IR 05000324/2021011
| 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) | |
Similar Documents at Brunswick | |
|---|---|
Category:Inspection Report
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IR 05000325/2023401
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:
Report Numbers:
05000324/2021011 and 05000325/2021011
Enterprise Identifier: I-2021-011-0009
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
Seismic Qualification 1/2E41-F006
Rev. 1
SLC Solution Design Requirements
Rev. 4
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
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-
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,
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
21 POV: Source for Wedge Angle Not Sited (sic) in
Calculations
04/13/2021
IST Program Classification of Valves
04/21/2021
21 POV: Incorrect Angle Assumption in BNP-MECH-
G31-F001
04/21/2021
21 POV: BNP-MECH-G31-F001(4) Not in Compl. w/
AD-EG-1415
04/26/2021
POV Inspection - MOV Program documentation error on
JOG Class
04/26/2021
21 POV: BNP-E-8.013 and 8.014 Torque Calculation
Error
04/27/2021
DBAI POV UFSAR not Updated for AST
04/28/2021
21 POV: Stem Lub. Degradation Term Requires
Change
04/28/2021
21 POV: NRC POV DBAI SLC Sys Inclusion in EQ
Prog
04/28/2021
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
Unit 1 SLC Boron Concentration Change for EPUR
Rev. 5
SLC Squib Valve Shelf Plus Service Life Extension
Rev. 0
Flowserve Anchor Darling Double-Disc Gate Valve wedge
pin
Rev. 0
Replace E41-F001 with Crane Sentinel Valve
Rev. 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Change MSIV Function to Require Both Air and Spring to
Close
Rev. 0
HPCI Valve Replacement
Rev. 4
Acceptability of Reducing Stroke Length of 2-E11-F020B
Rev. 0
Acceptability of Reducing Stroke Length of E11-F020
Valves
Rev. 0
EVALUATION OF PENETRATIONS AND VALVES
ELIGIBLE FOR APPENDIX J LOCAL LEAK RATE
TESTING EXCLUSION
Rev. 0
SLC Squib Valve Shelf Plus Service Life Extension
Rev. 0
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
Motor Operated Valve (MOV) Scoping GL 89-10 And GL 96-05
Rev. 3
Motor Operated Valve (MOV) Design Basis Information
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
Generic Letter 89-10 Motor-Operated Valve Program
Status After Completion of Committments
01/15/2001
Request for License Amendments Alternative
Radiological Source Term
08/01/2001
Response to Request for Additional Information
Regarding Request for License Amendments - Extended
03/12/2002
Response to the NRC Generic Letter 95-07, "Pressure
Locking and Thermal Binding of Safety-Related Power-
Operated Gate Valves"
2/13/1996
Request for License Amendment Regarding Core Flow
Operating Range Expansion
09/06/2016
Generic Letter 89-10 Motor-Operated Valve Program
Status
10/02/1997
Generic Letter 89-10 Motor-Operated Valve Program
Commitments Related to Program Closure
2/20/1998
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
Standby Liquid Control System
Rev. 14
PRIMARY CONTAINMENT ISOLATION SYSTEM
Rev. 9
Residual Heat Removal System
Rev. 29
High Pressure Coolant Injection System
Rev. 027
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
Valve Operators
Rev. 0AD
Valves, Main Steam Isolation
Rev. AB
VALVES AND OPERATORS
Rev. 0AF
ACTUATORS, VALVE
Rev. 00M
SWING CHECK, GATE VALVES; SINGLE & DOUBLE
DISC VALVES
Rev. G
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
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
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
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
Supplemental Response to Generic Letter 89-10:
Clarifications on Motor-Operated Valve Program
06/06/1991
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
Response to NRC Generic Letter 89-10, Supplement 3
2/17/1990
Generic Letter 89-10: Motor-Operated Valves
08/23/1994
US NRC Inspection Report Nos. 50-325/94-20 and 50-
24/94-20
09/21/1994
Supplemental Response to NRC Generic Letter 89-10,
Supplement 3
03/20/1991
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
Inspection Report: 50-325/91-31 and 50-324/91-31
2/12/1991
Response to NRC Request for Additional Information
Regarding CP&L Response to NRC Generic Letter 89-10,
Supplement 3
07/29/1991
File: B09-12510C, Response to NRC Inspection 91-31
2/24/1992
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
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
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
Response to NRC Generic Letter 95-07, "Pressure
Locking and Thermal Binding of Safety-Related Motor-
Operated Gate Valves"
06/20/1996
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
Response to Generic Letter 96-05, "Periodic Verification
of Design-Basis Capability of Safety-Related Valves"
11/18/1996
Request of Additional Information Regarding Generic Letter 96-05 Program at Brunswick (TAC Nos. M97023
and M97024)
2/25/1999
Response to NRC Generic Letter 96-05, "Periodic
Verification of Design-Basis Capability of Safety-Related
Motor-Operated Valves"
03/17/1997
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
NRC Integrated Inspection Report Nos. 50-325/97-11 50-
24/97-11 Notice of Violation
10/27/1997
1998 BSEP Generic Letter 89-10 Motor-Operated Valve
Program "End-of-Year" Status
01/27/1999
NRC Integrated Inspection Report Nos 50-325/98-03, 50-
24/98-03
04/13/1998
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
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)
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
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
Licensing Document Changes
Rev. 5
Inservice Inspection/ Testing Guideline
Rev. 13
MILLER FLUID POWER VALVE OPERATORS, MODEL
A61-B
Rev. 3
Repair Instructions for Model SMB-5T Limitorque Motor
Operator
Rev. 15
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
Repair Instructions for Limitorque Motor Operators Model
Number SMB-000
Rev. 24
Limitorque Motor Operators Model Number SMB-00 and
SB-00
Rev. 19
Limitorque Operator Types HBC-0 Through HBC-6
Rev. 20
Removal and Installation of SMB/SB Type Limitorque
Operators
Rev. 24
0ENP-16.8
Containment Leakage Tracking
Rev. 31
Post Test Evaluation and AOV Diagnostics
Rev. 3
Post-Maintenance Testing Program
Rev. 53
Air Operated Valve Diagnostic Testing
Rev. 4
AC and DC Limitorque Motor Operated Valve
Preventative Maintenance Procedure
Rev. 21
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
01, WO 20137934-01,
2, WO 20347641-05,
06, WO 20017784, WO 2075075-01, WO 20017784-21,
01, WO 1596071,
01, WO 20071746-01,
01, WO 2075944-
01, WO 243017-09,
01, WO 219747-03,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10, WO 20029439 -01,