IR 05000338/2020003
| 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
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:
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
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 Section Status LER 05000338/2020-001-01 Degraded Upper Cylinder Piston Pin Bushing Discovered during Maintenance Activities on Emergency Diesel Generator [Rev. 1]
71153 Closed LER 05000338/2020-001-00 Degraded Upper Cylinder Piston Pin Bushing Discovered during Maintenance Activities on Emergency Diesel Generator [Rev. 0]
71153 Closed EDG EA-20-092 Enforcement Action (EA) 20-092: 1J Emergency Diesel Generator (EDG)
Exceeded TS Allowed Outage Time -
Violation Without a Performance Deficiency 71153 Closed
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.03) (1 Sample)
- (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) (2 Samples)
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) (5 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) 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) (1 Sample)
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) (1 Sample)
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) (2 Samples)
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) (4 Samples)
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)
- (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 Sample)
- (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 Sample)
- (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 Sample)
- (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.
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 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
- 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:
- (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 Sample)
- (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
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) (6 Samples)
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 Sample)
- (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 Discretion Enforcement Action EA-20-092: 1J Emergency Diesel Generator (EDG) Exceeded TS Allowed Outage Time - Violation Without a Performance Deficiency 71153
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0-AP-41
Severe Weather Conditions
Corrective Action
Documents
CR1144261
2-QS-ICV-3001 has dried boric acid on valve stem and
stem nut
04/04/2020
CR1152813
2K-E7 (RS Pump Casing Cooling Tank Level Hi/Lo) is
locked in.
Corrective Action
Documents
Resulting from
Inspection
CR1151645
NRC Identified: equipment staged in yard near U1
QSPH/SFGDS
7/15/2020
Drawings
2050-FM-091B
Flow/Valve Operating Numbers Diagram Containment
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
Injection System
2-OP-7.10
Operation of Casing Cooling Subsystem of the Recirc
Spray System
2-OP-7.10A
Valve Checkoff - Casing Cooling System
2-OP-7.4A
Valve Checkoff - Quench Spray System
Corrective Action
Documents
Resulting from
Inspection
CR1153950
Fire Plans
0-FS-CT-1
Loss Prevention Fire Strategy, Cable Tray Spreading and
Battery Room 2-1, 1-1, 2-3, 1-3
1-FS-SBO-1
Station Blackout Building Fire Fighting Strategy
1-FS-SG-1
Fire Fighting Strategy for Safeguards Area Safe Shutdown
Equipment Unit 1
2-FS-MG-1
Fire Fighting Strategy for Motor Generator Set House Unit
2-FS-S-2
Fire Fighting Preplan for Cable Vault and Tunnel and 280'
Rod Drive Unit 2 Safe Shutdown Equipment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-FS-SG-1
Fire Fighting Strategy for Safeguards Area Safe Shutdown
Equipment Unit 2
Procedures
0-PT-105.3
Hose House Inspection
CM-AA-FPA-100
Fire Protection/ Appendix R (Fire Safe Shutdown) Program
Engineering
Evaluations
NOTEBK-PRA-
NAPS-IF.1B
Probabilistic Risk Assessment Model Notebook -
Partitioning and Source Identification and Characterization
- Flood Area Definition
NOTEBK-PRA-
NAPS-IF.2
Probabilistic Risk Assessment Model Notebook - Internal
Flooding - Flood Scenario Development
Miscellaneous
DNES-AA-GN-BAR-
1001
Passive Design Features and Barriers
71111.07A Corrective Action
Documents
CR1116423,
CR1115668,
CR555082
NDE Reports
Final Eddy Current Inspection Report for 1-FC-E-1A
2/07/2019
Final Eddy Current Inspection Report for 1-FC-E-1B
2/20/2019
Procedures
ER-AA-HTX-10
Heat Exchanger Program
ER-AA-HTX-1004
Heat Exchanger Program Eddy Current Testing
71111.07T Calculations
NA-CALC-MEC-
ME-0530
Component Cooling Heat Exchanger Tube Plugging Study
Rev. 0
Corrective Action
Documents
CR1089486
Pipe Tee downstream of 1-SW-1110 Pin Hole Leak,
2/06/2018
CR1112654
Through-wall Leak on Service Water Socket Weld
associated with 2-CH-P-1A
2/17/2018
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
- Tube Identification, 1-CC-E-1A, North Anna Power
Station
Rev. 0
11715-FV-091B
Component Cooling Heat Exchangers Tube Sheet Bundle
- Tube Identification, 1-CC-E-1B, North Anna Power
Station
Rev. 2
Miscellaneous
System Health Report Q2-2020 - Service Water
July 15,
20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
89-572H
Letter from W.L. Stewart to United States Nuclear
Regulatory Commission, Virginia Electric and Power
Company North Anna Power Station Units 1 and 2
Consolidated Response to Generic Letter 89-13 Service
Water System Problems Affecting Safety-Related
Equipment"
October 18,
1991
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
System
Rev. 1
0-PT-75.15
Generic Letter 89-13 Service Water System Testing
Requirements Coordination
Rev. 8
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
Administrative Limits for Tube Plugging
Rev. 4
ER-NA-SYS-320
Generic Letter 89-13 Program
Rev. 6
VPAP-0811
Service Water System Inspection and Maintenance
Program
Rev. 6
71111.08P Calibration
Records
Dominion Energy Calibration Certificate: Digital
Thermometer (ATK-2)
4/25/2018
Dominion Energy Calibration Certificate: Digital
Thermometer (ATK-1)
7/22/2020
2018-59-003
Eastern NDT Certificate of Calibration: CA-811 Light Meter
(SN 1046JGCY)
11/30/2018
Corrective Action
Documents
CR1104243
Part 21 Notification: CRDM Sleeve Vulnerability
08/29/2018
CR1156057
Discoloration Noted on RV Head Surface
09/22/2020
Engineering
Evaluations
BACCP Evaluation Form: Boric Acid Found on 2-SS-TV-
200B
05.02.2019
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
Case N-566-2 Compliance for 2-RC-P-1A
4/13/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ETE-NA-2019-1002
Steam Generator Condition Monitoring and Operational
Assessment North Anna Unit 2
Rev. 0
Miscellaneous
Curtiss-Wright Personnel Certification Statement: UT
(Sauter)
07/24/2020
Curtiss-Wright Certification of Visual Acuity and Color
Vision per LMT Procedure PVE-1 (Sauter)
07/24/2020
Ray-Check Mfg. Inc. Certificate of Compliance: Angle
Beam Test Block (S/N 05-5560, S/N 05-8258)
9/6/05
Curtiss-Wright Personnel Certification Statement: UT
(Fish)
07/15/2020
Curtiss-Wright Certification of Visual Acuity and Color
Vision per LMT Procedure PVE-1 (Fish)
8/21/2020
Curtiss-Wright Personnel Certification Statement: UT
(Cochran)
07/15/2020
Curtiss-Wright Certification of Visual Acuity and Color
Vision per LMT Procedure PVE-1 (Cochran)
03/13/2020
ITLS Vision Acuity Certification (Dunn)
1/29/2019
Industrial Testing Laboratory Services, L.L.C. Certificate of
Qualification and Certification Summary: PT (Dunn)
2/5/2019
Curtiss-Wright Personnel Certification Statement: UT
(Hacker)
2/11/2018
Curtiss-Wright Certification of Visual Acuity and Color
Vision per LMT Procedure PVE-1 (Hacker)
8/15/18
Magnaflux Certificate of Certification: Spotcheck Developer
SKD-S2 (Batch 14F02K)
6/20/14
Magnaflux Certificate of Certification: Spotcheck Penetrant
SKL-SP2 (Batch 15J02K)
09/08/2015
Magnaflux Certification: Ultragel II Couplant (Batch
17F087)
06/30/2017
NDE Reports
UT-20-011
UT Calibration/Examination Record: 12050-WMKS-
0102D/6-WFPD-419/27 (BPL 551)
9/17/2020
UT-20-019
UT Calibration/Examination Record: 12050-WMKS-RC-E-
2/2-RC-E-2/1
9/22/2020
UT-20-020
UT Calibration/Examination Record: 12050-WMKS-RC-R-
9/25/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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)
Inspections
Rev. 13
ER-AP-BAC-102
Boric Acid Corrosion Control Program (BACCP)
Evaluations
Rev. 14
Work Orders
Replacement of A Loop Drain Piping
Rev. 0
Corrective Action
Documents
CA7876917
Maintenance Rule (MR) Functional Failure Evaluation for
1-EE-EG-1J Upper Crank Debris
04/24/2020
CA7908528
Perform maintenance rule functional failure evaluation for
1H EDG
05/28/2020
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
11715-ESK-11C
Elem. Diagram Emer Diesel Gen 1H Unit1, Sheet 2
Procedures
ER-AA-MRL-100
Implementing Maintenance Rule
Procedures
0-GOP-13.3
Assessment of Maintenance Activities for Potential Loss of
Reactor Coolant Inventory
2-OP-5.4
Draining the Reactor Coolant System
Corrective Action
Documents
CA8082309
Investigate "self-test" programming of seismic sudden
pressure relay
08/14/2020
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
Transformer Protection, Units 1 and 2, Sheet 3
Engineering
Changes
NA-20-00058
Splash Guard on 1-FW-T-2 Turbine Shaft
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
Water in oil discovered from 1-FW-P-2 following quarterly
PT performance
Miscellaneous
Troubleshooting
Sheet for
CR1152481
Unit 2 IAC Rod Control Cabinet
Procedures
1-AR-42
1-EP-ST-2C, C Reserve Station Service Transformer
Corrective Action
Documents
CA7672277
SW MOVs HBC-0 Qualified Stroke Count Exceeded
Engineering
Changes
NA-20-00006
2-SW-MOV-203A/C and 2-SW-MOV-204A/C Replacement
Miscellaneous
DNES-VA-EEN-
0011, Attachment 5
Standard for Protective Device Settings, Thermal Overload
Relays and Heater Coil Selection GL-89-10 MOVs
Procedures
0-MCM-0803-01
Repair of the Control Room Air Conditioning Chillers (1/2-
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
Work Orders
203311984
Repair of MIC Leak in SW piping associated with 2-CH-P-
1C
7/7/2020
203311997
Remove/Reinstall Piping to Support MIC Leak
7/7/2020
Corrective Action
Documents
CR1154838
09/06/2020
CR1156216
09/24/2020
CR1156222
09/24/2020
Procedures
2-OP-3.7
Unit Shutdown from Mode 1 to Mode 5 for Refueling
Corrective Action
Documents
CR1151128
CR1155066
09/10/2020
CR1155095
09/10/2020
Corrective Action
Documents
Resulting from
Inspection
CR1151508
Drawings
2050-FM-091A
Containment Quench and Recirc Spray Subsystem, Unit 2
Procedures
0-PT-9.4
Inspection of Roof Drains, Yard Drains, Roofs, and BDB
Lip Flood Barriers
1-PT-36.3.1
Reactor Protection and ESF RTD Response-Time Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-PT-77.13A
Control Room Chiller Equipment Performance Test (1-HV-
E-4A)
2-PT-63.1B
Operations Periodic Test - Quench Spray System - B
Subsystem
ER-AA-IST-PMP-
101
Inservice Testing of Pumps Implementation
Work Orders
Corrective Action
Documents
Condition Report
(CR) numbers:
CR1128473,
CR1130250,
CR1130457,
CR1130460,
CR1131921,
CR1132546,
CR1137961,
CR1139656,
CR1142362,
CR1149400, and
CR1153635
Condition Reports Reviewed during the Inspection
Procedures
Access Controls for High and Very High Radiation Areas
Revision 10
Radiological Posting
Revision 13
Radiological Labeling and Marking
Revision 5
Radiation Surveys
Revision 3
Contamination Surveys
Revision 4
Unrestricted Release of Material
Revision 8
Radioactive Material Control
Revision 9
Radiation Work Permits
Revision 9
Radiation
Surveys
20-2115/4
Remove Pressurizer Relief Valve 2RC-5V-255/C
09/15/2020
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
Procedure
Type
Designation
Description or Title
Revision or
Date
20-2254
Unit 2 Reactor Containment 292 Shutdown Survey
09/13/2020
RWP Survey 20-
2018
Second Quarter ISFSI Pad Survey
06/01/2020
Survey RWP 20-
218-1
First Quarter ISFSI Pad Survey
2/20/2020
Radiation Work
Permits (RWPs)
20-2024
Reactor Coolant Pump Motor Removal
Revision 0
20-2115
Valves in HRA <50mr/hr
Revision 0
20-2251
Rx Head Disassembly
Revision 0
20-2253
Blind Flange Removal
Revision 0
Self-
Assessments
Audit 20-06
Radiological Protection, Process Control Program, and
Chemistry
07/24/2020
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
Radiation Exposure (CRE) Performance t
February
20
Calibration
Records
LAC174790
Posi3 Complete SCBA Test
09/20/2020
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
2/19/2020
LAC175825
Posi3 Complete SCBA Test
01/31/2019
Corrective Action
Documents
CR1104267,
CR1128465, and
CR1141954
Condition Reports Reviewed during the Inspection
Various
Miscellaneous
0-PT-114
Emergency Kit Inspection [of full face respirators] dated
2/26/2020, 05/21/2020, 06/16/2020, 07/14/2020, and
08/19/2020
Various
2-SA-109 Grade D
Air Certificate
2-SA-109 Grade D Air Certificate
2/18/2020
2-SA-109 Grade D
2-SA-109 Grade D Air Certificate
08/29/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Air Certificate
2-SA-111 Grade D
Air Certificate
2-SA-111 Grade D Air Certificate
08/29/2019
2-SA-111 Grade D
Air Certificate
2-SA-111 Grade D Air Certificate
2/18/2020
LAC175825
SCBA Repair Log
09/12/2020
Paint Shop Grade D
Air Certificate
Paint Shop Grade D Air Certificate
2/18/2020
Paint Shop Grade D
Air Certificate
Paint Shop Grade D Air Certificate
08/29/2019
Monthly Radiological Use SCBA Inspection Record for
July, August, and September 2020
Various
Operability
Evaluations
1-PT-76.10A,
CONTROL ROOM
EMERGENCY
VENTILATION
SYSTEM
LABORATORY
ANALYSIS FOR
1-HV-FL-8, Feb.
20
1-PT-76.10A, CONTROL ROOM EMERGENCY
VENTILATION SYSTEM LABORATORY ANALYSIS
FOR
1-HV-FL-8, Feb. 2020
2/12/2020
1-PT-76.12B,
CONTROL ROOM
EMERGENCY
VENTILATION
SYSTEM - POST-
MAINTENANCE
TEST ON THE
HEPA FILTER OF
1-HV-FL-9, Jan.
20
1-PT-76.12B, CONTROL ROOM EMERGENCY
VENTILATION SYSTEM - POST-MAINTENANCE TEST
ON THE HEPA FILTER OF 1-HV-FL-9, Jan. 2020
01/20/2020
O-PT-77.14A -
ECCS PREACS
TRAIN A FILTER
O-PT-77.14A - ECCS PREACS TRAIN A FILTER IN-
PLACE TEST (1 -H V-FL-3A)
09/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
IN-PLACE TEST (1
-H V-FL-3A)
O-PT-77.14B -
ECCS PREACS
TRAIN B FILTER
IN-PLACE TEST (1-
HV-FL-3B)
O-PT-77.14B - ECCS PREACS TRAIN B FILTER IN-
PLACE TEST (1-HV-FL-3B)
11/14/2018
O-PT95.3 - FUEL
BUILDING
VENTILATION
SYSTEM -
NEGATIVE
PRESSURE TEST
O-PT95.3 - FUEL BUILDING VENTILATION SYSTEM -
NEGATIVE PRESSURE TEST
09/06/2019
RP-AA-163 Inspection and Inventory of Respiratory
Protection Equipment-July 2020
07/16/2020
RP-AA-163, Inspection and Inventory of Respiratory
Protection Equipment - August 2020
08/17/2020
Procedures
C-HP-1033.620
PORTABLE AIR SAMPLERS CALIBRATION AND
OPERATION
Rev. 9
C-HP-1033.640
PORTABLE SAMPLING PUMPS CALIBRATION AND
OPERATION
Rev. 6
C-HP-1033.650
RADECO RAD-PRO 5/10 PERSONAL AIR SAMPLERS:
CALIBRATION AND OPERATION
Rev. 1
C-HP-1042.122
QUANTITATIVE FIT TESTING: PORTACOUNT PRO FIT
TESTING SYSTEM
Rev. 12
C-HP-1042.210
RESPIRATORY HAZARDS EVALUATION AND
RESPIRATORY PROTECTION SELECTION
Rev. 4
C-HP-1042.220
AIRBORNE RADIOACTIVE MATERIAL EXPOSURE
AUTHORIZATION
Rev. 4
C-HP-1042.510
ATMOSPHERE-SUPPLYING RESPIRATORY
EQUIPMENT PERFORMANCE VERIFICATION
Rev. 8
C-HP-1042.520
RESPIRATORY PROTECTION PROGRAM EQUIPMENT
CRITERIA AND VERIFICATION
Rev. 6
HP-1042.405
RESPIRATORY PROTECTION EQUIPMENT: CLEANING
Rev. 6
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AND CONTAMINATION MONITORING
HP-1042.451
SELF-CONTAINED BREATHING APPARATUS
MAINTENANCE
Rev. 5
HP-1042.525
USE OF THE POSICHEK 3 COMPUTERIZED
PERFORMANCE TESTER TO VERIFY PERFORMANCE
OF RESPIRATORY PROTECTION EQUIPMENT
Rev. 4
Donning and Removal of Respiratory Protection
Equipment
Rev. 0
Issue and Control of Respiratory Protection Equipment
Rev. 5
Inspection and Inventory of Respiratory Protection
Equipment
Rev. 6
ALPHA MONITORING
Rev. 5
Portable HEPA Ventilation Units
Rev. 4
ALARA Reviews and Reports
Rev. 10
Self-
Assessments
Assessment #
PA7487388
Radiological Respiratory Protection Program Review
11/12/2019
Corrective Action
Documents
CR1117838,
CR1117959, and
CR1131001
Condition Reports Reviewed during the Inspection
Various
Miscellaneous
North Anna Unit 1
Alpha Source Term
Characterization for
N1R27
North Anna Unit 1 Alpha Source Term Characterization for
N1R27
08/08/2019
North Anna Unit 2
Alpha Source Term
Characterization for
N2R26
North Anna Unit 2 Alpha Source Term Characterization for
N2R26
01/28/2019
Accreditation
Certificates
NVLAP Accreditation Certificates (07/2017-06/2020)
Various
Procedures
C-HP-1031.023
RWP DOSIMETRY: EXPOSURE CONTROL SUPPORT
Rev. 9
C-HP-1041.057
WHOLE BODY COUNTING INDIVIDUALS USING THE
PM-7
Rev. 3
C-HP-1042.210
RESPIRATORY HAZARDS EVALUATION AND
Rev. 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RESPIRATORY PROTECTION SELECTION
HP-1041.048
APEX INVIVO WHOLE BODY COUNTER: OPERATION
AND PERFORMANCE CHECKS
Rev. 2
HP-1041.058
APEX INVIVO WHOLE BODY COUNTER: WHOLE BODY
COUNTING INDIVIDUALS
Rev. 0
HP-1041.068
APEX INVIVO WHOLE BODY COUNTER: CALIBRATION
Rev. 3
Internal Radiation Exposure Control Program
Rev. 2
External Radiation Exposure Control Program
Rev. 2
Dosimetry Investigation and Processing
Rev. 9
Whole Body Monitoring
Rev. 2
Urine and Fecal Sampling and Analysis
Rev. 1
Internal Dose Calculation Based on Radionuclide Intake
Rev. 0
Radionuclide Intake Determination Based on Bioassay
Results
Rev. 2
Internal Dose Calculations Based on DAC-Hour Exposure
Rev. 0
Declared or Expected Pregnant Woman
Rev. 2
Airborne Radioactivity Surveys
Rev. 5
Personnel Contamination Monitoring and Decontamination
Rev. 12
Radiation Work Permits
Rev. 9
Radiation
Surveys
0-HSP-ISFSI-001
INDEPENDENT SPENT FUEL STORAGE INSTALLATION
(ISFSI), HEALTH PHYSICS TLD SURVEY
SURVEILLANCE
08/26/2019
0-HSP-ISFSI-001
INDEPENDENT SPENT FUEL STORAGE INSTALLATION
(ISFSI), HEALTH PHYSICS TLD SURVEY
SURVEILLANCE
2/10/2019
0-HSP-ISFSI-001
INDEPENDENT SPENT FUEL STORAGE INSTALLATION
(ISFSI), HEALTH PHYSICS TLD SURVEY
SURVEILLANCE
2/24/2020
0-HSP-RCAD-001
QTR RESTRICTED AND CONTROLLED AREA DOSE
EVALUATION
06/15/2020
0-HSP-RCAD-001
QTR RESTRICTED AND CONTROLLED AREA DOSE
EVALUATION
06/19/2019
0-HSP-RCAD-001
QTR RESTRICTED AND CONTROLLED AREA DOSE
EVALUATION
09/20/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-HSP-RCAD-001
QTR RESTRICTED AND CONTROLLED AREA DOSE
EVALUATION
2/16/2019
0-HSP-RCAD-001
QTR RESTRICTED AND CONTROLLED AREA DOSE
EVALUATION
03/27/2020
Calibration
Records
0-ICP-LW-RM-110
LIQUID WASTE EVAPORATOR RADIATION MONITOR
(RM-LW-1 10) CALIBRATION
05/07/2019
0-PT-44.2.48
PROCESS VENT NORMAL AND HIGH RANGE
EFFLUENT RADIATION MONITOR (GW-RM-178)
CHANNEL CALIBRATION
09/14/2018
0-PT-44.2.48
PROCESS VENT NORMAL AND HIGH RANGE
EFFLUENT RADIATION MONITOR
(GW-RM-178) CHANNEL CALIBRATION
03/17/2020
1-PT-38.2.2
LIQUID WASTE CLARIFIER RADIATION MONITOR (RM-
LW-111) CHANNEL CALIBRATION
08/24/2018
2-PT-34.8.5.3
CONTAINMENT RADIATION MONITORING
INSTRUMENT CALIBRATION (RMS-265)
03/22/2019
2-PT-34.8.5.4
CONTAINMENT RADIATION MONITORING
INSTRUMENT CALIBRATION (RMS-266)
03/22/2019
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-
LW-111) CHANNEL CALIBRATION
08/29/2019
Corrective Action
Documents
CR1105666,
CR1114718,
CR1128265,
CR1128445,
CR1129493,
CR1131469,
CR1138758,
CR1139938,
CR1142555, and
CR1142758
Condition Reports Reviewed during the Inspection
Various
Miscellaneous
& 3 QTR
& 3 QTR RESULTS OF RADIOCHEMISTRY CROSS
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RESULTS OF
RADIOCHEMISTRY
CROSS CHECK
PROGRAM (2018)
CHECK PROGRAM (INSTRUMENT
INTERCOMPARISON: 2018)
Co-60 Source
Number 6012
Calibration
Certificate
Co-60 Source Number 6012 Calibration Certificate
10/19/2000
Cs-137 Source
Number 02-691
Calibration
Certificate
Cs-137 Source Number 02-691 Calibration Certificate
07/1989
CS-137 Source
Number 02-754
Calibration
Certificate
CS-137 Source Number 02-754 Calibration Certificate
07/1989
TL-204 Source
Number 6054
Calibration
Certificate
TL-204 Source Number 6054 Calibration Certificate
10/19/2000
Operability
Evaluations
1-PT-38.1.12
CONDENSER AIR EJECTOR IN-LINE RADIO GAS
RADIATION MONITOR (1-SV-RM-121) QUARTERLY
CHANNEL OPERATIONAL TEST
2/04/2020
2-PT-44.2.32
Main Steam Loop A Noble Gas High Range Effluent
Radiation Monitor (2-MS-RM-270) Channel Operational
Test
07/28/2020
Procedures
C-HP-1033.012
PORTABLE RADIATION PROTECTION
INSTRUMENTATION CONTROL
Rev. 7
C-HP-1033.440
NE TECHNOLOGY SAM-9/SAM-11 CALIBRATION AND
OPERATION
Rev. 10
C-HP-1033.533
MGP TELEPOLE: CALIBRATION AND OPERATION
Rev. 4
C-HP-1033.650
RADECO RAD-PRO 5/10 PERSONAL AIR SAMPLERS:
CALIBRATION AND OPERATION
Rev. 1
HP-1033.022
JL SHEPHERD MODEL 89 SHIELDED CALIBRATION
Rev. 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SYSTEM, OPERATION AND SURVEILLANCE
Self-
Assessments
PA7793983
Self-Assessment (Instruments) 2020
06/22/2020
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
Documents
CR1117403,
CR1128633,
CR1136184, and
CR1137727
Condition reports reviewed during inspection
Various
Miscellaneous
Electronic
Dosimeter
Dose/Dose Rate
Alarm Log
March 2019 through August 2020
Various
HP-3010.032
Gaseous Effluents Cumulative Dose Summary (January-
July/2020)
08/05/2020
HP-3010.22
Liquid Effluents Cumulative Dose Summary (January-
July/2020)
08/05/2020
North Anna Power Station 2019 Annual Radiological
Environmental Operating Report
Procedures
NRC/INPO/WANO Performance Indicator and MOR
Reporting
Rev. 3
Performance Indicators
Rev. 5
Radiation Safety Performance Indicator Reporting
Rev. 4
Calculations
EE-0857
NAPS Station Batter 1-III Voltage Profile Calculation
Corrective Action
Documents
CA004535
01/08/2007
CR1143414
3/18/2020
CR1152771
08/03/2020
CR1153807
08/20/2020
Miscellaneous
Performance Improvement Action Plan
Miscellaneous
LER 2020-001-00
Technical Specification Required Shutdown due to Reactor
Coolant System Pressure Boundary Leakage
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LER 2020-001-01
Degraded Upper Cylinder Piston Pin Bushing Discovered
during Maintenance Activities on Emergency Diesel
Generator
1