Letter Sequence Request |
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TAC:ME0204, Changes to Reflect Revision of 10 CFR 50.55A, Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less (Approved, Closed) |
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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-Application for Facility Operating License (Amend/Renewal) DKT 50
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-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-23-001, 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-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant 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 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments 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-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-22-099, 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 ML21106A0202021-04-0707 April 2021 Enclosure a - Evaluation of Proposed Change L-20-240, License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control2021-03-0505 March 2021 License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control L-20-129, Emergency Plan Amendment Request2020-12-28028 December 2020 Emergency Plan Amendment Request L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020 ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names L-19-274, License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-3602020-04-24024 April 2020 License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-360 L-19-265, License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance2019-12-18018 December 2019 License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR2019-12-18018 December 2019 Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-18-046, License Amendment Request to Extend Containment Leakage Test Frequency2018-03-0707 March 2018 License Amendment Request to Extend Containment Leakage Test Frequency L-17-350, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement2018-02-14014 February 2018 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement L-17-045, Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control.2017-12-0606 December 2017 Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control. L-17-089, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips2017-06-20020 June 2017 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips L-17-042, Request for Licensing Action to Revise the Technical Specifications2017-06-0808 June 2017 Request for Licensing Action to Revise the Technical Specifications L-17-043, Request for Licensing Action to Revise the Environmental Protection Plan2017-04-26026 April 2017 Request for Licensing Action to Revise the Environmental Protection Plan L-17-052, Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32017-02-0606 February 2017 Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 L-16-179, License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits.2016-11-0101 November 2016 License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits. L-16-236, License Amendment Request for Adoption of Technical Specifications Task Force (Tstr Traveler TSTF-501. Revision 1. Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2016-10-27027 October 2016 License Amendment Request for Adoption of Technical Specifications Task Force (Tstr Traveler TSTF-501. Revision 1. Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-083, License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32016-03-15015 March 2016 License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 L-15-195, Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments2015-06-30030 June 2015 Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments L-14-271, Request for Licensing Action to Amend Technical Specification 3.8.4, DC Sources - Operating2014-11-24024 November 2014 Request for Licensing Action to Amend Technical Specification 3.8.4, DC Sources - Operating L-13-306, Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change2013-12-0606 December 2013 Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change ML13281A5362013-10-15015 October 2013 Meeting Slide for FENOC Presubmittal Guidance Checklist Part I L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013 Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest ML12249A3592012-09-0505 September 2012 License Amendment Request for Adoption of TSTF-275-A, Rev. 0, Clarify Requirement for EDG Start Signal on Rpv... & TSTF-300-A L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process2012-02-22022 February 2012 Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process L-11-331, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-11011 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-0303 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-038, License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation2011-04-12012 April 2011 License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation L-10-200, License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 12010-12-15015 December 2010 License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 1 ML1029804462010-10-21021 October 2010 License Amendment Request to Modify Technical Specification 2.1.1, Reactor Core Sls, to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values L-09-074, License Amendment Request to Provide Consistency in Division 3 Emergency Diesel Generator Start Time Technical Specification Surveillance Requirements2009-06-30030 June 2009 License Amendment Request to Provide Consistency in Division 3 Emergency Diesel Generator Start Time Technical Specification Surveillance Requirements L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. L-09-031, Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control2009-03-11011 March 2009 Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control ML0906306722009-03-0909 March 2009 Enclosure 14: Case Study 10: Perry Inability to Follow the RHR-SDC Required - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf L-08-325, License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 4972008-11-18018 November 2008 License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497 L-08-046, Request to Adopt TSTF-476-A, Improved BPWS Control Rod Insertion Process (NEDO-33091), Per the Consolidated Line Item Improvement Process2008-02-20020 February 2008 Request to Adopt TSTF-476-A, Improved BPWS Control Rod Insertion Process (NEDO-33091), Per the Consolidated Line Item Improvement Process 2024-01-24
[Table view] Category:Technical Specification
MONTHYEARML23303A1362023-10-27027 October 2023 Enclosure C - Pnpp Technical Specification Bases, Revision 18 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-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-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 ML21307A2072021-10-28028 October 2021 2 to Updated Safety Analysis Report, Revision 13 Technical Specifications Bases TS Bases L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-10-19019 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-20-185, License Amendment Request for Adoption of Tech Spec Task Force Traveler TSTF-230 Rev. 12021-02-17017 February 2021 License Amendment Request for Adoption of Tech Spec Task Force Traveler TSTF-230 Rev. 1 L-21-053, Supplemental Information Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-02-0202 February 2021 Supplemental Information Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-20-291, Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602020-11-19019 November 2020 Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 L-19-274, License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-3602020-04-24024 April 2020 License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-360 L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR2019-12-18018 December 2019 Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR L-18-174, Response to Request for Additional Information Regarding a Request to Revise the Technical Specifications to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control2018-07-24024 July 2018 Response to Request for Additional Information Regarding a Request to Revise the Technical Specifications to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control L-17-247, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602017-12-20020 December 2017 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 L-17-045, Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control.2017-12-0606 December 2017 Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control. ML17305A2382017-10-23023 October 2017 Technical Specification Bases, Rev. 11 L-17-108, Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules2017-08-11011 August 2017 Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules L-17-042, Request for Licensing Action to Revise the Technical Specifications2017-06-0808 June 2017 Request for Licensing Action to Revise the Technical Specifications L-15-235, Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler-4252015-08-24024 August 2015 Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler-425 L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process2012-02-22022 February 2012 Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process L-11-038, License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation2011-04-12012 April 2011 License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation L-10-200, License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 12010-12-15015 December 2010 License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 1 L-09-218, Submittal of Technical Specification Bases, Revision 72009-10-0505 October 2009 Submittal of Technical Specification Bases, Revision 7 L-09-031, Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control2009-03-11011 March 2009 Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control ML0906306722009-03-0909 March 2009 Enclosure 14: Case Study 10: Perry Inability to Follow the RHR-SDC Required - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf L-08-325, License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 4972008-11-18018 November 2008 License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497 ML0729102222007-10-12012 October 2007 Submittal of Technical Specification Bases, Revision 6 ML0711401262007-04-19019 April 2007 Technical Specification Pages, Deleting License Condition 2.F ML0630502502006-10-27027 October 2006 Issuance of Technical Specification Page Clarify Wording of Emergency Closed Cooling Water SR 3.7.10.2 ML0616700762006-06-0606 June 2006 License Amendment Requests to Revise Technical Specification 5.5.7, Ventilation Filter Test Program to Correct Referenced Flow Units ML0519402052005-07-0505 July 2005 License Amendment Request Pursuant to 10CFR50.90: Revision of Technical Specification Surveillance Requirement 3.3.1.3.5 Which Revises the Enabled Region for the Oscillation Power Range Monitors ML0500700132005-01-0606 January 2005 Tech Spec Pages for Amendment 131 Regarding Increase Flexibility in Mode Restraint ML0425300872004-08-31031 August 2004 License Amendment Request Pursuant to 1OCFR50.90: Revision of Technical Specification 3.4.1, 'Recirculation Loops Operating Associated with Single Recirculation Loop Operation ML0411701652004-04-23023 April 2004 Technical Specifications, Approve Administrative Procedures and Offsite Dose Calculation Manual ML0432202062004-04-0505 April 2004 License Amendment Request Pursuant to 10CFR50.90: Revision of the Minimum Critical Power Ratio Safety Limit ML0312200312003-04-29029 April 2003 Issuance of Amendment, Technical Specifications ML0309808202003-04-0808 April 2003 Issuance of Amendment, Technical Specification Page RBG-46072, Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing2003-03-14014 March 2003 Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing ML0231004072002-10-30030 October 2002 License Amendment Request Pursuant to 10 CFR 50.90: Elimination of Requirements for Post Accident Sampling System Using Consolidated Line Item Improvement Process 2023-06-05
[Table view] Category:Bases Change
MONTHYEARML23303A1362023-10-27027 October 2023 Enclosure C - Pnpp Technical Specification Bases, Revision 18 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-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 ML21307A2072021-10-28028 October 2021 2 to Updated Safety Analysis Report, Revision 13 Technical Specifications Bases TS Bases L-20-185, License Amendment Request for Adoption of Tech Spec Task Force Traveler TSTF-230 Rev. 12021-02-17017 February 2021 License Amendment Request for Adoption of Tech Spec Task Force Traveler TSTF-230 Rev. 1 L-21-053, Supplemental Information Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-02-0202 February 2021 Supplemental Information Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-20-291, Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602020-11-19019 November 2020 Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR2019-12-18018 December 2019 Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR L-17-045, Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control.2017-12-0606 December 2017 Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control. ML17305A2382017-10-23023 October 2017 Technical Specification Bases, Rev. 11 L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process2012-02-22022 February 2012 Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process L-11-038, License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation2011-04-12012 April 2011 License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation L-10-200, License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 12010-12-15015 December 2010 License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 1 L-09-218, Submittal of Technical Specification Bases, Revision 72009-10-0505 October 2009 Submittal of Technical Specification Bases, Revision 7 ML0906306722009-03-0909 March 2009 Enclosure 14: Case Study 10: Perry Inability to Follow the RHR-SDC Required - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf L-08-325, License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 4972008-11-18018 November 2008 License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497 ML0729102222007-10-12012 October 2007 Submittal of Technical Specification Bases, Revision 6 ML0519402052005-07-0505 July 2005 License Amendment Request Pursuant to 10CFR50.90: Revision of Technical Specification Surveillance Requirement 3.3.1.3.5 Which Revises the Enabled Region for the Oscillation Power Range Monitors ML0425300872004-08-31031 August 2004 License Amendment Request Pursuant to 1OCFR50.90: Revision of Technical Specification 3.4.1, 'Recirculation Loops Operating Associated with Single Recirculation Loop Operation 2023-06-05
[Table view] |
Text
FENOC %10 Perry Nuclear Power Ston CenterRoad FirstEnergyNuclear OperatingCompany Perry,Ohio 44081 Mark B. Bezilla 440-280-5382 Vice President Fax: 440-280-8029 November 18, 2008 L-08-325 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497 Pursuant to 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) hereby requests an amendment to the operating license for the Perry Nuclear Power Plant (PNPP). The proposed amendment would modify Technical Specification (TS) 5.5.6 to incorporate Technical Specification Task Force (TSTF) Travelers TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF 497, "Limit Inservice Testing Program SR
[Surveillance Requirement] 3.0.2 Application to Frequencies of 2 Years; or Less."
The PNPP second 10-year Inservice Testing (IST) interval concludes on May 17, 2009.
Therefore, FENOC requests approval of the proposed amendment by May 17, 2009, to coincide with the beginning of the third 10-year IST interval. There are no regulatory commitments contained in this letter. Ifthere are any questions or additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on November .L., 2008.
Sincerely, Mark B. Bezilla
Enclosure:
Evaluation of the Proposed License Amendment Request cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board 0C-/7
Evaluation of Proposed License Amendment Page 1 of 7
Subject:
License Amendment Request to incorporate Technical Specification Task Force Traveler (TSTF) 479 and TSTF 497.
- 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION
- 3. TECHNICAL EVALUATION
- 4. REGULATORY EVALUATION 4.1 Significant Hazards Consideration 4.2 Applicable Regulatory Requirements/Criteria 4.3 Precedent 4.4 Conclusions
- 5. ENVIRONMENTAL CONSIDERATION
- 6. REFERENCES Attachments:
- 1. Proposed Technical Specification Changes (Mark Up)
- 2. Proposed Technical Specification Changes (Re-typed -- For Information)
- 3. Proposed Technical Specification Bases Pages (Mark Up - For Information)
Perry Nuclear Power Plant License Amendment Request 08-018 Page 2 of 7 1.0
SUMMARY
DESCRIPTION The FirstEnergy Nuclear Operating Company requests Nuclear Regulatory Commission (NRC) review and approval of an amendment to the Perry Nuclear Power Plant (PNPP) Technical Specifications (TS). The proposed amendment updates references to the source of requirements for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves and addresses the applicability of Surveillance Requirement (SR) 3.0.2 to some non-standard pump and valve testing frequencies.
The proposed changes are administrative and are consistent with NRC-approved Technical Specification Task Force (TSTF) Traveler TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF 497, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less."
2.0 DETAILED DESCRIPTION The proposed change adopts TSTF-479, Revision 0 to revise references to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code in Technical Specification (TS) 5.5.6, "Inservice Testing Program." The proposed change deletes reference to Section XI of the Code and incorporates reference to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code). The proposed change also adopts TSTF-497, Revision 0 to limit Surveillance Requirement (SR) 3.0.2 applicability to normal and accelerated Inservice Testing (IST) Program frequencies specified as two years or less that are not specifically listed in the testing frequencies identified in TS 5.5.6.
2.1 Proposed Changes TS 5.5.6, "Inservice Testing Program," is revised to indicate that the Inservice Testing Program (IST) shall have testing Frequencies applicable to the ASME OM Code.
TS 5.5.6 is also revised to indicate that the provisions of SR 3.0.2 are applicable to some nonstandard frequencies utilized in the IST Program. Specifically, TS 5.5.6.b is revised to state:
"The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities."
Perry Nuclear Power Plant License Amendment Request 08-018 Page 3 of 7 Marked up pages of the affected Technical Specifications are provided in Attachment 1. Re-typed clean Technical Specification pages are provided for information in Attachment 2.
Various sections of the TS Bases will be revised for consistency with the requirements of 10 CFR 50.55a(f)(4). The changes to the affected TS Bases pages will be incorporated in accordance with TS 5.5.11, "Technical Specifications (TS)
Bases Control Program." Marked up pages of the affected Technical Specifications Bases are provided for information in Attachment 3.
2.2 Background
In 1990, the ASME published the initial edition of the ASME OM Code that provides rules for inservice testing of pumps and valves. The ASME OM Code was developed and is maintained by the ASME Committee on Operation and Maintenance of Nuclear Power Plants. The ASME OM Code was developed in response to the ASME Board on Nuclear Codes and Standards directive that transferred responsibility for development and maintenance of requirements for the inservice testing of pumps and valves from the ASME,Section XI, Subcommittee on Nuclear Inservice Inspection to the ASME OM Committee. Therefore, the ASME OM Code is to replace Section XI of the Boiler and Pressure Vessel Code for the inservice testing of pumps and valves. The 1995 edition of the ASME OM Code was incorporated by reference into 10 CFR 50.55a(b).
Since 10 CFR 50.55a(f)(4)(ii) requires that inservice testing during successive 10-year intervals complies with the requirements of the latest edition and addenda of the Code incorporated into 10 CFR 50.55a(b), TS 5.5.6 must be revised to reference the ASME OM Code.
3.0 TECHNICAL EVALUATION
The purpose of the Inservice Testing (IST) program is to assess the operational readiness of pumps and valves, to detect degradation that might affect component OPERABILITY, and to maintain safety margins with provisions for increased surveillance and corrective action. 10 CFR 50.55a defines the requirements for applying industry codes to each licensed nuclear power facility.Section XI of the ASME Code has been revised on a continuing basis over the years to provide updated requirements for the inservice inspection and inservice testing of components. As discussed above, until 1990, the ASME Code requirements addressing the inservice testing of pumps and valves were contained in Section Xl, Subsections IWP (pumps) and IWV (valves). Since the establishment of the 1990 Edition of the OM Code; the rules for inservice testing have been removed from Section XI.
Perry Nuclear Power Plant License Amendment Request 08-018 Page 4 of 7 The Code of record for the PNPP second 10-year IST testing interval, which concludes on May 17, 2009, is the 1989 Edition of ASME Code,Section XI. The PNPP third 10-year IST interval will begin on May 18, 2009, and the IST program for the interval will be in accordance with the 2001 Edition through the 2003 Addenda of the ASME OM Code, as required by 10 CFR 50.55a(f)(4)(ii).
By final rule issued on September 22, 1999, the NRC amended 10 CFR 50.55a(f)(4)(ii) to require licensees to update their IST Program to the latest approved edition of the ASME OM Code. The PNPP TS, 5.5.6, currently references the ASME Boiler and Pressure Vessel Code,Section XI, as the source of the IST Program requirements for ASME Code 1, 2, and 3 components.
Therefore, the proposed changes to TS 5.5.6 are necessary to reference the OM Code versusSection XI.
TS 5.5.6 is also revised to limit the scope of applicability of the provisions of SR 3.0.2 for those IST activities with frequencies that are not specifically listed in the testing frequencies identified in TS 5.5.6. The IST program may have frequencies for testing that are based on risk or other factors and do not conform to the standard testing frequencies. Application of SR 3.0.2 to these other IST frequencies specified as two years or less is consistent with the guidance in NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants," paragraph 3.1.3.
4.0 REGULATORY EVALUATION
The proposed changes are administrative in nature and revise the requirements in TS 5.5.6, "Inservice Testing Program," to update references to the ASME Boiler and Pressure Vessel Code, Section Xl, as the source of requirements for the inservice testing of ASME Code Class 1, 2, and 3 pumps and valves. The proposed changes delete reference to Section XI of the Code, incorporate reference to the ASME OM Code, and address the applicability of Surveillance Requirement (SR) 3.0.2 to normal and accelerated Inservice Testing Program frequencies specified as two years or less that are not specifically listed in the testing frequencies identified in TS 5.5.6.
4.1 Significant Hazards Consideration The FirstEnergy Nuclear Operating Company (FENOC) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment to the PNPP TS by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Perry Nuclear Power Plant License Amendment Request 08-018 Page 5 of 7 Response: No.
The proposed amendment revises TS 5.5.6, "Inservice Testing Program,"
for consistency with 10 CFR 50.55a(f)(4) requirements regarding inservice testing of pumps and valves. The proposed amendment incorporates revisions to the ASME Code that result in a net improvement in the measures for testing pumps and valves.
The proposed changes do not impact any accident initiators or analyzed events or assumed mitigation of accident or transient events. They do not involve the addition or removal of any equipment, or any design changes to the facility. Therefore, the proposed changes do not represent a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes do not involve a modification to the physical configuration of the plant. There is no new equipment to be installed or a change in the methods governing normal plant operation. The proposed change will not impose any new or different requirements or introduce a new accident initiator, accident precursor, or malfunction mechanism.
Additionally, there is no change in the types or increases in the amounts of any effluent that may be released off-site and there is no increase in individual cumulative occupational exposure. Therefore, the proposed change does not create the possibility of an accident of a different kind than previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed amendment revises TS 5.5.6, "lnservice Testing Program,"
for consistency with the requirements of 10 CFR 50.55a(f)(4) regarding the inservice testing of pumps and valves. The proposed amendment incorporates revisions to the ASME Code that result in a net improvement in the measures for testing pumps and valves. The safety function of the affected pumps and valves will be maintained. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Perry Nuclear Power Plant License Amendment Request 08-018 Page 6 of 7 Based on the above, FENOC concludes that the proposed amendment 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.
4.2 Applicable Regulatory Requirements/Criteria NRC regulation, 10 CFR 50.55a, defines the requirements for applying industry codes to each licensed nuclear powered facility. The regulations require that IST of pumps and valves conducted during successive 120-month intervals must comply with the requirements of the latest edition and addenda of the Code incorporated into paragraph (b) of 10 CFR 50.55a 12 months before the start of the 120-month interval.
The proposed amendment ensures FENOC will continue to comply with the requirements of 10 CFR 50.55a.
4.3 Precedent The NRC accepted TSTF-479 in December 2005 and TSTF-497 in October 2006.
Amendments adopting TSTF-479 and TSTF-497 have been approved for the Brunswick Steam Electric Plant (Amendments 247 and 275 - TAC Nos.
MD6916 and MD6917), the Diablo Canyon Power Plant (Amendments 196 and 197 - TAC Nos. MD3975 and MD3976), and the Columbia Generating Station (Amendment 205 - TAC No. MD6209).
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed change would change a requirement with respect to installation or use of a facility component located within the restricted areas, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii)a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase
Perry Nuclear Power Plant License Amendment Request 08-018 Page 7 of 7 in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
6.0 REFERENCES
- 1. U. S. Nuclear Regulatory Commission, "Guidance for Inservice Testing at Nuclear Power Plants," NUREG-1482, Revision 1, January 2005
- 2. Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a"
- 3. Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-497, Revision 0, "Limit Inservice Tresting Program SR 3.0.2 Application to Frequencies of 2 Years or Less"
- 4. Federal Register Notice: Industry Codes and Standards; Amended Requirements, published September 22, 1999 (64 FR 51370)
- 5. American Society of Mechanical Engineers Operation and Maintenance Code for Operation and Maintenance of Nuclear Power Plants, :2001 Edition including the OMa-2002 and OMb-2003 Addenda
Attachment 1 PROPOSED TECHNICAL SPECIFICATION CHANGES (Mark Ups)
Page 1 of 3
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program-shall include the__
following:
AM-endaterminolob' for inservice testinQ activities
....... ii Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually. At least once per 366 days Biennially or every 2 years At least once per 731 days
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities: and
- d. Nothing in the ASME Boiler and Pressure ___Conde shall bE construed to supersede the requlrements of any TS.
5.5.7 Ventilation Filter Testing ProQram (VFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.
(continued)
PERRY - UNIT 1 5.0-10 Amendment No.4
INSERT 1 The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
Attachment 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (Re-Typed - For Information Only)
Page 1 of 2
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2. and 3 components. The program shall include the following:
- a. Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code)and applicable Addenda as follows:
ASMEOM Code and applicable Required frequencies Addenda terminology for for performing inservice inservice testing activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Year]y or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.
5.5.7 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.
(continued)
PERRY - UNIT 1 5.0-10 Amendment No.
Attachment 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES (Mark Ups - For Information Only)
Page 1 of 11
S/RVs B 3.4.4 BASES SURVEILLANCE SR 3.4.4.3 (continued)
REQUIREMENTS The successful performance of the S/RVs tested provides
- reasonable assurance that the remaining installed S/RVs will perform in a similar fashion. After the. S/RVs are replaced, the power-operated actuator of all 19 S/RVs will be uncoupled from the S/RV stem, and cycled to ensure proper operation of the control circuit and actuator. Following cycling, the power-operated actuator is recoupled and the proper positioning of the stem nut is independently verified. This verifies that each S/RV will properly perform its intended function. If the valve actuator fails to operate due only to the failure of the solenoid but iscapable of opening the valve on overpressure, the safety function of theý S/RV is considered OPERABLE.
When removing and replacing the SIRVs, Foreign Material Exclusion controls will be in place to minimize the potential for unwanted materials from entering into any S/RV opening or the piping discharge lines.
SR 3.4.4.2 and the LOGIC SYSTEM FUNCTIONAL TEST performed in SR 3.3.6.4.4 overlap this surveillance to provide complete testing of the assumed safety function The 24 months on a STAGGERED TEST BASIS Frequency ensures that each solenoid for each S/RV is alternately tested. The 24 month Frequency wa develoed basedon th2eS/RVtests 9 rggure the ME( .... 'Pl=]Cod k)enn. The-24month Frequency is based on operaTing experien e. and is consistent with a typical industry refueling 1c S@
REFERENCES 1. 4AM oiler and Pressure Vessel Code. SectioneIII.
- 2. USAR, Chapter 15, Appendix 15B.
- 3. USAR, Section 15.
- 4. NRC Safety Evaluation to NEDC-31753P. March 8. 1993.
5P. -[UNT 1 5.42ppRendnX IN PERRY -UNIT 1 B 3.4-22 Revision No. 5
INSERT 1 ASME Code for Operation and Maintenance of Nuclear Power Plants
RCS PIV Leakage B 3.4.6 BASES SURVEILLANCE SR 3.4.6.1 (continued)
REQUIREMENTS The Frequency require rvice Testing Program is within the ASME Code. ,T,Frequency requirement.
REFERENCES 1. 10 CFR 50.2.
- 2. 10 CFR 50.55a(c).
- 3. 10 CFR 50. Appendix A, GDC 55.
- 4. 424, Rol!e@Pnd PPes,-re Vessel 9ed- Szectins* ]
- 5. NUREG-0677. "The Probability of Intersystem LOCA:
Impact Due to Leak Testing and Operational Changes,"
May 1980.
- 6. PNPP - Unit 1, Inservice Test Program.
PERRY - UNIT 1 B 03.4-32 Revision No. 1
"- -ECCS-Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7 (continued)
REQUIREMENTS SR 3.5.1.6 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1.6 overlap this Surveillance to provide complete testing of the safety function. The Frequency of 24 months on a STAGGERED TEST BASIS Frequency ensures that both solenoids for each ADS valve power-operated actuator are alternately tested. The Frequency of the required-power-opera ted__*ctuat~nG++/-est i,5 based on the tests required by ASM- Ns implemented by the Inservice c-T~i estig -- ogram6-tSpeciication 5.5.6. The testing Coc* Frequency required by the.Inservice Testing Program is based on operating experience and valve performance. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.5.1.8 This SR ensures that the ECCS RESPONSE TIMES are within limits for each of the ECCS injection and spray. subsystems.
This SR is modified by a note which identifies that the associated ECCS actuation instrumentation is not required to be response time tested. Response time testing of the remaining subsystem components is required. This is supported by Reference 15. Response time testing acceptance criteria are included in Reference 16.
ECCS RESPONSE TIME tests are conducted every 24 months. The 24 month Frequency is based on the need to perform this (continued)
PERRY - UNIT 1 B 3.5-13a Revision No. 5
ECCS-Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS SR 3.5.1.8 (continued)
Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on operating eýperience, and is consistent with a typical industry refueling cycle.
REFERENCES 1. USAR, Section 6.3:2.2.3.
- 2. USAR. Section 6.3.2.2.4.
- 3. USAR, Section 6.3.2.2.1.
- 4. USAR, Section 6.3.2.2.2.
- 5. USAR, Section 15.6.6.
- 6. USAR. Section 15.6.4.
- 7. USAR, Section 15.6.5.
- 8. 10 CFR 50, Appendix K.
- 9. USAR, Section 6.3.3.
- 10. 10 CFR 50.46.
- 11. USAR, Section 6.3.3.3.
- 12. Memorandum from R.L. Baer (NRC) to V. Stello, Jr.
(NRC), "Recommended Interim Revisions to LCO's for ECCS Components." December 1. 1975.
- 13. USAR, Section 5.2.2.4.1. EF - .
- 14. o SG.
- 15. NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements,"
January 1994.
- 16. USAR, Section 6.3, Table 6.3-1.
PERRY - UNIT 1 B 3.5-14 Revision No. 5
LLS Valves B 3.6.1.6 BASES (continued)
SURVEILLANCE SR 3.6.1.6.1 REQUIREMENTS Method 2:
The required population of LLS S/RVs tested will be stroke in the relief mode during testing at a qualified offsite facility to verify proper operation of the S/RV.
The successful performance of the S/RVs tested provides reasonable assurance that the remaining installed S/RVs will perform in a similar fashion. After the S/RVs are replaced, the power-operated actuator of all 19 S/RVs will be uncoupled from the S/RV stem, and cycled to ensure proper operation of the control circuit and actuator. Following cycling, the power-operated actuator is recoupled and the proper positioning of the stem nut is independently verified. This verifies that each S/RV will properly perform its intended function. If the valve actuator fails to operate due only to the failure of the solenoid but is capable of opening the valve on overpressure. the safety mode of the S/RV is considered OPERABLE.
When removing and replacing the S/RVs, Foreign Material Exclusion controls will be in place to minimize the potential for unwanted materials from entering into any S/RV opening or the piping discharge lines.
The STAGGERED TEST BASIS Frequency ensures that both solenoids for each LLS valve power-operated actuator are alternately tested. *The 24 Month Frequency of the required power-operated ac m-lesting i based on the tests required by ASRef. s implemented by the 1iie g.Prograaof Specification 5.5.6. The
- testing Frequency required by th Inservice Testing Program is based on operating-experience and valve performance.
Therefore, the Frequency was con luded to be acceptable from a reliability standpoint.
(continued)
PERRY - UNIT I B 3.6-41a Revision No. 5
LLS Valves B 3.6.1.6 BASES SURVEILLANCE SR 3.6.1.6.2 REQUIREMENT
.(continued) The LLS function S/RVs are required to actuate automatically upon receipt of specific initiation signals. A functional test is performed to verify that the mechanical portions (i.e.. solenoids) of the automatic LLS function operate as designed when initiated either by an actual or simulated automatic initiation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.4.4 overlaps this SR to provide complete testing of the-safety function.
The 24 month Frequency is based on the need to perform this Surveillance during a plant outage and the potential for an unplanned transient if the Survei-llance were performed with the reactor at power. The 24 month Frequency is based on operating experience, and is consistent with a typical industry refueling cycle.
This SR is modified by a Note that excludes valve actuation.
This prevents a reactor pressure vessel pressure blowdown.
REFERENCES 1. GESSAR-II. Appendix 3B. Attachment A, Section 3BA.8.
- 2. USAR, Section 7.6.1.11.
- 3. Af ltr--. " Xi _ .7_
PERRY - UNIT 1 B 3.6-42 Revision No. 5
RHR Containment .Spray System B 3.6.1.7 BASES SURVEILLANCE SR 3.6.1.7.1 (continued)
REQUIREMENTS A Note has been added to this SR that allows RHR containment spray subsystems to be considered OPERABLE during alignment and operation for decay heat removal with reactor steam pressure less than the RHR cut in ermissive pressure in MODE 3, if capable of being manually realigned (remote or local) and not otherwise inoperable. This allows operation in the RHR shutdown cooling mode during MODE 3 if necessary.
SR 3.6.1.7.2 Verifying each RHR pump develops a flow rate 2 5250 gpm with flow through the associated heat exchangers ensures that pump performance has not degraded below the required flow rate during the cycle. It is tested in the suppression pool cooling mode to demonstrate pump OPEFABILITY without spraying down equipment in primary containment. Flow is a normal test of tenfugal pump performance required by the ASME 2). This test confirms one point on the-pump-'sign curve and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY, trend performance. and detect incipient failures by indicating abnormal performance. The Frequency of this SR is in accordance with the Inservice Testing Program.
SR 3.6.1.7.3 This SR verifies that each RHR containment spray subsystem automatic valve actuates to its correct position upon receipt of an actual or simulated automatic initiation signal. Actual spray initiation is not required to meet this SR. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.3.5 overlaps this SR to provide complete testing of the safety function. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on (continued)
PERRY - UNIT 1 B 3.6-46 Revision No. 3
RHR Containment Spray System B 3.6.1.7 QBA SES SURVEILLANCE SR 3.6.1.7.3 (continued)
REQUIREMENTS operating experience, and is consistent with a typical industry refueling cycle.
SR 3.6.1.7.4 This Surveillance is performed following naintenance which could result in nozzle blockage using an inspection of the nozzle or an air or smoke flow test to verify that the spray nozzles are not obstructed and that flow will be provided when required. The frequency is adequate to detect degradation in performance due to the passive nozzle design and its normally dry state and has been shown to be acceptable through operating, experience.
REFERENCES 1. USAR, Section 6.2.1.1.5.
- 2. .... ......e . .. ........
PERRY - UNIT 1 B 3.6-47 Revision No. 3
RHR Suppression Pool Cooling System B 3.6.2.3 BAS ES SURVEILLANCE SR 3.6.2.3.2 REQUIREMENTS (continued) Verifying each RHR pump develops a flow rate z 7100 gpm with flow through the associated heat exchanger' to the suppression pool, ensures that pump performance has not degraded during the cycle. Flow is a normal test of centrifugal pump performance required by ASME Section XI (Ref. 2). This test confirms one point on the pump design curve, and the results are indicative of cverall performance. Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this SR is in accordance with the Inservice Testing Program.
REFERENCES 1. USAR., Section 6.2. * *..7_
- 2. 1 pd Pr-ess-r e aes1-lG A.d, S t4l PERRY - UNIT 1 B 3.6-82 Revision No. 1