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MONTHYEARML0515302672005-06-0303 June 2005 6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005 Response to Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI ML0603803422006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666 Project stage: RAI ML0613802732006-05-18018 May 2006 Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666) Project stage: Other L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors Project stage: Supplement ML0812301162008-02-29029 February 2008 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,... Project stage: Other L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0827402412008-09-30030 September 2008 Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps Project stage: Other ML0909001932009-03-31031 March 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Project stage: Other ML0910501002009-04-21021 April 2009 Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions Project stage: Request ML0912400302009-05-0505 May 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-06-30030 June 2009 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Supplement ML1002903182010-02-18018 February 2010 RAI, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: RAI ML1008407562010-03-31031 March 2010 Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staff'S Request for Additional Information and to Discuss Generic Letter 2004-02 Project stage: RAI ML1013206652010-05-18018 May 2010 Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013 Generic Safety Issue 191 Resolution Plan Project stage: Other 2009-03-11
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Category:Letter type:L
MONTHYEARL-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-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule 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-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report 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-24-054, 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-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., 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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 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-23-087, 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-23-086, 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-23-073, 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 Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to 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FENOC 0%%P.O.
Beaver Valley Power Station Box 4 FirstEnergyNuclear OperatingCompany Shippingport,PA 15077 PeterP. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 March 11, 2009 L-09-056 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 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Iniection System Pumps (TAC No. MC4665)
This letter provides supplemental information regarding the FirstEnergy Nuclear Operating Company (FENOC) response to Generic Letter 2004-02 (Reference 1) for Beaver Valley Power Station Unit No. 1 (BVPS-1). FENOC indicated in a letter dated October 29, 2008 (Reference 2) in response to Review Area 3.m (Reference 3) that during the final review of the downstream analysis, the need for additional evaluation was identified for the recirculation spray (RS) and low head safety injection (LHSI) pump wear analysis, and that evaluation results would be provided by March 20, 2009.
Additional evaluation of downstream effects on the BVPS-1 RS and LHSI pumps has been completed. Pump component wear, hydraulic performance, and seal leakage were considered as discussed below. The results of the downstream analysis indicate that the pumps are acceptable for their 30 day mission time.
The wear analysis for the BVPS-1 RS and LHSI pumps were developed in accordance with the requirements of WCAP-16406-P-A, Revision 1, "Evaluation of Downstream Debris Effects in Support of GSI-1 91." Modifications to replace calcium-silicate and fibrous Insulation are scheduled for the spring 2009 maintenance and refueling outage (1R19). The debris concentration inputs used for the pump analysis were based on the final predicted debris transported to the sump after insulation modifications are completed. The wear results for all components evaluated were found to be within the wear acceptance criteria of WCAP-16406-P-A.
A hydraulic performance assessment was performed based on the guidance of WCAP-16406-P-A. With relatively low wear predicted, the hydraulic performance of the pumps was evaluated as acceptable. 4ooJ
I Beaver Valley Power Station, Unit No. 1 L-09-056 Page 2 The effects of seal leakage on room habitability, room equipment operation, and environmental qualification were reviewed for the pumps located outside of the containment. These pumps use a tandem mechanical seal arrangement with a demineralized water accumulator that maintains a positive seal against leakage of radioactive fluid from the seals of these pumps and prevents debris-laden fluid from entering the seal. Therefore seal leakage for the RS and LHSI pumps is not an issue requiring evaluation under downstream effects analysis.
This information is provided in accordance with 10 CFR 50.54(f). There are no regulatory commitments 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 330-761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March il , 2009.
Sincerely, Peter P. Sena III
References:
- 1. NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized- Water Reactors," dated September 13, 2004.
- 2. FENOC letter dated October 29, 2008, Beaver Valley Power Station Unit Nos. 1 and 2, Supplemental Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized- Water Reactors," (TAC Nos. MC4665 and MC4666).
- 3. NRC Content Guide for Generic Letter 2004-02 Supplemental Response, dated August 15, 2007 and revised November 21, 2007.
cc: Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
Text
FENOC 0%%P.O.
Beaver Valley Power Station Box 4 FirstEnergyNuclear OperatingCompany Shippingport,PA 15077 PeterP. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 March 11, 2009 L-09-056 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 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Iniection System Pumps (TAC No. MC4665)
This letter provides supplemental information regarding the FirstEnergy Nuclear Operating Company (FENOC) response to Generic Letter 2004-02 (Reference 1) for Beaver Valley Power Station Unit No. 1 (BVPS-1). FENOC indicated in a letter dated October 29, 2008 (Reference 2) in response to Review Area 3.m (Reference 3) that during the final review of the downstream analysis, the need for additional evaluation was identified for the recirculation spray (RS) and low head safety injection (LHSI) pump wear analysis, and that evaluation results would be provided by March 20, 2009.
Additional evaluation of downstream effects on the BVPS-1 RS and LHSI pumps has been completed. Pump component wear, hydraulic performance, and seal leakage were considered as discussed below. The results of the downstream analysis indicate that the pumps are acceptable for their 30 day mission time.
The wear analysis for the BVPS-1 RS and LHSI pumps were developed in accordance with the requirements of WCAP-16406-P-A, Revision 1, "Evaluation of Downstream Debris Effects in Support of GSI-1 91." Modifications to replace calcium-silicate and fibrous Insulation are scheduled for the spring 2009 maintenance and refueling outage (1R19). The debris concentration inputs used for the pump analysis were based on the final predicted debris transported to the sump after insulation modifications are completed. The wear results for all components evaluated were found to be within the wear acceptance criteria of WCAP-16406-P-A.
A hydraulic performance assessment was performed based on the guidance of WCAP-16406-P-A. With relatively low wear predicted, the hydraulic performance of the pumps was evaluated as acceptable. 4ooJ
I Beaver Valley Power Station, Unit No. 1 L-09-056 Page 2 The effects of seal leakage on room habitability, room equipment operation, and environmental qualification were reviewed for the pumps located outside of the containment. These pumps use a tandem mechanical seal arrangement with a demineralized water accumulator that maintains a positive seal against leakage of radioactive fluid from the seals of these pumps and prevents debris-laden fluid from entering the seal. Therefore seal leakage for the RS and LHSI pumps is not an issue requiring evaluation under downstream effects analysis.
This information is provided in accordance with 10 CFR 50.54(f). There are no regulatory commitments 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 330-761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March il , 2009.
Sincerely, Peter P. Sena III
References:
- 1. NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized- Water Reactors," dated September 13, 2004.
- 2. FENOC letter dated October 29, 2008, Beaver Valley Power Station Unit Nos. 1 and 2, Supplemental Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized- Water Reactors," (TAC Nos. MC4665 and MC4666).
- 3. NRC Content Guide for Generic Letter 2004-02 Supplemental Response, dated August 15, 2007 and revised November 21, 2007.
cc: Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)