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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 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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 L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information 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, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, 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 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 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FENOC FirstEnergyNuclear OperatingCompany James H. Lash 724-682-5234 Site Vice President Fax: 724-643-8069 February 23, 2007 L-07-031 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Mitigation of Alloy 82/182 Pressurizer Butt Welds and Enhanced Reactor Coolant System Leakage Monitoring Program By letter dated January 31, 2007 (L-07-022), FirstEnergy Nuclear Operating Company (FENOC) provided the Nuclear Regulatory Commission (NRC) with information related to Alloy 82/182 pressurizer butt welds. The letter confirmed completion of inspection and mitigation activities at Beaver Valley Power Station Unit No. 2 (BVPS-2) during the 2006 refueling outage, outlined planned activities for Beaver Valley Power Station Unit No. I (BVPS-1) weld mitigation, and provided details regarding current Reactor Coolant System (RCS) leakage monitoring programs.
During a February 15, 2007 teleconference, the NRC staff provided feedback relevant to the adequacy of BVPS-1 RCS leakage monitoring program with associated reporting requirements and proposed additional details necessary to address NRC concerns. During a teleconference with NRC staff on February 16, 2007, FENOC provided verbal confirmation of the intent to establish regulatory commitments for the proposed leakage monitoring program enhancements.
Specific details of the enhanced RCS leakage monitoring program are provided in Attachment 1.
Regulatory commitments associated with this letter are listed in Attachment 2, and supersede in their entirety the regulatory commitments established by FENOC in the January 31, 2007 letter.
If there are any questions or if additional information is required, please contact Mr. Gregory H. Halnon, Director - FENOC Fleet Regulatory Affairs at (330) 315-7500.
Sincerely, ames H. Lash A4110
'Beaver Valley Power Station, Unit Nos. I & 2 L-07-031 Attachment 1 Page 2 Attachments:
- 1. Mitigation of Alloy 82/182 Pressurizer Butt Welds and Enhanced Reactor Coolant System Leakage Monitoring Program.
- 2. Regulatory Commitments.
cc: Ms. N. Morgan, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
Beaver Valley Power Station, Unit Nos. 1 & 2 L-07-031 Page 1 of 2 Mitigation of Alloy 82/182 Pressurizer Butt Welds and Enhanced Reactor Coolant System Leakage Monitorin2 Pro2ram As previously communicated to the NRC by letter dated January 31, 2007, and discussed during a teleconference on February 15, 2007, BVPS-2 Alloy 82/182 pressurizer butt weld mitigation activities are complete. Therefore, an enhanced RCS leakage monitoring program is not necessary for BVPS-2.
During the fall 2007 refueling outage, FENOC will perform mitigation activities and conduct the required inspections for the BVPS-1 Alloy 82/182 pressurizer butt welds. In order to alleviate RCS leakage concerns prior to weld mitigation, an enhanced RCS leakage monitoring program will be implemented at BVPS-1. The program will contain the following elements:
" Daily RCS leakage monitoring will be performed while in Modes 1, 2, or 3.
" The following action levels will be incorporated:
- a. 0.1 gpm change from one day to the next, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, with at least 0.1 gpm not confirmed from sources other than susceptible and unmitigated pressurizer nozzle welds.
- b. 0.25 gpm above a baseline, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, with at least 0.25 gpm not confirmed from sources other than susceptible and unmitigated pressurizer nozzle welds.
" The baseline for RCS leakage monitoring will be established following seven days of full power operation following the last bare metal visual inspection. The current baseline for BVPS-1 is 0.0 gallons per minute, and was established by using data generated during the first seven days of full power operation following the last refueling outage.
" The following action level response will be incorporated into the BVPS-l RCS leakage monitoring program:
Once a 72-hour evaluation period is complete, and leak rate is still elevated, place the unit in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and perform bare metal visual inspections of unmitigated pressurizer spray, safety, and relief nozzle butt welds and safe-end butt welds containing Alloy 82/182 material.
" Details of any corrective or mitigative actions taken will be reported within 60 days of unit restart, and results of any bare metal visual inspections will be reported within 60 days of unit restart.
- Alloy 82/182 pressurizer butt welds that are not mitigated or removed from service will be re-inspected every four years.
"Beaver Valley Power Station, Unit Nos. 1 & 2 L-07-031 Attachment 1 Page 2 of 2 Each of the activities related to the RCS leakage monitoring program will be incorporated into BVPS-1 procedures or daily instructions before March 1, 2007, and will remain in effect until completion of Alloy 82/182 pressurizer butt weld mitigation activities at BVPS-1. In accordance with FENOC's commitment management program and Nuclear Energy Institute's "Guideline for Managing NRC Commitments," the NRC will be notified, in writing, in advance of any changes to these commitments.
Beaver Valley Power Station, Unit Nos. 1 & 2 L-07-031 Page 1 of2 Re2ulatory Commitments The following list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station (BVPS) Unit No. 1 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. Gregory H. Halnon, Director - Fleet Regulatory Affairs at 330-315-7500 of any questions regarding this document or associated regulatory commitments.
Commitment Due Date
- 1. During the fall 2007 refueling outage, FENOC will perform Prior to startup after mitigation activities and conduct the required inspections for the the fall 2007 BVPS-1 Alloy 82/182 pressurizer butt welds. refueling outage.
- 2. In order to alleviate RCS leakage concerns prior to weld mitigation, February 28, 2007 an enhanced RCS leakage monitoring program will be implemented at BVPS-1. The program will contain the following elements:
" Daily RCS leakage monitoring will be performed while in Modes 1,2, or 3.
" The following action levels will be incorporated:
- a. 0.1 gpm change from one day to the next, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, with at least 0.1 gpm not confirmed from sources other than susceptible and unmitigated pressurizer nozzle welds.
- b. 0.25 gpm above a baseline, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, with at least 0.25 gpm not confirmed from sources other than susceptible and unmitigated pressurizer nozzle welds.
" The baseline for RCS leakage monitoring will be established following seven days of full power operation following the last bare metal visual inspection.
" The following action level response will be incorporated into the BVPS-1 RCS leakage monitoring program:
Once a 72-hour evaluation period is complete, and leak rate is still elevated, place the unit in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and perform bare metal visual inspections of unmitigated pressurizer spray, safety, and relief nozzle butt welds and safe-end butt welds containing Alloy 82/182 material.
(Continued)
- BeaverValley Power Station, Unit Nos. 1 & 2 L-07-031 Page 2 of 2 Commitment Due Date
- 2. In order to alleviate RCS leakage concerns prior to weld mitigation, an enhanced RCS leakage monitoring program will be implemented at BVPS-1. The program will contain the following elements (continued from previous page):
" Details of any corrective or mitigative actions taken will be reported within 60 days of unit restart, and results of any bare metal visual inspections will be reported within 60 days of unit restart.
" Alloy 82/182 pressurizer butt welds that are not mitigated or removed from service will be re-inspected every four years.
Each of the activities related to the RCS leakage monitoring program will be incorporated into BVPS-1 procedures or daily instructions before March 1, 2007, and will remain in effect until completion of Alloy 82/182 pressurizer butt weld mitigation activities at BVPS-1.
- 3. In accordance with FENOC's commitment management program and Ongoing Nuclear Energy Institute's "Guideline for Managing NRC Commitments," the NRC will be notified, in writing, in advance of any changes to these commitments.