IR 05000395/2022011
| ML22270A077 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/29/2022 |
| From: | Gerald Mccoy NRC/RGN-II/DRS/EB2 |
| To: | Stoddard D Dominion Energy Co |
| References | |
| IR 2022011 | |
| Download: ML22270A077 (11) | |
Text
September 29, 2022
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION - FIRE PROTECTION TEAM INSPECTION REPORT 05000395/2022011
Dear Mr. Stoddard:
On August 26, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Virgil C. Summer Nuclear Station. On August 25, 2022, the NRC inspectors discussed the results of this inspection with Mr. George Lippard III 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, Gerald J. McCoy, Branch Chief Engineering Branch 2 Division of Reactor Safety Docket No. 05000395 License No. NPF-12
Enclosure:
As stated
Inspection Report
Docket Number:
05000395
License Number:
Report Number:
Enterprise Identifier:
I-2022-011-0018
Licensee:
Dominion Energy
Facility:
Virgil C. Summer Nuclear Station
Location:
Jenkinsville, SC
Inspection Dates:
August 08, 2022 to August 25, 2022
Inspectors:
P. Braaten, Senior Reactor Inspector
W. Monk, Senior Reactor Inspector
M. Singletary, Reactor Inspector
D. Terry-Ward, Construction Inspector
Approved By:
Gerald J. McCoy, 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 Virgil C. Summer Nuclear Station, in accordance with the Reactor Oversight Process (ROP). 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 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.
- (1) Emergency Feedwater
- (2) 480 V Emergency AC Busses
- (3) Incipient Fire Detection Systems
- (4) Select Fire Barriers and Penetrations in Auxiliary Building
Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)
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) NFPA 805 Monitoring Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)
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.
- (1) ECR 50940 - Spent Fuel Pool Cooling Alternate Power
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 25, 2022, the inspectors presented the triennial fire protection inspection results to Mr. George Lippard III and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DC00340-001
Fire PRA Plant Final Report
Rev. 02
DC0780B-001
Fire Modeling: Generic Methodology
Rev. 10
DC07860-005
Fire Protection - Base Transient Combustible Loads
Rev. 1
DC07860-006
Fire Loading Calculation (Appendix R)
Rev. 7
DC08500-018
Cable Sizing Criteria Development
Rev. 9
DC08500-023
Cable Ampacity Considerations for power cable trays in
Kaowool Fire Barrier Blanket
Rev. 01
DC08500-024
Cable Ampacity Considerations for Power cable air drops
wrapped in Kaowool Fire Barrier
Rev. 02
DC08500-026
Cable Ampacity Considerations for Power cable raceways
wrapped with 3M Interam Fire Barrier System
Rev. 01
Calculations
DC08620-046
Electrical Cable Insulation Contribution to Fire Loading
Rev. 03
CR-20-00764
Breaker failed testing. While performing EMP280.004 on
breaker XMC1DB2Z 02HM breaker failed to
01/29/2022
CR-20-02387
During research for procurement of GE Q12IAC66K57A
relays (SKU 54-7602-0517-13)
01/29/2022
Corrective Action
Documents
CR-21-00631
Found fuses for FU1 had a 15-amp fuse on top and 10-
amp fuse on bottom. Found fuses for FU2
03/11/2021
CR 1205423
Determine whether DO NOT CUT THROUGH RELAY
ROOM Sign is Required
08/11/2022
Corrective Action
Documents
Resulting from
Inspection
CR 1206345
Incipient Detection NFPA 72 Code Reconciliation
08/24/2022
B-208-021
Charging/Safety Injection Pump C (XPP43C) (Channel B)
Rev. 10
B-208-021, page
A
Electrical - Elementary Diagram, Charging/Safety
Injection Pump C
Rev. 12
B-208-021, Page
B
Electrical - Elementary Diagram, Charging/Safety
Injection Pump C
Rev. 12
B-208-021, Page
C
Charging/Safety Injection Pump C (XPP43C) (Channel B)
Rev. 10
B-208-032
Electrical - Elementary Diagram, EF Isolation from
Turbine Driven Pump to Steam Gen. B IFV-3546
Rev. 15
71111.21N.05
Drawings
B-208-032
Electrical - Elementary Diagram, EF Isolation from Turb.
Rev. 12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Driven PPs to Steam Gen. B IFV-3546
B-814-207
I & C Instrument Diagram, INTMD Bldg EL 412-0 Emer
FDW to S. G. A flow FT-3561; PT-3563; and S.G. A
BLDWN FT-4702A
Rev. 05
B-814-212
I&C Instrument Diagram, Intermediate Bldg EL 412-0
Emergency FDW to Steam Generator FT-3571; PT-3573;
FT-3581 & FT-3541
Rev. 06
D-302-085
Piping, System Flow Diagram, Emergency Feedwater
(Nuclear)
Rev. 52
D-912-132
Aux Building Pump Room Cooling System
Rev. 21
E-201-240, sht.
3M INTERAM E-54A Installation. Electrical Raceway
Barrier System 21-3M-1, sht. 22
Rev. 00
E-201-240, sht.
3M INTERAM E-54A Installation. Elect. Raceway Barrier
Sys. 216-3M-3, sht. 44
Rev. 00
E-206-022
Electrical, one Line Diagram, 7200V SWGR Busses 1DA,
1DB, 1EA, 1EB
Rev. 17
E-206-047
Electrical, one Line & Relay Diagram, 480V Engineered
Safeguard MCC Power Feeds
Rev. 06
E-304-090
Piping System, Emergency Feedwater Pen. Access Area,
Plan above EL. 412-0 & 435-0
Rev. 06
E-811-017
Instrument Location Layout, Intermediate Bldg East &
Penetration Basement Floor EL. 412-0
Rev. 32
E-813-058
I & C Schematic Detail, Instrument Hookup, Details P and
Q (NSR),sht.1
Rev. 09
SS-211-032
Electrical Block Diagram, System EF, Emergency
Rev. E
SS-211-032
Electrical Block Diagram, System EF, Emergency
Feedwater, sht. number U1
Rev. K
VCS-IFT03561A-
EF
Instrument Loop Diagram, Emergency Feedwater to
Steam Generator A Flow, Train B
Rev. 01
50940
Spent Fuel Cooling Pumps Alternate Power
11/05/2020
2535
Replacement of Obsolete Chessell Model 344/345 Main
Control Board Recorders
Rev. 00
Engineering
Changes
2543
Replacement of Limitorque SMB-000 Torque Switches
Rev. 00
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(ETBT 72543)
2551
Replacement of Obsolete Rosemount Model 1153
Transmitters
06/20/2019
43046-RPT-01
VCSNS Circuit Analysis Updates for ECR 50940, Jensen
Hughes
Rev. 01
Engineering Services Specification, Installation, Repair
and Quality Verification of 3M INTERAM E-54 Series
Flexible Mat
Rev. 07
TR00180-015
License Renewal Aging Management Program, Program
Basis Document for the Fire Protection Program
Rev. 00
TR07800-033
Fire Safety Analysis Report
Rev. 00
TR0780E-001
VCS UNIT 1 SSD SEPARATION FIRE PROTECTION
ENGINEERING EQUIVALENCY EVALUATIONS
Rev. 00
TR0780E-003
VCS Unit 1 Fire Alarm & Detection Fire Protection
Engineering Equivalency Evaluations
Rev. 01
TR0780E-004
VCS Unit 1 Fire Protection Administrative Features and
Materials Fire Protection Engineering Equivalency
Evaluations
Rev. 00
TR0780E-005
VCS Unit 1 Fire Suppression Fire Protection Engineering
Equivalency Evaluations
Rev. 00
TR07870-017
Engineering Service Technical Report, 86-10 Evaluation:
INTERAM E-54A Fire Wrap
Rev. 01
TR08620-031
NFPA 805, NSCA Modification DROID Listing Appendix R
Compliance Review
Rev. 01
TR08620-034
FIRE RESPONSE ABNORMAL OPERATING
PROCEDURES TECHNICAL BASIS DOCUMENT
Rev. 02
TR08620-036
NFPA 805 RECOVERY ACTIONS,
FEASIBILITY/RELIABILITY STUDY
Rev. 02
TR08620-312
Engineering Service Technical Report Nuclear Safety
Capability Assessment Report Fire Shutdown Analysis
Rev. 03
Engineering
Evaluations
VCSNS-FP DBD
NFPA 805 Fire Protection - Design Basis Document
Rev. 02
FP1AB-388
Auxiliary Building
Rev. 03
FP1CB-436
Control Building
Rev. 04
Fire Plans
FP1CB-448
Control Building
Rev. 02
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP1LGD-001
FIRE PREPLAN LEGEND
09/07/2021
VC-FSAR-000-
VC-FSAR-000-FSAR, Chapter 8, page 8.3-39,
Reformatted February 2019
2/2019
VCSNS - EDBD -
EF
Enhanced Design Basis Document, Emergency
Feedwater System (EF)
Rev. 17
Miscellaneous
Xtralis VESDA
VFT-15
Product Guide
April 2009
APPENDIX C
LOCAL OPERATOR ACTIONS
Rev. 01
ARP-043-XPN-
5599
INCIPIENT DETECTION PANEL
Rev. 00
ICP-230.006
INCIPIENT DETECTION FUNCTIONAL CHECK
Rev. 01
Corrective Action
Rev. 38
STP-128.024
CO2 SYSTEM FUNCTIONAL REFUELING TEST
Rev. 10
STP-170.015
Surveillance Test Procedure, Fire Switch Functional Test
for XPP0043C, Charging SI Pump C
Rev. 05
STP-428.060
VENTILATION FIRE DAMPER UNITS
Rev. 09
Procedures
VCS-ERP-0020
PRE-PLAN DEVELOPMENT AND CONTROL
Rev. 02
1912689
Fire SW Func Test-XPP43C, CHG/SI PMP %
Preconditioning "Acceptable" Per CR-13-04664 Action 11
03/30/2022
88101014107
1904787 001 EMP0280.004-XMC1DB2Z 02HM Molded
Case Circuit Breaker XMC1DB2Z Feeder T
03/10/2020
88101382693
1103974 001 Replace 50/51/74 relay with a tested spare
relay. Verify proper pump start/stop
11/21/2011
WO 1903831-001
Incipient Detection Analyzer (15CHNL) for XPN5600
Panel
06/04/2020
WO 1903844-001
Incipient Detection Analyzer (15CHNL) for XPN5602
Panel
06/03/2020
WO 1912021-001
Incipient Detection Analyzer (15CHNL) for XPN5599
Panel
08/07/2020
WO 2009864-001
Incipient Detection Analyzer (15CHNL) for XPN5600
Panel
07/28/2021
Work Orders
WO 2009869-001
Incipient Detection Analyzer (15CHNL) for XPN5602
Panel
08/26/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
WO 2102525-001
Incipient Detection Analyzer (15CHNL) for XPN5599
Panel
2/07/2022
STP-428.060 HVAC Fire Damper Inspection
08/04/2020
STP-428.060 HVAC Fire Damper Inspection
03/08/2022