IR 05000338/2021002

Integrated Inspection Report 05000338/2021002 and 05000339/2021002

ML21208A018
Person / Time
Site:	North Anna
Issue date:	07/27/2021
From:	Stewart Bailey NRC/RGN-II/DRP/RPB4
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2021002
Download: ML21208A018 (22)

Text

July 27, 2021

SUBJECT:

NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2021002 AND 05000339/2021002

Dear Mr. Stoddard:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On July 15, 2021, the NRC inspectors discussed the results of this inspection with Fred Mladen and other members of your staff. The results of this inspection are documented in the enclosed report.

One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

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

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at North Anna Power Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Stewart N. Bailey, Chief Reactor Projects Branch 4 Division of Reactor Projects

Docket Nos. 05000338 and 05000339 License Nos. NPF-4 and NPF-7

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000338 and 05000339

License Numbers:

NPF-4 and NPF-7

Report Numbers:

05000338/2021002 and 05000339/2021002

Licensee:

Virginia Electric & Power Co.

Facility:

North Anna Power Station

Location:

Mineral, VA

Inspection Dates:

April 1, 2021 to June 30, 2021

Inspectors:

M. Tobin, Senior Resident Inspector

K. Carrington, Resident Inspector

B. Towne, Resident Inspector

B. Tindell, Reactor Engineer

B. Collins, Senior Reactor Inspector

C. Fontana, Emergency Preparedness Inspector

S. Sanchez, Senior Emergency Preparedness Insp

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

RCS Pressure Boundary Leakage Results in Condition Prohibited by Technical Specifications (TS)

Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000339/2021002-01 Open/Closed Not Applicable 71153 A self-revealed SL IV NCV of TS 3.4.13, RCS Operational Leakage and TS 3.4.4, RCS Loops - Mode 1 and 2 was identified for reactor coolant system pressure boundary leakage due to a cracked weld on the reactor coolant pump (RCP) seal injection piping for longer than the allowed completion time.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000339/2020-001-00 LER 2020-001-00 for North Anna Power Station, Unit 2,

Technical Specification Required Shutdown due to Reactor Coolant System Pressure Boundary Leakage 71153 Closed

PLANT STATUS

Unit 1 began the inspection period shutdown for refueling outage 1R28. The unit was restarted on April 22, 2021, and the turbine generator was synchronized to the grid on April 24, 2021.

The unit was returned to operating at or near rated thermal power on April 27, 2021. On May 6, 2021, the unit was shut down due to degrading condenser vacuum as a result of a leak inside the main condenser. The leak was repaired, and the unit was restarted on May 17, 2021.

The turbine generator was synchronized to the grid on May 17, 2021, and the unit was returned to operating at or near rated thermal power on May 19, 2021, where it remained through the end of the inspection period.

Unit 2 operated at or near rated thermal power for the entire 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 a 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

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems:

Emergency diesel generators (EDGs), heat trace systems, and ventilation systems on June 25, 2021.

71111.04 - Equipment Alignment

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

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

(1) Unit 1 high head safety injection system, on May 25, 2021;

(2) Unit 1 and Unit 2 fire loop, on May 24, 2021;

(3) Unit 2 'A' and 'B' motor-driven auxiliary feedwater (MDAFW) pump systems, on May 5, 2021;

(4) Unit 1 reactor coolant pump (RCP) oil seal collection system, on April 14, 2021; and

(5) Unit 1 hot-leg vent path, on April 14, 2021.

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 turbine building basement on June 15, 2021;

(2) Unit 1 safeguards alley building on June 7, 2021;

(3) Unit 1 and Unit 2 auxiliary service water pump rooms on April 25, 2021;

(4) Unit 1 quench spray building on April 18, 2021; and

(5) Unit 1 containment area on April 14, 2021.

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 A charging pump cubicle on April 15, 2021.

===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 April 5 - 9, 2021:

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

1. Ultrasonic Examination (UT)

a. 14" reactor coolant system weld (14-RC-10 / 38B), ASME Class 1 (reviewed)

2. Liquid Penetrant Examination (PT)

a. two 2" chemical & volume control system welds (welds 14 and 15; 01-CH-382-VALVE), ASME Class 1 (reviewed, including weld documentation)b. 6" safety injection system integral attachment (6-SI-133 / 19H), ASME Class 1 (reviewed)

3. Magnetic Particle Testing (MT)

a. 6" feedwater system weld (6-WFPD-18 / SW-42), Augmented ISI Item

4. Visual Testing (VT)

a. pressurizer manway bolting (1-RC-E-2 / MANWAY), ASME Class 1 (reviewed)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 Unit 1 refueling outage (RFO) 1R28 startup activities on April 22, 2021.

(2) The inspectors observed and evaluated licensed operator performance in the control room during shutdown and manual reactor trip of the Unit 1 reactor due to elevated chemistry parameters and loss of condenser vacuum associated with a main condenser leak on May 6, 2021.

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

(1) The inspectors observed and evaluated operator just-in-time training in the simulator associated with restart of the Unit 1 reactor from a forced outage on May 13, 2021.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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 2 risk associated with the June 16, 2021, testing of the turbine-drive auxiliary feedwater (TDAFW) pump during overhaul of Unit 2 C main feed pump, on June 29, 2021;

(2) Emergent risk associated with Unit 1 down power due to increased sodium levels in the steam generators, on May 17, 2021;

(3) Unit 1 loss of containment air cooling with B RSST supplied from its alternate feed and impending severe weather during the week of May 5, 2021; and

(4) Unit 1 heavy lift of the low pressure turbine rotor and contact with piping that occurred on March 29, 2021.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

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

(1) CR 1168035, Quench spray pump thrust bearing installed backwards, on June 25, 2021;

(2) CRs 1168069, 1168094; 1163599, Hot-leg and cold-leg recirculation MOV issues, on June 15, 2021;

(3) CR 1173238, Shutdown bank B rod E5 IRPI indication issues, on May 19, 2021;

(4) CR 1168848, Unit 1 MS-TV-101A check valve anti-rotation pin wear, on May 18, 2021;

(5) CR 1172779, Steam dump A only able to open to 85% travel, on May 16, 2021;

(6) CR 1167510, 1 FW-68 AFW check valve failed its backseat leakage test, on May 10, 2021; and

(7) CR 1167419, 2H EDG output breaker opened under full load during a surveillance test on March 11, 2021.

71111.18 - Plant Modifications

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

The inspectors evaluated the following temporary or permanent modifications:

(1) Design Change (DC) NA-17-00236, Unit 2 125 VDC Battery Charger Replacements (02-BY-BC-2-III)

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

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

(1)1J emergency diesel generator restoration following troubleshooting, on June 30, 2021;

(2) Unit 1 service water to recirculation spray heat exchanger MOVs following replacement, on June 25, 2021;

(3) Unit 1 main steam dump 1408A PMT (WO 59203365619) following removal of temporary modification, on May 25, 2021;

(4) Unit 1 turbine overspeed trip test following maintenance on April 23, 2021;

(5) Unit 1 TDAFW system PMT following turbine replacement, on April 14, 2021;

(6) Unit 1 MOV motor control center breaker bucket PMTs for valves 1-SI-MOV-1860A, 1-SI-MOV-1885A, and 1-SI-1885C following replacement, on April 14, 2021; and

(7) Unit 1 fuel transfer cart PMT following overload alarm on April 13, 2021.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)

(1) The inspectors evaluated refueling outage 1R28 activities from March 14 to April 24, 2021.

(2) The inspectors evaluated unplanned outage activities from May 6-19, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Unit 1 containment purge valve (penetration 90) leakage test, 1-PT-33.1, on June 15, 2021;

(2) Unit 1 service water flow balance test, 1-PT-75.6, on May 17, 2021; and

(3) Unit 2 motor-driven auxiliary feedwater pump (2-FW-P-3B) and valve test, 2-PT-71.3Q, on May 5, 2021.

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 RCS leakage detection test 1-PT-52.2A, for reactor vessel flange leakage concurrent with 1B RCP #2 seal degradation on May 20, 2021.

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

(1) Unit 1 containment isolation valve (penetration 56A) test, 1-PT-61.3, on April 14, 2021.

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of May 3, 2021.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the emergency response organization during the week of May 3, 2021.

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 May 3, 2021. This evaluation does not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of May 3, 2021.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) "D" team emergency preparedness drill on June 1,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified submittals for licensee performance indicators listed below:

MS07: High Pressure Injection Systems (IP Section 03.06)===

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

MS10: Cooling Water Support Systems (IP Section 03.09) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

BI02: RCS Leak Rate Sample (IP Section 03.11) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

EP01: Drill/Exercise Performance (IP Section 03.12) (1 Sample)

(1) Unit 1 (July 1, 2020, through March 31, 2021) Unit 2 (July 1, 2020, through March 31, 2021)

EP02: ERO Drill Participation (IP Section 03.13) (1 Sample)

(1) Unit 1 (July 1, 2020, through March 31, 2021) Unit 2 (July 1, 2020, through March 31, 2021)

EP03: Alert & Notification System Reliability (IP Section 03.14) (1 Sample)

(1) Unit 1 (July 1, 2020, through March 31, 2021) Unit 2 (July 1, 2020, through March 31, 2021)

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

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

(1) CR1165766, "Westinghouse Identified Potential Suspect NCD Cards." The inspectors selected this issue for annual follow-up since it was associated with a Part 21 report related to a potential defect in capacitor network cards procured by the site. The inspectors reviewed the site's corrective actions which included: a review of inventory, identification of affected cards, verification the defect was not present on cards installed in the plant; removal of any potentially affected cards from storage, and return of defected cards to the vendor for repair. The site performed additional follow-up actions as recommended by the vendor.

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

The inspectors evaluated the following licensee event report (LER):

(1) LER 2020-001-00 for North Anna Power Station, Unit 2, Technical Specification Required Shutdown due to Reactor Coolant System Pressure Boundary Leakage (ADAMS Accession No. ML20164A134). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated a manual trip on Unit 1 in response to a leak in the Unit 1 condenser and the licensees performance, on May 6,

INSPECTION RESULTS

RCS Pressure Boundary Leakage Results in Condition Prohibited by Technical Specifications Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000339/2021002-01 Open/Closed Not Applicable 71153 A self-revealed SL IV non-cited violation (NCV) of Technical Specification (TS) 3.4.13, RCS Operational Leakage and TS 3.4.4, RCS Loops - Mode 1 and 2 was identified for reactor coolant system pressure boundary leakage due to a cracked weld on the reactor coolant pump (RCP) seal injection piping for longer than the allowed completion time.

Description:

On April 6, 2020, at 0037, the station identified an increase in the unidentified leak rate as part of their normal monitoring, and entered licensee procedure 2-AP-16, Increasing Primary Plant Leakage due to an increase in unidentified leakage from 0.0247 gallons per minute (gpm) to 0.1081 gpm. At that time, the station immediately began taking appropriate actions to identify the source of the unidentified leakage. On April 9, 2020, at 0100, the station identified that a weld on the A RCP seal injection piping to the thermal barrier was leaking, which was defined as pressure boundary leakage, and was prohibited by TS 3.4.13. The station then began a controlled shutdown in accordance with the TS action statement to be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The licensee submitted licensee event report 05000339-2020-001-00.

Corrective Actions: The licensee repaired the weld by grinding out the defect and completing a repair weld. The station also implemented a non-destructive examination program on the similar welds for both North Anna Units 1 and 2, to be used until the welds are modified permanently.

Corrective Action References: CR1144530

Performance Assessment:

The NRC determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency.

Specifically, the equipment failure could not have been avoided or detected by the licensees quality assurance program or other related control measures. The weld in question was original from the equipment manufacturer, and had been in service for nearly 40 years. The station took prompt and reasonable actions to identify the location of the unidentified leakage and shut down within the required limiting condition for operation (LCO) completion time after identification.

Enforcement:

Reactor violations without a performance deficiency are dispositioned using the traditional enforcement process. Specifically, Enforcement Policy Section 2.2.4 states, in part, that violations dispositioned using traditional enforcement includesviolations not associated with ROP findings.

Severity: The inspectors reviewed Section 6.1.d.1 of the Enforcement Policy and determined this violation was characterized as a Severity Level IV because it was a failure to comply with a TS-required action for an LCO in Section 3.0.

Violation: North Anna Power Station, Unit 2 TS Subsection 3.4.13, RCS Operational Leakage, Condition B requires, in part, that if pressure boundary leakage exists, the unit must be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Additionally, TS Subsection 3.4.4, RCS Loops - Modes 1 and 2, requires that the unit must be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if there are not three operable RCS loops. Contrary to the above, between April 6, and April 9, 2020, three RCS loops were not operable due to pressure boundary leakage, and the unit was not placed in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Enforcement Action: This violation is being treated as a NCV, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On July 15, 2021, the inspectors presented the integrated inspection results to Mr. Fred Mladen and other members of the licensee staff.

• On May 6, 2021, the inspectors presented the Emergency Preparedness Program inspection results to Ms. Lisa Hilbert and other members of the licensee staff.

• On April 9, 2021, the inspectors presented the Unit 1 In-Service Inspection results to Mr. Fred Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Corrective Action

Documents

CRs 1171958,

1172022,

1171961,

1171918

Miscellaneous

National Weather Service-Watches, Warnings, and

Advisories for Mineral, Virginia

Procedures

0-AP-41

Severe Weather Conditions

0-GOP-4.1

Hot Weather Operations

0-GOP-5.5

EDG Hot Weather Operations

71111.04

Corrective Action

Documents

Resulting from

Inspection

CR1174226

CR1174227

CR1174228

CR1174229

CR1174230

CR1174231

CR1174233

CR1174236

CR1174238

CR1174239

CR1174240

CR1174241

Drawings

2000019-11715-

FM-074A, Sheet 1

Flow/Valve Operating Numbers Diagram Feedwater System

CS8820

Plant Fire Loop

Procedures

2-PT-71.3Q

2-FW-P-3B Motor-Driven AFW Pump, and Valve Test

71111.05

Fire Plans

1-FS-QS-1

Loss Prevention Fire Strategy for Quench Spray Building

(SG-74) Unit 1

Procedures

0-FS-TB-1

Turbine Building Fire Fighting Strategy

1-FS-ASWP-1

Auxiliary Service Water Pumphouse Fire Strategy

71111.06

Corrective Action

Documents

CA

8359916

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Drawings

11715-FB-090S,

sheet 1

Flow/Valve Operating Numbers Diagram Vent & Drain

System

Procedures

0-GOP-3.9

Weekly Check of Charging Pumps

0-MPM-1910-01

Flood Protection Floor Drain Backflow Preventer

Replacement

71111.08P

Corrective Action

Documents

CA8328174

1-CH-337 Pipe Cap Leaking

01/09/2021

CA8328175

1-CH-337 Pipe Cap Leak - Boric Acid Review

01/09/2021

CA8376965

Boric Acid Deposits downstream of 1-SI-79

03/14/2021

Engineering

Evaluations

BACCP Evaluation Form: 1-CH-P-1B, 1B Charging Pump

2.30.2019

BACCP Evaluation Form: 1-RS-P-3B, Casing Cooling Pump

01.19.2021

BACCP Evaluation Form: 1-SI-P-1A, Low-Head SI Pump

03.05.2020

Miscellaneous

Curtiss-Wright Personnel Certification Statement: PT-III (Van

Ruler)

01/08/2021

Curtiss-Wright Certification of Visual Acuity and Color Vision

per LMT Procedure PVE-1 (Van Ruler)

6/11/2020

Magnaflux Certification: Spotcheck Penetrant, SKL-SP2

(Batch #17J16K)

09/25/2017

20004041, Calibration Certificate: Digital Thermometer

(S/N 1074BGCY)

7/30/2020

Magnaflux Certification: Spotcheck Developer, SKD-S2

(Batch #18H12K)

08/23/2018

Curtiss-Wright Personnel Certification Statement: UT-II

(Kunze)

01/21/2021

Curtiss-Wright Certification of Visual Acuity and Color Vision

per LMT Procedure PVE-1 (Kunze)

6/3/2020

Magnaflux Certification: Ultragel II Couplant (Batch

1. 17F087)

06/30/2017

Curtiss-Wright Personnel Certification Statement: VT-1-II

(Van Ruler)

01/08/2021

Curtiss-Wright Personnel Certification Statement: MT-II

(Kunze)

01/21/2021

Magnaflux Certification: No. 2 Yellow Powder (Batch

1. 18H017)

08/06/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Dominion Energy Personnel Qualification and Certification

Record: VT (Eustice)

09/11/2020

Dominion Certification of Vision Examination (Eustice)

3/10/2021

Eastern NDT Certificate of Calibration: Light Meter (S/N

1044JGCY)

2/6/2021

Dominion ASME Section IX - Welder Performance

Qualification PQM 508 (Dods)

2/04/2019

Dominion ASME Section IX - Welder Performance

Qualification PQM801A (Dods)

04/26/2017

Curtiss-Wright Personnel Certification Statement: PT-III

(Cordes)

03/04/2021

Curtiss-Wright Certification of Visual Acuity and Color Vision

per LMT Procedure PVE-1 (Cordes)

7/20/2020

Curtiss-Wright Personnel Certification Statement: PT-II

(Grell)

2/04/2021

Curtiss-Wright Certification of Visual Acuity and Color Vision

per LMT Procedure PVE-1 (Grell)

6-1-2020

801

Procedure Qualification Record

2/20/01

805

Procedure Qualification Record

2/27/01

809

Procedure Qualification Record

2/21/01

830

Procedure Qualification Record

7/20/01

831

Procedure Qualification Record

7/20/01

BOP-PT-21-030

Liquid Penetrant Examination: 1-CH-382/Weld #15

3/9/2021

NDE Reports

BOP-PT-21-081

Liquid Penetrant Examination: 1-CH-382/Weld #14

4/1/2021

MT-21-002

Magnetic Particle Examination: 6-WFPD-18/SW-42

3/14/2021

PT-21-020

Liquid Penetrant Examination: 6-SI-133/19H

3/19/2021

UT-21-016

UT Calibration/Examination Record: 14-RC-10/38B

3/18/2021

VE-21-021

Visual Examination: 1-RC-R-1/RPVH and Nozzles

3/23/2021

VT-21-065

Visual Examination of Pressure Retaining Bolting (VT-1): 1-

RC-E-2/MANWAY

4/5/2021

Procedures

803

Welding Technique Sheet

CM-AA-NWP-102

Control of Welding Materials

ER-AA-NDE-MT-

Dry Magnetic Particle Examination Procedure Using Yokes

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

200

ER-AA-NDE-PT-

300

Visible Solvent Removable Liquid Penetrant Examination

Procedure

ER-AA-NDE-UT-

2

Ultrasonic Examination of Austenitic Piping Welds in

accordance with ASME Section XI, Appendix VIII

ER-AA-NDE-VT-

601

VT-1 Visual Examination Procedure

ER-AA-NDE-VT-

604

Visual Examination (VE) for Leakage of PWR Reactor Head

Penetrations

Work Orders

WO59203297018

Rockwell Edwards Valve Replacement: 1-CH-382 Valve

71111.11Q Corrective Action

Documents

CR1167501

71111.13

Corrective Action

Documents

CR1172015

CR116886

CR1168886

Engineering

Evaluations

ER-20210330-

1100

L-0 Blades Contact with MSR Pipe During Critical Pick

03/30/2021

Procedures

CH-99.600

Secondary Chemistry Specifications and Action Levels

71111.15

Corrective Action

Documents

CA8376988

CA8376332

Level of Effort Evaluation for CR 1167419

4/14/2021

CA8390883

1J EDG unable to accept load of 3000 KW 1-PT-83-12J

CA8381657

CA8381674

CR

1167510

CR 1163149

2H EDG output breaker tripped during a surveillance test

2/30/2020

CR1139164

1H EDG crankcase vacuum pressure trip 01/08/2020 PT-

2H (slow start)

CR1145061

1H EDG crankcase vacuum pressure trip 04/19/2020 PT-

2.2A (simulated LOOP)

CR1147420

CR1151019

1H EDG crankcase vacuum pressure trip 07/06/2020 PT-

2H (slow start)

CR1151058

1H EDG oil in the sensing line 07/07/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR1159712

2H EDG oil in the sensing line and pressure switch contacts

closed 10/29/2020

CR1168035

CR1168559

1J EDG crankcase vacuum pressure trip diesel 3/25/2021

CR1170953

Drawings

11714-FM-074,

Sheet 3

Flow/Valve Operating Numbers Diagram Feedwater System

11715-FM-074,

Sheet 1

Flow/Valve Operating Numbers Diagram Feedwater System

Miscellaneous

59-C432-00006

Vendor Technical Manual for Copes Vulcan Type D-100

Valves

RE502574

PM/Surveillance Detail Report

Procedures

1-DRP-02

Air Operated Valve Setpoints

ER-AA-IST-CKV-

104

ASME IST Program - Check Valve Condition Monitoring

Program Implementation

Work Orders

WO5903311344

71111.18

Corrective Action

Documents

CR1162213

Engineering

Changes

DC-NA-17-00236

Station Battery Chargers 2-III, 2-IV, 2C-III Replacement

Engineering

Evaluations

ETE-NA-2020-

0003

Documentation of Online Testing Method of a Third Station

Battery Charger

Miscellaneous

EE-0019

Station Battery Charger Specification for North Anna Power

Station

06/10/2016

EN 54520

Part 21 Report-Ametek 85-RP2675-01 Power Supply

Mounting Hardware

VTM-59-A705-

00001

Ametek Solid State Controls 250A Battery Charger

Instruction & Operating Manual with Drawings

11/26/2018

71111.19

Corrective Action

Documents

CR1172933

CR1167573

1J EDG minor speed oscillations when in Isochronous Mode

CR1168675

1J EDG load cannot be raised above 2800KW

CR1168720

1J EDG limited fuel rack movement

CR1168905

1J EDG discrepancies identified

CR1168968

1J EDG overspeed switch linkage noted with lock nut loose

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR1169140

1J EDG discrepancies identified with the 1J EDG #1 CS and

OCS injection pumps

CR1170249

EDG failed load reject time response for voltage during 1-

PT-83.12J

CR1167499

CR1167505

CR1168354

CR1168451

CR1168471

CR1168472

CR1168518

CR1168564

CR1168840

CR1169179

CR1169302

CR1169991

Drawings

2--C

North Anna FTS Carriage Wheel Study

000

CS9281

Wheel Bushing Data

Procedures

1-GEP-18

Stroking Service Water RSHZ MOVs Against Design

Condition Differential Pressure

1-PT-213.11

Valve Inservice Inspection (Service Water)

04/14/2021

1-PT-96.1

Refueling Systems Operability and Checkout

29-OTO2

DNES-AA-MOV-

1001

Dynamic Test Evaluation Review Checklist; Quarter Turn

Valve

04/10/2021

Work Orders

WO59203365619

WO59102915312

WO59203356018

71111.20

Corrective Action

Documents

CR1168434

CR1168601

Procedures

1-OP-1C.1

Estimated Critical Position Calculation Following Refueling

71111.22

Corrective Action

Documents

CR1171862

CR1168466

CR1169959

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Drawings

11715-FM-074A,

Sheet 1

Flow/Valve Operating Numbers Diagram Feedwater System

11715-FM-074A,

Sheet 2

Flow/Valve Operating Numbers Diagram Feedwater System

11715-FM-074A,,

Sheet 3

Flow/Valve Operating Numbers Diagram Feedwater System

11715-FM-078A

Flow/Valve Operating Numbers Diagram Service Water

System

11715-FM-078B

Flow/Valve Operating Numbers Diagram Service Water

System

Engineering

Evaluations

ETE-CEP-2019-

0005

Summary of Design Basis Accident Flow Rates for Pumps in

the North Anna IST Program

Procedures

1-PT-61.3

40

Valve Penetration Diagram - Penetration 56A

1-PT-75.2A.1

Service Water Pump (1-SW-P-1A) Head Curve Verification

1-PT-75.2B.1

Service Water Pump (1-SW-P-1B) Head Curve Verification

1-PT-75.6

Service Water Flow Balance

2-PT-71.3Q

2-FW-P-3B Motor-Driven AFW Pump and Valve Test

2-PT-75.2A.1

Service Water Pump (2-SW-P-1A) Head Curve Verification

2-PT-75.2B.1

Service Water Pump (2-SW-P-1B) Head Curve Verification

71114.06

Corrective Action

Documents

CR1174321

CR1174323

CR1174330

CR1174467

CR1174468

CR1174469

71152

Corrective Action

Documents

CR1165766

CA8355323

CA8355877

CA8357163

Miscellaneous

List of Installed NCD Cards at North Anna with Serial

numbers C2008-041. -042, -043, -044, -045, and C1948-005

PO 4500565887

10/25/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SAP-N-

200214159

03/12/2021

71153

Miscellaneous

North Anna Unit 1 Post Trip Review Report

05/09/2021