IR 05000413/2021011

NRC Fire Protection Team Inspection Report 05000413/2021011 and 05000414/2021011

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: NPF-35 and NPF-52 Report Numbers: 05000413/2021011 and 05000414/2021011 Enterprise Identifier: I-2021-011-0036 Licensee: Duke Energy Facility: Catawba Nuclear Station Location: South Carolina 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 Enclosure

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 CNC-1223.04-00-0119 CNS Units 1 and 2 Rev. 0

71111.21N.05 RCPs NFPA-805 Loss

of Seal Cooling Analysis

CNC-1223.49-02-0018 Fire Protection Piping Rev. 0

Friction Losses

CNC-1435.00-00-0080 NFPA 13 Code Rev. 0

Conformance Review

for KC Pump Sprinkler

System

CNS-1599.RF-00-0001 Fire Protection System Rev. 026

(RF/RY) Design Basis

Specification

Corrective Action 02364078 Site Fire Protection 01/06/2021

Documents 71111.21N.05 Engineers to Review IN 20-04

Corrective Action AR 02372737 NRC FP Insp - Calc 03/04/2021

Documents Resulting date reference has

from Inspection editorial error

71111.21N.05

AR 02373641 EC Reference Revised 03/10/2021

AR 02373895 NRC FP Insp. 03/12/2021

Observation from NRC

Insp Team

Drawings 71111.21N.05 CN-1705 Series 125V DC VITAL 13 - 17

INSTRUMENTATION

AND CONTROL

POWER SYSTEM

(EPL)

CN-2702-05.02 One Line Diagram 06/11/2015

Essential and Blackout

Auxiliary Power

Systems 4.16KV/600V

CNEE-0111-01.32-02 Elementary Diagram Rev. 9

MCC SMXG COMPT

F05C

SSF

PZR HTR GRP

CNEE-0211-01.32.02 Elementary Diagram Rev. 6

MCC SMXG COMPT

RO5B SSF PZR HTR

GRP

CNM-2206.09-0003.001 Unit 2 Component Rev. 014

Cooling Pump

Autosprinkler System S

Plans and Details

Engineering Evaluations Circuit Analysis Report Circuit Analysis Report

71111.21N.05 1ILE-SSSPZRHTRD

CNC -1381.05-00-0251 Units 1 and 2 NFPA 805 Rev. 33

Circuit Breaker and

Fuse Coordination

Study

CNC-1435.00-00-0044 Fire Protection Nuclear Rev. 003

Safety Capability

Assessment

CNC-1435.00-00-0067 NFPA 805 Transition - Rev. 004

Fire Risk Evaluation

(FRE)

Miscellaneous 600V MCC Load list 600V MCC Load list

71111.21N.05

CNS-1465.00-00-0006 Fire Protection Design Rev. 28

Bases Document

CNWT-1752-03.17 Wire Tabulation 09/24/2020

DUKE-QAPD-001 Topical Report - Quality Rev. 46

Assurance Program

Description Operating

Fleet

PRR-02307136 Revision Summary (and Rev. 004

basis) for

ABG/0/5500/045

Procedures 71111.21N.05 AP-0-A-5500-020 Loss of Nuclear Service Rev. 049

Water

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 Rev. 003

Recovery Action

Feasibility Review

OP-0-B-6100-013 Standby Shutdown Rev. 057

Facility Operations

PT-0-A-4400-001-J Spray Valve Sprinkler Rev. 030

System Functional Test

PT-0-A-4700-061 Time Critical Actions / Rev. 009

Time Sensitive Actions

Radiation Surveys IP/0/A/3850/023 Molded Case Circuit Rev. 134

71111.21N.05 Breaker Inspection and

Testing Procedure

Work Orders Work Order 20170423 2NV - Cal Standby 05/30/2018

71111.21N.05 01 Makeup Discharge

Work Order Package Calibration Pressurizer 12/01/2018

20189513 01 Instrumentation

7