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Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-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 ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter 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 ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) 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 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) 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 IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 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 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control 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 ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) 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 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports 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 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 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 IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 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 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report 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 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) 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 CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 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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IE energy
~harbor John J. Grabnar Site Vice President, Beaver Valley Nuclear November 22, 2021 L-21-164 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Energy Harbor Nuclear Corp.
Beaver Valley Power Station P. 0. Box4 Shippingport, PA 15077 724-682-5234 10 CFR 50.71(e) 10 CFR 50.54(a) 10 CFR 54.37(b)
Submittal of the Updated Final Safety Analysis Report, Revision 33 In accordance with the requirements of 10 CFR 50.71(e), the Energy Harbor Nuclear Corp. is hereby submitting to the Nuclear Regulatory Commission (NRG) the Beaver Valley Power Station, Unit No. 1 (BVPS-1), Updated Final Safety Analysis Report (UFSAR), Revision 33, in CD-ROM format. This submittal reflects facility and procedure changes implemented between November 5, 2019 (the end of Refueling Outage 26),
and May 11, 2021 (the end of Refueling Outage 27), along with several changes implemented after Refueling Outage 27.
In accordance with 10 CFR 50.4(b)(6), the BVPS-1 UFSAR Revision 33 is submitted electronically on a total replacement basis. As required by NRG guidance for electronic submissions, Attachments 1 and 2 provide a listing of the document components that make up the two enclosed CD-ROMs.
In addition to the BVPS-1 UFSAR, the first enclosed CD-ROM includes the BVPS-1 Licensing Requirements Manual (LRM), Revision 110, and the Technical Specification (TS) Bases, Revision 41, submitted to satisfy TS 5.5.10.d, which requires submittal of TS Bases changes implemented without prior NRG approval.
The second enclosed CD-ROM includes the BVPS-1 UFSAR, the BVPS-1 LRM, Revision 110, and the BVPS TS Bases, Revision 41 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.
Beaver Valley Power Station, Unit No. 1 L-21-164 Page3 includes a summary of information removed from the BVPS-1 UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, as endorsed by Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)."
Energy Harbor Nuclear Corp. conducted a review of BVPS-1 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."
There are no regulatory commitment changes to be submitted in accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," Revision 0, as endorsed by NRC RIS 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff."
This certifies, to the best of our judgment and belief, that Revision 33 of the BVPS-1 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 submittal 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, /4 John J. Grabnar 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 the BVPS, Unit No. 1 UFSAR
Beaver Valley Power Station, Unit No. 1 L-21-164 Page 3
Enclosures:
A.
Beaver Valley Power Station, Unit No. 1 UFSAR, Licensing Requirements Manual, and Technical Specification Bases (on CD-ROM 1)
B.
Beaver Valley Power Station, Unit No. 1 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-21-164 List of Document Components on CD-ROM 1 Page 1 of 1 File Name 001 UFSAR List of Effective Pages Rev 33.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 Appendix A.pdf 019 UFSAR Appendix B.pdf 020 BVPS-1 LRM Rev 11 0.pdf 021 BVPS TS Bases Rev 41. pdf 93 KB 3,191 KB 36,780 KB 6,515 KB 1,791 KB 4,128 KB 9,690 KB 4,741 KB 1,972 KB 2,068 KB 1,191 KB 1,323 KB 139 KB 415 KB 7,092 KB 131 KB 429 KB 618 KB 1,776 KB 1,701 KB 2,505 KB
L-21-164 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 33.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 Appendix A.pdf 019 UFSAR Appendix B.pdf 020 BVPS-1 LRM Rev 110.pdf 021 BVPS TS Bases Rev 41. pdf 93 KB 1,342 KB 36,298 KB 6,515 KB 1,739 KB 2,917 KB 9,690 KB 4,742 KB 2,188 KB 2,068 KB 1,191 KB 1,323 KB 139 KB 415 KB 7,092 KB 131 KB 429 KB 618 KB 1,775 KB 1,701 KB 2,505 KB L-21-164 Information Removed from BVPS, Unit No. 1 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 125 V DC Power System distribution panels from Section 8.5.3. The change removes reference to the specific number of poles in the battery distribution panel circuit breakers. The reference to the specific number of poles is excessive detail that is not important to the description of its safety function. The removed information has no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design basis functions and has no impact on plant operations.