IR 05000338/2022002

Integrated Inspection Report 05000338/2022002 and 05000339/2022002

ML22223A022
Person / Time
Site:	North Anna
Issue date:	08/11/2022
From:	Matthew Fannon NRC/RGN-II/DRP/RPB4
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2022002
Download: ML22223A022 (23)

Text

August 11, 2022

SUBJECT:

NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2022002 AND 05000339/2022002

Dear Mr. Stoddard:

On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On July 28, 2022, the NRC inspectors discussed the results of this inspection with Ms. Lisa Hilbert and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection.

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 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 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 Fannon, Matthew on 08/11/22 Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000338 and 05000339 License Nos. NPF-4 and NPF-7

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000338 and 05000339 License Numbers: NPF-4 and NPF-7 Report Numbers: 05000338/2022002 and 05000339/2022002 Enterprise Identifier: I-2022-002-0029 Licensee: Dominion Energy Facility: North Anna Power Station Location: Mineral, VA Inspection Dates: April 1, 2022 to June 30, 2022 Inspectors: K. Carrington, Senior Resident Inspector T. Fanelli, Senior Reactor Inspector L. Jones, Senior Reactor Inspector B. Kellner, Senior Health Physicist J. Rivera, Health Physicist A. Wilson, Senior Project Engineer Approved By: Matthew S. Fannon, 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: 71152S.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period operating at rated thermal power (RTP). On April 14, 2022, the unit experienced a high neutron flux rate, automatic, reactor trip from 100 percent RTP. The unit was restarted on April 16, 2022, and returned to rated thermal power on April 20, 2022, where it continued to operate for the remainder of the inspection period.

Unit 2 began the inspection period shutdown for a planned refueling outage. Unit 2 was restarted on April 10, 2022. The unit returned to rated thermal power on April 17, 2022, where it continued to operate 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 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.

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 extreme high temperatures for the following systems:

Station blackout diesel generator system Unit 1 auxiliary feedwater (AFW) system Unit 1 casing cooling system

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 2 turbine-driven AFW system during Unit 2 'B' motor-driven AFW (MDAFW)system planned maintenance, on April 9, 2022

(2) Unit 1 'A' and 'B' charging systems during Unit 1 'C' charging system planned maintenance, on April 26, 2022

(3) Unit 1 'A' MDAFW system during Unit 1 'B' MDAFW system planned maintenance, on April 27, 2022

(4) Unit 2 component cooling water system during Unit 1 'A' component cooling water system planned maintenance, on June 4, 2022

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) 2-FS-C-1, Unit 2 containment, elevations 262' and 291', on April 4, 2022

(2) 1-FS-S-3, Unit 1 emergency switchgear instrument rack and air conditioning rooms, service building elevation, on May 27, 2022

(3) 1-FS-QS-1, Unit 1 quench spray pump building, elevation 274', on June 27, 2022

(4) 1-FS-MS-1, Unit 1 main steam valve house, all elevations, on June 27, 2022

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Manhole 1-BLD-MBAR-4MH03, on May 25, 2022

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 2 'J' emergency diesel generator (EDG) lube oil cooler, on June 2, 2022

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 startup from Refuel Outage (RFO) 2R28, on April 9-10, 2022.

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

(1) The inspectors observed and evaluated operator performance in the plant simulator during just-in-time training for Unit 2 startup from RFO 2R28, on April 1, 2022, and Emergency Plan Drill, "NJun22EPD," on June 21, 2022.

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 2 'A' charging pump associated with a maintenance preventable functional failure on August 5, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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 containment isolation valve, 1-SI-TV-1842, stuck in the open position, on May 12, 2022

(2) Pennsylvania, New Jersey, Maryland (PJM) transmission company hot weather alert, Anticipated Transient Without a Scram mitigation system actuation circuitry (AMSAC)testing, severe thunderstorm warning, and tornado watch, on May 27, 2022

(3) PJM hot weather alert and increased seismic activity, on May 30, 2022

(4) Unit 1 power ascension from 97 to 100 percent rated thermal power and Unit 2 containment entry to investigate an increase in reactor coolant pump (RCP) seal leakage, on June 14, 2022

(5) Emergent repair of Unit 2 'J' EDG keep warm pump coupling and oil leak from Unit 2

'C' charging pump speed increaser oil gearbox, on June 16, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Various condition reports (CRs) associated with Unit 1 'H' EDG exhaust issues- past operability review, on April 1, 2022

(2) CR1195505, 2-MS-TV-211A slow to stroke open and CR1195506, 2-MS-TV-211B failed to stroke full open, on April 6, 2022

(3) Operability of Unit 1 'B' MDAFW pump following pump run, on April 27, 2022

(4) CR1197863, Station blackout diesel generator failed acceptance criteria of 0-PT-82.14, on April 28, 2022

(5) CR1201843, Unit 1 terry turbine trip throttle valve trip latch appears to be less than fully engaged, on June 16, 2022

(6) CR1201351, Small [60 drops per minute] oil leak Unit 2 'J' EDG, on June 22, 2022

(7) CR1175825, AFW motor-operated valve (MOV) and hand control valve headers pressurizing, on June 23, 2022

(8) Service water MOVs operating above nameplate voltage and current, on June 29, 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) Unit 1 'H' EDG 3-way valve removal associated with crank case vacuum pressure trips, on April 1, 2022

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) Work Order 59203300990 associated with Unit 2 service water MOV 204D testing following planned maintenance during 2R28, on April 8, 2022

(2) 1-PT-71.3Q, Unit 1 'B' MDAFW test following AFW system planned maintenance, on April 27, 2022

(3) 2-PT-138, Unit 2 low head safety injection post maintenance testing following planned maintenance during 2R28, on June 10, 2022

(4) 2-OP-6.9, Unit 2 'J' EDG slow start test following Unit 2 'J' EDG keep warm pump coupling repair, on June 16, 2022

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated RFO 2R28 activities from April 1 to April 17, 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) (2 Samples)

(1) 2-PT-64.1.1, Outside Recirculation Spray Pump 2-RS-P-2A, on April 11, 2022

(2) 2-PT-71.1Q, 2-FW-P-2, Turbine Driven Auxiliary Feedwater Pump and Valve Test, on

June 15, 2022 Inservice Testing (IP Section 03.01) (1 Sample)

(1) 2-PT-78.3B, Inservice Inspection- Residual Heat Removal System Pump 2-RH-P-1B, on June 16,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA)

(2) Workers exiting the RCA at Unit 2 during a refueling outage

(3) Workers staging and loading radioactive material and potentially contaminated equipment through the Unit 2 containment equipment hatch and exiting the RCA

Radiological Hazards Control and Work Coverage (IP Section 03.04) (5 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) As low as reasonably achievable (ALARA) Post Job Review Evaluation Number: 20-009, RWP/Task Number: 20-2251-1,2,3,4, Disassemble/Reassemble Reactor Head During U-2 2020 RFO, 01/13/2021

(2) ALARA Plan # 22-015, Repair 2-RC-MOV-2592 [2B loop stop valve], Radiation Work Permit # 22-2269

(3) ALARA Plan # 22-018, Perform NDE & ISI Exams During N2R28 U-2 2022 RFO

[High Radiation Areas and Locked High Radiation Areas], Radiation Work Permit #

22-2220

(4) North Anna Power Station 2021 Unit One Refueling Outage N1R28 ALARA Report

(5) Installation of Unit 2 upper internals (RWP 2252, Task 2, Work Order 59203323585)

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Unit 2 containment sump access hatch (Very High Radiation Area)

(2) Unit 2 containment - reactor head (on stand) access doors (4 doors) (Locked High Radiation Area)

(3) Unit 2 containment regenerative heat exchanger room (Locked High Radiation Area)

(4) Unit 2 containment 262/241 elevations - RCP motor cubes and SG loop rooms (High Radiation Area)

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Unit 1 and 2 auxiliary building ventilation system test records

(2) Main control room ventilation system test records (flowrate, HEPA, and charcoal filter testing)

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) 500 cfm HEPA Unit #18 setup for code safety removal

(2) 500 cfm HEPA Unit #27 setup for loop stop valve work

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Reviewed the whole-body count record for an individual who had facial contamination (facial Personnel Contamination Event)

(2) Reviewed the whole-body count records for a declared pregnant worker

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Multi-badging for 2-RC-MOV2592 (B Loop stop valve) internals work

(2) Reviewed monitoring records for a declared pregnant worker from 2020

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (8 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Two Telepole radiation survey meters ready for use in the instrumentation lab

(2) RO-20 ionization chamber survey meter ready for use in the instrumentation lab

(3) RadEye survey meter ready for use in the instrumentation lab

(4) An AMP-100 area monitor ready for use in the instrumentation lab

(5) Small articles monitor (SAM) at the radiologically controlled area (RCA) exit

(6) Personnel contamination monitor (PCM) at the RCA exit

(7) Portal monitor (PM) at the protected area (PA) exit

(8) Area radiation monitors (ARMs) in the auxiliary building

Calibration and Testing Program (IP Section 03.02) (15 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Count room LS-6000 liquid scintillation counter, serial no. 7065032

(2) Count room MCA detector no. 3

(3) Count room G-5000 alpha and beta counter, serial no. 121703

(4) Fast Scan Apex whole body counter

(5) AMP-100 area monitor, serial no. 5007-219/219

(6) SAM-11, serial no. 369

(7) GEM-5 PM, serial no. 1810-288-GEO-500G

(8) Telepole radiation survey meter, serial no. 6607-043

(9) RadEye-G survey meter, serial no. 30051

(10) AMS-4 continuous air monitor (CAM), serial no. 778

(11) RO-20 ionization chamber, serial no. 182AA

(12) PCM-2, serial no. 389

(13) Ludlum 2000 scalar, serial no. 310621

(14) Portable air sampler (gooseneck) no. 5630

(15) Containment High Range Radiation Monitoring System (CHRRMS) no. RMS-266 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Unit 1, Liquid waste evaporator radiation monitor, RM-LW-110

(2) Vent Stack A normal and high range effluent radiation monitor, VG-RM-179

(3) Vent Stack B normal and high range effluent radiation monitor, VG-RM-180

OTHER ACTIVITIES - BASELINE

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

MS07: High Pressure Injection Systems (IP Section 02.06) ===

(1) Unit 1 (April 1, 2021 through March 31, 2022)

(2) Unit 2 (April 1, 2021 through March 31, 2022)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (April 1, 2021 through March 31, 2022)

(2) Unit 2 (April 1, 2021 through March 31, 2022)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) March 1, 2021 through March 31.2022 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) March 1, 2021 through March 31, 2022

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the area of human performance related to implementation of the North Anna Fire Protection Program that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71152S This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: North Anna, Unit 2, Technical Specifications, Section 5.4.1, "Procedures," requires in part that procedures be established and implemented for Fire Protection Program implementation. Dominion procedure, CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe Shutdown) Program," was established for implementation of the North Anna Fire Protection Program. Attachment 2, "North Anna Power Station and Surry Power Station Program Requirements," Step 3.6.2.a, states, A fire watch will be required when any fire protection feature is degraded or declared nonfunctional, as outlined in Technical Requirements Manual (TRM). TRM 3.3.6, Condition A.1, requires in part, that a fire watch patrol be established within one hour and in accordance with TRM Table 7.1, to inspect the zone (specified in Table 3.3.6-2) with the nonfunctional equipment. TRM Table 3.3.6-2, "Unit 2 Fire Detection Instrumentation," specifies that detectors are required in the Unit 2 primary cable vault and tunnel to automatically initiate C02 or halon. TRM Table 7.1, "Compensatory Measures," specifies that for any barrier, suppression system, detection system, or passive fire protection item that is nonfunctional, establish an hourly or continuous fire watch, based on the noted number of conditions and Appendix R applicability.

Contrary to the above, from 0835 to 1400 on January 13, 2022, North Anna, Unit 2, failed to implement the requirements of its Fire Protection Program as specified by TRM 3.3.6, Condition A.1, when it did not establish a fire watch patrol for the Unit 2 cable vault and tunnel, within one hour of removing fire protection panel 1-FP-CB-97B from service, rendering the fire detection instrumentation for that zone nonfunctional.

Significance/Severity: Green. The inspectors assessed the significance of the finding using Appendix F, Fire Protection and Post-Fire Safe Shutdown SDP, and determined this issue was associated with the Fixed Fire Protection Systems category because fire watches were required to be posted as a compensatory measure for the 1-CP-97-A/B outage which impacted a fixed fire protection system. The inspectors determined a Phase 2 assessment was required since the finding could not be assigned a low degradation rating and the deficiency (reduced frequency fire watch) adversely affected the ability of the system to protect equipment important to safe shutdown. Additionally, North Anna does not have an approved fire probabilistic risk assessment available to screen the issue in accordance with Step 1.5. For the Phase 2 assessment, the inspectors conducted a bounding risk quantification using the following inputs and assumptions:

Duration factor of 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, which is based on the time that the station did not have a fire watch from the time the fire panel was deenergized until the issue was identified and corrected based upon station logs and condition reports (5.5/8760=6.28E-4)

Fire ignition frequencies for the Unit 2 cable tunnel and vault as listed in NA-NOTEBK-PRA-NAPS-FA.2 - Fire Ignition Frequencies is 5.83 E-3 Bounding values of 1.0 for adjustment factor, severity factor, and non-suppression probability Conditional core damage probability for a fire in the Unit 2 cable vault and tunnel is 6.78E-3 since TDAFW and all EDGs were available (NRC SPAR MODEL)

A fire in the Unit 2 cable vault and tunnel will result in a loss of the 2J and 2H emergency buses and control power to the EDG fuel oil transfer pumps so Unit 2 EDGs would be lost once the day tank is depleted Safe Shutdown procedures credit Unit 1 EDGs cross-connected to support Unit 2 loads. A train of MDAFW, a charging pump, and train of service water would be lost as well.

Based on the above, the inspectors determined that the change in core damage frequency is conservatively 2.48 E-8, which is of very low safety significance (i.e., Green).

Corrective Action References: CR1189272 Observation: Semi-Annual Trend Related to Fire Watch Implementation 71152S The inspectors reviewed the licensee's corrective program to determine if a potentially adverse trend existed in human performance with respect to implementation of fire watches in accordance with the station's Fire Protection Program which could be indicative of a more significant safety concern. Specifically, the inspectors reviewed the following condition reports generated over the last six months related to missed fire watches:

CR1201892, Fire watch missed for Unit 1 emergency switchgear room and cable vault and tunnel due to card reader issues; CR1200625, Fire watch stuck in auxiliary building elevator; CR1199303, Hourly fire watch missed in 2H emergency diesel generator room due to room being inaccessible; CR1193608, Hourly fire watch requirement not met; CR1191733, Service water pump house door caused fire watch delays; CR1191305, Fire watch missed due to self-reading dosimeter WACS stations being down; CR1190596, Hourly fire watch at service water pumphouse missed due to door lock issues; CR1189272, Hourly fire watch not established for U2 cable vault and tunnel; and CR1188858, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of U-2 cable vault/tunnel hourly fire watch missed.

The inspectors noted that in the aforementioned cases, the fire watches were reinstated within a reasonable timeframe and were not easily foreseeable due to equipment malfunctions or mitigating factors outside the watch's control. Since the watches were immediately reinstated at the most available opportunity in each of these cases, the issues were determined not to adversely affect nuclear safety. While the inspectors determined that the missed fire watches constituted minor violations of North Anna's Technical Specifications and Technical Requirements Manual, the inspectors noted that only one issue constituted a performance deficiency of more than minor significance. This issue is documented as a Green (very low safety significance) licensee-identified violation in this report. The inspectors continue to monitor the impact of equipment and other mitigating factors on the licensee's ability to implement its fire protection program.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On July 28, 2022, the inspectors presented the integrated inspection results to Ms. Lisa Hilbert and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 0-AP-41 Severe Weather Conditions 57

71111.04 Corrective Action CR 1171958

Documents

Corrective Action CA017909

Documents

Resulting from

Inspection

Drawings 11715-FM-079A Flow/Valve Operating Numbers Diagram Component 33

Cooling Water System North Anna Power Station Unit 2

PI N-2005-1336

Procedures 2-OP-51.1A Valve Checkoff- Component Cooling, Auxiliary Building and 24

Main Steam Valve House

71111.05 Engineering ETE-NA-2011-

Evaluations 0071

Fire Plans 1-FS-MS-1 Main Steam Valve House Unit 1

1-FS-QS-1 Quench Spray Building 274' (SG-74) Unit 1

2-FS-C-1 Loss Prevention Fire Strategy, Containment - Unit 2 Rev. 4

Miscellaneous NAS-3014

71111.07A Miscellaneous Supplemental NDE Personnel Certification Review Checklist 03/07/2022

for Employee ID: 04344

Personnel Certification Summary Record for Employee ID 11/24/2020

04344

Personnel Certification Summary Record for Employee ID: 07/25/2019

T2010

Supplemental NDE Personnel Certification Review Checklist 03/18/2022

for Employee ID: T2010

Supplemental NDE Personnel Certification Review Checklist 03/07/2022

for Employee ID: F1670

Personnel Summary Certification Record for Employee ID: 09/12/2021

F1670

71111.11Q Miscellaneous Emergency Plan Drill NJun22EPD

Reactivity Plan for N2C29 BOC Reactor Startup 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Reactivity Plan for N1C29 Dropped Rods Startup 0

71111.13 Miscellaneous Plan of Week April 1 to

June 30,

22

71111.15 Calculations 59-02-PT-213.20 Valve Inservice Testing 2-MS-TV-211A and 2-MS-TV-211B Rev. 13

ET No. ISI 02- System Stroke Time Design Requirements for Air Operated Rev. 0

0004 Valves in the North Anna Station, Units 1 and 2 Inservice

Testing Programs

Corrective Action CR 1195505 2-MS-TV-211A Slow to Stroke Open

Documents

CR 1195506 2-MS-TV-211B Failed to Stroke Open

CR1175825

CR1201351

Procedures DNES-NA- Over-Current and Voltage Phase Imbalance Analysis for 2

EE/MOV-1001 MOVs

ER-AA-IST-102 ASME IST Program - Inservice Testing of Valves Rev. 8

71111.19 Procedures 1-PT-71.3Q 1-FW-P-3B, B Motor-Driven AFEW Pump, and Valve Test 58, 59

2-OP-6.9 Slow Start and Operation of 2J Emergency Diesel Generator 40

71111.20 Miscellaneous Work Schedule for Covered Worker- Operations - Employee 03/03/2022

ID 45994 to

03/11/2022

Work Schedule for Covered Worker - Chemistry - Employee 03/07 to

IDs 93554, 43278 03/15/2022;

03/23 to

03/29/2022

Work Schedule for Covered Worker - Rad Protection/ Health 03/23/2022

Physics - Employee IDs 50609, 111372, 3383, 512, 25473, to

59818, 53062 03/29/2022

Work Schedule for Covered Worker - Security - Employee 04/11/2022

IDs 60228, 113193, 110597, 34578, 44725 to

04/20/2022

Work Schedule for Covered Workers- Maintenance- 04/03/2022

Employee IDs 68273, 44963, 1099, 51462, 61632, 82873 to

04/09/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Schedule for Covered Worker - Rad Protection/Health 03/07/2022

Physics - Employee Ids 50609, 111372, 3383, 512, 25473, to

59818 03/15/2022

N2C29 BOC Startup 0

RxManPO3.3

Procedures 1-OP-1.5 Unit Startup from Mode 3 to Mode 2 94

1-OP-1.5A Mode 3 to Mode 2 Checklist 33

2-OP-1.7 Unit Startup from Mode 3 to Mode 2 Following Refueling 38

2-OP-2.1 Unit Startup form Mode 2 to Mode 1 131

LI-AA-700 Fatigue Management and Work Hour Limits for Covered 14

Workers

71111.22 Procedures 2-PT-64.1.1 Outside Recirculation Spray Pump 2-RS-P-2A

2-PT-71.1Q 2-FW-P-2, Turbine Driven Auxiliary Feedwater Pump and

Valve Test

2-PT-78.3B Inservice Inspection- Residual Heat Removal System Pump

2-RH-P-1B

71124.01 ALARA Plans North Anna Power Station 2021 Unit One Refueling Outage

N1R28 ALARA Report

2-014 Perform Valve Maintenance To Include; Repack, Revision 0

Adjustment, Cut Out, Inspection Of Valves During N2R28

RFO

2-015 Repair 2-RC-MOV-2592, Revision 0 [including in-progress Various

review #1 & 2]

2-018 Perform NDE & ISI Exams During N2R28 U-2 2022 RFO, Various

Revision 0 [including in-progress review #1]

Corrective Action CR1155152, CR1157526, CR1157862, CR1158379, Various

Documents CR1168649, CR1168779, CR1169946, CR1170025, and

CR1172881

Miscellaneous North Anna Power Station Radiological Survey Location and 03/17/2022

Frequency (RP-AA-220, Attachment 1).

ALARA Daily Outage Report(s) - 03/15/2022 through Various

3/31/2022

Unit 2 Outage Day 2 and Day 7 dose rate assessment [2017 Various

thru 2022 containment dose rate/source term trending]

Inspection Type Designation Description or Title Revision or

Procedure Date

Station ALARA Committee Meeting Minutes (2-RV-MOV- 03/24/2022

2592 update and new dose projection)

Procedures RP-AA-201 Access Controls for High and Very High Radiation Areas Revision 10

RP-AA-202 Radiological Posting Revision 13

RP-AA-225 Unrestricted Release of Material Revision 8

RP-AA-300 ALARA Reviews and Reports Revision 10

RP-AA-5001 RP Department Survey and Surveillance Verification Revision 0

Radiation Unit 2 Upper Internal Lift Rig 03/28/2022

Surveys Temporary Reactor Vessel Cover (TRVC) pre and post Various

decontamination surveys [multiple surveys on 3/28 and

3/29/2022]

Remote Continuous Coverage Log and Stay Time Tracking 03/10/2022

Form for Unit 2 Blind Flange Removal

Unit 2 Initial Entry radiation, contamination and airborne 03/06/2022

survey(s), all elevations.

Unit 2 Transfer Canal, containment side surveys prior to Various

Blind Flange removal [including dose rate gradient

assessment]

2-RC-MOV-2592 Multiple radiation, contamination surveys for loop stop valve Various

work performed from 3/16/2022 through 3/25/2022.

2-2251-0307- Unit 2 Reactor Cavity air sample during deck plate 03/07/2022

0330 installation and Transfer Canal survey (PAPRs worn).

Analysis for beta, gamma, iodine, and alpha.

2-2252-0311- Air sample in the Unit 2 Cavity during the Reactor Head Lift 03/11/2022

0956 (respiratory protection worn (PAPH)). Analysis for beta,

gamma, iodine, and alpha.

2-2252-0311- Air sample at the Unit 2 Cavity Edge during the Reactor 03/11/2022

1014 Head Lift. Analysis for beta, gamma, iodine, and alpha.

Radiation Work 22-2015 Valve Maintenance in Radiation Areas Revision 0

Permits (RWPs) 22-2220 Perform ultrasonic, magnetic particle and liquid penetrant Revision 0

examination for the ASME Xl in service inspection program

in LHRA.

Self-Assessments Radiological Work Control Program Review November 2019 10/26/2021

- June 2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Audit 20-06 Nuclear Oversight Audit 20-06: Radiation Protection, 09/16/2020

Process Control Program, and Chemistry

71124.03 Calibration 8030084224 PortaCount Pro Model 8030 Calibration Certificate 08/09/2021

Records L01129 Posi3 USB Calibration Report, Certificate of Calibration, 07/19/2021

Certificate # 56071921L01129

L02179 Posi3 USB Calibration Report, Certificate of Calibration, 06/16/2021

Certificate # 56061621L02179

LAC174787 SCBA Pack #23 Test Record 01/28/2022

LAC182418 SCBA Pack #17 Test Record 01/31/2022

LAC182447 SCBA Pack #4 Test Record 02/01/2022

Corrective Action CR1142555, and CR1153635 Various

Documents

Miscellaneous 0-HSP-BSRD- North Anna Internal Exposure Control Program Surveillance 03/09/2021

001, Attachment - May 2020 through December 2020

0-PT-114 Emergency Kit Respirator Inspections [Quarterly, Monthly Various

emergency kit respirator inspections] - 12/19/2021,

01/13/2022, 02/27/2022, and 03/16/2022

RP-AA-163, Radiological Use SCBA Inspection Record - 12/19/2021, Various

01/13/2022, 02/15/2022, and 03/16/2022

RP-AA-226, North Anna Unit 2 Alpha Source Term Characterization for 02/15/2022

N2R28 (Routine Facility Characterization of Alpha Source

Term - North Anna Power Station, June 2020 to December

21)

Procedures HP-1033.620 Portable Air Samplers Calibration and Operation Revision 9

HP-1042.122 Quantitative Fit Testing: PortaCount Pro Fit Testing System Revision 12

HP-1042.451 Self-Contained Breathing Apparatus Maintenance Revision 5

HP-1042.520 Respiratory Protection Program Equipment Criteria and Revision 6

Verification

RP-AA-162 Issue and Control of Respiratory Protection Equipment Revision 7

RP-AA-163 Inspection and Inventory of Respiratory Protection Revision 8

Equipment

RP-AA-226 Alpha Monitoring Revision 5

RP-AA-243 Portable HEPA Ventilation Units Revision 4

Inspection Type Designation Description or Title Revision or

Procedure Date

Radiation HP-1042.510, Breathing Air Quality Verification Record [Grade D breathing Various

Surveys Attachment 3 air analysis results] for Air Compressor 2-SA-111 and 2-SA-

109 dated 03/09/2021 and 08/20/2021

HP-1042.510, Breathing Air Quality Verification Record [Grade D breathing Various

air analysis results] for Paint Shop Air Compressor dated

03/09/2021 and 08/20/2021

HP-1042.520, Respiratory Equipment Certification Record [Grade D Various

breathing air analysis results] for Diving Gas Mixture 35%

Oxygen/ Balance Nitrogen used for atmospheric

containment entry

Self-Assessments PA7793969 Internal Radiation Exposure Control Program Review 08/31/2020

2/2018 - 8/2020

Work Orders 59203296734 0-PT-77.4A, Laboratory Analysis - 1-HV-FL-3A- ECCS 02/10/2020

PREACS [Charcoal Radioiodine Sample]

203296795 0-PT-95.3, Fuel Building Ventilation - Negative Pressure 05/05/2021

Test

203316776 0-PT-77.14B, ECCS PREACS Train B Filter In-Place Test 11/03/2021

(1-HV-FL-38) [HEPA and charcoal filter test]

71124.04 Corrective Action CR1159911, CR1165985, CR1179245, and CR1183875 Various

Documents

Miscellaneous Whole Body Counter nuclide libraries [multiple libraries for Various

various counting geometries]

C-HP-1031.023, Multibadge RCA Authorization/Worksheet(s) [three 03/16/2022

individuals working on the loop stop valve internals]

NVLAP LAB National Voluntary Laboratory Accreditation Program 07/01/2010

CODE: 100555-0 Certificate of Accreditation to ISO/IEC 17025:2005 through

06/30/2021

NVLAP LAB National Voluntary Laboratory Accreditation Program 07/01/2019

CODE: 100555-0 Certificate of Accreditation to ISO/IEC 17025:2005 through

06/30/2020

NVLAP LAB National Voluntary Laboratory Accreditation Program 07/01/2021

CODE: 100555-0 Certificate of Accreditation to ISO/IEC 17025:2005 through

06/30/2022

Radiation 0-HSP-RCAD- Restricted and Controlled Area Dose evaluation [quarterly Various

Inspection Type Designation Description or Title Revision or

Procedure Date

Surveys 001, Attachment area monitoring TLD results] - First quarter 202 through third

quarter 2021

Self-Assessments PA7793973 RP-AA-111-1005, Attachment 1, External Radiation 09/25/2020

Exposure Control Program Review - 9/1/2017-9/25/2020

71124.05 Calibration FastScan Whole Body Counter Calibration Records (2020 Various

Records and 2021)

116575 Standard Reference Source Certificate of Calibration [Multi- 07/01/2020

Line gamma]

119329 Standard Reference Source Certificate of Calibration [Multi- 07/01/2021

Line gamma]

Corrective Action CRs 1182030, Various

Documents 1186087,

1187806, and

1189016

Corrective Action CR1195175 Missing Whole Body Counter Calibration Source Certificate 03/20/2022

Documents

Resulting from

Inspection

Miscellaneous 94810A Source 94810A (Cl-36) Transfer Calibration Data 11/21/2013

Procedures EP-AA-303 Equipment Important to Emergency Response Rev. 21

PI-AA-200 Corrective Action Rev. 38

71151 Calculations G-20220319-533- Gaseous Radioactive Release Permit, U-2 RWST Gas 03/25/2022

B (Vent)

G-20220319-534- Gaseous Radioactive Release Permit, U-2 Equipment Hatch 03/25/2022

B Gas

G-2022039-535B Gaseous Radioactive Release Permit, U-2 Reactor 03/25/2022

Containment

Corrective Action CR1167145, and CR1169039 Various

Documents

Engineering ETE-NA-2015- Review of Routine Surveillance Testing for Impact to MSPI 1

Evaluations 0031 Unavailability of HPSI and RHR

Miscellaneous URI and UAI MSPI Derivation Report- MSPI High Pressure April 1, 2021

Injection System for Units 1 and 2 to March 31,

22

Inspection Type Designation Description or Title Revision or

Procedure Date

RCS Identified Leakage spreadsheet for Units 1 and 2 April 1, 2021

to March 31,

22

Electronic Dosimeter Dose and Dose Rate Alarm Logs - Jan Various

21 through March 2022

Liquid Effluents Cumulative Dose Summary - January 2021 Various

through January 2022

Gaseous Effluents Cumulative Dose Summary - January Various

21 through January 2022

URI and UAI MSPI Derivation Report- MSPI Cooling Water April 1, 2021

System for Units 1 and 2 to March 31,

22

NAPS MSPI NRC Mitigating System Performance Index (MSPI) Basis 9

Basis Document Document - North Anna Power Station Units 1 and 2

71152S Corrective Action CR1199303

Documents CR1200625

CR1201892

Miscellaneous Station Performance Improvement Report - North Anna 06/14/2022

Power Station (January 1, 2022 - April 30, 2022)

Audit Report 21- Audit 21-08: NAPS Fire Protection QA Program and 10/19/2021

Implementation

Audit Report 22- Audit 22-01: Cyber Security, Fitness for Duty, and 03/22/2022

Unescorted Access Authorization

20