IR 05000324/2021011

Design Basis Assurance Inspection (Programs) Inspection Report 05000324/2021011 and 05000325/2021011

ML21154A045
Person / Time
Site:	Brunswick
Issue date:	06/02/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Krakuszeski J Duke Energy Progress
References
IR 2021011
Download: ML21154A045 (25)

Text

June 2, 2021

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000324/2021011 AND 05000325/2021011

Dear Mr. Krakuszeski:

On April 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant, Units 1 & 2. On May 27, 2021, the NRC inspectors discussed the results of this inspection with Mr. Jay Ratliff, Plant General 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,

/RA/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000324 and 05000325

License Numbers:

DPR-62 and DPR-71

Report Numbers:

05000324/2021011 and 05000325/2021011

Licensee:

Duke Energy Progress, LLC

Facility:

Brunswick Steam Electric Plant, Units 1 & 2

Location:

Southport, NC

Inspection Dates:

April 12, 2021 to April 30, 2021

Inspectors:

M. Greenleaf, Reactor Inspector

N. Hansing, Materials Engineer

G. Ottenberg, Senior 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 design basis assurance inspection (programs) inspection at Brunswick Steam Electric Plant, 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

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

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000325,05000324/20 21011-01 Potential Inappropriate 10 CFR 50, Appendix J, Type C Test Exclusion 71111.21N.02 Open

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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a. Evaluated whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.

c. Evaluated whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

(1)1-E41-F006, High Pressure Coolant Injection (HPCI) Injection Valve (2)2-E41-F001, HPCI Turbine Steam Supply Valve (3)2-B21-F022A, Inboard Main Steam Isolation Valve 'A' (4)1-E11-F007B, Residual Heat Removal (RHR) Minimum Flow Bypass Valve to Suppression Pool (5)2-E11-F048A, RHR Heat Exchanger '2A' Bypass Valve (6)2-E11-F020B, RHR Pump '2B' & '2D' Suppression Pool Suction Valve (7)1-C41-F004A & B, Standby Liquid Control Explosive Squib Valves (8)1-G31-F001, Reactor Water Cleanup Inlet Line Inboard Isolation Valve (9)1-G16-F020, Drywell Equipment Drain Outboard Isolation Valve

INSPECTION RESULTS

Unresolved Item (Open)

Potential Inappropriate 10 CFR 50, Appendix J, Type C Test Exclusion URI 05000325,05000324/2021011-01 71111.21 N.02

Description:

An unresolved item (URI) was identified related to the licensee's exclusion of the HPCI injection valves, 1(2)-E41-F006, from local leak rate testing. Engineering Change (EC)417109, Evaluation of Penetrations and Valves Eligible for Appendix J Local Leak Rate Testing Exclusion, dated March 2, 2020, evaluated Brunswicks Appendix J program to determine if the exclusion criteria contained in NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J, revision 3A, could be applied such that certain valves may be excluded from 10 CFR 50, Appendix J, Type C testing. Among the valves excluded by the EC were the HPCI injection valves, 1(2)-E41-F006, which constitute a portion of the outboard isolation boundary for primary containment penetrations X-9A. The licensees technical basis for the valves' removal from the Appendix J test program requirements was located in a vendor report, Local Leak Rate Testing Scope Reduction for HPCI, RCIC, RHR, RCR, CS, RWCU, RCC and RNA Systems Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program Brunswick Steam Electric Plant, Units 1 and 2, revision 2. Upon review of the vendors report, the inspectors were uncertain that the conclusion that 1(2)-E41-F006 are primary containment boundaries that DO NOT constitute primary containment atmospheric pathways during and following a DBA was technically supported.

Test procedure 0PT-20.3-B21, Local Leakrate Testing for Feedwater System, revision 13, indicates that 1(2)-E41-F006 were removed from the Appendix J program via PRR# 2362917 following implementation of EC 417109. If the vendors evaluation was not technically correct, removal of the HPCI valves from the Appendix J testing program by updating the test procedure to remove the HPCI valves, could have constituted a violation of 10 CFR 50, Appendix B, Criterion III, Design Control, which required that, measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in in § 50.2 and as specified in the license application, for those structures, systems, and components to which this appendix applies are correctly translated into specifications, drawings, procedures, and instructions. The inspectors believed at the time of the inspection that, if inappropriately excluded from the test procedure and if left uncorrected, the removal of the valves from the Appendix J test program could result in the valve seat leakage rate degrading past the point of acceptability.

Planned Closure Actions: The inspectors asked the licensee several additional questions to verify the appropriateness of the removal of the HPCI valves from the test program, however, due to resource limitations the questions have not been addressed as of the time of this inspection report issuance. The URI is opened pending determination of whether or not a violation exists. The licensees response to the inspector questions will assist in this determination.

Licensee Actions: If it is determined that the valves should not have been removed from the 10 CFR 50, Appendix J test program, the Unit 1 valve (1-E41-F006) would be due to be tested under 0PT-20.3-B21 by March 4, 2022. Therefore, no immediate action for the 1-E41-F006 valve was required. As a result of its removal from the test procedure, the Unit 2 valve (2-E41-F006) was not tested during the most recent refueling outage, B2R25 in 2021, but had been tested every outage prior. The other valves associated with the penetration were local leak rate tested during B2R25 and had acceptable results. In response to the inspector's concern, the licensee reviewed the historical performance of the 2-E41-F006 valve to determine if the allowances of 10 CFR 50, Appendix J, Option B would have been able to be utilized. The licensee determined that the test interval extension criteria in station procedures would have been met and would have allowed for an extension until B2R27 (2025). Therefore, no immediate action for the 2-E41-F006 valve was required.

Corrective Action References: NCR 02384029, "DBAI POV Inspection Unresolved Issue (URI) initiated"

EXIT MEETINGS AND DEBRIEFS

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

• On May 27, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Jay Ratliff, Plant General Manager, and other members of the licensee staff.

• On April 29, 2021, the inspectors presented the initial inspection results to Mr. John Krakuszeski, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02 Calculations

0E41-0003

Seismic Qualification 1/2E41-F006

Rev. 1

0SLC-0001

SLC Solution Design Requirements

Rev. 4

2SEIS-0019

Valve #2-B21-F013C, -F022a, -F028A, -F028B, -F028C, -

F028D & 2-E41-F002 Interaction Resolution

Rev. 0

3397C

Justification of Applicability of the EPRI Performance

Prediction Methodology to the Sentinel Gate Valve

Rev. 0

95135-C-104

Design Report and Weak Weak Link Analysis for MOVs

E41-F001

Rev. 0

95135-C-14

Seismic Weak Link Assessment MOV(s) 1/2-G31-F001 &

F004

Rev. 4

95135-C-17

Seismic Weak Link Assessment MOV(s) 1/2-E41-F006

Rev. 1

95135-C-35

SEISMIC WEAK LINK TORQUE CALCULATION MOV(S)

& 2-E1 1-F020A & B

Rev. 1

BNP-E-5.047

Cable Impedance Calculation for Brunswick Units 1 & 2

Rev. 1

BNP-E-6.032

Unit 2 DC Valve Overload Relay Heater Sizing

Rev. 10

BNP-E-6.033

Unit 1 DC Valve Overload Relay Heater Sizing

Rev. 11

BNP-E-6.109

Unit 1 Stroke Time and Motor Torque Calculation for 250

VDC Safety Related Motor Operated Valves

Rev. 14

BNP-E-6.110

Unit 2 Stroke Time and Motor Torque Calculation for 250

VDC Safety Related Motor Operated Valves

Rev. 15

BNP-E-6.120

25/250 VDC System Battery Load Study

Rev. 14

BNP-E-7.002

AC Auxiliary Electrical Distribution System Voltage / Load

Flow/Fault Current Study

Rev. 15

BNP-E-8.013

Motor Torque Analysis for AC Motor Operated Valves

Rev. 21

BNP-E-8.014

Motor Torque Analysis for AC Motor Operated Valves

Rev. 22

BNP-MECH-1-

G16-F020-AO

AOV Setup Calculation for 1-G16-F020-AO Drywell

Equipment Drain Outboard Isolation Valve

Rev. 0

BNP-MECH-95-

07-A

Initial Screening of BNP Power-Operated Valves in

Accordance with Generic Letter 95-07

Rev. 1

BNP-MECH-95-

07-B

Review of the Potential for Pressure Locking or Thermal

Binding of BNP Gate Valves in Accordance with Generic

Rev. 4

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Letter 95-07

BNP-MECH-

AOV-DP-MS

Functional Evaluation of 1/2-B21-F022A-D-AO and 1/2-

B21-F028A-D-AO Main Steam Isolation Valves

Rev. 2

BNP-MECH-

AOV-SCOPE

BNP AOV PROGRAM SCOPE

Rev. 3

BNP-MECH-E11-

F007A/B

Mechanical Analysis and Calculations for 1 & 2-E11-

F007A/B RHR Minimum Flow Valves

Rev. 8

BNP-MECH-E11-

F020A/B

MECHANICAL ANALYSIS AND CALCULATIONS FOR

1/2-E11-F020A/B RHR PUMP SUPPRESSION POOL

SUCTION VALVES

Rev. 7

BNP-MECH-E11-

F048A/B

Mechanical Analysis and Calculations for 1 & 2-E11-

F048A/B RHR Heat Exchanger Bypass

Rev. 6

BNP-MECH-E41-

F001

MECHANICAL ANALYSIS AND CALCULATIONS FOR

1/2-E41-F001 HIGH PRESSURE COOLANT INJECTION

TURBINE STEAM ADMISSION VALVE

Rev. 008

BNP-MECH-E41-

F006

MECHANICAL ANALYSIS AND CALCULATIONS FOR

1/2-E41-F006 HIGH PRESSURE COOLANT INJECTION

VALVE

Rev. 008

BNP-MECH-G31-

F001

MECHANICAL ANALYSIS AND CALCULATIONS OF 1 &

G31-F001 RWCU INBOARD ISOLATION VALVES

Rev. 9

BNP-MECH-

MOV-DP

Mechanical Analysis and Calculations for Differential

Pressure Calculations for all GL 89-10 and GL 96-05

MOVs

Rev. 9

BNP-MECH-

MOV-ROL

Review of BNP "As Tested" ROL Data & Determination of

ROL Values to Be Used for GL 98-10 Motor-Operated

Valves

Rev. 3

BNP-MECH-

MOV-SF

Review of BNP Test Data to Establish Bounding Stem

Factors for BNP GL 89-10 Motor-Operated Valves

Rev. 4

BNP-MECH-

MOV-

TRANSIENT

THERMAL

Determination of Transient Thermal Response for BNP

GL 89-10 & GL 96-05 Motor-Operated Valves

Rev. 1

BNP-MECH-

MOV-UNW

Review of BNP "As Tested" Unwedging Data & Validation

of EPRI Unwedging PPM Models BNP GL 89-10 Motor-

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Operated Valves

BNP-MECH-

MOV-VF

Review of BNP "As Tested" Valve Factors &

Determination of VF Values to be Used for BNP GL 89-10

Motor-Operated Valves

Rev. 7

BNP-PSA-104

BNP Air-Operated Valve, Motor-Operated Valve, and

Check Valve PRA Risk Significance

Rev. 000

DPC-1381.05-00-

0109

Thermal Analysis of the Steady-State Heat Rise Inside

Limitorque Actuator Limit Switch Compartments

Considering Energized Resistance Heaters - A Finite

Element Study for Brunswick Nuclear Plant

Rev. 0

DR 83.010

Anchor/Darling Valve Analysis

11/14/1983

Corrective Action

Documents

PRR 02362917,

NCR 738146,

NCR 02073255,

NCR 02061877,

NCR 02008039,

LTAM BNP-14-

0079, NCR

677459, OCR

677459, AR

2594-04, NCR

1952454, NCR

1953768, NCR

2010083, NCR

23669, NCR

2377405, AR

2321, NCR

281433, NCR

2073255, NCR

2188317, NCR

281433, NCR

291385, NCR

291132

Corrective Action

AR 0050917 Task Evaluat SLD for ball screw stems

04/26/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

Resulting from

Inspection

NCR 02378217

21 POV: Source for Wedge Angle Not Sited (sic) in

Calculations

04/13/2021

NCR 02379355

IST Program Classification of Valves

04/21/2021

NCR 02379361

21 POV: Incorrect Angle Assumption in BNP-MECH-

G31-F001

04/21/2021

NCR 02379828

21 POV: BNP-MECH-G31-F001(4) Not in Compl. w/

AD-EG-1415

04/26/2021

NCR 02379927

POV Inspection - MOV Program documentation error on

JOG Class

04/26/2021

NCR 02380090

21 POV: BNP-E-8.013 and 8.014 Torque Calculation

Error

04/27/2021

NCR 02380224

DBAI POV UFSAR not Updated for AST

04/28/2021

NCR 02380258

21 POV: Stem Lub. Degradation Term Requires

Change

04/28/2021

NCR 02380339

21 POV: NRC POV DBAI SLC Sys Inclusion in EQ

Prog

04/28/2021

NCR 02384029

DBAI POV Inspection Unresolved Issue (URI) initiated

05/26/2021

Drawings

0-FP-05101

Isolation Valve Primary Steam

Rev. B

0-FP-06006

24" - 150# GATE VALVE MOTOR OPERATED

Rev. C

0-FP-06094

Unit 1 & 2 Philadelphia Gear Corp Limitorque Valve

Control

Rev. C

0-FP-06152

Anchor 4" 300# Gate Valve

Rev. M

0-FP-06156

20" 300# Bolted Globe Valve

Rev. J

0-FP-06894

3"-150# GATE VALVE C.S.

Rev. D

0-FP-82679

Sheet 1

14"-900 Weld Ends Carbon Steel Double Disc Gate Valve

with Limitorque SB-2-60 Actuator with Ballscrew

Assembly

Rev. B

0-FP-82805 SHT

Units 1 & 2 Anchor/Darling Valve Company 6"-900

Double Disc Gate Valve

Rev. A

0-FP-85548

SH0001

X 5 MSIV ACTUATOR

Rev. 00E

0-FP-85548 SHT

x 5 MSIV Actuator

Rev. C

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

0-FP-85548 SHT

x 5 MSIV Actuator Ralph A. Hiller Company

Rev. B

0-FP-85548 SHT

x 5 MSIV Actuator

Rev. C

0-FP-85548 SHT

x 5 MSIV Actuator

Rev. C

0-FP-85548 SHT

x 5 MSIV Actuator

Rev. C

0-FP-87720

SH0001

Crane 10 x 8 x 10 Sentinel Gate Valve 1-E41-F001/ 2-

E41-F001

Rev. B

0-FP-87747 SHT

Limitorque Actuator Model No. SMB-2

Rev. A

0-FP-88781

SH0001

PILOT CONTROL THREE VALVE MANIFOLD

Rev. 00A

1-FP-50017

Residual Heat Removal System Elementary Wiring

Diagram - Sht. 16

Rev. 27

1-FP-55109 SHT

NUCLEAR STEAM SUPPLY SHUT OFF SYSYTEM

ELEMENTARY DIAGRAM

Rev. M

1-FP-55109, SH

ELEM DIAG NUCLEAR STEAM SUPPLY SHUTOFF SYS

UNIT 1

Rev. M

1-FP-81745

Reactor Building High Pressure Coolant Inject Limitorque

Valve Control-SMB-3 Unit No 1

Rev. 0

2-FP-50056

Unit 2 Nuclear Steam Supply Shutoff System Elementary

Diagram

Rev. J

2-FP-55013 SHT

Unit 2 Rockwell International Mainsteam Isolation Valve

Rev. C

2-FP-55013 Sht 3

Unit 2 Rockwell International Mainsteam Isolation Valve

List of Material

Rev. B

2-FP-81134

MSIV Limit Switch Bracket Detail

Rev. A

BN-19.0.1

High Pressure Coolant Injection (HPCI) System

Rev. 04

D-02040

SH0001A

CONDENSATE DEMINERALIZED WATER TRANSFER

SYSTEMS PIPING DIAGRAM

Rev. 041

D-02521

SH0001B

Reactor Building Nuclear Steam Supply System Piping

Diagram

Rev. 052

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

D-02523 SH0002

REACTOR BUILDING HIGH PRESSURE COOLANT

INJECTION SYSTEM PIPING DIAGRAM

Rev. 054

D-02523 SHT 1

REACTOR BUILDING HIGH PRESSURE COOLANT

INJECTION SYSTEM PIPING DIAGRAM

Rev. 59

D-02525

SH0001B

REACTOR BUILDING RESIDUAL HEAT REMOVAL

SYSTEM PIPING DIAGRAM

Rev. 72

D-02526

SH0002A

REACTOR BUILDING RESIDUAL HEAT REMOVAL

SYSTEM PIPING DIAGRAM

Rev. 57

D-02526

SH0002B

REACTOR BUILDING RESIDUAL HEAT REMOVAL

SYSTEM PIPING DIAGRAM

Rev. 84

D-02700

Reactor Building Instrument Air System Plan at 20' - 0" &

Sections - Sheet No. 2 Unit No. 2

Rev. 17

D-04219

Nuclear Safety Capability Assessment High Press.

Coolant Injection System (HPCI)

Rev. 14

D-07007

Reactor Building Instrument Air Supply System Piping

Diagram

Rev. 35

D-25021

SH0001C

Reactor Building Nuclear Steam Supply System Piping

Diagram

Rev. 48

D-25023-SH0001

Reactor Building High Pressure Coolant Injection System

Piping Diagram

Rev. 61

D-25023-SH0002

Reactor Building High Pressure Coolant Injection System

Piping Diagram

Rev. 54

D-25026

Reactor Building Residual Heat Removal System Piping

Diagram - Sht. 0002B

Rev. 72

D-25026

Reactor Building Residual Heat Removal System Piping

Diagram - Sht. 2A

Rev. 63

D-25027

SH0001B

UNIT NO. 1 REACTOR BUILDING REACTOR WATER

CLEAN-UP SYSTEM PIPING DIAGRAM

Rev. 47

D-25045

SH0003A

REACTOR BUILDING DRYWELL DRAINS PIPING

DIAGRAM

Rev. 42

D-25047

Reactor Building Standby Liquid Control System Piping

Diagram

Rev. 34

D-70029

SH0002A

Reactor Building Instrument Air Supply System Piping

Diagram

Rev. 38

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

F-02993

Unit 2 Reactor Building E.Q. Zone Maps - Sht. 1

Rev. 3

F-02993

Reactor Building E.Q. Zone Maps - Sht. 2

Rev. 6

F-07268

Reactor Building Instr. Air Piping Installation Detail Sheet

Rev. 9

F-29093

Unit 1 Reactor Building E.Q. Zone Maps - Sht. 4

Rev. 2

F-29093

Unit 1 Reactor Building E.Q. Zone Maps - Sht. 3

Rev. 2

F-7212

Reactor Building Instrument Air Piping Primary

Containment Plan Below Elev. 38 ' - 4 & 45' - 0 Unit No. 2

Sheet No. 3

Rev. 8

FS DW-25078

SHT 4

Piping Isometric-BLDG: Reactor System: Reactor Water

Cleanup Elev: 50'-0"

Rev. 4

LL-09236

RHR Heat Exchanger "2A" Bypass Valve 2-E11-F048A

Control Wiring Diagram - Sht. 75

Rev. 7

LL-09237 SHT 91

MCC "2XB"- COMPT. "2-DN6" RHR Suppression Pool

Suction Valve 2-E11-F020B Control Wiring Diagram

Rev. 15

LL-09237 SHT

91A

MCC "2XB"- COMPT. "2-DN6" RHR Suppression Pool

Suction Valve 2-E11-F020B Control Wiring Diagram

Rev. 3

LL-09272 SHT 31

MCC "2XDA" - COMPT. "2-B21" HPCI Steam Supply

Valve to Turbine 2-E41-F001 Control Wiring Diagram

Rev. 13

LL-92037

MCC "1XB" Compt. "1-DL3" RHR Pump 1B Minimum

Flow Bypass Valve 1-E11-F007B Control Wiring Diagram

- Sht. 48

Rev. 11

LL-92038 SHT 46

Unit No. 1' MCC "1XC" COMPT "1-DT9" RWCU Inboard

Isol Valve 1-G31-F001 Control Wiring Diagram

Rev. 12

LL-92043

MCC "1XG" - Compartment "1-EG6" Standby Liquid

Control Pump 1A - 1-C41-C001A Control Wiring Diagram

- Sht. 18

Rev. 7

LL-92072 SH. 23

Unit No. 1 MCC "1XDA" Compt "B17" HPCI Pump

Discharge Valve 1-E41-F006 Control Wiring Diagram

Rev. 13

Engineering

Changes

EC 250516

Unit 1 SLC Boron Concentration Change for EPUR

Rev. 5

EC 250522

SLC Squib Valve Shelf Plus Service Life Extension

Rev. 0

EC 290843

Flowserve Anchor Darling Double-Disc Gate Valve wedge

pin

Rev. 0

EC 294179

Replace E41-F001 with Crane Sentinel Valve

Rev. 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

EC 295980

Change MSIV Function to Require Both Air and Spring to

Close

Rev. 0

EC 296885

HPCI Valve Replacement

Rev. 4

EC 401998

Acceptability of Reducing Stroke Length of 2-E11-F020B

Rev. 0

EC 407614

Acceptability of Reducing Stroke Length of E11-F020

Valves

Rev. 0

EC 417109

EVALUATION OF PENETRATIONS AND VALVES

ELIGIBLE FOR APPENDIX J LOCAL LEAK RATE

TESTING EXCLUSION

Rev. 0

EC 50522

SLC Squib Valve Shelf Plus Service Life Extension

Rev. 0

EC 59983

MSIV accumulator system upgrade to safety-related

Rev, 0

ESR 9500589

LIMIT SEAT VALVES TO IMPROVE LLRT

REPEATABILITY

Rev. 0

ESR 98-00069

Replace Motor 1-G31-F001 to Increase Torque

Rev. 1

Engineering

Evaluations

0BNP-TR-003

Motor Operated Valve (MOV) Scoping GL 89-10 And GL 96-05

Rev. 3

0BNP-TR-006

Motor Operated Valve (MOV) Design Basis Information

GL 89-10 & GL 96-05

Rev. 8

2-B21-F022A

PTE 2015

Post Test Evaluation of AOV Diagnostics for 2-B21-

F022A, Test Date 3/19/15

04/15/2015

DR-227

Environmental Qualification Service Conditions

Rev. 21

ESR 97-00604

Resolution of Open Items from EQ DR 227

Rev. 0

ESR-96-00709

Q-Class A Components Excluded from the EQ Program

Rev. 0

Miscellaneous

BNP AOV Calculation Basis Document

Rev. 1

1-E41-F006

B120R1 PTE

MOV Post-Test Data Review Worksheet for 1-E41-F006

Test Date 03/08/14

03/31/14

2-B21-F022 CofC

Certificate of Compliance from Rockwell

2/15/1970

2-E41-F001

Certificate

Certification to Contract Specifications from Anchor Valve

Company for 2-E41-F001

Undated

2-E41-F001 PTE

MOV Post-Test Data Review Worksheet for 2-E41-F001

Test Date 03/24/19

03/29/19

248-118

GATE, GLOBE AND CHECK VALVES

Rev. 5

248-163

PROCUREMENT OF MAIN STEAM ISOLATION

VALVES

Rev. 003

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

50-325/00-02 and

50-324/00-02

NRC Integrated Inspection Report Nos. 50-325/00-02 and

50-324/00-02

04/25/2000

93164-01

Motor Operated Valve (MOV) Structural & Weak Link

Evaluation - Methodology

Rev. 0

9811020153

Generic Letter 96-05, "Periodic Verification of Design

Basis Capability of Safety-Related Motor-Operated

Valves" Commitment to Topical Report NEDC-32719,

Revision 2

10/27/1998

BSEP 01-0009

Generic Letter 89-10 Motor-Operated Valve Program

Status After Completion of Committments

01/15/2001

BSEP 01-0063

Request for License Amendments Alternative

Radiological Source Term

08/01/2001

BSEP 01-0166

Response to Request for Additional Information

Regarding Request for License Amendments - Extended

Power Uprate

03/12/2002

BSEP 06-0051

Response to the NRC Generic Letter 95-07, "Pressure

Locking and Thermal Binding of Safety-Related Power-

Operated Gate Valves"

2/13/1996

BSEP 16-0056

(ML16257A418)

Request for License Amendment Regarding Core Flow

Operating Range Expansion

09/06/2016

BSEP 97-0408

Generic Letter 89-10 Motor-Operated Valve Program

Status

10/02/1997

BSEP 98-0058

Generic Letter 89-10 Motor-Operated Valve Program

Commitments Related to Program Closure

2/20/1998

BSEP-00-0194

Response to Request for Additional Information

Regarding Generic Letter 96-05, "Periodic Verification of

Design-Basis Capability of Safety-Related Power-

Operated Valves"

2/20/1999

BWROG-8727

GE Licensing Topical Report NEDE-31096-P-A and

NEDE-31096-A, "Anticipated Transients Without SCRAM

Response to NRC ATWS Rule, 10CFR50.62",Dated

February 1987

06/12/1987

CSD-EG-BNP-

20

BNP IST Program Plan - 5th Interval

Rev. 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DBD-05

Standby Liquid Control System

Rev. 14

DBD-12

PRIMARY CONTAINMENT ISOLATION SYSTEM

Rev. 9

DBD-17

Residual Heat Removal System

Rev. 29

DBD-19

High Pressure Coolant Injection System

Rev. 027

DBD-23

CONTAINMENT PENETRATIONS SYSTEM

Rev. 9

Design Report

Nos. 12 and 13

Design Basis for Engineered Safety Features and

Generation and Consequences of Turbine Missiles

03/29/1972

DR 17.1

Qualification of EA740 Series Limit Switches for Use in

Nuclear Power Plants in Compliance with IEEE Standards

23-1974, 382-1972 and 344-1975

Rev. 0

DR 17.4

Supplement 02 to QTR111 Generic Qualification of Series

EA740 Limit Switches: Qualification By Similarity

Presentation to Support the Change of Contact Block/

Carrier Material

Rev. 0

DR 257

LIMITORQUE CORPORATION REPORT No. B0212

NUCLEAR POWER STATION QUALIFICATION TYPE

TEST FOR LIMITORQUE VALVE ACTUATORS WITH

TYPE LR MOTOR FOR WESTINGHOUSE PWR

Rev. 0

DR 265

General Electric Test Report No. NEDC-31344

Environmental Qualification Report on MSIV Limit

Switches for Nine Mile Point Nuclear Station Unit 2

Rev. 0

DR 274

General Electric Report No. NEDC 32370P Environmental

Qualification Report for Carolina Power & Light Brunswick

Unit 1 & 2 Main Steam Isolation Valve (MSIC) Solenoid

Valve Cluster Assembly (SVCA) with Automatic Valve

Corp (AVC) Solenoid Valves

Rev. 1

DR 4.3

Final Report on the Evaluation of the Qualification of the

Limitorque SMB Series MOV with Class B or Better AC or

DC Motors with Melamine or Phenolic Switches in the

BSEP Reactor Building Provided by the Limitorque

Corporation for Use in Carolina Power and Light

Company's Brunswick Steam Electric Plant

Rev. A

DR 80.1

NAMCO REPORT QTR 140-GENERIC QUALIFICATION

OF SERIES EA 740 SWITCHES (WITH SUPPLEMENT)

Rev. 002

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DR 80.9

NAMCO TEST REPORT NO. QTR 180: GENERIC

QUALIFICATION OF EA 740-SERIEW LIMIT SWITCHES

FOR USE IN NUCLEAR POWER PLANT CLASS 1E

APPLICATIONS

Rev. 001

DR-259

General Electric Test Report NEDC-31051

River Bend Station Unit 1 Environmental Qualification

Report (NUREG 0588, Category 1) Volumes 1 & 2

Rev. 0

EPRI TR-103232

EPRI MOV Performance Prediction Program Stem Thrust

Prediction Method for Anchor/Darling Double Disc Gate

Valves

dated

November

1994

FP-20243

Valve Operators

Rev. 0AD

FP-50554

Valves, Main Steam Isolation

Rev. AB

FP-61761

VALVES AND OPERATORS

Rev. 0AF

FP-82621

ACTUATORS, VALVE

Rev. 00M

FP-82808

SWING CHECK, GATE VALVES; SINGLE & DOUBLE

DISC VALVES

Rev. G

FP-87721

CRANE SENTINEL BOLTED BONNET GATE VALVE

Rev. A

GE 21A9230

Procurement and Design Specification GE Main Steam

Isolation Valves

Rev. 2

LDCR 03FSAR-

040

E41-F042 PCIV Function Update

dated

2/04/2004

M20205F215

Response to Request for Additional Information

Regarding Generic Letter 95-07, "Pressure Locking and

Thermal Binding of Safety-Related Power-Operated Gate

Valves" (TAC Nos. M93439 and M93440)

03/31/1999

ML003711034

Safety Evaluation of Licensee Response to Generic Letter 96-05, Brunswick Steam Electric Plant, Unit Nos. 1 and 2

(TAC M97023 and M97024)

05/03/2000

ML003712627

Brunswick 1 and 2 - Completion of Licensing Action for

Generic Letter 96-05, "Periodic Verification of Design-

Basis Capability of Safety-Related Motor-Operated

Valves" (TAC Nos. M97023 and M97024)

05/08/2000

ML14178B034

Revised Date for Completion of NEI Initiative Addressed

in NE 96-05

04/10/1997

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ML14188A815

Supplemental Response to Generic Letter 89-10:

Clarifications on Motor-Operated Valve Program

06/06/1991

ML20014D829

Second Request for Additional Information - Generic Letter 95-07, "Pressure Locking and Thermal Binding of

Safety-Related Power-Operated Gate Valves," Brunswick

Steam Electric Plant, Units 1 and 2 (TAC Nos. M93439

and M93440)

2/04/1998

ML20065S582

Response to NRC Generic Letter 89-10, Supplement 3

2/17/1990

ML20072N412

Generic Letter 89-10: Motor-Operated Valves

08/23/1994

ML20073M613

US NRC Inspection Report Nos. 50-325/94-20 and 50-

24/94-20

09/21/1994

ML20076M985

Supplemental Response to NRC Generic Letter 89-10,

Supplement 3

03/20/1991

ML20077G551

Request for Additional Information Re: Generic Letter

(GL) 89-10, Supplement 3, "Consideration of the Results

of NRC-Sponsored Tests of Motor-Operated Valves" -

Brunswick Steam Electric Plant, Units 1 and 2 (TAC Nos.

77768 and 77769)

06/25/1991

ML20086P598

Inspection Report: 50-325/91-31 and 50-324/91-31

2/12/1991

ML20091B821

Response to NRC Request for Additional Information

Regarding CP&L Response to NRC Generic Letter 89-10,

Supplement 3

07/29/1991

ML20092M512

File: B09-12510C, Response to NRC Inspection 91-31

2/24/1992

ML20093K310

Response to the NRC Staff Request for Information

Regarding NRC Generic Letter 95-07, "Pressure Locking

and Thermal Binding of Safety-Related Power Operated

Gate Valves"

10/16/1995

ML20095C924

Response to the NRC Staff Request for Information

Within 180 Days for NRC Generic Letter 95-07, "Pressure

Locking and Thermal Binding of Safety-Related Power-

Operated Gate Valves"

2/06/1995

ML20107L516

Response to the NRC Generic Letter 95-07, "Pressure

Locking and Thermal Binding of Safety-Related Motor-

Operated Gate Valves"

04/26/1996

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ML20113B086

Response to NRC Generic Letter 95-07, "Pressure

Locking and Thermal Binding of Safety-Related Motor-

Operated Gate Valves"

06/20/1996

ML20117G371

Request for Additional Information - Generic Letter 95-07,

"Pressure Locking and Thermal Binding of Safety-Related

Motor-Operated Gate Valves," Brunswick Steam Electric

Plant, Units 1 and 2 (TAC Nos. M93439 and M93440)

05/16/1996

ML20134N054

Response to Generic Letter 96-05, "Periodic Verification

of Design-Basis Capability of Safety-Related Valves"

11/18/1996

ML20136H370

Request of Additional Information Regarding Generic Letter 96-05 Program at Brunswick (TAC Nos. M97023

and M97024)

2/25/1999

ML20137C040

Response to NRC Generic Letter 96-05, "Periodic

Verification of Design-Basis Capability of Safety-Related

Motor-Operated Valves"

03/17/1997

ML20198L044

Request for Additional Information Regarding Generic Letter 95-07, "Pressure Locking and Thermal Binding of

Safety-Related Power-Operated Gate Valves" -

Brunswick Steam Electric Plant, Unit No. 1 and 2 (TAC

Nos. M93439 and M93440)

2/21/1998

ML20199C227

NRC Integrated Inspection Report Nos. 50-325/97-11 50-

24/97-11 Notice of Violation

10/27/1997

ML20202E432

1998 BSEP Generic Letter 89-10 Motor-Operated Valve

Program "End-of-Year" Status

01/27/1999

ML20216H288

NRC Integrated Inspection Report Nos 50-325/98-03, 50-

24/98-03

04/13/1998

ML993160030

Response to Request for Additional Information

Regarding Generic Letter 95-07, "Pressure Locking and

Thermal Binding of Safety-Related Power-Operated Gate

Valves" (TAC Nos. M93439 and M93440)

11/03/1999

ML993250087

Safety Evaluation of Licensee Response to Generic Letter 95-07, "Pressure Locking and Thermal Binding of Safety-

Related Power-Operated Gate Valves," Brunswick Steam

Electric Plant, Units 1 and 2 (TAC Nos. M93340 and

11/10/1999

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

M93440)

ML993410457

Safety Evaluation of Response to Generic Letter 95-07,

"Pressure Locking and Thermal Binding of Safety-Related

Power-Operated Gate Valves," Brunswick Steam Electric

Plant, Units 1 and 2 (TAC Nos. M93439 and M93440)

2/03/1999

MOV Stem

Lubricant Aging

Research

INEEL Presentation

dated

01/15/2003

NUREG/CP-

0152, Volume 5

EPRI MOV Stem Lubricant Test Program, Frictional

Performance of Exxon Nebula and MOV Long Life in a

Stem Lubrication Application, John Hosler

NUREG/CP-

0152,

Volume 5

QDP 103

MAIN STEAM ISOLATION VALVE (MSIV) SOLENOID

VALVE CLUSTER ASSEMBLY WITH AVC SOLENOID

VALVES

Rev. 011

QDP 29B

LIMITORQUE MOTOR OPERATED VALVES (MOVS)

WITH CLASS H (TYPE RH) INSULATED DC MOTORS

Rev. 14

QDP 48

NAMCO EA740 SERIES LIMIT SWITCHES

Rev. 016

RA-17-0053

Anchor Darling Double Disc Gate Valve Information and

Status

2/20/2017

RAL-1029

Design Report for Carolina Power and Light Co.

Brunswick Units 1 and 2 Size 24 x 20 x 24 Fig. 1612

JMMNY Main Steam Isolation Valve

Rev. 4

Rate of Loading

Flowserve Test

Program

2003 MUG Presentation

dated 2003

SD-19

HIGH PRESSURE COOLANT INJECTION (HPCI)

SYSTEM

Rev. 025

Procedures

0AP-019

Licensing Document Changes

Rev. 5

0BNP-TR-008

Inservice Inspection/ Testing Guideline

Rev. 13

0CM-AO519

MILLER FLUID POWER VALVE OPERATORS, MODEL

A61-B

Rev. 3

0CM-MO500

Repair Instructions for Model SMB-5T Limitorque Motor

Operator

Rev. 15

0CM-MO501

Limitorque Model Numbers SMB-0 Through 4, SMB-4T,

Rev. 28

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

and SB-0 Through SB-4

0CM-MO502

Repair Instructions for Limitorque Motor Operators Model

Number SMB-000

Rev. 24

0CM-MO503

Limitorque Motor Operators Model Number SMB-00 and

SB-00

Rev. 19

0CM-MO506

Limitorque Operator Types HBC-0 Through HBC-6

Rev. 20

0CM-MO507

Removal and Installation of SMB/SB Type Limitorque

Operators

Rev. 24

0ENP-16.8

Containment Leakage Tracking

Rev. 31

0ENP-646

Post Test Evaluation and AOV Diagnostics

Rev. 3

0PLP-20

Post-Maintenance Testing Program

Rev. 53

0PM-AO014

Air Operated Valve Diagnostic Testing

Rev. 4

0PM-MO009

AC and DC Limitorque Motor Operated Valve

Preventative Maintenance Procedure

Rev. 21

0PM-MO504

Mechanical Inspection and Lubrication of Limitorque

Operators

Rev. 46

0PT-06.1

Standby Liquid Control System Operability Test

Rev. 89

0PT-08.2.2B

LPCI/RHR System Operability Test - Loop B

Rev. 109

0PT-09.7

HPCI System Valve Operability Test

Rev. 039

0PT-11.3

DRYWELL DRAINS SYSTEM VALVE OPERABILITY

TEST

Rev. 32

0PT-12/1A 006A

No. 1 Diesel Generator LOOP/LOCA Loading Test

Rev. 0

0PT-14.6

REACTOR WATER CLEANUP SYSTEM OPERABILITY

TEST

Rev. 33

completed

03/12/2020

0PT-20.3-B21

Local Leakrate Testing for Feedwater System

Rev. 13

0PT-25.1

Nuclear Steam Supply System Main Steam Isolation

Valve Operability Test

Rev. 038

0PT-40.2.8

Main Steam Isolation Valve Closure Test

Rev. 035

AD-EG-ALL-1013

Conduct of Plant Engineering

Rev. 4

AD-EG-ALL-1107

Quality Classifications

Rev. 5

AD-EG-ALL-1110

Design Review Requirements

Rev. 9

AD-EG-ALL-1117

Design Analyses and Calculations

Rev. 8

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-EG-ALL-1202

Preventive Maintenance and Surveillance Testing

Administration

Rev. 10

AD-EG-ALL-1415

Motor Operated Valve Performance Prediction, Actuator

Settings, and Diagnostic Test Data Reconciliation

Rev. 0

AD-EG-ALL-1431

Air Operated Valve Scope and Categorization

Rev. 2

AD-EG-ALL-1432

Air Operated Valve Design Basis Review

Rev. 1

AD-EG-ALL-1433

Air Operated Valve Testing Requirements

Rev. 2

AD-EG-ALL-1434

Air Operated Valve Tracking and Trending Requirements

Rev. SUP

AD-EG-ALL-1450

Preconditioning of Structures, Systems and Components

Rev. 0

AD-EG-ALL-1612

Environmental Qualification (EQ) Program

Rev. 7

AD-LS-ALL-0005

UFSAR Updates

Rev. 8

AD-LS-ALL-0018

Evaluating and reporting of Defects and Noncompliance

in Accordance with 10 CFR 21

Rev. 2

AD-PI-ALL-0100

Corrective Action Program

Rev. 25

BNP-PSA-104

BNP Air-Operated Valve, Motor-Operated Valve, and

Check Valve PRA Risk Significance

Rev. 0

CSD-EG-BNP-

20

BNP IST Program Plan - 5th Interval

Rev. 2

CSD-EG-DEP-

0101

Electrical Calculation of Motor Output Torque for AC and

DC Motor Operated Valves (MOVs)

Rev. 0

CSD-EG-DEP-

0359

Motor Operated Valve Structural Evaluation

Rev. 0

EGR-NGGC-0101 Electrical Calculation of Motor Output Torque for AC and

DC Motor Operated Valves (MOVs)

Rev. 4

MNT-NGGC-0010 Installation and Use of Teledyne/ Quiklook Equipment for

MOV Diagnostic Testing

Rev. SUP

OENP-646

POST TEST EVALUATION OF AOV DIAGNOSTICS, 1-

G16-F020 B1R23 (2020)

Rev. 3,

completed

03/30/2020

OPT-08.2.28

LPCI/RHR SYSTEM OPERABILITY TEST - LOOP 8

Rev. 109

completed

2/31/2020

PD-EG-ALL-1430

Air Operated Valve Program

Rev. 2

TE-EG-ALL-1413

MOV Design Database Control, Calculation and

Rev. 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Diagnostic Test Instruction Development, and Test Data

Evaluation/Trending

TE-MN-ALL-0100

Installation and Use of Teledyne / Quiklook Equipment for

MOV Diagnostic Testing

Rev. 1

TE-MN-ALL-0101

Installation of Teledyne Quikstem Sensors (QSS),

Smartstems and Easy Torque Thrust Sensors (ETT)

Rev. 1

Work Orders

WO 20026517,

WO 12299262,

WO 20456657-

01, WO 20137934-01,

WO 20255313

2, WO 20347641-05,

WO 20067488-

06, WO 20017784, WO 2075075-01, WO 20017784-21,

WO 20193678-

01, WO 1596071,

WO 11596071,

WO 12280049,

WO 20193678-

01, WO 20071746-01,

WO 13384285-

01, WO 2075944-

01, WO 243017-09,

WO 20219747-

01, WO 219747-03,

WO 20219747-

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

10, WO 20029439 -01,

WO 20176606,

WO 20340163,

WO 20438847