IR 05000413/2021011
| ML21113A149 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/23/2021 |
| From: | Scott Shaeffer Division of Reactor Safety II |
| To: | Simril R Duke Energy Carolinas |
| References | |
| IR 2021011 | |
| Download: ML21113A149 (9) | |
Text
April 23, 2021
SUBJECT:
CATAWBA NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000413/2021011 AND 05000414/2021011
Dear Mr. Simril:
On March 12, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba 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. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414
License Numbers:
Report Numbers:
05000413/2021011 and 05000414/2021011
Enterprise Identifier: I-2021-011-0036
Licensee:
Duke Energy
Facility:
Catawba Nuclear Station
Location:
Inspection Dates:
February 22, 2021 to March 12, 2021
Inspectors:
P. Braaten, Senior Reactor Inspector
E. Coffman, Reactor Inspector
L. Jones, Senior Reactor Inspector
M. Singletary, Reactor Inspector
Approved By:
Scott M. Shaeffer, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Catawba 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 the following systems credited in the approved fire protection program could perform their licensing basis function:
(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.
The team selected the following SSCs as samples:
- Automatic Sprinkler System in room (2)
- Unit 2 Component Cooling Water System (KC Pumps)
(3)
- Unit 2 4160 VAC Safe Shutdown Power System (4)
- Unit 2 Battery
Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)
The inspectors verified that the following fire protection program administrative controls were implemented in accordance with the current licensing basis:
(1)
- Fire Brigade Training Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)
The inspectors reviewed the following changes to ensure that they did not constitute an adverse effect on the ability to safely shutdown post-fire and to verify that fire protection program documents and procedures affected by the changes were updated.
(1)
- Engineering Change (EC)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 12, 2021, the inspectors presented the triennial fire protection inspection results to Robert T. Simril and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Procedure
Type
Designation
Description or Title
Revision or Date
71111.21N.05
Calculations
71111.21N.05
CNC-1223.04-00-0119
CNS Units 1 and 2
of Seal Cooling Analysis
Rev. 0
CNC-1223.49-02-0018
Fire Protection Piping
Friction Losses
Rev. 0
CNC-1435.00-00-0080
NFPA 13 Code
Conformance Review
for KC Pump Sprinkler
System
Rev. 0
CNS-1599.RF-00-0001
Fire Protection System
(RF/RY) Design Basis
Specification
Rev. 026
Corrective Action
Documents 71111.21N.05
2364078
Site Fire Protection
Engineers to Review IN 20-04
01/06/2021
Corrective Action
Documents Resulting
from Inspection
71111.21N.05
NRC FP Insp - Calc
date reference has
editorial error
03/04/2021
EC Reference Revised
03/10/2021
NRC FP Insp.
Observation from NRC
Insp Team
03/12/2021
Drawings 71111.21N.05
CN-1705 Series
25V DC VITAL
INSTRUMENTATION
AND CONTROL
POWER SYSTEM
(EPL)
- 17
CN-2702-05.02
One Line Diagram
Essential and Blackout
Auxiliary Power
Systems 4.16KV/600V
06/11/2015
CNEE-0111-01.32-02
Elementary Diagram
MCC SMXG COMPT
F05C
SSF
PZR HTR GRP
Rev. 9
CNEE-0211-01.32.02
Elementary Diagram
MCC SMXG COMPT
RO5B SSF PZR HTR
GRP
Rev. 6
CNM-2206.09-0003.001
Unit 2 Component
Cooling Pump
Autosprinkler System S
Plans and Details
Rev. 014
Engineering Evaluations
71111.21N.05
Circuit Analysis Report
1ILE-SSSPZRHTRD
Circuit Analysis Report
CNC -1381.05-00-0251
Units 1 and 2 NFPA 805
Circuit Breaker and
Fuse Coordination
Study
Rev. 33
CNC-1435.00-00-0044
Fire Protection Nuclear
Safety Capability
Assessment
Rev. 003
CNC-1435.00-00-0067
NFPA 805 Transition -
Fire Risk Evaluation
(FRE)
Rev. 004
Miscellaneous
71111.21N.05
CNS-1465.00-00-0006
Fire Protection Design
Bases Document
Rev. 28
CNWT-1752-03.17
Wire Tabulation
09/24/2020
DUKE-QAPD-001
Topical Report - Quality
Assurance Program
Description Operating
Fleet
Rev. 46
PRR-02307136
Revision Summary (and
basis) for
ABG/0/5500/045
Rev. 004
Procedures 71111.21N.05
AP-0-A-5500-020
Loss of Nuclear Service
Water
Rev. 049
AP-0-A-5500-045
Plant Fire
Rev. 017
AP-1-A-5500-017
Loss of Control Room
Rev. 061
CNC-1435.00-00-0068
NFPA 805 Transition
Recovery Action
Feasibility Review
Rev. 003
OP-0-B-6100-013
Standby Shutdown
Facility Operations
Rev. 057
PT-0-A-4400-001-J
Spray Valve Sprinkler
System Functional Test
Rev. 030
PT-0-A-4700-061
Time Critical Actions /
Time Sensitive Actions
Rev. 009
Radiation Surveys
71111.21N.05
IP/0/A/3850/023
Molded Case Circuit
Breaker Inspection and
Testing Procedure
Rev. 134
Work Orders
71111.21N.05
2NV - Cal Standby
Makeup Discharge
05/30/2018
Work Order Package
20189513 01
Calibration Pressurizer
Instrumentation
2/01/2018