA (lattice physics code) fuel rod power calculational uncertainty should be verified when applied to fuel designs not included in the benchmark comparisons of Table 3.1 of NEDC-32601 P, since changes in fuel design can have a significant effect on calculation accuracy.
- 2. The effect of the correlation of rod power calculation uncertainties should be reevaluated to ensure the accuracy of A-Factor uncertainty when the methodology is applied to a new fuel lattice. 3. In view of the importance of MIP (MCPR Importance Parameter) criterion and its potential sensitivity to changes in fuel bundle designs, core loading and operating strategies, the MIP criterion should be reviewed periodically as part of the procedural review process to ensure that the specific value recommended in NEDC-32601-P is applicable to future designs and operating strategies.
2.2 Regulatory
Requirements and Guidance Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. In Section 50.36, "Technical specifications," of Title 1 O of the Code of Federal Regulations (1 O CFR), the NRC established its regulatory requirements related to the content of TSs. TSs are required to include items in the following five specific categories related to station operation:
(1) safety limits, limiting safety system settings, and limiting control settings, (2) limiting conditions for operation (LCOs), (3) surveillance requirements (SRs), (4) design features, and (5) administrative controls.
Section 50.36(c)(1
)(i)(A) requires that the licensee establish safety limits for important process variables necessary for an appropriate level of protection to maintain the integrity of certain physical barriers that guard against the uncontrolled release of radioactive material.
The SLMCPR is calculated on a cycle-specific basis because it is necessary to account for the core configuration-specific neutronic and thermal-hydraulic response.
General Design Criteria 10, "Reactor design," of Appendix A to 10 CFR Part 50 states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed to assure that specified acceptable fuel design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
Fuel design limits can be exceeded if the core exceeds critical power. Critical power is a term used for the power at which the fuel departs from nucleate boiling and enters a transition to film boiling. For BWRs, the critical power is predicted using a correlation known as the GE critical quality boiling length correlation, or better known as the GEXL correlation.
Due to core wide and operational variations, the margin to boiling transition is most easily described in terms of a critical power ratio (CPR), which is defined as the rod critical power as calculated by GEXL divided by the actual rod power. The more a CPR value exceeds 1.0, the greater the margin to boiling transition is. The SLMCPR is calculated using a statistical process that takes into account operating parameters and uncertainties.
The operating limit MCPR (OLMCPR) is equal to the SLMCPR plus a CPR margin for transients.
At the OLMCPR, at least 99.9 percent of the rods avoid boiling transition during steady state operation and transients (Section 4.4, "Thermal and Hydraulic Design," of NUREG-0800, Revision 3, dated June 1996) caused by a operator error or equipment malfunction.
3.0 TECHNICAL
EVALUATION
3.1 Topical
Report Guidance As discussed above, the following topical report guidance were identified to apply in support of the licensee's proposed change: 1. The TGBLA {lattice physics code) fuel rod power calculational uncertainty should be verified when applied to fuel designs not included in the benchmark comparisons of Table 3.1 of NEDC-32601 P, since changes in fuel design can have a significant effect on calculation accuracy.
- 2. The effect of the correlation of rod power calculation uncertainties should be reevaluated to ensure the accuracy of A-Factor uncertainty when the methodology is applied to a new fuel lattice. 3. In view of the importance of MIP (MCPR Importance Parameter) criterion and its potential sensitivity to changes in fuel bundle designs, core loading and operating strategies, the MIP criterion should be reviewed periodically as part of the procedural review process to ensure that the specific value recommended in NEDC-32601-P is applicable to future designs and operating strategies.
3.1.1 Use of GNF-2 Fuel In NEDC-32505P-A, Revision 1, the fuel vendor provided a methodology to address differences which could affect the GEXL correlation from new fuel types approved by the NRC in a letter dated January 11, 1999 (ADAMS Accession No. ML060520637).
At the time of approval of the topical report, the focus was on R-factor calculation method (used for GE 11, 12, and 13) and the reference
- R-factor calculation method (used for GE6, 7, 8, 9 and 10). As discussed in Section 2.5 (Methodology Restrictions) of the attachment to the submittal, when new fuel types were introduced an analysis confirming that the R-factor methodology approved in NEDC-32505P-A remained valid. In a letter dated September 24, 2001 (ADAMS Accession No. ML012710272), GNF addressed TGBLA fuel rod power calculational uncertainty and the effect of the correlation of rod power calculation uncertainties.
The NRC questioned the differences in design and geometrical considerations between GNF-2 and GE 14 fuel. In the supplement dated February 12, 2015, the licensee stated that GNF-2 is an evolutionary fuel product based on GE 14 and that it is not considered a new fuel design as it maintains the previously established 10X10 array. The licensee states that the rod power calculational uncertainties are dominated by geometrical considerations in which GE 14 is identical to GE 12. The NRC staff determined that GNF-2 fuel is designed for mechanical, nuclear, and hydraulic compatibility with the other 1OX10 GNF fuel designs. The design has features of the currently operating GE10, GE11/13 and GE12/14 fuel including pellet-cladding interaction resistant barrier cladding, high performance spacers, part length rods, interactive thick corner/thin wall channel, and axial enrichment loading. The GNF-2 design is a 10X10 array with 92 fuel rods and two large central water rods, and 14 part length fuel rods. The part length rod configuration improves efficiency and reactivity margins. Table 3.1 of NEDC-32601 P provides GE 12 1Ox10 lattices.
The values given in Table 3.1 for GE 12 are representative of the values being calculated for GE14 and GNF-2. Based on the rod power calculational uncertainties used by GNF to develop the Perry Cycle 16 SLMCPR values being valid for GNF-2 fuel, the NRC staff determined that confirmation of the applicability of the approved R-factor methodology is not required for Perry's use of GNF-2 fuel. 3.1.2 MCPR Importance Parameter In Section 2.2.2 (Core Flow Rate and Randon Effective TIP [transverse core proble] Training) of Enclosure B to the submittal the licensee indicates that for Cycle 16, the minimum core flow SLMCPR calculation performed at 81 percent core flow and rated core power condition was limiting as compared to the rated core flow and rated core power condition.
The analysis indicates that, at low core flows, the limiting rod pattern and the nominal rod pattern are essentially the same. In its application, the licensee determined that the rod pattern used to calculate the SLMCPR at 100 percent rated power and 81 percent rated flow reasonably assures that at least 99.9 percent of fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences during the operation of Cycle 16. The NRC staff determined that the rod patterns used to calculate the SLMCPR at 81 percent of rated core flow and 100 percent of rated core power produce a limiting MCPR distribution that reasonably bounds the MCPR distributions that would be expected during the operation of the Perry core throughout Cycle 16. Therefore, the staff concludes that the licensee's submittal follows guidance for GNF-2 fuel and the minimum core flow condition.
3.1.3 Conclusion
In summary, the NRC staff concludes that the licensee has adequately addressed the guidance of Topical Reports NEDC-32601 P-A, NEDC-32694P-A, Amendment 25 to NEDE-24011-P-A (GESTAR II), and NEDC-32505P-A, and that the use of these reports to evaluate the Cycle 16 SLMCPR is acceptable.
3.2 Deviations
from the NRG-Approved Calculational Uncertainties
3.2.1 Channel
Bow The R-factor is an input into the GEXL correlation used to describe the local pin-by-pin power distribution and the fuel assembly and channel geometry on the fuel assembly critical power. The R-factor uncertainty analysis includes an allowance for power peaking modeling uncertainty, manufacturing uncertainty and channel bow uncertainty.
GNF has increased this uncertainty for all SLMCPR calculations to account for the potential impact of control blade shadow corrosion induced bow. As discussed in NEDC-32505P-A, GNF has generically increased the GEXL R-Factor uncertainty to account for an increase in channel bow due to the emerging unforeseen phenomenon called control blade shadow corrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved R-Factor uncertainty.
As discussed in Section 2.2.1 of the submittal, the Cycle 16 analysis shows an expected channel bow which is bounded by a GEXL R-Factor uncertainty that accounts for channel bow uncertainty.
Thus, the NRC staff finds that the use of a GEXL R-Factor uncertainty bounds the expected control blade shadow corrosion-induced channel bow for Cycle 16. 3.2.2 Core Flow Rate and Random Effective TIP Reading In a letter dated August 24, 2004 (ADAMS Accession No. ML042720293), GNF committed to the expansion of the state points used in the determination of the SLMCPR. Consistent with those commitments, analyses were performed at the rated core power and minimum licensed core flow point in addition to analyses at the rated core power and rated core flow point. The NRG-approved SLMCPR methodology was applied at each statepoint that was analyzed.
In Section 2.2.2 (Core Flow Rate and Random Effective TIP Reading) of the submittal, the licensee indicated that the core flow and random TIP reading uncertainties used in SLO minimum core flow SLMCPR analysis remain the same as in the rated core flow SLO SLMCPR analysis because these uncertainties (which are substantially larger than used in TLO analysis) already account for the effects of operating at reduced core flow. For SLO calculations performed at 81 percent core flow, the NRG-approved uncertainty values for the core flow rate (2.5 percent) and the random effective TIP reading (1.2 percent) are adjusted by dividing them by 81/100. The treatment of the core flow and random effective Tl P reading uncertainties is based on the assumption that the signal to noise ratio deteriorates as core flow is reduced. The licensee indicates in the submittal that this increase is conservative based on the expectation that the variability in the absolute flow will decrease as flow decreases.
Based on this increase in the uncertainty bounding the original non-flow dependent uncertainties, the NRC staff finds the treatment of core flow and random effective TIP reading uncertainties acceptable.
3.5 Core Monitoring System In Section 2.8 (Core Monitoring System) of the attachment to the submittal, the licensee indicates that for Cycle 16, the GNF 3D MONICORE system will be used as the core monitoring system. The 3D MONICORE system is in widespread use throughout the GNF fueled fleet of BWRs, including BWR/6 plants like Perry. Use of a current version of 3D MONICORE provides the plant capability to perform the reactivity anomaly surveillance.
Use of 30 MONICORE has been previously evaluated and accepted by the NRC in a letter dated March 11, 1999 (ADAMS Accession No. ML993140059).
Therefore, the NRC staff finds the use of the GNF 3D MON I CORE system for Cycle 16 to be acceptable.
3.6 Technical
Evaluation Conclusion The NRC staff concludes the licensee's proposed Cycle 16 SLMCPR value of 1.13 for SLO acceptable for Cycle 16 because it is developed through the appropriate use of NRG-approved methodologies in accordance with NRC staff guidance.
The staff further concludes that the licensee used methods consistent with the regulatory requirements and guidance identified in Section 2.0 above.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL
CONSIDERATION This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (80 FR 5819; February 3, 2015). Accordingly, this amendment meets 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 this amendment.
6.0 CONCLUSION
The NRC staff 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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Letter from C. R Pierce (First Energy Nuclear Operating Company (FENOC) to U.S. Nuclear Regulatory Commission, "Proposed Change to the PNPP's Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio," October 8, 2014. 2. Letter from C. R Pierce (First Energy Nuclear Operating Company (FENOC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information (RAI) Regarding Proposed Safety Limit Minimum Critical Power Ratio License Amendment (SLMCPR)," February 12, 2015 . 3. Global Nuclear Fuels Licensing Topical Report NEDE-24011-P-A-20, "General Electric Standard Application for Reactor Fuel," December 2013 (ADAMS Accession Nos. ML 13352A466 and ML 13352A467).
- 4. General Electric Nuclear Energy Licensing Topical Report NEDC-32601 P-A, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," August 1999 (ADAMS Accession No. ML 14093A216).
- 5. General Electric Nuclear Energy Licensing Topical Report NEDC-32505P-A, Revision 1, "R-Factor Calculation Method for GE11, GE12, and GE13 Fuel," July 1999 (ADAMS Accession No. ML060520636).
- 6. MFN-003-99, Letter, Frank Akstulewicz (NRC) to Glen A Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601 P, Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-24011-P-A on Cycle Specific Safety Limit MCPR," March 11, 1999 (ADAMS Accession No. ML993140059).
- 7. MFN 04-081, Letter from J.S. Post (GE) to NRC, "Part 21 Reportable Condition and 60-Day Interim Report; Notification:
Non-Conservative SLMCPR," August 24, 2004 (ADAMS Accession No. ML042720293).
- 8. NED0-31152 Revision 9, "Global Nuclear Fuels Fuel Bundle Designs", dated May 2007 (ADAMS Accession No. ML071510287). 9. Confirmation of 1Ox10 Fuel Design Applicability to Improved SLMCPR, Power Distribution and A-Factor Methodologies, dated September 24, 2001 (ADAMS Accession No. ML012710272).
Principal Contributor:
F. Forsaty, NRR .. Dateof Issuance:
fv'arch 27, 2015