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Category:Inspection Report
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 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) IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports 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 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 IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 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) IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 ML23157A1072023-06-0707 June 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011 IR 05000334/20230012023-05-0808 May 2023 Integrated Inspection Report 05000334/2023001 and 05000412/2023001 L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report IR 05000334/20230102023-03-0808 March 2023 Biennial Problem Identification and Resolution Inspection Report 05000334/2023010 05000412/2023010 IR 05000334/20220062023-03-0101 March 2023 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2022006 and 05000412/2022006) IR 05000334/20220042023-02-0909 February 2023 Integrated Inspection Report 05000334/2022004 and 05000412/2022004 IR 05000334/20224012023-01-0909 January 2023 Security Baseline Inspection Report 05000334/2022401 and 05000412/2022401 (Cover Letter Only) ML22314A2682022-12-16016 December 2022 – Review of the Fall 2021 2R22 Steam Generator Tube Inspection 180 Day Report IR 05000334/20220032022-11-10010 November 2022 Integrated Inspection Report 05000334/2022003 and 05000412/2022003 and Independent Spent Fuel Storage Installation Inspection Report 07201043/2022001 IR 05000334/20220052022-08-31031 August 2022 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2022005 and 05000412/2022005) IR 05000334/20220022022-08-12012 August 2022 Integrated Inspection Report 05000334/2022002 and 05000412/2022002 IR 05000334/20224022022-08-12012 August 2022 Cyber Security Problem Identification and Resolution Inspection Report 05000334/2022402 and 05000412/2022402 (Cover Letter Only) IR 05000334/20225012022-06-29029 June 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2022501 and 05000412/2022501 IR 05000334/20220112022-06-29029 June 2022 Temporary Instruction 2515/194 Inspection Report 05000334/2022011 and 05000412/2022011 IR 05000412/20223012022-06-14014 June 2022 Initial Operator Licensing Examination Report 05000412/2022301 IR 05000334/20224202022-05-11011 May 2022 Security Baseline Inspection Report 05000334/2022420 and 05000412/2022420 - Cover Letter IR 05000334/20220012022-05-10010 May 2022 Integrated Inspection Report 05000334/2022001 and 05000412/2022001 IR 05000334/20210062022-03-0202 March 2022 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2021006 and 05000412/2021006) IR 05000334/20210042022-02-14014 February 2022 Integrated Inspection Report 05000334/2021004 and 05000412/2021004 L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022 Steam Generator Inspection Report- Fall 2021 Refueling Outage IR 05000334/20220102022-01-13013 January 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010 IR 05000334/20210032021-11-0909 November 2021 Integrated Inspection Report 05000334/2021003 and 05000412/2021003 IR 05000334/20210112021-10-19019 October 2021 Temporary Instruction 2515/194 Inspection Report 05000334/2021011 and 05000412/2021011 IR 05000334/20210102021-09-29029 September 2021 Triennial Fire Protection Inspection Report 05000334/2021010 and 05000412/2021010 IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) IR 05000334/20214022021-08-18018 August 2021 Security Baseline Inspection Report 05000334/2021402 and 05000412/2021402 IR 05000334/20214012021-08-12012 August 2021 Material Control and Accounting Program Inspection Report 05000334/2021401 and 05000412/2021401 (Cover Letter Only) IR 05000334/20210022021-08-11011 August 2021 Integrated Inspection Report 05000334/2021002 and 05000412/2021002 IR 05000334/20214032021-05-13013 May 2021 Cyber Security Problem Identification and Resolution Inspection Report 05000334/2021403 and 05000412/2021403 (Cover Letter Only) IR 05000334/20210012021-05-13013 May 2021 Integrated Inspection Report 05000334/2021001 and 05000412/2021001 2024-08-05
[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
ril 11, 2019
SUBJECT:
BEAVER VALLEY UNITS 1 AND 2 - PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000334/2019010 AND 05000412/2019010
Dear Mr. Bologna:
On March 21, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Beaver Valley Units 1 and 2. On March 21, 2019, the NRC inspectors discussed the results of this inspection with R. Pennfield, General Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Matthew R. Young, Chief Projects Branch 6 Docket Nos.: 05000334 and 05000412 License Nos.: DPR-66 and NPF-73
Enclosure:
Inspection Report 05000334/2019010 and 05000412/2019010
Inspection Report
Docket Numbers: 05000334 and 05000412 License Numbers: DPR-66 and NPF-73 Report Numbers: 05000334/2019010 and 05000412/2019010 Enterprise Identifier: I-2019-010-0004 Licensee: FirstEnergy Nuclear Operating Co.
Facility: Beaver Valley, Units 1 and 2 Location: Shippingport, PA 15077-0004 Inspection Dates: March 04, 2019 to March 21, 2019 Inspectors: J. Brand, Reactor Inspector S. Elkhiamy, Reactor Inspector J. Krafty, Senior Resident Inspector S. Shaffer, Senior Project Engineer Approved By: Matthew R. Young, Chief Projects Branch 6 Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a problem identification and resolution inspection at Beaver Valley Units 1 and 2 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations No findings were identified.
Additional Tracking Items None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness - The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems.
- Operating Experience, Self-Assessments and Audits - The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits, and self-assessments.
- Safety Conscious Work Environment - The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Observation The inspectors reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the inspectors determined FENOCs performance in each of these areas supported nuclear safety.
The inspectors also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments. Based on the samples reviewed, the inspectors determined that FENOCs performance in each of these areas supported nuclear safety.
Finally, the inspectors reviewed the stations programs to establish and maintain a safety conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the inspectors observations and the results of these interviews, the inspectors found no evidence of challenges to the organizations safety conscious work environment. A cross section of FENOC employees were interviewed, and all stated a willingness to raise nuclear safety concerns through at least one of the several means available.
Observation 71152B Operating Experience Screening Process is not consistently implemented in accordance with the requirements of NOBP-LP-2100, FENOC Operating Experience Process. Specifically, in accordance with step 4.1.2 the screening process provides for three possible outcomes: Not applicable, Information only, or Evaluation, all of which require documenting justification. The inspectors noted many examples while reviewing Operating Experience where screening documentation was not provided nor justification made for not evaluating in accordance with station procedures. In one case, OE-2017-0236, FW heater control, met the criteria for an evaluation since it affects plant reliability or availability (i.e. reactivity management level 4 event and plant power excursion), however no screening or justification was documented.
Contributing to the inconsistent application of requirements may be vague or interpretative guidance.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On March 21, 2019, the inspector presented the Biennial Problem Identification and Resolution Inspection to Mr. Rod Penfield and other members of the licensee staff.
DOCUMENTS REVIEWED
Procedures
NOP-LP-2001, Corrective Action Program, Revision 46
NOBP-LP-2011, FENOC Cause Analysis, Revision 25
1/2OM-56B.4A.E, Unit 1/2 Safe Shutdown Intent and Methodology, Revision 0
NORM-OP-1002, Conduct of Operations, Revision 7
NOBP-LP-2100, FENOC Operating Experience Process, Revision 18
1/2-ADM-0600, Environmental Protection Programs, Revision 5
1/2-ADM-0605, Control of Water and Wastewater Disposal and Draining Activities, Revision 7
1/2OM-35.4A.A, voltage Schedule Guidance, Revision 15
2OST-30.13B, Train B Service Water System Full Flow Test, Revision 45
2OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification,
Revision 20
Condition Reports
CR-2018-08406 CR-2017-01830 CR-2016-12107 CR-2018-00709
CR-2018-07052 CR-2017-01836 CR-2017-02305 CR-2018-01542
CR-2018-04735 CR-2017-06990 CR-2017-04022 CR-2018-01549
CR-2017-04023 CR-2017-02410 CR-2017-04146 CR-2018-02456
CR-2017-05260 CR-2017-02493 CR-2017-04211 CR-2018-03372
CR-2018-03574 CR-2018-08392 CR-2017-05270 CR-2018-04780
CR-2017-08308 CR-2016-13722 CR-2017-05721 CR-2018-05063
CR-2018-06128 CR-2017-05957 CR-2017-06376 CR-2018-07447
CR-2018-10075 CR-2017-01836 CR-2017-07506 CR-2018-07760
CR-2016-13722 CR-2016-14253 CR-2017-08205 CR-2018-07933
CR-2017-08406 CR-2017-02997 CR-2017-10327 CR-2018-08299
CR-2016-13722 CR-2017-08406 CR-2017-10852 CR-2018-08730
CR-2016-14253 CR-2018-04285 CR-2017-10857 CR-2018-10384
CR-2017-00036 CR-2017-09825 CR-2017-11030 CR-2018-10653
CR-2017-02997 CR-2009-62810 CR-2017-11191 CR-2018-11228
CR-2018-07262 CR-2013-15679 CR-2017-11220 CR-2019-00075
CR-2018-08392 CR-2015-05473 CR-2017-12308 CR-2019-00264
CR-2018-08311 CR-2015-11473 CR-2018-00258 CR-2019-00851
CR-2018-06843 CR-2016-00190 CR-2018-00283 CR-2019-01418
CR-2018-11224 CR-2016-03633 CR-2018-00470
CR-2017-12282 CR-2016-10087 CR-2018-00665
Miscellaneous Documents
Standing Order 18-006
OE-2018-0136, IN1803 Operating Experience Regarding Failure to meet TS Requirements
Changing Conditions
OE-2017-0349, Feedwater Heater Level Control Valve Failure to Control Level
IN1804, Failure of Operators to trip the Plant when experiencing unstable conditions.
SA-BN-2017-0614, 2R19 Shutdown Defense in Depth Post Outage Critique
SA-BN-2017-0595, 2017 Semi- Annual EPlan Health Physics Drill #1- 6/13/17
OFO-2018-0012, 2018 Emergency Preparedness Audit
IER L1-17-5, Line of Sight to the Reactor Core
SA-BN-2017-0766, Beaver Valley 2016 Annual Snap Shot Assessment on Clearance Process,
Procedure and Practices.
ATA 2019-2685
ATA-2018-1216
B-062B, Safeguards Area Ventilation - Loads and Air Rates, Revision 3
B-244. Evaluation of Capacity of 2HVR-ACU-207A, B (Safeguard Area), Revision 1
DCP-1604, Test Package for IWP #1604-1, Revision 0
DMC-3606, Isokinetic Flow Assessment and Penetration of Airborne Particles for RM-1VS-109,
RM-1VS-110, and RM-1GW-109, Revision 0
DMC-3811, Beaver Valley Unit 2 Safeguards building Heatup Analysis Using MAAP-DBA,
Revision 0
ECP-17-0389, Isokinetic Flow Assessment and Penetration of Airborne Particles for
RM-1VS-109, RM-1VS-110, and RM-1GW-109, Revision 0
EER 600965045
EER 601191559
EER 601191560
EER 601206768
Inservice Testing Program Health Report 2014 through 2018
MS-C-18-01-13, Design Control, Engineering Programs and ASME
N-785, Minimum Service Water Pressure Setpoint to Protect SWS Pumps - Emergency Diesel
Test Acceptance Curves, Revision 2
N-800, Minimum Service Water Flow Requirements for the Unit 2 Emergency Diesel Generator
Coolers, Revision 0
N-864, Service Water System Performance Calculation, Revision 0
OE-2017-0561, IN 1706 Battery and Short Circuits on DC Systems
Pennsylvania Department of Environmental Protection Letter Dated April 12, 2017
SA-BN-2017-0626, Tier 1 Calculations Self Assessment
SA-BN-2018-1139, NOP-ER-3001 Problem Solving and Decision Making
SA-BN-2018-1298, Pre-PI&R 2019 NRC Inspection Assessment
SA-BN-2019-1326, Snapshot SA-CSA Owner JFG
Standing Order 13-014
Unit 2 Control Room Logs July 17, 2017
Unit 2 Service Water System Health Report 2014 through 2018