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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406 | | {{#Wiki_filter:uly 12, 2018 |
| -2713 July 12, 2018 Mr. Richard Bologna Site Vice President First Energy Nuclear Operating Company Beaver Valley Power Station P. O. Box 4
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| - Route 168 Shippingport, PA 15077
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| -0004
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| SUBJECT: BEAVER VALLEY POWER STATION - NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT NOS. 05000334/201 8 4 10 AND 05000412/201 8 4 10 | | ==SUBJECT:== |
| | BEAVER VALLEY POWER STATION - NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT NOS. |
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| | 05000334/2018410 AND 05000412/2018410 |
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| ==Dear Mr. Bologna:== | | ==Dear Mr. Bologna:== |
| On June 1 5, 201 8, the U.S. Nuclear Regulatory Commission (NRC) completed a n inspection at Beaver Valley Power Station, Units 1 and 2, and discussed the inspection results with you and other members of your staff. The results of this inspection are documented in the enclosed report. | | On June 15, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2, and discussed the inspection results with you and other members of your staff. The results of this inspection are documented in the enclosed report. |
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| The NRC inspectors did not identify any finding or violation of more than minor significance. | | The NRC inspectors did not identify any finding or violation of more than minor significance. |
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| This letter will be made available for public inspection and copying at http://www.nrc.gov/reading | | This letter will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding. |
| -rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding." | |
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| However, the enclosed report contains Security
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| -Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1)
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| . If you choose to provide a response that contains Security
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| -Related Information, please mark your entire response is necessary to provide an acceptable response, please mark your entire response "Security-Related Information
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| -Withhold from Public Disclosure under 10 CFR 2.390" in Enclosure contains sensitive, unclassified, non-safeguards information. When separated from the enclosure, the transmittal document is decontrolled. accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1).
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| The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii)
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| Sincerely,/RA/ Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-334 and 50-412 License Nos. DPR
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| -66 and NPF-73 Non-Public
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| ===Enclosure:===
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| NRC Inspection Report Nos. 05000334/201 8 4 1 0 and 05000412/201 8 4 1 0 (OUO-SRI) cc w/o encl; w/o OUO
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| -SRI: Distribution via ListServ cc w/encl; w/OUO
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| -SRI: M. Fox, Manager, Site Protection , FENOC, Beaver Valley Station D. Allard, State Liaison Officer, PA DEP C. Salz, State Liaison Officer, State of Ohio J. Frame, State Liaison Officer Designee, State of West Virginia
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| ML18194A460 (Cover letter)
| | However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from Public Disclosure under 10 CFR 2.390 in Enclosure contains sensitive, unclassified, non-safeguards information. When separated from the enclosure, the transmittal document is decontrolled. accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii). |
| ADAMS ACCESSION NUMBER:
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| ML1 8194A468 (Cover letter w/enclosure)
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| Cover Letter:
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| SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available Cover Letter w/
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| ===Enclosure:===
| | Sincerely, |
| SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME MOrr MYoung/SWS MGray DATE 07/10/2018 07/10/2018 07/12/2018 | | /RA/ |
| | Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-334 and 50-412 License Nos. DPR-66 and NPF-73 Non-Public Enclosure: |
| | NRC Inspection Report Nos. 05000334/2018410 and 05000412/2018410 (OUO-SRI) |
| | cc w/o encl; w/o OUO-SRI: Distribution via ListServ cc w/encl; w/OUO-SRI: |
| | M. Fox, Manager, Site Protection, FENOC, Beaver Valley Station D. Allard, State Liaison Officer, PA DEP C. Salz, State Liaison Officer, State of Ohio J. Frame, State Liaison Officer Designee, State of West Virginia ML18194A460 (Cover letter) |
| | ADAMS ACCESSION NUMBER: ML18194A468 (Cover letter w/enclosure) |
| | Cover Letter: Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available Cover Letter w/ Enclosure: Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME MOrr MYoung/SWS MGray DATE 07/10/2018 07/10/2018 07/12/2018 |
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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
uly 12, 2018
SUBJECT:
BEAVER VALLEY POWER STATION - NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT NOS.
05000334/2018410 AND 05000412/2018410
Dear Mr. Bologna:
On June 15, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2, and discussed the inspection results with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from Public Disclosure under 10 CFR 2.390 in Enclosure contains sensitive, unclassified, non-safeguards information. When separated from the enclosure, the transmittal document is decontrolled. accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).
Sincerely,
/RA/
Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-334 and 50-412 License Nos. DPR-66 and NPF-73 Non-Public Enclosure:
NRC Inspection Report Nos. 05000334/2018410 and 05000412/2018410 (OUO-SRI)
cc w/o encl; w/o OUO-SRI: Distribution via ListServ cc w/encl; w/OUO-SRI:
M. Fox, Manager, Site Protection, FENOC, Beaver Valley Station D. Allard, State Liaison Officer, PA DEP C. Salz, State Liaison Officer, State of Ohio J. Frame, State Liaison Officer Designee, State of West Virginia ML18194A460 (Cover letter)
ADAMS ACCESSION NUMBER: ML18194A468 (Cover letter w/enclosure)
Cover Letter: Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available Cover Letter w/ Enclosure: Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME MOrr MYoung/SWS MGray DATE 07/10/2018 07/10/2018 07/12/2018