IR 05000298/2021010

Design Basis Assurance Inspection (Teams) Inspection Report 05000298/2021010

ML21140A206
Person / Time
Site:	Cooper
Issue date:	06/07/2021
From:	David Proulx NRC Region 4
To:	Dent J Nebraska Public Power District (NPPD)
References
IR 2021010
Download: ML21140A206 (19)

Text

June 7, 2021

SUBJECT:

COOPER NUCLEAR STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000298/2021010

Dear Mr. Dent:

On April 23, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On May 6, 2021, 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.

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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Cooper Nuclear Station.

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

J. Dent, Jr.

Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, David Proulx, Acting Chief Engineering Branch 1 Division of Reactor Safety

Docket No. 05000298 License No. DPR-46

Enclosure:

As stated

Inspection Report

Docket Number:

05000298

License Number:

DPR-46

Report Number:

05000298/2021010

Licensee:

Nebraska Public Power District

Facility:

Cooper Nuclear Station

Location:

Brownville, NE

Inspection Dates:

March 08, 2021 to April 23, 2021

Inspectors:

L. Flores, Senior Reactor Inspector

N. Okonkwo, Reactor Inspector

D. Reinert, Reactor Inspector

W. Sifre, Senior Reactor Inspector

F. Thomas, Reactor Inspector

Approved By:

David Proulx, Acting Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Cooper 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

Preconditioning of 4160 Vac Circuit Breaker for As-Found Tests Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000298/2021010-01 Open/Closed None (NPP)71111.21M The team identified a Green non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XI, Test Control, involving the licensees failure to establish a test program which demonstrates that components will perform satisfactorily in service. Specifically, the licensee failed to record as-found test values prior to performing maintenance for safety related 4160 Vac magne blast circuit breakers.

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 - Design Bases Assurance Inspection (Teams)

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (2 Samples)

(1) HPCI Steam Supply to Turbine Valve HPCI-MOV-MO14

• Valve Testing Procedures and performance history to assure consistency with vendor and industry recommendations.

• Component maintenance history and corrective action reports to verify the monitoring of potential degradation.

• Design basis documents and calculations including maximum expected differential pressure, minimum required stem thrust, limiting component analysis to verify valve and actuator functionality is within acceptable limits.

• Change equivalent document 6017820, HPCI-MOV-MO14 valve replacement, including changes in valve opening times to verify within design basis.

• Vendor specifications for replacement valve and valve and actuator drawings.

(2)125V DC Charger 1B:

• Battery short circuit calculations, sizing calculations, coordination studies, voltage drop calculations, and switchgear maintenance activities were appropriate for the design of the system.

• Design basis documents

• Current system health reports

• Selected drawings

• Vendor manual and installation specifications.

• Condition Reports associated with the 125V DC 1B Charger.

• Component maintenance history and corrective action program reports.

• Preventive maintenance, inspection, and testing procedures for Class 1E 125 VDC System components.

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===

(1) RHR Heat Exchanger Service Water Discharge Valve SW-MOV-89B

• Valve testing procedures and performance history were reviewed to assure consistency with vendor and industry recommendations.

• Component maintenance history and corrective action program reports to verify the monitoring of potential degradation.

• Design basis calculations including the maximum expected differential pressure, minimum required stem thrust, limiting component analysis to verify that the valve and actuator functional capability remained within acceptable limits.

• Valve and actuator drawings and vendor specifications.

• Setpoints and instrument calibration procedures for the valve and associated instrumentation.

(2)125 Volts Direct Current (VDC) Bus 1B:

• Battery short circuit calculations, sizing calculations, coordination studies, voltage drop calculations, and switchgear maintenance activities were appropriate for the design of the system.

• Input and output operating voltage characteristics to verify the 125V DC Bus 1B and downstream components can perform their design function through all input voltage ranges.

• Design basis documents

• Current system health reports

• Selected drawings

• Vendor manual and installation specifications

• Condition Reports associated with the 125V DC 1B Bus

• Component maintenance history and corrective action program reports.

• Preventive maintenance, inspection, and testing procedures for Class 1E 125V DC System components.

(3)4160 Switchgear G & Load Center G (4160V)

• System health reports, component maintenance history, and corrective action program reports to verify the monitoring and correction of potential degradation.

• Calculations for electrical distribution, system load flow/voltage drop, short-circuit, and electrical protection to verify that bus capacity and voltages remained within the minimum acceptable limits.

• The protective device settings and feeder circuit breaker ratings to ensure adequate selective protection coordination of connected equipment during worst-case short circuit conditions.

• Procedures for preventive maintenance, inspection, and testing to compare maintenance practices against industry and vendor guidance; including the cable aging management program.

• Results of completed preventative maintenance on switchgear and breakers, including breaker tracking.

• Switchgear loading study during normal plant operation and Design Basis Accident (DBA) load conditions.

(4) Transformer G (4160/480V)

• System health reports, component maintenance history, and corrective action program reports to verify the monitoring and correction of potential degradation.

• Calculations for transformer sizing and loading to ensure capacity, transformer cabling, and protection to verify that transformer nameplate capacity and voltages remained within minimum acceptable limits.

• The protective device settings and circuit breaker ratings to ensure adequate selective protection coordination of connected equipment during worst-case short circuit conditions.

• Procedures for preventive maintenance, inspection, and testing to compare maintenance practices against industry and vendor guidance.

• Results of completed preventative maintenance on the transformer to ensure data acceptability are within tolerance.

• Seismic qualification reports for the transformer to ensure SSC will respond to seismic event.

• Vendor document and data for the transformer to ensure design and operations requirement.

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) Design Equivalent Change 5223334, Replacement of the CRD A Pump

(2) Change Evaluation Document 6030460, Reactor Recirculation Pump Impeller Replacements

(3) Engineering Change 4899459, 1200Amp, 4160Volt Vacuum Bottle Circuit Breaker Replacement

(4) Design Equivalent Change 6040920, Emergency Station Service Transformer (ESST)

Bus Replacement.

(5) Change Evaluation Document 6016581, Diesel Generator Voltage Regulator Upgrade

(6) Design Evaluation Change 5248627 - High Pressure Core Injection REL-K45 Relay Replacement

Review of Operating Experience Issues (IP Section 02.06) (3 Samples)

(1) OE LO-2018-0047, In Vessel Visual Inspections (IWI) at several BWRs have discovered instances of degradation on feedwater sparger end brackets.

(2) OE - LO 2018-0047-004, GE-SC-18-05 - R0 - GGN Power Supply DA343A1281P002 Derating Depends on Baseplate Temperature.

(3) OE - LO-2020-0047-018, IRIS# 468726 - Torus T-quencher damage due to prolonged SRV leak

INSPECTION RESULTS

Preconditioning of 4160 Vac Circuit Breaker for As-Found Tests Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems

Green NCV 05000298/2021010-01 Open/Closed

None (NPP)71111.21M The team identified a Green non-cited violation of 10 CFR 50, Appendix B, Criterion XI, Test Control, involving the licensees failure to establish a test program which demonstrates that components will perform satisfactorily in service. Specifically, the licensee failed to record as-found test values prior to performing maintenance for safety related 4160 Vac magne blast circuit breakers.

Description:

The team reviewed preventive maintenance procedures for 4160 Vac magne blast circuit breakers and several work orders that performed the preventive maintenance.

During the review, the team identified that Maintenance Procedure 7.3.17.1 4160 Breaker Examination, Revision 30 used to perform inspection of GE Magne Blast Circuit Breakers, directed maintenance personnel to cycle breaker 20 times, clean, adjust, and manipulate the physical condition of 4160 Vac circuit breaker contacts, insulators, and other critical circuit breaker components before performing an as-found test to determine if the circuit breakers would have performed their intended design function.

For example, Maintenance Procedure 7.3.17.1 4160 Breaker Examination, section 3.34.2 directs the maintenance to check resistance of normally closed (NC) contacts for control relay. Record AS FOUND NC values on Attachment 1, Table 2. In addition, section 3.36.2 directs the maintenance personnel to check resistance of each main contact and record the value on Attachment 1, Table 3. Prior to performing these steps, the procedure had directed maintenance personnel to cycle the breaker 20 times in step 3.20.8.8, cleaned primary disconnect fingers, movable and stationary primary contacts, and secondary disconnects with approved solvent in step 3.21, manipulated and lubricated the main and arcing contacts in steps 3.23 thru 3.28. The cycling, cleaning, lubrication and manipulations of the breaker were completed before any as-found tests and reading are performed in steps 3.34.2 and 3.36.2, to verify the operability of the critical components of the circuit breaker, such as main contact resistance, main contact and control relay contact resistance.

The team reviewed the data sheets resulting from the February 7, 2013, and August 21, 2019, tests and preventative maintenance performed on 4160 Vac circuit breaker 4160G 1GS, under work order 4846461 & 5167080, respectively, using Procedure 7.3.17.1. Those results show that maintenance personnel documented the same results for as-found and as-left for multiple tested parameters. Therefore, the team determined that the procedure could mask existing conditions such as unacceptable contact resistance, setpoint drift, and mechanical binding. Additionally, the procedure resulted in the inability to verify past operability of circuit breaker 4160G 1GS.

Corrective Actions: The licensee reviewed test results to validate operability. The licensee is also reviewing the associated procedures to update the testing process.

Corrective Action References: CR-CNS-2021-02009

Performance Assessment:

Performance Deficiency: The failure to establish a test program which ensures that test and maintenance procedures associated with safety-related 4160 Vac circuit breakers would perform satisfactorily in service was a performance deficiency.

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, the failure to perform as-found tests prior to performing maintenance in preventive maintenance procedures was a significant programmatic deficiency which could cause unacceptable conditions to go undetected.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, issued November 30, 2020, the inspectors determined this finding is not a deficiency affecting the design or qualification of a mitigating structure, system, or component; the finding does not represent a loss of function of a Technical Specification train, system, or two separate Technical Specification systems for greater than their Technical Specification allowed outage time; the finding does not represent a loss of system and/or function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and the finding does not represent an actual loss of function of one or more non-Technical Specification trains of equipment designated as risk-significant in accordance with the licensees maintenance rule program.

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: Title 10 CFR 50, Appendix B, Criterion XI, Test Control, requires, in part, A test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.

Contrary to the above, the licensee failed to establish a test program that assured that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service was identified and performed in accordance with written test procedures which incorporated the requirements and acceptance limits contained in applicable design documents. Specifically, prior to April 5, 2021, the licensees preventive Maintenance Procedure 7.3.17.1, 4160 Breaker Examination, failed to assure that the 4160 Vac circuit breakers would perform satisfactorily in service when the licensee performed maintenance prior to completing as-found tests to verify past operability of the circuit breakers.

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 May 6, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to John Dent, Jr. and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations91-255

Review of Advent LCA Calculation 96007TR-16, Rev. 2 for

SW-MOV-89A and SW-MOV-89B

NEDC 00-003

CNS AUX. Power System Load Flow and Voltage Analysis

NEDC 00-110

MOV Program Valve Margin Determination

NEDC 00-111

CNS Auxiliary Power System AC Loads

3C6

NEDC 13-040

CRD Supply to RR Pump A Pipe Stress Analysis

NEDC 13-041

Owner Accepted Review of Zachary Calc 13-239 CRD

Supply to RR Pump B Pipe Stress Analysis

NEDC 86-105C

CNS DC Short Circuit Study

NEDC 86-105D

CNS Critical DC Bus Coordination Study

NEDC 87-131D

25 VDC Division II Load and Voltage Study

NEDC 87-221

25 Volt Battery Racks and Battery Charger Mounting

Calculations

01/17/2017

NEDC 89-149

Class IIN Main Steam Piping Analysis Problem MS-02

8C2

NEDC 90-028

Review of Seismic Qualification of GE Relay Panels in Aux.

[Auxiliary] Relay Room

06/26/2014

NEDC 91-078

System Level Design Basis Review of HPCI Program MOVs

NEDC 91-088C

Review of ADVRNT Calc 96007TR-3 Rev. 3; Limiting

Component Analysis for HPCI-MOV-MO14

NEDC 91-176

Review of EGS Calculation 0955-3.2.1, "DC System High

Voltage"

NEDC 91-185

MOV Thermal Overload Heater Sizing

NEDC 92-024

Reactor Water Level 2 (Low-Low) Set Point Calculation for

NBI-LIS-72A, B, C, D (Sw. 3 & 4)

NEDC 92-050D

Reactor Low Pressure, Injection Valve Permissive Setpoint

Calculation for NBI-PIS-52B (S2) and NBI-PIS-52D (S2)

NEDC 93-184

RHR Heat Exchangers Thermal Performance and Tube

Plugging Margin

NEDC 95-003

Determination of Allowable Operating Parameters for CNS

MOV Program MOVs

NEDC 95-003

Determination of Allowable Operating Parameters for CNS

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MOV Program MOVs

NEDC 96-018

Design Specification for Valve Limiting Component Analysis

NEDC 96-018

Design Specification for Valve Limiting Component Analysis

NEDC 96-039

DC Powered Motor Operated Valve Stroke Time and

Capability Calculation

3C1

Corrective Action

Documents

2015-05401, 2014-06711, 2016-04225, 2017-03656, 2014-

04547, 2018-06339, 2018-06417, 2005-00675, 2005-00674,

2005-00676, 2005-00678, 2005-00680, 2005-00703, 2009-

07839, 2013-00847, 2019-04407, 2013-00850, 2004-07938,

2017-05129, 2021-01893, 2016-00778, 2021-01973, 2020-

279, 2020-03340, 2021-00046, 2016-01478, 2016-05162,

2016-07365, 2017-01350, 2017-01759, 2017-02399, 2017-

04580, 2018-00048, 2018-00864, 2018-02055, 2018-05717,

2018-06096, 2019-00455, 2019-02395, 2019-04865, 2019-

06563, 2021-00636, 2021-01258, 2018-01248, 2018 -02135,

2012-06426, 2013-00116, 2013-00117, 2014-06968, 2020-

01667, 2018-07107, 2014-07965, 2015-00772, 2015-03279,

2015-03353, 2015-03370, 2015-03949, 2016-02566, 2016-

276, 2016-07380, 2016-07395, 2017-03567, 2019-01773,

2016-07388, 2016-06128, 2016-07387

Corrective Action

Documents

Resulting from

Inspection

21-01762, 2021- 01785, 2021-01269, 2021-02002, 2021-

2013, 2021-01930, 2021-01964, 2021-02008, 2021-02009,

21-02010

Drawings

0168R0288

HDO Metal Clad Switchgear

23R0558, Sh.

18G

Power and Control Circuit line up 03 Unit 6 1GB - Bus 1

AG/18

0l33C8689

Horizontal Draw out M/C Swgr, Device & Harness

Identification

2036

Isometric Key Service Water Reactor Building

2851-4

Service Water - Reactor Building

N18

3002, sh. 1

Auxiliary One Line Diagram, MCC Z, Swgr Bus 1A, 1B, IE

and Critical Swgr. Bus 1F 1G

AM/60

3012

Main Three Line Diagram, Sheet #3

AH/27

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

3058

DC One Line Diagram

10/15/2016

444125599

Anchorage modification for Auxiliary Relay room Panels 9-

30, 9-32, 9-33, 9-39, 9-41, 9-42, 9-45 (MP-96-083B)

NO1

444125599

Anchorage Modifications for Auxiliary Relay Room Panels 9-

30, 9-32, 9-33, 9-39, 9-41, 9-42, and 9-45 (MP 96-0838)

06/24/1997

450005685

Recirculation Pump P&ID

451213802

480 VOLT Critical Switchgear Bus "1 G" Anchorage

AB/01

2006490

Engineered Safeguard Subsystem Relay Cabinet Panel 9-33 01/07/2020

2006639

RCIC Relay Cabinet

AC/04

454003886

(3912)

Main Three Line Diagram Sheet #3

AH/27

454006581

Elementary Diagram RCIC System

10/14/20

5759-D001, sh. 1

5kV 2000A 3P 3W BUS Replacement Layout

5759-D001, sh. 2

5kV 2000A 3P 3W BUS Replacement Layout

5759-D060, sh. 1

2000A BUS Support Assembly Detail

5759-D061, sh. 1

2000A BUS Support Assembly Detail

5759-D070, sh. 1

5kV 2000A 3P 3W Special Assembly

5759-D071, sh. 1

5kV 2000A 3P 3W Special Assembly

5759-D998, sh. 1

Heater Assembly

5759-D999, sh. 1

5KV 2000A 3P 3W Heater Schematic Details

CNS-EE-208

DB-50 Modifications Details

N00

CNS-EE-209

DB-25 Modification Details

N00

CNS-EE-329

Connection Wiring Diagram Panel EE-M-BUSHEA

Engineering

Changes

CED 6016581

DG [Diesel Generator] Voltage Regulator Upgrade

08/18/2020

CED 6017820

HPCI MOV-14 Valve Replacement

CED 6030460

Reactor Recirculation Pump Impeller Replacements

DC 6040760

HPCI-PS-106 Setpoint Correction

DC 90-181

Modification of DC Westinghouse DB Breakers

03/25/1991

DEC-5169220

Changes to SW-P {MM 2112205) During Repair,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Refurbishment and Reverse Engineering Via PO

4500203150

DEC-5223334

Replacement of CRD-P-A

DEC-5248627

HPCI-REL-K45 Replacement

DEC-6040920

Emergency Station Service Transformer (ESST) Bus

Replacement

EC 4899459

200A, 4160V Vacuum Bottle Circuit Breaker Replacement

ECR-

11360575.EC- 5183056

Reverse Engineering of Top Shaft for SW-P

Engineering

Evaluations

2-057

Implementation of JOG Valve Factors at CNS

EC Q-11539060

Evaluation if the Safety Classification of HPCI-MO14 Gland

EE 12-057

Engineering Evaluation, Implementation of JOG Valve

Factors at CNS

NUC2020135

Cooper Nuclear Station Refueling Outage RE 31 October

20 Reactor Torus Desludging, IWE/IWF Examination,

Coating Inspection and Coating Repair

01/06/2021

Miscellaneous

25286

Seismic Walkdown Guidance For Resolution of Fukushima

Near-Term Task Force Recommendation 2.3: Seismic

05/2012

2014-022

USAR Change Request for HPCI MOV14 Stroke Time

21A1064AL

GE Purchase Specification for Cooper Recirculation Pumps

EE-Swgr.-4160F0

0Screening Evaluation Worksheet (SEWS) for 4160 Swgr. F

Seismic evaluation

GE-NE-L12-

00867-07-01

Cooper Nuclear Station MIG Project Task Report

GEK-9688

Cooper Operation and Maintenance Instructions High

Pressure Coolant Injection System

09/1986

IEEE Std C37.23

IEEE Standard for Metal-Enclosed Bus

9/11/2003

LO 2018-0047-

003

Written Evaluation for GEH-SIL-658 - Feedwater Sparger

End Bracket Degradation.

07/05/2018

LO 2018-0047-

004

Written Evaluation for GE-SC-18-05 - R0 - GGN Power

Supply DA343A1281P002 Derating Depends on Baseplate

Temperature..

09/26/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MI-182

Maintenance & Installation Manual, Crane Nuclear Vendor

Manual

NQ 8508

Refurbishment/Repair: ASSY.28in. 28KXL 1 Stage Type

VCT-Pump Consists of Bowl Assembly, Bottom Column,

Lower Column, Intermediate Column, Top Column and

Discharge Head

04/23/2018

TR-109641

EPRI Guidance on Routine Preventive Maintenance for

Magne-Blast Circuit Breakers Supplement to NP-7410-V2P2

10/1998

TR-112814

EPRI Reduced Control Voltage Testing of Breakers

7/1999

VM-0009

CNS Vendor Manual Byron Jackson Pump Division Reactor

Recirculating Pumps

VM-0230

Vendor manual 480 VOLT Unit Substation, Switchgear &

Low Voltage Circuit Breakers

VM-0230

Cooper Nuclear Station Vendor Manual, Westinghouse

Electric Corp, 480 Volt Unit Substation, Switchgear & Low

Voltage Circuit Breakers

VM-0233

Vendor Manual for GE 4160V Metal Clad Switchgear

7/26/2019

VM-1026

Cooper Nuclear Station, Vendor Manual, Nutherm

International, Inc., Nutherm DC Motor Starters

VM-1750

Cooper Nuclear Station Vendor Manual, General Electric,

GE Relay Composite Manual

Procedures

3.9

ASME OM Code Testing of Pumps and Valves

CNS OE 100

Regulatory Affairs & Compliance - Performance

0-CNS-LI-108-01

10CFR21 Evaluation and Reporting

0-PWG-01

Procedure Writers guide

0.31

Equipment Status Control

0.5 OPS

Operations Review of Condition Reports/Operability

Determination

14.24.1

HIGH PRESSURE COOLANT INJECTION SYSTEM

INSTRUMENT CALIBRATION

14.28.1

Service Water System Instrument Calibration

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

14.34.1

Reactor Equipment Cooling System Instrument Calibration

2.1.11.2

Reactor Building Data

2.1.12

Control Room Data

140

2.2.18.1

System Operating Procedure 4160V Auxiliary Power

Distribution System

2.2.18.2

System Operating Procedure, 4160V Breaker Operations

2.2.18.3. DIV2

System Operating Procedure 4160V DIV 2 Distribution

Support.

2.2.18.4

System Operating Procedure 4160V Distribution Abnormal

Power

2.2.18.4

System Operating Procedure 4160V Distribution Abnormal

Power

2.2.68

Reactor Recirculation System

2.2.68.1

Reactor Recirculation Systems Operations

2.2.69.3

RHR Suppression Pool Cooling and Containment Spray

2.2.70

RHR Service Water Booster Pump System

2.2.90A

2.5 KV System Component Checklist

2.2.90A

2.5 KV System Component Checklist

2.2A.RR.DIV1

Reactor Recirculation System Component Checklist (Div 1)

2.2A.RR.DIV2

Reactor Recirculation System Component Checklist (Div 2)

2.3_9-4-3

Alarm Procedure 2.3_9-4-3

3-EN-DC-115

Engineering Change Process

15C15

3-EN-DC-203

Maintenance Rule Program

4C0

3-EN-DC-204

Maintenance Rule Scope and Basis

4C0

3.33

Motor Operated Valve Program

6.2SW.101

SERVICE WATER SURVEILLANCE OPERATION (DIV 2)

(IST)

6.2SWBP.101

RHR Service Water Booster Pump Flow Test and Valve

Operability Test (Div 2)

6.HPCI.103

HPCI IST and 92 Day Test Mode Surveillance Operation

6.HPCI.201

HPCI Valve Operability Test (IST)

6.HPCI.313

HPCI Beginning of Cycle Test

6.MISC.401

Position Indicator Inservice Testing

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

6.SWBP.201

SW-MO-89A/B Full Stroke Operability (IST)

7.0.5

CNS Post-Maintenance Testing

7.2.5.1

Reactor Recirculation Pump Seal Cartridge Removal and

Installation

7.3.17

4160V BREAKER MAINTENANCE

7.3.17

4160V BREAKER MAINTENANCE

7.3.17

4160V Breaker Maintenance

7.3.17

4160V Breaker Maintenance

7.3.17.1

4160 Breaker Examination

7.3.17.1

4160 Breaker Examination

7.3.17.1

Maintenance Procedure, 4160 Breaker Examination

7.3.17.1

4160 BREAKER EXAMINATION

7.3.17.1

4160 BREAKER EXAMINATION

7.3.17.4

4160V Vacuum Bottle Breaker Maintenance

7.3.2.2

Westinghouse DB-25 Breakers Testing and Maintenance

7.3.20.1

Reactor Recirculation Pump Motor and MG Set Insulation

Testing

7.3.20.3

Motor Analysis

7.3.40

Inspection and Meggering of 4160 Volt Buses

7.3.40.1

Maintenance Procedure Inspection and Meggering of 480

Volt Buses

7.3.41

Examination, Repair, and High Pot Testing of Non-

Segregated Buses and Associated Equipment.

7.3.44

Transformer Turns Ration Testing

7.3.50.3

SW 89A/B Minimum Flow Adjustment

7.5.16

HPCI-MO-14 Dynamic Test

7.5.3

MOV Diagnostics

7.7.3.1

General Welding Standards for ASME and ANSI Code

Applications

EN-OP-104

Operability Determination Process

IP-ENG-001

Standard Design Process

N/A

CNS Vessel Internals Program

20.9

o-EN-WM-107

Post-Maintenance Testing

06/21/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SP 14-001

Reactor Recirculation Pump Motor Uncoupled Operation

06/20/2018

Work Orders

4744415, 4744498, 4748510, 4748513, 4748688, 4753046,

4762192, 4801684, 4801687, 4819708, 4819715, 4849331,

4910881, 4910944, 4916903, 4941728, 4943635, 4944401,

5012044, 5012045, 5012848, 5029171, 5029388, 5050159,

5066017, 5066080, 5145274, 5155539, 5166045, 5167942,

5172357, 5172377, 5193722, 5207435, 5207438, 5207594,

239148, 5248626, 5242316, 5278402, 5285077, 5285646,

291652, 5182630, 5122010, 5337256, 5057949, 5090650,

5049906, 5201058, 5285304, 5284540, 5211045, 5211550,

270579, 5284566, 5242443, 5211639, 5269841, 5210723,

5155031, 5062935, 5084375, 5062936, 5053598, 5089601,

4709109, 4821940, 4821941, 4840958, 4840959, 4952148,

5062934, 4821799, 4840957, 5041265, 5218034, 5178903,

218035, 5292501, 5039797, 5167081, 5172315, 5169417,

5302551, 5210306, 5207503, 5281974, 5283020, 5302550,

4362745, 4949062, 5167080, 4846461