Letter Sequence Request |
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TAC:ME0886, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action (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:Amendment
MONTHYEARL-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-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-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-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-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-17-108, 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-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 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 ML0500700132005-01-0606 January 2005 Tech Spec Pages for Amendment 131 Regarding Increase Flexibility in Mode Restraint 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] |
Text
FENOC Perry Nuclear Power Station 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 MarkB. Bezilla 440-280-5382 Vice President Fax: 440-280-8029 March 11,2009 L-09-031 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 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequencv Example In accordance with the provisions of 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the technical specifications (TS) for the Perry Nuclear Power Plant (PNPP).
The proposed amendment would: (1) revise TS surveillance requirement (SR) frequency in TS 3.1.3, Control Rod OPERABILITY, and (2) revise Example 1.4-3 in Section 1.4 Frequency to clarify the applicability of the 1.25 surveillance test interval extension.
The enclosure provides the evaluation for the proposed amendment.
Approval of the license amendment is requested prior to August 29, 2009, with the amendment to be implemented within 90 days following its effective date.
Regulatory commitments associated with this submittal are included in the attachment. If there are any questions or if 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 March L\, 2009.
Mark B. Bezillal/
March 11, 2009 L-09-031 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 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example In accordance with the provisions of 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the technical specifications (TS) for the Perry Nuclear Power Plant (PNPP).
The proposed amendment would: (1) revise TS surveillance requirement (SR) frequency in TS 3.1.3, Control Rod OPERABILITY, and (2) revise Example 1.4-3 in Section 1.4 Frequency to clarify the applicability of the 1.25 surveillance test interval extension.
The enclosure provides the evaluation for the proposed amendment.
Approval of the license amendment is requested prior to August 29, 2009, with the amendment to be implemented within 90 days following its effective date.
Regulatory commitments associated with this submittal are included in the attachment. If there are any questions or if 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 March ___, 2009.
Sincerely, Mark B. Bezilla
Perry Nuclear Power Plant L-09-031 Page 2 of 2
Attachment:
Regulatory Commitment List
Enclosure:
Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment L-09-031 Regulatory Commitment List Page 1 of 1 The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Perry Nuclear Power Plant in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not Regulatory Commitments. Please notify Mr.
Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071 of any questions regarding this document or associated Regulatory Commitments.
Regulatory Commitment Due Date
- 1. FENOC commits to revising Technical Concurrent with amendment Specification Bases based on TSTF-475, implementation.
Revision 1 as proposed in Attachment 2 to the Enclosure.
Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example
- 1. DESCRIPTION
- 2. ASSESSMENT 2.1 APPLICABILITY OF PUBLISHED SAFETY EVALUATION 2.2 OPTIONAL CHANGES AND VARIATIONS
- 3. REGULATORY ANALYSIS 3.1 NO SIGNIFICANT HAZARDS DETERMINATION 3.2 VERIFICATION AND COMMITMENTS
- 4. ENVIRONMENTAL EVALUATION Attachments:
- 1. Proposed Technical Specification Changes (Mark-Up)
- 2. Proposed Changes to Technical Specifications Bases
- 3. Proposed Technical Specification Changes (Retyped)
Page 2 of 3
1.0 DESCRIPTION
The proposed amendment would: (1) revise the Technical Specification (TS)
Surveillance Requirement (SR) 3.1.3.2 frequency in TS 3.1.3, Control Rod OPERABILITY, and (2) revise Example 1.4-3 in Section 1.4, Frequency, to clarify the applicability of the 1.25 surveillance test interval extension.
The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification (STS) change TSTF-475, Revision 1. The Federal Register notice published on November 13, 2007 announced the availability of this TS improvement through the consolidated line item improvement process (CLIIP).
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation FirstEnergy Nuclear Operating Company (FENOC) has reviewed the safety evaluation dated November 5, 2007 as part of the CLIIP. This review included a review of the NRC staffs evaluation, as well as the background information provided to support TSTF-475, Revision 1. FENOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Perry Nuclear Power Plant (PNPP), Unit 1 and justify this amendment for the incorporation of the changes to the PNPP TS.
2.2 Optional Changes and Variations TSTF-475, Revision 1 proposes three changes to the STS. The proposed change: (1) revises the TS control rod notch surveillance frequency in TS 3.1.3, (2) clarifies the TS 3.3.1.2 requirement for fully inserting control rods for one or more inoperable SRMs in Mode 5, and (3) revises one example in Section 1.4, Frequency, to clarify the applicability of the 1.25 surveillance test interval extension.
Only two of the changes are proposed for this amendment application. The change to TS 3.3.1.2, which is not included in this amendment application, would have incorporated the word fully into Required Action E.2, Source Range Monitoring Instrumentation, as follows:
Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
The word fully is already in PNPP TS 3.3.1.2, Required Action E.2, Source Range Monitoring Instrumentation. Therefore, no change is necessary to incorporate this aspect of TSTF-475 into the PNPP TS.
Page 3 of 3 FENOC is not proposing any other variations or deviations from the TS changes described in the modified TSTF-475, Revision 1 and the NRC staffs model safety evaluation dated November 5, 2007.
FENOC is proposing a variation relative to the proposed TS Bases changes contained in TSTF-475, Revision 1. The TSTF-475 proposed TS Bases discussion for SR 3.1.3.3 (previously identified as SR 3.1.3.4) would remove SR 3.1.4.4 from the listed SRs performed in conjunction with SR 3.1.3.3. Incorporation of this change would be inconsistent with TS SR 3.1.3.3, which includes SR 3.1.4.4 in the Frequency column.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination FENOC has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the CLIIP. FENOC has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to PNPP without need for modification despite the deviation described in Section 2.2 of this application and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
3.2 Verification and Commitments As discussed in the notice of availability published in the Federal Register on November 13, 2007 for this TS improvement, FENOC verifies the applicability of TSTF-475 to PNPP, and commits to revising Technical Specification Bases based on TSTF-475, Revision 1, as proposed in Attachment 2.
These changes are based on TSTF change traveler TSTF-475, Revision 1, which proposes revisions to the STS by: (1) revising the frequency of SR 3.1.3.2, notch testing of fully withdrawn control rod, from 7 days after the control rod is withdrawn and THERMAL POWER is greater than the [Low Power Setpoint] LPSP of [Rod Pattern Control System] RPCS to 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RPCS, and (2) revising Example 1.4-3 in Section 1.4, Frequency, to clarify that the 1.25 surveillance test interval extension in SR 3.0.2 is applicable to time periods discussed in NOTES in the SURVEILLANCE column in addition to the time periods in the FREQUENCY column.
4.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model safety evaluation dated November 5, 2007 as part of the CLIIP. FENOC has concluded that the staffs findings presented in that evaluation are applicable to PNPP without need for modification despite the deviation described in Section 2.2 of this application, and the evaluation is hereby incorporated by reference for this application.
Page 1 of 9 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)
"Thereafter" lndicates future performances must be established per SR 3.0.2, but only after a specified condition i s ffrst met (Le., the "once" performance i n t h i s example).
I f reactor power decreases to < 25% RTP, the measurement o f both intervals stops. New intervals start upon reactor power reaching 25% RTP.
EXAMPLE 1, 4-3 The interval continues whether or not the unit operation i s
< 25% RTP between perfownces.
As the Note modifies the required performance o f the Surveillance, i t i s construed to be p a r t o f the "specified Frequency." Should the 7 day interval be exceeded while operation i s < 25% RTP, t h i s Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches 2 25% RTP t o perform the Surveillance. The Surveillance i s still consldered to be within the "specffied Frequency. Therefore, i f the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) Interval, but operatton was < 25% RTP, 3t would not c o n s t j t u t e a failure of the SR or fai'luret o meet the LCO. Also, no v i o l a t i o n o f SR 3,0.4 occurs when changing MDU, even w i t h the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i t h power 2 25% RTP.
tCORt5W$dl I
PERRY - UNIT 1 1.0-27 Amendment No, 69
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)
Once the u n i t reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed f o r I f the Survei 1lance were not ompletingwthe erformed t h j 1lance.
i t h i nSurvei hour i@erVtiJp there would then be t a l lure t o perrorinsalhver I lance wqthin the specified Frequency, and the provisions o f SI? 3.0.3 would apply.
EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify leakage rates are w i t h i n l i m i t s . 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-4 specifies t h a t the requirements o f t h i s Surveillance do not have t o be met u n t i l the u n i t i s in MODE 1. The interval measurement f o r the Frequency o f t h i s Surveillance continues a t a l l times, as described i n Example 1.4-1. However, the Note constitutes an "otherwise stated" exception t o the A p p l i c a b i l i t y o f this Surveillance.
R Therefore. i f the Surveillance were not erformed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (plus the extension allowed by S 3.0.2) i n t e r v a l ,
but the u n i t was not i n MODE 1, there would be no failure o f the SR nor f a i l u r e t o meet the LCO. Therefore, no v i o l a t i o n o f SR 3.0.4 occurs when changing MODES, even with the d
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Fre uency exceeded, provided t h e MODE change was not made i n t o DE 1. Prior t o entering MOD 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would re u i r e satisfying the SR, except as provided by SR 3 . 0 . 3 1
an LCO 3.0.4.
1.0-28 Amendment No. 131
Control Rod OPERABILITY
' 1 1 2 3 . 1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS
- - - - - - - - - - - - - - - - - - - - _ _ _ c _ _ _ _ _ _ _ _ _ _ _ _ _ NOTE-------------------------------------
Separate Condition entry i s allowed for each control rod.
CONDITION REQUIRE0 ACTION COMPLETION TIME A. One withdrawn control - - - - - - - - - - - - NOTE-------------
rod stuck. A stuck rod may be bypassed in the Rod Action Control System (RACS) i n accordance with SR 3.3.2.1.9 i f required to allow continued operation.
A. 1 Verify stuck control Inpnedi ately rod separation c r i t e r i a are met.
A.2 Disarm the associated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> control rod drive (CRD) .
AND (continued)
PERRY - UNIT 1 3.1-7 Amendment No. 120
Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 3.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from for discovery o f each withdrawn Cond-ition A OPERABLE control rod. concurrent w i t h THERM1 POWER greater than or equal t o the 1ow power setpoint (LPSP) o f the Rod Pattern Control AND System (RPCS).
A.4 Perform SR 3.1.1.1. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Two or more withdrawn B.l Be i n MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> control rods stuck.
C. One or more control c.1 - - _ - - - - -NOTE---------
rods inoperable f o r Inoperable control reasons other than rods may be bypassed Condition A or B. i n RACS i n accordance with SR 3.3.2.1.9. i f required. t o a1 low insertion o f inoperabl e control rod and continued operation, Fully insert 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> inoperable control rod.
C.2 Disarm the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CRD .
(continued)
PERRY - UNIT 1 3.1-8 Amendment No. 1 20
Control Rod OPERABILITY 3.1.3 D. 1 Restore cornpli&nc-d t h 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> BPMS .
OR D.2 Restore control rod t o 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Two or more inoperable OPERABLE status.
control rods not i n compl iance with banked pos i t i on w i t hdraw1%
sequence (BPWSJ and not separated by twu or more OPERABtE control rods.
E. Required Action and E.1 Be i n MODE 3.
a ssoci a t ed Compl et iun Time o f Condition A.
C, or D not met.
Nine or more cantm3 rods i noperabl e,.
PERRY - UNIT 1 3.1-9 Amendment No. 112
Control Koa UYLKH~Z~LIII 3.1.3 SURYEICLANCE REQUIREM,ENTS SURVE I lLAElCE FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Insert each w i thdrawn control rod 31 days a t least one no c SR 3.1,3@
d Verify each control rad scram time frum f u l l y wjthdrann t o notch positton 13 i s L 7 seconds.
In accordance w#t h S R 3.1.4*1, SR 3.1-4,2, SR J,Z,4.3, and SR 3.1.4.4 (continued)
PERRY - UNIT 1 3.1-10 Amendment No. 69
PERRY - 3.1-11 Amendment No, 69 Table 3.1.4-1 Control Rod Scram Times (a) Maximum scram time from fully withdrawn position, based on de-energization o f scram p i l o t valve solenoids as time zero-(b) Scram times as a functlon of reactor steam dome pressure when < 950 PSig are within established l i m i t s .
(c) For intermediate reactor steam dome pressures, the scram time criteria are deterrained by 1 inear interpol ation.
PERRY - UNIT 1 3.1-14 Amendment No. 69 Page 1 of 7 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS BASES (PROVIDED FOR INFORMATION)
Control Rod OPERABILITY B 3.1.3 BASES LCO (cont inued) satisf contro control r the intended reactivity control r e uirements, s t r i c t 8
over the number and distribution o inoperable rods i s required t o satisfy the assumptions o f the DBA and transient analyses.
APPCICABI L IN I n MODES 1 and 2. the control rods are assumed t o function durin a DBA or transient and are therefore required t o be O P E d L E i n these MODES. In MODES 3 and 4, control rods are not able t o be withdrawn since the reactor mode switch i s in Shutdown and a control rod block i s ap lied. This provides E
adequate requirements f o r control rod PERABILITY during these conditions. Control rod r e uirements i n PKIDE 5 are 1
located i n LCO 3.9.5."Control Ro OPERABl[LITY-Refueling.
ACTIONS The ACTIONS table i s modified by a Note indicating that a separate Condition entry i s allowed f o r each control rod.
This i s acceptable, since the Required Actions for each z
Condition provide appropriate compensator actions for each inoperable control rod. Complying with t e Required Actions may a1low f o r continued operation, and subsequent inoperable control rods are governed by subsequent Condition entry and application o f associated Required Actions.
A . 1 , A.2. A.3, and A.4 A control rod i s considered stuck i f i t w i l l not insert (using a71 available insertion methods) by either CRD drive water o r scram pressure. With a f u l l y inserted control rod stuck. no actions are required as long as the control-rod remains f u l l y inserted. The Required Actions are modified b a Note that allows a stuck control rod t o be bypassed i n K
t e Rod Action Control System (RACS) t o allow cont-inued o e r a t i on. SR 3 3.2.1.9-provides addi t ional requi rements den control rods are bypassed i n RACS t o ensure compliance with the CRDA analysis. With one withdrawn control rod stuck. the local scram reactivity rate assumptions may not be met i f the stuck control rod separation c r i t e r i a are not met. Therefore. verification that the separation c r i t e r i a (continued)
Control Rod OPERABILITY 8 3.1.3 BASES ACTIONS A . l . A.2, A.3. and A.4 (continued) are met must be performed immediately. The stuck control rod separation criteria are that the stuck control rod ma not occupy a location adjacent t o a 'slow" control rod. {he description o f "slow" control rods i s provided i n LCO 3.1.4 "Control Rod Scram Times". I n addition, the control rod must be disarmed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The allowed Completion Time o f 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i s acceptable, considerin the reactor can 3
still be shut dorm. assuming no additiona control rods f a i l t o insert. and provides a reasonable amount of time t o 4
perform the Re uired Action i n an orderly manner. Isolating the control r from scram prevents damage t o the CRDM. The control rod can be (cont inued1 PERRY - UNIT 1 B 3.1-15a Revision No. 4
Control Rod OPERABILITY B 3.1.3 BASES ACTIONS A . 1 . A.2. A.3. and A.4 (continued) isolated from scram by isolating the hydraulic control u n i t from scram and normal drive and withdraw pressure. yet still maintain cooling water t o the CRD. A control rod can be hydraulically disarmed by closing the drive water and exhaust water isolation valves. Electrically. the control rod can be disarmed by dlsconnecting power from a l l four directional control valve solenoids.
Monitoring o f the insertion capability for each withdrawn_
control r d must a l s o H r f o r m e d within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A 7 3
SR 3.1.3.2 Eerforflperiodic tests o f the control rod( insert% caDa i l i t y o f withdrawn control rods.
Testing each withdrawn control rod ensures that a. generic problem does not exist. The allowed Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provides a reasonable t i m e t o test the control rods, considering the potential fur a need t o reduce power t o perform the tests. Required Action A.2 has a modifjed t i m e zero Completion Time. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time for t h i s Required Action starts when the withdrawn control rod i s discovered t o be stuck and THERMAL POWER i s greater than P
the actual low Ower set i n t (LPSP) o f the rod pattern
!?
control fer (RPC , since he notch insertions may not be co a t i b l e with the r e uirements o f rod pattern control (LE 2 3.1.6) and the RP (LCO 3.3.2.1, Control Rod Block Instrumentation 1.
To allow continued operation with a withdrawn control rod stuck. an evaluation of adequate SDM i s also required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Should a DBA or transient require a shutdown. t o preserve the single failure c r i t e r i o n an additional control rod would have t o be assumed t o have failed t o insert when s
required. Therefore. the ori inal SM demonstration may not be v a l i d . The SOM must there ore be evaluated (by measurement or analysis) with the stuck control rod a t i t s stuck position and the highest worth OPERABLE control rod assumed t o be fully withdrawn.
The allowed Completion Time o f 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> t o v e r i f y SDM i s adequate, considering that with a single control rod stuck In a withdrawn position, the remaining OPERABLE control rods are capable o f providing the re uired scram and shutdown reactivitl d
. Failure t o reach DE 4 i s on1 likely ifan 51 additiona control rod adjacent t o the stuc control rod (continuedl PERRY - UNIT 1 B 3.1-16 Revision No. 4
Control Rod OPERABILITY B 3.1.3 BASES ACTIONS A . 1 . A.2. A.3. and A.4 (continued) 9 also f a i l s t o insert durin a required scram. Even with the postulated additional sing e failure o f an adjacent control rod t o insert, sufficient reactivity control remains t o reach and maintain MODE 3 conditions (Ref. 7).
With two or more withdrawn control rods stuck, the plant should be brought t o WDE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Isolating the control rod from scram prevents damage t o the CRDM. The occurrence o f more than one control rod stuck a t a withdrawn s i t i o n increases the probabi 1i t y that the reactor cannot shut down i f required. Insertion o f a l l insertable control rods eliminates the possibilit .of an additional f a i l u r e o f a control rod t o insert. Tie allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i s reasonable, based on operating experience, t o reach MODE 3 from f u l l power conditions i n an orderly manner and without challenging plant systems.
C.l and C.2 With one or more control rods inoperable for reasons other than being stuck i n the withdrawn position, operation may continue, provided the control rods are f u l l y inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarmed (electrically or hydraulically) a control rod ensures the w i t h i n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Inserting shutdown and scram capabi i t i e s are not adversely affected.
The control rod i s disarmed t o prevent inadvertent withdrawal during subsequent o erations. The control rods E
can be hydraulically disarmed y closing the drive water and exhaust water isolation valves. Electrically, the control 7 R rods can be disarmed b disconnecting ower from a l l four directional control va ve solenoids. i t h a control rod not coupled t o i t s associated drive mechanism, i n s e r t the control rod drive mechanism t o accomplish recoup1ing.
i Verify recouplin by withdrawing the control rod and observing any i n icated response o f the nuclear instrumentation and demonstrating that the control rod drive w i l l not go t o the overtravel position. Required Action C.1 z
i s modified b a Note that allows control rods t o be 1
bypassed i n t e RACS i f r e uired t o allow insertion of the ino erable control rods an continued operation.
SR g.3.2.1.9 provides additional requirements when the control rods are bypassed t o ensure compliance with the CRDA analysis.
(continuedl
Control Rod OPERABILITY B 3.1.3 SASES (continued)
SURVEILLANCE SR 3.1.3.1 REQUIREMENTS The position o f each control rod must be determined, t o ensure adequate information on control rod position i s available t o the operator f o r determining control rod OPERABILITY andecontrol 1ing rod patterns. Control rod osition may be determined by the use o f at least one gPERA6i-E position indicator, by moving control rods t o a position with an OPERABLE indicator, or by the use o f other appropriate methods. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency o f t h i s SR i s based on operating experience related t o expected changes i n control rod position and the availability o f control rod position indications i n the control r m .
SR 3.1.3.21ki;6&$R fll.Y&J Control rod insertion capabilit i s demonstrated b T T inserting each p a r t i a l l y or f u l y withdrawn contro rod a t least one notch and observing that the control rod moves.
The control rod may then be returned t o i t s original position. Observation o f changes i n indicated control rod position provides evidence that the control rod osition indication i s OPERABLE. This ensures the contro rod i s not stuck and i s free t o insert on a scram signal. When plant P
rocedures permit, these SRs may also be met by rod scram.
h e s e Surveillances are not required when THEWL POWER i s less than or equal t o the actual LPSP o f the RPC since the notch insertions may not be cmatible with the reauirements e w @ i e d e relawd t o t h d c h a m e d i n CRD d r f o r d c e an&he
'awn control rods are t i? Frequenck based on the Dotential - m e rrxxhctim ntwco~dd;imfJ Furthermore. the atins exDerience related to'changes in CRD performance'. A t any t h e , ifa e
control rod i s imnovable. a determination o f t h a t control rod's t r i p a b i l i t y (OPERABILITY) must be made and appropria e action taken.
SR 3 .1 .3 .w Verifying the scram time for each control rod t o notch position 13 i s s 7 seconds provides reasonable assurance that the control rod will insert when required during a DBA or transient, thereby completing i t s shutdown function.
+!j (continued)
~ZnformatM?
PERRY - UNIT 1 B 3.1-19 Revision No. 3
BASES SURVEILLANCE (continued)
REQUIREMENTS i n conjunction with the control rod SR 3.1.4.1. SR 3.1.4.2, SR 3.1.4.3, SYSTEM FUNCTIONAL TEST i n LCO 3.3.1.1. "Reactor Protection System (Rps)
InstrumentatJon." and the functional testing o f SDV vent and drain valves i n LCO 3.1.8. "Scram Discharge Volume W I V )
Vent and Drain Valves." overlap this Surveillance t o provide complete testing o f the assunred safety function. The associated Frequencies are acceptable, considering the more frequent testing erformed t o demonstrate other aspects of control rod OPERA[1ILIiv and operati ty e y i e n c e . which shows scram times do not slgnlficant y c ange over an operating cycle.
Coupling verification i s performed t o ensure the control rod is connected to the CRDM and will perform i t s internled function when necessary. The Survei 11 ance requi res verifying that a control rod does not go t o the withdrawn overtravel positi i t i s f u l l y withdrawn. The ture rovides a positlve check on the overtravel posf ti P
coupling i n t pity, since on y an uncoupled CRD can reach 7
the overtrave position. The verification i s required t o be performed anytime a control rod i s withdrawn t o the "full out" position (notch,posltion 48) or prior t o declaring the control rod OPERABtEafter work on the control rod or CRD System that could affect coupling. This includes control rods inserted one notch and then returned t o the "full out" position durtng the performance o f SR 3.1.3.2. Until the control rod reaches the " f u l l out" position where coupling can be verified, the nuclear Instrumentation i s observed for 7 7 any indicated response duri withdrawal. This Frequency 1s acceptable, consideri the ow probability that a control rod will become uncoup ed when it is not k i n g moved and operati ng experi m e re1ated t o uncoupl ing events .
PERRY - UNIT 1 8 3.1-20 Revision No. 1 Page 1 of 7 PROPOSED TECHNICAL SPECIFICATION CHANGES (RETYPED)
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)
"Thereafter" indicates f u t u r e performances must be established per SR 3.0.2, but only a f t e r a specified condition i s f i r s t met ( i . e . , t h e "once" performance i n t h i s example). I f reactor power decreases t o < 25% RTP, the measurement o f both i n t e r v a l s s t o s. New i n t e r v a l s s t a r t upon reactor power reaching 25% RP. 4!
EXAMPLE 1.4-3 SURVEILLANCE REOUIREMENTS SURV E I LLANCE FREQUENCY Perform channel adjustment. 7 days The i n t e r v a l continues whether o r not t h e u n i t operation i s 25% RTP between performances.
+
As t h e Note modifies the required erformance o f the Frequency." Should t h e 7 day i n t e r v a l be exceeded while Surveillance, operation i s c i25% t i sRTP, construed t o be t h i s Note allows o hours p a r t 12 t h e "specified after
!ower reaches 2 25% RTP t o perform t h e Surveillance. The u r v e i l l a n c e i s s t i l l considered t o be w i t h i n t h e "specified Fre uency . Therefore, i f t h e Survei 17 ance were not
'I 9ormed iw SR 3.0.2) per n ti tehr ivna lt ,h ebut 7 day (plus twas operation < 25% RTP,allowed h e extension not c o n s t i t u t e a f a i l u r e o f t h e SR o r f a i l u r e t o meet the i t would by LCO. Also, no v i o l a t i o n o f SR 3.0.4 occurs when changing MODES, even w i t h the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus t h e extension allowed by SR 3.0.2) w i t h power 225% RTP.
(continued)
PERRY - UNIT 1
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)
Once t h e u n i t reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. I f the Surveillance were not performed w i t h i n t h i s 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i n t e r v a l (plus the extension allowed by SR 3.0.2). there would then be a f a i l u r e t o perform a Survei 7 1ance w i t h i n the speci f ied Frequency, and t h e provisions o f SR 3.0.3 would apply.
EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Only required t o be met i n MODE 1.
V e r i f y leakage rates are w i t h i n l i m i t s . 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-4 specifies t h a t t h e requirements o f t h i s Surveillance do not have t o be met u n t i l t h e u n i t i s i n MODE 1. The i n t e r v a l measurement f o r t h e Frequency o f t h i s Surveillance continues a t a l l times, as described i n Example 1.4-1. However, the Note constitutes an "otherwise stated" exception t o the A p p l i c a b i l i t y o f t h i s Surveillance.
g Therefore, i f the Surveillance were not erformed w i t h i n t h e 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (plus the extension allowed by S 3.0.2) i n t e r v a l ,
but the u n i t was not i n MODE 1. there would be no f a i l u r e of t h e SR nor f a i l u r e t o meet the LCO. Therefore, no v i o l a t i o n o f SR 3.0.4 occurs when changing MODES, even w i t h t h e 8
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Fre uency exceeded, provided t h e MODE change was not made i n t o M DE 1. P r i o r t o entering MODE 1 (assuming again t h a t the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would r e u i r e s a t i s f y i n g t h e SR-, except as provided by SR 3.0.3 an LCO 3.0.4.
PERRY - UNIT 1 1.0-28 Amendment No.
ACTIONS --
CONDITION REQUIRED ACTION COMPLETION TIME
~~~
A. (continued) A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from f o r each withdrawn discovery o f t OPERABLE control rod. Condition A concurrent w i t h THERMAL POWER greater than or equal t o the low power setpoint (LPSP) o f the Rod
-AND Pattern Control System (RPCS).
A.4 Perform SR 3.1.1.1.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ,
B. Two o r more withdrawn B.1 Be i n MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ,
control rods stuck.
C. One o r more control c.1 - - - - - - - - NOTE---------
rods inoperable f o r Inoperable control reasons other than rods may be bypassed Condition A o r B. i n RACS i n accordance w i t h SR 3.3.2.1.9, i f required, t o allow insertion o f inoperable control rod and continued opera t ion.
Fully insert 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> inoperabl e control rod.
c.2 Disarm t h e associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CRD .
(cont inued 1 PERRY - UNIT 1 3.1-8 Amendment No. I
Control Rod OPERABILITY 3.1.3 Not required t o be performed u n t i l 31 days a f t e r the control rod i s withdrawn and THERMAL POWER i s greater than t h e LPSP o f t h e RPCS.
I n s e r t each withdrawn control rod a t l e a s t 31 days one notch.
SR 3.1.3.3 V e r i f y each control rod scram time from I n accordance f u l l y withdrawn t o notch p o s i t i o n 13 i s with I 7 seconds. SR 3.1.4.1.
SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (cont inued1 PERRY - UNIT 1 3.1-10 Amendment No.
Control Rod OPEM8ILITY 1 1 7 3.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.3.4 V e r i f y each control rod does not go t o the Each time t h e withdrawn overtravel position. control rod i s withdrawn t o
" f u l l out" position Prior t o declaring control rod OPERABLE after work on control rod o r CRD System t h a t could a f f e c t coup1 ing PERRY - UNIT 1 3.1-11 Amendment No.
Control Rod Scram Times 3.1.4 Table 3.1.4-1 Control Rod Scram Times
- - - - - - - - - - - - - - - - - - _ _ - - - - - - - - - - - - - - - - -N O T E S - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1. OPERABLE control rods w i t h scram times not w i t h i n t h e l i m i t s o f t h i s Table a r e considered "slow."
Enter a p l i c a b l e Conditions and Required Actions o f LCO 3.1.3, "Control 2.
i Rod OPE ABILITY," f o r control rods w i t h scram times > 7 seconds t o notch p o s i t i o n 13, These control rods are inoperable, i n accordance w i t h SR 3.1.3.3, and are not considered "slow."
- - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ c _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
SCRAM TIMES(a) ( b )
(seconds 1 REACTOR REACTOR STEAM DOME PRESSURE(c) STEAM DOME PRESSURE ( C )
NOTCH POSITION 950 p s i g 1050 p s i g
( a > Maximum scram time from f u l l y withdrawn p o s i t i o n , based on de-energization o f scram p i l o t valve solenoids as time zero.
(b) Scram times as a function o f reactor steam dome pressure when < 950 p s i g are w i t h i n established l i m i t s .
(c) For intermediate reactor steam dome pressures, the scram time c r i t e r i a are determined by l i n e a r i n t e r p o l a t i o n .