IR 05000324/2021011: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:June 2, 2021
{{#Wiki_filter:
 
==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) ===
{{IP sample|IP=IP 71111.21|count=9}}
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
MOVs
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
TRANSIENT
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,
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 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
GL 89-10 & GL 96-05
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
Power Uprate
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,
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 Type Designation  Description or Title Revision or
Procedure                                          Date
10, WO
20029439 -01,
WO 20176606,
WO 20340163,
WO 20438847
23
}}
}}

Revision as of 10:49, 22 June 2021

Design Basis Assurance Inspection (Programs) Inspection Report 05000324/2021011 and 05000325/2021011
ML21154A045
Person / Time
Site: Brunswick  Duke Energy icon.png
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