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Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 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 L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report 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) 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-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 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BLVD.. SUITE 1OO KING OF PRUSSIA. PA 19406-2713 November 23, 2015 Mr. Eric A. Larson Site Vice President FirstEnergy Nuclear Generation, LLC Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077-0004
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 2 RESPONSE TO A REQUEST FOR INFORMATION CONCERN I N G LI CENSED OPERATOR FITN ESS-FOR-DUTY-TEST
Dear Mr. Larson:
The U.S. Nuclear Regulatory Commission (NRC) has received your letter dated October 30, 2015 (L-15-329), in response to our letter dated October 5,2015. Your response adequately addressed our questions. Based on the fact that the individual's blood alcohol level was below that which would constitute a regulatory concern, and considering FENOC's response to this issue, we plan no further actions in this matter.
Also, we have reviewed your request and the material in accordance with the requirements of 10 CFR 2.390(bXl )(ii) and, on the basis of your statements, have determined that the submitted information sought to be withheld contains personal information, the disclosure of which would be an unwarranted invasion of privacy. Therefore, the enclosure of your letter will be withheld from public disclosure pursuant to 10 CFR 2.390(bX1)(ii) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," your letter without the enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http:i/www.nrc.qovlreadinq-rmladams.html (the Public Electronic Reading Room). Withholding the document from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents.
lf the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future if, for example, the scope of a Freedom of Information Act request includes the operator's information. In all review situations, if the NRC makes a determination adverse to the above, the operator will be notified in advance of any public disclosure.
Eric A. Larson lf you have any questions, regarding the disclosure of the information, please contact Mr. Brett M. Klukan, Regional Counsel, at 610-337-5301.
Raymond K. Lorson, Director Division of Reactor Safety Docket No. 50-412 License No. NPF-73 cc: Distribution via ListServ
Eric A. Larson lf you have any questions, regarding the disclosure of the information, please contact Mr. Brett M. Klukan, Regional Counsel, at 610-337-5301.
Sincerely, lRA/
Raymond K. Lorson, Director Division of Reactor Safety Docket No. 50-412 License No. NPF-73 cc: Distribution via ListServ DISTRIBUTION:
S. Sloan, Chief, NRRYDIRS/IOLB M. Scott, Region I/DRP D D. Dorman, Region l/RA J. Colaccino, Region I/DRP Acting DD D. Lew, Region l/RA S. Kennedy, Region I/DRP BC B. Klukan, Region lCounsel C. Bickett, Region I/DRP SRI B. Bickett, Region l/OE D. Jackson, Region I/DRS/OB R. Lorson, Region I/DRS D C. Bixler, Region I/DRS/OB (with concurrences)
G. Suber, Region I/DRS Acting DD DOCUMENT NAME: G:\DRS\Operations Byanch\Bixler\FitnessforDuty\9-25-15 RAI FFD BV2 Response Letter.docx ADAMS ACCESSION NO L I 2o g Non-Sensitive V Publicly Available g SUNSI Review tr tr Sensitive Non-Pu bl icly Available OFFICE Rl/DRS/ RI/ORA Rt/DRS/OB^
NAME RLorsy'/tut BKlukan ft\! ( '"o..lact<son )c DATE ttt{lns il tt1tts rFl ^
11{1/15 v OFFICIAL RECORD COP
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BLVD.. SUITE 1OO KING OF PRUSSIA. PA 19406-2713 November 23, 2015 Mr. Eric A. Larson Site Vice President FirstEnergy Nuclear Generation, LLC Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077-0004
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 2 RESPONSE TO A REQUEST FOR INFORMATION CONCERN I N G LI CENSED OPERATOR FITN ESS-FOR-DUTY-TEST
Dear Mr. Larson:
The U.S. Nuclear Regulatory Commission (NRC) has received your letter dated October 30, 2015 (L-15-329), in response to our letter dated October 5,2015. Your response adequately addressed our questions. Based on the fact that the individual's blood alcohol level was below that which would constitute a regulatory concern, and considering FENOC's response to this issue, we plan no further actions in this matter.
Also, we have reviewed your request and the material in accordance with the requirements of 10 CFR 2.390(bXl )(ii) and, on the basis of your statements, have determined that the submitted information sought to be withheld contains personal information, the disclosure of which would be an unwarranted invasion of privacy. Therefore, the enclosure of your letter will be withheld from public disclosure pursuant to 10 CFR 2.390(bX1)(ii) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," your letter without the enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http:i/www.nrc.qovlreadinq-rmladams.html (the Public Electronic Reading Room). Withholding the document from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents.
lf the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future if, for example, the scope of a Freedom of Information Act request includes the operator's information. In all review situations, if the NRC makes a determination adverse to the above, the operator will be notified in advance of any public disclosure.
Eric A. Larson lf you have any questions, regarding the disclosure of the information, please contact Mr. Brett M. Klukan, Regional Counsel, at 610-337-5301.
Raymond K. Lorson, Director Division of Reactor Safety Docket No. 50-412 License No. NPF-73 cc: Distribution via ListServ
Eric A. Larson lf you have any questions, regarding the disclosure of the information, please contact Mr. Brett M. Klukan, Regional Counsel, at 610-337-5301.
Sincerely, lRA/
Raymond K. Lorson, Director Division of Reactor Safety Docket No. 50-412 License No. NPF-73 cc: Distribution via ListServ DISTRIBUTION:
S. Sloan, Chief, NRRYDIRS/IOLB M. Scott, Region I/DRP D D. Dorman, Region l/RA J. Colaccino, Region I/DRP Acting DD D. Lew, Region l/RA S. Kennedy, Region I/DRP BC B. Klukan, Region lCounsel C. Bickett, Region I/DRP SRI B. Bickett, Region l/OE D. Jackson, Region I/DRS/OB R. Lorson, Region I/DRS D C. Bixler, Region I/DRS/OB (with concurrences)
G. Suber, Region I/DRS Acting DD DOCUMENT NAME: G:\DRS\Operations Byanch\Bixler\FitnessforDuty\9-25-15 RAI FFD BV2 Response Letter.docx ADAMS ACCESSION NO L I 2o g Non-Sensitive V Publicly Available g SUNSI Review tr tr Sensitive Non-Pu bl icly Available OFFICE Rl/DRS/ RI/ORA Rt/DRS/OB^
NAME RLorsy'/tut BKlukan ft\! ( '"o..lact<son )c DATE ttt{lns il tt1tts rFl ^
11{1/15 v OFFICIAL RECORD COP