IR 05000413/2022010
| 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:
Report Numbers:
05000413/2022010 and 05000414/2022010
Enterprise Identifier: I-2022-010-0038
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-
C
0797.001
Corrective Action
2373087, 02294259, 01497427, 02407695, 02294259,
Documents
01497427, 02428219, 01898027, 02300922
Corrective Action
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
22 NRC DBAI POV - 2NI173A Motor Brake Internals
06/02/2022
Inspection
22 NRC DBAI POV - 1KC-50A Maximum Transmitted
06/06/2022
22 NRC DBAI POV - Lesson Plans not revised post
06/07/2022
Mod
PT/1/A/4350/002 E enclosure 13.16 could not be located
06/07/2022
22 NRC POV DBAI - Incorrect Reference in Flowserve
06/07/2022
Letter
Obstructions on 522' elevation floor drains
06/08/2022
NRC DBAI POV-EOPs do not align with UFSAR
06/09/2022
22 NRC DBAI POV - 2NC35B - Actuator Fastener Bolt
06/09/2022
Preload
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
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
08/11/1999
Revise MOV Set-Up Sheets to Meet GL 96-05
Requirements for 1KC001A, 002B, 050A
09/07/2012
Engineering
Changes
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
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
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
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
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
OP/1/B/6100/010
Z
Annunciator Response for Radiation Monitoring Panel
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
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
2050985, 20341710 01, 20436333 01, 20444997 02,
204646 01, 02119855 01, 20407902 01, 20380724 01
11