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

July 25, 2023

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, Signed by Stamm, Eric on 07/25/23 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 Enclosure

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

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)

(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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Procedures OP/2/A/6400/005 Component Cooling System 135

PT/1/A/4350/003 Electrical Power Source Alignment Verification 058

71111.05 Corrective Action 02468650, 02476384

Documents 20246572, 20246575, 20246576, 20246577,

Resulting from 20246578, 20246579

Inspection 71111.05

Fire Plans CSD-CNS-PFP-AB- Auxiliary Building Elevation 554 & 560 Pre-Fire Plan 000

0560-001

CSD-CNS-PFP-AB- Auxiliary Building Elevation 574 Cable Rooms &

0577-001 Corridors

CSD-CNS-PFP-AB- Auxiliary Building Elevation 574 and 577 Pre-Fire Plan 000

0577-001

CSD-CNS-PFP-AB- Auxiliary Building Elevation 594 Control Room & OSM

0594-001 Office

CSD-CNS-PFP-RB1- Unit 1 Reactor Building Elevation: All Pre-Fire Plan 000

0000-001

Miscellaneous CNM 1376.00- Fire Detection System (EFA) Detector Locations U2 001

0143.001 Aux Building El. 577-0

CNM 1376.02- Aux Building 577 West Outer Unit 2 0

0001.019

CNM 1376.02- Aux Building 577 West Outer Unit 1 0

0001.020

Procedures PT/0/A/4200/048 Periodic Inspections of Fire Barriers and Related 033

Structures

71111.07A Calculations CNC-1201.06-00- Balance of Plant Heat Exchanger Tube Plugging 10

0011 Limits

Drawings CN-1680-163 KC1B Component Cooling Heat Exchanger Tube 7

Plugging Map

CN-1680-163-01 KC1B Component Cooling Heat Exchanger Tube 7

Plugging Map

Procedures MP/0/A/7650/056C KC Heat Exchanger Corrective Maintenance 36

Work Orders 20553527

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Miscellaneous Catawba Unit 1 C1R27: Steam Generator 0

Degradation Assessment

262-TECR-102829 Steam Generator Condition Monitoring and Final 000

Operational Assessment for Catawba Unit 1 C1R24

Outage

NDE Reports 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

VT-23-044 Visual examination of 1-RPV-HEAD-SURFACE 05/05/2023

Work Orders 20416529-08

71111.11Q Procedures 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 042

PT/1/A/4250/002D Main Turbine Actual Overspeed Tests 027

71111.12 Corrective Action 2473173, 2466960

Documents

71111.13 Corrective Action 02468311, 02470759

Documents

Miscellaneous PRT-1-23-23FT B Protected Equipment Clearance

DOWN -0095

PRT-1-23-C1R27 KF Protected Equipment Clearance

PE -0088

Procedures 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

OP/2/A/6400/005 Component Cooling System 103

Work Orders 20246581

71111.15 Calculations KC-2003 Turbine Sump Pump Flow Calculation 004

Inspection Type Designation Description or Title Revision or

Procedure Date

OSC-6118 Loss of Non Emergency AC Power Event Mitigation 016

Requirements Type III

OSC-8966 Allowable LPSW Leakage for Containment Operability 0

Corrective Action 02465116, 02473493, 02466953, 02473087,

Documents 02468021, 02476718

Drawings 02-0380-21 Exhaust Manifold Assy, contained in CNM-

1301.00.0237.002, Diesel Generator Instruction

Manual Vol. II

Miscellaneous CNM 1301.00- Seismic Qualification Reports for Diesel Generator

285.001 Units

Procedures PT/1/A/4200/001 L Controlling Procedure For Type B & C Leak Rate 035

Tests

PT/1/A/4200/006 B ECCS Valve Lineup Verification 068

Work Orders 20245334, 20568131, 20607677, 20607678,

20607679, 2060768

71111.20 Procedures OP/1/A/6100/001 Controlling Procedure for Unit Startup 256

OP/1/A/6100/002 Controlling Procedure for Unit Shutdown 205

Work Orders 20249095, 20249096, 20249097, 20249103

71111.24 Corrective Action 02465116, 02475670, 02471674

Documents

Procedures IP/1/A/320/004/B NIS Source Range (SR) N31/N32 Intermediate Range 066

71111.24 (IR) N35/N36 Channel Calibration

PT/1/A/4200/010 E Residual Heat Removal Pump A1B Comprehensive 003

Test

Work Orders 20590002, 20547306, 20585665-01

71124.01 Corrective Action 02471247, 02471621, 02471624

Documents

Resulting from

Inspection

Engineering PT/0/B/4600/099 Inspection and Integrity Testing of HEPA Filters, 05/03/2023

Evaluations Enclosure 13.1, HEPA # 20

Procedures AD-RP-ALL-0002 Radiation and Contamination Surveys 3

Inspection Type Designation Description or Title Revision or

Procedure Date

AD-RP-ALL-0003 Radiological Air Sampling 4

AD-RP-ALL-0004 Radiological Posting and Labeling 7

AD-RP-ALL-0008 Use and Control of HEPA Filtration and Vacuum 1

Equipment

Radiation Surveys CNS-M-20230425-13 Room 104 ND Pump 1B 04/25/2023

71151 Miscellaneous MS07 High Pressure Injection Performance Data

04/2022 to 03/2023

MS08 Heat Removal Performance Data 04/2022 to

03/2023

Catawba Master File: Emergency AC Power System MSPI/WANO

CN-854.02-01 Unavailability

15