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Integrated Inspection Report 05000338/ 2022001 and 05000339/2022001 and 07200056/2022001
	ML22132A308
Person / Time
Site:	North Anna
Issue date:	05/13/2022
From:	Matthew Endress; Division Reactor Projects II
To:	Stoddard D; Virginia Power (Virginia Electric & Power Co)
References
	IR 2022001
	Download: ML22132A308 (28)
	v • d • e

May 13, 2022

SUBJECT:

NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2022001 AND 05000339/2022001 AND 07200056/2022001

Dear Mr. Stoddard:

On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On April 25, 2022, the NRC inspectors discussed the results of this inspection with Ms. Lisa Hilbert, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

Two findings of very low safety significance (Green) are documented in this report. Both findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. 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 violations or the significance or severity of the violations 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 North Anna 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.

Sincerely, Signed by Endress, Matthew on 05/13/22 Matthew F. Endress, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000338 and 05000339 and 07200056 License Nos. NPF-4 and NPF-7

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000338 and 05000339 and 07200056 License Numbers: NPF-4 and NPF-7 Report Numbers: 05000338/2022001; 05000339/2022001; and 07200056/2022001 Enterprise Identifier: I-2022-001-0034 and I-2021-001-0155 Licensee: Virginia Power & Electric Company Facility: North Anna Power Station Location: Mineral, VA Inspection Dates: January 1, 2022 to March 31, 2022 Inspectors: K. Carrington, Senior Resident Inspector J. England, Senior Resident Inspector (Acting)

L. Jones, Senior Reactor Inspector D. Lanyi, Senior Operations Engineer A. Rosebrook, Senior Reactor Analyst M. Schwieg, Senior Reactor Inspector J. Seat, Senior Project Engineer B. Towne, Resident Inspector J. Viera, Senior Operations Engineer A. Wilson, Senior Project Engineer Approved By: Matthew F. Endress, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at North Anna 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. A licensee-identified non-cited violation is documented in report section: 71111.11

List of Findings and Violations

Failure to Translate the Licensing Basis into Instructions for Fuel Handling Activities Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green None (NPP) 60855 NCV 05000338,05000339/2022001-01 Open/Closed The inspectors identified a Green, non-cited violation (NCV) of Title 10, Code of Federal Regulations Part 50, Appendix B, Criterion III, Design Control, for the licensees failure to assure that the design basis was correctly translated into procedures and instructions.

Specifically, the inspectors identified that the licensee failed to translate the maximum cask lift elevation and the locking of the trunnion axis into site procedures.

Inadequate Cable Separation for Vital AC Bus Control Power and Monitoring Circuits Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71153 Systems NCV 05000339/2022001-02 Open/Closed The NRC identified a Green, non-cited violation of 10 CFR Part 50, Appendix R, due to inadequate cable separation of safety-related control power cables routed through common fire areas. The design change process review for NA-13-00016, "Station Service Bus to Emergency Bus Crosstie Installation," failed to identify the violation of Appendix R requirements and a modification was installed on Unit 2 in 2013. The design review was a reasonable opportunity to identify the condition also existed on Unit 1.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power for the entire inspection period.

Unit 2 began the inspection period operating at 100 percent rated thermal power until entering its end of cycle coast down on February 27, 2022. On March 5, Unit 2 was shut down for refuel outage 2R28 and remained shut down for the rest 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 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

71111.01 - 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 cold temperatures for the station blackout diesel generator and service water systems, on January 3, 2022.

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather [snow and low temperatures],

from January 13 to 14, 2022.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2 'H' emergency diesel generator (EDG) system during 2J EDG system maintenance, on January 14, 2022;

(2) Unit 1 service water system, following Unit 2 service water pump run and the No. 4 auxiliary service water pump maintenance, the week of February 7, 2022;

(3) Unit 1 and Unit 2 vital 125-volt direct current (VDC) buses, in response to Surry condition report (CR)1190494, the week of February 14, 2022;

(4) Unit 1 and Unit 2 shared fuel pit cleaning and refueling and purification system during Unit 2 core offload, on March 16, 2022; and

(5) Unit 2 'J' EDG system during 2H 4160-volt emergency bus maintenance and prior to 2H EDG post-maintenance run, on March 17, 2022.

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 low head safety injection system, from March 28 to March 31, 2022.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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) Fire Area 3-1, Unit 1 cable vault and tunnel and 280' rod drive room, on January 12, 2022;

(2) Fire Area 8, Unit 1 and Unit 2 turbine building, on January 21, 2022;

(3) Fire Area Z18, Unit 1 and Unit 2 fuel building, on January 27, 2022;

(4) Fire Area 5-2, Unit 2 normal switchgear room, on March 16, 2022;

(5) Fire Area 4-2, Unit 2 cable tray spreading room, on March 16, 2022;

(6) Fire Area 12, service water pump house, on March 16, 2022; and

(7) Fire Area 48, service water valve house, on March 16, 2022.

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

Main article: IP 71111.08

(1) The inspectors evaluated the following pressurized water reactor non-destructive examinations from March 13 to March 17, 2022:

Visual Inspections:

Pressurizer auxiliary spray piping restraint 2-CH-R-1 Ultrasonic Examination Thermal sleeve tack welds SLV 12-422 Thermal sleeve tack welds SLV 14-410 Thermal sleeve tack welds SLV 06-417 Thermal sleeve tack welds SLV 06-419 Liquid Penetrant Examination Reactor coolant safe end to elbow 6-RC-437.

The inspectors evaluated the licensees boric acid control program performance.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)

(1) Biennial Requalification Written Examinations Inspectors evaluated the quality of licensed operator biennial requalification written examinations administered on February 4 and February 25, 2021.

Annual Requalification Operating Tests Inspectors evaluated the quality of annual licensed operator requalification operating examinations administered the weeks of January 10 and January 24, 2022.

Inspectors performed an as-run evaluation of the facility licensees annual requalification operating test the week of January 24, 2022.

Administration of an Annual Requalification Operating Test Inspectors evaluated the effectiveness of the facility licensee in administering and evaluating facility staff during annual requalification operating tests required by 10 CFR 55.59(a)(2).

Requalification Examination Security Inspectors evaluated the effectiveness of the facility licensee's requalification examination security measures.

Remedial Training and Re-examinations Inspectors evaluated the effectiveness of remedial training conducted by the licensee and reviewed the adequacy of re-examinations for licensed operators who did not pass their required requalification examination.

Operator License Conditions Inspectors evaluated individual licensed operator records to verify appropriate and effective processes for ensuring conformance with operator license conditions.

Control Room Simulator Inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution Inspectors evaluated the licensees ability to identify and resolve problems associated with both licensed operator and simulator performance.

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 main control room during Unit 2 shutdown for Refuel Outage (RFO) 2R28, on March 5, 2022.

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

(1) The inspectors observed and evaluated operator requalification scenario SXG-29, on March 1, 2022, and just-in-time training for RFO 2R28, on March 2, 2022.

71111.12 - Maintenance Effectiveness

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 2 reactor coolant pump seals associated with work order (WO) 5920332554; and Unit 2 safety injection motor-operated valve 2869B associated with purchase order

===4500629735.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) ===

Main article: IP 45006

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) 500 KV switchyard transformer 6 bushing fire, on January 3, 2022;

(2) Unit 2 charging pump planned maintenance, on February 17, 2022;

(3) Unit 2 reactor cavity drain down and decreased inventory, the week of March 9, 2022;

(4) Shared 1A fuel pit cooling system pump gearbox oil bubbler found empty with core offloaded, on March 23, 2022; and

(5) Tornado watch and Unit 2 refueling cavity drain down activities, on March 31, 2022.

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) CR1188767, Conflicting Status Indications of Train A Reactor Trip Bypass Breaker, on January 11, 2022;

(2) CR1190093, 1-BY-BC-1-1 [Battery Charger] Ground Worsening, on February 11, 2022;

(3) CR1190294, 10M Windspeed and Backup Tower Windspeed [Sensors] Not Responding, on February 14, 2022;

(4) CR1193750, 2-RS-129 (2-RS-MOV-256B Inlet Vent Valve) requires Repair, on March 22, 2022; and

(5) CR1194625, During 2-PT-36.13J Auxiliary Relay 27XC-2J1 Did Not Pick Up, on March 24, 2022.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Design Change NA-18-00096, Valve Removal from 1H EDG Crankcase Pressure Sensing Line.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) 2-PT-82.2B, 2J emergency diesel generator test following planned maintenance, on January 15, 2022;

(2) 2-SI-MOV-2890B valve operator as-left test following planned maintenance, on March 21, 2022;

(3) Post-maintenance testing following 2H1-2N-K1 motor control center bucket replacement, on March 23, 2022; and

(4) 2-IV station battery performance discharge test following replacement, on March 25, 2022.

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 (RFO) 2R28 activities from March 5 toMarch 31, 2022.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (5 Samples)

(1) 2-PT-17.1, Control Rod Operability, on February 22, 2022;

(2) 2-PT-83.1, Simulated Loss of Offsite Power (LOOP) and ESF Actuation - H Bus, on March 6, 2022;

(3) 2-PT-57.4, Safety Injection Operational Test, on March 7, 2022;

(4) 2-PT-96.1, Refueling Systems Operability and Checkout, on March 10, 2022; and

(5) 2-PT-88.3J, Station Battery 2-III Modified Performance Test, on March 23, 2022.

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 1-PT-71.1, 1-FW-P-2, Turbine Driven Auxiliary Feedwater Pump, IST Comprehensive Pump Test and Valve Testing, on February 22, 2022.

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) 2-PT-61.3, Containment Type C Test [Penetration 106 - Safety Injection Accumulator Test line to RWST Isolation Valve], on March 15,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

Main article: IP 71151