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Category:Letter type:L
MONTHYEARL-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-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-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 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-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023 Submittal of the Updated Final Safety Analysis Report, Revision 27 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-23-065, 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 2024-09-26
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23144A3052023-05-23023 May 2023 Updated Final Safety Analysis Report, Revision 34 ML22144A1282022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22144A1162022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22144A1142022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22144A1312022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Featres ML22144A1302022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22144A1362022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22144A1172022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22144A1192022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22144A1202022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22144A1292022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML22144A1222022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, List of Effective Pages ML22144A1212022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22144A1262022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22144A1332022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22144A1322022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML22144A1242022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22144A1232022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22144A1182022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report2022-05-18018 May 2022 Submittal of Revision 26 to Updated Final Safety Analysis Report ML21334A0292021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, List of Effective Pages ML21334A0262021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21334A0352021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Wastes and Radiation Protection ML21334A0312021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 3, Reactor ML21334A0252021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 16, Managing the Effects of Component Aging ML21334A0202021-11-22022 November 2021 Submittal of the Updated Final Safety Analysis Report, Revision 33 ML21334A0222021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML21334A0272021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix B, Seismic Design ML21334A0232021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ML21334A0332021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis ML21334A0212021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operation ML21334A0362021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix a, Quality Assurance ML21334A0372021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML21334A0242021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 5, Containment Systems ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases L-21-164, 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations2021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations ML21334A0322021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency System ML21334A0392021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML21334A0282021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20335A1382020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20335A1412020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML20335A1402020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML20335A1252020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations L-20-186, 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection2020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20335A1392020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML20335A1202020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20335A1302020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20335A1362020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20335A1372020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML20335A1222020-11-23023 November 2020 Submittal of Revision 25 to Updated Final Safety Analysis Report 2023-05-23
[Table view] |
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harbor John J. Grabnar Site Vice President, Beaver Valley Nuclear May 18, 2022 L-22-058 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Energy Harbor Nuclear Corp.
Beaver Valley Power Station P. 0. Box4 Shippingport, PA 15077 724-682-5234 10 CFR 50.71 (e) 10 CFR 54.37(b)
Submittal of the Updated Final Safety Analysis Report, Revision 26 In accordance with the requirements of 10 CFR 50.71 (e), the Energy Harbor Nuclear Corp. is hereby submitting to the Nuclear Regulatory Commission (NRC) the Beaver Valley Power Station, Unit No. 2 (BVPS-2), Updated Final Safety Analysis Report (UFSAR) Revision 26 in CD-ROM format. This submittal reflects facility and procedure changes implemented between May 6, 2020 (the end of Refueling Outage 21), and November 13, 2021 (the end of Refueling Outage 22), along with several changes implemented after Refueling Outage 22.
The BVPS-2 UFSAR Revision 26 incorporates a presentation format change. The format change included adjustments such as the elimination of unnecessary extra pages, correction of spacing, renumbering of pages, and so on. All pages affected by the reformatting were provided with a page indicator of "Rev. 26." Those pages where actual text and table information were changed (non-format related) were indicated with a revision bar.
In accordance with 10 CFR 50.4(b)(6), the BVPS-2 UFSAR Revision 26 is being submitted electronically on a total replacement basis. As required by NRC guidance for electronic submissions to the Commission, Attachment 1 and 2 provide a listing of the document components that make up the two enclosed CD-ROMs. In addition to the UFSAR, the first enclosed CD-ROM includes the following:
BVPS-2 Licensing Requirements Manual (LRM), Revision 99 Technical Specification (TS) Bases, Revision 43, submitted to satisfy TS 5.5.1 0.d, which requires submittal of TS Bases changes implemented without prior NRC approval
Beaver Valley Power Station, Unit No. 2 L-22-058 Page2 The second enclosed CD-ROM includes the BVPS-2 UFSAR, LRM, and TS Bases with information identified in accordance with NRG Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents," removed.
In accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," as endorsed by Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)," a summary of information removed from the BVPS-2 UFSAR is provided in Attachment 3.
In accordance with NEI 99-04, "Guidelines for Managing NRG Commitment Changes,"
as endorsed by NRG RIS 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRG Staff," a summary of regulatory commitment changes is provided in Attachment 4.
Energy Harbor Nuclear Corp. conducted a review of BVPS-2 plant changes for 10 CFR 54.37(b) applicability. No components were determined to meet the criteria for newly identified components as clarified by Regulatory Information Summary (RIS) 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.34(b) for Holders of Renewed Licenses."
This certifies, to the best of our judgment and belief, that Revision 26 of the BVPS-2 UFSAR accurately presents changes made since the previous submittal that are necessary to reflect information and analysis submitted to the Commission or pursuant to Commission requirements.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.
Sincerely,
~
John J. Grabnar
Beaver Valley Power Station, Unit No. 2 L-22-058 Page 3 Attachments:
- 1.
List of Document Components on CD-ROM 1
- 2.
List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed)
- 3.
Information Removed from BVPS-2 UFSAR
- 4.
Commitment Change Summary Request
Enclosures:
A.
Beaver Valley Power Station, Unit No. 2 UFSAR, Licensing Requirements Manual, and Technical Specification Bases (on CD-ROM 1)
B.
Beaver Valley Power Station, Unit No. 2 UFSAR With Information Identified Per RIS 2015-17 Removed, Licensing Requirements Manual, and Technical Specification Bases (on CD-ROM 2) cc:
NRC Region I Administrator (without Enclosure B)
NRC Resident Inspector (without Enclosure B)
NRC Project Manager (without Enclosure B)
Director BRP/DEP (without Enclosures)
Site BRP/DEP Representative (without Enclosures)
L-22-058 List of Document Components on CD-ROM 1 Page 1 of 1 File Name 001 UFSAR List of Effective Pages, Rev 26.pdf 002 UFSAR Section 1.pdf 003 UFSAR Section 2.pdf 004 UFSAR Section 3.pdf 005 UFSAR Section 4.pdf 006 UFSAR Section 5.pdf 007 UFSAR Section 6.pdf 008 UFSAR Section 7.pdf 009 UFSAR Section 8.pdf 010 UFSAR Section 9.pdf 011 UFSAR Section 1 0.pdf 012 UFSAR Section 11.pdf 013 UFSAR Section 12.pdf 014 UFSAR Section 13.pdf 015 UFSAR Section 14.pdf 016 UFSAR Section 15.pdf 017 UFSAR Section 16.pdf 018 UFSAR Section 17.pdf 019 UFSAR Section 18.pdf 020 UFSAR Section 19.pdf 021 BVPS-2 LRM Rev 99.pdf 022 BVPS TS Bases, Rev 43.pdf Size 148KB 3, 176KB 37,693KB 39,339KB 5,2188 3,354KB 12,579KB 10,501 KB 1,799KB 6,269KB 2,524KB 2,839KB 4,643KB 511KB 831KB 8,809KB 84KB 51KB 150KB 1,294KB 1,433KB 3,443KB L-22-058 List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed)
Page 1 of 1 File Name 001 UFSAR List of Effective Pages, Rev 26.pdf 002 UFSAR Section 1.pdf 003 UFSAR Section 2.pdf 004 UFSAR Section 3.pdf 005 UFSAR Section 4.pdf 006 UFSAR Section 5.pdf 007 UFSAR Section 6.pdf 008 UFSAR Section 7.pdf 009 UFSAR Section 8.pdf 010 UFSAR Section 9.pdf 011 UFSAR Section 10.pdf 012 UFSAR Section 11.pdf 013 UFSAR Section 12.pdf 014 UFSAR Section 13.pdf 015 UFSAR Section 14.pdf 016 UFSAR Section 15.pdf 017 UFSAR Section 16.pdf 018 UFSAR Section 17.pdf 019 UFSAR Section 18.pdf 020 UFSAR Section 19.pdf 021 BVPS-2 LRM Rev 99.pdf 022 BVPS TS Bases, Rev 43.pdf 148KB 2,969KB 35,484KB
'33,585KB 5,217KB 3,355KB 12,535KB 10,501KB 1,799KB 6,028KB 2,523KB 2,839KB 4,096KB 452KB 831KB 8,809KB 84KB 51KB 150KB 1,294KB 1,433KB 3,443KB L-22-058 Information Removed from BVPS-2 UFSAR Page 1 of 1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees periodically report a brief description of information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides a summary of the information removed from the UFSAR and the basis for removal.
- 1. Removed excessive detail in the description of the BVPS-2 Plant Safety Monitoring System (PSMS) display component. This change replaces the word plasma with PSMS in Table 7.5-1 and removes the word plasma from the component's description "plasma display" in Section 7.7.2.10. The PSMS channel A display (2PSMS-A) was replaced with a liquid crystal display. The channel B plasma display remains currently installed. Describing the display as plasma is excessive detail and is not relevant to the component's functionality as described in the UFSAR. The removed information has no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design basis function(s).
COMMITMENT NUMBER/SOURCE/DATE BV A2003045K BV-L-06-085, 5/30/2006 (NRC Order Section B.5.b-related commitment)
BV-L-07-009-01 BV-L-07-009, 1/26/2007 (NRC Order Section B.5.b-related commitment)
List of Abbreviations Used:
L-22-058 Commitment Change Summary Request Page 1 of 1 COMMITMENT DESCRIPTION Procedures will be revised to require, where feasible and practical, consistent with safe fuel handling practices, every attempt will be made to pre~configure the SFP to enable direct replacement of the expended assemblies from the vessel to the final distributed fuel pattern. Where this is not feasible or practical, the fuel will be distributed into the final pattern as soon as possible, but no later than 60 days after subcriticality.
Plant procedures will include the SFP internal strategy, the SFP external makeup strategy, and the SFP external spray strategy as described in the general description in Attachment 1 of BV-L-07-009.
CHANGE BVPS-1 and BVPS-2 will implement a two-path mitigation strategy for SFP mitigation measures. The preferred method credits TSOAs for SFP external makeup and SFP external spray implementation within 120 minutes. The alternate method disperses discharged f!,.Jel assemblies in an approved pattern until they have been subcritical for more than 1.25 years.
BVPS-1 and BVPS-2 will implement a two-path mitigation strategy for SFP mitigation measures. The preferred method credits TSOAs for SFP external makeup and SFP external spray implementation within 120 minutes. The alternate method disperses discharged fuel assemblies in an approved pattern until they have been subcritical for more than 1.25 years.
Spent Fuel Pool REASON FOR CHANGE The two-path strategy reduces risk associated with fuel movements, while still providing an effective mitigation of the postulated loss of level event.
The two-path strategy reduces risk associated with fuel movements, while still providing an effective mitigation of the postulated loss of level event.
BVPS-1 BVPS-2 NRC Beaver Valley Power Station, Unit No. 1 Beaver Valley Power Station, Unit No. 2 Nuclear Regulatory Commission SFP TSOA Time Sensitive Operator Action