IR 05000369/2025003

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Integrated Inspection Report 05000369/2025003 and 05000370/2025003
ML25328A131
Person / Time
Site: Mcguire, McGuire  
Issue date: 11/26/2025
From: Robert Williams
NRC/RGN-II/DORS
To: Pigott E
Duke Energy Carolinas
References
IR 2025003
Download: ML25328A131 (0)


Text

SUBJECT:

MCGUIRE NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000369/2025003 AND 05000370/2025003

Dear Edward Pigott:

On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station. On November 19, 2025, the NRC inspectors 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.

Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.

No findings or violations of more than minor significance were identified during this inspection.

November 26, 2025 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, Robert E. Williams, Jr., Chief Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000369 and 05000370

License Numbers:

NPF-9 and NPF-17

Report Numbers:

05000369/2025003 and 05000370/2025003

Enterprise Identifier:

I-2025-003-0023

Licensee:

Duke Energy Carolinas, LLC

Facility:

McGuire Nuclear Station

Location:

Huntersville, North Carolina

Inspection Dates:

July 1, 2025, to September 30, 2025

Inspectors:

C. Safouri, Senior Resident Inspector

F. Young, Resident Inspector

S. Battenfield, Operations Engineer

K. Lei, Emergency Preparedness Inspector

M. Rich, Emergency Preparedness Inspector

J. Tornow, Physical Security Inspector

J. Walker, Senior Emergency Preparedness Inspector

Approved By:

Robert E. Williams, Jr., Chief

Projects Branch 1

Division of Operating Reactor Safety

SUMMARY

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

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power (RTP) for the entire 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.

REACTOR SAFETY

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) Unit 1 and Unit 2 auxiliary feedwater (CA) pumps assured suction sources from nuclear service water system, on July 23, 2025
(2) Unit 1 and Unit 2 interior doghouses, including portions of the main steam system, main steam vent to atmosphere system, and main steam supply to auxiliary equipment for steam generators 1B, 1C, 2B, and 2C, on September 6, 2025

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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) Unit 2 train A and train B 4160V switchgear and electrical penetration rooms, on July 25, 2025
(2) Unit 1 and Unit 2 shared equipment areas of auxiliary building elevation 716 and mechanical penetration rooms, on August 22, 2025

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 rod cluster control assembly bank repositioning, on August 11, 2025, and Unit 1 train B main feedwater pump high pressure governor steam leak in the turbine building, on August 12, 2025.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (4 Samples)

(1) The inspectors observed and evaluated annual requalification operating testing, on July 22, 2025
(2) The inspectors observed and evaluated annual requalification operating testing, on July 24, 2025
(3) The inspectors observed and evaluated annual requalification operating testing, on July 29, 2025
(4) The inspectors observed and evaluated annual requalification operating testing, on August 5 and 8, 2025

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

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

(1) Nuclear condition report (NCR) 02526647, Unit 1 train A diesel generator (D/G)battery charger failure, on July 15, 2025
(2) NCRs 02540897 and 02541049, Unit 2 train A CA suction swap over pressure switches, 2CAPS5002 and 2CAPS5350, found out of tolerance during calibration, on September 10, 2025

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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) NCR 02566232, Unit 1 turbine driven CA pump implementation of risk-informed completion time in response to an emergent gearbox seal issue, on August 28, 2025

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) NCR 02560176, Unit 1 train B D/G control air to shutdown cylinders solenoid failure, 1VGSV5171, on July 2, 2025
(2) NCR 02535481, station lubrication manual discrepancies for Unit 1 and Unit 2 diesel ventilation fan motors, on July 2, 2025
(3) NCR 02540358, Unit 1 turbine driven CA pump bearing vibrations in alert range, on July 17, 2025
(4) NCR 02566122, diesel building ventilation calculation indicating classification as a harsh environment per 10 CFR 50.49, on August 18, 2025
(5) Room temperature gradient and annunciator response during Unit 1 train A D/G 24-hour surveillance run, on August 18, 2025

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) (4 Samples)

(1) PT/0/A/4200/002, "Standby Shutdown Facility Operability Test," following standby shutdown facility planned maintenance window, on July 8, 2025
(2) PT/0/A/4350/028B, "125 Volt Vital Battery Quarterly Inspection," for Unit 1 and Unit 2 shared vital battery, EVCD, following equalizing charge, on July 30, 2025
(3) PT/1/A/4350/002A, "Diesel Generator 1A Operability Test," following Unit 1 train A D/G 24-hour run and subsequent maintenance, on August 21, 2025
(4) PT/1/A/4252/001, "Unit 1 Turbine Driven Auxiliary Feedwater Pump Performance Test," and PT/1/A/4252/007, "Auxiliary Feedwater System Turbine Driven Train Performance Test," following replacement of turbine governor gearbox shaft seal, on August 29, 2025

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) Unit 1 upper personnel airlock overall leak rate test, on July 31, 2025
(2) Unit 2 channel IV power range ex-core nuclear instrument channel, 2N-44, channel operational test, on July 31, 2025
(3) Unit 2 loop A, B, C, and D reactor coolant pump undervoltage and underfrequency 18-month calibration and functional test, on August 4, 2025

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of August 26, 2025. The simulated scenario began with a small leak on the reactor cold leg exceeding the threshold value for declaration of an Unusual Event. A short time later, an auxiliary feed pump failed to start due to a breaker issue, while concurrently the reactor failed to trip thus meeting the conditions for declaration of an Alert. As the scenario progressed, the turbine driven CA pump tripped due to a governor link issue.

The loss of heat sink resulted in a red critical safety functional area, thus meeting the conditions for declaration of a Site Area Emergency. The Offsite Response Organizations were able to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of August 25, 2025. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

(1) The inspectors evaluated an emergency preparedness drill that consisted of a faulted steam generator tube rupture, on September 24, 2025.

71114.08 - Exercise Evaluation - Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

OTHER ACTIVITIES - BASELINE

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

MS08: Heat Removal Systems (IP Section 02.07)===

(1) Unit 1 (July 1, 2024, through June 30, 2025)
(2) Unit 2 (July 1, 2024, through June 30, 2025)

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 (July 1, 2024, through June 30, 2025)
(2) Unit 2 (July 1, 2024, through June 30, 2025)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (July 1, 2024, through June 30, 2025)
(2) Unit 2 (July 1, 2024, through June 30, 2025)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (July 1, 2024, through June 30, 2025)
(2) Unit 2 (July 1, 2024, through June 30, 2025)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (July 1, 2024, through June 30, 2025)
(2) Unit 2 (July 1, 2024, through June 30, 2025)

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) July 1, 2024, through June 30, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
(1) July 1, 2024, through June 30, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
(1) January 1, 2025, through June 30, 2025

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 02550766, Unit 1 safety injection system containment penetration check valve, 1NI-436, failed as found penetration test, on September 8, 2025

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program to identify potential trends in out-of-tolerance evaluations associated with measurement and test equipment that might be indicative of a more significant safety issue.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On August 28, 2025, the inspectors presented the emergency preparedness exercise inspection results to T. Scott and other members of the licensee staff.
  • On November 19, 2025, the inspectors presented the integrated inspection results to Edward Pigott and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCFD-1574-01.00

Flow Diagram of Nuclear Service Water System - RN

MCFD-1574-01.01

Flow Diagram of Nuclear Service Water System - RN

MCFD-1574-02.00

Flow Diagram of Nuclear Service Water System - RN

MCFD-1574-03.00

Flow Diagram of Nuclear Service Water System - RN

MCFD-1592-01.00

Flow Diagram of Auxiliary Feedwater System (CA)

MCFD-1592-01.01

Flow Diagram of Auxiliary Feedwater System (CA)

MCFD-1593-01.01

Flow Diagram of Main Steam System (SM), Main Steam

Vent to Atmosphere (SV)

MCFD-1593-01.02

Flow Diagram of Main Steam Supply to Auxiliary Equipment

System (SA), Turbine Exhaust System (TE)

71111.04

Drawings

MCFD-1593-01.03

Flow Diagram of Main Steam System (SM), Main Steam

Vent to Atmosphere (SV)

CSD-MNS-PFP-

AB-0716-001

Auxiliary Building Elevation 716 Pre-Fire Plan

CSD-MNS-PFP-

AB-0733-001

Auxiliary Building Elevation 733 Pre-Fire Plan

71111.05

Fire Plans

CSD-MNS-PFP-

AB-0750-001

Auxiliary Building Elevation 750 Pre-Fire Plan

Drawings

MCFD-1593-02.00

Flow Diag of Steam Supply to FDWP Turb Sys (SP) Turb

Exhaust Sys (TE) Moisture Sep REHT Bleed Stm System

(HM)

ASE-16

Annual Requalification Operating Exam - Scenario 16

08/05/2025

ASE-17

Annual Requalification Operating Exam - Scenario 17

08/05/2025

ASE-18

Annual Requalification Operating Exam - Scenario 18

07/24/2025

ASE-19

Annual Requalification Operating Exam - Scenario 19

07/22/2025

ASE-32

Annual Requalification Operating Exam - Scenario 32

07/29/2025

ASE-33

Annual Requalification Operating Exam - Scenario 33

07/22/2025

ASE-35

Annual Requalification Operating Exam - Scenario 35

07/29/2025

Miscellaneous

ASE-44

Annual Requalification Operating Exam - Scenario 44

07/29/2025

AP/1/A/5500/01

Steam Leak

71111.11Q

Procedures

PT/0/A/4150/041

RCCA Bank Repositioning

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCC-1210.04-00-

0043

Instrument Loop Uncertainty for CA-RN Swapover Suction

Pressure Switch Loops CAPS5002, 5012, 5042, 5350,

5360, 5370, 5380, 5381, 5390, 5391

Calculations

MCC-1223.42-00-

0054

Documentation of the Adequacy of the Assured Suction

Sources to the Unit 2 CA Pumps

MC-24-0055

Plant Health Committee Action Commitment - 1A EDG

Battery Charger Failure

2/19/2024

71111.12

Miscellaneous

MCM 1356.08-

0015.001

Instruction Manual for 125 VDC 50 Amp Diesel Generator

Battery Chargers

AD-OP-ALL-0212

Risk Informed Completion Time Program Calculations,

3, RICT Projection Overview for Unit 1 turbine

driven auxiliary feedwater pump emergent issue

71111.13

Miscellaneous

RICT-2025-03

Risk Informed Completion Time Datasheet for Unit 1 turbine

driven auxiliary feedwater

08/26/2025

Calculations

MCC-1211.00-00-

0004

Diesel Generator Ventilation Calculation

Nuclear Condition

Report

2551623

Corrective Action

Documents

Problem

Investigation

Program (PIP)

M-91-00088

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report

2566122

MCEE-0120-09.07

Elementary Diagram Diesel Gen 1B Start Circuit

MCFD-1591-01.01

Flow Diagram of Feedwater System (CF)

MCFD-1609-04.00

Flow Diagram of Diesel Generator Starting Air System (VG)

MCID-1499-VG.03

Instrument Detail D.G. Pneumatic/Hydraulic Control

Schematic

Drawings

MCM 1205.08-

0083.001

Valve, Solenoid, Position Indication, Nuclear Service Model:

V573-5231-9

1.0

71111.15

Miscellaneous

MCS-1206.00-00-

0001

McGuire Pipe Rupture Analysis Criteria Specification

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCS-1206.00-02-

0002

Specification for the Design of Power Piping Systems

Materials and Components

217

MCS-1591.CF-00-

0001

Design Basis Specification for the CF System

MCS-1593.SM-00-

0001

Design Basis Specification for the SM, SV and SB Systems

MCS-1609.VG-00-

0001

Design Basis Specification for the VG System

MCS-1609.VN-00-

0001

Design Basis Specification for the VN System

MCTC-1609-

VG.V009-01

Valve Design Criteria/Operability Requirements and

Compensatory Measures: Solenoid Valves 1/2VG-5160,

1/2VG-5161, 1/2VG-5170, 1/2VG-5171

Procedures

OP/1/A/6101/010A

Annunciator Response for Panel 1AD-19 (Diesel Generator

Panel 1A)

20735067, 20700520

Work Orders

Work Request(s)

281681

Corrective Action

Documents

Nuclear Condition

Report

2562044, 02566232, 02566519, 02553074

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report

2567693

25926

M, CGI, PQL, 9230058046, Mechanical Seal, SKF, HGB/TS

Engineering

Changes

25927

Turbine Driven CA Pump Governor Gearbox shaft seal

equivalency

Miscellaneous

LCOTR# A-1-25-

01160

LCO Tracking: Unit 1 Upper Containment Airlock Overall

Leak Rate Test

07/31/2025

IP/0/A/3061/012

Charging Site Lead-Acid Batteries

PT/0/A/4200/041

Standby Shutdown Facility Diesel Load Rejection Test

PT/1/A/4200/001

E

Upper PAL Overall LRT

71111.24

Procedures

PT/2/A/4600/014

G

NIS Power Range N-44 Channel Operational Test

033

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

PT/2/A/4971/021

Reactor Coolant Pump (RCP)

Undervoltage/Underfrequency Functional Test

PT/2/A/4971/022

Reactor Coolant Pump (RCP) Undervoltage Relay (ABB

27N) Calibration)

PT/2/A/4971/023

Reactor Coolant Pump (RCP) Underfrequency Relay (ABB

81) Calibration

20633048, 20653991, 20660639, 20661904, 20700339,

20700340, 20709106, 20711351, 20724996, 20724997,

20724998, 20725000, 20717637, 20700520, 20746078,

20746193, 20725192, 20724671

Work Orders

Work Request(s)

291020, 20291094, 20291095, 20291107, 20292010

71114.01

Procedures

CSD-EP-MNS-

0101-01

MNS EAL TECHNICAL BASIS DOCUMENT

EP-ALL-EPLAN

Duke Energy Common Emergency Plan

71114.04

Procedures

EP-MNS-EPLAN-

ANNEX

Duke Energy McGuire Emergency Plan Annex

Corrective Action

Documents

Nuclear Condition

Report

2569804, 02569805

71114.06

Miscellaneous

MNS Drill 25-04

09/16/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Cooling

Water System - Unavailability Index (UAI)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Cooling

Water System - Unreliability Index (URI)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Cooling

Water System - Performance Limit Exceeded (PLE)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Cooling

Water System - Unavailability Index (UAI)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Cooling

Water System - Unreliability Index (URI)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Heat

Removal System - Performance Limit Exceeded (PLE)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Heat

Removal System - Unavailability Index (UAI)

08/11/2025

71151

Miscellaneous

MSPI Derivation Report - McGuire Unit 1 - MSPI Heat

08/11/2025

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Removal System - Unreliability Index (URI)

MSPI Derivation Report - McGuire Unit 2 - MSPI Heat

Removal System - Performance Limit Exceeded (PLE)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Heat

Removal System - Unavailability Index (UAI)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Heat

Removal System - Unreliability Index (URI)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Residual

Heat Removal System - Performance Limit Exceeded (PLE)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Residual

Heat Removal System - Unavailability Index (UAI)

08/11/2025

MSPI Derivation Report - McGuire Unit 1 - MSPI Residual

Heat Removal System - Unreliability Index (URI)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Residual

Heat Removal System - Performance Limit Exceeded (PLE)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Residual

Heat Removal System - Unavailability Index (UAI)

08/11/2025

MSPI Derivation Report - McGuire Unit 2 - MSPI Residual

Heat Removal System - Unreliability Index (URI)

08/11/2025

24/Q3 MNS PI Data

24/Q4 MNS PI Data

25/Q1 MNS PI Data

25/Q2 MNS PI Data

MSPI Derivation Report - McGuire Unit 1 - MSPI Cooling

Water System - Performance Limit Exceeded (PLE)

08/11/2025

Corrective Action

Documents

Nuclear Condition

Report

2554562, 02542835, 02488726, 02488727

71152A

Work Orders

20721023, 20444744, 20437522

Corrective Action

Documents

Resulting from

Inspection

Nuclear Condition

Report

2570856

AD-EG-ALL-1107

Quality Classifications

71152S

Procedures

AD-NS-NGO-0005

Conduct of Standards Lab

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-SS-ALL-0001

Control of Portable Measuring and Test Equipment and

Plant Tools and Portable Media/Mobile Devices (PMMD)

Nuclear Condition

Report

2541641, 02543290, 02543405, 02545032, 02546856,

2555319, 02560887

PD-NS-ALL-0001

Measuring and Test Equipment Program

3