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) | |
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 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 Enclosure
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 Potential Inappropriate 10 71111.21N.02 Open 21011-01 CFR 50, Appendix J, Type C Test Exclusion
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 Potential Inappropriate 10 CFR 50, Appendix J, Type C Test 71111.21 (Open) Exclusion N.02 URI 05000325,05000324/2021011-01
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 Type Designation Description or Title Revision or
Procedure 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, - Rev. 0
F028D & 2-E41-F002 Interaction Resolution
3397C Justification of Applicability of the EPRI Performance Rev. 0
Prediction Methodology to the Sentinel Gate Valve
95135-C-104 Design Report and Weak Weak Link Analysis for MOVs Rev. 0
E41-F001
95135-C-14 Seismic Weak Link Assessment MOV(s) 1/2-G31-F001 & Rev. 4
F004
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) Rev. 1
& 2-E1 1-F020A & B
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 Rev. 14
VDC Safety Related Motor Operated Valves
BNP-E-6.110 Unit 2 Stroke Time and Motor Torque Calculation for 250 Rev. 15
VDC Safety Related Motor Operated Valves
BNP-E-6.120 125/250 VDC System Battery Load Study Rev. 14
BNP-E-7.002 AC Auxiliary Electrical Distribution System Voltage / Load Rev. 15
Flow/Fault Current Study
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- AOV Setup Calculation for 1-G16-F020-AO Drywell Rev. 0
G16-F020-AO Equipment Drain Outboard Isolation Valve
BNP-MECH-95- Initial Screening of BNP Power-Operated Valves in Rev. 1
07-A Accordance with Generic Letter 95-07
BNP-MECH-95- Review of the Potential for Pressure Locking or Thermal Rev. 4
07-B Binding of BNP Gate Valves in Accordance with Generic
Inspection Type Designation Description or Title Revision or
Procedure Date
Letter 95-07
BNP-MECH- Functional Evaluation of 1/2-B21-F022A-D-AO and 1/2- Rev. 2
AOV-DP-MS B21-F028A-D-AO Main Steam Isolation Valves
BNP-MECH- BNP AOV PROGRAM SCOPE Rev. 3
AOV-SCOPE
BNP-MECH-E11- Mechanical Analysis and Calculations for 1 & 2-E11- Rev. 8
F007A/B F007A/B RHR Minimum Flow Valves
BNP-MECH-E11- MECHANICAL ANALYSIS AND CALCULATIONS FOR Rev. 7
F020A/B 1/2-E11-F020A/B RHR PUMP SUPPRESSION POOL
SUCTION VALVES
BNP-MECH-E11- Mechanical Analysis and Calculations for 1 & 2-E11- Rev. 6
F048A/B F048A/B RHR Heat Exchanger Bypass
BNP-MECH-E41- MECHANICAL ANALYSIS AND CALCULATIONS FOR Rev. 008
F001 1/2-E41-F001 HIGH PRESSURE COOLANT INJECTION
TURBINE STEAM ADMISSION VALVE
BNP-MECH-E41- MECHANICAL ANALYSIS AND CALCULATIONS FOR Rev. 008
F006 1/2-E41-F006 HIGH PRESSURE COOLANT INJECTION
VALVE
BNP-MECH-G31- MECHANICAL ANALYSIS AND CALCULATIONS OF 1 & Rev. 9
F001 2 G31-F001 RWCU INBOARD ISOLATION VALVES
BNP-MECH- Mechanical Analysis and Calculations for Differential Rev. 9
MOV-DP Pressure Calculations for all GL 89-10 and GL 96-05
BNP-MECH- Review of BNP "As Tested" ROL Data & Determination of Rev. 3
MOV-ROL ROL Values to Be Used for GL 98-10 Motor-Operated
Valves
BNP-MECH- Review of BNP Test Data to Establish Bounding Stem Rev. 4
MOV-SF Factors for BNP GL 89-10 Motor-Operated Valves
BNP-MECH- Determination of Transient Thermal Response for BNP Rev. 1
MOV- GL 89-10 & GL 96-05 Motor-Operated Valves
THERMAL
BNP-MECH- Review of BNP "As Tested" Unwedging Data & Validation Rev. 0
MOV-UNW of EPRI Unwedging PPM Models BNP GL 89-10 Motor-
Inspection Type Designation Description or Title Revision or
Procedure Date
Operated Valves
BNP-MECH- Review of BNP "As Tested" Valve Factors & Rev. 7
MOV-VF Determination of VF Values to be Used for BNP GL 89-10
Motor-Operated Valves
BNP-PSA-104 BNP Air-Operated Valve, Motor-Operated Valve, and Rev. 000
Check Valve PRA Risk Significance
DPC-1381.05-00- Thermal Analysis of the Steady-State Heat Rise Inside Rev. 0
0109 Limitorque Actuator Limit Switch Compartments
Considering Energized Resistance Heaters - A Finite
Element Study for Brunswick Nuclear Plant
DR 83.010 Anchor/Darling Valve Analysis 11/14/1983
Corrective Action PRR 02362917,
Documents 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 Type Designation Description or Title Revision or
Procedure Date
Documents 46
Resulting from NCR 02378217 2021 POV: Source for Wedge Angle Not Sited (sic) in 04/13/2021
Inspection Calculations
NCR 02379355 IST Program Classification of Valves 04/21/2021
NCR 02379361 2021 POV: Incorrect Angle Assumption in BNP-MECH- 04/21/2021
G31-F001
NCR 02379828 2021 POV: BNP-MECH-G31-F001(4) Not in Compl. w/ 04/26/2021
AD-EG-1415
NCR 02379927 POV Inspection - MOV Program documentation error on 04/26/2021
JOG Class
NCR 02380090 2021 POV: BNP-E-8.013 and 8.014 Torque Calculation 04/27/2021
Error
NCR 02380224 DBAI POV UFSAR not Updated for AST 04/28/2021
NCR 02380258 2021 POV: Stem Lub. Degradation Term Requires 04/28/2021
Change
NCR 02380339 2021 POV: NRC POV DBAI SLC Sys Inclusion in EQ 04/28/2021
Prog
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 Rev. C
Control
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 14"-900 Weld Ends Carbon Steel Double Disc Gate Valve Rev. B
Sheet 1 with Limitorque SB-2-60 Actuator with Ballscrew
Assembly
0-FP-82805 SHT Units 1 & 2 Anchor/Darling Valve Company 6"-900 Rev. A
Double Disc Gate Valve
0-FP-85548 20 X 5 MSIV ACTUATOR Rev. 00E
SH0001
0-FP-85548 SHT 20 x 5 MSIV Actuator Rev. C
Inspection Type Designation Description or Title Revision or
Procedure Date
0-FP-85548 SHT 20 x 5 MSIV Actuator Ralph A. Hiller Company Rev. B
0-FP-85548 SHT 20 x 5 MSIV Actuator Rev. C
0-FP-85548 SHT 20 x 5 MSIV Actuator Rev. C
0-FP-85548 SHT 20 x 5 MSIV Actuator Rev. C
0-FP-87720 Crane 10 x 8 x 10 Sentinel Gate Valve 1-E41-F001/ 2- Rev. B
SH0001 E41-F001
0-FP-87747 SHT Limitorque Actuator Model No. SMB-2 Rev. A
0-FP-88781 PILOT CONTROL THREE VALVE MANIFOLD Rev. 00A
SH0001
1-FP-50017 Residual Heat Removal System Elementary Wiring Rev. 27
Diagram - Sht. 16
1-FP-55109 SHT NUCLEAR STEAM SUPPLY SHUT OFF SYSYTEM Rev. M
ELEMENTARY DIAGRAM
1-FP-55109, SH ELEM DIAG NUCLEAR STEAM SUPPLY SHUTOFF SYS Rev. M
UNIT 1
1-FP-81745 Reactor Building High Pressure Coolant Inject Limitorque Rev. 0
Valve Control-SMB-3 Unit No 1
2-FP-50056 Unit 2 Nuclear Steam Supply Shutoff System Elementary Rev. J
Diagram
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 Rev. B
List of Material
2-FP-81134 MSIV Limit Switch Bracket Detail Rev. A
BN-19.0.1 High Pressure Coolant Injection (HPCI) System Rev. 04
D-02040 CONDENSATE DEMINERALIZED WATER TRANSFER Rev. 041
SH0001A SYSTEMS PIPING DIAGRAM
D-02521 Reactor Building Nuclear Steam Supply System Piping Rev. 052
SH0001B Diagram
Inspection Type Designation Description or Title Revision or
Procedure Date
D-02523 SH0002 REACTOR BUILDING HIGH PRESSURE COOLANT Rev. 054
INJECTION SYSTEM PIPING DIAGRAM
D-02523 SHT 1 REACTOR BUILDING HIGH PRESSURE COOLANT Rev. 59
INJECTION SYSTEM PIPING DIAGRAM
D-02525 REACTOR BUILDING RESIDUAL HEAT REMOVAL Rev. 72
SH0001B SYSTEM PIPING DIAGRAM
D-02526 REACTOR BUILDING RESIDUAL HEAT REMOVAL Rev. 57
SH0002A SYSTEM PIPING DIAGRAM
D-02526 REACTOR BUILDING RESIDUAL HEAT REMOVAL Rev. 84
SH0002B SYSTEM PIPING DIAGRAM
D-02700 Reactor Building Instrument Air System Plan at 20' - 0" & Rev. 17
Sections - Sheet No. 2 Unit No. 2
D-04219 Nuclear Safety Capability Assessment High Press. Rev. 14
Coolant Injection System (HPCI)
D-07007 Reactor Building Instrument Air Supply System Piping Rev. 35
Diagram
D-25021 Reactor Building Nuclear Steam Supply System Piping Rev. 48
SH0001C Diagram
D-25023-SH0001 Reactor Building High Pressure Coolant Injection System Rev. 61
Piping Diagram
D-25023-SH0002 Reactor Building High Pressure Coolant Injection System Rev. 54
Piping Diagram
D-25026 Reactor Building Residual Heat Removal System Piping Rev. 72
Diagram - Sht. 0002B
D-25026 Reactor Building Residual Heat Removal System Piping Rev. 63
Diagram - Sht. 2A
D-25027 UNIT NO. 1 REACTOR BUILDING REACTOR WATER Rev. 47
SH0001B CLEAN-UP SYSTEM PIPING DIAGRAM
D-25045 REACTOR BUILDING DRYWELL DRAINS PIPING Rev. 42
SH0003A DIAGRAM
D-25047 Reactor Building Standby Liquid Control System Piping Rev. 34
Diagram
D-70029 Reactor Building Instrument Air Supply System Piping Rev. 38
SH0002A Diagram
Inspection Type Designation Description or Title Revision or
Procedure 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 Rev. 8
Containment Plan Below Elev. 38 ' - 4 & 45' - 0 Unit No. 2
Sheet No. 3
FS DW-25078 Piping Isometric- BLDG: Reactor System: Reactor Water Rev. 4
SHT 4 Cleanup Elev: 50'-0"
LL-09236 RHR Heat Exchanger "2A" Bypass Valve 2-E11-F048A Rev. 7
Control Wiring Diagram - Sht. 75
LL-09237 SHT 91 MCC "2XB"- COMPT. "2-DN6" RHR Suppression Pool Rev. 15
Suction Valve 2-E11-F020B Control Wiring Diagram
LL-09237 SHT MCC "2XB"- COMPT. "2-DN6" RHR Suppression Pool Rev. 3
91A Suction Valve 2-E11-F020B Control Wiring Diagram
LL-09272 SHT 31 MCC "2XDA" - COMPT. "2-B21" HPCI Steam Supply Rev. 13
Valve to Turbine 2-E41-F001 Control Wiring Diagram
LL-92037 MCC "1XB" Compt. "1-DL3" RHR Pump 1B Minimum Rev. 11
Flow Bypass Valve 1-E11-F007B Control Wiring Diagram
- Sht. 48
LL-92038 SHT 46 Unit No. 1' MCC "1XC" COMPT "1-DT9" RWCU Inboard Rev. 12
Isol Valve 1-G31-F001 Control Wiring Diagram
LL-92043 MCC "1XG" - Compartment "1-EG6" Standby Liquid Rev. 7
Control Pump 1A - 1-C41-C001A Control Wiring Diagram
- Sht. 18
LL-92072 SH. 23 Unit No. 1 MCC "1XDA" Compt "B17" HPCI Pump Rev. 13
Discharge Valve 1-E41-F006 Control Wiring Diagram
Engineering EC 250516 Unit 1 SLC Boron Concentration Change for EPUR Rev. 5
Changes EC 250522 SLC Squib Valve Shelf Plus Service Life Extension Rev. 0
EC 290843 Flowserve Anchor Darling Double-Disc Gate Valve wedge Rev. 0
pin
EC 294179 Replace E41-F001 with Crane Sentinel Valve Rev. 3
Inspection Type Designation Description or Title Revision or
Procedure Date
EC 295980 Change MSIV Function to Require Both Air and Spring to Rev. 0
Close
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 Rev. 0
Valves
EC 417109 EVALUATION OF PENETRATIONS AND VALVES Rev. 0
ELIGIBLE FOR APPENDIX J LOCAL LEAK RATE
TESTING EXCLUSION
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 Rev. 0
REPEATABILITY
ESR 98-00069 Replace Motor 1-G31-F001 to Increase Torque Rev. 1
Engineering 0BNP-TR-003 Motor Operated Valve (MOV) Scoping GL 89-10 And GL Rev. 3
Evaluations 96-05
0BNP-TR-006 Motor Operated Valve (MOV) Design Basis Information Rev. 8
2-B21-F022A Post Test Evaluation of AOV Diagnostics for 2-B21- 04/15/2015
PTE 2015 F022A, Test Date 3/19/15
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 MOV Post-Test Data Review Worksheet for 1-E41-F006 03/31/14
B120R1 PTE Test Date 03/08/14
2-B21-F022 CofC Certificate of Compliance from Rockwell 12/15/1970
2-E41-F001 Certification to Contract Specifications from Anchor Valve Undated
Certificate Company for 2-E41-F001
2-E41-F001 PTE MOV Post-Test Data Review Worksheet for 2-E41-F001 03/29/19
Test Date 03/24/19
248-118 GATE, GLOBE AND CHECK VALVES Rev. 5
248-163 PROCUREMENT OF MAIN STEAM ISOLATION Rev. 003
VALVES
Inspection Type Designation Description or Title Revision or
Procedure Date
50-325/00-02 and NRC Integrated Inspection Report Nos. 50-325/00-02 and 04/25/2000
50-324/00-02 50-324/00-02
93164-01 Motor Operated Valve (MOV) Structural & Weak Link Rev. 0
Evaluation - Methodology
9811020153 Generic Letter 96-05, "Periodic Verification of Design 10/27/1998
Basis Capability of Safety-Related Motor-Operated
Valves" Commitment to Topical Report NEDC-32719,
Revision 2
BSEP 01-0009 Generic Letter 89-10 Motor-Operated Valve Program 01/15/2001
Status After Completion of Committments
BSEP 01-0063 Request for License Amendments Alternative 08/01/2001
Radiological Source Term
BSEP 01-0166 Response to Request for Additional Information 03/12/2002
Regarding Request for License Amendments - Extended
BSEP 06-0051 Response to the NRC Generic Letter 95-07, "Pressure 02/13/1996
Locking and Thermal Binding of Safety-Related Power-
Operated Gate Valves"
BSEP 16-0056 Request for License Amendment Regarding Core Flow 09/06/2016
(ML16257A418) Operating Range Expansion
BSEP 97-0408 Generic Letter 89-10 Motor-Operated Valve Program 10/02/1997
Status
BSEP 98-0058 Generic Letter 89-10 Motor-Operated Valve Program 02/20/1998
Commitments Related to Program Closure
BSEP-00-0194 Response to Request for Additional Information 12/20/1999
Regarding Generic Letter 96-05, "Periodic Verification of
Design-Basis Capability of Safety-Related Power-
Operated Valves"
BWROG-8727 GE Licensing Topical Report NEDE-31096-P-A and 06/12/1987
NEDE-31096-A, "Anticipated Transients Without SCRAM
Response to NRC ATWS Rule, 10CFR50.62",Dated
February 1987
CSD-EG-BNP- BNP IST Program Plan - 5th Interval Rev. 2
20
Inspection Type Designation Description or Title Revision or
Procedure 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 Design Basis for Engineered Safety Features and 03/29/1972
Nos. 12 and 13 Generation and Consequences of Turbine Missiles
DR 17.1 Qualification of EA740 Series Limit Switches for Use in Rev. 0
Nuclear Power Plants in Compliance with IEEE Standards
23-1974, 382-1972 and 344-1975
DR 17.4 Supplement 02 to QTR111 Generic Qualification of Series Rev. 0
EA740 Limit Switches: Qualification By Similarity
Presentation to Support the Change of Contact Block/
Carrier Material
DR 257 LIMITORQUE CORPORATION REPORT No. B0212 Rev. 0
NUCLEAR POWER STATION QUALIFICATION TYPE
TEST FOR LIMITORQUE VALVE ACTUATORS WITH
TYPE LR MOTOR FOR WESTINGHOUSE PWR
DR 265 General Electric Test Report No. NEDC-31344 Rev. 0
Environmental Qualification Report on MSIV Limit
Switches for Nine Mile Point Nuclear Station Unit 2
DR 274 General Electric Report No. NEDC 32370P Environmental Rev. 1
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
DR 4.3 Final Report on the Evaluation of the Qualification of the Rev. A
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
DR 80.1 NAMCO REPORT QTR 140-GENERIC QUALIFICATION Rev. 002
OF SERIES EA 740 SWITCHES (WITH SUPPLEMENT)
Inspection Type Designation Description or Title Revision or
Procedure Date
DR 80.9 NAMCO TEST REPORT NO. QTR 180: GENERIC Rev. 001
QUALIFICATION OF EA 740-SERIEW LIMIT SWITCHES
FOR USE IN NUCLEAR POWER PLANT CLASS 1E
APPLICATIONS
DR-259 General Electric Test Report NEDC-31051 Rev. 0
River Bend Station Unit 1 Environmental Qualification
Report (NUREG 0588, Category 1) Volumes 1 & 2
EPRI TR-103232 EPRI MOV Performance Prediction Program Stem Thrust dated
Prediction Method for Anchor/Darling Double Disc Gate November
Valves 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 Rev. G
DISC VALVES
FP-87721 CRANE SENTINEL BOLTED BONNET GATE VALVE Rev. A
GE 21A9230 Procurement and Design Specification GE Main Steam Rev. 2
Isolation Valves
LDCR 03FSAR- E41-F042 PCIV Function Update dated
040 02/04/2004
M20205F215 Response to Request for Additional Information 03/31/1999
Regarding Generic Letter 95-07, "Pressure Locking and
Thermal Binding of Safety-Related Power-Operated Gate
Valves" (TAC Nos. M93439 and M93440)
ML003711034 Safety Evaluation of Licensee Response to Generic Letter 05/03/2000
96-05, Brunswick Steam Electric Plant, Unit Nos. 1 and 2
(TAC M97023 and M97024)
ML003712627 Brunswick 1 and 2 - Completion of Licensing Action for 05/08/2000
Generic Letter 96-05, "Periodic Verification of Design-
Basis Capability of Safety-Related Motor-Operated
Valves" (TAC Nos. M97023 and M97024)
ML14178B034 Revised Date for Completion of NEI Initiative Addressed 04/10/1997
in NE 96-05
Inspection Type Designation Description or Title Revision or
Procedure Date
ML14188A815 Supplemental Response to Generic Letter 89-10: 06/06/1991
Clarifications on Motor-Operated Valve Program
ML20014D829 Second Request for Additional Information - Generic 12/04/1998
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)
ML20065S582 Response to NRC Generic Letter 89-10, Supplement 3 12/17/1990
ML20072N412 Generic Letter 89-10: Motor-Operated Valves 08/23/1994
ML20073M613 US NRC Inspection Report Nos. 50-325/94-20 and 50- 09/21/1994
24/94-20
ML20076M985 Supplemental Response to NRC Generic Letter 89-10, 03/20/1991
Supplement 3
ML20077G551 Request for Additional Information Re: Generic Letter 06/25/1991
(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)
ML20086P598 Inspection Report: 50-325/91-31 and 50-324/91-31 12/12/1991
ML20091B821 Response to NRC Request for Additional Information 07/29/1991
Regarding CP&L Response to NRC Generic Letter 89-10,
Supplement 3
ML20092M512 File: B09-12510C, Response to NRC Inspection 91-31 02/24/1992
ML20093K310 Response to the NRC Staff Request for Information 10/16/1995
Regarding NRC Generic Letter 95-07, "Pressure Locking
and Thermal Binding of Safety-Related Power Operated
Gate Valves"
ML20095C924 Response to the NRC Staff Request for Information 12/06/1995
Within 180 Days for NRC Generic Letter 95-07, "Pressure
Locking and Thermal Binding of Safety-Related Power-
Operated Gate Valves"
ML20107L516 Response to the NRC Generic Letter 95-07, "Pressure 04/26/1996
Locking and Thermal Binding of Safety-Related Motor-
Operated Gate Valves"
Inspection Type Designation Description or Title Revision or
Procedure Date
ML20113B086 Response to NRC Generic Letter 95-07, "Pressure 06/20/1996
Locking and Thermal Binding of Safety-Related Motor-
Operated Gate Valves"
ML20117G371 Request for Additional Information - Generic Letter 95-07, 05/16/1996
"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)
ML20134N054 Response to Generic Letter 96-05, "Periodic Verification 11/18/1996
of Design-Basis Capability of Safety-Related Valves"
ML20136H370 Request of Additional Information Regarding Generic 02/25/1999
Letter 96-05 Program at Brunswick (TAC Nos. M97023
and M97024)
ML20137C040 Response to NRC Generic Letter 96-05, "Periodic 03/17/1997
Verification of Design-Basis Capability of Safety-Related
Motor-Operated Valves"
ML20198L044 Request for Additional Information Regarding Generic 12/21/1998
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)
ML20199C227 NRC Integrated Inspection Report Nos. 50-325/97-11 50- 10/27/1997
24/97-11 Notice of Violation
ML20202E432 1998 BSEP Generic Letter 89-10 Motor-Operated Valve 01/27/1999
Program "End-of-Year" Status
ML20216H288 NRC Integrated Inspection Report Nos 50-325/98-03, 50- 04/13/1998
24/98-03
ML993160030 Response to Request for Additional Information 11/03/1999
Regarding Generic Letter 95-07, "Pressure Locking and
Thermal Binding of Safety-Related Power-Operated Gate
Valves" (TAC Nos. M93439 and M93440)
ML993250087 Safety Evaluation of Licensee Response to Generic Letter 11/10/1999
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
Inspection Type Designation Description or Title Revision or
Procedure Date
M93440)
ML993410457 Safety Evaluation of Response to Generic Letter 95-07, 12/03/1999
"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)
MOV Stem INEEL Presentation dated
Lubricant Aging 01/15/2003
Research
NUREG/CP- EPRI MOV Stem Lubricant Test Program, Frictional NUREG/CP-
0152, Volume 5 Performance of Exxon Nebula and MOV Long Life in a 0152,
Stem Lubrication Application, John Hosler Volume 5
QDP 103 MAIN STEAM ISOLATION VALVE (MSIV) SOLENOID Rev. 011
VALVE CLUSTER ASSEMBLY WITH AVC SOLENOID
VALVES
QDP 29B LIMITORQUE MOTOR OPERATED VALVES (MOVS) Rev. 14
WITH CLASS H (TYPE RH) INSULATED DC MOTORS
QDP 48 NAMCO EA740 SERIES LIMIT SWITCHES Rev. 016
RA-17-0053 Anchor Darling Double Disc Gate Valve Information and 12/20/2017
Status
RAL-1029 Design Report for Carolina Power and Light Co. Rev. 4
Brunswick Units 1 and 2 Size 24 x 20 x 24 Fig. 1612
JMMNY Main Steam Isolation Valve
Rate of Loading 2003 MUG Presentation dated 2003
Flowserve Test
Program
SD-19 HIGH PRESSURE COOLANT INJECTION (HPCI) Rev. 025
SYSTEM
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 Rev. 3
A61-B
0CM-MO500 Repair Instructions for Model SMB-5T Limitorque Motor Rev. 15
Operator
0CM-MO501 Limitorque Model Numbers SMB-0 Through 4, SMB-4T, Rev. 28
Inspection Type Designation Description or Title Revision or
Procedure Date
and SB-0 Through SB-4
0CM-MO502 Repair Instructions for Limitorque Motor Operators Model Rev. 24
Number SMB-000
0CM-MO503 Limitorque Motor Operators Model Number SMB-00 and Rev. 19
SB-00
0CM-MO506 Limitorque Operator Types HBC-0 Through HBC-6 Rev. 20
0CM-MO507 Removal and Installation of SMB/SB Type Limitorque Rev. 24
Operators
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 Rev. 21
Preventative Maintenance Procedure
0PM-MO504 Mechanical Inspection and Lubrication of Limitorque Rev. 46
Operators
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 Rev. 32
TEST
0PT-12/1A 006A No. 1 Diesel Generator LOOP/LOCA Loading Test Rev. 0
0PT-14.6 REACTOR WATER CLEANUP SYSTEM OPERABILITY Rev. 33
TEST 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 Rev. 038
Valve Operability Test
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 Type Designation Description or Title Revision or
Procedure Date
AD-EG-ALL-1202 Preventive Maintenance and Surveillance Testing Rev. 10
Administration
AD-EG-ALL-1415 Motor Operated Valve Performance Prediction, Actuator Rev. 0
Settings, and Diagnostic Test Data Reconciliation
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 Rev. 2
in Accordance with 10 CFR 21
AD-PI-ALL-0100 Corrective Action Program Rev. 25
BNP-PSA-104 BNP Air-Operated Valve, Motor-Operated Valve, and Rev. 0
Check Valve PRA Risk Significance
CSD-EG-BNP- BNP IST Program Plan - 5th Interval Rev. 2
20
CSD-EG-DEP- Electrical Calculation of Motor Output Torque for AC and Rev. 0
0101 DC Motor Operated Valves (MOVs)
CSD-EG-DEP- Motor Operated Valve Structural Evaluation Rev. 0
0359
EGR-NGGC-0101 Electrical Calculation of Motor Output Torque for AC and Rev. 4
DC Motor Operated Valves (MOVs)
MNT-NGGC-0010 Installation and Use of Teledyne/ Quiklook Equipment for Rev. SUP
MOV Diagnostic Testing
OENP-646 POST TEST EVALUATION OF AOV DIAGNOSTICS, 1- Rev. 3,
G16-F020 B1R23 (2020) 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 Type Designation Description or Title Revision or
Procedure Date
Diagnostic Test Instruction Development, and Test Data
Evaluation/Trending
TE-MN-ALL-0100 Installation and Use of Teledyne / Quiklook Equipment for Rev. 1
MOV Diagnostic Testing
TE-MN-ALL-0101 Installation of Teledyne Quikstem Sensors (QSS), Rev. 1
Smartstems and Easy Torque Thrust Sensors (ETT)
Work Orders WO 20026517,
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 Type Designation Description or Title Revision or
Procedure Date
10, WO 20029439 -01,
23