IR 05000334/2022010
| ML22131A393 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/12/2022 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Grabnar J Energy Harbor Nuclear Corp |
| Gray M | |
| References | |
| IR 2022010 | |
| Download: ML22131A393 (7) | |
Text
May 12, 2022
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000334/2022010 AND 05000412/2022010
Dear Mr. Grabnar:
On April 19, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. The NRC inspectors discussed the results of this inspection with you and other members of your staff on April 1 and April 19, 2022. 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, Mel Gray, Chief Engineering Branch 1 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:
05000334/2022010 and 05000412/2022010
Enterprise Identifier: I-2022-010-0044
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Beaver Valley Power Station
Location:
Shippingport, PA
Inspection Dates:
March 14, 2022 to April 19, 2022
Inspectors:
P. Cataldo, Senior Reactor Inspector
L. Dumont, Reactor Inspector
J. Kulp, Senior Reactor Inspector
D. Werkheiser, Senior Reactor Analyst
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Beaver Valley Power Station, 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.
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.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Determined whether the sampled power-operated valves (POVs) are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Determined whether the sampled POVs are capable of performing their design-basis functions.
c. Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluate maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) MOV-1FW-151D, 1B Steam Generator Auxiliary Feedwater Throttle Valve
- (2) MOV-1RW-102C2, 1C River Water Pump Discharge Valve
- (3) MOV-1SI-860B, 1B Low Head Safety Injection Pump Containment Sump Suction Isolation Valve (4)2QSS*MOV101A, 21A Quench Spray Pump Discharge Isolation Valve (5)2RCS*MOV536, Power-Operated Relief Valve (2RCS*PCV456) Isolation Valve (6)2SWS*MOV113D, 21B Emergency Diesel Generator Service Water Cooling Water Inlet Valve
- (7) HYV-1FW-100C, 1C Steam Generator Main Feedwater Containment Isolation Valve
- (8) TV-1MS-105B, B-Train Auxiliary Feedwater Turbine Steam Supply Trip Valve (9)2FWE*HCV100A, 21C Steam Generator Auxiliary Feedwater Throttle Valve (10)2MSS*SOV105A, A-Train Turbine-Driven Auxiliary Feedwater Pump Steam Line Isolation Valve
- (11) MOV-1FW-160, Dedicated Auxiliary Feedwater Pump Discharge Isolation Valve
INSPECTION RESULTS
No findings of more than minor safety significance were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 1, 2022, the inspectors debriefed on the design basis assurance inspection (programs) inspection results with Mr. John Grabnar, Site Vice President, and other members of the licensee staff, with inspection continuing regarding one sample involving component MOV-1FW-160.
- On April 19, 2022, the inspectors completed an exit meeting with Ms. Julie Hartig, Regulatory Compliance Supervisor.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Corrective Action
Documents
Resulting from
Inspection
CR-2022-02328
CR-2022-02329
CR-2022-02330
CR-2022-02336
CR-2022-02374
CR-2022-02548
CR-2022-02599
CR-2022-02606
CR-2022-02608
CR-2022-02818
CR-2022-02854
Miscellaneous
8700-DQC-0195
Qualified Life and Post Accident Operability -
FlowServe/Edward Valves Model A-180 Main Feedwater
Isolation Valve Actuators
FAQ 10-0059
NFPA 805 Monitoring
Procedures
1/2-ADM-1900
1/2-ADM-1908
Fire Protection Performance Monitoring Program
1/2-PMP-E-75-
20
Limitorque MOV Inspection and Test
8700-DMC-2780
Determination of Max Differential Pressure Across the QA
Cat 1 MOVs in the BVPS-1 Feedwater System (FW)
NOBP-SS-1217
Cyber Security Control of Portable Media and Mobile
Devices
NOP-ER-3004
Work Orders
200592599
Repair/Repack MOV-1FW-160