IR 05000369/2021011
| ML21140A217 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 05/20/2021 |
| From: | Scott Shaeffer NRC/RGN-II/DRS/EB2 |
| To: | Teresa Ray Duke Energy Carolinas |
| References | |
| IR 2021011 | |
| Download: ML21140A217 (9) | |
Text
May 20, 2021
SUBJECT:
MCGUIRE NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000369/2021011 AND 05000370/2021011
Dear Mr. Ray:
On April 8, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station and discussed the results of this inspection with you 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,
/RA/
Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety
Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
Report Numbers:
05000369/2021011 and 05000370/2021011
Enterprise Identifier: I-2021-011-0022
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, NC
Inspection Dates:
March 22, 2021 to April 09, 2021
Inspectors:
P. Braaten, Senior Reactor Inspector
L. Jones, Senior Reactor Inspector
M. Singletary, Reactor Inspector
D. Strickland, Reactor Inspector
Approved By:
Scott M. Shaeffer, Chief
Engineering Branch 2
Division of Reactor Safety
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at McGuire Nuclear 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 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).
(1)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.
- EVD/EPL - 125vDC Distribution System (2)
- RN - Nuclear Service Water System (3)
- Battery Room Common Suppression System, FA 13 (4)
- Suppression at RN pumps, Auxiliary Building Elevation 716', FA 4
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)
- Combustible Control 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)
- EC 0000109071 - Assured CA Suction for Extended SBO
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 8, 2021, the inspectors presented the triennial fire protection inspection results to Tom Ray and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Calculations
MCC-1223.42-00-
0037
Evaluation of the Use of Non-Safety Water Sources for
the Auxiliary Feedwater System
Rev. 12
MCC-1435.00-00-
0019
NFPA 805 Transition - Radiological Release Input to LAR
E
Rev. 02
MCC-1435.00-00-
21
NFPA 805 Transition NEI 04-02 B-2 Table - Nuclear
Safety Capability Assessment Methodology Review
Rev. 05
MCC-1435.00-00-
22
Fire Protection Manual Action Feasibility and Reliability
Demonstration
Rev. 00
MCC-1435.00-00-
23
NFPA 805 Expert Panel Report for Addressing Potential
McGuire Multiple Spurious Operations
Rev. 04
MCC-1435.00-00-
24
NFPA 805 Transition - NEI 04-02 B-3 Table Fire Area
Transition
Rev. 06
MCC-1435.00-00-
25
Nuclear Safety Capability Assessment (NSCA) for Fire
Protection Safe Shutdown Analysis in Support of NFPA
805 Transition
Rev. 02
MCC-1435.00-00-
28
NFPA 805 Transition B-1 Table/Report
Rev. 09
MCC-1435.00-00-
0041
NFPA 805 Transition Risk-Informed Performance-Based
Fire Risk Evaluations
Rev. 04
MCC-1435.00-00-
0045
NFPA 805 Transition Recovery Action Feasibility Review
Rev. 02
MCC-1435.00-00-
0047
NFPA 13 Code Conformance Review Nuclear Service
Water (RN) Pumps
Rev. 01
MCC-1435.00-00-
0049
NFPA 13 Code Conformance Review - Battery Rooms
Rev. 01
MCC-1435.00-00-
0065
Fire Watch Reduction Analysis
Rev. 01
MCC-1535.00-00-
20
McGuire Nuclear Station Fire PRA Quantification
Notebook
Rev. 01
MCM-1206-07-
0080
Sprinkler Hydraulic Calculation Nuclear Service Water
Pumps
Rev. 00
MCM-1206-07-
Sprinkler Hydraulic Calculation Battery Room Pipe Chase
Rev. 00
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0091
Unit #2
MCM-2206-07-
24
Sprinkler Hydraulic Calculation Battery Room Pipe Chase
Unit #1
Rev. 00
MCS-1465.00-00-
0008
Plant Design Basis Specification for Fire Protection
Rev. 24
Corrective Action
Documents
01587372
07/25/2002
01632230
2/16/2009
235455
10/05/2018
Corrective Action
Documents
Resulting from
Inspection
2375636
03/25/2021
2377639
04/08/2021
Drawings
MC-1705-01.00
One Line Diagram 125 VDC/120VAC Vital Instr & Cont
Power Sys
Rev. 124
MC-1705-01.01
One Line Diagram 125VDC/120VAC Vital Instr and
Control PWR Sys
Rev. 45
MCEE-111-00.55-
ELEMENTARY DIAGRAM
GROUP 1D/STANDBY SHUTDOWN
PRESSURIZER HEATERS
Rev. 10
MCFD-1574-
01.00
Nuclear Service Water System (RN)
Rev. 33
MCFD-1574-
03.00
Nuclear Service Water System (RN)
Rev. 45
MCFD-1574-
05.00
Nuclear Service Water System (RN)
Rev. 07
MCFD-1592-
01.01
Auxiliary Feedwater System (CA)
Rev. 34
MCFD-1599-01.0
Flow Diagram of Fire Protection System (RF,RY)
Rev. 19
MCM-1206.07-
0087.001
Battery Room Sprinkler Installation Plan
Rev. 00
MCM-1376.00-
0107.001
Fire Detection and Alarm System Auxiliary Building Units
and 2 - Floor 733+6 - Battery Room and Electrical
Equipment Room
Rev. 00
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
0000109071
Assured CA Suction For Extended SBO Per NRC Order
03/02/2015
Engineering
Evaluations
51-9235439-001
Appendix B: Safe Shutdown Equipment List (SSEL)
Rev. 02
MCC -1381.05-
00-0335
UNIT 1/2, NFPA 805 CIRCUIT BREAKER AND FUSE
COORDINATION STUDY
Rev. 34
MCEE-111-
00.55-04
E/D STANDBY SHUTDOWN FACILITY 600V MCC
SMXG COMPT
F5A GROUP ID/STANDBY SHUTDOWN PRESSURIZER
HEATERS
Rev. 10
Miscellaneous
DUKE-QAPD-001
Duke Energy Corporation Topical Report Quality
Assurance Program Description Operating Fleet
Rev. 46
Procedures
AP/0/A/5500/45
Plant Fire or Turbine BLDG Oil System Leak
Rev. 20
AP/2/A/5500/24
Loss of Plant Control Due to Fire or Sabotage
Rev. 35
PD-FP-ALL-1500
Fleet Fire Protection Program Manual
Rev. 00
PT/0/A/4600/113
McGuire Time Critical Actions/Time Sensitive Actions
Rev. 29
Work Orders
20119469
Operator Time Critical Task Verification
09/29/2016
257961
Engineered Safety Features Actuation Periodic Test Train
B
03/23/2019
258353
CA System Train 1B Performance Test
2/25/2019
20330859
CA System Train 2B Performance Test
04/10/2020
20331141
CA System Train 2A Performance Test
03/23/2020
20331172/06
Flushing of Unit 2 RN/RC Suction Lines to TD CA Pump
(SSS/ELAP)
03/26/2020
2036652
Engineered Safety Features Actuation Periodic Test Train
A
09/21/2020
20366718/01
CA System Train 1B Performance Test
10/09/2020