IR 05000338/2019003
| ML19318D724 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/13/2019 |
| From: | Bradley Davis Division Reactor Projects II |
| To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| Geanette D | |
| References | |
| IR 2019003 | |
| Download: ML19318D724 (24) | |
Text
November 13, 2019
SUBJECT:
NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2019003 AND 05000339/2019003
Dear Mr. Stoddard:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On October 9, 2019, the NRC inspectors discussed the results of this inspection with Ms. Lisa Hilbert, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Bradley J. Davis, Chief Reactor Projects Branch 4 Division of Reactor Projects
Docket Nos. 05000338 and 05000339 License Nos. NPF-4 and NPF-7
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000338 and 05000339
License Numbers:
Report Numbers:
05000338/2019003 and 05000339/2019003
Enterprise Identifier:
I-2019-003-0029
Licensee:
Virginia Electric & Power Co.
Facility:
North Anna Power Station
Location:
Mineral, VA
Inspection Dates:
July 1, 2019 to September 30, 2019
Inspectors:
B. Collins, Reactor Inspector
J. Diaz-Velez, Senior Health Physicist
G. Eatmon, Resident Inspector
R. Kellner, Senior Health Physicist
W. Pursley, Health Physicist
M. Tobin, Senior Resident Inspector
Approved By:
Bradley J. Davis, 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 URI 05000338,05000339/20 19010-03 Potential 50.9 Violation for Incomplete Information Submittal 71111.21N Closed LER 05000339/2019-001-00 LER 2019-001-00 for North Anna Unit 2, Manual Reactor Trip on Degrading Condenser Vacuum due to a Failed Weld.
71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On September 7, the unit was down powered for a planned refueling outage. The unit remained shut down for the remainder 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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on July 30, 2019.
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 train "J" electrical lineup during the 3-year overhaul of the "H" diesel on July 13, 2019
- (2) Unit 1 Low Head Safety Injection (LHSI) System train B on August 23, 2019.
- (3) Unit 1 primary grade water flow path isolation secured closed in Mode 3, 4, 5, and 6 on September 28, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 High Head Safety Injection system train B on July 29, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 1 motor driven auxiliary feedwater pump house and turbine driven auxiliary feedwater pump house on August 14, 2019
- (2) Unit 1 and Unit 2 service water pump house on August 20, 2019
- (3) Unit 1 and Unit 2 Auxiliary building (all elevations) on September 24, 2019
- (4) Unit 1 Containment building (all elevations) on September 24, 2019
- (5) Unit 1 and Unit 2 Emergency Diesel Generator pump rooms on September 25, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1, main control room cooler condenser, 1-HV-E-4B-2, and Unit 2, main control room cooler condenser, 2-HV-E-4B-2, on September 18, 2019.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from September 16 - 20, 2019:
- (1) Ultrasonic Examination (UT)a. 31" reactor coolant pipe-to-elbow weld (11715-WMKS-1019E-1/31-RC-2/SW-17), ASME Class 1 (reviewed)b. 14" reactor coolant valve-to-pipe weld (11715-WMKS-0110B-2/4-RC-14/9),
ASME Class 1 (reviewed)
- (2) Radiographic Examination (RT)a. 8" chemical and volume control system pipe-to-valve and valve-to-pipe welds (1-CH-MOV-1115B-VALVE-1,-2), ASME Class 2, WO59203140221 (weld sample; reviewed)
- (3) Liquid Penetrant Examination (PT)a. 8" chemical and volume control system pipe-to-valve and valve-to-pipe welds (1-CH-MOV-1115B-VALVE-1,-2), ASME Class 2, WO59203140221 (weld sample; reviewed)b. 14" reactor coolant valve-to-pipe weld (11715-WMKS-0110B-2/4-RC-14/9),
ASME Class 1 (reviewed)
- (4) Visual Examination (VT)a. bottom-mounted reactor vessel instrumentation, ASME Class 1 (reviewed)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 1 transition from approximately 80% power to Mode 3 on September 7 and 8, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the operators in the simulator during an emergency preparedness requal drill on July 16, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Unit 1 and Unit 2 emergency diesel generators on August 21, 2019
- (2) Review of Unit 1 and Unit 2 (a)(3) periodic evaluation on September 16, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Units 1 and 2 at elevated risk due to a PJM hot weather alert on July 22, 2019
- (2) Unit 1 emergent work control for loss of Vital Bus 1-III on August 10, 2019
- (3) Unit 2 packing adjustment for steam leak on 'A' main feedwater regulating valve with work order, WO 59203296739
- (4) Unit 1 heavy lift for the reactor head on September 12, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (5 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Units 1 and 2 instrument air safety related accumulators on July 22, 2019
- (2) Units 1 and 2 service water operability due to seismic concerns with staged equipment in the service water pump house on July 19, 2019
- (3) Unit 1, low head safety injection 'A' main discharge snubber with low oil on September 5, 2019
- (4) Unit 2, OD7651286, "Pressure readings on one of the nitrogen reserve tanks show a leak in the system which challenges the operability of the associated pressurizer power operated relief valve" on September 9, 2019
- (5) Units 1 and 2 emergency diesel generators during extreme hot weather on September 20, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 1 and Unit 2 reactor containment polar crane safety classification downgrade (ETE-NA-2019-0005)
- (2) Lowering fuel assembly 51N to seated position in spent fuel pool location using temporary rigging on August 21, 2019
- (3) Unit 1 and Unit 2 emergency diesel generator surveillance test interval evaluation from monthly to quarterly (STI-N12-2017-003)
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Unit 1, Quench Spray Pump 'A' after planned maintenance, on July 10, 2019
- (2) Unit 1, ventilation damper 1-HV-AOV-228-2 after replacement of the Part-21 required change out of the Hytork actuator on August 19, 2019
- (3) Unit 1, component cooling supply check valve to residual heat removal heat exchanger unplanned maintenance due to PT failures, WO59203279199
- (4) Unit 1, Service water return header from the recirc spray heat exchangers motor operated valve (MOV) 1-SW-MOV-105C following planned maintenance on September 27, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial) The inspectors evaluated 1R27 activities from September 8, 2019 to September 30, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 1 quench spray pump 'A' pressure test, on July 24, 2019 (2)1-PT-48, Unit 1 Mode 5 walkdown on September 8, 2019 (3)1-PT-138, Unit 1 LHSI system functional verification on September 24, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Units 1 and 2 service water pump flow surveillance test re-baselining on September 30, 2019
Containment Isolation Valve Testing (IP Section 03.01) (2 Samples)
(1)1-PT-61.3, service water to and from the recirc spray heat exchanger 'D' on September 25, 2019 (2)1-HV-MOV-100A, Containment Purge valve on September 26, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Units 1 and 2 beyond design basis flooding barrier yearly equipment testing on July 16, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency preparedness drill on July 16,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walk Downs and Observations (IP Section 02.01) (1 Sample)
The inspectors walked down gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.
- (1) Systems included the following:
Gaseous or Liquid Radioactive Effluent Monitoring Systems
- Process Vent Normal & High Range Effluent Monitor (GW-RM-178)
- Vent Stack A Normal & High Range Effluent Monitor (VG-RM-179)
- Liquid Waste Clarifier Radiation Monitor (RM-LW-111)
Filtered Ventilation Systems
- Unit 1 and 2 Containment Purge Exhaust Ventilation System
- Unit 1 and 2 Auxiliary Building General Exhaust Ventilation System
- Unit 1 and 2 Auxiliary Building Central Exhaust Ventilation System
- Unit 1 and 2 Safeguards Exhaust Ventilation System
- Fuel Building Exhaust Ventilation System
Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)
The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:
- (1) Systems included the following:
Process Vent Normal & High Range Effluent Monitor Work Order (WO) # 59102886914 - 0-PT-44.2.4 WO # 59103065651 - 0-PT-44.2.4 WO # 59103065651 - 0-PT-44.2.48 WO # 59102985571 - 0-PT-44.2.52
Vent Stack A Normal & High Range Effluent Monitor WO # 59102882205 - 0-PT-44.2.50 WO # 59103051507 - 0-PT-44.2.50
Vent Stack B Normal & High Range Effluent Monitor WO # 59102756143 - 0-PT-44.2.5 WO # 59102985571 - 0-PT-44.2.5
Sampling and Analysis (IP Section 02.03) (1 Sample)
The inspectors reviewed the following:
- (1) Radioactive Effluent Sampling and Analysis Activities
- Observed sampling of U-1 and U-2 High Capacity (S/G) Blowdown
- Observed Process Vent (Main Stack) Gaseous Sampling
- Observed Vent Vent A Particulate, Iodine, and Noble Gas Sampling
- Observed Vent Vent B Particulate, Iodine, and Noble Gas Sampling
Effluent Discharges
- No batch effluent discharges were available for review during the inspection. Open continuous release permits were reviewed.
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
- (1) ECCS PREACS WO # 59203269622 - 0-PT-77.4A (1-HV-FL-3A) Charcoal Efficiency WO # 59102939905 - 0-PT-77.4B (1-HV-FL-3B) Charcoal Efficiency WO # 59103005349 - 0-PT-77.14A (1-HV-FL-3A) HEPA-Charcoal In-Place Test WO # 59103062602 - 0-PT-77.14B (1-HV-FL-3B) HEPA-Charcoal In-Place Test
Unit 1 Containment Radio Gas Radiation Monitor WO # 59102803829 - 1-PT-38.2.1.20 WO # 59102986302 - 1-PT-38.2.1.20
Liquid Waste Clarifier Radiation Monitor WO # 59102897494 - 1-PT-38.2.2 WO # 59103108509 - 1-PT-38.2.2 WO # 59103069394 - 0-ICP-LW-RM-110
Dose Calculations (IP Section 02.05) (1 Sample)
The inspectors reviewed the following to assess public dose:
- (1) Liquid and Gaseous Discharge Permits
- Unit 1 Condenser Air Ejector Gas Permit # G-20190801-278-C
- Unit 2 Condenser Air Ejector Gas Permit # G-20190801-279-C
- Clarifier Continuous Liquid Permit # L-20190728-068-C
Annual Radiological Effluent Release Reports (ARERR)
- North Anna 2018 ARERR
- North Anna 2017 ARERR
Abnormal Gaseous or Liquid Tank Discharges
- No abnormal gaseous or liquid effluent discharges were available for review during this inspection
71124.07 - Radiological Environmental Monitoring Program
Inspectors evaluated licensee performance in ensuring REMP is implemented in accordance with licensing documentation and REMP is validating doses are within the legal dose limits. Inspectors also reviewed the licensees effort to continue to implement the NEI/Industry Groundwater Protection Initiative.
Site Inspection (IP Section 02.01) (1 Sample)
The inspectors performed walkdowns of sampling stations, thermoluminescent locations and meteorological instrumentation. Inspectors also performed observations of preparation and collections of different environmental sample types. Inspectors reviewed sampling results and maintenance, calibration, quality control and ground water records.
- (1) Records reviewed, and samples observed included but were not limited to the following:
Walkdowns, Calibrations, and Maintenance Record Review
- Environmental Air Sample Kit #1, Station 5A, 10/09/2018
- Environmental Air Sample Kit #4, Station 1, 10/09/2018
- Environmental Air Sample Kit #8, Station 8, 10/09/2018
- Environmental Air Sample Kit #11, Station 3, 10/09/2018
Environmental Sample Collections and Preparation Observation
- Environmental Air Sample Kits #1, Kit #4, Kit #8, Kit #11, particulate and charcoal air sample preparation for shipment to environmental lab
Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement
- Condition Report CR1081346 - Monthly Milk Sample not Available
- Condition Report CR1084829 - Quarterly TLDs Missing
- Condition Report CR1111079 - GWP Well #3 showed elevated tritium
Sampling Program for the Potential of Licensed Material Entering Groundwater
- Unit 2 Reactor Water Storage Tank
- Unit 1 Reactor Water Storage Tank
- Unit 1 & 2 Circulating Water Discharge Tunnels
Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees continuing implementation of the voluntary NEI/Ground Water Protection Initiative.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage areas for compliance with postings, labels, radiological controls and physical controls during plant walk downs. Inspectors also evaluated the material condition of observed containers of radioactive materials for signs of degradation.
- (1) Walkdown of radioactive material storage areas included the following:
- Warehouses 5 and 9
- Generator Rewind Building
- Outside Yard
- Auxiliary Building including the Solid Waste area
Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)
The inspectors evaluated liquid and solid radioactive waste processing systems and processes during plant walkdowns for alignment with licensing descriptions, material condition, administrative and physical controls. Inspectors also evaluated changes to the systems, waste stream mixing methodologies and process control program descriptions.
- (1) Radioactive Waste Resin and/or Sludge Discharges Processes
- Advanced Liquid Processing System (ALPS)
- Low-Level Liquid Waste Subsystem
- Spent Resin Dewatering Tank
Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated radioactive waste stream characterization and classification.
- (1) Radioactive waste streams:
- ALPS Charcoal (11/2016)
- 1-RP-FL-2 BARS (4/25/2017)
- 2-CH-I-1B (6/28/17)
- 1-RL-FL-1A (8/17)
- Common DAW (8/17)
- 1-LW-TK-1 Resin
- 2-CH-I-1A (10/17)
- 1-LW-TK-1 Resin
- 1-CH-I-2 (4/13/18)
- 1-RP-FL-1B Smear
- 2-CH-I-1B Resin
- ALPS Charcoal (4/19)
Shipment Preparation (IP Section 02.04) (1 Sample)
The inspectors evaluated and observed the radioactive material shipment preparation process.
- (1) Shipment Number:
- 19-1051
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following non-excepted package shipment records:
- (1) Shipment Numbers:
- 17-DUR-08
- 18-BCO-06,
- 18-BCO-10
- 17-ERS-01
- 19-BCO-04
- 19-BCO-05
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample.
(IP Section 02.16) (1 Sample)
The inspectors verified licensee performance indicators submittals for the period:
- (1) January 31, 2018 - July 31, 2019
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 05000339/2019-001-00, Manual Reactor Trip on Degrading Condenser Vacuum due to a Failed Weld (ADAMS accession: ML19123A099). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.
INSPECTION RESULTS
Unresolved Item (Closed)
Potential 50.9 Violation for Incomplete Information Submittal URI 05000338,05000339/2019010-03 71111.21N
Description:
During the 2019 Design Bases Assurance Inspection (EQ Program) inspection, the team identified a URI associated with a proposed technical specification change the licensee had submitted on June 22, 2000, wherein the licensee omitted information potentially material to the NRCs review. Specifically, the URI was established to allow the NRC to determine whether the issue was material in accordance with the NRC Enforcement Policy (ADAMS ML19123A129), Section 2.3.11, Inaccurate and Incomplete Information, and the NRC Enforcement Manual (ADAMS ML18018B134), Part II, Section 1.5, Material False Statements and Completeness and Accuracy of Information.
After review by staff in the Office of Nuclear Reactor Regulation (NRR), the NRC determined that the information which was omitted was not material to the decision-making process for the proposed technical specification change and is therefore not a violation of 10 CFR 50.9.
Corrective Action Reference(s): CR1123701
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 9, 2019, the inspectors presented the integrated inspection results to Ms.
Lisa Hilbert, Plant Manager and other members of the licensee staff.
- On September 19, 2019, the inspectors presented the North Anna Unit 1 ISI Debrief inspection results to Larry Lane, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Corrective Action
Documents
ACE000342
ACE to Engineering for unplanned inoperability of 1-SI-P-1B
to add oil
3/19/2007
CR1086669
1-SI-P-1B leaking oil
2/27/2017
Drawings
11715-FE-1D
4160V One Line Diagram - Sheet 3, Emergency Bus 1H
and 1J
1175-FE-1BB
One Line Diagram Electrical Distribution System
Engineering
Evaluations
ER-AP-BAC-101
BACCP Evaluation Screening
Miscellaneous
Engineering log of oil addition vs. leakage for mission time
of 1-SI-P-1B
2/28/2018
North Anna Power Station Lubrication Manual for low head
safety injection pump motor, and bearings
Procedures
0-GOP-4.34
Administrative Lock List
1-OP-1.4
Unit Startup from Mode 4 to Mode 3
1-OP-4A
Mode Change Checklist Mode 5 to Mode 6 or defueled to
Mode 6
1-OP-7.1A
Valve Checkoff - Low Head Safety Injection System
1-OP-8.1A
Valve Checkoff - Chemical and Volume Control System
Auxiliary Building
CM-NA-STI-101
Technical Specification Surveillance Test Interval (STI) List
Work Orders
Refueling Water Storage Tank Level Channel III (1-QS-L-
100A) Calibration
6/17/2019
Corrective Action
Documents
CR1094210
Air Void found during 1-PT-14.5
4/8/2019
Miscellaneous
Large AC Motors - Life-line D Horizontal Induction Motor,
Frames 5000, 5800, 6800, Drip proof, Weather Protected,
Type I Sleeve or Rolling Bearings
1/25/2013
1-CH-P-1B
North Anna Power Station Lube Oil Manual for charging
pump motor, gear reducer, and bearings
10/21/2008
Procedures
1-OP-7.2A
Valve Checkoff - High Head Safety Injection System
1-PT-138.1
HHSI Flow Balance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CM-NA-STI-101
Technical Specification Surveillance Test Interval List
Work Orders
203277804
Venting ECCS Lines
3/27/2019
Combined Charging Pump "1A" Head Curve Verification
and HHSI Branch Flow Verification Using Smart
Transmitters
4/18/2018
71111.05Q Corrective Action
Documents
Resulting from
Inspection
CR1128815
Smoke Detector in U1 TDAFW room is hanging by the wires 8/13/2019
CR1129074
Unit 1 Aux. Feedwater fire strategy
8/16/2019
Fire Plans
North Anna Power Station Appendix R Report
1-FS-AF-1
Safe Shutdown Equipment Auxiliary Feedwater Pumphouse
1-FS-SW-1
Service Water Pumphouse Units 1 and 2
Miscellaneous
Summary for 1-FP-1315 Valve Cycle
7/6/2019
NDE Reports
Eddy Current Inspection of Control Room Chiller Tube
Bundle 1-HV-E-4B-2 (condenser bundle)
6/9/2015
Eddy Current Inspection of Control Room Chiller Bundle 2-
HV-E-4B-2 (condenser bundle)
5/12/2016
Procedures
ER-AA-HTX-1002
Heat Exchanger Program Visual and Leak Testing
Work Orders
Heat Exchanger Visual Inspection Form - Tubeside (1-HV-
E-4B-2)
6/10/2015
Corrective Action
Documents
CR1117235
Excessive Boric Acid Leak on 2-RC-HCV-2544
03/04/2019
CR1117434
Discolored Boric Acid Found on 1-RC-MOV-2592
03/06/2019
CR1117772
Discolored Boric Acid Found on Body-to-Bonnet Connection
of 2-CH-FCV-2160
03/09/2019
Corrective Action
Documents
Resulting from
Inspection
CR1131188
Neutron Shield Tank Cooling Pump 1-NS-P-1A Packing
Leak
09/18/2019
CR1131224
Presence of Oil Noted on NRC Walkdown of Containment
09/18/2019
CR1131366
NRC Observation for Weld Traveler Documentation
09/19/2019
Engineering
Changes
RCN59203140221
Record Change Notice for Work Order 59203140221
Rev. 0
Engineering
Evaluations
ETE-NA-2018-
0003
North Anna Unit 1 Spring 2018 Steam Generator Condition
Monitoring and Operational Assessment
Rev. 0
ETE-NA-2019-
North Anna Unit 1 5th Interval Risk-Informed Inservice
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0007
Inspection Program, N-716-1 Conversion
ETE-NA-2019-
0033
North Anna Unit 1 - Steam Generator Degradation
Assessment and Inspection Interval Review - September
2019 Refueling Outage (N1R27)
Rev. 0
Miscellaneous
Curtiss-Wright Personnel Certification Statement: UT-LII
(Fuechtmann)
07/27/2019
Curtiss-Wright Personnel Certification Statement: UT-LII
(Fuechtmann)
07/27/2019
Curtiss-Wright Certification of Visual Acuity and Color Vision
(Fuechtmann)
8/7/19
Curtiss-Wright Personnel Certification Statement: UT-LII
(Sauter)
08/16/2019
Curtiss-Wright Certification of Visual Acuity and Color Vision
(Sauter)
8-15-19
Industrial Testing Services, LLC Certificate of Qualification
and Certification Summary: PT-LII (Flood)
2/22/2019
ITLS Vision Acuity Certification (Flood)
2/22/2019
Applied Technical Systems, Incorporated Nuclear
Construction Qualification and Certification of
Nondestructive Inspection Personnel: Radiography
(Lubinski)
March 3,
2017
Curtiss-Wright Certification of Visual Acuity and Color Vision
(Zollner)
7/24/19
Curtiss-Wright Personnel Certification Statement: UT-LII
(Zollner)
07/27/2019
Applied Technical Systems, Incorporated Vision Acuity
Examination (Lubinski)
01/08/2018
214
C-T Manufacturing Revised Certificate of Test-Mill Products:
UT Calibration Block VGB-33
December
11, 1991
677388
Equipment Specification: Reactor Coolant Centrifugally Cast
Pipe to ANSI B31.7 Class I
Rev. 0
801
Weld Procedure Specification
Rev. 8
830
Procedure Qualification Record
7/20/01
831
Procedure Qualification Record
7/20/01
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
JH-2438
Welder Performance Qualification: Manual GTAW P1 to P1
04/15/2011
JH-2632
Welder Performance Qualification: Manual GTAW P1 to P1
03/01/2010
TM-5756
Welder Performance Qualification: Manual GTAW P1 to P1
04/16/2006
NDE Reports
1-PT-48.4
Bare Metal Inspection of Vessel BMI Nozzles
09.08.19
PT-19-028
Liquid Penetrant Examination (11715-WMKS-0110B-2/4-
RC-14/9)
9/13/2019
UT-19-082
UT Calibration/Examination Record (11715-SMKS-0103N/6-
RC-17/SW-23)
9/10/2019
UT-19-085
UT Calibration/Examination Record (11715-WMKS-0109E-
1/31-RC-2/SW-17)
9/11/2019
UT-19-100
UT Calibration/Examination Record (11715-WMKS-0110B-
2/4-RC-14/9)
9/13/2019
Procedures
0-MCM-1801-01
Welding Safety-Related and Seismic-Related Equipment
Rev. 28
1-PT-48.3
Visual Inspection Borated Systems in Containment
Rev. 6
1-PT-48.4
Bare Metal Inspection of Vessel BMI Nozzles
Rev. 8
CM-AA-NWP-101
Control of Welding
Rev. 2
CM-AA-NWP-102
Control of Welding Materials
Rev. 2
ER-AA-NDE-PT-
301
Balance-of-Plant Liquid Penetrant Examination Procedure
Rev. 7
ER-AA-NDE-RT-
400
Radiographic Examination Procedure
Rev. 1
ER-AA-NDE-UT-
700
Ultrasonic Examination of Cast Stainless Steel Piping Welds Rev. 1
ER-AA-NDE-UT-
2
Ultrasonic Examination of Austenitic Piping Welds in
accordance with ASME Section XI, Appendix VIII
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. 12
Rev. 23
Work Orders
Replace 1-CH-MOV-1115B-VALVE
Rev. 0
71111.11Q Procedures
1-OP-3.7
Unit Shutdown from Mode 1 to Mode 5 for Refueling
Corrective Action
Documents
CR1124035
CR1124035
Corrective Action
CR1128672
1-III inverter output voltage and frequency not stable
8/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Miscellaneous
14
Medium Risk Plan Actions: Adjust packing on 2-FW-FCV-
2478 (U2 "A" MFRV) IAW WO59203296739
9/6/2019
Procedures
1-AR-F-A4
Main FD PPS Disch HDR Lo Press
1-AR-H-A3
Vital Bus 1-III Invert Trouble
1-OP-26.5
20-Volt Vital Bus Distribution
1-PT-80.1
AC Distribution and Reactor Coolant Pump Operability
Verification
2-AP-31
Loss of Main Feedwater
Work Orders
Packing adjust to last known torque on U2 A MFRV (2-FW-
FCV-2478)
9/6/2019
Calculations
ME-0193
Minimum Required No. of Cycles for Auxiliary Feedwater
Corrective Action
Documents
CR1125173
CR1127682
CR1129031
01-SI-HSS-104A discovered with oil level at 1/3
8/15/2019
Engineering
Evaluations
CE-0039
Civil Engineering Technical Report - Justification of Seal
Service Life of Small Bore Grinnell Snubbers at North Anna
Power Station
8/26/1994
ER-NA-ISI-SN-615 Safety Related Snubbers, Determination of Proper Snubber
Reservoir Level
8/15/2019
ET-CEM-04-0011
Recommendation for Extension of Service Life for
Grinnell/Anvil Hydraulic Snubbers - North Anna Units 1 and
2/17/04
ME-0098
EDG Room Temperature Rise Study
Operability
Evaluations
OD7651286
Pressure readings on one of the Nitrogen Reserve Tanks
(NRT) for Unit 2, 2-GN-TK-1A, show a leak in the system,
which challenges the opereability of 2-RC-PCV-2456,
Pressurizer Power Operated Relief Valve (PORV)
8/1/2019
Procedures
1-OP-24.2
Operation of the PORV Nitrogen Back-up Fill System,
3, 2-GN-TK-1A Nitrogen Leakage Determination
9/4/2019
1-OP-24.2
Operation of the PROV Nitrogen Back-up Fill System,
3, 2-GN-TK-1A Nitrogen Leakage Determination
8/30/2019
1-OP-24.2
Operation of the PORV Nitrogen Back-up Fill System, 2-
8/18/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
GN-TK-1A Nitrogen Leakage Determination
1-OP-24.2
Operation of the PORV Nitrogen Back-up Fill System
1-PT-212.14
Valve Inservice Inspection (Backup Air Supply for Aux
Feedwater Valves)
2-AR-C-E7
Technical Procedure Approval
7/21/2019
ER-NA-ISI-SN-615 Safety Related Snubbers
Work Orders
Small Bore Hydraulic Snubber Functional Testing
10/2/2016
Corrective Action
Documents
CR1129258
1-FH-CRN-13 hoist #2 stopped moving and smoke was
seen coming out at hoist
8/20/2019
Engineering
Changes
STI-N12-2017-003
Surveillance Test Interval Evaluation and approval change
EDG SR from 31 day to 92 day frequency
2/26/2019
Engineering
Evaluations
ETE-NA-2019-
0005
North Anna Unit 1 and Unit 2 Reactor Containment Polar
Crane Safety Classification Downgrade
6/4/2019
Miscellaneous
MR Function
MH002
Polar Crane is scoped in Maintenance Rule as Function
MH002
4/15/2019
NAPS-UCR-2014-
28
SAR Change Request: Update based on new Regulatory
Guide 1.9 in place
9/2/2014
Seismic Design Classification
Electrical Penetrations Assemblies in Containment
Structures for Nuclear Power Plants
Selection, Design, Qualification, and Testing of Emergency
Diesel Generator Units as Class 1E Onsite Electrical Power
Systems at Nuclear Power Plants
Procedures
0-OP-4.10
Fuel Building Bridge and Trolley Crane 1-FH-CRN-13
2-OTO1
CM-AA-STI-101
Risk Informed Technical Specification Surveillance
Frequency Control Program
NAPS1-EVAL-
2019-0004
50.59/72.48 Evaluation to perform a hook-to-hook transfer
of a fuel assembly from 1-FH-CRN-13 to a 3 ton chain fall
and lower the remaining exposed portion of the assembly
into the rack.
B5B Fuel Pit Shuffle evolution hoist stopped moving, task to
8/21/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
14:
Medium Risk Plan
Actions
Lower Fuel Assembly 51N to seated position in SFP
location F46 using Temporary rigging IAW 0-OP-4.10 OTO1
Corrective Action
Documents
CR1131036
U1 CC to RHR supply check valves 1-CC-193 and 1-CC-
198 failed 1-PT-210.14
9/16/2019
CR1131106
1-CC-193 and 1-CC-198 failed to pressurize during type C
testing IAW 1-PT-61.3
9/17/2019
CR1131139
Work performed on 1-CC-193 using work order 1-CC-198
9/17/2019
Drawings
1175-CBM-078A-4 ISI Classification Boundary DWG Interval - 4
Engineering
Changes
NA-19-00108
1-SW-MOV-105C Valve Replacement
Procedures
0-ECM-1509-03
MOV Testing - Quarter Turn Valves
0-MCM-0305-01
Inspection and Repair of Limitorque Valve Control Units,
Type SMB-0, with HBC Acutuators for Butterfly Valves
0-MCM-0307-01
NOV Stem Cuts and Spline Adapter Machining to Permit
Installation of Strain Gauges
0-MCM-0404-02
Removal and Installation of Allis-Chalmers / Rodney Hunt
Butterfly Valves
Work Orders
01-QS-PI-105A (Pressure Indicator Calibration)
1/10/2017
01-QS-PI-104A (Pressure Indicator Calibration)
7/6/2018
01-QS-FI-104 (Flow Indicator Calibration)
10/18/2018
01-QS-FI-103 (Flow Indicator Calibration)
10/18/2018
1-PT-63.1A: Quench Spray System - "A" Subsystem
7/10/2019
CC supply check valves to RHR HX open and inspect
9/18/2019
Valve Replacement DC 19-00108
WO592032997861 HBC3 Valve Adapter Plate
Corrective Action
Documents
Resulting from
Inspection
CR1132024
Containment Coating Damage Identified during NRC Final
Walkdown
9/28/2019
CR1132047
NRC identified items during containment walkdown
9/29/2019
Miscellaneous
2019 Outage Plan Safety Review North Anna Unit 1
8/8/2019
ER-AA-RXE-1004
Reactivity Plan for North Anna 1, N1C27
8/23/2019
Calculations
59-02-PT-75.2A
Service Water Pump Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
CR112384
CR1124166
CR1124170
Engineering
Changes
ETE-NA-2019-
0013
1-SW-P-1B & 2-SW-P-1A Performance Evaluation
Miscellaneous
Nuclear Qualifications for Visual Testing - 2 Level - 2
Examiner
7/17/2019
Procedures
1-PT-138
Valve Inservice Inspection -- LHSI System Functional
Verification
1-PT-210.19
Inservice Inspection SI Accumulator Discharge Check
Valves Full Open Test
2-PT-75.2A
Service Water Pump Quarterly Test
ER-AA-NDE-VT-
2
VT-2 Visual Examination Procedure
Work Orders
Quench Spray Pump 1-QS-P-1A System Pressure Test
7/10/2019
Corrective Action
Documents
Condition Reports (CRs) 1094202, 1107476, 1118898, and
20814
Various
Work Orders
Work Order
Number
59102939905
Perform Surveillance, 0-PT-77.4B, Emergency Core Cooling
Eystem (ECCS) Pump Room Exhaust Air Cleanup System
(PREACS) Filter 1-HV-FL-3B Charcoal Laboratory Test
2/14/2017
Work Order
Number
59103005349
Perform Surveillance 0-PT-77.14A, ECCS PREACS
(Emergency Core Cooling System Pump Room Exhaust Air
Cleanup System ) Filter Train A In-Place Test (1-HV-FL-3A)
2/15/2018
Work Order
Number
59103062602
Perform Surveillance 0-PT-77.14B, ECCS PREACS
(Emergency Core Cooling System Pump Room Exhaust Air
Cleanup System ) Filter Train B In-Place Test (1-HV-FL-3B)
11/08/2018
Work Order
Number
203269622
Perform Surveillance, 0-PT-77.4A, Emergency Core Cooling
Eystem (ECCS) Pump Room Exhaust Air Cleanup System
(PREACS) Filter 1-HV-FL-3A Charcoal Laboratory Test
10/17/2018
Calculations
0-HSP-MET-001
X/Q and D/Q
Calculation
North Anna Power Station - 2018 Meteorological Data
Summary (5 Year Summary)
Corrective Action
CR1103691
Aquatic sediment samples from Station 9A collected at the
08/16/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
wrong location
Miscellaneous
2017 AREOR
2017 Annual Radiological Environmental Operating Report
2017
2018 AREOR
2018 Annual Radiological Environmental Operating Report
2018
VPAP-2103N
Offsite Dose Calculation Manual (North Anna)
Revision 28
Procedures
0-HSP-MET-001
X/Q AND GROUND LEVEL D/Q
Revision 0
0-HSP-REMP-001
Radiological Environmental Monitoring Program, Land Use
Census
Revision 1
C-HP-1033.620
Portable Air Samplers Calibration and Operation
Revision 9
HP-3051.010
Radiological Environmental Monitoring Program
Revision 31
Groundwater Protection Program
Revision 8
Radiation
Surveys
59-04-2017
Ground Water Protection Plan Implementation Campaign
Analysis 4th Quarter 2017
01/22/2018
GWPP 59004-
2018
Ground Water Protection Plan Campaign Analysis Results
4th Quarter 2018
03/29/2018
Self-Assessments SAR PIR1082665
NEI 07-07 App B Ground Water Protection Initiative
Implementation Assessment
10/31/2017
Corrective Action
Documents
CR 1113595, CR
23792, CR
1117959, and CR
23476
71151
Calculations
HP-3010.022
Liquid Effluents Dose Summary July 2019
08/06/2019
HP-3010.032,
10
Gaseous Liquid Effluents Cumulative Dose Summary
08/07/2019
Engineering
Evaluations
Technical Report
No. SE-0007
NRC Mitigating System Performance Index (MSPI) Basis
Document, North Anna Power Station Unit 1 and Unit 2
Corrective Action
Documents
CA7525215