IR 05000338/2019002
| ML19217A249 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/05/2019 |
| From: | Bradley Davis NRC/RGN-II/DRP/RPB4 |
| To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| Geanette D | |
| References | |
| IR 2019001, IR 2019002 | |
| Download: ML19217A249 (17) | |
Text
August 5, 2019
SUBJECT:
NORTH ANNA POWER STATION - INTEGRATED INSPECTION REPORT 05000338/2019002 AND 05000339/2019002; 07200056/2019001
Dear Mr. Stoddard:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station. On July 17, 2019, the NRC inspectors discussed the results of this inspection with Mr. Larry Lane 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
07200056 License Nos. NPF-4 and NPF-7
Enclosure:
Inspection Report 05000338/2019002; 05000339/2019002;
and 07200056/2019001
Inspection Report
Docket Numbers:
05000338 and 05000339
07200056
License Numbers:
Report Numbers:
05000338/2019002 and 05000339/2019002
07200056/2019001
Enterprise Identifier: I-2019-002-0029
I-2019-001-0119
Licensee:
Virginia Electric & Power Co.
Facility:
North Anna Power Station
Location:
Mineral, VA
Inspection Dates:
April 1, 2019 to June 30, 2019
Inspectors:
M. Tobin, Senior Resident Inspector
G. Eatmon, Resident Inspector
R. Carrion, Senior Reactor Inspector
C. Fontana, Emergency Preparedness Inspector
R. Kellner, Senior Health Physicist
S. Sanchez, Senior Emergency Preparedness Inspector
J. Tornow, Physical Security 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 a 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
Failure to Adequately Implement the Equipment Clearance Procedure Cornerstone Significance Cross-cutting Aspect Report Section Not Applicable NOV 05000338/2019001-01 Closed EA-18-159 Not Applicable Not Applicable A licensee-identified Severity Level IV violation (NOV) of TS 5.4.1.a, Procedures, was identified when the licensee failed to adequately implement licensee procedure OP-AA-200,
Equipment Clearance.
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection period.
Unit 2 began the inspection period at zero percent power for a planned refueling outage. On April 12, 2019, the unit was returned to rated thermal power. On June 25, 2019, the unit was downpowered to 8 percent thermal power due to a hotspot in the transformer yard, was returned to rated thermal power on June 29, 2019 following repairs, and remained at or near rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors 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
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the following areas on May 23, 2019:
- General site area
- Auxiliary feedwater pump buildings
- Safeguards buildings
- Service water dam and flood berm
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated readiness for impending adverse weather conditions for high winds and severe thunderstorms on May 22, 2019.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, emergency diesel generator starting air, 'H' and 'J' EDG, train 'A' and 'B' on April 26, 2019.
- (2) Units 1 & 2 fire water system main header loop on May 8, 2019.
- (3) Units 1 & 2 safety related portions of the instrument air system on June 14, 2019.
- (4) Unit 2, quench spray system, train B on June 16, 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 2 emergency switchgear instrument rack and air conditioning rooms on April 10, 2019
- (2) Unit 2 Auxiliary Feedwater Pumphouses on April 10, 2019
- (3) Spent fuel storage area on June 13, 2019
- (4) Unit 2 quench spray pump house on June 16, 2019
- (5) Unit 1 and 2 auxiliary feedwater pump house on June 18, 2019
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 risk significant plant conditions such as power changes, completed on June 27, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator control room activities during a station emergency preparedness drill on May 14, 2019.
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:
- (1) Diesel fire pump failure on June 9, 2019
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Required seals on building roofs and groundwater inleakage control in the safeguards building following a sump pump failure on May 7, 2019.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 2 elevated risk due to lifting and rigging associated with condensate pump 'A' motor replacement and Unit 2 startup concluding on April 26, 2019
- (2) Units 1 and 2 protected equipment with the C station reserve transformer out of service for transformer replacement on May 15, 2019
- (3) Fire drill being conducted in the emergency switchgear room during cable pulls for the C station reserve transformer replacement on May 17, 2019.
- (4) Cable manhole inspection periodicity going from periodic to on-demand on May 13, 2019
- (5) Unit 2 emergent work control for hot spot identified on main transformer 'C' bushing and associated down power with 'B' Service water header out of service on June 25, 2019
- (6) Diesel fire pump failure requiring replacement and station priorities during pump outage on June 20, 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) Unit 1 and Unit 2, updated margin for unqualified coatings in containment on May 15, 2019
- (2) Boric acid tank operability with non-functional heat trace on the tank on May 10, 2019
- (3) Part-21 notice for Hytork Actuators on May 30, 2019
- (4) Unit 1 charging pump 'C' inoperable due to temperature indicting controller failure for the pump lube oil cooler on June 16, 2019
- (5) Unit 2 seal water injection valve leaking on June 20, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Unit 2 outside recirculation spray pump 'A' seal replacement, 2-RS-P-2A completed on April 26, 2019
- (2) Units 1 and 2 EDG coolant changeout using bleed and feed method completed on May 26, 2019
- (3) Unit 1 main control room chiller 'A' maintenance, 1-HV-E-4A, completed on June 14, 2019
- (4) Unit 2 rod control cabinet 2BD non-urgent failure alarm on June 21, 2019
- (5) Unit 2 exciter field breaker 2-EP-BKR-41 replacement and testing using 2-OP-15.2, Main Generator Operation, on June 27, 2019
- (6) Unit 2 component cooling water heat exchanger testing following tube cleaning with non-standard cleaning tools on June 20, 2019
- (7) Unit 2 N42 power range instrument was declared inoperable and replaced on June 26, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage 2R26 activities from April 1, 2019, to April 9, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Inservice Testing (IP Section 03.01)
- (1) Unit 1, Charging pump 'C' (1-CH-P-1C), on June 14, 2019
Surveillance Tests (other) (IP Section 03.01) (3 Samples)
- (1) Unit 2 Degraded voltage/loss of voltage operational and Emergency Safeguards Function response time test: 2J bus on April 18, 2019
- (2) Unit 2 rod drop timing test on May 7, 2019
- (3) Unit 2 A train containment air recirculation fan inside isolation air return valve stroke time test on May 30, 2019
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 June 10, 2019
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 June 10, 2019
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 June 10, 2019. 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 June 10, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Licensee drill and notification procedure performance on May 14,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI02: RCS Leak Rate Sample (IP Section 02.11)===
- (1) Unit 1 (June 2018 - March 2019)
- (2) Unit 2 (June 2018 - March 2019)
EP01: Drill/Exercise Performance (IP Section 02.12) (1 Sample)
- (1) EP01: Drill & Exercise Performance for the period July 1, 2018, through March 31, 2019
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) EP02: Emergency Response Organization Drill Participation for the period July 1, 2018, through March 31, 2019
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) EP03: Alert & Notification System Reliability for the period July 1, 2018, through March 31, 2019
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (June 2018 - March 2019)
- (2) Unit 2 (June 2018 - March 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (June 2018 - March 2019)
- (2) Unit 2 (June 2018 - March 2019)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Appendix R fire cooldown methodology
NRC inspectors reviewed condition report CR1123506, which identified the station's concerns with the current Appendix R cooldown methodology. Specifically, the licensee questioned if the procedures in place for postulated fires in the Unit 1 and Unit 2 emergency switchgear rooms, Unit 1 and Unit 2 cable vault and tunnels, Unit 1 and Unit 2 containment buildings, and the main control room would have successfully allowed the unit to cool down to cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as required by Appendix R. As a compensatory measure while the calculations are being reworked, the licensee established hourly roving fire watches for the affected areas, and established an interim process to inform the emergency response teams on site of the potential to not be able to meet the requirements using existing procedural guidance. The site continues to have the ability to achieve and maintain safe and stable conditions following any postulated fire.
- (2) Safety Conscious Work Environment
NRC inspectors reviewed the stations programs to establish and maintain a safety-conscious work environment (SCWE), and interviewed station personnel to evaluate the effectiveness of these programs specifically in the licensees physical security department. During the inspection, inspectors assessed whether issues exist that may represent challenges to the free flow of information, and whether underlying factors exist that would produce a reluctance to raise nuclear safety concerns. Based on insights obtained from safety culture interviews, and discussions with management and Employee Concerns Program (ECP) personnel, the inspectors found no evidence of challenges to the organizations safety-conscious work environment. Most personnel were comfortable using the corrective action program, and appeared willing to raise nuclear safety concerns through at least one of the several means available.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants
- (1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loadings from April 29 through May 2, 2019. Specifically, the inspectors reviewed the normal operation of the ISFSI as the licensee loaded dry shielded canister (DSC) 062 and transferred it to horizontal storage module (HSM) 31 on the ISFSI pad. The inspectors reviewed evaluations required by 10 CFR 72.212(b), 10 CFR 50.59, and 10 CFR 72.48 and changes made to the ISFSI program and associated procedures to verify that changes were consistent with the license or CoC and did not reduce the effectiveness of the program and that the procedures continued to fulfill the commitments and requirements specified in the SAR, SER, CoC, 10 CFR Part 72, and the general license. The inspectors verified that the loading activities and transfer activities to the pad were performed in a safe manner and in compliance with approved procedures and that surveillance activities have been conducted at the specified periods. The inspectors verified that the licensee identified each fuel assembly placed in the ISFSI, recorded the parameters and characteristics of each fuel assembly, and maintained a record of each fuel assembly as a controlled document. The inspectors evaluated the effectiveness of the licensees management oversight and QA assessments of ISFSI activities for the loading operations and transfer activities to the pad.
During the course of the loading activities, the inspectors observed the following;
- Drying and backfill evolutions
- Closure welding and non-destructive weld evaluations
- Transfer and transport evolutions
- Radiological field surveys
The inspectors also evaluated the following corrective action documents:
- CA 7590652, Review the Requirements for Building Inspection Along the Haul Path
- CR 1082061, TN-32 Cask Lifting Procedures Need Additional Content for NUREG-0612 Heavy Loads Commitments
- CR 1112483, Plant Equipment Modified without Required Design Change Documentation
- CR 1122388, NRC Question Regarding Spent Fuel Cask Haul Route
INSPECTION RESULTS
Assessment - NOV 05000338/2019001-01 Closure
The inspectors reviewed the licensees response to NOV 05000338/2019001-01 and determined that the reason, corrective actions taken to address recurrence, and the date when full compliance was achieved for this violation is adequately addressed and captured on the docket. This closes NOV 05000338/2019001-01.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 17, 2019, the inspectors presented the integrated inspection results to Mr. Larry Lane and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60855.1
Calculations
Calculation
Number SF-0005
Standoff Distances for Gasoline Use at the ISFSI
Revision 0
Corrective Action
Documents
CA 7590652
Review the Requirements for Building Inspection Along the
Haul Path
CR 1082061
TN-32 Cask Lifting Procedures Need Additional Content for
NUREG-0612 Heavy Loads Commitments
CR 1112483
Plant Equipment Modified without Required Design Change
Documentation
Corrective Action
Documents
Resulting from
Inspection
CR 1122388
NRC Question Regarding Spent Fuel Cask Haul Route
CR 1122397
NRC Observations during ISFSI Inspection
Engineering
Changes
Design Change
No.07-017
Haul Route Assessment/NAPS/Units 1 and 2
February 8,
2011
Engineering
Evaluations
ETE-NAF-2010-
0003
North Anna Power Station Independent Spent Fuel Storage
Installation 10 CFR 72.212 Evaluation Report
Revision 5
Miscellaneous
Virginia Electric
and Power
Company Letter
18-108
Virginia Electric and Power Company Letter 18-108, sending
CFR 72.48 Evaluation NAPS 0-EVAL-2017-0012 for
bolting of cask lid of High Burn-up Demonstration (HBU)
cask to the NRC
March 28,
2018
Virginia Electric
and Power
Company Letter
19-177
Virginia Electric and Power Company Letter 19-177, sending
the Annual Radiological Environmental Operating Report for
North Anna Power Station Unit Nos. 1 and 2 and the
Independent Spent Fuel Storage Installation (ISFSI) to the
NRC
April 26,
2019
Procedures
0-OP-4.5
NUHOMS32 PTH Shielded Canister Loading and Handling
Revision 14
0-OP-4.52
NUHOMS Vacuum Drying System Operation
Revision 14
0-OP-4.54
Transfer Cask/Dry Shielded Canister Transfer to ISFSI and
Dry Shielded Canister Transfer from Transfer Cask to
Horizontal Storage Module
Revision 10
GQP-9.2-10
High Temperature Liquid Penetrant Examination and
Acceptance Standards for Welds, Base Materials and
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cladding
GQP-9.6-18
Visual Examination of Welds
Revision 0
NF-AA-NSF-601
NUHOMS HD Transfer Haul Route Walkdown
Revision 4
PI-CNSTR-OP-
DOM-T-01-04
Closure Welding of Transnuclear NUHOMS Dry Shielded
Canisters for Dominion Nuclear at the Millstone, North Anna
& Surry Power Stations
Revision 0
Corrective Action
Documents
Resulting from
Inspection
CR1123832
CR1125869
Procedures
0-PT-9.4
Inspection of Roof Drains, Yard Drains, and Roofs
Calibration
Records
01-EG-RV-601HA
Relief/Safety Valve Database
4/17/2019
01-EG-RV-601JB
Relief/Safety Valve Database
4/17/2019
01-EG-RV-602HA
Relief/Safety Valve Database
4/17/2019
01-EG-RV-602JB
Relief/Safety Valve Database
4/17/2019
Corrective Action
Documents
CR1089958
Minor boric acid discovered on 2-QS-17
2/14/2018
CR1117219
Safety Valve Manual Lifting Levers are not in Compliance
with Code Requirements
3/4/2019
Corrective Action
Documents
Resulting from
Inspection
CR1120555
NRC Identified - Relief Valve Handles Secured Down
4/12/2019
CR1121268
2-QS-P-1B boric acid leak
4/19/2019
Drawings
11715-FB-101E
Valve Operating Numbers Underground Fire Protection
System Warehouse 5 and Training Center Area
11715-FM
Flow/Valve Operating Numbers Diagram Compressed Air
System
Miscellaneous
1-EG-TK-1HA
Certificate of Inspection
2/1/2017
1-EG-TK-1HB
Certificate of Inspection
2/1/2017
Procedures
0-PT-100.3
Fire Protection Valve Verification
1-OP-6.7A
Operating Procedure - Valve Checkoff Diesel Starting Air
2-OP-7.4A
Operating Procedure - Valve Checkoff - Quench Spray
System
Drawings
11715-FB-101A
Valve Operating Numbers Diagram Underground Yard
Water and Fire Protection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Corrective Action
Documents
Resulting from
Inspection
CR1125934
NRC issue of concern for discrepancies in pre-fire plans for
U2 QSPH and ASWPH
6/27/2019
Engineering
Evaluations
NA-2011-0021
Evaluation of Permanently Stored Combustible Material
Fire Plans
1-FS-ASWP-1
Aux. Service Water Pumphouse
10/3/1994
2-FS-QS-1
Quench Spray Building 274' Safe shutdown Equipment
5/28/1992
Procedures
CM-AA-FPA-100
Fire Protection/Appendix R (Fire Safe Shutdown) Program
ETE-NA-2011-
21
Evaluation of Permanently Stored Combustible Material
2-OP-2.1
Unit Startup from Mode 2 to Mode 1
28
2-OP-2.2
Unit Power Operation from Mode 1 to Mode 2
NMAY19FD
Emergency Plan Drill
Corrective Action
Documents
CA7594994
CA7594994
CA7618752
CR1069331
CR1076213
CR1122557
CR1122557
CR1124204
CR1124441
CR1124509
CR1124544
Work Orders
Corrective Action
Documents
CR1122475
CR1125681
Unit 2 "C" Main TX H2 (Neutral) connection hotspot
6/24/2019
Corrective Action
Documents
Resulting from
Inspection
CR1121700
NRC question the rigor involved in determining whether a
scaffold would interfere with BDB equipment
4/24/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
6/25/2019
High Risk Plan Actions for 2-CN-P-1A - Upper motor bearing
failure
4/9/2019
6/28/2019
2-EP-MT-1C
Forced Outage plan
6/28/2019
2-EP-MT-1C
Forced outage plan
6/25/2019
ODM CA7566215
Operational Decision Making for 02-CN-P-1A
4/10/2019
P-NANN-427513
Manhole - Pumping
04/05/2017
Procedures
2-AP-2.2
Fast Load Reduction
2-AP-31
Loss of Main Feedwater
ER-AA-PRS-1011
Just in Time Preventive Maintenance Review Process
Operational Risk Assessment
Work Orders
203289710
Scaffolding Order
4/9/2019
Calculations
ME-0780
Post LOCA Debris Transport to Containment Sump Strainer
for Resolution of GSI-191
Corrective Action
Documents
21529
2-CH-22d reachrod may have come disconnected from
actual valve handwheel
4/22/2019
CA7605926
Level of Effort for failed 1-SW-TIC-102C, "C" charging pump
temperature indicating controller
6/12/2019
CR1118930
CR1121553
4B seal water injection vent valve 2-CH-225
4/23/2019
CR1122181
CR1122216
CR1122241
CR1122304
CR1123245
1-SW-TI-103C pegged high
5/13/2019
CR1123471
CR1123644
Engineering
Changes
DC-07-172
PREACS Bypass Damper Replacements/NAPS/Units 1&2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
Engineering
Transmittal SE
97-055
Charging Pump Lube Oil Temperature Low Limit
4/9/1997
ETE-NA-2014-
0046
Updated Margin for Unqualified Coatings in Containment
4/29/2019
Miscellaneous
Technical Report
No NAN2-34325-
TR-001
Reduced-Scale Testing for North Anna 1 and 2
Replacement Containment Sump Strainers
2/28/2009
Procedures
1-AR-33
North Anna Power Station Annunciator Response; Heat
Tracing Annunciator 1-LOG-4
C CH PP Low CLR SW Out Temperature
3/27/2015
2-AR-A-D1
Rod Control Urgent Failure
2-LOG-20
ECCS Leakage Log
4/23/2019
2-PT-59.3
Heat Tracing Operational Test
CM-AA-CTG-101
Coating Service Level 1 Application
Work Orders
Installation of Brace Kits for PREACS Bypass Dampers
Installation of Brace Kits for PREACS Bypass Dampers
Corrective Action
Documents
CR1121154
Received annunciator 2A-D2 (rod control non-urgent failure)
4/18/2019
CR1125524
Received Annunciator 2A-D2 (rod control non-urgent failure)
6/21/2019
CR1125775
N42 indication erratic
6/26/2019
CR1125777
Found U2 PCS point N00044A with security level zero
6/26/2019
Procedures
2-OP-15.2
Main Generator Operation
0-MOP-49.30
Draining SW from CC Heat Exchangers
1-MOP-6.94
1J EDG Coolant Changeout Using Bleed and Feed Method
1-MOP-6.95
1H EDG Coolant Changeout Using Bleed and Feed Method
1-PT-77.11A
Control Room Chiller 1-HV-E-4A Pump and Valve Test
6/14/2019
2-AP-4.3
Malfunction of Nuclear Instrumentation (Power Range)
2-AR-A-D2
Rod Control Non-Urgent Failure
Work Orders
59101675190
2-RS-P-2A-Pump Seal Replacement
3/29/2019
203290549
6/21/2019
203293442
6/26/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
CALC-59-01-PT-
14.3-08
Charging pump 1-CH-P-1C revise acceptance criteria for
hydraulic and vibration data
7/29/2011
Engineering
Changes
ET NAF-2003-
0005
Elimination of Seismic Allowance from Control Rod Drop
Times, North Anna Power Station, Units 1 and 2
01/16/2003
TSCR N-008
Bases for SR 3.1.4, Rod Group Alignment Limits
06/11/2002
Miscellaneous
1-CH-P-1C
Normal
Machine History Report
6/27/2019
IST Program
Basis Document,
Int 4
Inservice Testing (IST) Program Basis Interval 4
6/9/2017
Procedures
1-PT-14.3
Operating Periodic Test, Charging Pump 1-CH-P-1C
2-PT-36.11J
Degraded Voltage/Loss of Voltage Operational and ESF
Response Time Test: 2J Bus
2-PT-83.12J
2J Diesel Generator Test (Start by ESF Actuation) Followed
by 24-Hour Run and Hot Restart Test
NMAY19FD
Emergency Plan Drill
Calculations
SM-1841
Appendix R Emergency Switchgear Room (ESGR) Fire
Natural Circulation Cooldown for NAPS
Corrective Action
Documents
CR1092157
CR1123506
Procedures
1-FCA-2
Emergency Switchgear Room Fire
43