IR 05000369/2024010

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Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010
ML24071A231
Person / Time
Site: McGuire, Mcguire  
Issue date: 03/13/2024
From: James Baptist
NRC/RGN-II/DRS/EB1
To: Pigott E
Duke Energy Carolinas
References
IR 2024010
Download: ML24071A231 (20)
v • d • e


Text

March 13, 2024

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 & 2 - COMPREHENSIVE ENGINEERING TEAM INSPECTION REPORT 05000369/2024010 AND 05000370/2024010

Dear Edward Pigott:

On February 8, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at McGuire Nuclear Station, Units 1 & 2 and discussed the results of this inspection with Mr.

Brent Bare, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at McGuire Nuclear Station, Units 1 & 2. 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. 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:

05000369/2024010 and 05000370/2024010

Enterprise Identifier:

I-2024-010-0020

Licensee:

Duke Energy Carolinas, LLC

Facility:

McGuire Nuclear Station, Units 1 & 2

Location:

Huntersville, NC

Inspection Dates:

January 22, 2024, to February 08, 2024

Inspectors:

P. Braxton, Reactor Inspector

L. Day, Reactor Inspector

S. Downey, Senior Reactor Inspector

R. Fanner, Reactor Inspector

C. Franklin, Reactor Inspector

G. Ottenberg, Senior Reactor Inspector

D. Ray, Reactor Inspector

A. Ruh, Reactor Inspector

T. Su, Reactor Inspector

J. Vasquez, Reactor Inspector

Approved By:

James B. Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Comprehensive Engineering Team Inspection at McGuire Nuclear Station, Units 1 & 2, 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

Failure to Include Inservice Test (IST) Requirements in IST Plan in Accordance with ASME OM Code Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000369,05000370/2024010-01 Open/Closed None (NPP)71111.21M The inspectors identified a Green finding and associated non-cited violation (NCV) of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(f), for the licensee's failure to identify components and their testing requirements in their inservice testing (IST) interval testing plan.

The licensee failed to fully implement changes which credited newly installed check valves as pressure relief devices, thus, the requirements of the 2004 Edition through the 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) were not met.

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

===71111.21M - Comprehensive Engineering Team Inspection The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Structures, Systems, and Components (SSCs) (IP section 03.01)===

Main article: IP 71111.21

For each structure, system, or component sample listed below, the team reviewed licensing and design basis documents and a sampling of applicable operator actions, periodic testing results, corrective action program documents, internal and external operating experience, preventive and corrective maintenance work orders, modifications, and aging management programs. Additionally, the team performed walkdowns of the component or procedure and conducted interviews with licensee personnel.

The team used the attributes contained in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below as guidance. Specifically, the team evaluated these attributes in the course of applying 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.

(1)1NC-31B, 1NC-33A, 1NC-35B, Unit 1 Pressurizer Power Operated Relief Valves (PORV) Block Valves

  • Surveillance testing & maintenance records

(2)2B ND Pump, Unit 2 Residual Heat Removal Pump B

  • Translation of design basis performance into system calculations and surveillance test acceptance criteria
  • Performance during inservice testing and selection of instrumentation
  • Walkdown of equipment configuration and material condition
  • Detection, evaluation and control of system gas voids
  • System boundary leakage testing and controls (3)1NV-238, Unit 1 Charging Header Control Air Operated Valve
  • Control circuit design and evaluation of various failure modes and effects on availability of reactor coolant pump seal injection
  • Safety classification of the mechanical and electrical components as compared to the UFSAR and TS design descriptions
  • Consistency between operational procedures and operator actions
  • Walkdown of equipment configuration and material condition (4)2B ND HX, Unit 2 Residual Heat Removal Heat Exchanger B
  • Design bases documents and calculations, including heat transfer capacity and design basis accident response capability
  • Visual inspection during walkdown of component
(5) Unit 1 Relay 1ESGAX3
  • Preventative maintenance and surveillance
  • Design Calculations
  • Vendor Manuals
(6) Unit 2 Auto Reset Relay ED(TRB3), 2B D/G Load Sequencer Auto-Reset Relay
  • 2ETB Blackout During ESF Testing Restoration Sequence
  • Design verification
  • Vendor manual review
  • Maintenance work review
(7) Unit 1 600 VAC Load Center 1ELXA
  • Walkdown of equipment to assess material condition
  • Review of operating experience
  • Workorders, operator training, time critical actions, and applicable procedure reviews

Modifications (IP section 03.02) (4 Samples)

(1) EC 401581, Permanently Fail Valve, 2KD-9, Open. Remove and/or Abandon In Place 2KDTT5260 And Associated Equipment, Revision 1
(2) EC 1111341, Delete Jog Circuit on Unit 1 RN to KC Inlet Reverse EC 102708 and Remove Jog Circuit, Revision 3
(3) EC 107430, RN (1B) Suction Piping - Supplemental Vent Line, Revision 10
(4) EC 420097-003, U2 D/G Sequencer Reset Contact Change, Revision 3 10 CFR 50.59 Evaluations/Screening (IP section 03.03) (8 Samples)

(1)10 CFR 50.59 Screening: EC 413368, Interferences Associated With 2B2 KC Motor Replacement, Revision 4 (2)10 CFR 50.59 Evaluation: AR 02453578, Update to UFSAR Table 15-33: Parameters for Minimum Safeguards (Design Basis) LOCA Dose Analysis (3)10 CFR 50.59 Screening: EC 418694, Replace 2NI-436 with 09J-2060, Revision 0 (4)10 CFR 50.59 Evaluation: AR 2365577, EC 417951,1B SSPS Printed Circuit Board Replacement (5)10 CFR 50.59 Screening: EC 416278-001, Add Train Related CA Instruments Physical Separation Requirements to Instrument Details (6)10 CFR 50.59 Screening: Screening-AR 2154349, Change the Actuator on 2NV0842AC from a Rotork 11NA2-57 (7)10 CFR 50.59 Evaluation: AR 2404321, EC419503/000 & EC418989/005, MNS Waste Gas H2 Recombiner Gas Analyzer Digital Upgrade (8)10 CFR 50.59 Screening: AR 2325304, 0000106371 - 000 Replace Panelboard 2EKVD

Operating Experience Samples (IP section 03.04) (1 Sample)

(1) Information Notice 2019-01: Inadequate Evaluation of Temporary Alterations

INSPECTION RESULTS

Failure to Include Inservice Test (IST) Requirements in IST Plan in Accordance with ASME OM Code Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000369,05000370/2024010-01 Open/Closed None (NPP)71111.21M The inspectors identified a Green finding and associated non-cited violation (NCV) of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(f), for the licensee's failure to identify components and their testing requirements in their inservice testing (IST) interval testing plan.

The licensee failed to fully implement changes which credited newly installed check valves as pressure relief devices, thus, the requirements of the 2004 Edition through the 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) were not met.

Description:

During a review of engineering changes (ECs) 107089, 107090, 107430, and 107431, the NRC inspectors identified that although the licensee had intended to begin IST of the check valves which were installed as a result of the modifications, the licensee failed to include them in their current 4th interval IST Plan. Consequently, the ASME OM Code required testing of the check valves (1/2RN-1146, 1/2RN-1150) was not performed.

ECs 107089, 107090, 107430, and 107431 were implemented to address potential overpressure conditions of the Nuclear Service Water (RN) system during certain design basis occurrences. The EC changes included installation of a supplemental vent line on each train which included the 1/2RN-1146, 1/2RN-1150 check valves. The check valves in the newly installed lines open to prevent overpressure of the RN pump suction piping during events which include an actuation signal of the RN system and a postulated single failure which leads to a train of the RN pump suction being isolated from its normal vent path, either Lake Norman or the Standby Nuclear Service Water Pond. Loss of the pump suction piping structural integrity due to overpressure was not evaluated along with the events that cause the system actuation signal, so the modification was intended to prevent exceeding the Service Limits specified in the Design Specifications during those design basis events.

The licensees IST plan for the 4th interval, which began on March 1, 2014, identified the 2004 Edition through the 2006 Addenda of the ASME OM Code as the OM Code of record applying to the interval. In this edition of the OM Code, Subsection ISTA, General Requirements, paragraph ISTA-1100, Scope, states, in part, These requirements apply to

(a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident
(b) pressure relief devices that protect systems or portions of systems that perform one or more of these three functions." Since the check valves installed in the supplemental vent line are functioning as pressure relief devices protecting the RN pump suction piping, they were scoped into the IST program during EC development. The 2004 Edition of the ASME OM Code, paragraph ISTA-3110, further requires that Test plans shall be prepared for the preservice test period, initial inservice, and subsequent inservice test intervals.1 Each inservice test plan shall include the following: (c)identification of the components subject to tests and examination
(d) the Code requirements for each component and the test or examination to be performed
(e) the Code requirements for each component that are not being satisfied by the tests or examinations; and justification for substitute tests or examinations.

Test acceptance criteria drawing, MCTC-1574-RN.V054-01," Check Valves 1/2RN1146, 1/2RN1150, Testing and Acceptance Criteria, Units 1 & 2" was updated as a result of the licensees intent to include the check valves in their IST plan for performance of the required ASME OM Code testing. As an example, revision 1 of MCTC-1574-RN.V054-01, dated August 30, 2016, indicated

(1) that the check valve opening function was Provides Overpressure Protection and the check valve closing function was Prevent Reverse Flow Rate Through (gross diversion)and
(2) that the check valves were to be tested in accordance with the Subsection ISTC requirements of the ASME OM Code for each open and close function. However, following their installation in the supplemental vent lines, the check valves were not included in the current 4th IST Interval Plan, so their corresponding test requirements from Subsection ISTC of the OM Code were not identified or completed.

Corrective Actions: Upon the discovery that the check valves had not been tested as intended, the licensee generated nuclear condition report (NCR) 2503196 and assessed their capability to provide the intended overpressure protection function. The licensee concluded that the valve function was not expected to be lost. The licensee further began planning test procedures to perform the required IST of the affected check valves.

Corrective Action References: NCR 2503196

Performance Assessment:

Performance Deficiency: The licensees failure to identify components which were scoped into the IST program and their associated testing requirements in their IST interval testing plan in accordance with ASME OM Code, subsection ISTA, paragraph ISTA-3110 was a performance deficiency (PD).

Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, check valve degradation to the point of loss of function could go undetected absent the required testing being performed.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors used IMC 0609, Attachment 4, "Initial Characterization of Findings," and determined that the PD affected the Mitigating Systems cornerstone. Using IMC 0609, Appendix A, Exhibit 2, Mitigating Systems Screening Questions, section A, the screening questions were all answered as NO due to the PD not representing a loss of operability or PRA function; therefore, the inspectors determined the finding was of very low safety significance (Green).

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Violation: 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, requires in part that, Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the inservice test requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in paragraphs (f)(2) and

(3) of this section and that are incorporated by reference in paragraph (a)(1)(iv) of this section, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The current IST Program Code of Record for the McGuire Nuclear Station is the 2004 Edition through the 2006 Addenda of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a, which requires in Subsection ISTA, paragraph ISTA-3110, that, Test plans shall be prepared for the preservice test period, initial inservice, and subsequent inservice test intervals.1 Each inservice test plan shall include the following:(c) identification of the components subject to tests and examination
(d) the Code requirements for each component and the test or examination to be performed
(e) the Code requirements for each component that are not being satisfied by the tests or examinations; and justification for substitute tests or examinations.

Contrary to the above, since the check valves were installed in 2015 and 2016, the licensee failed to identify the components to be subsequently subjected to test and examination and did not include the Code requirements for each component in the inservice test plan. Specifically, the licensee did not include check valves 1/2RN-1146, 1/2RN-1150 in the IST 4th interval plan and identify their test and examination requirements. Consequently, the testing required in Subsection ISTC was not performed.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

  • On February 8, 2024, the inspectors presented the Comprehensive Engineering Team Inspection results to Mr. Brent Bare, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DPC-1381.05-00-

0018

Cutler-Hammer Relay Qualified Life Analysis

Rev. 0

DPC-1552.08-00-

0109

Safety Injection Flows for Safety Analysis

Rev. 27

EC0000106371

ONE LINE DIAGRAM 125VDC/120VAC VITAL INSTR AND

CONTROL PWR SYS

Rev. 46

MCC 1205.19-00-

0003

Electric Motor Operator Sizing Guidelines per GL89-10 for

Gate Valves

Rev. 55

MCC 1205.19-00-

0035

GL 89-10 Verification for MOV Group K, Borg Warner 3"

28 lb. Glass Gate Valve

Rev. 14

MCC 1205.19-00-

0101

Evaluation of MNS MOVs 1/2 NC-31,33,35 Using EPRI PPM

Rev. 0

MCC 1206.16-18-

26

Support Restraint Calculation for SAG Math Model RN-528-

Rev. 12

MCC-1201.06-00-

0007

Qualification of Residual Heat Removal Heat Exchanger

Partition Plate Design

03/11/1998

MCC-1211.00-17-

23-ICC-0015

Control Room and Control Room Heal Load Calculation

Rev. 0

MCC-1223.11-00-

21

ND Pump Miniflow Line Addition, Unit 1, Type II

Rev. 1

MCC-1223.11-00-

0035

ND Heat Exchanger Margin Post-LOCA with ECCS Sump

Recirculation

05/20/2008

MCC-1223.11-00-

0039

RHR System Capability Basis - UFSAR Support

01/23/2013

MCC-1223.12-00-

0030

Technical Input for Response to NRC Generic Letter 2008-

01: Managing Gas Accumulation in Emergency Core

Cooling, Decay Heat Removal, and Containment Spray

Systems

Rev. 8

MCC-1223.12-00-

0034

Calculation of Pipe Segment Volumes and Void Fractions

for Arc Lengths

Rev. 1

71111.21M

Calculations

MCC-1223.12-00-

0037

Evaluation of ND System Gas Accumulation

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCC-1227.00-00-

0094

Radiological Consequences of a Design Basis LOCA at

McGuire Nuclear Station

Rev. 19

MCC-1232.00-00-

0175

Maximum Allowable Containment Leakage Rate (La)

Rev. 2

MCC-1381.05-00-

230

U1/2 125VDC Vital I&C Power System (EPL) Voltage Drop

Analysis ( Priority E Calc)

Rev. 9

MCC-1381.05-00-

260

McGuire U1 ETAP DG Dynamic Analysis

Rev. 8

MCC-1381.05-00-

0301

U1_6.9KV_4.16KV_600V Aux Power Systems Short Circuit

Analysis

Rev. 8

MCC-1552.08-00-

0084

Long Term EQ Containment Temperature Response for

LOCA and SLB

10/22/2014

MCS 1205.00-00-

001

McGuire Nuclear Station Specification for Cast Stainless

Stell Gate, Globe, and Check Valves

Rev. 9

MCTC 1609-

KD.V001-01

Control Valves 1/2KD9 and 29. Testing and Acceptance

Criteria, Units 1&2

Rev. 3

PT/2/A/4204/001

B

2B ND Pump Performance Test

Rev. 57

PT/2/A/4204/004

C

2A and 2B Pump Head Curve Verification

Rev. 16

Corrective Action

Documents

NCRs

1613309, 2337888, 1339778, 1662173, 2428564, 2408408,

2417937, 2428564, 2441496, 2448744, 2451930, 2452007,

1618523, 1649096, 1674900, 1899547, 1901594, 2378576,

28151, 1533121, 1643533, 1661336, 1666804, 1685192,

1901452, 2012549, 2425450, 2461384, 2462369, 2464418,

2482758, 2488856, 2489684, 2489685, 2490407, 2500063,

01651047, 01903702, 01903743, 01903669, 02397398,

2399977

NCR 02502346

RHR System (ND) DBD identifies the incorrect system

temperature

01/24/2024

NCR 02503006

Omitted reference to Tech Spec 5.5.12 in 5EVAL AR

2404321.

01/30/2024

Corrective Action

Documents

Resulting from

Inspection

NCR 02503196

RN Suppl. Vent Line Check Valves 1/2RN-1146, 1150 Not

Tested as Required per IST

01/31/2024

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NCR 02503891

Cracks on Walls in the Stairwell AUX 733

2/06/2024

NCR 02504105

24 NRC CETI: 50.59 Product Quality Observations

2/07/2024

MC -1705-01.00

One Line Diagram 125 VDC/120VAC Vital Instr &

Cont Power Sys

Rev. 126

MC-1753-01.01

Connection Diagram Diesel Load Sequencing System,

Diesel Gen 1A Load SEQ PNL 1DGLSA Wiring Section

No.1

Rev. 38

MC-2414-04.41-

Piping Layout System - ND Plan Elevation 716'-0" Auxiliary

Building

Rev. 17

MC-2414-04.42-

Piping Layout System - ND Plan & Section Elev. 733+0

Auxiliary Building

Rev. 17

MC-2414-04.42-

Piping Layout System - ND Plan Elevation 733'-0" Auxiliary

Building

Rev. 25

MC-2414-04.42-

Piping Layout System - ND Section Elevation 733'-0"

Auxiliary Building

MC-2414-04.43-

Piping Layout System - ND Plan Elevation 750'-0" Auxiliary

Building

Rev. 9

MCCD-1700-

00.00

One Line Diagram Unit One Configuration Essential Power

System

Rev. 7

MCCD-1703-

06.00

One Line Diagram 6VAC Load Centers 1ELXA and 1ELXC

Rev. 4

MCFD 1553-

2.00

Flow Diagram of Reactor Coolant System (NC)

Rev. 10

MCFD-1571-

01.00

Flow Diagram Refueling Water System

Rev. 30

MCFD-1574-01.0

FLOW DIAGRAM OF NUCLEAR SERVICE WATER

SYSTEM (RN)

Rev. 40

MCFD-1574-

01.00

FLOW DIAGRAM OF NUCLEAR SERVICE WATER

SYSTEM - RN

Rev. 35

MCFD-1604-

2.00

FLOW DIAGRAM OF LOW-LEVEL INTAKE COOLING

WATER SYSTEM (RC)

Rev. 5

MCFD-2561-

01.00

Flow Diagram of Residual Heat Removal System

Rev. 29

Drawings

MCFD-2574-

FLOW DIAGRAM OF NUCLEAR SERVICE WATER

Rev. 44

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

01.01

SYSTEM (RN)

MCID-1499-

NV.31

Instrument Detail Charging Line Flow Control

Rev. 7

MCM 1205.00-

0478-001

Valve Assembly, Gate 3 Inch, 1528 lb. CRES with Motor

Oper., Sch 160

Rev. F

MCTC-1574-

RN.V054-01

CHECK VALVES 1/2RN1146, 1RN1150, TESTING AND

ACCEPTANCE CRITERIA, UNITS 1 & 2

Revs. 0 and

EC 107430

RN (1B) Suction Piping - Supplemental Vent Line

Rev. 10

EC 401581

Permanently Fail Valve, 2KD-9, Open. Remove and/or

Abandon in Place 2KDTT5260 and Associated Equipment.

Rev. 1

EC 416278

Add Train Related CA Instruments Physical Separation

Requirements to Instrument Details

Rev. 1

EC 417951

SSPS Semi-Automatic Tester Switches

Rev. 0

Engineering

Changes

EC413368

Interferences Associated With 2B2 KC Motor Replacement

Rev. 4

Engineering

Evaluations

EC 417951

1B SSPS PRINTED CIRCUIT BOARD REPLACEMENT

Rev. 3

Cutler-Hammer Manual

09/2016

205.19-0060.001

Valve Thrust Assessment Stem T-Head and Disc for Borg

Warner 3" 1528 Class Gate Valve

Rev. 0

22-MNS-024

UFSAR Change Summary Form

AR 5SCR

01347755

EC107430 & EC107431: Adding RN 1B & 2B Supplemental

Vent Lines

11/12/2014

DUKE-QAPD-001

Duke Energy Corporation Topical Report Quality Assurance

Program Description Operating Fleet

Amendment

EC 107430 Rev

OAC Implementation Package

05/02/2019

EQMM-1393.01-

E02-00

ENVIRONMENTAL QUALIFICATION MAINTENANCE

MANUAL EQUIPMENT TYPE: 600 VAC MOTOR

CONTROL, 125 VDC DISTRIBUTION CENTERS, 120

VAC/125 VDC POWER PANELBOARDS & REMOTE

MOTOR STARTERS MODEL/SERIES: 1035U CLASS

Rev. 17

MCLL-1703-03.01

1ELXA Load list

Rev. 6

Miscellaneous

MCM 1205.01-

0614.001

Design Specification for Gate, Globe, and Check Vlvs

Rev. 00G

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCM 1205.19-

0043.002

ROTORK Overthrust Testing for NAX Actuators

Rev. 0

MCM 1205.19-

0059.001

Borg Warner Motor Operator Valve Thermal Binding Test

Program

Rev. 1

MCM 1205.32-

0002.001

Thrust, Torque and Limiting Component Report: 3 Inch,

28 Class, Stainless Steel Motor Operated Gate Valves

10/14/1993

MCM 1218.02-

0034-001

RN SUCTION -SUPPLEMENTAL VENT LINE: ASME CODE

REVIEW

Rev. 0

MCM 1301.00-

0078.001

Nordberg Diesel Engine Instruction Manual

Rev. 21

MCM 1301.00-

0093.001

Model FS-1316-HSC Diesel Engine Auxiliary Bulletins

Rev. 57

MCM

1301.00.007.001

Diesel Generator Engine Parts Manual

Rev. 92

MCM 1314.01-

0341.010

Vital Panel Board Retrofit Qualification Report

Rev. 2

MCM 1399-08-

0192.001

SSPS Undervoltage Driver Board Technical Manual

Rev. 0

MCM 1399.03-

0537.028

Unit 1 & 2 NSSS Control Systems Upgrade FMEA

Rev. 1

MCM 1399.03-

0537.029

Unit 1 & 2 DCS NSSS Control Systems Upgrade Reliability

Analysis

Rev. 1

MCM 1399.08-

0159-001

Westinghouse SSPS Board Replacement Licensing

Summary Report

Rev. 0

MCS 1553.NC-

00-001

Design Basis Specification for the NC System

Rev. 40

MCS 1573.KC-

00-0001

Design Basis Specification for the KC System

Rev. 30

MCS-112.00-

EPE-0001

Design Basis Specification for the 600V Essential Auxiliary

Power System (EPE)

Rev. 14

MCS-114.00-

EQB-0001

Design Basis Specification for the EQB System

Rev. 19

MCS-1390.01-00-

26

Wire Termination Installation, Labeling, and Termination

Rev. 19

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MCS-1554.NV-

00-0001

Design Basis Specification for the NV System

Rev. 44

MCS-1561.ND-

00-0001

Design Basis Specification for the ND System

Rev. 30

MCS-1567.WG-

00-0001

Design Basis Specification for the WG System

Rev. 014

MCS-1574.RN-

00-0001

DESIGN BASIS SPECIFICATION FOR THE RN SYSTEM

Rev. 64

MCTC-1561-

ND.P001-01

ND Pumps 1/2 A and B, Testing and Acceptance Criteria,

Units 1 & 2

Rev. 3

MCTC-1561-

ND.S001-01

ND Flow Balance

Rev. 2

MCTC-1561-

ND.S003-01

ND System High Point Allowable Gas Volumes, Testing and

Acceptance Criteria, Units 1 & 2

Rev. 0

MCTC-1561-

ND.S003-02

ND System High Point Allowable Gas Volumes, Testing and

Acceptance Criteria, Units 1 & 2

Rev. 0

MCTC-1561-

ND.S003-03

ND System High Point Allowable Gas Volumes, Testing and

Acceptance Criteria, Units 1 & 2

Rev. 0

OP-MC-EL-EP

Main Power Distribution (EP)

Rev. 52

OP-MC-EL-EPL

25 VDC (EPL) and 120 VAC (EPG) VITAL I & C POWER

Rev. 27E

OP-MC-PS-ILE

Operations Training: Pressurizer Level Control (ILE)

OP-MC-PS-NV

Operations Training: Chemical and Volume Control (NV)

System Health

Report Unit 2 ND

System

Q4-2023

01/03/2024

Unit 2 ND System

ECCS Venting

Challenges

Engineering Recommendation Form

10/25/2023

WNA-TR-05160-

DAP

Upgrade Factory Acceptance Test Report Phase 4

Rev. 0

AD-EG-ALL-1103

Procurement Engineering Products

Rev. 7

AD-EG-ALL-1132

Preparation and Control of Engineering Changes

Rev. 26

AD-EG-ALL-1137

Engineering Change Product Selection

Rev. 12

Procedures

AD-EG-ALL-1155

Post Modification Testing

Rev. 6

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-EG-ALL-1157

Engineering of Plant Digital Systems and Components

Rev. 6

AD-EG-ALL-1214

Condition Monitoring of Structures

Rev. 1

AD-LS-ALL-0008

CFR 50.59 Review Process

Rev. 5

AD-MN-ALL-0005

Nuclear Planning

Rev. 24

AD-OP-ALL-0105

Operability Determinations

Rev. 7

AD-OP-MNS-

205

MNS Time Critical Actions (TCA) and Time Sensitive

Actions (TSA)

Rev. 002

AD-PI-ALL-0100

Corrective Action Program

Rev. 29

AP-1-A-5500-10

NC System Leakage Within the Capacity of Both NV Pumps

Rev. 29

AP/1/A/5500/07

Loss of Electrical Power

Rev. 46

AP/1/A/5500/12

Loss of Letdown, Charging or Seal Injection

Rev. 26

EP-1-A-5000-E-3

Steam Generator Tube Rupture

Rev. 29

EP/1/A/5000/E-0

Reactor Trip or Safety Injection

Rev. 38

IP-0-A-3066-002

D

Rotork Actuator Preventive Maintenance

Rev. 47

IP-0-A-3066-002

N

Rotork Actuator Lubrication and Inspection

Rev. 19

IP-0-A-3066-013

H

Testing Motor Operated Gate Diaphragm or Non-Kerostest

Globe Valves Using Teledyne Quicklook System

Rev. 3

IP-0-A-3190-012

NAMCO Limit Switch Preventive and Corrective

Maintenance

Rev. 45

IP-0-A-3219-003

Setting Stem-Mounted Limit Switches

Rev. 17

IP/1/A/3250/012 A

Diesel Load Sequencer 1A Timer Calibration

Rev.10

MC-2NDHX0004

2B Residual Heat Removal Heat Exchanger Tube Layout

and Plugging Record

Rev. 0

MCM 3.6

Closed Cooling Systems Analytical Requirements and

Corrective Actions

Rev. 044

MCS-1201.6-1

Auxiliary Building Heat Exchangers

11/02/1988

MP/0/A/7650/002

Vertical U-Tube Heat Exchanger Corrective Maintenance

Rev. 006

NSD 408

Testing

Rev. 20

NSD-408

Testing

Rev. 20

OP-1-A-6100-003

Operation of the PZR PORV Isolation Valves

Rev. 236

OP/1/A/6100/010

ANNUNCIATOR RESPONSE FOR PANEL 1AD-12

Rev. 57

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

M

OP/2/A/6200/004

Residual Heat Removal System

Rev. 103

OP/2/A/6200/004

Residual Heat Removal System

Rev. 102

PT-1-A-4150-001

D

Identifying NC System Leakage

Rev. 18

PT-1-A-4151-002

NC Train A Valve Stoke Timing - Quarterly

Rev. 24

PT-1-A-4151-002

B

NC Train B Valve Stoke Timing - Quarterly

Rev. 27

PT/0/A/4200/018

Ice Bed Analysis

03/06/2023

PT/1/A/4200/001

J

Unit 1 Containment Leakage

11/07/2023

PT/1/A/4200/009

A

Engineered Safety Features Actuation Periodic Text Train A

09/17/2023

PT/1/A/4350/003

A

Electrical Power Source Alignment Verification

Rev. 31

PT/2/A/4200/017

A

NV to Cold Legs Flow Balance

Rev. 12

PT/2/A/4200/017

B

NI to Cold Legs Flow Balance

Rev. 8

PT/2/A/4200/019

ECCS Pumps and Piping Vent

Rev. 80

PT/2/A/4204/016

2ND-35 Seat Leakage Test

Revs. 4 and

RP/0/A/5700/007

Earthquake

Rev. 32

TT/I/A/9100/647

1B RN Post Mod Testing for EC 107430

Rev. 0,

completed

03/29/2016

WPM-501

WORK PROCESS MANUAL

Rev. 15

Work Orders

WOs

2137477, 02137478, 02137479, 20403155, 20422172,

20428100, 20431155, 20438096, 20447254, 20456082,

20464425, 20472509, 20477301, 20483316, 20491537,

20499511, 20508129, 20518268, 20526069, 20533969,

20541153, 20550514, 20550514, 20559128, 20566723,

20574679, 20575235, 20582820, 20591853, 20597604,

20607124, 20615994, 20623184, 20464673, 20538434,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20542088, 20628747, 20359201, 20623536, 20367003,

207257-03, 20447448-10, 20447448-11, 20447448-12,

20477017-10, 20477017-11, 20366502, 20447448-13,

20574986-02, 20477130-01, 02201097-26

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