IR 05000338/2024010
| ML24144A250 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/24/2024 |
| From: | Daniel Bacon Division of Reactor Safety II |
| To: | Hilbert L Dominion |
| References | |
| IR 2024010 | |
| Download: ML24144A250 (10) | |
Text
SUBJECT:
NORTH ANNA POWER STATION - NRC FIRE PROTECTION TEAM INSPECTION (FPTI) REPORT 05000338/2024010 AND 05000339/2024010
Dear Lisa Hilbert:
On May 16, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station and discussed the results of this inspection with Mr. James Jenkins, Plant General Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety 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:
05000338/2024010 and 05000339/2024010
Enterprise Identifier:
I-2024-010-0031
Licensee:
Dominion
Facility:
North Anna Power Station
Location:
Mineral, VA
Inspection Dates:
April 29, 2024 to May 16, 2024
Inspectors:
E. Coffman, Reactor Inspector
W. Monk, Senior Reactor Inspector (Team Lead)
A. Ruh, Senior Reactor Inspector (Observing)
D. Strickland, Senior Reactor Inspector
Approved By:
Daniel M. Bacon, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team 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
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and industry standards.
REACTOR SAFETY
71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)
The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
a. Review deficiencies or open fire protection impairments for the selected system, including any temporary modifications, operator workarounds, or compensatory measures.
b. Verify that operator actions can be accomplished as assumed in the licensees FHA, or as assumed in the licensees fire probabilistic risk assessment (FPRA) analysis and SSA.
c. Review repetitive or similar maintenance work requests which could be an indicator of a design deficiency and could affect the ability of the components to perform their functions, when needed.
d. Ensure that post maintenance and/or surveillance activities are performed as scheduled.
e. Perform a walkdown inspection to identify equipment alignment discrepancies. Inspect for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.
f. Ensure the selected SSCs that are subject to aging management review (AMR) pursuant to 10 CFR Part 54 are being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verify that the licensees aging management program activities (such as, Fuel Oil Analysis or Selective Leaching Aging Management Program) associated with FP equipment are being implemented.
g. If a review of operating experience issues will be completed for the selected inspection sample, verify that the licensee adequately reviewed and dispositioned the operating experience in accordance with their processes.
- (3) SSC #3 (Safe Shutdown) - U1/U2 EDG System & 4.1KV Emergency Distribution
- (4) SSC #4 (Safe Shutdown) - U1/U2 Auxiliary Feedwater (AFW) System
Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)
The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) Fire Protection Administration Program #1 - Hot Work Program
- (2) Fire Protection Administration Program #2 - Fire Brigade Drills and Training Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors verified the following:
a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.
b. The adequacy of the design modification, if applicable.
c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.
d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, FHA, and SSA were updated consistent with the FPP or design change.
e. Post-fire SSD operating procedures, such as abnormal operating procedures, affected by the modification were updated.
- (2) FPP Change #2 - App R Report Change Notice N-2022-001 - ETE-NA-2021-0068, EDG Starting Circuit Appendix R Review
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 16, 2024, the inspectors presented the Fire Protection Exit Meeting inspection results to Mr. James Jenkins, Plant Manager, and other members of the licensee staff.
THIRD PARTY REVIEWS No third-party reviews were conducted during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NA-CALC-000-
ME-3031
Seismic/JOG Weak-Link Analysis for FW-MOV-100D
Rev. 1
NA-CALC-000-
ME-3162
JOG Calculation of Required Thrust Settings for MOV-2-
FW-MOV-200D
Rev. 2
NE-0154
Minimum Quantity for Fire Protection Low Pressure CO2
Tanks 1-FP-TK-06 and 1-FP-TK-5
Rev. 2
Calculations
Minimum Levels for the Fire Protection Low Pressure CO2
Tanks
05/25/2021
CA8539011
Evaluate EDG start circuit in accordance with the
requirements of OP-AA-102
07/20/2021
CA8560108
Document the review of the EDG battery negative
conductors in an ETE
08/19/2021
CR 1172800
NRC Identified Discrepancies in the NAPS Appendix R
Report
05/13/2021
CR 1177199
App R concern identified with cable separation associated
with U1&U2 EDG and Emergency Bus Operation
07/20/2021
CR 1177399
Update to CR1177199 App R concern with U1 & U2
EDG/Emerg Bus BKR Cable Separation
07/22/2021
CR 1199293
Inadvertent CO2 Release in 2H EDG Room
05/12/2022
CR 1205683
Crack on 6-ton CO2 Tank Fill Line
08/15/2022
CR 1219577
Operations Minimum Fire Brigade Staffing Not Met per TR
7.3
2/14/2023
CR 1226275
NRC Identified: Transient fire loading report in U1 cable
spreading room Questioned
04/27/2023
CR 1230930
Audit Recommendation as a result of NOD Audit 23-04:
Fire Protection QA Program and Implementation
06/14/2023
CR 1235778
Observed minor CO2 line Corrosion above 2-FP-89
Caused by Overhead Drain Leak
08/17/2023
CR 1246311
NRC Identified a Penetration in the Aux building (244)
that Appeared Degraded
2/14/2023
71111.21N.05
Corrective Action
Documents
CR 1247679
Operations below OP-AA-100 - Conduct of Operations
manning requirements - ELAP only
01/7/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 1249239
Control of Combustible and Flammable Material CBT not
assigned IAW with the Training Program Guide
01/24/2024
CR 1250480
1-FP-P-10-ENGINE oil sample 1/23/2024; fuel dilution
(5.9%), viscosity (7.7 cSt)
2/8/2024
CR 1253981
2J EDG Room North Door will not Latch
03/19/2024
CR1177199
App R concern identified with cable separation associated
with U1&U2 EDG and Emergency bus operation
07/20/2021
CR 1258107
NRC Identified 2J EDG Room Non-Appendix R
Emergency Light Lamp not Directed at Pathway
04/30/2024
CR 1258254
NRC Identified Plastic Bottle with Fluid Found in U2 Cable
Vault / Tunnel
05/01/2024
CR 1258259
NRC Identified Transient Combustibles Outside U1
Control Room Door (printer paper)
05/01/2024
CR 1258262
NRC Identified Transient Material in U1 Cable Vault and
Tunnel
05/01/2024
CR 1258290
NRC Identified: Minor Discrepancies Identified in FCA
Procedures
05/02/2024
CR 1258373
NRC Identified: Small Access Door Missing from 02-BLD-
STR-S71-12
05/02/2024
CR 1259519
NRC Identified: Plastic bottle with fluid found in U2 Rod
Drive Room
05/15/2024
CR 1259521
NRC Identified: Plastic bottle with fluid found in U2 Cable
Vault / Tunnel
05/15/2024
Corrective Action
Documents
Resulting from
Inspection
CR 1259525
NRC Identified: FCA steps for establishing AFW do not
contain explicit steps to prevent SG Overfill
05/15/2024
CR 1259641
NRC Fire Protection Team Inspection Exit Meeting
05/16/2024
11715-DAR-74A
Appendix 'R' Safe Shutdown Flow Diagram Feedwater
Rev. 7
11715-DAR-74A
Appendix R SSD Flow Diagram for U1 Feedwater
Rev. 7
11715-ESK-11C
Elementary Diagram Emer Diesel Gen 1H Sh. 1
Rev. 29
11715-FAR-206
Equipment Location - APP R Service Building Plan EL
271 - 6
Rev. 7
Drawings
2050-ESK-11C
Elementary Diagram Emer Diesel Gen 2H Sh. 1
Rev. 28
Engineering
Changes
ETE-NA-2021-
0068
Emergency Diesel Generator Starting Circuit Appendix R
Review
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N-2021-007
Change Evaluation to Appendix R Report
10/01/2021
ET CEP 00-0043
Availability of MOV's for Local Operation
Rev. 0
ET-N-09-0063
Appendix R Assumptions for Operator Manual Actions
Rev. 1
ETE-CEP-2011-
0003
Appendix R Multiple Spurious Operation (MSO)
Identification and Evaluation - North Anna Units 1 and 2
Rev. 3
Engineering
Evaluations
NA-ETE-000-
ETE-CEP-2011-
0003
Risk Screening for Previously Identified MSO's
Rev. 3
1-FS-AF-1
SAFE SHUTDOWN EQUIPMENT AUXILIARY
FEEDWATER PUMPHOUSE Unit 1
Rev. 3
1-FS-DR-1
UNIT 1 AND 2 EMERGENCY DIESEL ENGINE ROOMS
Rev. 8
1-FS-S-3
UNIT 1 EMERGENCY SWITCHGEAR INSTRUMENT
RACK AND AIR CONDITIONING ROOMS SERVICE
BUILDING ELEV. 254 FT (S-54) SAFE SHUTDOWN
EQUIPMENT
Rev. 15
Fire Plans
2-FS-AF-1
FIRE FIGHTING STRATEGY FOR SAFE SHUTDOWN
EQUIPMENT FOR AUXILIARY FEEDWATER
PUMPHOUSE
Rev. 2
O-FPMA-3
SCBA Operability Test
05/10/2024
O-FPMA-3
SCBA Operability Test
04/09/2024
Fire Drill Evaluation Form
2/03/2023
Fire Drill Evaluation Form
2/16/2024
SDBD-NAPS-
System Design Basis Document for Auxiliary Feedwater
System North Anna Power Station
03/15/2023
Miscellaneous
SDBD-NAPS-EG
System Design Basis Document Emergency Diesel
Generator System
Rev. 36
0-FCA-0
Fire Protection Operations Response
Rev. 22
0-FCA-1
Control Room Fire SSD Procedure
Rev. 57
0-GOP-17.0
Time Critical Action Validation and Verification
Rev. 17
0-PT-107.0
Periodic Appendix R Locker Inspection
04/01/2024
1-FCA-2
Unit 1 ESGR SSD Procedure
Rev. 50
Procedures
1-FCA-3
Cable Vault and Tunnel Fire SSD Procedure
Rev. 39
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-FPMP-2.10
Fire Protection Maintenance
Rev. 10
2-FPMP-2.2
Loss Prevention Fire Protection Maintenance
Rev. 14
CM-AA-FPA-100
Fire Protection/Appendix R (Fire Safe Shutdown) Program
Rev. 20
CM-AA-FPA-101
Control of Combustible and Flammable Materials
Rev. 17
O-FPMP-2.6
Loss Prevention Fire Protection Maintenance
Rev. 4
Conduct of Operations
Rev. 47
CONDUCT OF FIRE DRILLS
Rev. 8
VPAP-0505
Writers Guide for Dual-Column Procedures
Rev. 9
Self-
Assessments
PIR1152016
NAPS Pre-TFPI 2021 Self-Assessment
7/27/2021