IR 05000413/2023002

Integrated Inspection Report 05000413/2023002 and 05000414/2023002

ML23205A215
Person / Time
Site:	Catawba
Issue date:	07/25/2023
From:	Eric Stamm NRC/RGN-II/DRP/RPB1
To:	Flippin N Duke Energy Carolinas
References
IR 2023002
Download: ML23205A215 (17)

Text

SUBJECT:

CATAWBA NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000413/2023002 AND 05000414/2023002

Dear Nicole Flippin:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba Nuclear Station. On July 19, 2023, the NRC inspectors discussed the results of this inspection with Jon Huecker, Plant Manager, 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, Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects 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:

05000413/2023002 and 05000414/2023002

Enterprise Identifier:

I-2023-002-0016

Licensee:

Duke Energy Carolinas, LLC

Facility:

Catawba Nuclear Station

Location:

York, South Carolina

Inspection Dates:

April 1, 2023, to June 30, 2023

Inspectors:

D. Rivard, Acting Senior Resident Inspector

A. Donley, Acting Senior Resident Inspector

J. Austin, Senior Project Engineer

S. Downey, Senior Reactor Operations Engineer

C. Dykes, Senior Health Physicist

J. Hickey, Senior Project Engineer

A. Hutto, Senior Project Engineer

J. Nadel, Senior Resident Inspector

A. Nielsen, Senior Health Physicist

C. Safouri, Senior Resident Inspector

C. Smith, Resident Inspector

A. Wang, Resident Inspector

Approved By:

Eric J. Stamm, Chief

Reactor Projects Branch 1

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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

Type Issue Number Title Report Section Status LER 05000414/2022-002-00 Catawba Nuclear Station,

Unit 2, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination 71153 Closed

PLANT STATUS

Unit 1 started the inspection period in power coast down at 94 percent rated thermal power (RTP). Unit 1 was shut down for a scheduled refueling outage on April 19, 2023. The unit was placed online on May 28, 2023, and returned to near 100 percent RTP on May 31, 2023. The unit operated at or near 100 percent RTP for the remainder of the inspection period.

Unit 2 operated at or near 100 percent RTP for the entire inspection period.

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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk-significant activities, and completed on-site portions of IPs. 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Train B of component cooling (KC) system during unplanned orange risk entry for loss of the KC train A on April 13, 2023

(2) Unit 1, train B qualified circuit between offsite transmission network and on-site essential auxiliary power system during Unit 1 outage on May 25, 2023

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire areas 14 and 15, Units 1 and 2, elevation 577', train A essential switchgear rooms, on April 12, 2023

(2) Fire area 18, Units 1 and 2, elevation 577', trains A and B spent fuel pool cooling pumps and heat exchangers, on April 25, 2023

(3) Fire areas 29 and 30, nuclear service water pump structure, building 7778, on April 26, 2023

(4) Fire area RB1, Unit 1, reactor building, lower and upper containment, on May 18, 2023

(5) Fire area 6, Unit 1, auxiliary building elevation 560', electrical penetration room, room 370, on June 15, 2023

(6) Fire area 5, Unit 2, auxiliary building elevation 560', electrical penetration room, room 360, on June 15, 2023

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 1, train B, KC heat exchanger during cleaning and inspection under work order 20554187

===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from May 1, 2023, to May 9, 2023.

PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Liquid Penetrant Examination

Weld 1KC276-1, pipe to pipe weld, ASME Class 2. This included a review of the associated welding activities.

Weld 1KC276-2, pipe to valve weld, ASME Class 2. This included a review of the associated welding activities.

Magnetic Particle Examination

Weld 1SGD-W259, nozzle to shell weld, ASME Class 2 Ultrasonic Examination

Weld 1-CF19-9, pipe to elbow weld, ASME Class 2

Weld 1NC82-1, nozzle to pipe weld, ASME Class 1

Weld 1NV613-3, pipe to elbow weld, ASME Class 1

Weld 1SGD-W259, steam generator D auxiliary feedwater nozzle to shell weld, ASME Class 2 Visual Examination

Bare metal visual examination of Reactor Vessel Bottom Mounted Instrument Nozzles, ASME Class 1 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) Bare metal visual examination of the reactor pressure vessel upper head

Eddy current examination (pre-peening) of reactor pressure vessel upper head, penetrations 4 and 60

Ultrasonic examination (pre-peening) of the reactor pressure vessel upper head, penetrations 4 and 60 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1) Boric acid walkdown on May 2, 2023

Work request (WR) 20221003 and evaluation nuclear condition report (NCR) 2418160

WR 20224279 and evaluation NCR 2425058

WR 20226756 and evaluation NCR 2437630 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)

The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:

(1) Eddy Current Examination o

Steam Generator 1A - eddy current testing (ECT) for tubes R69C112, R1078C82 o

Steam Generator 1B - ECT for tube R95C76 o

Steam Generator 1C - ECT for tubes R85C76, R104C83 o

Steam Generator 1D - ECT for tube R53C76

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (3 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 shutdown and cooldown for C1R27 refueling outage on April 19, 2023.

(2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 reactor startup following C1R27 refueling outage on May 27, 2023.

(3) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 planned control rod re-positioning at power on June 5, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (4 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1) NCR 02468311, WR 20246540, 2KC5 check valve failure

(2) NCRs 02459924, 02457768, shared auxiliary transformer SATB, cracks in winding casings and high core temperatures in transformers 1ATC, 1ATD, 2ATC, 2ATD, SATA

(3) NCR 02471723, wire found not terminated properly on point A-15R in cabinet 1EB4, Unit 1 - train B main power system protective relaying cabinet, on May 6, 2023

(4) NCR 02471740, nuclear oversight identified loose jam nut on support for strut of 1ND-2A, 1A decay heat removal pump suction isolation valve, on May 7, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 2 unplanned orange risk entry for component cooling 2KC5 discharge check valve failure and loss of train 2A of KC water, on April 18, 2023

(2) Unit 1 entry into yellow risk condition for reduced reactor coolant system inventory for reactor vessel head removal, on April 22, 2023

(3) Unit 1 high risk activity due to fuel offload during refueling outage, on April 26, 2023

(4) Unit 1 train B work window created yellow condition on decay heat removal, on April 27, 2023

(5) NCR 02470759, 10 CFR 50.65(a)(4) risk evaluation not performed for isolation of a steam supply to Unit 2 turbine driven auxiliary feedwater pump and entry into technical specification limiting condition for operation 3.7.5.A, on June 12, 2023

(6) Unit 1 spent fuel pool cooling system - protected equipment measures for high heat load following refueling, on June 14, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) NCR 02465959, 2B diesel generator cylinder 3 exhaust thermocouple broke during 5-hour diesel run

(2) NCR 02473925, 1B safety injection flow transmitter leak (potential void formation in discharge pipe)

(3) NCR 02468021, 2A emergency diesel generator (EDG) exhaust snubber issue

(4) NCR 02473493, 1A auxiliary feedwater pump recirculation control room indication failed

(5) NCR 02465116, N31 source range detector inoperable during fuel movement

(6) NCR 02476249, Overall containment leakage tracking methodology using PT/1/A/4200/001 L, Controlling Procedure for Type B & C Leakrate Tests, Revision 035

(7) NCR 02476718, 2B EDG jacket water shroud clamp

(8) NCR 02473087, Unit 2 fuel water storage tank wide range level instrument mounting bolts require retorque due to torque wrench reported out of tolerance

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage C1R27 activities from April 19, 2023, to May 28, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (6 Samples)

(1) IP/1/A3240/004D, Source Range (N31) and Intermediate Range (N35) Channel Operational Test (COT), on April 5, 2023

(2) PT/2/A/4400/003A, Component Cooling (KC) Train 2A Performance Test, on April 12, 2023

(3) PT/1/A/4200/001 C, 1RN-485 As-Left Local Leak Rate Test, following valve seat cleaning, on May 5, 2023

(4) PT/1/A/4200/010 E, Residual Heat Removal Pump Comprehensive Test, on May 10, 2023 (5)1ATC Transformer Doble testing performed in accordance with TE-MN-ALL-0202, Transformer and Apparatus Testing, Revision 2, following repair of cracks found in the winding casing, on May 16-17, 2023

(6) PT/1/A/4600/019 B, Premode 2 Periodic Surveillance Items, on May 27, 2023

Surveillance Testing (IP Section 03.01) (5 Samples)

(1) PT/1/A/4200/009, Engineered Safety Features (ESF) Actuation Period Test for B Safety Bus, on April 20-21, 2023

(2) PT/1/A/4200 009, Engineered Safety Features Actuation Periodic Test, B Train Blackout/LOCA and LOCA only, on April 21, 2023

(3) PT/2/A/4350/002 A, Diesel Generator 2A Operability Test, on May 2, 2023

(4) PT/2/A/4200/001, RCCA Movement Test, on June 5, 2023

(5) PT/2A/A/4350/015 A, Diesel Generator 2A Periodic Test, on June 6, 2023

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1) PT/1/A/4200/001 C, As Left Containment Isolation Valve Leak Rate Test, performed on Penetration M386, 1VQ-3B, and 1VQ-2A, on May 11, 2023

Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1) PT/0/A4200/086, Ice Bed Analysis Periodic Test, on June 30, 2023

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) NCR 02474037, elevated unidentified leakage upon entry to mode 3 and implementation of PT/1/B/4150/001 E, Identifying NC [reactor coolant system]

Leakage, on May 31,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Control of radioactive material stored in the Unit 1 spent fuel pool

(2) Licensee surveys of potentially contaminated material leaving the radiologically controlled area

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Unit 1 reactor head peening

(2) Unit 1 steam generator eddy current testing

(3) Unit 1 guide card inspection/replacement activities High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Unit 1 entrance to under-vessel area

(2) Unit 1 regenerative heat exchanger room

(3) Auxiliary building valve galleries Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Radioactive Material Storage (IP Section 03.01)

The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:

(1) Completed a walkdown of the remote radwaste storage location

(2) Radioactive material storage observed during plant walkdown on 577' elevation of the auxiliary building

Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)

The inspectors walked down the following radioactive waste systems and evaluated system configuration and functionality:

(1) Accessible portions of the solid radioactive waste system, including tanks and control panels in different areas of the auxiliary building, waste solidification facility, and other locations; discussed and reviewed system health with radwaste operations supervisor

(2) Accessible portions of the liquid radwaste system in the auxiliary building and monitor tank building, and observed current configuration of system; discussed system health with radwaste operations supervisor

Waste Characterization and Classification (IP Section 03.03) (2 Samples)

The inspectors evaluated the characterization and classification of radioactive waste for the following waste streams:

(1) Dry active waste (DAW), 12/06/2021

(2) Radwaste batch tank resin, 06/14/2022

Shipment Preparation (IP Section 03.04) (1 Sample)

(1) The inspectors observed portions of the preparation of radioactive shipment RSR 23-09 CNS

Shipping Records (IP Section 03.05) (4 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) RSR-23-09-CNS, UN3321, radioactive material, low specific activity (LSA-II), 7, DAW

(2) RSR-23-01-CNS, UN3321, radioactive material, low specific activity (LSA-II), 7, Resin

(3) RSR-21-07-CNS, UN3321, radioactive material, low specific activity (LSA-II), 7, DAW

(4) RSR-22-22-CNS, UN2916, radioactive material, Type B(U) package, 7, RQ-Radionuclides

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05)===

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) October 1, 2022, through May 5, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) January 1, 2022, through March 31, 2023

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event report (LER):

(1) LER 414/2022-002-00, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination (ADAMS Accession Number ML22340A427). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On May 5, 2023, the inspectors presented the radiation protection inspection results to Nicole Flippin and other members of the licensee staff.

On May 9, 2023, the inspectors presented the inservice inspection results to Nicole Flippin and other members of the licensee staff.

On July 19, 2023, the inspectors presented the integrated inspection results to Jon Huecker and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OP/2/A/6400/005

Component Cooling System

135

71111.04

Procedures

PT/1/A/4350/003

Electrical Power Source Alignment Verification

058

2468650, 02476384

Corrective Action

Documents

Resulting from

Inspection 71111.05

246572, 20246575, 20246576, 20246577,

246578, 20246579

CSD-CNS-PFP-AB-

0560-001

Auxiliary Building Elevation 554 & 560 Pre-Fire Plan

000

CSD-CNS-PFP-AB-

0577-001

Auxiliary Building Elevation 574 Cable Rooms &

Corridors

CSD-CNS-PFP-AB-

0577-001

Auxiliary Building Elevation 574 and 577 Pre-Fire Plan

000

CSD-CNS-PFP-AB-

0594-001

Auxiliary Building Elevation 594 Control Room & OSM

Office

Fire Plans

CSD-CNS-PFP-RB1-

0000-001

Unit 1 Reactor Building Elevation: All Pre-Fire Plan

000

CNM 1376.00-

0143.001

Fire Detection System (EFA) Detector Locations U2

Aux Building El. 577-0

001

CNM 1376.02-

0001.019

Aux Building 577 West Outer Unit 2

Miscellaneous

CNM 1376.02-

0001.020

Aux Building 577 West Outer Unit 1

71111.05

Procedures

PT/0/A/4200/048

Periodic Inspections of Fire Barriers and Related

Structures

033

Calculations

CNC-1201.06-00-

0011

Balance of Plant Heat Exchanger Tube Plugging

Limits

CN-1680-163

KC1B Component Cooling Heat Exchanger Tube

Plugging Map

Drawings

CN-1680-163-01

KC1B Component Cooling Heat Exchanger Tube

Plugging Map

Procedures

MP/0/A/7650/056C

KC Heat Exchanger Corrective Maintenance

71111.07A

Work Orders

20553527

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Catawba Unit 1 C1R27: Steam Generator

Degradation Assessment

Miscellaneous

262-TECR-102829

Steam Generator Condition Monitoring and Final

Operational Assessment for Catawba Unit 1 C1R24

Outage

000

MT-23-002

Magnetic Particle Examination of 1SGD-W259

05/05/2023

UT-23-005

Ultrasonic Examination of 1NC82-1

04/25/2023

UT-23-011

Ultrasonic Examination of 1NV613-3

04/29/2023

UT-23-016

Ultrasonic examination of 1SGD-W259

05/05/2023

VT-23-001

Visual Examination of 1RPV-BMI-NOZZLE

04/21/2023

NDE Reports

VT-23-044

Visual examination of 1-RPV-HEAD-SURFACE

05/05/2023

71111.08P

Work Orders

20416529-08

AP/1/A/5500/028

Secondary Steam Leak

013

OP/1/A/6100/002

Controlling Procedure for Unit Shutdown

205

OP/1/A/6100/003

Controlling Procedure for Unit Operation

146

PT/0/A/4150/019

1/M Approach to Criticality

041

PT/0/A/4150/030

RCCA Bank Repositioning

2

71111.11Q

Procedures

PT/1/A/4250/002D

Main Turbine Actual Overspeed Tests

27

71111.12

Corrective Action

Documents

2473173, 2466960

Corrective Action

Documents

2468311, 02470759

PRT-1-23-23FT B

DOWN -0095

Protected Equipment Clearance

Miscellaneous

PRT-1-23-C1R27 KF

PE -0088

Protected Equipment Clearance

AD-OP-ALL-0101

Event Response and Notification

013

AD-WC-ALL-0240

Online Risk Management Process

003

AD-WC-ALL-0410

Work Activity Integrated Risk Management

013

Procedures

OP/2/A/6400/005

Component Cooling System

103

71111.13

Work Orders

246581

71111.15

Calculations

KC-2003

Turbine Sump Pump Flow Calculation

004

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

OSC-6118

Loss of Non Emergency AC Power Event Mitigation

Requirements Type III

016

OSC-8966

Allowable LPSW Leakage for Containment Operability

Corrective Action

Documents

2465116, 02473493, 02466953, 02473087,

2468021, 02476718

Drawings

2-0380-21

Exhaust Manifold Assy, contained in CNM-

1301.00.0237.002, Diesel Generator Instruction

Manual Vol. II

Miscellaneous

CNM 1301.00-

285.001

Seismic Qualification Reports for Diesel Generator

Units

PT/1/A/4200/001 L

Controlling Procedure For Type B & C Leak Rate

Tests

035

Procedures

PT/1/A/4200/006 B

ECCS Valve Lineup Verification

068

Work Orders

245334, 20568131, 20607677, 20607678,

20607679, 2060768

OP/1/A/6100/001

Controlling Procedure for Unit Startup

256

Procedures

OP/1/A/6100/002

Controlling Procedure for Unit Shutdown

205

71111.20

Work Orders

249095, 20249096, 20249097, 20249103

Corrective Action

Documents

2465116, 02475670, 02471674

IP/1/A/320/004/B

NIS Source Range (SR) N31/N32 Intermediate Range

(IR) N35/N36 Channel Calibration

066

Procedures

71111.24

PT/1/A/4200/010 E

Residual Heat Removal Pump A1B Comprehensive

Test

003

71111.24

Work Orders

20590002, 20547306, 20585665-01

Corrective Action

Documents

Resulting from

Inspection

2471247, 02471621, 02471624

Engineering

Evaluations

PT/0/B/4600/099

Inspection and Integrity Testing of HEPA Filters,

13.1, HEPA # 20

05/03/2023

71124.01

Procedures

AD-RP-ALL-0002

Radiation and Contamination Surveys

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-RP-ALL-0003

Radiological Air Sampling

AD-RP-ALL-0004

Radiological Posting and Labeling

AD-RP-ALL-0008

Use and Control of HEPA Filtration and Vacuum

Equipment

Radiation Surveys

CNS-M-20230425-13

Room 104 ND Pump 1B

04/25/2023

MS07 High Pressure Injection Performance Data

04/2022 to 03/2023

MS08 Heat Removal Performance Data 04/2022 to

03/2023

71151

Miscellaneous

Catawba Master File:

CN-854.02-01

Emergency AC Power System MSPI/WANO

Unavailability