IR 05000338/2022002
| 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
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.
August 11, 2022 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. 05000338 and 05000339 License Nos. NPF-4 and NPF-7
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000338 and 05000339
License Numbers:
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
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.
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 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
- (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
'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,
RADIATION SAFETY
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
[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
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0-AP-41
Severe Weather Conditions
Corrective Action
Documents
CR
1171958
Corrective Action
Documents
Resulting from
Inspection
CA017909
11715-FM-079A
Flow/Valve Operating Numbers Diagram Component
Cooling Water System North Anna Power Station Unit 2
Drawings
PI N-2005-1336
Procedures
2-OP-51.1A
Valve Checkoff-Component Cooling, Auxiliary Building and
Main Steam Valve House
Engineering
Evaluations
ETE-NA-2011-
0071
1-FS-MS-1
Main Steam Valve House Unit 1
1-FS-QS-1
Quench Spray Building 274' (SG-74) Unit 1
Fire Plans
2-FS-C-1
Loss Prevention Fire Strategy, Containment - Unit 2
Rev. 4
Miscellaneous
NAS-3014
Supplemental NDE Personnel Certification Review Checklist
for Employee ID: 04344
03/07/2022
Personnel Certification Summary Record for Employee ID
04344
11/24/2020
Personnel Certification Summary Record for Employee ID:
T2010
07/25/2019
Supplemental NDE Personnel Certification Review Checklist
for Employee ID: T2010
03/18/2022
Supplemental NDE Personnel Certification Review Checklist
for Employee ID: F1670
03/07/2022
Miscellaneous
Personnel Summary Certification Record for Employee ID:
F1670
09/12/2021
Emergency Plan Drill NJun22EPD
Miscellaneous
Reactivity Plan for N2C29 BOC Reactor Startup
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Reactivity Plan for N1C29 Dropped Rods Startup
Miscellaneous
Plan of Week
April 1 to
June 30,
22
59-02-PT-213.20
Valve Inservice Testing 2-MS-TV-211A and 2-MS-TV-211B
Rev. 13
Calculations
0004
System Stroke Time Design Requirements for Air Operated
Valves in the North Anna Station, Units 1 and 2 Inservice
Testing Programs
Rev. 0
CR 1195505
2-MS-TV-211A Slow to Stroke Open
CR 1195506
2-MS-TV-211B Failed to Stroke Open
CR1175825
Corrective Action
Documents
CR1201351
DNES-NA-
EE/MOV-1001
Over-Current and Voltage Phase Imbalance Analysis for
Procedures
ER-AA-IST-102
ASME IST Program - Inservice Testing of Valves
Rev. 8
1-PT-71.3Q
1-FW-P-3B, B Motor-Driven AFEW Pump, and Valve Test
58, 59
Procedures
2-OP-6.9
Slow Start and Operation of 2J Emergency Diesel Generator
Work Schedule for Covered Worker-Operations - Employee
ID 45994
03/03/2022
to
03/11/2022
Work Schedule for Covered Worker - Chemistry - Employee
IDs 93554, 43278
03/07 to
03/15/2022;
03/23 to
03/29/2022
Work Schedule for Covered Worker - Rad Protection/ Health
Physics - Employee IDs 50609, 111372, 3383, 512, 25473,
59818, 53062
03/23/2022
to
03/29/2022
Work Schedule for Covered Worker - Security - Employee
IDs 60228, 113193, 110597, 34578, 44725
04/11/2022
to
04/20/2022
Miscellaneous
Work Schedule for Covered Workers-Maintenance-
Employee IDs 68273, 44963, 1099, 51462, 61632, 82873
04/03/2022
to
04/09/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Schedule for Covered Worker - Rad Protection/Health
Physics - Employee Ids 50609, 111372, 3383, 512, 25473,
59818
03/07/2022
to
03/15/2022
N2C29
RxManPO3.3
BOC Startup
1-OP-1.5
Unit Startup from Mode 3 to Mode 2
1-OP-1.5A
Mode 3 to Mode 2 Checklist
2-OP-1.7
Unit Startup from Mode 3 to Mode 2 Following Refueling
2-OP-2.1
Unit Startup form Mode 2 to Mode 1
131
Procedures
Fatigue Management and Work Hour Limits for Covered
Workers
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
Procedures
2-PT-78.3B
Inservice Inspection-Residual Heat Removal System Pump
2-RH-P-1B
North Anna Power Station 2021 Unit One Refueling Outage
N1R28 ALARA Report
2-014
Perform Valve Maintenance To Include; Repack,
Adjustment, Cut Out, Inspection Of Valves During N2R28
Revision 0
2-015
Repair 2-RC-MOV-2592, Revision 0 [including in-progress
review #1 & 2]
Various
ALARA Plans
2-018
Perform NDE & ISI Exams During N2R28 U-2 2022 RFO,
Revision 0 [including in-progress review #1]
Various
Corrective Action
Documents
CR1155152, CR1157526, CR1157862, CR1158379,
CR1168649, CR1168779, CR1169946, CR1170025, and
CR1172881
Various
North Anna Power Station Radiological Survey Location and
Frequency (RP-AA-220, Attachment 1).
03/17/2022
ALARA Daily Outage Report(s) - 03/15/2022 through
3/31/2022
Various
Miscellaneous
Unit 2 Outage Day 2 and Day 7 dose rate assessment [2017
thru 2022 containment dose rate/source term trending]
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Station ALARA Committee Meeting Minutes (2-RV-MOV-
2592 update and new dose projection)
03/24/2022
Access Controls for High and Very High Radiation Areas
Revision 10
Radiological Posting
Revision 13
Unrestricted Release of Material
Revision 8
ALARA Reviews and Reports
Revision 10
Procedures
RP Department Survey and Surveillance Verification
Revision 0
Unit 2 Upper Internal Lift Rig
03/28/2022
Temporary Reactor Vessel Cover (TRVC) pre and post
decontamination surveys [multiple surveys on 3/28 and
3/29/2022]
Various
Remote Continuous Coverage Log and Stay Time Tracking
Form for Unit 2 Blind Flange Removal
03/10/2022
Unit 2 Initial Entry radiation, contamination and airborne
survey(s), all elevations.
03/06/2022
Unit 2 Transfer Canal, containment side surveys prior to
Blind Flange removal [including dose rate gradient
assessment]
Various
2-RC-MOV-2592
Multiple radiation, contamination surveys for loop stop valve
work performed from 3/16/2022 through 3/25/2022.
Various
2-2251-0307-
0330
Unit 2 Reactor Cavity air sample during deck plate
installation and Transfer Canal survey (PAPRs worn).
Analysis for beta, gamma, iodine, and alpha.
03/07/2022
2-2252-0311-
0956
Air sample in the Unit 2 Cavity during the Reactor Head Lift
(respiratory protection worn (PAPH)). Analysis for beta,
gamma, iodine, and alpha.
03/11/2022
Radiation
Surveys
2-2252-0311-
1014
Air sample at the Unit 2 Cavity Edge during the Reactor
Head Lift. Analysis for beta, gamma, iodine, and alpha.
03/11/2022
2-2015
Valve Maintenance in Radiation Areas
Revision 0
Radiation Work
Permits (RWPs)
2-2220
Perform ultrasonic, magnetic particle and liquid penetrant
examination for the ASME Xl in service inspection program
in LHRA.
Revision 0
Self-Assessments
Radiological Work Control Program Review November 2019
- June 2021
10/26/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Audit 20-06
Nuclear Oversight Audit 20-06: Radiation Protection,
Process Control Program, and Chemistry
09/16/2020
8030084224
PortaCount Pro Model 8030 Calibration Certificate
08/09/2021
L01129
Posi3 USB Calibration Report, Certificate of Calibration,
Certificate # 56071921L01129
07/19/2021
L02179
Posi3 USB Calibration Report, Certificate of Calibration,
Certificate # 56061621L02179
06/16/2021
LAC174787
SCBA Pack #23 Test Record
01/28/2022
LAC182418
SCBA Pack #17 Test Record
01/31/2022
Calibration
Records
LAC182447
SCBA Pack #4 Test Record
2/01/2022
Corrective Action
Documents
CR1142555, and CR1153635
Various
0-HSP-BSRD-
001, Attachment
North Anna Internal Exposure Control Program Surveillance
- May 2020 through December 2020
03/09/2021
0-PT-114
Emergency Kit Respirator Inspections [Quarterly, Monthly
emergency kit respirator inspections] - 12/19/2021,
01/13/2022, 02/27/2022, and 03/16/2022
Various
Radiological Use SCBA Inspection Record - 12/19/2021,
01/13/2022, 02/15/2022, and 03/16/2022
Various
Miscellaneous
North Anna Unit 2 Alpha Source Term Characterization for
N2R28 (Routine Facility Characterization of Alpha Source
Term - North Anna Power Station, June 2020 to December
21)
2/15/2022
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
Verification
Revision 6
Issue and Control of Respiratory Protection Equipment
Revision 7
Inspection and Inventory of Respiratory Protection
Equipment
Revision 8
Alpha Monitoring
Revision 5
Procedures
Portable HEPA Ventilation Units
Revision 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
HP-1042.510,
Breathing Air Quality Verification Record [Grade D breathing
air analysis results] for Air Compressor 2-SA-111 and 2-SA-
109 dated 03/09/2021 and 08/20/2021
Various
HP-1042.510,
Breathing Air Quality Verification Record [Grade D breathing
air analysis results] for Paint Shop Air Compressor dated
03/09/2021 and 08/20/2021
Various
Radiation
Surveys
HP-1042.520,
Respiratory Equipment Certification Record [Grade D
breathing air analysis results] for Diving Gas Mixture 35%
Oxygen/ Balance Nitrogen used for atmospheric
containment entry
Various
Self-Assessments PA7793969
Internal Radiation Exposure Control Program Review
2/2018 - 8/2020
08/31/2020
203296734
0-PT-77.4A, Laboratory Analysis - 1-HV-FL-3A-ECCS
PREACS [Charcoal Radioiodine Sample]
2/10/2020
203296795
0-PT-95.3, Fuel Building Ventilation - Negative Pressure
Test
05/05/2021
Work Orders
203316776
0-PT-77.14B, ECCS PREACS Train B Filter In-Place Test
(1-HV-FL-38) [HEPA and charcoal filter test]
11/03/2021
Corrective Action
Documents
CR1159911, CR1165985, CR1179245, and CR1183875
Various
Whole Body Counter nuclide libraries [multiple libraries for
various counting geometries]
Various
C-HP-1031.023,
Multibadge RCA Authorization/Worksheet(s) [three
individuals working on the loop stop valve internals]
03/16/2022
NVLAP LAB
CODE: 100555-0
National Voluntary Laboratory Accreditation Program
Certificate of Accreditation to ISO/IEC 17025:2005
07/01/2010
through
06/30/2021
NVLAP LAB
CODE: 100555-0
National Voluntary Laboratory Accreditation Program
Certificate of Accreditation to ISO/IEC 17025:2005
07/01/2019
through
06/30/2020
Miscellaneous
NVLAP LAB
CODE: 100555-0
National Voluntary Laboratory Accreditation Program
Certificate of Accreditation to ISO/IEC 17025:2005
07/01/2021
through
06/30/2022
Radiation
0-HSP-RCAD-
Restricted and Controlled Area Dose evaluation [quarterly
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Exposure Control Program Review - 9/1/2017-9/25/2020
09/25/2020
FastScan Whole Body Counter Calibration Records (2020
and 2021)
Various
116575
Standard Reference Source Certificate of Calibration [Multi-
Line gamma]
07/01/2020
Calibration
Records
119329
Standard Reference Source Certificate of Calibration [Multi-
Line gamma]
07/01/2021
Corrective Action
Documents
CRs 1182030,
1186087,
1187806, and
1189016
Various
Corrective Action
Documents
Resulting from
Inspection
CR1195175
Missing Whole Body Counter Calibration Source Certificate
03/20/2022
Miscellaneous
94810A
Source 94810A (Cl-36) Transfer Calibration Data
11/21/2013
Equipment Important to Emergency Response
Rev. 21
Procedures
Corrective Action
Rev. 38
G-20220319-533-
B
Gaseous Radioactive Release Permit, U-2 RWST Gas
(Vent)
03/25/2022
G-20220319-534-
B
Gaseous Radioactive Release Permit, U-2 Equipment Hatch
Gas
03/25/2022
Calculations
G-2022039-535B
Gaseous Radioactive Release Permit, U-2 Reactor
Containment
03/25/2022
Corrective Action
Documents
CR1167145, and CR1169039
Various
Engineering
Evaluations
ETE-NA-2015-
0031
Review of Routine Surveillance Testing for Impact to MSPI
Unavailability of HPSI and RHR
71151
Miscellaneous
URI and UAI MSPI Derivation Report-MSPI High Pressure
Injection System for Units 1 and 2
April 1, 2021
to March 31,
22
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
21 through March 2022
Various
Liquid Effluents Cumulative Dose Summary - January 2021
through January 2022
Various
Gaseous Effluents Cumulative Dose Summary - January
21 through January 2022
Various
URI and UAI MSPI Derivation Report-MSPI Cooling Water
System for Units 1 and 2
April 1, 2021
to March 31,
22
Basis Document
NRC Mitigating System Performance Index (MSPI) Basis
Document - North Anna Power Station Units 1 and 2
CR1199303
CR1200625
Corrective Action
Documents
CR1201892
Station Performance Improvement Report - North Anna
Power Station (January 1, 2022 - April 30, 2022)
06/14/2022
Audit Report 21-
Audit 21-08: NAPS Fire Protection QA Program and
Implementation
10/19/2021
Miscellaneous
Audit Report 22-
Audit 22-01: Cyber Security, Fitness for Duty, and
Unescorted Access Authorization
03/22/2022