IR 05000334/2025004
| ML26028A061 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/28/2026 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Blair B Vistra Operations Company |
| References | |
| IR 2025004 | |
| Download: ML26028A061 (0) | |
Text
January 28, 2026
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2025004 AND 05000412/2025004
Dear Barry Blair:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On January 12, 2026, 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.
No findings or violations of more than minor significance were identified during this inspection.
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 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Glenn T. Dentel, Acting Chief Projects Branch 2 Division of Operating Reactor Safety
Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000334 and 05000412
License Numbers:
Report Numbers:
05000334/2025004 and 05000412/2025004
Enterprise Identifier: I-2025-004-0041
Licensee:
Vistra Operations Company, LLC
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA
Inspection Dates:
October 1, 2025 to December 31, 2025
Inspectors:
N. Day, Senior Resident Inspector
A. Nugent, Resident Inspector
P. Cataldo, Senior Reactor Inspector
B. Dyke, Senior Operations Engineer
R. Rolph, Senior Health Physicist
C. Henckel, Operations Engineer
Approved By:
Glenn T. Dentel, Acting 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On August 7, 2025, the unit started
coast down operations for the upcoming Unit 1, refueling outage 30. The unit was shut down for
refueling outage 30 on October 12, 2025. The unit was returned to rated thermal power on
November 25, 2025, and remained 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 DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to
the onset of extreme cold for the following systems:
Unit 2, service water underground valve pits on December 1, 2025
Unit 1, emergency diesel generators (EDGs) on December 2, 2025
Units 1 and 2, turbine buildings on December 2, 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 1, 1-1 EDG starting air system, December 2, 2025
(2)
Unit 2, 'A' auxiliary feedwater following completion of Unit 2 23B auxiliary feedwater
pump test per 2OST-24.3, December 9, 2025
(3)
Unit 2, diesel fuel oil system, trains 'A' and 'B' following restoration from licensee
inspection of Unit 2 EDG 2-2 fuel oil transfer pump per Drawing RM-0436-001,
December 10, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 2, fan room, cable spreading area, west communication room, and
instrumentation and relay area, fire areas 2-CB-5, 3-CR-1, 2-CB-4, 2-CB-1, and
2-CB-6, October 2, 2025
(2)
Units 1 and 2, intake structure, fire areas 3-IS-1, 3-IS-2, 3-IS-3, 3-IS-4, and 3-IS-6,
December 1, 2025
(3)
Unit 2, safeguards building 737' elevation, fire areas 2-SG-1S and 2-SG-1N,
December 3, 2025
71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified, through remote document review following the government shutdown,
that the reactor coolant system (RCS) boundary, reactor vessel internals, risk-significant piping
system boundaries, and containment boundary are appropriately monitored for degradation and
that repairs and replacements were appropriately fabricated, examined, and accepted by
reviewing the following activities at Beaver Valley Unit 1, during refueling outage 1R30, from
November 17 through December 12, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination (NDE) and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities
were performed appropriately:
(1)
American Society of Mechanical Engineers (ASME)Section XI Repair and
Replacement (R&R) activity, for replacement of Class 2 river water piping
segment WR-87, under order 200956059, including welding, phased array
ultrasonic testing (UT) of welds F01, F03, and F04, and radiographic testing
(RT) of weld F02; NDE reports for UT contained in IIA Report No. 25-01-434
and RT contained in TEAM Report No. 1100-006602-01-CR-1Jl
Class I Volumetric UTs of reactor coolant butt weld RC-71-8-S-02 (NDE
Report UT-BV-1R30-025), safety injection butt weld SI-260-1502-Q1 (NDE
Report UT-BV-1R30-021) and safety injection butt weld SI-261-1502-Q1 (NDE
Report UT-BV-1R30-022)
Remote UT of ten (10), remaining thermal shield support block bolts
(Westinghouse NDE Report WDI-PJF-353109-NDE-002)
Remote Enhanced Visual Inspection (EVT-1) of Rx Vessel Internals (thermal
shield support block bolts, 330 degree thermal shield flexure, and core barrel
upper girth weld); Westinghouse NDE Report WDI-PJF-353109-EPP-001,
Revision 1
General Visual examination of the containment liner and moisture barrier
under 1BVT-1.47.1, Containment Structural Integrity Test, Revision 18, Work Order 200924126, and Condition Report (CR)-2025-07827
- Augmented visual examination of reactor vessel bottom-mounted
instrumentation nozzles, based on ASME Code Case N-722, Category B15.80
(NDE Report VT-BV-1R30-017) and Category B15.100 (NDE Report VT-BV-
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head
penetration inspections and addressed any identified defects appropriately:
(1)
Visual examination based on ASME Code Case N-729-6, of penetrations 48
and 55 (Westinghouse NDE Report WDI-PJF-352692-NDE-002)
Volumetric examination of 62 reactor pressure vessel head penetrations,
based on ASME Code Case N-729-6 and applicable requirements of Title 10
of the Code of Federal Regulations 50.55a
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities
(IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program
through a review of the following evaluations:
(1)
Boric acid evaluation and corrective actions for 1RC-241 (CR-2025-07257)
Boric acid evaluation and corrective actions for 1RC-459 (CR-2025-07266)
Boric acid evaluation and corrective actions for the 1B residual heat removal
heat exchanger (CR-2025-07908)
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 Unit 1 requalification annual operating exam completed on April 3, 2025.
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 the Unit 1 plant shutdown for 1R30 on October 12, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated "just in time" operator simulator training
session for the Unit 1 shutdown preparations for 1R30 on October 9, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
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 1, containment, system 47, October 7, 2025
(2)
Unit 1, river water, system 30, December 12, 2025
(3)
Unit 1, rod control and protection system, system 1, December 15, 2025
(4)
Unit 1, 4KV electrical, system 36, December 17, 2025
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to
ensure the following SSC remains capable of performing its intended function:
(1)
Unit 1, hydraulic oil for feedwater isolation system evaluated for equivalency via
Notification (NOTF) 601507590, November 13, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
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, Yellow risk window for decay heat removal during 1R30, October 15, 2025
(2)
Unit 1, plant protection scheme for low heat safety injection pump B unavailability,
December 12, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
Unit 1, residual heat removal flow control valve due to flow fluctuation as described in
CR 2025-08052, October 28, 2025
(2)
Unit 1, transition to Mode 4 using Limiting Condition for Operation (LCO) 3.0.4.b with
inoperable recirculation spray train 'A', November 18, 2025
(3)
Unit 1, turbine driven auxiliary pump run differential pressure during Mode 3 following
refueling outage per CR 2025-08780 during 1OST-24.9, November 19, 2025
(4)
Units 1 and 2, operability determination for Unit 1, RCS pressure detector and Unit 2,
main steam pressure detector following Part 21 notification from Rosemount Nuclear
Instruments made on November 25, 2025, per CR 2025-09136, December 4, 2025
(5)
Unit 2, turbine driven auxiliary feedwater pump alignment per Licensing
Requirements Manual Table 3.6.1-1 for inoperable 2MSS-SOV105D per CR 2025-
008799, December 15, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Limited Use Change to 1OM-7.4.A to allow isolation of the RCP seal injection header
during CVCS startup in order to fill reactor cavity with charging pumps for refueling,
rather than the low head safety injection pumps, on October 18, 2025
(2)
Temporary plant power due to replacement of transformer 1-9 via design equivalent
change package 23-1030-003, October 14, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated Unit 1 refuel outage 30, from October 12 to
November 20, 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) (6 Samples)
(1)
Unit 1, EDG 1-2 following outage maintenance per 1OST-36.2, October 22, 2025
(2)
Unit 1, EDG 1-1 following outage maintenance per 1OM-36.AV, 1OM-36.4.AM, and
operability evaluation in CR 2025-8381, November 7, 2025
(3)
Unit 1, recirculation spray heat exchanger 'C' minimum wall weld repair and welding
NDE per Work Order 200984933, November 10, 2025
(4)
Unit 1, recirculation spray heat exchanger 'A' post tube sheet plugging pressure
testing per Work Order 200986227, November 12, 2025
(5)
Unit 1, type B test of river water outlet piping mechanical expansion joint from
recirculation spray heat exchanger 'A' following replacement of mechanical expansion
joint and heat exchanger outlet piping per Work Order 200956058, November 17,
2025
(6)
Unit 1, EDG 1-1 run following maintenance on the 1A fuel transfer pump per 1OST-
36.1, December 16, 2025
Surveillance Testing (IP Section 03.01) (1 Sample)
(1)
Unit 1, low head safety injection pump 'B' quarterly test per 1OST-11.2 on
December 11, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Unit 2, low head safety injection pump test per 2OST-11.2, October 7, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
Unit 1, containment penetration 17 which underwent local leakage rate testing per
1OST-47.116 on October 22, 2025
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of
radiation levels, identifies the concentrations and quantities of radioactive materials,
and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related
radiological hazards and the radiation protection requirements intended to protect
workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and
controlling contamination and radioactive material:
(1)
Licensee surveys of potentially contaminated material leaving the Unit 2 radiologically
controlled area
(2)
Workers exiting the Unit 1 radiologically controlled area
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following
radiological work:
(1)
Transfer Canal decontamination
(2)
Reactor Head and Internals moves
(3)
Reactor Head inspections
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very
(1)
Unit 1, Chemical and Volume Control Tank Room
(2)
Unit 2, Chemical and Volume Control Tank Room
(3)
Dry Drum Storage area
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section
03.06) (1 Sample)
(1)
The inspectors evaluated licensee records to determine radiation worker and
radiation protection technician performance as it pertains to radiation protection
requirements.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
(1)
Unit 1 (October 1, 2024 through September 30, 2025)
(2)
Unit 2 (October 1, 2024 through September 30, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
(1)
Unit 1 (October 1, 2024 through September 30, 2025)
(2)
Unit 2 (October 1, 2024 through September 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
October 1, 2024 through September 30, 2025
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual
Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample
(IP Section 02.16) (1 Sample)
(1)
October 1, 2024 through September 30, 2025
71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1)
The inspectors reviewed CR-2025-00331, CR-2025-08345, CR-2025-08462, and CR-
2025-08674 and corrective action procedures to assess the effectiveness of the
licensee in prioritizing and evaluating the quench spray QS-1 piping leak and
repairs. The inspectors focused on the extent of condition reviews performed via
NDEs for similar piping.
71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
Following multiple minor transient combustible storage issues, the inspectors
reviewed the licensees corrective action program to identify potential trends in
storage of combustible materials that might be indicative of a more significant safety
issue.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this
report.
- On January 12, 2026, the inspectors presented the integrated inspection results to
Barry Blair, Site Vice President, and other members of the licensee staff.
On December 12, 2025, the inspectors presented the Refueling Outage 1R30 Inservice
inspection results to Hope Gilliam, Manager of Regulatory Compliance, and other
members of the licensee staff.
On December 18, 2025, the inspectors presented the RP PI Verifications inspection
results to Barry Blair, Site Vice President, and other members of the licensee staff.
On December 18, 2025, the inspectors presented the Radiological Hazard Assessment
and Exposure Control inspection results to Barry Blair, Site Vice President, and other
members of the licensee staff.