Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARL-09-086, License Amendment Request No. 08-027, Spent Fuel Pool Rerack2009-04-0909 April 2009 License Amendment Request No. 08-027, Spent Fuel Pool Rerack Project stage: Request ML0915201072009-06-0101 June 2009 Supplemental Information Needed for Acceptance of Requested Licensing Action Spent Fuel Pool Rerack Project stage: Acceptance Review L-09-162, Additional Technical Information Pertaining to License Amendment Request No. 08-0272009-06-15015 June 2009 Additional Technical Information Pertaining to License Amendment Request No. 08-027 Project stage: Request ML0917510672009-06-25025 June 2009 Acceptance of Requested Licensing Action Spent Fuel Pool Rerack Project stage: Acceptance Review ML0932809142009-12-0404 December 2009 Request for Additional Information Regarding Spent Fuel Pool Rerack License Amendment Project stage: RAI ML1003800022010-02-16016 February 2010 Request for Additional Information Spent Fuel Pool Rerack Amendment Project stage: RAI ML1001303452010-03-0505 March 2010 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing, and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information Project stage: Other L-10-082, Response to NRC Staff Request for Additional Information Regarding Criticality Analyses Supporting a Spent Fuel Pool Re-rack2010-03-18018 March 2010 Response to NRC Staff Request for Additional Information Regarding Criticality Analyses Supporting a Spent Fuel Pool Re-rack Project stage: Request ML1007605842010-03-19019 March 2010 Request for Additional Information Spent Fuel Pool Rerack Round 3 Project stage: RAI ML1008407842010-04-15015 April 2010 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance L-10-121, Response to Request for Additional Information Related Spent Fuel Pool Rerack License Amendment Request2010-05-0303 May 2010 Response to Request for Additional Information Related Spent Fuel Pool Rerack License Amendment Request Project stage: Response to RAI L-10-151, Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request2010-05-21021 May 2010 Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request Project stage: Response to RAI L-10-130, Remainder of Responses to NRC Staff Request for Additional Information Regarding Unit 2 Spent Fuel Pool Rerack Criticality Analyses2010-06-0101 June 2010 Remainder of Responses to NRC Staff Request for Additional Information Regarding Unit 2 Spent Fuel Pool Rerack Criticality Analyses Project stage: Request ML1013805462010-06-11011 June 2010 Request for Additional Information Spent Fuel Pool Rerack License Amendment Project stage: RAI ML1017203652010-06-24024 June 2010 Impacts to the Review Schedule Regarding the Spent Fuel Pool Rerack License Amendment Request Project stage: Other L-10-235, Response to Request for Additional Information for License Amendment Request No. 08-027 Re Spent Fuel Pool Rerack2010-08-0909 August 2010 Response to Request for Additional Information for License Amendment Request No. 08-027 Re Spent Fuel Pool Rerack Project stage: Response to RAI ML1025107802010-09-14014 September 2010 Notice of Forthcoming Meeting with First Energy Nuclear Operating Company, Beaver Valley Power Station, Unit No. 2 & Holtec, Inc., to Discuss the Licensee'S Responses, Dated August 9, 2010 Project stage: Meeting L-10-282, Supplemental Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request2010-10-0707 October 2010 Supplemental Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request Project stage: Supplement L-10-275, License Amendment Request for Spent Fuel Pool Rerack2010-10-18018 October 2010 License Amendment Request for Spent Fuel Pool Rerack Project stage: Request ML1029404582010-10-18018 October 2010 Holtec Report No: HI-2084175, Licensing Report for Beaver Valley, Unit 2, Rerack. Project stage: Other ML1027903512010-10-18018 October 2010 Summary of Meeting with Firstenergy Nuclear Operating Company, on the Request for Additional Resposnses Regarding the Spent Fuel Rerack for Beaver Valley Power Station, Unit No. 2 Project stage: Meeting ML1035606612010-12-29029 December 2010 Summary of Beaver Valley Power Station, Unit 2 Public Conference Call Regarding Spent Fuel Pool Rerack LAR Draft RAI Responses Discussion Project stage: Draft RAI L-10-329, Supplemental Information for Spent Fuel Pool Rereack License Amendment Request2011-01-0505 January 2011 Supplemental Information for Spent Fuel Pool Rereack License Amendment Request Project stage: Supplement ML1102006022011-01-24024 January 2011 Request for Additional Information Spent Fuel Pool Rerack Amendment (ME1079) Project stage: RAI L-11-024, Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack2011-02-18018 February 2011 Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack Project stage: Request L-11-057, Responses to NRC Staff Request for Additional Information Regarding Unit No. 2 Spent Fuel Pool Rerack Criticality Analyses2011-02-18018 February 2011 Responses to NRC Staff Request for Additional Information Regarding Unit No. 2 Spent Fuel Pool Rerack Criticality Analyses Project stage: Request ML1107504782011-03-10010 March 2011 E-mail Summary of Clarification Phone Call Regarding the Beaver Valley 2 Spent Fuel Pool Rerack Amendment (ME1079) Project stage: Other ML1108001222011-03-18018 March 2011 Supplement to Spent Fuel Pool Rerack Amendment Request Project stage: Supplement L-11-101, Supplemental Information for Spent Fuel Pool Rerack License Amendment Request2011-03-21021 March 2011 Supplemental Information for Spent Fuel Pool Rerack License Amendment Request Project stage: Supplement ML1108005702011-03-21021 March 2011 Supplemental Information for Spent Fuel Pool Rerack License Amendment Request Project stage: Supplement ML1108908442011-04-29029 April 2011 Issuance of Amendment Regarding the Spent Fuel Pool Rerack Project stage: Approval 2010-05-21
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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
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Text
"N Beaver Valley Power Station
-"* P.O. Box 4 FirstEnergyNuclear OperatingCompany. Shippingport,PA 15077 Paul A.Harden 724-682-5234 Site Vice President Fax: 724-643-8069 October 7, 2010 L-1 0-282 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Supplemental Response to Request for Additional Information Related to Beaver Valley Power Station Unit No. 2 Spent Fuel Pool Rerack License Amendment Request (TAC No. ME1079)
By letter dated April 9, 2009 (Reference 1), and as supplemented by letters dated June 15, 2009 (Reference 2), January 18, 2010 (Reference 3), March 18, 2010 (Reference 4), May 3, 2010 (Reference 5), May 21, 2010 (Reference 6), and June 1, 2010 (Reference 7), FirstEnergy Nuclear Operating Company (FENOC) requested an amendment to the operating license for Beaver Valley Power Station (BVPS) Unit No. 2.
The proposed amendment would revise the Technical Specifications to support the installation of high density fuel storage racks in the BVPS Unit No. 2 spent fuel pool (SFP).
On June 11, 2010, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) regarding the bulk SFP calculation methodology (Reference 9). FENOC responded'in correspondence dated August 9, 2010 (Reference 8). On September 1,2010, a telephone call between FENOC and NRC staff was held to discuss NRC staff concerns regarding the SFP bulk thermal analysis.
On a September 22, 2010 telephone call, FENOC summarized the results of a SFP bulk thermal analysis that was representative of bounding conditions associated with planned refueling outages.
The following information summarizes the bounding conditions assumed in the SFP bulk thermal analysis and is consistent with the conditions provided in Section 3.1.1.1.
of'the Review Standardfor Extended Power Uprates (RS-001) (Reference 10).
(1) decay heat load is calculated assuming a full core offload initiated at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after reactor shutdown following a full power cycle of 2,918 megawatts thermal with the SFP containing more than 1,690 assemblies and previous batch AXO0f
Beaver Valley Power Station, Unit No. 2 L-10-282 Page 2 discharges consisting of 72 assemblies each beginning in the fall 2009 refueling outage; and (2) heat removal capability is based on an inlet component cooling water (CCW) temperature of 88 degrees Fahrenheit, a total cooling system flow rate of 2,200 gallons per minute, a total tube side flow rate of 1,500 gallons per minute, two SFP cooling pumps, and two SFP cooling heat exchangers having a tube side fouling factor of 0.0010 [1/Btu/hr/sqft/F] and a shell side fouling factor of 0.0005
[1/Btu/hr/sqft/F]; and, (3) alternate heat removal paths, such as evaporative cooling, are conservatively neglected.
The peak bulk SFP temperature was calculated to be 150 degrees Fahrenheit in the bulk thermal analysis realistic case defined above. Bounding assumptions regarding SFP cooling heat exchanger performance were used. Additionally, assuming a loss of all SFP cooling at the time of the peak temperature, the time to boil is greater than three hours and the associated boil-off rate is less than 80 gallons per minute.
The calculated peak SFP temperature occurs following completion of the full core offload and prior to the reactor vessel core reload. During plant MODES 4, 5, 6, and undefined (defueled), the Shutdown Defense in Depth administrative procedure is in effect, which includes observation of the SFP temperature and calculation of the associated time to boil (in the event of a loss of all forced cooling).
While in plant MODES 1 through 6 and defueled, the tour operator monitors the SFP heat exchanger inlet temperatures daily to ensure the maximum SFP heat exchanger temperature does not exceed 140 degrees Fahrenheit.
In accordance with the Fuel Pool PurificationTrouble alarm response procedure (Reference 11), the Fuel Pool Demineralizer Supply Temperature High alarm is set at 140 degrees Fahrenheit. Following annunciation, Operators will follow the Fuel Pool Purification Trouble procedure requirements. If the elevated temperature alarm is valid, the procedure provides steps to shutdown purification flow and then increase cooling of the SFP/refueling cavity.
In accordance with the Fuel Pool Cooling Trouble alarm response procedure (Reference 12), the Fuel Pool Temperature High alarms are set at 160 degrees Fahrenheit. Following annunciation, Operators will follow the Fuel Pool Cooling Trouble procedure requirements. If the elevated temperature alarm is valid, the procedure provides steps to increase cooling of the SFP.
FENOC will evaluate and if necessary, modify the current 140 degrees Fahrenheit and 160 degrees Fahrenheit SFP alarm setpoints, in conjunction with implementation of the
Beaver Valley Power Station, Unit No. 2 L-10-282 Page 3 BVPS Unit No. 2 rerack license amendment request. The evaluation will ensure that the alarm setpoints are consistent with the analysis assumptions representative of bounding conditions associated with planned refueling outages.
The Attachment provides the Regulatory Commitment made in this submittal. The information provided by this submittal does not invalidate the no significant hazard evaluation submitted by Reference 1. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - FENOC Fleet Licensing, at 330-761-6071.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October __j, 2010.
Sincere Paul A. Harden
Attachment:
Regulatory Commitment List
Beaver Valley Power Station, Unit No. 2 L-10-282 Page 4
References:
- 1. FENOC Letter L-09-086, "License Amendment Request No.08-027, Unit 2 Spent Fuel Pool Rerack," dated April 9, 2009 (Accession No. ML091210251).
- 2. FENOC Letter L-09-162, "Additional Technical Information Pertaining to License Amendment Request No.08-027 (TAC No. ME1079)," dated June 15, 2009 (Accession No. ML091680614).
- 3. FENOC Letter L-1 0-001, "Response to Request for Additional Information for License Amendment Request No.08-027, Unit 2 Spent Fuel Pool Rerack (TAC No. ME1079)" dated January 18, 2010 (Accession No. ML100191805).
- 4. FENOC Letter L-10-082, "Response to NRC Staff Request for Additional Information Regarding Criticality Analyses Supporting a Spent Fuel Pool Re-rack for Unit 2 (TAC No. ME1079)," dated March 18, 2010 (Accession No. ML100820165).
- 5. FENOC Letter L-10-121, "Response to Request for Additional Information for License Amendment Request No.08-027 (TAC No. ME1079)," dated May 3, 2010 (Accession No. ML101260059).
- 6. FENOC Letter L-1 0-151, "Response to Request for Additional Information for License Amendment Request No.08-027 (TAC No. ME1079)," dated May 21, 2010 (Accession No. ML101460057).
- 7. FENOC Letter L-10-130, "Remainder of Responses to NRC Staff Request for Additional Information Regarding Unit 2 Spent Fuel Pool Rerack Criticality Analyses (TAC No. ME1079)", dated June 1,2010 (Accession No. ML101610118).
- 8. FENOC Letter L-10-235, "Response to Request for Additional Information for License Amendment Request No.08-027, Unit 2 Spent Fuel Pool Rerack (TAC No. ME1079)", dated August 9, 2010 (Accession No. ML102240256).
- 9. NRC Letter dated June 11, 2010, titled "BEAVER VALLEY POWER STATION, UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION RE: SPENT FUEL POOL RERACK LICENSE AMENDMENT (TAC NO. ME1079)" (Accession No. ML101380546).
- 10. RS-001, Review Standard for Extended Power Uprates, Section 3.1.1.1., "Full Cooling System Capability Evaluation," of Attachment 2 to Matrix 5 of Section 2.1, Revision 0, December 2003.
- 11. 20M-20.4.AAC, Fuel Pool Purification Trouble, Revision 4.
- 12. 20M-20.4.AAA, Fuel Pool Cooling Trouble, Revision 6 cc: NRC Region I Administrator NRC Senior Resident Inspector NRR Project Manager Director BRP/DEP Site Representative BRP/DEP
r . .
ATTACHMENT L-1 0-282 Regulatory Commitment List Page 1 of 1 The following identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station (BVPS) Unit No. 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) 761- 6071 of any concerns regarding this document or associated Regulatory Commitments.
Regulatory Commitment Due Date
- 1. FENOC will evaluate and if necessary, 1. Subsequent to NRC approval modify the current 140 degrees Fahrenheit and concurrent with the and 160 degrees Fahrenheit SFP alarm implementation of License setpoints, in conjunction with implementation Amendment Request 08-027.
of the BVPS Unit No. 2 rerack license amendment request. The evaluation will ensure that the alarm setpoints are consistent with the analysis assumptions representative of bounding conditions associated with planned refueling outages.