IR 05000413/2022010

Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010

ML22202A530
Person / Time
Site:	Catawba
Issue date:	07/21/2022
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Simril T Duke Energy Carolinas
References
IR 2022010
Download: ML22202A530 (13)

Text

July 21, 2022

SUBJECT:

CATAWBA NUCLEAR STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000413/2022010 AND 05000414/2022010

Dear Mr. Simril:

On June 10, 2022, 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, James B. Baptist, Chief Engineering Branch 1 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:

05000413/2022010 and 05000414/2022010

Licensee:

Duke Energy Carolinas, LLC

Facility:

Catawba Nuclear Station

Location:

York, SC

Inspection Dates:

May 23, 2022, to June 10, 2022

Inspectors:

R. Fanner, Reactor Inspector

N. Morgan, Intergovernmental Liaison Project Manager

G. Ottenberg, Senior Reactor Inspector

J. Zudans, Contractor

Approved By:

James B. Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a. Evaluated whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

Specific Guidance b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.

c. Evaluated whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

(1)1KC050A, Auxiliary Building Non-Essential Header Isolation (2)1ND027, 1A Residual Heat Removal (ND) Heat Exchanger Bypass Control (3)2CA050A, Auxiliary Feedwater (CA) Pump 2 Discharge to Steam Generator 2C Isolation (4)1NV010A, Letdown Orifice 1B Outlet Containment Isolation (5)2CA056, CA Pump 2A Flow to Steam Generator 2B (6)2NC035B, Pressurizer Power Operated Relief Valve Isolation (7)2NI173A, ND Header 2A to Cold Legs C & D (8)1CF033, 1A Steam Generator Feedwater Containment Isolation

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On June 10, 2022, the inspectors presented the design basis assurance inspection (programs) inspection results to Tom Simril and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02

Calculations

AD-EG-ALL-1117

U2, 6.9KV, 4.16KV, & 600V Auxiliary Power Systems

Safety-Related Voltage Analysis

CNC -1205.19-00-

Generic Letter 89-10 MOV Calculations, NC System; 1(2)

28

NC033A, 035B, 1NC031B

CNC -1205.19-00-

89-10 Calculation for 1&2 CA038A, 42B, 46B, 50A, 54B,

29

58A, 62A, 66B

CNC -1205.19-00-

Generic Letter 89-10 Calculation For Valves 1 and

0033

NI173A and NI178B

CNC -1205.19-00-

GL 89-10 Set-Up Calculation for Valves 1KC001A,

0110

1KC002B, 1KC050A, 1KC053B, 2KC001A, AND

2KC002B

CNC -1205.19-00-

Required Thrust Calculation for 1(2)NC31B, 33A, 35B

000

0195

(AD/DD PPM); Item NO. 09J-363 & 364

CNC -1205.41-00-

(2) ND 26, 27, 60, and 61 Fisher Actuator and Margin

27

Capability Calculations

CNC -1206.02-80-

KCC - Component Cooling Heat Exchangers 1 A & 1 B to

018

2019

the RHR Heat Exchangers 1A & 1 B. Also to the Inlet of

the Letdown & Fuel Pool Heat Exchangers

CNC -1223.11-00-

Limiting 1ST Stroke Time for ND26, ND27, ND60 and

000

0055

ND6V

CNC -1381.05-00-

U2, 6.9KV, 4.16KV, & 600V AUXILIARY POWER

0199

SYSTEMS SAFETY-RELATED VOLTAGE ANALYSIS

CNC 1205.41-00-

(2) NV 010A, 011A, and 013A Required Thrust

0018

Evaluation supporting Air Operated Valve (AOV) Program

CNC-1205.41-00-

Air Operated Valve (AOV) Program Scope Calculation

0001

CNC-1205.41-00-

FEEDWATER ISOLATION VALVES, 1(2)CF33, 42, 51,

05/03/2022

0005

AND

60, DESIGN BASIS SIZING CALCULATION

CNC-1205.41-00-

Catawba Air-operated Valve (AOV) Risk Ranking

0016

Calculation

CNC-1205.41-00-

(2) NV 010A, 011A, and 013A Required Thrust

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

0018

Evaluation supporting Air Operated Valve (AOV) Program

CNC-1205.41-00-

1(2) CA-040, 044, 056, 060 and 1(2) CA-036, 048, 052,

22

064 Actuator Capability Evaluation Supporting Air

Operated (AOV) Program

CNC-1206.03-00-

Doghouse Environmental Temperature Due to Main

Rev. 3

0181

Steam Line Break

CNC-1223.02-00-

Inservice Testing (IST) Valve Response Measurement

04/08/2011

23

Uncertainty

CNC-1223.12-00-

Design Parameters for ND Header to Cold Leg

0045

Containment Isolation Valves 1 & 2 NI173A, NI178B

CNC-1552.08-00-

Long-Term Containment Response - Manual NS Initiation

0390

CNM 1205.00-

Design/Seismic Report (Weak Link) for 09J-2056, 2",

2182.001

1500#, SS, Gate Valve

CNM 1205.01-

Design & Seismic RPT 6J-339

C

0797.001

Corrective Action

ARs

2373087, 02294259, 01497427, 02407695, 02294259,

Documents

01497427, 02428219, 01898027, 02300922

Corrective Action

NCR 02318266

OP-CN-CF-CF lesson plan does not identify the safety

06/24/2022

Documents

related power supply for Feedwater Isolation Valve's

Resulting from

NCR 02429804

22 NRC DBAI POV - 2NI173A Motor Brake Internals

06/02/2022

Inspection

NCR 02430135

22 NRC DBAI POV - 1KC-50A Maximum Transmitted

06/06/2022

Torque

NCR 02430281

22 NRC DBAI POV - Lesson Plans not revised post

06/07/2022

Mod

NCR 02430301

PT/1/A/4350/002 E enclosure 13.16 could not be located

06/07/2022

NCR 02430342

22 NRC POV DBAI - Incorrect Reference in Flowserve

06/07/2022

Letter

NCR 02430464

Obstructions on 522' elevation floor drains

06/08/2022

NCR 02430567

NRC DBAI POV-EOPs do not align with UFSAR

06/09/2022

NCR 02430713

22 NRC DBAI POV - 2NC35B - Actuator Fastener Bolt

06/09/2022

Preload

NCR 02431086

22 NRC DBAI POV - UFSAR sec.6.2.4.1 incorrect

06/14/2022

statement

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NCR 2428952

22 NRC DBAI POV - 2NC035B High Temp Torque

Factor

05/26/2022

NCR 2430567

NRC DBAI POV-EOPs do not align with UFSAR

06/09/2022

2-403-0012-3

Limitorque Valve Control

DI

40846-08

20- Class 150 Valve Assembly and Limitorque H2BC-

SMB-00-10

DE

CN -1561-01.00

Flow Diagram of Residual Heat Removal System (ND)

CN -2561-01.00

Flow Diagram of Residual Heat Removal System (ND)

CN -2562-01.01

Flow Diagram, Safety Injection System (NI)

CN -2592-01.01

Flow Diagram Auxiliary Feedwater System (CA)

CN-1573-01.0

Flow Diagram of Component Cooling System (KC)

CN-2499-CA.07-

Instrument Detail Motor Driven Auxiliary Feedwater Pump

to Steam Generator Flow Control

CN-2553-01.01

Flow Diagram of Reactor Coolant System (NC)

CN-2562-01.03

Flow Diagram of Safety Injection System (NI)

CNEE-0247-04.12

Auxiliary Feedwater System (CA) CA Pump No. 2 Disch

to S/D 2C Isol. Vlv. 2CA050A

CNEE-0247-

04.12-01

Auxiliary Feedwater System (CA) CA Pump No. 2 Disch

to S/D 2C Isol. Vlv. 2CA050A Controls

CNEE-0250-01.09

Reactor Coolant System (NC) Pzr Power Operated Relief

Isolation Valve 2NC035B

CNEE-0251-01.32

Elementary Diagram Safety Injection System (NI) ND

HDR to NC Cold Legs C and D Isolation Valve 2NI173A

CNM 1205.00-

0074.001

8"SS Motor Oper Gate Vlv Item 9J211

CNM 1205.00-

2181.001

O/L Drawing for 09J-2056, 2", 1500#, SS, Gate Valve

CNM 1205.01-

0790.001

4" 1500LB CS EMO DP Gate Valve 6J-339

H

CNM 1205.01-

0790.002

4" 1500LB CS DP Gate Valve 6J-339

J

CNM 1205.06-

20.001

O/L, C/S, B/M, OPR, W/D Control Valves 1&2/CA/40, 44,

& 60

J

Drawings

W9223811, Sht. 1

3"- 1530 Weld Ends Stainless Steel Double Disc Gate

B

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Valve for SMB-00-15 Limitorque Actuator

W9223811, Sht. 2

3"- 1530 Weld Ends Stainless Steel Double Disc Gate

Valve for SMB-00-15 Limitorque Actuator

B

CN 20328

Modify control circuit wiring on 2NI-9A, 10B, 100B, 183B,

2A, 173A, 178B, 184B, 185A, 2NV-89A, 91B, 188A,

189B, 252A, 253B, 312A, and 314B to provide "limit

actuated" torque switch bypass contacts which can be

adjusted independent of Indication or interlocks.

11/07/1988

CN 21319

Modify CA Control Valves to Prevent S/G Overfill During

SGTR

08/11/1999

EC 0000106724

Revise MOV Set-Up Sheets to Meet GL 96-05

Requirements for 1KC001A, 002B, 050A

09/07/2012

Engineering

Changes

EC 0000402775

U-1 AND U-2 NW System Isolation to Specific CIVs

CNC -1205.19-00-

0176-ICC-0003

EC420978 - Revise valve factor for 1(2)NI173A &

1(2)NI178B

000

CNC -1205.19-00-

0179

Kalsi Engineering Report 2919C, GL96-05 Periodic

Verification Program for Butterfly Valves with 316

Microseal Bearings {JOG Class D)

CNC -1381.05-00-

0199

U2, 6.9KV, 4.16KV, & 600V Auxiliary Power Systems

Safety-Related Voltage Analysis

CNC-1205.00-00-

0048

GL 95-07 Pressure Locking and Thermal Binding Review

of Valves Without an Active to Open Safety Function

CNC-1205.19-00-

0170

Operability Evaluation of Rotork Part 21 for Switch

Mechanisms

CNM 1205.00-

0549.001

ASME Section III Gate Valve Seismic Report

CNM 1205.00-

2050.001

Design and Seismic Analysis Report for 3" EMO Gate

Valve, Item 9J-364

00C

CNM 1205.02-

0766.001

Weak-Link Report for CNS BFV Item Number 05B-501

CNM 1205.19-

0094.001

Stress Report for Westinghouse Class 1 Nuclear Valves-

Gate Valves

D3

Engineering

Evaluations

CNM 1205.19-

099.011

9J-211 Seismic and Weak Link Analysis Report for

Westinghouse Class 1 Nuclear Valve

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DPC 1205.41-00-

0001

Evaluation of AOV Issues Needed for Margin Calculations

DPC-1205.00-00-

0008

Microseal Bearing Test Report: Kalsi Engineering

Document 2800C

[N/A]

OAC Alarm Response Information for loss of SOV Power

BACKGROUND

INFORMATION

FOR

WESTINGHOUSE

OWNERS

GROUP

EMERGENCY

RESPONSE

GUIDELINE

ES-1.3 Transfer to Cold Leg Recirculation HP-Rev. 3

03/31/2014

CDUK-1205.41-

0001.001

Unit 1 and Unit 2 AOV Test Set Up Sheets

CE 0000106724

Revise MOV Set-Up Sheets to Meet GL 96-05

Requirements for 1KC001A, 002B, 050A, AND 053B

09/17/2012

CN 500404

Allow Replacement of Solenoid Valves w/ New Model

05/17/2005

CN-11413

De-energize the Hydraulic Solenoids on the Main

Feedwater Isolation Valves

08/06/2001

CNC -1205.19-00-

0176-ICC-0004

EC420956-Revise Valve Factor and Functions for CA

MOVs

CNM 1205.00-

22.001

l/B Manual M/0 Gate Valves & Swing Check Vlvs

D10

CNM 1205.00-

1997.001

EMO Torque Switch Setting Sheets

CNM 1205.00-

1997.001

EMO Torque Switch Setting Sheets

CNM 1205.00-

2049-001

Instruction Manual Number ET347 for 3" 1530 Class

Double Disc Gate Valves with Motor Actuators

10/01/1997

CNM 1205.02-

0762.001

Posi-Seal Butterfly Valve Technical Bulletin Series

Miscellaneous

CNM 1205.06-

I/M & Parts List for Control Valves and Regulators

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

268.001

CNM 1205.19-

0001.001

Limitorque Nuclear Qualification Reports

CNM 1205.19-

0083.001

Technical Repair Guide for Rotork Valve Actuators "NA"

Range Models

CNM 1205.19-

0114.001

Rotork Motor Operator Bench Test Certificates

D7

CNS-1205.00-00-

0008

ASME Section 3 Stainless Steel Gate Globe and Check

Valves

CNS-1205.06-00-

0003

Control Valves to ASME Section III

CNS-1553.NC-00-

0001

Reactor Coolant System (NC) Design Basis Specification

CNS-1554.NV-00-

0001

Chemical and Volume Control System (NV) Design Basis

Specification

CNS-1561.ND-00-

0001

Design Basis Specification for The Residual Heat

Removal (ND) System

CNS-1562.NI-00-

0001

Design Basis Specification For the Safety Injection (NI)

System

CNS-1573.KC-00-

0001

Component Cooling System (KC) Design Basis

Specification

CNS-1591.CF-00-

0001

Design Basis Specification for the Feedwater (CF)

System

Rev. 034

CNS-1592.CA-00-

0001

Auxiliary Feedwater System (CA) Design Basis

Specification

CNS-1592.CA-00-

0001

Auxiliary Feedwater System (CA) Design Basis

Specification

DPS 1205.00-00-

0002

Nuclear Safety Related Carbon and Stainless Steel

Forged and Cast Electric Motor Operated Valves

DPS-1205.19-00-

0004

Safety Related Rotork Motor Operators and Spare Parts

EQMM-1393.01-

Q03-01

Environmental Qualification Maintenance Manual

Equipment Type: Solenoid Valve Manufacturer: Valcor

Engineering Corporation Model/Series: V70900-65 Series

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Valves

OEDB Number:

2-12415

LIMITORQUE TECHNICAL UPDATE #92-O1 Kalsi

Engineering Document #17O7-C, Rev. o (11-25-91)

Thrust Rating Increase SMB-OOO, SMB-OO, SMB-O &

SMB-1 Actuators

01/06/1992

OP-CN-CF-CF

Feedwater System Lesson Plan

04/07/2014

OP-CN-EP-INTRO

Emergency Procedures Intro Lesson Plan CNOB50

System Health

Report

KC - Component Cooling System

04/19/2022

System Health

Report

ND - Residual Heat Removal System

04/19/2022

System Health

Report

CA - CNS l Unit 2 l CA - Auxiliary Feedwater System

04/19/2022

Torque and

Margin for 1ND27

As Left C1R26

10/23/2021

Westinghouse

Guideline

Document

ES-1.3 Transfer to Cold Leg Recirculation HP-Rev 3

03/31/2014

AD-EG-ALL-1432

Air Operated Valve Design Basis Review

AD-EG-ALL-1433

Air Operated Valve Testing Requirements

AD-OP-ALL-0105

Operability Determinations

AD-OP-ALL-0205

Time Critical Actions/Time Sensitive Actions

CNC-1205.19-00-

0176

JOG Classification of Catawbas GL96-05 MOV

Population

DPS-1205.19-00-

0002

Guideline for Performing Motor Operated Valve Reviews

and Calculations (For Engineering use only)

EP/2/A/5000/E-3

CNS Steam Generator Tube Rupture

EP/2/A/5000/ES-

1.3

Transfer to Cold Leg Recirculation

IP/0/A/3820/004 Q

MOV Diagnostic Testing

IP/0/A/3820/004 Q

MOV Diagnostic Testing

IP/0/A/3820/034

Removal/Restoration of Interferences and Packing Re-

Torque on Air Operated Valves (AOVs)

Procedures

IP/0/A/3820/047

AOV Diagnostic Testing using the QUIKLOOK3 System

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OP/1/A/6100/010K

Annunciator Response for Panel 1AD-10

OP/1/B/6100/010

X

Annunciator Response for Radiation Monitoring Panel

1RAD-1

OP/1/B/6100/010

Z

Annunciator Response for Radiation Monitoring Panel

1RAD-3

PD-EG-ALL-1430

Air Operated Valve Program

PT/0/A/4700/061

Time Critical Actions/ Time Sensitive Actions

PT/1/A/4200/021

A

KC Valve Inservice Test (QU)

PT/2/4/4200/013

G

NI Valve Inservice Test (UNK)

41,

completed

04/11/2021

PT/2/A/4200/0

CA Valve Inservice Test (QU)

13E

PT/2/A/4200/013

E

CA Valve Inservice Test (QU)

PT/2/A/4200/023

NC Valve Inservice Test (QU)

21,

completed

03/22/2022

PT/2/A/4200/079

Auxiliary Feedwater Flow Control Valve Air Accumulator

Leakage Test

PT/l/A/4200/001 T

Containment Penetration Valve Injection Water System

Performance Test

PT/l/A/4200/013 I

NV Valve Inservice Test

SI/0/A/5200/006

MOV Actuator Lubrication and Inspection

WO 1899772

ASSIST THE C.C.I. TECH IN REASSEMBLING THE

C.F.I.V. VALVES

2/16/2009

WO 20338520 01

1. Duke_WorkOrderPackage_Rpt_B 1CF - REPLACE

HYDRAULIC FLUID/INSPECT DESICCANT FOR CFIV 2.

IP/0/A/3010/024 MAIN FEEDWATER (CF) SYSTEM

FEEDWATER ISOLATION

05/17/2020

Work Orders

WOs

2050985, 20341710 01, 20436333 01, 20444997 02,

204646 01, 02119855 01, 20407902 01, 20380724 01

11