Letter Sequence Response to RAI |
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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
[Table View] |
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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
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 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-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023
Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H
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 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-032, Discharge Monitoring Report (NPDES) Permit No. 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 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
[Table view] |
Text
-ENOC FENOCRoute Beaver Valley Poer Station 168 RPO. Box 4 FirstEnergy Nuclear Operating Comnpany Shippingport, PA 15077-0004 James IL.Lash 724-682-7773 Director, Site Operations July 22, 2005 L-05-123 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information on Generic Letter 2004-02 (TAC Nos. MC4665 and MC4666)
By letter dated March 4, 2005, the FirstEnergy Nuclear Operating Company (FENOC) submitted its initial response to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. I and 2. By letter dated June 3, 2005, the NRC requested additional information regarding the FENOC response to Generic Letter 2004-02. The FENOC responses to this request are provided in Attachment 1. Attachment 2 provides a list of regulatory commitments made in this submittal.
Should you have any questions or require additional information, please contact Mr. Henry L. Hegrat, Supervisor - Licensing, at (330) 315-6944.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July _2L~, 2005.
Sincerely, es H. Lash Attachments
- 1. FENOC Response to Request for Additional Information
- 2. Commitment List
Beaver Valley Power Station, Unit Nos. 1 and 2 Response to RAI on Generic Letter 2004-02 L-05-123 Page 2
References:
- 1. 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. Response (L-05-034) to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. 1 and 2, dated March 4, 2005
- 3. NRC Request for Additional Information Related to Generic Letter 2004-02, dated June 3, 2005 c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator
ATrACHMENT 1 to L-05-123 FENOC Response to Request for Additional Information Regarding Generic Letter 2004-02 Beaver Valley Power Station REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02 "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS" FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function.
Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical and downstream effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1,2005, but did not discuss the evaluation of chemical and downstream effects. Although the GL did not specifically request that the evaluation of chemical and downstream effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical and downstream effects and verify whether your September 1, 2005, response will include an evaluation of these effects.
Response
The NRC and the nuclear industry are examining the impact of chemical interactions on the long-term head loss correlation presently used in containment sump analyses. A test program is currently underway at the Los Alamos National Laboratory (LANL). While no finalized results have yet been published, initial information shows that there are, in fact, long-term chemical effects on the debris bed head loss. The testing is attempting to develop a correlation to permit quantification of these effects. At this time, it is not feasible to quantify the impact of the chemical effects. Since a quantitative assessment is not possible at this time, the September 1, 2005 response for Beaver Valley Power Station will include a qualitative assessment of chemical effects. Additionally, following completion of the LANL testing program, an evaluation of the chemical effects on the debris bed head loss will be performed.
Page 1 of 2 to L-05-123 FENOC is doing a downstream effects review in accordance with the guidance of Regulatory Guide 1.82, Rev. 3, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident", and of Section 7.3 of NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology". The Safety Evaluation Report on NEI 04-07 raised additional issues to consider when doing downstream effects analyses. The Westinghouse Owners Group developed WCAP-16406, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191" to describe methods to be used in addressing the downstream effects issues. The WCAP was just published in June 2005. FENOC will do additional evaluations using the guidance provided in the WCAP. However, a vendor with the expertise and availability to do these evaluations has not yet been identified, so the schedule for the evaluations has not yet been defined. The plan for conducting evaluations of the downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Page 2 of 2
ATTACHMENT 2 to L-05-123 Comniitment List The following list identifies those actions committed to by FENOC for Beaver Valley Power Station (BVPS) 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. Henry L.
Hegrat, Supervisor - Licensing at 330-315-6944 of any questions regarding this document or associated regulatory commitments.
Commitment Due Date The September 1, 2005 response to Generic Letter September 1, 2005 2004-02 will include a qualitative assessment of chemical effects Perform an evaluation of the chemical effects on Following completion of the the debris bed head loss. LANL testing program The plan for conducting evaluations of the September 1, 2005 downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Page 1 of 1
Text
-ENOC FENOCRoute Beaver Valley Poer Station 168 RPO. Box 4 FirstEnergy Nuclear Operating Comnpany Shippingport, PA 15077-0004 James IL.Lash 724-682-7773 Director, Site Operations July 22, 2005 L-05-123 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information on Generic Letter 2004-02 (TAC Nos. MC4665 and MC4666)
By letter dated March 4, 2005, the FirstEnergy Nuclear Operating Company (FENOC) submitted its initial response to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. I and 2. By letter dated June 3, 2005, the NRC requested additional information regarding the FENOC response to Generic Letter 2004-02. The FENOC responses to this request are provided in Attachment 1. Attachment 2 provides a list of regulatory commitments made in this submittal.
Should you have any questions or require additional information, please contact Mr. Henry L. Hegrat, Supervisor - Licensing, at (330) 315-6944.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July _2L~, 2005.
Sincerely, es H. Lash Attachments
- 1. FENOC Response to Request for Additional Information
- 2. Commitment List
Beaver Valley Power Station, Unit Nos. 1 and 2 Response to RAI on Generic Letter 2004-02 L-05-123 Page 2
References:
- 1. 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. Response (L-05-034) to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. 1 and 2, dated March 4, 2005
- 3. NRC Request for Additional Information Related to Generic Letter 2004-02, dated June 3, 2005 c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator
ATrACHMENT 1 to L-05-123 FENOC Response to Request for Additional Information Regarding Generic Letter 2004-02 Beaver Valley Power Station REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02 "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS" FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function.
Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical and downstream effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1,2005, but did not discuss the evaluation of chemical and downstream effects. Although the GL did not specifically request that the evaluation of chemical and downstream effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical and downstream effects and verify whether your September 1, 2005, response will include an evaluation of these effects.
Response
The NRC and the nuclear industry are examining the impact of chemical interactions on the long-term head loss correlation presently used in containment sump analyses. A test program is currently underway at the Los Alamos National Laboratory (LANL). While no finalized results have yet been published, initial information shows that there are, in fact, long-term chemical effects on the debris bed head loss. The testing is attempting to develop a correlation to permit quantification of these effects. At this time, it is not feasible to quantify the impact of the chemical effects. Since a quantitative assessment is not possible at this time, the September 1, 2005 response for Beaver Valley Power Station will include a qualitative assessment of chemical effects. Additionally, following completion of the LANL testing program, an evaluation of the chemical effects on the debris bed head loss will be performed.
Page 1 of 2 to L-05-123 FENOC is doing a downstream effects review in accordance with the guidance of Regulatory Guide 1.82, Rev. 3, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident", and of Section 7.3 of NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology". The Safety Evaluation Report on NEI 04-07 raised additional issues to consider when doing downstream effects analyses. The Westinghouse Owners Group developed WCAP-16406, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191" to describe methods to be used in addressing the downstream effects issues. The WCAP was just published in June 2005. FENOC will do additional evaluations using the guidance provided in the WCAP. However, a vendor with the expertise and availability to do these evaluations has not yet been identified, so the schedule for the evaluations has not yet been defined. The plan for conducting evaluations of the downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Page 2 of 2
ATTACHMENT 2 to L-05-123 Comniitment List The following list identifies those actions committed to by FENOC for Beaver Valley Power Station (BVPS) 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. Henry L.
Hegrat, Supervisor - Licensing at 330-315-6944 of any questions regarding this document or associated regulatory commitments.
Commitment Due Date The September 1, 2005 response to Generic Letter September 1, 2005 2004-02 will include a qualitative assessment of chemical effects Perform an evaluation of the chemical effects on Following completion of the the debris bed head loss. LANL testing program The plan for conducting evaluations of the September 1, 2005 downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Page 1 of 1