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 Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations AD-EG-ALL-1117 U2, 6.9KV, 4.16KV, & 600V Auxiliary Power Systems 19

Safety-Related Voltage Analysis

CNC -1205.19-00- Generic Letter 89-10 MOV Calculations, NC System; 1(2)11

28 NC033A, 035B, 1NC031B

CNC -1205.19-00- 89-10 Calculation for 1&2 CA038A, 42B, 46B, 50A, 54B, 14

29 58A, 62A, 66B

CNC -1205.19-00- Generic Letter 89-10 Calculation For Valves 1 and 4

0033 NI173A and NI178B

CNC -1205.19-00- GL 89-10 Set-Up Calculation for Valves 1KC001A, 3

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- 1 (2) ND 26, 27, 60, and 61 Fisher Actuator and Margin1

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 19

0199 SYSTEMS SAFETY-RELATED VOLTAGE ANALYSIS

CNC 1205.41-00- 1 (2) NV 010A, 011A, and 013A Required Thrust 2

0018 Evaluation supporting Air Operated Valve (AOV) Program

CNC-1205.41-00- Air Operated Valve (AOV) Program Scope Calculation 5

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 1

0016 Calculation

CNC-1205.41-00- 1 (2) NV 010A, 011A, and 013A Required Thrust 2

Inspection Type Designation Description or Title Revision or

Procedure 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, 1

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 4

0045 Containment Isolation Valves 1 & 2 NI173A, NI178B

CNC-1552.08-00- Long-Term Containment Response - Manual NS Initiation 7

0390

CNM 1205.00- Design/Seismic Report (Weak Link) for 09J-2056, 2", 5

2182.001 1500#, SS, Gate Valve

CNM 1205.01-Design & Seismic RPT 6J-339 C

0797.001

Corrective Action ARs 02373087, 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 2022 NRC DBAI POV - 2NI173A Motor Brake Internals 06/02/2022

Inspection NCR 02430135 2022 NRC DBAI POV - 1KC-50A Maximum Transmitted 06/06/2022

Torque

NCR 02430281 2022 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 located06/07/2022

NCR 02430342 2022 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 2022 NRC DBAI POV - 2NC35B - Actuator Fastener Bolt 06/09/2022

Preload

NCR 02431086 2022 NRC DBAI POV - UFSAR sec.6.2.4.1 incorrect 06/14/2022

statement

Inspection Type Designation Description or Title Revision or

Procedure Date

NCR 2428952 2022 NRC DBAI POV - 2NC035B High Temp Torque 05/26/2022

Factor

NCR 2430567 NRC DBAI POV-EOPs do not align with UFSAR 06/09/2022

Drawings 02-403-0012-3 Limitorque Valve Control DI

40846-08 20- Class 150 Valve Assembly and Limitorque H2BC-DE

SMB-00-10

CN -1561-01.00 Flow Diagram of Residual Heat Removal System (ND) 34

CN -2561-01.00 Flow Diagram of Residual Heat Removal System (ND) 38

CN -2562-01.01 Flow Diagram, Safety Injection System (NI) 23

CN -2592-01.01 Flow Diagram Auxiliary Feedwater System (CA) 33

CN-1573-01.0 Flow Diagram of Component Cooling System (KC) 30

CN-2499-CA.07-Instrument Detail Motor Driven Auxiliary Feedwater Pump 9

to Steam Generator Flow Control

CN-2553-01.01 Flow Diagram of Reactor Coolant System (NC) 20

CN-2562-01.03 Flow Diagram of Safety Injection System (NI) 28

CNEE-0247-04.12 Auxiliary Feedwater System (CA) CA Pump No. 2 Disch 4

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

CNEE-0247-Auxiliary Feedwater System (CA) CA Pump No. 2 Disch 2

04.12-01 to S/D 2C Isol. Vlv. 2CA050A Controls

CNEE-0250-01.09 Reactor Coolant System (NC) Pzr Power Operated Relief 12

Isolation Valve 2NC035B

CNEE-0251-01.32 Elementary Diagram Safety Injection System (NI) ND 6

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

CNM 1205.00- 8"SS Motor Oper Gate Vlv Item 9J211 16

0074.001

CNM 1205.00- O/L Drawing for 09J-2056, 2", 1500#, SS, Gate Valve 0

2181.001

CNM 1205.01-4" 1500LB CS EMO DP Gate Valve 6J-339 H

0790.001

CNM 1205.01-4" 1500LB CS DP Gate Valve 6J-339 J

0790.002

CNM 1205.06-O/L, C/S, B/M, OPR, W/D Control Valves 1&2/CA/40, 44, J

20.001 56 & 60

W9223811, Sht. 1 3"- 1530 Weld Ends Stainless Steel Double Disc Gate B

Inspection Type Designation Description or Title Revision or

Procedure Date

Valve for SMB-00-15 Limitorque Actuator

W9223811, Sht. 2 3"- 1530 Weld Ends Stainless Steel Double Disc Gate B

Valve for SMB-00-15 Limitorque Actuator

Engineering CN 20328 Modify control circuit wiring on 2NI-9A, 10B, 100B, 183B, 11/07/1988

Changes 162A, 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.

CN 21319 Modify CA Control Valves to Prevent S/G Overfill During 08/11/1999

SGTR

EC 0000106724 Revise MOV Set-Up Sheets to Meet GL 96-05 09/07/2012

Requirements for 1KC001A, 002B, 050A

EC 0000402775 U-1 AND U-2 NW System Isolation to Specific CIVs 1

Engineering CNC -1205.19-00- EC420978 - Revise valve factor for 1(2)NI173A & 000

Evaluations 0176-ICC-0003 1(2)NI178B

CNC -1205.19-00- Kalsi Engineering Report 2919C, GL96-05 Periodic 0

0179 Verification Program for Butterfly Valves with 316

Microseal Bearings {JOG Class D)

CNC -1381.05-00- U2, 6.9KV, 4.16KV, & 600V Auxiliary Power Systems 19

0199 Safety-Related Voltage Analysis

CNC-1205.00-00- GL 95-07 Pressure Locking and Thermal Binding Review 1

0048 of Valves Without an Active to Open Safety Function

CNC-1205.19-00- Operability Evaluation of Rotork Part 21 for Switch 1

0170 Mechanisms

CNM 1205.00- ASME Section III Gate Valve Seismic Report 5

0549.001

CNM 1205.00- Design and Seismic Analysis Report for 3" EMO Gate 00C

2050.001 Valve, Item 9J-364

CNM 1205.02-Weak-Link Report for CNS BFV Item Number 05B-501 0

0766.001

CNM 1205.19-Stress Report for Westinghouse Class 1 Nuclear Valves-D3

0094.001 Gate Valves

CNM 1205.19-9J-211 Seismic and Weak Link Analysis Report for 0

099.011 Westinghouse Class 1 Nuclear Valve

Inspection Type Designation Description or Title Revision or

Procedure Date

DPC 1205.41-00- Evaluation of AOV Issues Needed for Margin Calculations2

0001

DPC-1205.00-00- Microseal Bearing Test Report: Kalsi Engineering 0

0008 Document 2800C

Miscellaneous [N/A] OAC Alarm Response Information for loss of SOV Power

BACKGROUND ES-1.3 Transfer to Cold Leg Recirculation HP-Rev. 3 03/31/2014

INFORMATION

FOR

WESTINGHOUSE

OWNERS

GROUP

EMERGENCY

RESPONSE

GUIDELINE

CDUK-1205.41-Unit 1 and Unit 2 AOV Test Set Up Sheets 7

0001.001

CE 0000106724 Revise MOV Set-Up Sheets to Meet GL 96-05 09/17/2012

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

CN 500404 Allow Replacement of Solenoid Valves w/ New Model 05/17/2005

CN-11413 De-energize the Hydraulic Solenoids on the Main 08/06/2001

Feedwater Isolation Valves

CNC -1205.19-00- EC420956-Revise Valve Factor and Functions for CA 0

0176-ICC-0004 MOVs

CNM 1205.00- l/B Manual M/0 Gate Valves & Swing Check Vlvs D10

22.001

CNM 1205.00- EMO Torque Switch Setting Sheets 90

1997.001

CNM 1205.00- EMO Torque Switch Setting Sheets 90

1997.001

CNM 1205.00- Instruction Manual Number ET347 for 3" 1530 Class 10/01/1997

2049-001 Double Disc Gate Valves with Motor Actuators

CNM 1205.02-Posi-Seal Butterfly Valve Technical Bulletin Series 0

0762.001

CNM 1205.06-I/M & Parts List for Control Valves and Regulators 42

Inspection Type Designation Description or Title Revision or

Procedure Date

268.001

CNM 1205.19-Limitorque Nuclear Qualification Reports 3

0001.001

CNM 1205.19-Technical Repair Guide for Rotork Valve Actuators "NA" 9

0083.001 Range Models

CNM 1205.19-Rotork Motor Operator Bench Test Certificates D7

0114.001

CNS-1205.00-00- ASME Section 3 Stainless Steel Gate Globe and Check 5

0008 Valves

CNS-1205.06-00- Control Valves to ASME Section III 17

0003

CNS-1553.NC-00- Reactor Coolant System (NC) Design Basis Specification 50

0001

CNS-1554.NV-00- Chemical and Volume Control System (NV) Design Basis 53

0001 Specification

CNS-1561.ND-00- Design Basis Specification for The Residual Heat 42

0001 Removal (ND) System

CNS-1562.NI-00- Design Basis Specification For the Safety Injection (NI) 52

0001 System

CNS-1573.KC-00- Component Cooling System (KC) Design Basis 49

0001 Specification

CNS-1591.CF-00- Design Basis Specification for the Feedwater (CF) Rev. 034

0001 System

CNS-1592.CA-00- Auxiliary Feedwater System (CA) Design Basis 50

0001 Specification

CNS-1592.CA-00- Auxiliary Feedwater System (CA) Design Basis 50

0001 Specification

DPS 1205.00-00- Nuclear Safety Related Carbon and Stainless Steel 4

0002 Forged and Cast Electric Motor Operated Valves

DPS-1205.19-00- Safety Related Rotork Motor Operators and Spare Parts 4

0004

EQMM-1393.01-Environmental Qualification Maintenance Manual 15

Q03-01 Equipment Type: Solenoid Valve Manufacturer: Valcor

Engineering Corporation Model/Series: V70900-65 Series

Inspection Type Designation Description or Title Revision or

Procedure Date

Valves

OEDB Number: LIMITORQUE TECHNICAL UPDATE #92-O1 Kalsi 01/06/1992

2-12415 Engineering Document #17O7-C, Rev. o (11-25-91)

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

SMB-1 Actuators

OP-CN-CF-CF Feedwater System Lesson Plan 04/07/2014

OP-CN-EP-INTRO Emergency Procedures Intro Lesson Plan CNOB50 11

System Health KC - Component Cooling System 04/19/2022

Report

System Health ND - Residual Heat Removal System 04/19/2022

Report

System Health CA - CNS l Unit 2 l CA - Auxiliary Feedwater System 04/19/2022

Report

Torque and As Left C1R26 10/23/2021

Margin for 1ND27

Westinghouse ES-1.3 Transfer to Cold Leg Recirculation HP-Rev 3 03/31/2014

Guideline

Document

Procedures AD-EG-ALL-1432 Air Operated Valve Design Basis Review 1

AD-EG-ALL-1433 Air Operated Valve Testing Requirements 2

AD-OP-ALL-0105 Operability Determinations 6

AD-OP-ALL-0205 Time Critical Actions/Time Sensitive Actions 2

CNC-1205.19-00- JOG Classification of Catawbas GL96-05 MOV 9

0176 Population

DPS-1205.19-00- Guideline for Performing Motor Operated Valve Reviews 4

0002 and Calculations (For Engineering use only)

EP/2/A/5000/E-3 CNS Steam Generator Tube Rupture 41

EP/2/A/5000/ES-Transfer to Cold Leg Recirculation 31

1.3

IP/0/A/3820/004 Q MOV Diagnostic Testing 13

IP/0/A/3820/004 Q MOV Diagnostic Testing 13

IP/0/A/3820/034 Removal/Restoration of Interferences and Packing Re-43

Torque on Air Operated Valves (AOVs)

IP/0/A/3820/047 AOV Diagnostic Testing using the QUIKLOOK3 System 5

Inspection Type Designation Description or Title Revision or

Procedure Date

OP/1/A/6100/010K Annunciator Response for Panel 1AD-10 21

OP/1/B/6100/010 Annunciator Response for Radiation Monitoring Panel 67

X 1RAD-1

OP/1/B/6100/010 Annunciator Response for Radiation Monitoring Panel 25

Z 1RAD-3

PD-EG-ALL-1430 Air Operated Valve Program 2

PT/0/A/4700/061 Time Critical Actions/ Time Sensitive Actions 9

PT/1/A/4200/021 KC Valve Inservice Test (QU) 79

A

PT/2/4/4200/013 NI Valve Inservice Test (UNK) 41,

G completed

04/11/2021

PT/2/A/4200/0 CA Valve Inservice Test (QU) 13E

PT/2/A/4200/013 CA Valve Inservice Test (QU) 66

E

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 11

Leakage Test

PT/l/A/4200/001 T Containment Penetration Valve Injection Water System 76

Performance Test

PT/l/A/4200/013 I NV Valve Inservice Test 49

SI/0/A/5200/006 MOV Actuator Lubrication and Inspection 33

Work Orders WO 1899772 ASSIST THE C.C.I. TECH IN REASSEMBLING THE 12/16/2009

C.F.I.V. VALVES

WO 20338520 01 1. Duke_WorkOrderPackage_Rpt_B 1CF - REPLACE 05/17/2020

HYDRAULIC FLUID/INSPECT DESICCANT FOR CFIV 2.

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

FEEDWATER ISOLATION

WOs 02050985, 20341710 01, 20436333 01, 20444997 02,

204646 01, 02119855 01, 20407902 01, 20380724 01

11