Similar Documents at Perry |
---|
Category:Letter
MONTHYEARIR 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-171, Spent Fuel Storage Cask Registration2024-07-30030 July 2024 Spent Fuel Storage Cask Registration ML24150A2022024-07-25025 July 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-License Renewal Scoping Summary Rpt L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 ML24157A3782024-06-0606 June 2024 – Revised Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 ML24141A1632024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams ML24117A1222024-04-26026 April 2024 Confirmation of Initial License Examination IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency L-24-083, Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification2024-04-15015 April 2024 Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification ML24088A1922024-03-28028 March 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 L-24-057, Submittal of the Decommissioning Funding Status Report2024-03-28028 March 2024 Submittal of the Decommissioning Funding Status Report L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-076, Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-22022 March 2024 Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24064A2212024-03-14014 March 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1 - Summary of the Jan-Feb 2024 Environmental Audit Related to the Review of the License Renewal Application Environmental Report ML24059A3922024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0080 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000440/20230062024-02-28028 February 2024 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2023006) L-24-053, Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-02-27027 February 2024 Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 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-23-207, 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 IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application 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 IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) 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 ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement 2024-08-08
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24057A0782024-03-0101 March 2024 Amendments to Indemnity Agreements - Enclosure 2 ML24057A0772024-03-0101 March 2024 Conforming License Amendments - Enclosure 1 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4412023-09-29029 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Federal Register Notice, Direct and Indirect License Transfer Issuance Order ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML20030A4402020-02-27027 February 2020 Issuance of Amendment Nos. 304, 194, 299, and 187; Order Approving Transfers of Facility Operating Licenses and Independent Spent Fuel Storage Installation General Licenses and Conforming Amendments ML19326A7592019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Non-Proprietary, Letter & Encl 2-5, Order Approving Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18214A6672018-08-22022 August 2018 FENOC Fleet - Perry Nuclear Power Plant, Unit No. 1 - Correction to the Issuance of Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules (CAC No. MG0136; EPID L-2017-LLA-0259) ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML17033A0142017-02-16016 February 2017 Issuance of Amendment Concerning Revision to Technical Specifications to Permit Installation of Upper Containment Pool Gate During Modes 1, 2, and 3 (CAC No. MF7476) (L-16-083) ML16158A3312016-09-14014 September 2016 Issuance of Amendment Concerning Revision to the Perry Nuclear Power Plant Emergency Plan ML16130A5362016-05-31031 May 2016 Issuance of Conforming Amendment Related to the Direct License Transfer of the Facility Operating License NPF-58 ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) ML15075A1392015-03-30030 March 2015 Issuance of Amendment Concerning Full Implementation of Alternative Source Term (TAC No. MF3197) (L-13-306) L-14-325, Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325)2015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML15075A0912015-03-27027 March 2015 Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) ML14205A6192014-08-29029 August 2014 Amendments to Indemnity Agreements (TAC MF0701, MF0702, MF0703, and MF0704) ML13136A1432013-05-16016 May 2013 Nucelar Power Plant, Unit 1 - Re-Issuance of Amendment Regarding Adoption of TSTF-275 and TSTF-300 ML13051B1442013-05-0606 May 2013 Issuance of Amendment Regarding Adoption of TSTF-275, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-Up, and TSTF-300 ML13017A4312013-04-18018 April 2013 Issuance of Amendment Revise Technical Specification 3.10.1, Inservice Leak, and Hydrostatic Testing Operation ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC ML1128602452011-10-17017 October 2011 Issuance of Amendment No. 160, Revise Technical Specification 3.8.1, AC Sources - Operating, Regarding Use of a Delayed Circuit as a Required Offsite Circuit (Emergency Circumstances) 2024-03-01
[Table view] Category:Safety Evaluation
MONTHYEARML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) ML21063A1572021-03-0404 March 2021 Safety Evaluation for Alternative Request SR-2, Revision 0 Related to one-time Extension Snubbers Testing to ASME OM Code for the Fourth 10-year Inservice Interval at Perry Nuclear Power Plant Unit 1, Docket Nos. 50-440 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19072A0122019-03-15015 March 2019 Correction to License Amendment No. 184 Related to Adoption of Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML17193A3822017-07-18018 July 2017 Correction to Safety Evaluation for License Amendment No. 177 ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) 2023-09-28
[Table view] |
Text
August 14, 2019 Mr. Frank R. Payne Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, SB306 Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 186 CONCERNING CHANGES TO EMERGENCY RESPONSE ORGANIZATION (EPID L-2018-LLA-0484)
Dear Mr. Payne:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 186 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1 (PNPP). The amendment consists of changes to PNPP Emergency Plan in response to your application dated November 28, 2018.
The amendment revises the PNPP Emergency Plan to (1) transfer rescue and first aid duties from two on-shift security force members to on-shift fire brigade personnel and eliminate the two security force positions; (2) reduce the number of offsite radiation monitoring teams from three to two and transfer augmentation staff responsibility for onsite (out-of-plant) surveys from radiation monitoring teams to radiation protection technicians; (3) add definitions for offsite surveys and onsite (out-of-plant) surveys; and (4) make other administrative changes needed to implement the noted changes.
F. Payne A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 186 to NPF-58
- 2. Safety Evaluation cc: Listserv
FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION, LLC DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 186 License No. NPF-58
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by FirstEnergy Nuclear Operating Company, et al. (the licensee, FENOC), dated November 28, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, by Amendment No. 186, Facility Operating License No. NPF-58 is hereby amended to authorize revision to the Perry Nuclear Power Plant Emergency Plan as set forth in the licensees application dated November 28, 2018, and evaluated in the NRC staffs safety evaluation enclosed with this amendment.
- 3. This license amendment is effective as of its date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA Eric J. Benner for/
Ho K. Nieh, Director Office of Nuclear Reactor Regulation Date of Issuance: August 14, 2019
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 186 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION, LLC PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By application dated November 28, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18332A500), FirstEnergy Nuclear Operating Company (the licensee or FENOC) requested changes to the Perry Nuclear Power Plant (PNPP) Emergency Plan pursuant to Section 50.54(q) of Title 10 of the Code of Federal Regulations (10 CFR). The proposed changes would revise the PNPP Emergency Plan to (1) transfer rescue and first aid duties from two on-shift security force members to on-shift fire brigade personnel and eliminate the two security force positions; (2) reduce the number of offsite radiation monitoring teams (RMTs) from three to two and transfer augmentation staff responsibility for onsite (out-of-plant) surveys from RMTs to radiation protection (RP) technicians; (3) add definitions for offsite surveys and onsite (out-of-plant) surveys; and (4) make other administrative changes needed to implement the noted changes.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance on which the U.S. Nuclear Regulatory Commission (NRC or Commission) staff based its review are provided below.
2.1 Regulatory Requirements The planning standards in 10 CFR 50.47(b) establish the requirements that the onsite and offsite emergency response plans must meet for the NRC staff to make a finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Specifically, on-shift and augmented emergency response organization (ERO) staffing is addressed under 10 CFR 50.47(b)(2), which states:
[10 CFR 50.47(b)(2)] On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely Enclosure 2
augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.
The requirement for emergency medical support is in 10 CFR 50.47(b)(12), which states:
Arrangements are made for medical services for contaminated injured individuals.
In addition, Appendix E to 10 CFR Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities,Section IV, Part A, Organization, states, in part, that The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensees emergency organization. . .
2.2 Guidance Regulatory Guide (RG) 1.101, Revision 2, Emergency Planning and Preparedness for Nuclear Power Reactors, October 1981 (ADAMS Accession No. ML090440294), provides guidance on methods acceptable to the NRC staff for implementing specific parts of the NRCs regulations -
in this case, 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. RG 1.101 endorses Revision 1 to NUREG-0654/FEMA-REP-1 (NUREG-0654), Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November 1980 (ADAMS Accession No. ML040420012), which provides specific acceptance criteria for complying with the standards set forth in 10 CFR 50.47(b). These criteria provide a basis for NRC licensees, and State and local governments to develop acceptable radiological emergency plans and to improve emergency preparedness.
NUREG-0654,Section II, Evaluation Criteria II.B.1 and II.B.5 address the planning standard in 10 CFR 50.47(b)(2).
Evaluation Criterion II.B.1 states:
Each licensee shall specify the onsite emergency organization of plant staff personnel for all shifts and its relation to the responsibilities and duties of the normal shift complement.
Evaluation Criterion II.B.5 states, in part:
Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, Minimum Staffing Requirements for Nuclear Power Plant Emergencies. The minimum on-shift staffing levels shall be as indicated in Table B-1. The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1. . . .
NUREG-0654,Section II, Evaluation Criterion II.L.2 addresses the planning standard in 10 CFR 50.47(b)(12) and states:
Each licensee shall provide for onsite first aid capability.
Regulatory Issue Summary 2016-10, License Amendment Requests for Changes to Emergency Response Organization Staffing and Augmentation, dated August 5, 2016 (ADAMS Accession No. ML16124A002), provides examples of the scope and detail of information that should be provided in license amendment requests related to ERO staffing and augmentation to facilitate NRC review.
By letter dated June 12, 2018 (ADAMS Accession No. ML18022A352), the NRC staff provided alternative guidance to Evaluation Criterion II.B.5 in NUREG-0654, Revision 1, for minimum ERO on-shift and augmentation staffing. The letter states, in part:
The NRC has revised Section II.B, Table B-1 of NUREG-0654, based in part on comments received from the public on the draft Revision 2 of NUREG-0654, located at www.regulations.gov under Docket ID FEMA-2012-0026. The revised ERO staffing guidance has been finalized, and the NRC will include it when the entire NUREG-0654, Revision 2, is ready for issuance. Until then, the NRC staff is making available on an interim basis the ERO on-shift and augmentation staffing plan (attached). Regardless of whether a licensee chooses to use the guidance contained in Revision 1 of NUREG-0654, the attached, or an alternative approach, licensees are still required to adhere to 10 CFR 50.54(q) when revising their ERO staffing plans.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of the proposed changes to the PNPP Emergency Plan, as described in the application dated November 28, 2018.
3.1 Proposed Changes In its application dated November 28, 2018, FENOC provided a justification for the following proposed PNPP Emergency Plan changes:
Reduce the number of offsite RMTs by one from three to two, and transfer the responsibilities of onsite (out-of-plant) surveys to RP technicians; and Transfer the responsibilities for on-shift rescue and first aid from on-shift security personnel to the fire brigade.
Additionally, the application identified other changes, which are administrative in nature to support the implementation of the above changes. These changes include revising the definitions for offsite survey and onsite (out-of-plant) surveys.
The NRC staffs technical evaluation of the proposed changes to the PNPP Emergency Plan is described below.
3.1.1 Reduce the Number of Radiation Monitoring Teams In the current PNPP Emergency Plan, offsite and onsite (out-of-plant) surveys consist of two RMTs mobilized at the declaration of an Alert or higher classification level with a response time of 30 minutes. This initial RMT response was augmented by the mobilization of a third RMT at the declaration of a Site Area Emergency or higher classification level with a response time of 60 minutes. RMTs were normally comprised of one leader and one helper. The RMT Leader actions include reading dose rate instrumentation and obtaining air samples, if required. The RMT Helper actions include driving to and from field positions and communicating results to dose assessment personnel in the PNPP Technical Support Center and Emergency Operations Facility to support event classification and protective action recommendation development. The first two RMTs were responsible for monitoring for possible releases, and the third RMT was responsible for obtaining air samples and performing field measurements.
In the proposed PNPP Emergency Plan, mobilization of two offsite RMTs would continue to occur at the declaration of an Alert or higher classification level with a 30-minute response time, but the mobilization of a third RMT at the declaration of a Site Area Emergency or higher emergency classification is being eliminated. In lieu of a third RMT, FENOC proposes to mobilize one RP technician within 30 minutes of the declaration of an Alert or higher classification level and a second RP technician within 60 minutes to perform onsite (out-of-plant) surveys. In support of this change, FENOC proposed to also revise Table 5-1b, Perry Plant Emergency Response Organization Shift Staff Augmentation Functions and Staffing, to separate offsite and onsite (out-of-plant) survey activities.
FENOC stated that the RMTs will continue to be dispatched from a location just outside the Protected Area fence and use dose assessment instrumentation to perform environmental radiation assessments and plume tracking. The RMTs will also continue to be trained to conduct radiation surveys for plume tracking, perform air sampling, and provide radiological input for dose projections. As such, the proposed reduction in the number of RMTs does not adversely impact the ability to perform timely offsite surveys in the event of a potential or actual radiological release from the PNPP.
FENOC proposed to combine the onsite (out-of-plant) surveys major task with the in-plant surveys major task. FENOC further stated that shift and augmenting RP technicians performing these combined major tasks will meet or exceed the qualifications of the American National Standards Institute Standard N18.1-1971, Selection and Training of Nuclear Power Plant Personnel. To facilitate the use of an RP technician to perform onsite (out-of-plant) surveys, FENOC is proposing to redefine the boundary between the offsite and onsite (out-of-plant) survey areas as the Protected Area fence, rather than the site owner-controlled area fence, to reduce the survey area and remove the need for a vehicle and RMT Helper position. Based on the redefinition of the onsite (out-of-plant) survey area and in-plant and site radiological capabilities described by FENOC, the use of augmenting RP technicians does not adversely impact the ability to perform timely in-plant and onsite (out-of-plant) surveys in the event of a potential or actual radiological event at the PNPP.
Based on the assessment above, the NRC staff concludes that the proposed PNPP Emergency Plan continues to meet the planning standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50.
3.1.2 Transfer the Responsibilities for On-Shift Rescue and First Aid from On-Shift Security Personnel to the Fire Brigade The guidance in NUREG-0654, Table B-1, specifies the Rescue Operations and First-Aid Major Functional Area should be fulfilled by two personnel on-shift that may be assigned other functions. To address rescue operations and first aid, the current PNPP Emergency Plan identifies two on-shift security force members who receive first aid training and are not included in the PNPP Security Plan response requirements.
FENOC proposed that the rescue operations and first aid function be performed by on-shift fire brigade personnel, as described in Section 3.2.3, Rescue Operations and First Aid Function, of the application, in lieu of two dedicated on-shift security force members. These two dedicated on-shift security force positions would be eliminated in the revised Table 5-1b.
FENOC stated that the fire brigade as a collateral duty is acceptable because the fire brigade is trained under the current PNPP Emergency Plan to perform rescue operations, which includes first aid. FENOC stated that an on-shift RP technician would continue to provide the necessary health physics coverage for rescue and first aid response activities.
FENOC performed a functional and staffing analysis to ensure that the proposed change does not result in a reduction of event response capability. The analysis demonstrated that the collateral use on-shift personnel to perform on-shift rescue and first aid, in conjunction with their currently assigned fire brigade emergency plan implementation functions, would not prevent the timely performance of these functions as specified in the PNPP Emergency Plan.
The NRC staff evaluated the proposed changes and determined that transfer of the rescue and first aid functions from the two on-shift security force members to the on-shift fire brigade personnel is acceptable because the fire brigade is already trained to perform these duties.
Further, the elimination of the two on-shift security force positions, which existed for purpose of performing the rescue operations and first aid, is acceptable because the duties will now be performed by the on-shift fire brigade, making the need for these two positions unnecessary.
Therefore, the NRC staff concludes that the proposed PNPP Emergency Plan continues to meet the standards of 10 CFR 50.47(b)(12) and the requirements of Appendix E to 10 CFR Part 50.
3.1.3 Other Administrative Changes The NRC staff reviewed the other miscellaneous changes to the PNPP Emergency Plan made to support the implementation of the changes above and determined that they are administrative in nature. Specifically, FENOC proposed to revise the definitions for offsite survey and onsite (out-of-plant) surveys to support the mobilization of RP technicians in lieu of a third RMT.
These definition changes, as well as the other administrative changes, were evaluated as part of the proposed changes in Sections 3.1.1 and 3.1.2 of this safety evaluation, and the NRC staff concludes that these changes do not negatively impact the licensees ability to continue to meet the standards of 10 CFR 50.47(b)(12) and the requirements of Appendix E to 10 CFR Part 50.
3.2 Summary The NRC staff performed a technical and regulatory review of the proposed changes to the PNPP Emergency Plan against the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, informed by the guidance provided in NUREG-0654, Regulatory Issue Summary 2016-10, and the NRC staffs letter dated June 12, 2018. This review included letters of concurrence from the State of Ohio and the local counties
of Lake, Geauga and Ashtabula, indicating that they had been briefed and concur on the proposed changes as not having a negative impact on offsite radiological emergency response plans. Based on this review, the NRC staff finds that the proposed PNPP Emergency Plan, as changed, continues to meet the standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Therefore, the NRC staff concludes that the proposed PNPP Emergency Plan changes to certain ERO staffing provisions, as described in the application dated November 28, 2018, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Ohio State official was notified of the proposed issuance of the amendment on June 11, 2019. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Register on July 16, 2019 (84 FR 33993).
Accordingly, based upon the environmental assessment, the Commission has determined that the issuance of the amendment will not have a significant effect on the quality of the human environment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions 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.
Principal Contributors: J. Arce, NSIR M. Norris, NSIR Date of issuance: August 14, 2019
ML19163A023 *by email NSIR/DPR/RLB/BC* OGC (NLO OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA w/revisions)*
NAME KGreen SRohrer JAnderson STurk DATE 06/13/19 06/12/19 03/08/19 07/10/19 OFFICE NRR/DORL/LPL3/BC (A) NRR/DORL/DD NRR/OD NRR/DORL/LPL3/PM NAME LRegner GSuber HNieh (EBenner for) KGreen DATE 07/10/19 07/29/19 8/12/19 8/14/19