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Category:Letter type:L
MONTHYEARL-24-226, License Renewal Application for the Perry Nuclear Power Plant Revision O - Response to Requests for Confirmatory Information (Rcls) - Set 12024-10-31031 October 2024 License Renewal Application for the Perry Nuclear Power Plant Revision O - Response to Requests for Confirmatory Information (Rcls) - Set 1 L-24-179, License Renewal Application for the Perry Nuclear Power Plant Revision 0 - Supplement 52024-10-21021 October 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0 - Supplement 5 L-24-208, License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2)2024-10-0202 October 2024 License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2) L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 12024-09-16016 September 2024 License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1 L-24-201, Spent Fuel Storage Cask Registration2024-09-0909 September 2024 Spent Fuel Storage Cask Registration L-24-200, License Renewal Application for Revision to Supplement 4 for Editorial Corrections2024-09-0505 September 2024 License Renewal Application for Revision to Supplement 4 for Editorial Corrections L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-174, Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information2024-08-15015 August 2024 Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information 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 L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report 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 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-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments 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-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions 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 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 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 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 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 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request 2024-09-09
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SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 FENOC 76 South Main Street Akron. Ohio 44308 PeterP. Sena II/
Presidentand Chief Nuclear Officer February 27, 2013 L-1 3-035 10 CFR 2.202 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 FirstEnergy Nuclear Operating Company's (FENOC's) Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
References:
- 1. Nuclear Regulatory Commission (NRC) Order Number EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, Revision 0, dated August 29, 2012
- 3. Nuclear Energy Institute (NEI) 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 0, dated August 2012
- 4. FirstEnergy Nuclear Operating Company's (FENOC's) Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 26, 2012 On Ma"rch 12, 2012, the Nuclear Regulatory Commission (NRC or Commission) issued an order (Reference 1) to FENOC. Reference 1 was immediately effective and directs FENOC to develop, implement, and maintain guidance and strategies to maintain or Security-Related Information -Withhold Under 10 CFR 2.390 Enclosures Contain Security-Related Information; Upon Separation from Enclosures, this Cover Letter is Decontrolled
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Beaver Valley Power Station, Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station Perry Nuclear Power Plant L-13-035 Page 2 restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.
Reference 1 requires submission of an overall integrated plan by February 28, 2013.
The NRC Interim Staff Guidance (ISG) (Reference 2) endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 3 provides direction regarding the content of this overall integrated plan.
Reference 4 provided the FENOC initial status report regarding mitigation strategies, as required by Reference 1.
The purpose of this letter is to provide the overall integrated plan pursuant to Section IV, Condition C.1 of Reference 1, for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS), Davis-Besse Nuclear Power Station (DBNPS), and Perry Nuclear Power Plant (PNPP) (Enclosures A, B, and C, respectively). This letter confirms FENOC has received Reference 2 and has an overall integrated plan developed in accordance with the guidance for defining and deploying strategies that will enhance the ability to cope with conditions resulting from beyond-design-basis external events.
The information in the enclosures provides FENOC overall integrated plans for mitigation strategies pursuant to Reference 3. The enclosed integrated plans are based on conceptual design information. Final design details and associated procedure guidance, as well as any revisions to the information contained in the enclosures, will be provided in the six-month integrated plan updates required by Reference 1.
FENOC requests that the enclosures to this letter, which contain security-related information, be withheld from public disclosure in accordance with 10 CFR 2.390.
This letter contains no new regulatory commitments. If you have any questions regarding these plans, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at 330-315-6810.
Security-Related Information -Withhold Under 10 CFR 2.390 Enclosures Contain Security-Related Information; Upon Separation from Enclosures, this Cover Letter is Decontrolled
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Beaver Valley Power Station, Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station Perry Nuclear Power Plant L-13-035 Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on February A-7 , 2013.
Respectfully submitted, Peter P. Sena, III
Enclosures:
A. Overall Integrated Plan for Beaver Valley Power Station, Unit Nos. 1 and 2 B. Overall Integrated Plan for Davis-Besse Nuclear Power Station C. Overall Integrated Plan for Perry Nuclear Power Station cc: Director, Office of Nuclear Reactor Regulation (NRR)
NRC Region I Administrator NRC Region III Administrator NRC Resident Inspector (BVPS)
NRC Resident Inspector (DBNPS)
NRC Resident Inspector (PNPP)
NRC Project Manager (BVPS)
NRC Project Manager (DBNPS)
NRC Project Manager (PNPP)
Director BRP/DEP (without Enclosures)
Site BRP/DEP Representative (without Enclosures)
Utility Radiological Safety Board (without Enclosures)
Security-Related Information -Withhold Under 10 CFR 2.390 Enclosures Contain Security-Related Information; Upon Separation from Enclosures, this Cover Letter is Decontrolled