IR 05000338/2020003

Integrated Inspection Report 05000338/2020003 and 05000339/2020003 and Exercise of Enforcement Discretion

ML20310A166
Person / Time
Site:	North Anna
Issue date:	11/05/2020
From:	Mark Miller Division Reactor Projects II
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
EA-20-092 IR 2020003
Download: ML20310A166 (35)

Text

November 5, 2020 EA-20-092 Mr. Daniel Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 500 Dominion Boulevard Glen Allen, VA 29060 SUBJECT: NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2020003 AND 05000339/2020003 AND EXERCISE OF ENFORCEMENT DISCRETION

Dear Mr. Stoddard:

On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On October 14, 2020, the NRC inspectors discussed the results of this inspection with Mr. F. Mladen and other members of your staff. The results of this inspection are documented in the enclosed report.

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

This inspection report documents an exercise of enforcement discretion in accordance with the NRC Enforcement Policy, Section 3.10, Reactor Violations With No Performance Deficiencies, for an issue that closely matched a Severity Level III violation example in Section 6.1.c.1 of the Enforcement Policy. The inspectors concluded that there was no performance deficiency associated with the 1J emergency diesel generator piston pin bushing failure because the equipment failure was not avoidable by reasonable licensee quality assurance measures or management controls.

Based on the facts detailed in the enclosed report, and consultation with the Office of Enforcement and the Regional Administrator, I have been authorized to exercise enforcement discretion in accordance with Section 3.10 of the Enforcement Policy, and refrain from issuing enforcement for the violation. This violation will not be considered in the assessment process or the NRCs Action Matrix. 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,

/RA/

Mark S. Miller, Director 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: 05000338/2020003 and 05000339/2020003 Enterprise Identifier: I-2020-003-0062 Licensee: Virginia Electric & Power Co Facility: North Anna Power Station Location: Mineral, VA Inspection Dates: July 1, 2020 to September 30, 2020 Inspectors: M. Tobin, Senior Resident Inspector G. Eatmon, Resident Inspector P. Niebaum, Senior Project Engineer A. Patz, Resident Inspector B. Towne, Resident Inspector D. Jackson, Project Engineer D. Bacon, Senior Operations Engineer B. Collins, Senior Reactor Inspector J. Diaz-Velez, Senior Health Physicist B. Kellner, Senior Health Physicist W. Pursley, Health Physicist S. Sanchez, Senior Emergency Preparedness Inspector C. Fontana, Emergency Preparedness Inspector J. Walker, Emergency Response Inspector Approved By: Stewart N. Bailey, 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.

List of Findings and Violations

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

Additional Tracking Items

Type Issue Number Title Report Status Section LER 05000338/2020-001-01 Degraded Upper Cylinder Piston Pin 71153 Closed Bushing Discovered during Maintenance Activities on Emergency Diesel Generator [Rev. 1]

LER 05000338/2020-001-00 Degraded Upper Cylinder Piston Pin 71153 Closed Bushing Discovered during Maintenance Activities on Emergency Diesel Generator [Rev. 0]

EDG EA-20-092 Enforcement Action (EA) 20-092: 1J 71153 Closed Emergency Diesel Generator (EDG)

Exceeded TS Allowed Outage Time -

Violation Without a Performance Deficiency

PLANT STATUS

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

Unit 2 began the inspection period at rated thermal power. On September 13, 2020, the unit was shut down for a planned refueling outage. The unit remained shut down 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 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. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection External Flooding Sample (IP Section 03.03)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Unit 1, Low Head Safety Injection, Train A, while Unit 1, Charging Pump 'A' was out of service on July 15, 2020.

(2) Unit 2, Quench Spray, Train A, while Unit 2, Quench Spray Pump 'B' was out of service on August 11, 2020.

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 casing cooling system on August 26, 2020.

71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01)

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) Unit 1 and Unit 2, Cable Tray Spreading and Battery Room 2-1, 1-1, 2-3, 1-3 on July 6, 2020

(2) Unit 2, Cable Vault and Tunnel and 280' Rod Drive on July 16, 2020

(3) Unit 1 and Unit 2, Safeguards Area on August 13, 2020

(4) Unit 2, Motor Generator Set House on August 22, 2020

(5) Station Blackout Diesel Building on August 23, 2020

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 03.01)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 1 and Unit 2 Safeguards Areas on August 13, 2020

71111.07A - Heat Sink Performance Annual Review (IP Section 03.01)

The inspectors evaluated readiness and performance of:

(1) Common spent fuel pool heat exchangers

71111.07T - Heat Sink Performance Triennial Review (IP Section 03.02)

The inspectors evaluated heat exchanger/sink performance on the following from July 27-31, 2020:

(1) Unit 1 B component cooling water heat exchanger (1-CC-E-1B), Section 02.02b

(2) Unit 1 A residual heat removal heat exchanger (1-RH-E-1A), Section 02.02b

(3) Unit 2 C main control room/switchgear room cooler (2-HV-E-4C-2), Section 02.02b

(4) Unit 2 B charging pump lube oil/gearbox coolers (2-CH-E-1B1, 2-CH-E-5B),

Section 02.02b

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

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from September 21-25, 2020:

(1) 03.01.a - Nondestructive Examination and Welding Activities.

1. Ultrasonic Examination (UT)a. pressurizer longitudinal weld (12050-WMKS-RC-E-2 / 2-RC-E-2 / 1), ASME Class 1 (reviewed)b. 6" feedwater system weld (12050-WMKS-0102D / 6-WFPD-419 / 27 BPL 551), ASME Class 2 (reviewed)c. 2" reactor coolant system welds (12050-WMKS-0103CB/2-RC-455/10, /78,

/SW-64, /SW-65), ASME Class 1 (reviewed, including weld documentation)d. 4" control rod drive mechanism weld (12050-WMKS-RC-R-1.2 / 2-RC-R-1 /

CRD-43), ASME Class 1 (reviewed)2. Liquid Penetrant Examination (PT)a. 2" reactor coolant system welds (12050-WMKS-0103CB/2-RC-455/10, /78,

/SW-64, /SW-65), ASME Class 1 (reviewed, including weld documentation)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

1. Bare Metal Visual Examination a. reactor vessel head (all visible surfaces under insulation package), ASME Class 1 (reviewed)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

The inspectors reviewed the licensee's boric acid corrosion control program performance.

03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

The inspectors reviewed the licensee's justification for skip-cycle approach on steam generator ISI activities.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during a fire drill on August 24, 2020

(2) The inspectors observed and evaluated licensed operator performance in the Control Room during the Unit 2 shutdown for refueling outage on September 12, 2020

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

(1) The inspectors observed and evaluated a training drill on July 14, 2020

71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Unit 1: 1H emergency diesel generator (EDG) tripped after starting on April 19, 2020

(2) Unit 1: 1J EDG removed from service due to elevated copper levels in the oil on February 16, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed;

(1) Unit 1 and 2 in elevated green risk due to the diesel fuel above ground tank inspections on August 10, 2020

(2) Unit 2 in elevated shutdown risk due to decreased inventory for vessel head removal on September 16, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) Unit 1 H EDG following crankcase overpressure trip on July 22, 2020

(2) Unit 2 control rods following an urgent rod failure alarm on August 3, 2020

(3) Station Blackout diesel following an aborted surveillance due to high engine temperatures on August 11, 2020

(4) Turbine-driven auxiliary feedwater pump with water intrusion into the oil system on September 8, 2020

(5) C reserve station service transformer (RSST) trouble alarm on August 10, 2020

(6) Unit 1 and Unit 2 condensate storage tank due to leakage from the auxiliary feedwater pump seals on July 13, 2020

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 2 service water motor-operated valves (2-SW-MOV-203 A/C and 2-SW-MOV-204A/C) replacements on September 30, 2020

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Unit 1, Control Room Chiller, 1-HV-E-4A, corrective maintenance after failure to pass a Technical Specification surveillance requirement on July 15, 2020

(2) Unit 2, repair of MIC leak in Service Water pipe associated with Charging Pump 'C' oil cooler, 2-CH-P-1C, on July 15, 2020

(3) Unit 1 and 2, station blackout diesel generator after surveillance run failure on September 22, 2020

(4) Unit 2, 2-PT-88.3J, Station Battery 2-III Modified Performance Test, on September 28, 2020

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated refueling outage 2R27 activities from September 13, 2020 to September 30, 2020

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01) (2 Samples)

(1) Unit 1, Control Room Chiller, 1-HV-E-4A, performance test and associated chiller failure of the performance test on July 7, 2020

(2) Unit 1 Reactor Protection System and Engineered Safety Features Resistance Temperature Detector response time testing on July 24, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 2, Quench Spray Pump, Train B, 2-QS-P-1B, performance test on

August 11, 2020 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) 2-PT-61.3, Type C testing, penetration 94 on September 28, 2020

FLEX Testing (IP Section 03.02) (1 Sample)

(1) Unit 1 and 2 Beyond Design Basis Auxiliary Feedwater Pump test on September 22, 2020

71114.01 - Exercise Evaluation Inspection Review (IP Section 02.01-02.11)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of August 17, 2020. The simulated scenario began with an earthquake of magnitude greater than the Operational Bases Earthquake, thus meeting the criteria for declaration of an Alert. A significant aftershock caused damage to the spent fuel pool, resulting in a 300 gallon per minute leak. Subsequently, a small break loss of coolant accident (LOCA) occurred, resulting in a reactor trip and safety injection, along with a report from Chemistry that the dose equivalent iodine exceeded the threshold for indication of a loss of fuel clad barrier. This met the conditions for declaring a Site Area Emergency. When a large break LOCA occurred and both containment spray trains became inoperable for different reasons, conditions for a General Emergency were met, and the offsite response organizations were able to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of August 17, 2020. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1 Sample)

(1) Emergency Preparedness Drill on July 14, 2020

71114.08 - Exercise Evaluation Scenario Review Inspection Review (IP Section 02.01 - 02.04)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

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 radiological protection-related instructions to plant workers.

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

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) Evaluated the licensee's physical and programmatic controls for non-fuel radioactive material in the spent fuel pool.

(2) Observed material handlers supported by radiation protection technicians during the installation and removal of radioactive outage support equipment at the Unit 2 reactor building containment equipment hatch during the Unit 2 fall Outage.

(3) Observed workers removing protective clothing exiting Unit 2 containment at the personnel hatch during the Unit 2 fall Outage.

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

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) Removal of Pressurizer Safety Relief Valve under RWP #20-2115. This work involved a breach of the reactor coolant system boundary.

(2) Removal of the Unit 2 Transfer Canal Blind Flange under RWP #20-2253 which involved high dose rates, high contamination levels, high dose gradients, and the use of respiratory protection.

(3) Reactor vessel head stud de-tensioning on RWP #20-2251 which involved dose gradients in a high radiation area.

(4) NDE testing and preparations for the removal of 2B reactor coolant pump motor under RWP # 20-2204 involving work in a high radiation area.

(5) Maintenance check outs of the fuel handling bridge gripper tube assembly on RWP

1. 20-2251 involving potential alpha level III controls.

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 1 Volume Control Tank Room in the Auxiliary Building

(2) Unit 2 A Gas Stripper Room in the Auxiliary Building

(3) Unit 2 B Reactor Coolant Pump Cubicle in Containment

(4) Unit 1 personnel hatch 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

(2) Fuel Handling Building Ventilation System

Temporary Ventilation Systems (IP Section 03.02) (5 Samples)

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

(1) HEPA #26 Setup for valve test stand/booth - DOP Test Date 06/26/2020

(2) S/N 2045 Staged for use in Unit 2 Containment - DOP Test Date 08/21/2020

(3) S/N 2090 Staged for use in Unit 2 Containment - DOP Test Date 08/21/2020

(4) Air powered Vacuum S/N 30 Staged for use in Unit 2 Containment - DOP Test Date 07/11/2019

(5) Air powered Vacuum S/N 34 Staged for use in Unit 2 Containment - DOP Test Date 07/11/2019

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) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization. Reviewed Alpha Source Term Characterization Reports for Units 1 and 2, dated August 8, 2019, and January 28, 2019, respectively.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (3 Samples)

The inspectors evaluated the following internal dose assessments for actual internal exposures:

(1) Whole Body Count (WBC) records for a personnel contamination event (facial),09/15/2019

(2) Reviewed WBC records for CR 1117959 for positive random WBC, 03/11/2019

(3) Reviewed WBC records for CR 1131001 for positive random WBC, 09/15/2019

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

The inspectors evaluated the following special dosimetric situations:

(1) Reviewed dose assessment for two declared pregnant workers

(2) Multi-badging of workers removing the blind flange in the Unit 2 fuel transfer canal

71124.05 - Radiation Monitoring Instrumentation Walkdowns and Observations (IP Section 03.01)

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

(1) Unit 2 Containment High Range Radiation Monitors RMS-265A and B

(2) Unit 2 Containment Entrance Area Radiation Monitor 2-RM-ARM-261

(3) Unit 1 Containment Airborne Radiation Monitor 1-RM-RMS-159/160

(4) Unit 2 Containment Airborne Radiation Monitor 2-RM-RMS-259/260

(5) Unit 1 and 2 Steam Generator Blowdown Radiation Monitors RMS-122, 123, 124 and RMS 222, 223, 224

(6) Portable friskers located at various locations in the auxiliary building

Calibration and Testing Program (IP Section 03.02) (13 Samples)

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

(1) Telepole survey meter - Serial Number (S/N) 6607-037, 09/11/2019 and 0729/2020

(2) RO20AA Ion Chamber survey meter - S/N 176AA, 02/14/2018, 02/26/2019

(3) RadEye G survey meter - S/N 30039, 08/24/2018, 01/31/2019

(4) RadEye GX frisker survey meter - S/N 11635, 02/08/2019, 03/06/2020

(5) Sirius-5PAB hand and foot monitor - S/N 1508-117, 02/11/2019, 07/30/2020

(6) SAM-11 (small article monitor) - S/N 601, 01/21/2019, 0716/2020

(7) AMP-100 underwater survey meter - S/N 5097-021/021, 07/17/2017, 09/18/2019

(8) AMS-4 Continuous air monitor - S/N 1551, 10/24/2018, 10/09/2019; S/N 1040, 02/04/2019, 02/13/2020

(9) GEM-5 portal monitor - S/N 1810-300, 12/11/2019

(10) Ludlum 3030 alpha/beta scaler - S/N 328901, 07/23/2019, 01/14/2020; S/N 328913, 07/24/2019, 08/19/2020

(11) Ludlum 2000 alpha scaler - S/N 310621/PR329674, 10/03/2017, 01/23/2020

(12) Low Volume Gooseneck air sampler - S/N 6244, 09/27/2018, 03/03/2020; S/N 6245, 09/05/2017 02/28/2019

(13) High Volume air sampler - S/N 8629, 08/19/2019, 08/03/2020; S/N 11909, 08/01/2019, 08/03/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

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

(1) Liquid effluent radiation monitors 1-LW-RM-110 and 111

(2) Normal-Range and High Range Process Vent, Ventilation Vent A, and Ventilation Vent B Effluent Monitor skids

OTHER ACTIVITIES - BASELINE

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

EP01: Drill/Exercise Performance (IP Section 02.12) ===

(1) April 1, 2019, through June 30, 2020

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) April 1, 2019, through June 30, 2020

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) April 1, 2019, through June 30, 2020

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (July 2019 - June 2020)

(2) Unit 2 (July 2019 - June 2020)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (July 2019 - June 2020)

(2) Unit 2 (July 2019 - June 2020)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (July 2019 - June 2020)

(2) Unit 2 (July 2019 - June 2020)

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

(1) April 2019 to June 2020 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) August 2019 to June 2020

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) Inspectors reviewed a licensee-identified trend in missed surveillances and preventative maintenance to determine if a larger issue is occurring on site. The inspectors did not identify any trend beyond what the licensee had already identified, and licensee corrective actions appear to be adequate to address the trend.

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Unit 1 J emergency diesel generator inoperability on September 16, 2020

(2) Unit 1 and Unit 2 intercell connection resistance readings for the station and diesel batteries on September 22, 2020

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000338/2020-001-00, and -01, Degraded Upper Cylinder Piston Pin Bushing Discovered during Maintenance Activities on Emergency Diesel Generator, (Agency Document and Management System (ADAMS) Accession No. ML20122A056). The NRC exercised enforcement discretion in Enforcement Action (EA)-2020-092, in accordance with Section 3.10 of the Enforcement Policy because the violation was not associated with a licensee performance deficiency. The enforcement discretion is documented in the results section of this report. This LER is closed.

INSPECTION RESULTS

Enforcement Enforcement Action EA-20-092: 1J Emergency Diesel Generator 71153 Discretion (EDG) Exceeded TS Allowed Outage Time - Violation Without a Performance Deficiency

Description:

On February 18, 2020, during planned maintenance activities, brass shavings were discovered on the upper crankcase of the 1J emergency diesel generator (EDG). Further investigation revealed degradation of the number one cylinder upper piston pin bushing. This was likely caused by a degradation of the connecting rod aluminum cooling oil spherical retainer ring, which resulted in an increased oil bypass flow and subsequent inadequate lubrication (oil wedge) between the piston pin and the piston pin bushing. Over time, the inadequate lubrication led to bushing degradation that created the shavings that were the visual indication of a failure. Subsequent maintenance activities and inspections were performed on additional EDG cylinders with no indication of abnormal wear or degradation. The affected cylinder and cylinder internals were all replaced, and the EDG was returned to service on February 26, 2020.

The licensee determined that the significant bushing degradation occurred during the surveillance run on January 22, 2020. Although the EDG never actually failed any surveillance tests, it was determined that the EDG would likely have been unable to meet its 30-day mission time following the previous successful surveillance on December 16, 2019.

Prior to the failure, the on-site diesel engineer determined that the slowly rising trend in engine oil copper concentration warranted increased observation, including increased frequency of surveillances for trending purposes, and an increased scope of the maintenance planned for February 2020. At no point did the EDG exceed the allowable copper levels that were provided by the equipment manufacturer. Therefore, the licensee identified that the EDG internals were experiencing wear but had no reason to suspect that the extent of the wear could challenge the operability of the EDG.

The inspectors reviewed the LER and the Level of Effort Evaluation (cause evaluation)conducted by the licensee, and conducted a review of relevant operating experience to determine whether a performance deficiency was associated with this type of EDG degradation. Although the LER discussed that inadequate lubrication was the apparent cause of the failure, there was no evidence in the timeframe of the increasing copper trend that would have indicated a loss of lubrication, nor did the EDG copper levels enter the alert range or require any specific action based on vendor recommendations. Following identification of the failed bushing, the licensee completed extensive inspection, analysis and operating experience review to identify the root cause. The licensee and vendor determined that this was a first-of-a-kind failure in nuclear applications.

The inspectors concluded that this failure was not reasonably foreseeable and preventable by the licensee and subsequently, the technical specification (TS) violation was not a result of a clearly defined and identifiable performance deficiency, therefore this event will be appropriately addressed using traditional enforcement under the NRCs Enforcement Policy.

The LER documented that the latent failure of the 1J EDG existed for approximately 72 days, which exceeded the T.S. 3.8.1 Condition B allowed outage time of 14 days. The LER additionally documented that both EDGs were out of service for approximately 39.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, which exceeded the T.S. 3.8.1 Condition I allowed outage time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The NRC Enforcement Policy, Section 6, Violation Examples states, in part, that when an enforcement case scenario very nearly achieves all or some of the criteria set forth in an example, the case should be considered to be at the severity level of that example. For this event, the TS violation closely matched example 6.1.c.1 for a Severity Level (SL) III violation for the licensees failure to shut down the reactor or follow actions required by TS when a Limited Condition for Operation was not met (i.e., noncompliance with 10 CFR 50.36(c)(2)(i)).

The NRC did not complete a detailed risk assessment of this event. This decision was based on not having an underlining performance deficiency associated with the event, the ability to use enforcement discretion for violations without a performance deficiency, and having an applicable SL III violation example in the NRC Enforcement Policy. The SL III example approximately bounded the upper severity level of the event.

Corrective Actions: The licensee replaced the piston pin bushing and associated components. Additionally, the licensee plans to review and modify the elemental analysis wear metal criteria for the EDG lubricating oil to establish a more conservative criterion and communicate these results to the Fairbanks Morse Diesel Owners Group.

Corrective Action References: CR1136269, CR1141471, CA7899887

Enforcement:

Violation:

T.S. 3.8.1, AC SourcesOperating, requires, in part, that two diesel generators capable of supplying the onsite Class 1E power shall be operable in Modes 1, 2, 3, and 4. T.S. 3.8.1, Action B, requires, in part, that if one diesel generator is inoperable, then restore the diesel generator to operable status within 14 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

TS 3.8.1, Action I, requires, that if two EDGs are inoperable, restore one EDG to operable status within two hours.

Contrary to the above, from December 16, 2019, to February 26, 2020, the 1J EDG was inoperable due to a failed piston pin bushing. The EDG was not returned to operable status within 14 days and was not placed in hot standby within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Additionally, during several instances, from December 16, 2019, the 1H EDG was inoperable for normal maintenance and surveillance activities for approximately 39.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> concurrently with the 1J EDG. With both EDGs inoperable during this period, the licensee failed to restore one EDG to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Basis for Discretion: The NRC exercised enforcement discretion in Enforcement Action (EA)-20-092, in accordance with Section 3.10 of the Enforcement Policy, because the violation was not associated with a licensee performance deficiency. Specifically, the violation was not attributable to equipment failures that were avoidable by reasonable licensee quality assurance measures or management controls. Therefore, inspectors concluded that there was no performance deficiency associated with the 1J EDG piston pin bushing failure. The affected 1J EDG cylinder and cylinder internals were replaced and the EDG was returned to an operable condition. This enforcement discretion will not be considered in the assessment process of the NRCs Action Matrix.

EXIT MEETINGS AND DEBRIEFS

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

• On October 14, 2020, the inspectors presented the integrated inspection results to Mr. F. Mladen, Site Vice President (VP) and other members of the licensee staff.

• On July 30, 2020, the inspectors presented the Triennial Heat Sink Performance Inspection results to Ms. Lisa Hilbert, Plant Manager and other members of the licensee staff.

• On September 24, 2020, the inspectors presented the North Anna Unit 2 Inservice Inspection results to Mr. Fred Mladen, Site VP and other members of the licensee staff.

• On September 25, 2020, the inspectors presented the RP Inspection results to Mr. F. Mladen, Site VP 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 77

71111.04 Corrective Action CR1144261 2-QS-ICV-3001 has dried boric acid on valve stem and 04/04/2020

Documents stem nut

CR1152813 2K-E7 (RS Pump Casing Cooling Tank Level Hi/Lo) is 0

locked in.

Corrective Action CR1151645 NRC Identified: equipment staged in yard near U1 7/15/2020

Documents QSPH/SFGDS

Resulting from

Inspection

Drawings 12050-FM-091B Flow/Valve Operating Numbers Diagram Containment 18

Quench and Recirc Spray Sub System, North Anna Unit 2

Miscellaneous System Health Report for Recirc Spray System - Q2-2020

NCRODP-54-NA System Description - Recirculation Spray System 10/16/2018

Procedures 1-OP-7.1A Operating Procedure, Valve Checkoff - Low Head Safety 24

Injection System

2-OP-7.10 Operation of Casing Cooling Subsystem of the Recirc 38

Spray System

2-OP-7.10A Valve Checkoff - Casing Cooling System 12

2-OP-7.4A Valve Checkoff - Quench Spray System 11

71111.05 Corrective Action CR1153950

Documents

Resulting from

Inspection

Fire Plans 0-FS-CT-1 Loss Prevention Fire Strategy, Cable Tray Spreading and 5

Battery Room 2-1, 1-1, 2-3, 1-3

1-FS-SBO-1 Station Blackout Building Fire Fighting Strategy 6

1-FS-SG-1 Fire Fighting Strategy for Safeguards Area Safe Shutdown 6

Equipment Unit 1

2-FS-MG-1 Fire Fighting Strategy for Motor Generator Set House Unit 1

2-FS-S-2 Fire Fighting Preplan for Cable Vault and Tunnel and 280' 12

Rod Drive Unit 2 Safe Shutdown Equipment

Inspection Type Designation Description or Title Revision or

Procedure Date

2-FS-SG-1 Fire Fighting Strategy for Safeguards Area Safe Shutdown 5

Equipment Unit 2

Procedures 0-PT-105.3 Hose House Inspection 6

CM-AA-FPA-100 Fire Protection/ Appendix R (Fire Safe Shutdown) Program 14

71111.06 Engineering NOTEBK-PRA- Probabilistic Risk Assessment Model Notebook - 2

Evaluations NAPS-IF.1B Partitioning and Source Identification and Characterization

- Flood Area Definition

NOTEBK-PRA- Probabilistic Risk Assessment Model Notebook - Internal 1

NAPS-IF.2 Flooding - Flood Scenario Development

Miscellaneous DNES-AA-GN-BAR- Passive Design Features and Barriers 10

1001

71111.07A Corrective Action CR1116423,

Documents CR1115668,

CR555082

NDE Reports WO 59102749337 Final Eddy Current Inspection Report for 1-FC-E-1A 02/07/2019

WO59102754078 Final Eddy Current Inspection Report for 1-FC-E-1B 02/20/2019

Procedures ER-AA-HTX-10 Heat Exchanger Program 8

ER-AA-HTX-1004 Heat Exchanger Program Eddy Current Testing 5

71111.07T Calculations NA-CALC-MEC- Component Cooling Heat Exchanger Tube Plugging Study Rev. 0

ME-0530

Corrective Action CR1089486 Pipe Tee downstream of 1-SW-1110 Pin Hole Leak, 02/06/2018

Documents CR1112654 Through-wall Leak on Service Water Socket Weld 12/17/2018

associated with 2-CH-P-1A

CR1131315 1-SW-P-25A Discharge Piping Leak 09/19/2019

CR1136853 Leak in Copper Pipe Elbow Upstream of 1-VSW-2 11/27/2019

CR1150998 MIC Leak in SW Piping Associated with 2-CH-P-1C 07/06/2020

Drawings 11715-FV-091A Component Cooling Heat Exchangers Tube Sheet Bundle Rev. 0

- Tube Identification, 1-CC-E-1A, North Anna Power

Station

11715-FV-091B Component Cooling Heat Exchangers Tube Sheet Bundle Rev. 2

- Tube Identification, 1-CC-E-1B, North Anna Power

Station

Miscellaneous System Health Report Q2-2020 - Service Water July 15,

20

Inspection Type Designation Description or Title Revision or

Procedure Date

89-572H Letter from

W.L. Stewart to United States Nuclear October 18,

Regulatory Commission, Virginia Electric and Power 1991

Company North Anna Power Station Units 1 and 2

Consolidated Response to Generic Letter 89-13 Service

Water System Problems Affecting Safety-Related

Equipment"

Procedures 0-EPM-2303-01 Inspection of Service Water Cathodic Protection System Rev. 14

0-EPM-2303-02 Corrosion Survey of Service Water Cathodic Protection Rev. 1

System

0-PT-75.15 Generic Letter 89-13 Service Water System Testing Rev. 8

Requirements Coordination

ER-AA-HTX-1002 Heat Exchanger Program Visual and Leak Testing Rev. 6

ER-AA-HTX-1003 Heat Exchanger Monitoring and Assessment Rev. 7

ER-AA-HTX-1004 Heat Exchanger Program Eddy Current Testing Rev. 5

ER-AA-HTX-1005 Dominion Nuclear Fleet Heat Exchanger Guidelines for Rev. 4

Administrative Limits for Tube Plugging

ER-NA-SYS-320 Generic Letter 89-13 Program Rev. 6

VPAP-0811 Service Water System Inspection and Maintenance Rev. 6

Program

71111.08P Calibration Dominion Energy Calibration Certificate: Digital 4/25/2018

Records Thermometer (ATK-2)

Dominion Energy Calibration Certificate: Digital 7/22/2020

Thermometer (ATK-1)

2018-59-003 Eastern NDT Certificate of Calibration: CA-811 Light Meter 11/30/2018

(SN 1046JGCY)

Corrective Action CR1104243 Part 21 Notification: CRDM Sleeve Vulnerability 08/29/2018

Documents CR1156057 Discoloration Noted on RV Head Surface 09/22/2020

Engineering BACCP Evaluation Form: Boric Acid Found on 2-SS-TV- 05.02.2019

Evaluations 200B

BACCP Evaluation Form: Boric Acid Found on 2-CH-P-1B 05.02.2019

BACCP Evaluation Form: Boric Acid Noted on 1-RS-P-3B 06.12.2018

BACCP Evaluation Form: Seal Leakage from 2-RC-P-1C 05/06/2020

Inservice Inspection Indication Evaluation Record for Code 4/13/20

Case N-566-2 Compliance for 2-RC-P-1A

Inspection Type Designation Description or Title Revision or

Procedure Date

ETE-NA-2019-1002 Steam Generator Condition Monitoring and Operational Rev. 0

Assessment North Anna Unit 2

Miscellaneous Curtiss-Wright Personnel Certification Statement: UT 07/24/2020

(Sauter)

Curtiss-Wright Certification of Visual Acuity and Color 07/24/2020

Vision per LMT Procedure PVE-1 (Sauter)

Ray-Check Mfg. Inc. Certificate of Compliance: Angle 9/6/05

Beam Test Block (S/N 05-5560, S/N 05-8258)

Curtiss-Wright Personnel Certification Statement: UT 07/15/2020

(Fish)

Curtiss-Wright Certification of Visual Acuity and Color 8/21/2020

Vision per LMT Procedure PVE-1 (Fish)

Curtiss-Wright Personnel Certification Statement: UT 07/15/2020

(Cochran)

Curtiss-Wright Certification of Visual Acuity and Color 03/13/2020

Vision per LMT Procedure PVE-1 (Cochran)

ITLS Vision Acuity Certification (Dunn) 1/29/2019

Industrial Testing Laboratory Services, L.L.C. Certificate of 2/5/2019

Qualification and Certification Summary: PT (Dunn)

Curtiss-Wright Personnel Certification Statement: UT 12/11/2018

(Hacker)

Curtiss-Wright Certification of Visual Acuity and Color 8/15/18

Vision per LMT Procedure PVE-1 (Hacker)

Magnaflux Certificate of Certification: Spotcheck Developer 6/20/14

SKD-S2 (Batch 14F02K)

Magnaflux Certificate of Certification: Spotcheck Penetrant 09/08/2015

SKL-SP2 (Batch 15J02K)

Magnaflux Certification: Ultragel II Couplant (Batch 06/30/2017

17F087)

NDE Reports UT-20-011 UT Calibration/Examination Record: 12050-WMKS- 9/17/2020

0102D/6-WFPD-419/27 (BPL 551)

UT-20-019 UT Calibration/Examination Record: 12050-WMKS-RC-E- 9/22/2020

2/2-RC-E-2/1

UT-20-020 UT Calibration/Examination Record: 12050-WMKS-RC-R- 9/25/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

1.2/2-RC-R-1/CRD-43

Procedures 2-PT-48.6 Vessel Head Bare Metal Visual Inspection Rev. 7

ER-AP-BAC-10 Boric Acid Corrosion Control Program Rev. 13

ER-AP-BAC-101 Boric Acid Corrosion Control Program (BACCP) Rev. 13

Inspections

ER-AP-BAC-102 Boric Acid Corrosion Control Program (BACCP) Rev. 14

Evaluations

Work Orders WO59203285848 Replacement of A Loop Drain Piping Rev. 0

71111.12 Corrective Action CA7876917 Maintenance Rule (MR) Functional Failure Evaluation for 04/24/2020

Documents 1-EE-EG-1J Upper Crank Debris

CA7908528 Perform maintenance rule functional failure evaluation for 05/28/2020

1H EDG

CR1145061 1H EDG tripped after starting during 1-PT-82.2A 04/19/2020

Drawings 11715-ESK-11C Elem. Diagram Emer Diesel Gen 1H Unit1, Sheet 1 28

11715-ESK-11C Elem. Diagram Emer Diesel Gen 1H Unit1, Sheet 2 20

Procedures ER-AA-MRL-100 Implementing Maintenance Rule 12

71111.13 Procedures 0-GOP-13.3 Assessment of Maintenance Activities for Potential Loss of 04

Reactor Coolant Inventory

2-OP-5.4 Draining the Reactor Coolant System 77

71111.15 Corrective Action CA8082309 Investigate "self-test" programming of seismic sudden 08/14/2020

Documents pressure relay

CR1152481 07/29/2020

CR1152649 07/31/2020

CR1152700 08/02/2020

CR1152700 08/02/2020

CR1152855 08/04/2020

CR1153080 08/07/2020

CR1153081 08/07/2020

CR1153223 Received XFMR 1C Trouble [H-D7] 08/10/2020

Drawings 11715-FE-21P DC Elementary Diagram, Reserve Station Service 2

Transformer Protection, Units 1 and 2, Sheet 3

Engineering NA-20-00058 Splash Guard on 1-FW-T-2 Turbine Shaft 0

Changes

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering OP-AA-102 Water in oil discovered from 1-FW-P-2 following quarterly 0

Evaluations Attachment 5 PT performance

Miscellaneous Troubleshooting Unit 2 IAC Rod Control Cabinet 0

Sheet for

CR1152481

Procedures 1-AR-42 1-EP-ST-2C, C Reserve Station Service Transformer 1

71111.18 Corrective Action CA7672277 SW MOVs HBC-0 Qualified Stroke Count Exceeded

Documents

Engineering NA-20-00006 2-SW-MOV-203A/C and 2-SW-MOV-204A/C Replacement 1

Changes

Miscellaneous DNES-VA-EEN- Standard for Protective Device Settings, Thermal Overload 2

0011, Attachment 5 Relays and Heater Coil Selection GL-89-10 MOVs

71111.19 Procedures 0-MCM-0803-01 Repair of the Control Room Air Conditioning Chillers (1/2- 40

HV-E-4A, B, and C) and Front Office Air Conditioning

Chillers (1-HV-E-3A, B, and C)

2-PT-88.3J Station Battery 2-III Modified Performance Test 14

Work Orders 59203311984 Repair of MIC Leak in SW piping associated with 2-CH-P- 7/7/2020

1C

203311997 Remove/Reinstall Piping to Support MIC Leak 7/7/2020

71111.20 Corrective Action CR1154838 09/06/2020

Documents CR1156216 09/24/2020

CR1156222 09/24/2020

Procedures 2-OP-3.7 Unit Shutdown from Mode 1 to Mode 5 for Refueling 58

71111.22 Corrective Action CR1151128

Documents CR1155066 09/10/2020

CR1155095 09/10/2020

Corrective Action CR1151508

Documents

Resulting from

Inspection

Drawings 12050-FM-091A Containment Quench and Recirc Spray Subsystem, Unit 2 32

Procedures 0-PT-9.4 Inspection of Roof Drains, Yard Drains, Roofs, and BDB 5

Lip Flood Barriers

1-PT-36.3.1 Reactor Protection and ESF RTD Response-Time Test 16

Inspection Type Designation Description or Title Revision or

Procedure Date

1-PT-77.13A Control Room Chiller Equipment Performance Test (1-HV- 23

E-4A)

2-PT-63.1B Operations Periodic Test - Quench Spray System - B 36

Subsystem

ER-AA-IST-PMP- Inservice Testing of Pumps Implementation 9

101

Work Orders WO59203294489 0

WO59203294614 0

WO59203305922

71124.01 Corrective Action Condition Report Condition Reports Reviewed during the Inspection

Documents (CR) numbers:

CR1128473,

CR1130250,

CR1130457,

CR1130460,

CR1131921,

CR1132546,

CR1137961,

CR1139656,

CR1142362,

CR1149400, and

CR1153635

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

RP-AA-202 Radiological Posting Revision 13

RP-AA-203 Radiological Labeling and Marking Revision 5

RP-AA-222 Radiation Surveys Revision 3

RP-AA-223 Contamination Surveys Revision 4

RP-AA-225 Unrestricted Release of Material Revision 8

RP-AA-232 Radioactive Material Control Revision 9

RP-AA-274 Radiation Work Permits Revision 9

Radiation 20-2115/4 Remove Pressurizer Relief Valve 2RC-5V-255/C 09/15/2020

Surveys 20-2251 Unit 2 Reactor Cavity Survey 09/17/2020

20-2251 Reactor Gripper Tube Assembly 09/16/2020

20-2253 Remove Blind Flange in Fuel Transfer Canal 09/14/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

20-2254 Unit 2 Reactor Containment 292 Shutdown Survey 09/13/2020

RWP Survey 20- Second Quarter ISFSI Pad Survey 06/01/2020

2018

Survey RWP 20- First Quarter ISFSI Pad Survey 02/20/2020

218-1

Radiation Work 20-2024 Reactor Coolant Pump Motor Removal Revision 0

Permits (RWPs) 20-2115 Valves in HRA <50mr/hr Revision 0

20-2251 Rx Head Disassembly Revision 0

20-2253 Blind Flange Removal Revision 0

Self- Audit 20-06 Radiological Protection, Process Control Program, and 07/24/2020

Assessments Chemistry

PA #7487304 Radioactive Contamination Control Program Assessment 09/19/2019

PA7487345 Radioactive Material Control Program Assessment 09/19/2019

PIR 1145372 Radiological Protection Review Dominion Fleet Collective February

Radiation Exposure (CRE) Performance t 2020

71124.03 Calibration LAC174790 Posi3 Complete SCBA Test 09/20/2020

Records LAC174790 Posi3 Complete SCBA Test 07/31/2019

LAC174790 Posi3 Complete SCBA Test 09/13/2018

LAC175813 Posi3 Complete SCBA Test 09/02/2020

LAC175813 Posi3 Complete SCBA Test 07/25/2019

LAC175818 Posi3 Complete SCBA Test 09/19/2019

LAC175825 Posi3 Complete SCBA Test, 09/12/2020 09/12/2020

LAC175825 Posi3 Complete SCBA Test 02/19/2020

LAC175825 Posi3 Complete SCBA Test 01/31/2019

Corrective Action CR1104267, Condition Reports Reviewed during the Inspection Various

Documents CR1128465, and

CR1141954

Miscellaneous 0-PT-114 Emergency Kit Inspection [of full face respirators] dated Various

2/26/2020, 05/21/2020, 06/16/2020, 07/14/2020, and

08/19/2020

2-SA-109 Grade D 2-SA-109 Grade D Air Certificate 02/18/2020

Air Certificate

2-SA-109 Grade D 2-SA-109 Grade D Air Certificate 08/29/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Air Certificate

2-SA-111 Grade D 2-SA-111 Grade D Air Certificate 08/29/2019

Air Certificate

2-SA-111 Grade D 2-SA-111 Grade D Air Certificate 02/18/2020

Air Certificate

LAC175825 SCBA Repair Log 09/12/2020

Paint Shop Grade D Paint Shop Grade D Air Certificate 02/18/2020

Air Certificate

Paint Shop Grade D Paint Shop Grade D Air Certificate 08/29/2019

Air Certificate

RP-AA-163, Monthly Radiological Use SCBA Inspection Record for Various

July, August, and September 2020

Operability 1-PT-76.10A, 1-PT-76.10A, CONTROL ROOM EMERGENCY 02/12/2020

Evaluations CONTROL ROOM VENTILATION SYSTEM LABORATORY ANALYSIS

EMERGENCY FOR

VENTILATION 1-HV-FL-8, Feb. 2020

SYSTEM

LABORATORY

ANALYSIS FOR

1-HV-FL-8, Feb.

20

1-PT-76.12B, 1-PT-76.12B, CONTROL ROOM EMERGENCY 01/20/2020

CONTROL ROOM VENTILATION SYSTEM - POST-MAINTENANCE TEST

EMERGENCY ON THE HEPA FILTER OF 1-HV-FL-9, Jan. 2020

VENTILATION

SYSTEM - POST-

MAINTENANCE

TEST ON THE

HEPA FILTER OF

1-HV-FL-9, Jan.

20

O-PT-77.14A - O-PT-77.14A - ECCS PREACS TRAIN A FILTER IN- 09/10/2019

ECCS PREACS PLACE TEST (1 -H V-FL-3A)

TRAIN A FILTER

Inspection Type Designation Description or Title Revision or

Procedure Date

IN-PLACE TEST (1

-H V-FL-3A)

O-PT-77.14B - O-PT-77.14B - ECCS PREACS TRAIN B FILTER IN- 11/14/2018

ECCS PREACS PLACE TEST (1-HV-FL-3B)

TRAIN B FILTER

IN-PLACE TEST (1-

HV-FL-3B)

O-PT95.3 - FUEL O-PT95.3 - FUEL BUILDING VENTILATION SYSTEM - 09/06/2019

BUILDING NEGATIVE PRESSURE TEST

VENTILATION

SYSTEM -

NEGATIVE

PRESSURE TEST

RP-AA-163, RP-AA-163 Inspection and Inventory of Respiratory 07/16/2020

Protection Equipment-July 2020

RP-AA-163, RP-AA-163, Inspection and Inventory of Respiratory 08/17/2020

Protection Equipment - August 2020

Procedures C-HP-1033.620 PORTABLE AIR SAMPLERS CALIBRATION AND Rev. 9

OPERATION

C-HP-1033.640 PORTABLE SAMPLING PUMPS CALIBRATION AND Rev. 6

OPERATION

C-HP-1033.650 RADECO RAD-PRO 5/10 PERSONAL AIR SAMPLERS: Rev. 1

CALIBRATION AND OPERATION

C-HP-1042.122 QUANTITATIVE FIT TESTING: PORTACOUNT PRO FIT Rev. 12

TESTING SYSTEM

C-HP-1042.210 RESPIRATORY HAZARDS EVALUATION AND Rev. 4

RESPIRATORY PROTECTION SELECTION

C-HP-1042.220 AIRBORNE RADIOACTIVE MATERIAL EXPOSURE Rev. 4

AUTHORIZATION

C-HP-1042.510 ATMOSPHERE-SUPPLYING RESPIRATORY Rev. 8

EQUIPMENT PERFORMANCE VERIFICATION

C-HP-1042.520 RESPIRATORY PROTECTION PROGRAM EQUIPMENT Rev. 6

CRITERIA AND VERIFICATION

HP-1042.405 RESPIRATORY PROTECTION EQUIPMENT: CLEANING Rev. 6

Inspection Type Designation Description or Title Revision or

Procedure Date

AND CONTAMINATION MONITORING

HP-1042.451 SELF-CONTAINED BREATHING APPARATUS Rev. 5

MAINTENANCE

HP-1042.525 USE OF THE POSICHEK 3 COMPUTERIZED Rev. 4

PERFORMANCE TESTER TO VERIFY PERFORMANCE

OF RESPIRATORY PROTECTION EQUIPMENT

RP-AA-160 Donning and Removal of Respiratory Protection Rev. 0

Equipment

RP-AA-162 Issue and Control of Respiratory Protection Equipment Rev. 5

RP-AA-163 Inspection and Inventory of Respiratory Protection Rev. 6

Equipment

RP-AA-226 ALPHA MONITORING Rev. 5

RP-AA-243 Portable HEPA Ventilation Units Rev. 4

RP-AA-300 ALARA Reviews and Reports Rev. 10

Self- Assessment # Radiological Respiratory Protection Program Review 11/12/2019

Assessments PA7487388

71124.04 Corrective Action CR1117838, Condition Reports Reviewed during the Inspection Various

Documents CR1117959, and

CR1131001

Miscellaneous North Anna Unit 1 North Anna Unit 1 Alpha Source Term Characterization for 08/08/2019

Alpha Source Term N1R27

Characterization for

N1R27

North Anna Unit 2 North Anna Unit 2 Alpha Source Term Characterization for 01/28/2019

Alpha Source Term N2R26

Characterization for

N2R26

NVLAP NVLAP Accreditation Certificates (07/2017-06/2020) Various

Accreditation

Certificates

Procedures C-HP-1031.023 RWP DOSIMETRY: EXPOSURE CONTROL SUPPORT Rev. 9

C-HP-1041.057 WHOLE BODY COUNTING INDIVIDUALS USING THE Rev. 3

PM-7

C-HP-1042.210 RESPIRATORY HAZARDS EVALUATION AND Rev. 4

Inspection Type Designation Description or Title Revision or

Procedure Date

RESPIRATORY PROTECTION SELECTION

HP-1041.048 APEX INVIVO WHOLE BODY COUNTER: OPERATION Rev. 2

AND PERFORMANCE CHECKS

HP-1041.058 APEX INVIVO WHOLE BODY COUNTER: WHOLE BODY Rev. 0

COUNTING INDIVIDUALS

HP-1041.068 APEX INVIVO WHOLE BODY COUNTER: CALIBRATION Rev. 3

RP-AA-104 Internal Radiation Exposure Control Program Rev. 2

RP-AA-105 External Radiation Exposure Control Program Rev. 2

RP-AA-124 Dosimetry Investigation and Processing Rev. 9

RP-AA-131 Whole Body Monitoring Rev. 2

RP-AA-132 Urine and Fecal Sampling and Analysis Rev. 1

RP-AA-133 Internal Dose Calculation Based on Radionuclide Intake Rev. 0

RP-AA-134 Radionuclide Intake Determination Based on Bioassay Rev. 2

Results

RP-AA-136 Internal Dose Calculations Based on DAC-Hour Exposure Rev. 0

RP-AA-138 Declared or Expected Pregnant Woman Rev. 2

RP-AA-224 Airborne Radioactivity Surveys Rev. 5

RP-AA-230 Personnel Contamination Monitoring and Decontamination Rev. 12

RP-AA-274 Radiation Work Permits Rev. 9

Radiation 0-HSP-ISFSI-001 INDEPENDENT SPENT FUEL STORAGE INSTALLATION 08/26/2019

Surveys (ISFSI), HEALTH PHYSICS TLD SURVEY

SURVEILLANCE

0-HSP-ISFSI-001 INDEPENDENT SPENT FUEL STORAGE INSTALLATION 12/10/2019

(ISFSI), HEALTH PHYSICS TLD SURVEY

SURVEILLANCE

0-HSP-ISFSI-001 INDEPENDENT SPENT FUEL STORAGE INSTALLATION 02/24/2020

(ISFSI), HEALTH PHYSICS TLD SURVEY

SURVEILLANCE

0-HSP-RCAD-001 1 QTR RESTRICTED AND CONTROLLED AREA DOSE 06/15/2020

EVALUATION

0-HSP-RCAD-001 1 QTR RESTRICTED AND CONTROLLED AREA DOSE 06/19/2019

EVALUATION

0-HSP-RCAD-001 2 QTR RESTRICTED AND CONTROLLED AREA DOSE 09/20/2019

EVALUATION

Inspection Type Designation Description or Title Revision or

Procedure Date

0-HSP-RCAD-001 3 QTR RESTRICTED AND CONTROLLED AREA DOSE 12/16/2019

EVALUATION

0-HSP-RCAD-001 4 QTR RESTRICTED AND CONTROLLED AREA DOSE 03/27/2020

EVALUATION

71124.05 Calibration 0-ICP-LW-RM-110 LIQUID WASTE EVAPORATOR RADIATION MONITOR 05/07/2019

Records (RM-LW-1 10) CALIBRATION

0-PT-44.2.48 PROCESS VENT NORMAL AND HIGH RANGE 09/14/2018

EFFLUENT RADIATION MONITOR (GW-RM-178)

CHANNEL CALIBRATION

0-PT-44.2.48 PROCESS VENT NORMAL AND HIGH RANGE 03/17/2020

EFFLUENT RADIATION MONITOR

(GW-RM-178) CHANNEL CALIBRATION

1-PT-38.2.2 LIQUID WASTE CLARIFIER RADIATION MONITOR (RM- 08/24/2018

LW-111) CHANNEL CALIBRATION

2-PT-34.8.5.3 CONTAINMENT RADIATION MONITORING 03/22/2019

INSTRUMENT CALIBRATION (RMS-265)

2-PT-34.8.5.4 CONTAINMENT RADIATION MONITORING 03/22/2019

INSTRUMENT CALIBRATION (RMS-266)89-400 SN: 8282 DOSE RATE PROFILES FOR 89-400 SN: 8282 SOURCE 06/16/2020

89-400 SN:8256 DOSE RATE PROFILES FOR 89-400 SN:8256 SOURCE 06/16/2020

I -PT-38 2.2 LIQUID WASTE CLARIFIER RADIATION MONITOR (RM- 08/29/2019

LW-111) CHANNEL CALIBRATION

Corrective Action CR1105666, Condition Reports Reviewed during the Inspection Various

Documents CR1114718,

CR1128265,

CR1128445,

CR1129493,

CR1131469,

CR1138758,

CR1139938,

CR1142555, and

CR1142758

Miscellaneous 1 & 3 QTR 1 & 3 QTR RESULTS OF RADIOCHEMISTRY CROSS Various

Inspection Type Designation Description or Title Revision or

Procedure Date

RESULTS OF CHECK PROGRAM (INSTRUMENT

RADIOCHEMISTRY INTERCOMPARISON: 2018)

CROSS CHECK

PROGRAM (2018)

Co-60 Source Co-60 Source Number 6012 Calibration Certificate 10/19/2000

Number 6012

Calibration

Certificate

Cs-137 Source Cs-137 Source Number 02-691 Calibration Certificate 07/1989

Number 02-691

Calibration

Certificate

CS-137 Source CS-137 Source Number 02-754 Calibration Certificate 07/1989

Number 02-754

Calibration

Certificate

TL-204 Source TL-204 Source Number 6054 Calibration Certificate 10/19/2000

Number 6054

Calibration

Certificate

Operability 1-PT-38.1.12 CONDENSER AIR EJECTOR IN-LINE RADIO GAS 02/04/2020

Evaluations RADIATION MONITOR (1-SV-RM-121) QUARTERLY

CHANNEL OPERATIONAL TEST

2-PT-44.2.32 Main Steam Loop A Noble Gas High Range Effluent 07/28/2020

Radiation Monitor (2-MS-RM-270) Channel Operational

Test

Procedures C-HP-1033.012 PORTABLE RADIATION PROTECTION Rev. 7

INSTRUMENTATION CONTROL

C-HP-1033.440 NE TECHNOLOGY SAM-9/SAM-11 CALIBRATION AND Rev. 10

OPERATION

C-HP-1033.533 MGP TELEPOLE: CALIBRATION AND OPERATION Rev. 4

C-HP-1033.650 RADECO RAD-PRO 5/10 PERSONAL AIR SAMPLERS: Rev. 1

CALIBRATION AND OPERATION

HP-1033.022 JL SHEPHERD MODEL 89 SHIELDED CALIBRATION Rev. 4

Inspection Type Designation Description or Title Revision or

Procedure Date

SYSTEM, OPERATION AND SURVEILLANCE

Self- PA7793983 Self-Assessment (Instruments) 2020 06/22/2020

Assessments

Work Orders 59101904056 RAD MONITOR REPAIR 03/24/2017

59102865764 IPM/01-RM-RM-157 (RAD MONITOR CALIBRATION) 05/18/2017

59103069394 IPM/01-LW-RM-110 (RAD MONITOR CALIBRATION) 05/08/2019

59103085831 IPM/01-RM-RM-157 (RAD MONITOR CALIBRATION) 08/21/2019

71151 Corrective Action CR1117403, Condition reports reviewed during inspection Various

Documents CR1128633,

CR1136184, and

CR1137727

Miscellaneous Electronic March 2019 through August 2020 Various

Dosimeter

Dose/Dose Rate

Alarm Log

HP-3010.032 Gaseous Effluents Cumulative Dose Summary (January- 08/05/2020

July/2020)

HP-3010.22 Liquid Effluents Cumulative Dose Summary (January- 08/05/2020

July/2020)

ML20122A157 North Anna Power Station 2019 Annual Radiological

Environmental Operating Report

Procedures LI-AA-500 NRC/INPO/WANO Performance Indicator and MOR Rev. 3

Reporting

PI-AA-100-1000 Performance Indicators Rev. 5

RP-AA-112 Radiation Safety Performance Indicator Reporting Rev. 4

71152 Calculations EE-0857 NAPS Station Batter 1-III Voltage Profile Calculation 0

Corrective Action CA004535 01/08/2007

Documents CR1143414 3/18/2020

CR1152771 08/03/2020

CR1153807 08/20/2020

Miscellaneous PI-AA-100-1003 -- Performance Improvement Action Plan 0

71153 Miscellaneous LER 2020-001-00 Technical Specification Required Shutdown due to Reactor 0

Coolant System Pressure Boundary Leakage

Inspection Type Designation Description or Title Revision or

Procedure Date

LER 2020-001-01 Degraded Upper Cylinder Piston Pin Bushing Discovered 1

during Maintenance Activities on Emergency Diesel

Generator

2