IR 05000280/2024004
| ML25036A124 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/06/2025 |
| From: | James Baptist NRC/RGN-II/DORS |
| To: | Carr E Virginia Electric & Power Co (VEPCO) |
| References | |
| IR 2024004 | |
| Download: ML25036A124 (10) | |
Text
SUBJECT:
SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2024004 AND 05000281/2024004
Dear Eric S. Carr:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station. On January 16, 2025, the NRC inspectors 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.
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, James B. Baptist, Chief Projects Branch 4 Division of Operating Reactor Safety 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:
05000280/2024004 and 05000281/2024004
Enterprise Identifier:
I-2024-004-0026
Licensee:
Virginia Electric and Power Company
Facility:
Surry Power Station
Location:
Surry, VA
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
W. Deschaine, Senior Project Engineer
M. Donithan, Senior Operations Engineer
J. Hickey, Senior Project Engineer
D. Jung, Resident Inspector
S. Kennedy, Senior Resident Inspector
G. Smith, Senior Resident Inspector
D. Turpin, Resident Inspector
J. Vasquez, Construction Project Inspector
Approved By:
James B. Baptist, Chief
Projects Branch 4
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated 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.
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection period.
Unit 2 began the inspection period at rated thermal power. On October 27, 2024, the unit was
shut down for a planned refueling outage. The unit was placed online on December 7, 2024,
and remained at or near rated thermal power for the remainder of the 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 seasonal cold temperatures for the following systems:
Unit 1 refueling water storage tank
Unit 2 refueling water storage tank
Unit 1 emergency condensate storage tank
Unit 2 emergency condensate storage tank
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
Unit 2 residual heat removal (RHR) system walkdown following plant cool down on
October 20, 2024
(2)
Unit 2 reactor coolant system level instrumentation during drain down to lowered
inventory on October 31, 2024
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)
Mechanical equipment rooms No.1 and No. 2, fire areas 45 and 54, elevation 9 feet -
6 inches, on October 9, 2024
(2)
Unit 2 reactor containment, fire area 16, elevation 47 feet - 4 inches; elevation 18
feet - 4 inches; elevation (-) 3 feet - 6 inches; and elevation (-) 27 feet - 7 inches, on
October 31, 2024
(3)
Auxiliary building, fire area 17, elevation 27 feet - 6 inches, on December 11, 2024
71111.08P - Inservice Inspection Activities (PWR)
The inspectors reviewed the reactor coolant system boundary, reactor vessel internals, risk-
significant piping system boundaries, and containment boundary to verify if they were
appropriately monitored for degradation and that repairs and replacements were appropriately
fabricated, examined and accepted by reviewing the following activities in unit 2 during refueling
outage 2R32 from November 4th to November 8th.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities
were performed appropriately:
(1)
Ultrasonic Examination
1.
11548-WMKS-RC -R-1.3/S1 - S58, reactor vessel head closure studs, ASME
XI, 2019, Report No. ISI-2-UT-24-017
Dye Penetrant Examination
1.
1158-WMKS-0122A1/12-SI-247/H003-1, integral attachment on pipe
connecting accumulator to cold leg on loop 3, ASME Section XI, 2019Ed,
Report No. ISI-2-PT-24-002
Visual # Examination
1.
11548-WMKS-RC - 1.4/N1 through N58, reactor vessel head closure nuts,
ASME XI, 2019, Report No. ISI-2-VT-24-034
2.
11548-WMKS-0122A1, Pipe Support, ASME XI, Inspection Reports: ISI-2-VT-
24-046, ISI-2-VT-24-044, and ISI-2-VT-24-045
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 Walkdown - November 5, 2024.
Review of boric acid evaluations:
CR/WO No.: CR1247872
CR/WO No.: CR1255776
Review of corrective action documents associated with identified boric acid leaks:
CR 1274263
CR 1274264
CR 1274265
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial
written examinations required to be administered to all licensed operators in accordance
with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification
Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office
review of the overall pass/fail results of the individual operating examinations, the crew
simulator operating examinations, and the biennial written examinations in accordance with
Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program and
Licensed Operator Performance." These results were compared to the thresholds
established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
(1)
The inspectors reviewed and evaluated the licensed operator examination failure
rates for the requalification annual operating exams completed March 8, 2024, and
the biennial written examinations also completed March 8, 2024.
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 2 shut down for refueling outage, 2R32, on October 26 and 27,
2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the
classroom and simulator during licensed operator requalification training involving 1-
AP-10.20, Response to Spurious Safety Injection with Reactor Coolant Temperature
<350 degrees Fahrenheit, on October 9, 2024.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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 2 shutdown risk plan in preparation for 2R32 refueling outage on October 23,
2024
(2)
Unit 2 elevated shutdown risk due to N-31, source range nuclear instrument, out of
service on October 29 and 30, 2024
(3)
Shutdown risk due to full core offload to the spent fuel pit on November 7, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
CR1269884, Potential through wall leak upstream of 2-SW-544, recirculation spray
heat exchanger B flow transmitter isolation valve, on September 25, 2024
(2)
CR1274129, Waste gas decay tank high oxygen on November 4, 2024
(3)
CR1277013, Flow induced vibration during testing of 2-RH-E-1A, Unit 2 A residual
heat removal heat exchanger, on November 26, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Unit 2 refueling outage 2R32 activities from October 27,
2024, to December 6, 2024. The inspectors completed inspection procedure
71111.20, except Section 03.01(e).
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) (4 Samples)
(1)
2-OPT-EG-009, Number 2 Emergency Diesel Generator Major Maintenance
Operability Test, following 18-month preventive maintenance activities on November
6 and 7, 2024
(2)
2-OPT-RH-002, Stroke Test of the RHR System Motor Operated Valve, following
valve stem maintenance on 2-RH-MOV-2720A, RHR outlet valve, on November 17,
2024
(3)
2-OPT-RH-002, Stroke Test of the RHR System Motor Operated Valve, following
valve stem maintenance on 2-RH-MOV-2720B, RHR outlet valve, on November 17,
2024
(4)
2-OPT-RH-001, Stroke Test of 2-RH-FCV-2605 and 2-RH-HCV-2758, RHR heat
exchanger bypass flow control valve and RHR heat exchanger flow control valve,
following actuator maintenance on both valves on November 20, 2024
Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
2-OPT-ZZ-001-OTO-1, '2H' Logic Bus Test, on October 29, 2024
(2)
2-PT-41.2, Cold Shut Down Test of Component Cooling Check Valves and Trip
Valves for Residual Heat Removal Heat Exchangers and Reactor Coolant Pumps, on
November 22, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
2-OPT-CT-201, Containment Isolation Valve Local Leak Rate Testing (Type C
Containment Testing), on December 11, 2024
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 (July 2023, through September 2024)
(2)
Unit 2 (July 2023, through September 2024)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
(1)
Unit 1 (July 2023, through September 2024)
(2)
Unit 2 (July 2023, through September 2024)
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)
1-CH-P-1A, Unit 1 'A' charging pump, junction box failure (CA12426377)
71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective actions program and related
documents such as trend reports, licensee performance indicators, and system health
reports for potential adverse trends that might be indicative of a more significant
safety issue.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 7, 2024, the inspectors presented the inservice inspection results to
James Shell, Plant Manager, and other members of the licensee staff.
On January 16, 2025, the inspectors presented the integrated inspection results to David
Wilson, Site Vice President, and other members of the licensee staff.
THIRD PARTY REVIEWS
Inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the
inspection period.