IR 05000280/2024010
| ML24275A217 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/02/2024 |
| From: | Matthew Fannon Division Reactor Projects II |
| To: | Carr E Virginia Electric & Power Co (VEPCO) |
| References | |
| IR 2024010 | |
| Download: ML24275A217 (8) | |
Text
SUBJECT:
SURRY POWER STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000280/2024010 AND 05000281/2024010
Dear Eric S. Carr:
On August 29, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Surry Power Station and discussed the results of this inspection with David Wilson, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight Process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
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.
October 2, 2024 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, Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000280 and 05000281
License Numbers:
Report Numbers:
05000280/2024010 and 05000281/2024010
Enterprise Identifier:
I-2024-010-0039
Licensee:
Virginia Electric and Power Company
Facility:
Surry Power Station
Location:
Surry, VA
Inspection Dates:
August 12, 2024 to August 29, 2024
Inspectors:
M. Donithan, Senior Operations Engineer
D. Jung, Resident Inspector
G. Khouri, Construction Project Manager
J. Seat, Senior Project Engineer
Approved By:
Matthew S. Fannon, Chief
Reactor Projects Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting a biennial problem identification and resolution inspection at Surry
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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution
Biennial Team Inspection (IP Section 03.04) (1 Sample)
(1)
The inspectors performed a biennial assessment of the effectiveness of the licensees
Problem Identification and Resolution program, use of operating experience, self-
assessments and audits, and safety conscious work environment.
Problem Identification and Resolution Effectiveness: The inspectors assessed
the effectiveness of the licensees Problem Identification and Resolution
program in identifying, prioritizing, evaluating, and correcting problems. The
inspectors also conducted a five-year review of the alternate alternating
current power, emergency diesel generator, and safety injection systems. The
corrective actions for the following non-cited violations (NCVs) were evaluated
as part of the assessment: 2022003-01, 2022003-02, 2022004-01, 2022004-
02, 2022004-03, 2023001-01, 2023001-02, 2023002-01, 2023002-02,
2023004-01, 2023004-02, 2024001-01, and 2024002-01.
Operating Experience: The inspectors assessed the effectiveness of the
licensees processes for use of operating experience.
Self-Assessments and Audits: The inspectors assessed the effectiveness of
the licensees identification and correction of problems identified through
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
Assessment
PI&R Assessment
1. Corrective Action Program Effectiveness
Problem Identification: The inspectors determined that the licensee was effective in
identifying problems and entering them into the corrective action program and there was a
low threshold for entering issues into the corrective action program. This conclusion was
based on a review of the requirements for initiating condition reports as described in licensee
procedure PI-AA-200, "Corrective Action," and managements expectation that employees
were encouraged to initiate condition reports. Additionally, site management was actively
involved in the corrective action program and focused appropriate attention on significant
plant issues.
Problem Prioritization and Evaluation: Based on the review of condition reports, the
inspectors concluded that problems were prioritized and evaluated in accordance with the
condition report significance determination guidance in procedure PI-AA-200. The inspectors
determined that adequate consideration was given to system or component operability and
associated plant risk. The inspectors determined that plant personnel had conducted cause
evaluations in compliance with the licensees corrective action program procedures and
cause determinations were appropriate, and considered the significance of the issues being
evaluated.
Corrective Actions: Based on a review of corrective action documents, interviews with
licensee staff, and verification of completed corrective actions, the inspectors determined that
corrective actions were timely, commensurate with the safety significance of the issues, and
effective, in that conditions adverse to quality were corrected. For significant conditions
adverse to quality, the corrective actions directly addressed the cause and effectively
prevented recurrence. The inspectors reviewed condition reports and effectiveness reviews to
verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews
for corrective actions to preclude repetition were sufficient to ensure corrective actions were
properly implemented and were effective.
Based on the samples reviewed, the team determined that the licensees corrective action
program complied with regulatory requirements and self-imposed standards. The licensees
implementation of the corrective action program adequately supported nuclear safety.
2. Operating Experience
The inspectors determined that the station's processes for the use of industry and NRC
operating experience information were effective and complied with all regulatory requirements
and licensee standards. The implementation of these programs adequately supported nuclear
safety. The inspectors concluded that operating experience was adequately evaluated for
applicability and that appropriate actions were implemented to address lessons learned as
needed.
3. Self-Assessments and Audits
The inspectors determined that the licensee was effective at performing self-assessments
and audits to identify issues at a low level, properly evaluated those issues, and resolved
them commensurate with their safety significance. Self-assessments were generally detailed
and critical. The inspectors verified that condition reports were created to document areas for
improvement and findings resulting from self-assessments, as well as verified that
actions had been completed consistent with those recommendations. Audits of the quality
assurance program appropriately assessed performance and identified areas for
improvement. Generally, the licensee performed evaluations that were technically accurate.
4. Safety Conscious Work Environment
Based on interviews with plant staff and reviews of the latest safety culture survey results to
assess the safety conscious work environment on site, the inspectors found no evidence of
challenges to the safety conscious work environment. Employees appeared willing to raise
nuclear safety concerns through at least one of the several means available.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 29, 2024, the inspectors presented the biennial problem identification and
resolution inspection results to David Wilson, Site Vice President, and other members of
the licensee staff.