IR 05000334/2025002
| ML25216A250 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, 07201043 |
| Issue date: | 08/05/2025 |
| From: | Matt Young Division of Operating Reactors |
| To: | Blair B Vistra Operations Company |
| References | |
| IR 2025002, IR 2025001 | |
| Download: ML25216A250 (1) | |
Text
August 5, 2025
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2025002 AND 05000412/2025002, AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07201043/2025001
Dear Barry Blair:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On July 7, 2025, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Beaver Valley Power Station, Units 1 and 2.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; and the NRC Resident Inspector at Beaver Valley Power Station, Units 1 and 2. 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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety
Docket Nos. 05000334, 05000412, and
07201043 License Nos. DPR-66 and NPF-73
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000334, 05000412, and 07201043
License Numbers:
Report Numbers:
05000334/2025002, 05000412/2025002, and 07201043/2025001
Enterprise Identifier: I-2025-002-0041 and
I-2025-001-0099
Licensee:
Vistra Operations Company, LLC
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA
Inspection Dates:
April 01, 2025 to June 30, 2025
Inspectors:
N. Day, Senior Resident Inspector
A. Nugent, Resident Inspector
C. Borman, Health Physicist
J. Demarshall, Senior Operations Engineer
T. Fish, Senior Operations Engineer
C. Hargest, Health Physicist
A. Kostick, Health Physicist
J. Lilliendahl, Senior Emergency Response Coord
S. Mercurio, Sr Emergency Preparedness Inspector
R. Rolph, Senior Health Physicist
Approved By:
Matt R. Young, Chief
Projects Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Beaver Valley Power Station, 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.
List of Findings and Violations
Failure to Establish, Implement, and Maintain Procedure for Surveillance Testing Emergency Diesel Generator 2-1 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000412/2025002-01 Open/Closed
[H.12] - Avoid Complacency 71111.24 A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1A, Procedures, was identified for failure to establish, implement, and maintain Step 30 of procedure 2OST-36.1, "Emergency Diesel Generator [2EDGS*EG2-1]
Monthly Test," during a routine surveillance test to ensure the availability and reliability of the 2-1 emergency diesel generator (EDG). Specifically, during a run of EDG 2-1, the 30 second load timer for reverse power was exceeded, causing an unplanned trip of EDG 2-1.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000412/2025-001-00 LER 2025-001-00 for Beaver Valley Power Station, Unit 2,
Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System due to Loose Feedback Linkage on Feedwater Regulating Valve 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On May 24, 2025, the unit was down powered to approximately 55 percent power to repair steam generator feedwater regulatory valves. On May 26, 2025, the unit returned to full power. The unit operated at or near rated thermal power for the remainder of the inspection period.
Unit 2 operated at or near rated thermal power for the entire inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather for forecasted severe thunderstorms on April 29, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2, component cooling water heat exchangers trains 'A', 'B', and 'C', April 1, 2025
- (3) Unit 2, EDG 2-1 starting air system, June 9, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1, normal switchgear room and motor generator room, fire areas NS-1 and MG-1, April 16, 2025
- (2) Unit 1, west safeguards, fire area PT-1, May 29, 2025
- (3) Unit 1, service building 722' cable tray mezzanine, fire area CS-1, June 18, 2025
- (4) Unit 2, EDG 2-1 room, fire area DG-1, June 30, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on April 23, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Partial)
The inspectors evaluated readiness and performance of:
(1)
(Partial)
Unit 2, primary component cooling water heat exchanger 'B' following cleaning and tube plugging, May 19, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exams administered April through May 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations
The inspectors evaluated the quality of the licensed operator biennial requalification written examinations administered February through March 2025.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the facility licensees annual requalification operating tests administered April through May 2025.
Administration of an Annual Requalification Operating Test
The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during down power to 95 percent for steam generator narrow range water level calibration on April, 25, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operators in the Unit 1 simulator on May 8, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 2, safety injection system, June 17, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample 1 Partial)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 1, planned downpower to support 'A' main feedwater regulating valve maintenance, May 23 - 25, 2025 (2)
(Partial)
Work schedule changes due to grid demand, June 27, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1, steam generator oscillations due to main feedwater regulation valve demand changes described in Condition Report (CR) 2025-02712, April 22, 2025
- (2) Unit 2, rod control urgent lockout alarm described in CR 2025-03111, April 24, 2025
- (3) Unit 2, EDG 2-2 starting air system operability determination, June 6, 2025
- (4) Unit 1, 'B' auxiliary feedwater pump operability determination after discovery of gland seal leakage, June 24, 2025
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (3 Samples)
- (1) Unit 1, 'B' component cooling water pump 'B' test following maintenance, per 1OST-15.2, April 30, 2025
- (2) Unit 2, motor-driven auxiliary feedwater pump 'A' test following maintenance, per 2OST-24.2, May 7, 2025
- (3) Unit 1, reactor river water 'C' comprehensive pump test following maintenance, per 1OST-30.6A, May 13, 2025
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) Unit 2, Loop 3 Channel 2 steam generator narrow range water level, per 2MSP-24.24-I, April 25, 2025
- (3) Unit 2, auxiliary service water pump 'B', per 2OST-30.1B, June 27, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1, low head safety injection pump 'B', per 1OST-11.2, June 23, 2025
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) Vistra onsite emergency responders participated in a simulated explosion and fire exercise scenario which damaged the spent fuel pool in order to demonstrate the extensive damage mitigation guidelines described in 10 CFR 50.155(b)(2) as required by 10 CFR 50, Appendix E.IV.F.2.j, on May 7, 2025.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the licensee's maintenance and testing of the station alert and notification system on May 5 - 8, 2025, for the period of July 2023 through April 2025.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the licensee's Emergency Preparedness Organization on May 5 - 8, 2025.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
- BV-2025-005-00, Update to include additional Dry Cask Design; EPP-PLAN-SECTION-4, Emergency Conditions-Emergency Action Level Bases, Revision 37; EPP-l-1a.F01 Beaver Valley Unit 1 EAL Wallboard, Revision 7; EPP-I-1b.F01 Beaver Valley Unit 2 EAL Wallboard, Revision 5
- BV-2025-004-00, EPP-PLAN Section 7, Emergency Facilities and Equipment, Update to Phone services-Removal of T-1 carrier
- BV-2024-016-00, Vesta to Everbridge Software Change (ERONS)
This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program on May 5 - 8, 2025, for the period of July 2023 through April 2025.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Red Team drill, May 8, 2025
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated the proposed scenario that demonstrates the extensive damage mitigation guidelines described in 10 CFR 50.155(b)(2) as required by 10 CFR 50, Appendix E.IV.F.2.j, on April 2,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements. [Document incomplete or discontinued elements of the GPI per IMC 0611-12]
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1, April 1, 2024 through March 31, 2025
- (2) Unit 2, April 1, 2024 through March 31, 2025
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1, April 1, 2024 through March 31, 2025
- (2) Unit 2, April 1, 2024 through March 31, 2025
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1, April 1, 2024 through March 31, 2025
- (2) Unit 2, April 1, 2024 through March 31, 2025
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1, 2024 through March 31, 2025
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2024 through March 31, 2025
EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
This is a new NRC performance indicator, introduced in NEI 99-02, Revision 8 (ML24331A114). Licensees began collecting data for this performance indicator on January 1, 2025.
- (1) January 1, 2025 through March 31, 2025
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in feedwater that might be indicative of a more significant safety issue.
The inspectors noted that over the past two years there have been several plant transients due to the health of the steam generator feedwater system. The licensee is managing the current issues via procedural changes, operational decision making instructions, and adverse condition monitoring plans and have long-term corrective actions scheduled to restore system degradation (e.g. Unit 1 main feedwater regulatory valve modifications and Unit 2 steam generator replacements).
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2025-001-00, Unit 2 Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System due to Loose Feedback Linkage on Feedwater Regulating Valve (ADAMS Accession No. ML25092A162). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified.
Personnel Performance (IP Section 03.03) (2 Samples)
- (1) The inspectors evaluated operator response to a spurious fire alarm inside Unit 2 containment and licensees performance per 1/2-ADM-1900 on April 8, 2025.
- (2) The inspectors evaluated licensee response to an event on May 11,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===60854 - Preoperational Testing of an ISFSI
The inspectors evaluated the licensee's Independent Spent Fuel Storage Installation (ISFSI)activities performed to fulfill the pre-operational requirements of the HI-STORM FW Certificate of Compliance (CoC) #1032, Amendment 7, from April 7 - 10, 2025, April 21 - 24, 2025, May 12 - 15, 2025, and June 2 - 5, 2025. Specifically, the inspectors observed the following activities:
Preoperational Testing of an ISFSI===
(1)
- Multi-purpose container (MPC) lid to shell welding and non-destructive examination
- MPC port cover welding and non-destructive testing
- MPC closure ring welding and non-destructive testing
- Installation of MPC RVOA assemblies
- Demonstration of MPC reflooding and alternate cooling
- MPC hydrostatic testing
- MPC blowdown
- MPC vacuum drying
- MPC gas sampling and depressurization
- Stack-up and download of MPC from HI-TRAC to HI-STORM
- Upload of MPC from HI-STORM to HI-TRAC
- HI-STORM lid installation
- Transportation of HI-STORM to the ISFSI pad via HI-PORT and HI-TRAN
- Installation of empty MPC into HI-TRAC
- Flooding of MPC cavity
- Installation of HI-TRAC into CLP
- Dummy Fuel Assembly Loading into MPC
- Installation of MPC Lid
- Removal of MPC Lid
- Removal of HI-TRAC from CLP
- HI-TRAC Decontamination
===60855 - Operation of an ISFSI
The inspectors evaluated the licensee's ISFSI dry storage cask loadings from June 16 - 20, 2025. Specifically, the inspectors observed the following activities for Cask #1 of the ISFSI campaign:
Operation of an ISFSI===
(1)
- Fuel selection and fuel loading
- Heavy load movement of the MPC, transfer cask (loaded and unloaded), and overpack
- Drying and backfill evolutions
- Closure welding and non-destructive weld evaluations
- Transfer evolutions
- Radiological field surveys
===60856 - Review of 10 CFR 72.212(b) Evaluations
The inspectors evaluated the licensee's written evaluations compliance with the requirements of 10 CFR 72.212 associated with the HI-STORM FW CoC #1032, Amendment 7, from March 3, 2025 through June 20, 2025. Specifically, the inspectors reviewed and assessed the following:
Review of 10 CFR 72.212(b) Evaluations===
(1)
- Written evaluations demonstrating compliance with the requirements of 10 CFR 72.212(b)(2)-(b)(6) for the use of the HI-STORM FW storage system
- 10 CFR 72.212(b)(3) site-specific evaluations, including assessments of potential design basis accidents, natural phenomena hazards, and cask drop accident scenarios
- 10 CFR 72.212(b)(5) evaluations to verify these evaluations properly addressed the technical specifications and conditions of use described in CoC
- 1032 Amendment 7
- Engineering analyses supporting the seismic, structural, and thermal performance of the HI-STORM FW storage system at the site
- Records demonstrating the implementation of changes permitted under 10 CFR 72.48, including screenings and evaluations
- Licensee programs and procedures to ensure consistency with the terms, conditions, and specifications of the general license and CoC
INSPECTION RESULTS
Failure to Establish, Implement, and Maintain Procedure for Surveillance Testing Emergency Diesel Generator 2-1 Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000412/2025002-01 Open/Closed
[H.12] - Avoid Complacency 71111.24 A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1A, Procedures, was identified for failure to establish, implement, and maintain Step 30 of procedure 2OST-36.1, "Emergency Diesel Generator [2EDGS*EG2-1]
Monthly Test," during a routine surveillance test to ensure the availability and reliability of the 2-1 emergency diesel generator (EDG). Specifically, during a run of EDG 2-1, the 30 second load timer for reverse power was exceeded, causing an unplanned trip of EDG 2-1.
Description:
On May 13, 2025, during a monthly surveillance test, an operator in license candidate training was at the controls during the syncing of 2-1 EDG with the grid. While conducting Step 30 of procedure 2OST-36.1, the procedure directed to manipulate the 2-1 emergency diesel governor control switch intermittently to raise generator output to 450 kilowatts (KWs). While performing this step, the operator instead mistakenly manipulated the 2-1 emergency diesel voltage adjust switch, causing the unit supervisor to declare an all-stop, pausing any manipulations of the governor control switch. Due to this pause, Step 30 was not accomplished in a timely manner and a 30 second timer elapsed for reverse power protection, causing the output breaker to automatically open to protect the diesel generator.
The diesel generator was declared inoperable and unavailable.
On May 14, 2025, 2OST-36.1 was performed successfully and the 2-1 EDG was returned to service.
The licensee promptly entered this issue into their corrective action program.
Corrective Actions: Following the EDG tripping, the protective relays were reset and the 2-1 EDG was returned to available status. On May 14, 2025, 2OST-36.1 was performed successfully and the 2-1 EDG was declared operable and returned to service. Longer term corrective actions include: performing a causal evaluation to determine and correct procedure detail, and enhancements to address prolonging the time the diesel output breaker is closed and loading the diesel to 450 KW.
Corrective Action References: CR-2025-03639
Performance Assessment:
Performance Deficiency: The failure to timely load a diesel generator following closure of the output breaker is a performance deficiency. Specifically, this failure led to the elapsing of the 30 second timer and actuation of the reverse power trip protection, causing a trip of the 2-1 EDG.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, all questions in Section A of Exhibit 2, "Mitigating Systems Screening Questions," were answered no, therefore, the finding screened as Green significance.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, not understanding the consequences of stopping while in the middle of a procedure was an added risk causing the performance deficiency to occur.
Enforcement:
Violation: Technical Specification 5.4.1A, states, in part, that written procedures shall be established, implemented, and maintained covering the following activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Section 8.b.1.q of Appendix A of Regulatory Guide 1.33, requires written surveillance procedures for emergency power tests (e.g., EDGs).
Revision 89 of station procedure 2OST-36.1, "Emergency Diesel Generator [2EDGS*EG2-1]
Monthly Test, was written to perform the startup, operation, and shutdown of the EDG 2-1 during monthly surveillance testing. Step 30 of the procedure requires the 2-1 emergency diesel governor control to be used to intermittently raise to 450 KW.
Contrary to the above, on May 13, 2025, while implementing Step 30 of 2OST-36.1, the operator failed to manipulate the emergency diesel governor control switch causing an unplanned trip of the 2-1 EDG.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 7, 2025, the inspectors presented the integrated inspection results to Barry Blair, Site Vice President, and other members of the licensee staff.
- On May 8, 2025, the inspectors presented the emergency preparedness program inspection results to Barry Blair, Site Vice President, and other members of the licensee staff.
- On June 26, 2025, the inspectors presented the radiological environmental monitoring program inspection results to Sean Denny, Director, Nuclear Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
10080-RM-0415-
001
Valve Oper No Diagram Primary Component Cooling Water
Revision 20
10080-RM-436-2
Valve Oper No Diagram Diesel Air Intake, Exh & Vacuum
Revision 4
RM-0436-001
Valve Oper No Diagram Emergency Diesel Generator Air
Start System
Revision 12
Miscellaneous
Maintenance Rule System Basis Document - Safety Injection
System, System 11
Revision 7
List of Station Functional Failures as of June 16, 2025
06/16/2025
Corrective Action
Documents
CR-2025-03773
Increased Oscillations of 'A' Main Feed Reg Valve - FCV-
05/18/2025
Corrective Action
Documents
CR-2025-04222
2EGA-DRY21B, Diesel Start Air Dryer, Low Refrigerant
Condition, Resulted in 2-2 Diesel Low Air Starting Pressure
06/06/2025
Miscellaneous
Beaver Valley Emergency Preparedness 2025 ERO Severe
Accident Management Guideline (SAMG) Evaluator Tabletop
03/03/2025
BVPS Emergency Preparedness Plan
Revision 17
Miscellaneous
Beaver Valley Power Station Alert and Notification System
Design Report
Revision 5
Corrective Action
Documents
Resulting from
Inspection
25-03466
25-03472