IR 05000338/2019003

Integrated Inspection Report 05000338/2019003 and 05000339/2019003

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

{{#Wiki_filter:ber 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: NPF-4 and NPF-7 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 Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at North Anna Power Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items Type Issue Number Title Report Section Status URI 05000338,05000339/20 Potential 50.9 Violation for 71111.21N Closed 19010-03 Incomplete Information Submittal LER 05000339/2019-001-00 LER 2019-001-00 for North 71153 Closed Anna Unit 2, Manual Reactor Trip on Degrading Condenser Vacuum due to a Failed Weld.

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.

71111.01 - Adverse Weather Protection Summer Readiness Sample (IP Section 03.01)

(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)

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) 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)

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)

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) 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)

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)

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)

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)

[[IP sample::=

=IP 71111.18|count=4}}

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)

The inspectors evaluated:

(1) Emergency preparedness drill on July 16,

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walk Downs and Observations (IP Section 02.01)

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)==

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 Potential 50.9 Violation for Incomplete Information 71111.21N (Closed) Submittal URI 05000338,05000339/2019010-03

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 Type Designation Description or Title Revision or Procedure Date 71111.04Q Corrective Action ACE000342 ACE to Engineering for unplanned inoperability of 1-SI-P-1B 3/19/2007 Documents to add oil CR1086669 1-SI-P-1B leaking oil 12/27/2017 Drawings 11715-FE-1D 4160V One Line Diagram - Sheet 3, Emergency Bus 1H 26 and 1J 1175-FE-1BB One Line Diagram Electrical Distribution System 50 Engineering ER-AP-BAC-101 BACCP Evaluation Screening 12 Evaluations Miscellaneous Engineering log of oil addition vs. leakage for mission time 12/28/2018 of 1-SI-P-1B North Anna Power Station Lubrication Manual for low head 1 safety injection pump motor, and bearings Procedures 0-GOP-4.34 Administrative Lock List 11 1-OP-1.4 Unit Startup from Mode 4 to Mode 3 79 1-OP-4A Mode Change Checklist Mode 5 to Mode 6 or defueled to 28 Mode 6 1-OP-7.1A Valve Checkoff - Low Head Safety Injection System 23 1-OP-8.1A Valve Checkoff - Chemical and Volume Control System 38 Auxiliary Building CM-NA-STI-101 Technical Specification Surveillance Test Interval (STI) List 14 Work Orders WO59203131674 Refueling Water Storage Tank Level Channel III (1-QS-L- 6/17/2019 100A) Calibration 71111.04S Corrective Action CR1094210 Air Void found during 1-PT-14.5 4/8/2019 Documents Miscellaneous Large AC Motors - Life-line D Horizontal Induction Motor, 1/25/2013 Frames 5000, 5800, 6800, Drip proof, Weather Protected, Type I Sleeve or Rolling Bearings 1-CH-P-1B North Anna Power Station Lube Oil Manual for charging 10/21/2008 pump motor, gear reducer, and bearings Procedures 1-OP-7.2A Valve Checkoff - High Head Safety Injection System 20 1-PT-138.1 HHSI Flow Balance 14 Inspection Type Designation Description or Title Revision or Procedure Date CM-NA-STI-101 Technical Specification Surveillance Test Interval List 14 Work Orders 59203277804 Venting ECCS Lines 3/27/2019 WO59103025464 Combined Charging Pump "1A" Head Curve Verification 4/18/2018 and HHSI Branch Flow Verification Using Smart Transmitters 71111.05Q Corrective Action CR1128815 Smoke Detector in U1 TDAFW room is hanging by the wires 8/13/2019 Documents CR1129074 Unit 1 Aux. Feedwater fire strategy 8/16/2019 Resulting from Inspection Fire Plans North Anna Power Station Appendix R Report 44 1-FS-AF-1 Safe Shutdown Equipment Auxiliary Feedwater Pumphouse 2 1-FS-SW-1 Service Water Pumphouse Units 1 and 2 2 Miscellaneous Summary for 1-FP-1315 Valve Cycle 7/6/2019 71111.07A NDE Reports Eddy Current Inspection of Control Room Chiller Tube 6/9/2015 Bundle 1-HV-E-4B-2 (condenser bundle) Eddy Current Inspection of Control Room Chiller Bundle 2- 5/12/2016 HV-E-4B-2 (condenser bundle) Procedures ER-AA-HTX-1002 Heat Exchanger Program Visual and Leak Testing 5 Work Orders WO59102439016 Heat Exchanger Visual Inspection Form - Tubeside (1-HV- 6/10/2015 E-4B-2) 71111.08P Corrective Action CR1117235 Excessive Boric Acid Leak on 2-RC-HCV-2544 03/04/2019 Documents CR1117434 Discolored Boric Acid Found on 1-RC-MOV-2592 03/06/2019 CR1117772 Discolored Boric Acid Found on Body-to-Bonnet Connection 03/09/2019 of 2-CH-FCV-2160 Corrective Action CR1131188 Neutron Shield Tank Cooling Pump 1-NS-P-1A Packing 09/18/2019 Documents Leak Resulting from CR1131224 Presence of Oil Noted on NRC Walkdown of Containment 09/18/2019 Inspection CR1131366 NRC Observation for Weld Traveler Documentation 09/19/2019 Engineering RCN59203140221 Record Change Notice for Work Order 59203140221 Rev. 0 Changes Engineering ETE-NA-2018- North Anna Unit 1 Spring 2018 Steam Generator Condition Rev. 0 Evaluations 0003 Monitoring and Operational Assessment ETE-NA-2019- North Anna Unit 1 5th Interval Risk-Informed Inservice Rev. 0 Inspection Type Designation Description or Title Revision or Procedure Date 0007 Inspection Program, N-716-1 Conversion ETE-NA-2019- North Anna Unit 1 - Steam Generator Degradation Rev. 0 0033 Assessment and Inspection Interval Review - September 2019 Refueling Outage (N1R27) Miscellaneous Curtiss-Wright Personnel Certification Statement: UT-LII 07/27/2019

                                     (Fuechtmann)

Curtiss-Wright Personnel Certification Statement: UT-LII 07/27/2019

                                     (Fuechtmann)

Curtiss-Wright Certification of Visual Acuity and Color Vision 8/7/19

                                     (Fuechtmann)

Curtiss-Wright Personnel Certification Statement: UT-LII 08/16/2019

                                     (Sauter)

Curtiss-Wright Certification of Visual Acuity and Color Vision 8-15-19

                                     (Sauter)

Industrial Testing Services, LLC Certificate of Qualification 2/22/2019 and Certification Summary: PT-LII (Flood) ITLS Vision Acuity Certification (Flood) 2/22/2019 Applied Technical Systems, Incorporated Nuclear March 3, Construction Qualification and Certification of 2017 Nondestructive Inspection Personnel: Radiography

                                     (Lubinski)

Curtiss-Wright Certification of Visual Acuity and Color Vision 7/24/19

                                     (Zollner)

Curtiss-Wright Personnel Certification Statement: UT-LII 07/27/2019

                                     (Zollner)

Applied Technical Systems, Incorporated Vision Acuity 01/08/2018 Examination (Lubinski) 214 C-T Manufacturing Revised Certificate of Test-Mill Products: December UT Calibration Block VGB-33 11, 1991 677388 Equipment Specification: Reactor Coolant Centrifugally Cast Rev. 0 Pipe to ANSI B31.7 Class I 801 Weld Procedure Specification Rev. 8 830 Procedure Qualification Record 7/20/01 831 Procedure Qualification Record 7/20/01 Inspection Type Designation Description or Title Revision or Procedure 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- 9/13/2019 RC-14/9) UT-19-082 UT Calibration/Examination Record (11715-SMKS-0103N/6- 9/10/2019 RC-17/SW-23) UT-19-085 UT Calibration/Examination Record (11715-WMKS-0109E- 9/11/2019 1/31-RC-2/SW-17) UT-19-100 UT Calibration/Examination Record (11715-WMKS-0110B- 9/13/2019 2/4-RC-14/9) 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- Balance-of-Plant Liquid Penetrant Examination Procedure Rev. 7 301 ER-AA-NDE-RT- Radiographic Examination Procedure Rev. 1 400 ER-AA-NDE-UT- Ultrasonic Examination of Cast Stainless Steel Piping Welds Rev. 1 700 ER-AA-NDE-UT- Ultrasonic Examination of Austenitic Piping Welds in Rev. 7 2 accordance with ASME Section XI, Appendix VIII ER-AP-BAC-10 Boric Acid Corrosion Control Program Rev. 13 ER-AP-BAC-101 Boric Acid Corrosion Control Program (BACCP) Inspections Rev. 12 MA-AA-102 Foreign Material Exclusion Rev. 23 Work Orders WO59203140221 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 51 71111.12 Corrective Action CR1124035 Documents CR1124035 71111.13 Corrective Action CR1128672 1-III inverter output voltage and frequency not stable 8/10/2019 Inspection Type Designation Description or Title Revision or Procedure Date Documents Miscellaneous WM-AA-301 Medium Risk Plan Actions: Adjust packing on 2-FW-FCV- 9/6/2019 14 2478 (U2 "A" MFRV) IAW WO59203296739 Procedures 1-AR-F-A4 Main FD PPS Disch HDR Lo Press 0 1-AR-H-A3 Vital Bus 1-III Invert Trouble 3 1-OP-26.5 120-Volt Vital Bus Distribution 33 1-PT-80.1 AC Distribution and Reactor Coolant Pump Operability 15 Verification 2-AP-31 Loss of Main Feedwater 17 Work Orders WO59203296739 Packing adjust to last known torque on U2 A MFRV (2-FW- 9/6/2019 FCV-2478) 71111.15 Calculations ME-0193 Minimum Required No. of Cycles for Auxiliary Feedwater 0 PCV & HCV Valves Corrective Action CR1125173 Documents CR1127682 CR1129031 01-SI-HSS-104A discovered with oil level at 1/3 8/15/2019 Engineering CE-0039 Civil Engineering Technical Report - Justification of Seal 8/26/1994 Evaluations Service Life of Small Bore Grinnell Snubbers at North Anna Power Station ER-NA-ISI-SN-615 Safety Related Snubbers, Determination of Proper Snubber 8/15/2019 Reservoir Level ET-CEM-04-0011 Recommendation for Extension of Service Life for 12/17/04 Grinnell/Anvil Hydraulic Snubbers - North Anna Units 1 and ME-0098 EDG Room Temperature Rise Study 0 Operability OD7651286 Pressure readings on one of the Nitrogen Reserve Tanks 8/1/2019 Evaluations (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) Procedures 1-OP-24.2 Operation of the PORV Nitrogen Back-up Fill System, 9/4/2019 3, 2-GN-TK-1A Nitrogen Leakage Determination 1-OP-24.2 Operation of the PROV Nitrogen Back-up Fill System, 8/30/2019 3, 2-GN-TK-1A Nitrogen Leakage Determination 1-OP-24.2 Operation of the PORV Nitrogen Back-up Fill System, 2- 8/18/2019 Inspection Type Designation Description or Title Revision or Procedure Date GN-TK-1A Nitrogen Leakage Determination 1-OP-24.2 Operation of the PORV Nitrogen Back-up Fill System 14 1-PT-212.14 Valve Inservice Inspection (Backup Air Supply for Aux 13 Feedwater Valves) 2-AR-C-E7 RCS PORV TK A N2 Sup Lo Press 1 AD-AA-100, Technical Procedure Approval 7/21/2019 ER-NA-ISI-SN-615 Safety Related Snubbers 2 Work Orders WO59102848049 Small Bore Hydraulic Snubber Functional Testing 10/2/2016 71111.18 Corrective Action CR1129258 1-FH-CRN-13 hoist #2 stopped moving and smoke was 8/20/2019 Documents seen coming out at hoist Engineering STI-N12-2017-003 Surveillance Test Interval Evaluation and approval change 2/26/2019 Changes EDG SR from 31 day to 92 day frequency Engineering ETE-NA-2019- North Anna Unit 1 and Unit 2 Reactor Containment Polar 6/4/2019 Evaluations 0005 Crane Safety Classification Downgrade Miscellaneous MR Function Polar Crane is scoped in Maintenance Rule as Function 4/15/2019 MH002 MH002 NAPS-UCR-2014- SAR Change Request: Update based on new Regulatory 9/2/2014 28 Guide 1.9 in place Regulatory Guide Seismic Design Classification 5 1.29 Regulatory Guide Electrical Penetrations Assemblies in Containment 3 1.63 Structures for Nuclear Power Plants Regulatory Guide Selection, Design, Qualification, and Testing of Emergency 3 1.9 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 42-OTO1 CM-AA-STI-101 Risk Informed Technical Specification Surveillance 2 Frequency Control Program NAPS1-EVAL- 50.59/72.48 Evaluation to perform a hook-to-hook transfer 0 2019-0004 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. WM-AA-301 B5B Fuel Pit Shuffle evolution hoist stopped moving, task to 8/21/2019 Inspection Type Designation Description or Title Revision or Procedure Date 14: Lower Fuel Assembly 51N to seated position in SFP Medium Risk Plan location F46 using Temporary rigging IAW 0-OP-4.10 OTO1 Actions 71111.19 Corrective Action CR1131036 U1 CC to RHR supply check valves 1-CC-193 and 1-CC- 9/16/2019 Documents 198 failed 1-PT-210.14 CR1131106 1-CC-193 and 1-CC-198 failed to pressurize during type C 9/17/2019 testing IAW 1-PT-61.3 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 8 Engineering NA-19-00108 1-SW-MOV-105C Valve Replacement 0 Changes Procedures 0-ECM-1509-03 MOV Testing - Quarter Turn Valves 0 0-MCM-0305-01 Inspection and Repair of Limitorque Valve Control Units, 10 Type SMB-0, with HBC Acutuators for Butterfly Valves 0-MCM-0307-01 NOV Stem Cuts and Spline Adapter Machining to Permit 4 Installation of Strain Gauges 0-MCM-0404-02 Removal and Installation of Allis-Chalmers / Rodney Hunt 20 Butterfly Valves Work Orders WO59102494733 01-QS-PI-105A (Pressure Indicator Calibration) 1/10/2017 WO59102941198 01-QS-PI-104A (Pressure Indicator Calibration) 7/6/2018 WO59103134512 01-QS-FI-104 (Flow Indicator Calibration) 10/18/2018 WO59103134519 01-QS-FI-103 (Flow Indicator Calibration) 10/18/2018 WO59203271357 1-PT-63.1A: Quench Spray System - "A" Subsystem 7/10/2019 WO59203279199 CC supply check valves to RHR HX open and inspect 9/18/2019 WO59203294982 Valve Replacement DC 19-00108 1 WO592032997861 HBC3 Valve Adapter Plate 0 71111.20 Corrective Action CR1132024 Containment Coating Damage Identified during NRC Final 9/28/2019 Documents Walkdown Resulting from CR1132047 NRC identified items during containment walkdown 9/29/2019 Inspection 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 71111.22 Calculations 59-02-PT-75.2A Service Water Pump Test 16 Inspection Type Designation Description or Title Revision or Procedure Date Corrective Action CR112384 Documents CR1124166 Resulting from CR1124170 Inspection Engineering ETE-NA-2019- 1-SW-P-1B & 2-SW-P-1A Performance Evaluation 0 Changes 0013 Miscellaneous Nuclear Qualifications for Visual Testing - 2 Level - 2 7/17/2019 Examiner Procedures 1-PT-138 Valve Inservice Inspection -- LHSI System Functional 34 Verification 1-PT-210.19 Inservice Inspection SI Accumulator Discharge Check 19 Valves Full Open Test 2-PT-75.2A Service Water Pump Quarterly Test 58 ER-AA-NDE-VT- VT-2 Visual Examination Procedure 6 2 Work Orders WO59102993539 Quench Spray Pump 1-QS-P-1A System Pressure Test 7/10/2019 71124.06 Corrective Action Condition Reports (CRs) 1094202, 1107476, 1118898, and Various Documents 1120814 Work Orders Work Order Perform Surveillance, 0-PT-77.4B, Emergency Core Cooling 12/14/2017 Number Eystem (ECCS) Pump Room Exhaust Air Cleanup System 59102939905 (PREACS) Filter 1-HV-FL-3B Charcoal Laboratory Test Work Order Perform Surveillance 0-PT-77.14A, ECCS PREACS 02/15/2018 Number (Emergency Core Cooling System Pump Room Exhaust Air 59103005349 Cleanup System ) Filter Train A In-Place Test (1-HV-FL-3A) Work Order Perform Surveillance 0-PT-77.14B, ECCS PREACS 11/08/2018 Number (Emergency Core Cooling System Pump Room Exhaust Air 59103062602 Cleanup System ) Filter Train B In-Place Test (1-HV-FL-3B) Work Order Perform Surveillance, 0-PT-77.4A, Emergency Core Cooling 10/17/2018 Number Eystem (ECCS) Pump Room Exhaust Air Cleanup System 203269622 (PREACS) Filter 1-HV-FL-3A Charcoal Laboratory Test 71124.07 Calculations 0-HSP-MET-001 North Anna Power Station - 2018 Meteorological Data X/Q and D/Q Summary (5 Year Summary) Calculation Corrective Action CR1103691 Aquatic sediment samples from Station 9A collected at the 08/16/2018 Inspection Type Designation Description or Title Revision or Procedure 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 Revision 1 Census C-HP-1033.620 Portable Air Samplers Calibration and Operation Revision 9 HP-3051.010 Radiological Environmental Monitoring Program Revision 31 RP-AA-502 Groundwater Protection Program Revision 8 Radiation 59-04-2017 Ground Water Protection Plan Implementation Campaign 01/22/2018 Surveys Analysis 4th Quarter 2017 GWPP 59004- Ground Water Protection Plan Campaign Analysis Results 03/29/2018 2018 4th Quarter 2018 Self-Assessments SAR PIR1082665 NEI 07-07 App B Ground Water Protection Initiative 10/31/2017 Implementation Assessment 71124.08 Corrective Action CR 1113595, CR Documents 1123792, CR 1117959, and CR 23476 71151 Calculations HP-3010.022 Liquid Effluents Dose Summary July 2019 08/06/2019 HP-3010.032, Gaseous Liquid Effluents Cumulative Dose Summary 08/07/2019 10 Engineering Technical Report NRC Mitigating System Performance Index (MSPI) Basis 3 Evaluations No. SE-0007 Document, North Anna Power Station Unit 1 and Unit 2 71153 Corrective Action CA7525215 Documents 2| ]]