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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] Category:Technical Specifications
MONTHYEARML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition ML21027A2282021-01-27027 January 2021 License Amendment Request for One-time Deferral of Steam Generator Inspections ML20335A1292020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications L-20-298, Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-11-0909 November 2020 Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20160A0742020-05-20020 May 2020 2 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases ML18022B1162018-03-0101 March 2018 Issuance of Amendment Nos. 302 and 191 Regarding the Use of Optimized Zirlo Fuel Rod Cladding (CAC Nos. MF9580 and MF9581; EPID L-2017-LLA-0201) ML17291A0812018-01-22022 January 2018 Issuance of Amendments Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) ML17216A5702017-10-12012 October 2017 Issuance of Amendments Emergency Action Level Scheme Changed Based on NEI 99-01, Revision 6 (CAC Nos. MF8448 and MF8449; EPID L-2016-LLA-0011) ML17221A2802017-08-16016 August 2017 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML15294A4392015-12-16016 December 2015 Issuance of Amendments License Amendment Request to Revise Steam Generator Technical Specifications (CAC Nos. MF6054 and 6055) ML15086A2512015-05-20020 May 2015 Issuance of Amendment Revise Technical Specification 4.3.2, Spent Fuel Storage Minimum Inadvertent Drainage Elevation L-15-026, License Amendment Request to Steam Generator Technical Specifications2015-04-0101 April 2015 License Amendment Request to Steam Generator Technical Specifications ML14322A4612015-03-0606 March 2015 Issuance of Amendments Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5b. L-14-300, Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 4252014-09-21021 September 2014 Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 425 ML14245A1512014-09-17017 September 2014 Issuance of Amendments Regarding Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement L-12-271, License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions2012-07-25025 July 2012 License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions L-11-269, Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report2011-09-20020 September 2011 Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report ML1119401232011-07-28028 July 2011 License Amendment, Issuance of Amendment Regarding Approval of the First Energy Nuclear Operating Company Cyber Security Plan L-11-141, License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System2011-05-27027 May 2011 License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System ML1108001222011-03-18018 March 2011 Supplement to Spent Fuel Pool Rerack Amendment Request L-11-103, Supplement to Spent Fuel Pool Rerack Amendment Request2011-03-18018 March 2011 Supplement to Spent Fuel Pool Rerack Amendment Request ML1103501622011-02-24024 February 2011 License Amendment, Issuance of Amendment Regarding the Revised Steam Generator Inspection Scope Using F* Inspection Methodology L-10-275, License Amendment Request for Spent Fuel Pool Rerack2010-10-18018 October 2010 License Amendment Request for Spent Fuel Pool Rerack L-10-063, License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope2010-02-26026 February 2010 License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope ML0929503052009-11-0505 November 2009 Technical Specifications, Appendices a, B, and C ML0527202912009-11-0505 November 2009 Current Facility Operating License No. DPR-66, Technical Specifications, Revised 03/02/2018 ML0929200562009-11-0505 November 2009 Renewed Facility Operating License, Appendices a, B, and D L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. L-08-236, License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System2008-09-24024 September 2008 License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System ML0807300272008-03-11011 March 2008 Technical Specifications to Amend 164 ML0805103742008-02-15015 February 2008 Tech Spec Pages for Amendments 281 and 163 Control Room Envelope Habitibility in Accordance with Technical Specification Task Force Traveler 448 ML0728200762007-10-0505 October 2007 Technical Specifications, Issuance of Amendment Changes to the Recirculation Spray System Pump Start Signal Due to the Containment Sump Screen Modification L-07-074, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008)2007-08-30030 August 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008) ML0717202522007-06-14014 June 2007 Beaver and Perry, Technical Specifications, Issuance of Amendments Modification of Technical Specification Requirements for Inoperable Snubbers ML0703902842007-02-21021 February 2007 Improved Technical Specifications L-07-017, License Amendment Requests Nos. 334 and 2052007-02-0909 February 2007 License Amendment Requests Nos. 334 and 205 L-07-006, Technical Specification 6.9.7 - Steam Generator Inspection Report2007-02-0202 February 2007 Technical Specification 6.9.7 - Steam Generator Inspection Report L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2007-01-11011 January 2007 Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process L-06-162, Supplement to License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion2006-12-0707 December 2006 Supplement to License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion 2023-10-02
[Table view] |
Text
FENOC NP.O.
Beaver Valley Power Station Box 4 FirstEnergy Nuclear Operating Company Shippingport,PA 15077 Paul A. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 March 18, 2011 L-11-103 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 Supplement to Beaver Valley Power Station Unit No. 2 Spent Fuel Pool Rerack Amendment Request (TAC No. ME1079)
Pursuant to 10 CFR 50.90, by letter dated April 9, 2009 (Accession No. ML091210251),
as supplemented by letters dated June 15, 2009 (Accession No. ML091680614),
January 18, 2010 (Accession No. ML100191805), March 18, 2010 (Accession No. ML100820165), May 3, 2010 (Accession No. ML101260059), May 21, 2010 (Accession No. ML101460057), June 1, 2010 (Accession No. ML101610118), August 9, 2010 (Accession No. ML102240256), October 7, 2010 (Accession No. ML102860124),
October 18, 2010 (Accession No. ML102940454), January 5, 2011 (Accession No. ML110110217), February 18, 2011 (Accession No. ML110530463), and February 18, 2011 (Accession No. ML110540328), FirstEnergy Nuclear Operating Company (FENOC) submitted a request to amend the Beaver Valley Power Station Unit No. 2 (BVPS-2) operating license. The proposed amendment would revise the Technical Specifications (TS) to support installation of high density fuel storage racks in the BVPS-2 spent fuel pool.
On March 11, 2011, a teleconference was held between the Nuclear Regulatory Commission (NRC) and FENOC staff to discuss the unintended restriction relative to storage of Region 3 fuel cells. Based on this discussion, FENOC hereby submits a revised TS page to supplement the license amendment request. The revised TS page supercedes the page previously provided. The FENOC evaluation of the proposed change is provided in the enclosure. The information provided by this submittal does not invalidate the no significant hazards consideration submitted in the original amendment request dated April 9, 2009 (Accession No. ML091210251).
Aode kI(4L
Beaver Valley Power Station, Unit No. 2 L-11-103 Page 2 There are no new 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 _/, 2011.
Sincere ly Paul A. Harden
Enclosure:
Evaluation of the Proposed Amendment cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative k
Evaluation of the Proposed Amendment Page 1 of 3
Subject:
Supplement to Beaver Valley Power Station Unit No. 2 Fuel Storage Pool Rerack Amendment Table of Contents Section Title Paeg 1.0 SUM MARY DESCRIPTION ................................................................... 2 2.0 DETAILED DESCRIPTIO N .................................................................... 2
3.0 TECHNICAL EVALUATION
................................................................. 2
4.0 REGULATORY EVALUATION
.............................................................. 3
5.0 ENVIRONMENTAL CONSIDERATION
.................................................. 3 Attachments 1 Revised Proposed Technical Specification Change (Mark Up) 2 Revised Proposed Technical Specification Page (Re-typed - For Information)
Evaluation of the Proposed Amendment Page 2 of 3
Subject:
Supplement To Beaver Valley Power Station Unit No. 2 Fuel Storage Pool Rerack Amendment 1.0
SUMMARY
DESCRIPTION This evaluation supplements the evaluation presented in the FirstEnergy Nuclear Operating Company (FENOC) request to amend Operating License NPF-73 for Beaver Valley Power Station Unit No. 2 (BVPS-2), submitted by letter dated October 18, 2010 (Accession No. ML102940454). The license amendment request proposes to expand the BVPS-2 fuel storage capacity through the use of high density fuel storage racks.
The proposed change presented in this enclosure supercedes the proposed BVPS-2 Technical Specification (TS) mark up page 4.0-2 and retyped page 4.0-3 provided in the October 18, 2010 submittal. The change is proposed in response to a teleconference held between FENOC and Nuclear Regulatory Commission (NRC) staff on March 11,2011.
2.0 DETAILED DESCRIPTION The proposed TS change is shown in Attachment 1. The retyped TS page is provided in Attachment 2. The retyped page is labeled as "Unofficial" because the license amendment has not been issued.
This supplement will revise proposed changes to TS 4.3.1, "Criticality." The proposed change will remove a parenthetical phrase. In the October 18, 2010 submittal, the Metamic Rack section of TS 4.3.1.1.e contained the following: "Region 3 cells are located on the interior of the rack (at least three rows in from the rack periphery) and are prohibited from being located in the outer two rows of the rack ... ." The proposed change presented in this enclosure removes "(at least three rows in from the rack periphery)."
3.0 TECHNICAL EVALUATION
The revised license amendment request submitted by letter dated October 18, 2010 and the additional change proposed herein have been evaluated by FENOC. The license amendment request proposes to expand the BVPS-2 fuel storage capacity through the use of high density fuel storage racks. This supplemental response is not introducing or changing any requirements that were considered in the previous submittal. The removal of the parenthetical phrase clarifies the language for Region 3 cells and removes an unintended restriction. This proposed change is consistent with the previous evaluation submitted by letter dated October 18, 2010.
Evaluation of the Proposed Amendment Page 3 of 3
Subject:
Supplement To Beaver Valley Power Station Unit No. 2 Fuel Storage Pool Rerack Amendment
4.0 REGULATORY EVALUATION
The license amendment request submitted by letter dated October 18, 2010 and the additional change proposed herein have been evaluated by FENOC to determine if the additional change to the TS will impact the no significant hazards consideration determination. The proposed change to the TS is bounded by the analysis submitted in the original amendment request dated April 9, 2009. Based on the initial no significant hazards consideration determination bounding the TS revision in this supplement, it is concluded that the proposed license amendment request presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.0 ENVIRONMENTAL CONSIDERATION
Section 10 CFR 51.22(c)(9) provides criteria for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment or environmental impact statement. A proposed amendment to a facility operating license does not require an environmental assessment or environmental impact statement if operation of the facility in accordance with the proposed amendment would not: (i) involve a significant hazards consideration, (ii) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) result in a significant increase in individual or cumulative occupational radiation exposure.
FENOC has reviewed this license amendment application supplement and has determined that it meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
Attachment 1 Revised Proposed Technical Specification Page (Mark Up) for Beaver Valley Power Station Unit No. 2 Fuel Storage Pool Rerack Amendment (One Page Follows)
Contained in this attachment is a replacement page for the amendment application previously submitted to the NRC dated October 18, 2010 (Accession No. ML102940454). The page replaces the specific page from the previous submittal.
- 2. Region 2 cells are located on the rack periphery (outer row) interspaced with (separating) Region 1 cells and are also located in the second row of cells (from the outside of the rack) separating the Region 1 cells from the Region 3 cells,
- 3. Region 3 cells are located on the interior of the rack and are prohibited from being located in the outer two rows of the rack, and
- 4. Two empty rows of storage locations shall exist between the fuel assemblies in a Boraflex rack and the fuel assemblies in an i Deleted: the adjacent Metamic rack in the fuel storage pool.
Beaver Valley Units 1 and 2 4.0-2 Amendments 278 / TBD, f -- Deleted: 165 I
Attachment 2 Revised Proposed Technical Specification Page (Retyped) for Beaver Valley Power Station Unit No. 2 Fuel Storage Pool Rerack Amendment (One Page Follows)
Contained in this attachment is a replacement page for the amendment application previously submitted to the NRC dated October 18, 2010 (Accession No. ML102940454). The page replaces the specific page from the previous submittal.
Unofficial Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) cells (including a Region 2 cell in the diagonal direction). Since Region 1 cells are qualified for the storage of fresh fuel, any fuel assembly (fresh or burned) meeting the maximum enrichment requirement may be stored in a Region 1 location,
- 2. Region 2 cells are located on the rack periphery (outer row) interspaced with (separating) Region 1 cells and are also located in the second row of cells (from the outside of the rack) separating the Region 1 cells from the Region 3 cells,
- 3. Region 3 cells are located on the interior of the rack and are prohibited from being located in the outer two rows of the rack, and
- 4. Two empty rows of storage locations shall exist between the fuel assemblies in a Boraflex rack and the fuel assemblies in the adjacent Metamic rack in the fuel storage pool.
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.00 weight percent with a tolerance of + 0.05 weight percent,
- b. Keff _<0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.12 of the Unit 1 UFSAR and Section 9.1 of the Unit 2 UFSAR,
- c. Unit I Keff < 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.12 of the UFSAR, Unit 2 Keff < 0.95 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR, and
- d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainage Unit 1 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 750 feet - 10 inches.
Beaver Valley Units 1 and 2 4.0 -3 Amendments 278 / TBD I