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MONTHYEAR0CAN091302, Assistance in Obtaining Information on Dams2013-09-30030 September 2013 Assistance in Obtaining Information on Dams Project stage: Request L-PI-14-024, Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task For2014-03-10010 March 2014 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Project stage: Request L-14-113, Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights.2014-03-11011 March 2014 Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights. Project stage: Request 0CAN031401, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 22014-03-12012 March 2014 Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 Project stage: Request 0CAN041402, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report2014-04-14014 April 2014 Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Project stage: Request ML14168A0182014-05-16016 May 2014 Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests Project stage: Other ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants Project stage: Meeting ML14153A0252014-06-20020 June 2014 Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants Project stage: Meeting ML14162A3712014-06-26026 June 2014 5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1 Project stage: Meeting ML14171A5292014-07-17017 July 2014 Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident Project stage: Approval ML14171A1662014-07-29029 July 2014 Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident Project stage: Approval ML15155A6312015-06-0808 June 2015 Nuclear Regulatory Commission Plan for the Audit of Duke Energy Carolinas, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Catawba Nuclear Station, Units 1 and 2 Project stage: Other 2014-05-16
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Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report 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-23-188, 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-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological 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for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary 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PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, 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Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
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FE NOCŽ FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President March 11, 2014 L-14-113 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852
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 Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 10 CFR 50.54(f) Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a letter titled, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 2 of the 10 CFR 50.54(f) letter addresses NTTF Recommendation 2.1 for flooding.
One of the required responses is for licensees to submit a Hazard Reevaluation Report (HRR) in accordance with the NRC's prioritization plan. By letter dated May 11, 2012, the NRC placed the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS), in Category 2 requiring a response by March 12, 2014. By letter dated March 1, 2013, the NRC provided supplemental information regarding flood hazard reevaluations stating that incomplete HRRs that only contain an analysis of some flooding hazard mechanisms would not be of substantive benefit for staff review and would not be acceptable.
Therefore, licensees should not submit partial reports, but rather submit an extension request on or before the submittal due date. The letter also provided guidance in requesting extensions of the reporting requirement, in that the Beaver Valley Power Station, Unit Nos. 1 and 2 L-14-113 Page 2 following information should be included:
(1) the reason for the delay; (2) a proposed schedule for the submittal of a complete HRR; and (3) the basis for the acceptability of the revised schedule.
FirstEnergy Nuclear Operating Company (FENOC) hereby submits the attached extension request for BVPS (Attachment 1 ), which contains the reasons for the delay, the proposed schedule, and the basis for the acceptability of the revised schedule.
Attachment 2 identifies the regulatory commitment contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager-Fleet Licensing, at 330-315-6810.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March_lL, 2014. Respectfully, z.c1 Eric A. Larson Attachments:
- 1. Extension Request for Beaver Valley Power Station, Unit Nos. 1 and 2, Flood Hazard Reevaluation Report 2. Regulatory Commitment List cc: Director, Office of Nuclear Reactor Regulation (NRR) NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative Attachment 1 L-14-113 Extension Request for Beaver Valley Power Station, Unit Nos. 1 and 2, Flood Hazard Reevaluation Report Page 1of2 FirstEnergy Nuclear Operating Company (FENOC) hereby submits an extension request for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS), Flood Hazard Reevaluation Report (HRR), which contains the reasons for the delay, the proposed schedule, and the basis for the acceptability of the revised schedule.
Reason for the Delay Following the guidance of JLD-ISG-2013-01, Section 1.5.3, FENOC has contacted the Nuclear Regulatory Commission (NRC) (by letter dated December 17, 2013) requesting the NRC interface with the U.S. Army Corps of Engineers (USAGE). FENOC requires information from the USAGE in order to complete the Flooding HRR. An initial telecon was held between the NRC and FENOC on January 10, 2014. During that telecon, the NRC indicated that they would arrange a meeting with the NRC, USAGE, and FENOC staffs. At this time, a date for the meeting has not yet been established, and a schedule for receiving the information has not been determined.
Calculations to support the BVPS flooding reevaluation are not yet finalized.
The going calculations will include incorporation of site-specific local intense precipitation (LIP) rainfall and USAGE dam information.
FENOC is performing a detailed 2D model of the LIP hazard for the BVPS site, and additional time is required to complete the 2D model and the verification and validation of the calculation assumptions, input data, and results. Proposed Submittal Schedule FENOC will submit the required BVPS Flood Hazard Reevaluation Report within 180 days of receiving the USAGE information.
Basis for the Acceptability of the Revised Schedule As recognized in the request for information pursuant to 10 CFR 50.54(f), NRC letter dated March 12, 2012, the current regulatory approach and the resultant plant capabilities provide confidence that an accident with consequences similar to the Fukushima Dai-ichi accident is unlikely to occur in the United States, and that continued operation does not pose an imminent risk to the public health and safety. Therefore, the duration of this extension request has no impact on safe plant operations.
An updated analysis modeled the site configuration from April 2012 and the current design basis for the LIP event. This analysis verified that the combination of site configuration changes since the original analyses have not adversely affected the current design basis.
Attachment 1 L-14-113 Page 2 of 2 In addition, FENOC has completed walkdowns of the BVPS site and verified that existing flood barriers and protection features comply with current BVPS flooding licensing basis. The BVPS current licensing basis (CLB) is met. The current plant operating procedure addressing flooding at the site provides actions to be taken in the event of a high river water level. These actions are initiated when the river reaches a pre-determined elevation as indicated on the river water level indicator at the BVPS intake structure.
Continuing actions are described for incremental changes in water level. These actions include monitoring water levels, monitoring plant equipment, de-energizing plant equipment, communication with outside organizations on flooding forecasts and local dam conditions, and plant shutdown, as applicable for the water level. No additional actions beyond those currently in place are necessary.
The events being analyzed in the BVPS flood hazard reevaluation are beyond the plant design and licensing basis. Therefore, any reevaluation results based on design-basis events would not constitute an operability concern. This is consistent with the NRC supplemental information letter dated March 1, 2013.
Attachment 2 L-14-113 Regulatory Commitment List Page 1 of 1 The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station, Unit Nos. 1 and 2, 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 330-315-6810 of any questions regarding this document or associated Regulatory Commitments.
Regulatory Commitment
- 1. FENOC will submit the required BVPS Flood Hazard Reevaluation Report within 180 days of receiving the USAGE information.
Due Date Within 180 days of receipt of USAGE information