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Category:Inspection Report Correspondence
MONTHYEARML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML20057D4142020-02-24024 February 2020 Ti 2515/194 Inspection Documentation Request IR 05000334/20164032016-08-18018 August 2016 Security Inspection Report 05000334/2016403 and 05000412/2016403 (Cover Letter-PUBLIC) ML13114A9602013-05-0202 May 2013 No. 1 - Review of Steam Generator Tube Inspection Report for Spring 2012 Refueling Outage IR 05000041/20090082009-10-15015 October 2009 IR 05000334-09-008, and IR 0500041-09-008, Beaver Valley Problem Identification & Resolution Inspection - Request for Documents ML0929200622009-10-15015 October 2009 IR 05000334-09-008, and IR 0500041-09-008, Beaver Valley Problem Identification & Resolution Inspection - Request for Documents ML0929200762009-10-15015 October 2009 IR 05000334-09-008, and IR 05000412-09-008, Beaver Valley Problem Identification and Resolution - Entrance Meeting Attendees IR 05000334/20090082009-10-15015 October 2009 IR 05000334-09-008, and IR 05000412-09-008, Beaver Valley Problem Identification and Resolution Inspection - Exit Meeting Attendees IR 05000334/20074052007-12-0505 December 2007 IR 05000334-07-405, and IR 05000412-07-405, on 10/22/2007, Beaver Valley Power Stations, Units 1 and 2, Access Control IR 05000334/20052012007-10-0303 October 2007 Letter to Mr. P. Sena Beaver Valley Power Station - NRC Material Control and Accounting Program Inspection - Report 05000334/2005201 and 05000412/2005201 IR 05000334/20060112006-10-0303 October 2006 IR 05000334/2006011 and 05000412/2006011; Beaver Valley Power Station, Units 1 and 2; Ti 2515/168 ML0626203412006-09-18018 September 2006 IR 05000334-06-009, 05000412-06-009; on 06/26/2006 - 08/22/2006; Beaver Valley Nuclear Power Station, Units 1 and 2; Exercise Evaluation IR 05000334/20050052005-06-29029 June 2005 IR 05000334-05-005, IR 05000412-05-005, Beaver Valley PI&R Inspection Request Form with CR Lists IR 05000334/20040092004-05-27027 May 2004 IR 05000334-04-009, & IR 05000412-04-009, on 04/19/2004 Through 04/23/2004, for Beaver Valley Power Station, Physical Security Baseline Inspection ML0327403282003-10-0101 October 2003 Beaver Valley Unit 2 - Notification of Conduct of a Triennial Fire Protection Baseline Inspection ML0312108572003-04-30030 April 2003 Attachment 3 - Tabular Results from the Expanded Extent of Condition for CR 02-02202 ML0312108422003-04-30030 April 2003 Attachment 4 - Corrective Action ML0312108152003-04-30030 April 2003 Attachment 3 - Corrective Action 02-02202-24 Expanded Extent of Condition IR 05000334/20020022002-04-24024 April 2002 IR 05000334/2002-002, IR 05000412/2002-002, on 02/10-03/30/2002; Firstenergy Nuclear Operating Company; Beaver Valley Power Station; Units 1 & 2. Event Follow-up. One Issue of Very Low Safety Significance Identified IR 05000334/20020032002-04-12012 April 2002 IR 05000334/2002-003, IR 05000412/2002-003, on 09/01/01-03/15/2002; Firstenergy Nuclear Operating Company; Units 1 and 2; Alert and Notification System. One Yellow Violation Identified 2024-05-29
[Table view] Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 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-24-015, 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 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-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2024-02-20020 February 2024 Missile Barrier Door Left Open Resulting in a Loss of Safety Function IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 2024-09-17
[Table view] |
Text
ber 5, 2007
SUBJECT:
BEAVER VALLEY POWER STATION - NRC EVENT FOLLOWUP INSPECTION REPORT 05000334/2007405 AND 05000412/2007405
Dear Mr. Sena:
On October 22, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an event follow-up inspection at your Beaver Valley Nuclear Power Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were debriefed with Mr. Craine, Security Manager, Beaver Valley Power Station, and other members of your staff at the conclusion of the inspection on October 22, 2007. An exit meeting was conducted by telephone on November 1, 2007 with Mr. Craine who acknowledged the finding.
The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. DETERMINATION Warning: Violation of section 147 of the Atomic MADE BY:
Energy Act, Safeguards Information is subject NAME/TITLE: James M. Trapp, Chief to civil and criminal penalties ORGANIZATION: RI/DRS/PSB1 BASIS - DG-SG-1 (300) Physical Protection Program SIGNATURE____/RA/___________ DATE: 12/05/07 This report documents one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiency was promptly corrected and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the site. The finding had a cross-cutting aspect in the in the area of human performance for not communicating human error techniques (H.4(a)). However, because of the very low safety significance and because it is entered into your corrective action program, the NRC is treating this violation as a non-cited violation (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest this non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.:
Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region I; the Director of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Beaver Valley Power Station (BVPS).
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Security-Related Information - Withhold Under 10 CFR 2.390 and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely,
/RA/
James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos: 50-334; 50-412 License Nos: DPR-66, NPF-73 Enclosure: Inspection Report No. 05000334/2007405, 05000412/2007405 w/Attachment: Supplemental Information (CONTAINS (SGI))