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Integrated Inspection Report 05000280/2023003 and 05000281/2023003
	ML23296A031
Person / Time
Site:	Surry
Issue date:	10/25/2023
From:	Matthew Fannon; Division Reactor Projects II
To:	Carr E; Virginia Electric & Power Co (VEPCO)
References
	IR 2023003
	Download: ML23296A031 (1)
	v • d • e

SUBJECT:

SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2023003 AND 05000281/2023003

Dear Eric S. Carr:

On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station. On October 16, 2023, 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.

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 II; the Director, Office of Enforcement; and the NRC Resident Inspector at Surry Power Station.

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 II; and the NRC Resident Inspector at Surry Power Station.

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.

October 25, 2023

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:

DPR-32 and DPR-37 Report Numbers:

05000280/2023003 and 05000281/2023003 Enterprise Identifier:

I-2023-003-0031 Licensee:

Virginia Electric and Power Company Facility:

Surry Power Station Location:

Surry, VA Inspection Dates:

July 01, 2023 to September 30, 2023 Inspectors:

P. Gresh, Operations Engineer D. Jung, Resident Inspector S. Kennedy, Senior Resident Inspector J. Tornow, Physical Security Inspector B. Towne, Senior Resident Inspector J. Walker, Senior Emergency Preparedness Inspector A. Wilson, 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 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

Transient Combustibles Stored in Restricted Areas Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000280,05000281/2023003-01 Open/Closed

[P.3] -

Resolution 71152A The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation (NCV) of License Condition 3.I, Fire Protection, associated with the licensee's failure to implement and maintain in effect, the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR), which resulted in storage of transient combustibles within restricted or combustion free zones in various areas of Unit 1 and Unit 2.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire 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

71111.04 - 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) Diverse and flexible coping strategies beyond design basis equipment in the equipment dome on August 7, 2023 (2)

1 emergency diesel generator following routine surveillance on September 12, 2023

(3) Control room ventilation following failure of 1-VS-MOD-103C, control room supply isolation motor operated damper, on September 25, 2023

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) Security central alarm station, elevation 27 feet, on July 20, 2023

(2) Unit 1 safeguards building valve room and low head safety injection pump cubes, elevations 27 feet, 19 feet, and 12 feet, on August 10, 2023

(3) Fire pump house, elevation 27 feet, on August 13, 2023

(4) Unit 1 cable vault penetration area, elevation 15 feet, on August 24, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) Fire brigade drill performance observation for unannounced simulated fire in Unit 2 turbine building basement from the B instrument air compressor, on August 15, 2023

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification training involving a scenario which included a loss of all instrument and station air requiring a manual reactor trip and emergency boration on September 13, 2023.

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 1 and Unit 2 switchgear rooms backflow preventer valves

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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 and Unit 2 emergent risk assessment due to 'A' emergency service water pump emergent fuel oil line repair on July 31, 2023

(2) High risk plan assessment for replacement of electronic module in Unit 1 turbine control system on August 3, 2023

(3) Unit 1 and Unit 2 elevated risk due to #2 emergency diesel generator and canal level probe testing on September 18, 2023

(4) Unit 1 and Unit 2 elevated risk due to the alternate AC diesel maintenance on September 26, 2023

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) Condition Report (CR) 1232411, Unit 1 boric acid transfer pump failure of 1-CH-FI-1180, boric acid filter outlet flow indicator, on July 3, 2023

(2) CR1234395, 1-VS-AC-2, Unit 1 control room air handling unit, high current readings on July 31, 2023

(3) CR1234933, Unit 2 C charging pump discharge sample valve, 2-SS-HCV-203C, failed to close during performance of 2-NPT-CH-003, In-service Inspection of 2-CH-P-1C, on August 7, 2023

(4) CR1235475, Seismic support spring can to trunnion misalignment on A and B auxiliary feedwater injection headers near containment penetrations, on August 14, 2023

(5) CR1236002, Rising Unit 2 pressurizer power operated relief valve tailpipe temperatures after draining pressurizer relief tank on August 22, 2023

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) Design Equivalent Change Package SU-23-00112, Temporary Chiller for 1-VS-AC-3 Mechanical Equipment Room-2 AC Unit, on August 16, 2023

(2) Design Equivalent Change Package SU-23-00117, Isolation of Flux Thimble 2-RC-TW-R8, on September 26, 2023

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) (5 Samples)

(1)0-MOP-SW-001, Removal from Service and Return to Service of Emergency Service Water Pumps, following repair of leak on 'A' emergency service water pump fuel oil line on August 2, 2023 (2)1-OPT-SI-005, Low Head Safety Injection Pump Test, following drain and refill of the seal head tank on August 9, 2023

(3) PMT-BKR-OP-01, Breaker Operability Test, following 10-year planned refurbishment of 01-IP-BKR-15H10-CKTBRK, component cooling pump 1A circuit breaker, August 24, 2023 (4)2-IPT-CC-CW-L-202, Intake Canal Level Probe Time Response and Calibration, following cleaning of channel 3 canal level probe on September 1, 2023 (5)2-OPT-RC-11.1, 10-Year Inservice Inspection System Pressure Test of Class 1 Components Associated with the Reactor Coolant System, following installation of plug for flux thimble 2-RC-TW-R8 on September 22, 2023

Surveillance Testing (IP Section 03.01) (5 Samples)

(1)2-NPT-FW-001, Inservice Inspection System Pressure Test of the Suction Flow Path from the Fire Protection System to the Auxiliary Feedwater Pumps, on August 2, 2023 (2)2-OSP-ZZ-001, Auxiliary Shutdown Panel Functional Surveillance, on August 3, 2023 (3)2-OPT-ZZ-002, Engineered Safety Features Actuation with Undervoltage and Degraded Voltage - 2J Bus, on August 4, 2023 (4)2-OPT-CS-006, Containment Spray System Motor Operated Valve Stroke Test, on August 28, 2023 (5)0-OSP-AAC-003, 18 Month Frequency: Automatic Start Test of AAC Diesel Generator, on August 29, 2023

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of July 17, 2023. The simulated scenario began with a loose parts alarm in the lower reactor vessel, followed by a high radiation alarm from the reactor coolant system letdown radiation monitor. This met the conditions for declaring a Notice of Unusual Event. Subsequently, a steam generator tube rupture occurred resulting in the loss of reactor coolant system boundary, meeting the conditions for declaring an Alert. As the scenario progressed, a main steam safety valve on the effected steam generator failed open, meeting the conditions for a Site Area Emergency. When off-site field team readings exceeded threshold criteria, conditions for a General Emergency were met, and the Offsite Response Organizations were able to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of July 17, 2023. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) The inspectors observed and evaluated the conduct of an emergency preparedness drill on Unit 1 involving a steam generator tube rupture and a stuck open main steam safety valve resulting in a General Emergency declaration on July 18, 2023.

71114.08 - Exercise Evaluation - Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise prior to the day of the exercise.

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)===

Main article: IP 71151

(1) Unit 1 (July 2022 through June 2023)

(2) Unit 2 (July 2022 through June 2023)