IR 05000259/2021010: Difference between revisions

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Sincerely,
Sincerely,
/RA/
/RA/  
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68
 
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety  
 
Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68  


===Enclosure:===
===Enclosure:===
As stated
As stated  


==Inspection Report==
==Inspection Report==
Docket Numbers: 05000259, 05000260 and 05000296 License Numbers: DPR-33, DPR-52 and DPR-68 Report Numbers: 05000259/2021010, 05000260/2021010 and 05000296/2021010 Enterprise Identifier: I-2021-010-0038 Licensee: Tennessee Valley Authority Facility: Browns Ferry Nuclear Plant Location: Athens, AL Inspection Dates: May 17, 2021 to June 11, 2021 Inspectors: C. Baron, Contractor D. Bollock, Senior Reactor Operations Engineer W. Deschaine, Senior Resident Inspector S. Kobylarz, Contractor R. Patterson, Senior Reactor Inspector J. Winslow, Reactor Systems Engineer Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
Docket Numbers:
05000259, 05000260 and 05000296  
 
License Numbers:
DPR-33, DPR-52 and DPR-68  
 
Report Numbers:
05000259/2021010, 05000260/2021010 and 05000296/2021010  
 
Enterprise Identifier: I-2021-010-0038  
 
Licensee:
Tennessee Valley Authority  
 
Facility:
Browns Ferry Nuclear Plant  
 
Location:
Athens, AL  
 
Inspection Dates:
May 17, 2021 to June 11, 2021  
 
Inspectors:
C. Baron, Contractor  
 
D. Bollock, Senior Reactor Operations Engineer  
 
W. Deschaine, Senior Resident Inspector  
 
S. Kobylarz, Contractor  
 
R. Patterson, Senior Reactor Inspector  
 
J. Winslow, Reactor Systems Engineer  
 
Approved By:
James B. Baptist, Chief
Engineering Branch 1
Division of Reactor Safety  


=SUMMARY=
=SUMMARY=
Line 45: Line 87:


===List of Findings and Violations===
===List of Findings and Violations===
No findings or violations of more than minor significance were identified.
No findings or violations of more than minor significance were identified.


Line 58: Line 99:


==REACTOR SAFETY==
==REACTOR SAFETY==
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)


===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
(1)250V DC Reactor Motor Operated Valve (RMOV) Board 2B
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)
: (1) 250V DC Reactor Motor Operated Valve (RMOV) Board 2B
* Material condition and configuration (e.g., visual inspection during a walkdown)
* Material condition and configuration (e.g., visual inspection during a walkdown)
* Operating environment
* Operating environment
Line 78: Line 122:
* Normal and emergency operating procedures
* Normal and emergency operating procedures
* Modifications
* Modifications
* Completed surveillance tests to ensure acceptance criteria have been met
* Completed surveillance tests to ensure acceptance criteria have been met  
: (3) 480V RMOV BD 2D
 
(3)480V RMOV BD 2D
* Material condition and configuration (e.g., visual inspection during a walkdown)
* Material condition and configuration (e.g., visual inspection during a walkdown)
* Operating environment
* Operating environment
Line 100: Line 145:
* Evaluation of RCIC Pump Suction Transfer
* Evaluation of RCIC Pump Suction Transfer
* Material Condition of Pump and Associated Equipment
* Material Condition of Pump and Associated Equipment
* Corrective Action History Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
* Corrective Action History  
 
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
{{IP sample|IP=IP 71111.21|count=1}}
{{IP sample|IP=IP 71111.21|count=1}}
: (1) Unit 2 Automatic Depressurization System (ADS) Valves
: (1) Unit 2 Automatic Depressurization System (ADS) Valves
Line 109: Line 156:
* Evaluation of Electrical Control and Power Supplies
* Evaluation of Electrical Control and Power Supplies
* Evaluation of Testing of Backup Electrical Control and Power Supplies
* Evaluation of Testing of Backup Electrical Control and Power Supplies
* Corrective Action History
* Corrective Action History  


===Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
===Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
Line 117: Line 164:
: (4) DCN 69466A, Replace Core Spray and Residual Heat Removal Room Cooler Fan Motors, Fans, and Shafts
: (4) DCN 69466A, Replace Core Spray and Residual Heat Removal Room Cooler Fan Motors, Fans, and Shafts
: (5) BFN-1-2020-068-003, Temporary Replacement of Recirculation Loop 1B Flow Measurement (T-Mod)
: (5) BFN-1-2020-068-003, Temporary Replacement of Recirculation Loop 1B Flow Measurement (T-Mod)
: (6) DCN 70747-71, 480V RMOV BD 2A/15D ALT FDR from SD BD
: (6) DCN 70747-71, 480V RMOV BD 2A/15D ALT FDR from SD BD  


===Review of Operating Experience Issues (IP Section 02.06) (2 Samples)===
===Review of Operating Experience Issues (IP Section 02.06) (2 Samples)===
Line 132: Line 179:
=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


Inspection Type       Designation     Description or Title                                   Revision or
Inspection
Procedure                                                                                      Date
Procedure
71111.21M Calculations BFN-1-47E859-1   Flow Diagram, Emergency Equipment Cooling Water         Rev. 99
Type
CDQ-0067-881511 Seismic Qualification for the Automatic Self-Cleaning   Rev. 1
Designation
Description or Title
Revision or
Date
71111.21M Calculations
BFN-1-47E859-1
Flow Diagram, Emergency Equipment Cooling Water
Rev. 99
CDQ-0067-881511
Seismic Qualification for the Automatic Self-Cleaning
Strainer
Strainer
CDQ-0067894672   Evaluation and Review of Small Bore Unit 0 Piping and   Rev. 12
Rev. 1
CDQ-0067894672
Evaluation and Review of Small Bore Unit 0 Piping and
Supports within the Scope of the System 067 Safe
Supports within the Scope of the System 067 Safe
Shutdown Boundary
Shutdown Boundary
CDQ-1067895300   Pipe Stress Analysis of Stress Problem No. 1-67-859-1- Rev. 3
Rev. 12
CDQ-2067890748   Strainer Backwash Blowdown Piping at Pumping Station   Rev. 2
CDQ-1067895300
CDQ0303880436   Assess the RHRSW and the EECW Piping and               Rev. 2
Pipe Stress Analysis of Stress Problem No. 1-67-859-1-
Components for the Affects of Tornadic Wind- RHRSW
Rev. 3
CDQ-2067890748
Strainer Backwash Blowdown Piping at Pumping Station
Rev. 2
CDQ0303880436
Assess the RHRSW and the EECW Piping and
Components for the Affects of Tornadic Wind-RHRSW
Pump
Pump
CDQ0999910005   Evaluation of Seismic- Induced Spray Hazards at BFN,   Rev. 3
Rev. 2
CDQ0999910005
Evaluation of Seismic-Induced Spray Hazards at BFN,
Unit 2 and Common
Unit 2 and Common
CDQ107320021062 Small Bore Piping and Supports Program System           Rev. 6
Rev. 3
CDQ107320021062
Small Bore Piping and Supports Program System
Calculation for Seismic Class 1 HPCI System (73) Piping
Calculation for Seismic Class 1 HPCI System (73) Piping
CDQ107320031063 Pipe Stress Analysis of Stress Problem N1-173-67R       Rev. 1
Rev. 6
EDQ0057920034   4.16KV and 480V Busload, Voltage Drop and Short         Rev. 92
CDQ107320031063
Pipe Stress Analysis of Stress Problem N1-173-67R
Rev. 1
EDQ0057920034
4.16KV and 480V Busload, Voltage Drop and Short
Circuit Calculation
Circuit Calculation
EDQ024820020042 250V DC Unit Battery Load Study                         Rev. 91
Rev. 92
EDQ2000870054   Control Circuit Voltage Drop Calculations - 250V DC     Rev. 43
EDQ024820020042
250V DC Unit Battery Load Study
Rev. 91
EDQ2000870054
Control Circuit Voltage Drop Calculations - 250V DC
circuits
circuits
EDQ2000870550   Cable and Bus Protection/Breaker/Fuse Coordination for Rev. 54
Rev. 43
EDQ2000870550
Cable and Bus Protection/Breaker/Fuse Coordination for
250V DC System
250V DC System
EDQ2092900118   Setpoint and Scaling Calculation for Neutron Monitoring Rev. 37
Rev. 54
EDQ2092900118
Setpoint and Scaling Calculation for Neutron Monitoring
System & Recirculation Flaw Loops
System & Recirculation Flaw Loops
EDQ2999870549   Power Cable Protection Analysis for 480V MCCs           Rev. 54
Rev. 37
EQD29998801715   Thermal Overload Heater Calculation                     Rev. 50
EDQ2999870549
MD-N0026-910163 Combustible Load Table                                 Rev. 71
Power Cable Protection Analysis for 480V MCCs
MDQ-             MOV 0-FCV-067-0001/0005/0008/0011, Operator             Rev. 1
Rev. 54
0000672019000460 Requirements and Capabilities
EQD29998801715
MDQ-0067890059   Analytical Limits for the EECW Strainers and Strainer   Rev. 2
Thermal Overload Heater Calculation
Inspection Type             Designation         Description or Title                                 Revision or
Rev. 50
Procedure                                                                                              Date
MD-N0026-910163
Combustible Load Table
Rev. 71
MDQ-
0000672019000460
MOV 0-FCV-067-0001/0005/0008/0011, Operator
Requirements and Capabilities
Rev. 1
MDQ-0067890059
Analytical Limits for the EECW Strainers and Strainer
Rev. 2  
 
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drain Valves Start/Stop Controls
Drain Valves Start/Stop Controls
MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis         Rev. 3
MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis  
                                                (Pump Water Suction and Discharge)
(Pump Water Suction and Discharge)
MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS   Rev. 0
Rev. 3
MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS
Piping
Piping
MDQ0032870288       Control Air Volume and Wall Thickness of Accumulators Rev. 14
Rev. 0
MDQ0071910235       Reactor Core Isolation Cooling System Design         Rev. 12
MDQ0032870288
Control Air Volume and Wall Thickness of Accumulators
Rev. 14
MDQ0071910235
Reactor Core Isolation Cooling System Design
Pressure/Temperature
Pressure/Temperature
MDQ099920040034     Setpoint Controls Parameters Review Calculation for   Rev. 17
Rev. 12
MDQ099920040034
Setpoint Controls Parameters Review Calculation for
BFN Category 2 Air Operated Valves (AOVs)
BFN Category 2 Air Operated Valves (AOVs)
MDQ099920040040     HPCI and RCIC Test Requirements                       Rev. 11
Rev. 17
NDN00099920070032   BFN Probablistic Risk Assessment - Human Reliability Rev. 8
MDQ099920040040
HPCI and RCIC Test Requirements
Rev. 11
NDN00099920070032
BFN Probablistic Risk Assessment - Human Reliability
Analysis
Analysis
Corrective Action 0044691
Rev. 8
Documents        0128951
Corrective Action
Documents
0044691
28951
0175232
0175232
200183
200183
Line 200: Line 312:
27370
27370
1638651
1638651
1655591
1655591  
Inspection Type             Designation Description or Title                                 Revision or
 
Procedure                                                                                    Date
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1656541
1656541
1656544
1656544
Line 214: Line 332:
1688353
1688353
1695185
1695185
201387
201387  
21012
 
1434874
21012  
1435350
 
1613271
1434874  
Corrective Action 1695185     A3 RHRSW Lube Oil Strainer Sight Glass
 
Documents        1695266     Control of HPCI and RCIC System Flow Controller
1435350  
Resulting from                Settings
 
Inspection        1695742     Danger sign was identified on the top of 480V RMOV
1613271  
 
Corrective Action
Documents
Resulting from
Inspection
1695185
A3 RHRSW Lube Oil Strainer Sight Glass
1695266
Control of HPCI and RCIC System Flow Controller
Settings
1695742
Danger sign was identified on the top of 480V RMOV
Board 2D
Board 2D
1695748     Review and Evaluate Unit 2 RCIC System CQS Test
1695748
Review and Evaluate Unit 2 RCIC System CQS Test
Results
Results
1695790     NRC DBAI Inspection - Minor Correction Needed on
1695790
NRC DBAI Inspection - Minor Correction Needed on
FPPCIS for ECP 71425
FPPCIS for ECP 71425
1695802     NRC DBAI 2021 Inspection - Correction Needed to 1/2-
1695802
NRC DBAI 2021 Inspection - Correction Needed to 1/2-
ARP-9-23A/B/C/D and 0-ARP-25-41A/B/C/D
ARP-9-23A/B/C/D and 0-ARP-25-41A/B/C/D
1696259     Pipe Wrench Laying on Top of the C# EECW Strainers
1696259
Pipe Wrench Laying on Top of the C# EECW Strainers
Gearbox01
Gearbox01
1696423     NRC DBAI Inspection - Incorrect M&TE Number
1696423
NRC DBAI Inspection - Incorrect M&TE Number
Documented in WO 116092256
Documented in WO 116092256
1696542     250V Reactor MOV Board 2B board is missing 3
1696542
250V Reactor MOV Board 2B board is missing 3
finishing plugs
finishing plugs
1696552     480V Reactor MOV board 2A missing 1 finishing plug
1696552
Inspection Type     Designation   Description or Title                                     Revision or
480V Reactor MOV board 2A missing 1 finishing plug  
Procedure                                                                                  Date
 
1696556       480V Reactor MOV board 2D remove RTV from
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1696556
480V Reactor MOV board 2D remove RTV from
Finishing Plug hole and install Finishing Plug
Finishing Plug hole and install Finishing Plug
1696713       Request PCRs for RCIC Flowrate Procedures
1696713
1698638       MDQ0071910235 Evaluation Didnt Account for
Request PCRs for RCIC Flowrate Procedures
1698638
MDQ0071910235 Evaluation Didnt Account for
Tolerance
Tolerance
1699579       Fire seal label is required at the S25932501 penetration
1699579
Fire seal label is required at the S25932501 penetration
per MAI-3.4A and is missing
per MAI-3.4A and is missing
1699961       Fire Seal Penetration R26395139 not conforming to
1699961
Fire Seal Penetration R26395139 not conforming to
design output drawing 0-45E830-27
design output drawing 0-45E830-27
1699971       Fire Seal Penetration R36395359 not conforming to
1699971
Fire Seal Penetration R36395359 not conforming to
design output drawing 0-45E830-27
design output drawing 0-45E830-27
1700011       DP Between RCIC Pump Discharge and RPV
1700011
1700151       Response to RCIC Overspeed
DP Between RCIC Pump Discharge and RPV
1700334       RCIC Surveillance Procedure Non-Conservative with
1700151
Response to RCIC Overspeed
1700334
RCIC Surveillance Procedure Non-Conservative with
Respect to TS
Respect to TS
1700335       NRC Observation Recirc Temp Mod
1700335
Drawings 0-45E830-27   Conduit & Grounding Cable Trays Fire Stop Dets-SH 14     Rev. 7
NRC Observation Recirc Temp Mod
0-47E392-1   Fire Protection - 10 CFR 50 - NFPA 805 Penetration       Rev. 5
Drawings
0-45E830-27
Conduit & Grounding Cable Trays Fire Stop Dets-SH 14
Rev. 7
0-47E392-1
Fire Protection - 10 CFR 50 - NFPA 805 Penetration
Seal Tabular Drawings General Notes and Legend
Seal Tabular Drawings General Notes and Legend
0-47E840-3   Flow Diagram, Fuel Oil System                           Rev. 27
Rev. 5
0-731E700     One Line Diagram of DC & Instrument Control AC           Rev. 8
0-47E840-3
Flow Diagram, Fuel Oil System
Rev. 27
0-731E700
One Line Diagram of DC & Instrument Control AC
Systems
Systems
1-45E751-3   Wiring Diagram, 480V Reactor MOV Board 1B               Rev. 43
Rev. 8
2-45E712-2   Wiring Diagram 250V Reactor MOV BD 2B Single Line       Rev. 35
1-45E751-3
2-47E610-1-1 Mechanical Control Diagram - Main Steam System           Rev. 43
Wiring Diagram, 480V Reactor MOV Board 1B
2-47E610-71-1 Mechanical Control Diagram - RCIC System                 Rev. 45
Rev. 43
2-47E610-71-2 Mechanical Control Diagram - RCIC System                 Rev. 7
2-45E712-2
2-47E801-1   Flow Diagram - Main Steam                               Rev. 34
Wiring Diagram 250V Reactor MOV BD 2B Single Line
2-47E813-1   Flow Diagram - Reactor Core Isolation Cooling System     Rev. 60
Rev. 35
2-47W2392-702 Fire Protection - 10 CFR 50 Appendix R Penetration       Rev. 1
2-47E610-1-1
Mechanical Control Diagram - Main Steam System
Rev. 43
2-47E610-71-1
Mechanical Control Diagram - RCIC System
Rev. 45
2-47E610-71-2
Mechanical Control Diagram - RCIC System
Rev. 7
2-47E801-1
Flow Diagram - Main Steam
Rev. 34
2-47E813-1
Flow Diagram - Reactor Core Isolation Cooling System
Rev. 60
2-47W2392-702
Fire Protection - 10 CFR 50 Appendix R Penetration
Seal Location Drawings Plan View Area I
Seal Location Drawings Plan View Area I
2-47W2392-708 Fire Protection - 10 CFR 50 Appendix R Penetration       Rev. 1
Rev. 1
2-47W2392-708
Fire Protection - 10 CFR 50 Appendix R Penetration
Seal Location Drawings EL 639
Seal Location Drawings EL 639
Inspection Type         Designation           Description or Title                                 Revision or
Rev. 1
Procedure                                                                                          Date
 
2-47W2392-716         Fire Protection - 10 CFR 50 Appendix R Penetration   Rev. 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-47W2392-716
Fire Protection - 10 CFR 50 Appendix R Penetration
Seal Tabular Drawings EL 639
Seal Tabular Drawings EL 639
2-730E929-2           Automatic Blowdown System                           Rev. 24
Rev. 3
2-730E929-3           Elementary Diagram - Automatic Blowdown System       Rev. 16
2-730E929-2
2-730E929-4           Automatic Blowdown System                           Rev. 18
Automatic Blowdown System
BFN-0-47E610-67-2     Mechanical Control Diagram, Emergency Equipment     Rev. 38
Rev. 24
2-730E929-3
Elementary Diagram - Automatic Blowdown System
Rev. 16
2-730E929-4
Automatic Blowdown System
Rev. 18
BFN-0-47E610-67-2
Mechanical Control Diagram, Emergency Equipment
Cooling Water
Cooling Water
BFN-1-47E610-67-1     Mechanical Control Diagram, Emergency Equipment     Rev. 50
Rev. 38
BFN-1-47E610-67-1
Mechanical Control Diagram, Emergency Equipment
Cooling Water
Cooling Water
BFN-1-47E812-1-CC     Flow Diagram, High Pressure Coolant Injection System Rev. 48
Rev. 50
BFN-2-45E751-1       Wiring Diagram 480V Reactor MOV BD 2A Single Line   Rev. 068
BFN-1-47E812-1-CC
BFN-2-45E751-8       Wiring Diagram 480V Reactor MOV BD 2D Single Line   Rev. 2
Flow Diagram, High Pressure Coolant Injection System
BFN-2-47E812-1-CC     Flow Diagram, High Pressure Coolant Injection System Rev. 77
Rev. 48
BFN-3-47E812-1-CC,   Flow Diagram, High Pressure Coolant Injection System Rev. 73
BFN-2-45E751-1
Engineering   DCN 72338-03         Replacement of 4160V/480V Emergency Shutdown
Wiring Diagram 480V Reactor MOV BD 2A Single Line
Changes                            Board 2A & 2B Transformer
Rev. 068
EC 71425             Upgrade Unit 1/2 DG Fuel Oil Piping Configuration   Rev. A
BFN-2-45E751-8
Miscellaneous                       System Health Report Scorecard for RHRSW and
Wiring Diagram 480V Reactor MOV BD 2D Single Line
EECW (April 2020-September 2020)
Rev. 2
BFN-2-47E812-1-CC
Flow Diagram, High Pressure Coolant Injection System
Rev. 77
BFN-3-47E812-1-CC,
Flow Diagram, High Pressure Coolant Injection System
Rev. 73
Engineering
Changes
DCN 72338-03
Replacement of 4160V/480V Emergency Shutdown
Board 2A & 2B Transformer
EC 71425
Upgrade Unit 1/2 DG Fuel Oil Piping Configuration
Rev. A
Miscellaneous
System Health Report Scorecard for RHRSW and
EECW (April 2020-September 2020)  
 
System Health Report Scorecard for RHRSW and
System Health Report Scorecard for RHRSW and
EECW (October 2020-March 2021)
EECW (October 2020-March 2021)  
Vendor Letter, Instructions for Changing Assembly of dated
 
DSMM40A Reducer                                     03/12/02
Vendor Letter, Instructions for Changing Assembly of
DSMM40A Reducer
dated
03/12/02
System Health Report Scorecard for RHRSW and
System Health Report Scorecard for RHRSW and
EECW (October 2019-March 2020)
EECW (October 2019-March 2020)
0-SI-4.5.C.1(A3-COMP) RHRSW Pump A3 IST Comprehensive Pump Test           Rev. 16
0-SI-4.5.C.1(A3-COMP)
0-TI-444             Augmented Inservice Testing Program                 Rev. 12
RHRSW Pump A3 IST Comprehensive Pump Test
0-TI-641             Time Critical Operator Actions                       Rev. 0
Rev. 16
0048-0051-LTR-002     BFN HPCI System Waterhammer Evaluation               Rev. 0
0-TI-444
0048-0065-RPT-001     HPCI and RCIC Systems Overpressure Transient         Rev. 0
Augmented Inservice Testing Program
Rev. 12
0-TI-641
Time Critical Operator Actions
Rev. 0
0048-0051-LTR-002
BFN HPCI System Waterhammer Evaluation
Rev. 0
0048-0065-RPT-001
HPCI and RCIC Systems Overpressure Transient
Technical Review and Development of Mitigation
Technical Review and Development of Mitigation
Options
Options
70747-71             480V RMOV BD 2A/15D ALT FDR from SD BD               Rev. A
Rev. 0
Inspection Type Designation             Description or Title                                   Revision or
70747-71
Procedure                                                                                      Date
480V RMOV BD 2A/15D ALT FDR from SD BD
BFN-1-2020-068-003     Rev. 0
Rev. A  
BFN-19-918             U1, U2, and U3 HPCI Gland Seal CKV Addition             Rev. 1
 
BFN-19-918-1           U1 HPCI Gland Seal CKV Addition                         Rev. 0
Inspection
BFN-50-7071             Design Criteria - Reactor Core Isolation Cooling System Rev. 23
Procedure
BFN-50-7200C           Design Basis Document for the 250V DC Power             Rev. 8
Type
Designation
Description or Title
Revision or
Date
BFN-1-2020-068-003
Rev. 0
BFN-19-918
U1, U2, and U3 HPCI Gland Seal CKV Addition
Rev. 1
BFN-19-918-1
U1 HPCI Gland Seal CKV Addition
Rev. 0
BFN-50-7071
Design Criteria - Reactor Core Isolation Cooling System
Rev. 23
BFN-50-7200C
Design Basis Document for the 250V DC Power
Distribution System
Distribution System
BFN-50-720D, 480V       480V Auxiliary System                                  Rev. 12
Rev. 8
BFN-50-720D, 480V
Auxiliary System
Auxiliary System
BFN-VTD-D088-0010       Installation, Operation and Maintenance for Delroyd     Rev. 2
480V Auxiliary System
Rev. 12
BFN-VTD-D088-0010
Installation, Operation and Maintenance for Delroyd
Double Worm Gear Speed Reducers
Double Worm Gear Speed Reducers
BFN-VTD-G080-1440       Vendor Document - Instructions Installation and         Rev. 2
Rev. 2
BFN-VTD-G080-1440
Vendor Document - Instructions Installation and
Maintenance of 7700 Line Motor Control Center
Maintenance of 7700 Line Motor Control Center
BFN-VTD-K143-0020       Installation and Maintenance Instructions for Kinney   Rev. 8
Rev. 2
BFN-VTD-K143-0020
Installation and Maintenance Instructions for Kinney
Automatic Self-Cleaning Strainers Model AV Series
Automatic Self-Cleaning Strainers Model AV Series
BFN-VTD-K143-0040       Preventative Maintenance Instructions for S.P. Kinney   Rev. 0
Rev. 8
BFN-VTD-K143-0040
Preventative Maintenance Instructions for S.P. Kinney
Strainers
Strainers
BFN-VTD-K143-0050       Instruction Manual for S.P. Kinney Model AV Series     Rev. 0
Rev. 0
BFN-VTD-K143-0050
Instruction Manual for S.P. Kinney Model AV Series
Motorized Automatic Self-Cleaning Strainers
Motorized Automatic Self-Cleaning Strainers
BFPER971270             BF response to NRC IN 91-50 Supplement 1               Rev. 0
Rev. 0
DCN 69466A             Replace CS and RHR Room Cooler Fan Motors, Fans,       Rev. A
BFPER971270
BF response to NRC IN 91-50 Supplement 1
Rev. 0
DCN 69466A
Replace CS and RHR Room Cooler Fan Motors, Fans,
and Shafts
and Shafts
DCN 70747A             50.59 Evaluation                                       Rev. 0
Rev. A
DCN 71376               Increase Rated Speed of RCIC Pump/Turbine to 4650       Rev. A
DCN 70747A
50.59 Evaluation
Rev. 0
DCN 71376
Increase Rated Speed of RCIC Pump/Turbine to 4650
RPM
RPM
EDC 50911               Option for Rotating EECW Strainer Gear Reducer 180     Rev. B
Rev. A
EDC 50911
Option for Rotating EECW Strainer Gear Reducer 180
Degrees
Degrees
Rev. B
Fire Protection
Fire Protection
Impairment Permit
Impairment Permit  
                (FPIP) # 21-90 - Unit 3
(FPIP) # 21-90 - Unit 3
Reactor Building
Reactor Building
Elevation 621/638
Elevation 621/638  
 
Fire Protection
Fire Protection
Impairment Permit
Impairment Permit  
                (FPIP) # 21-91 - Unit 2
(FPIP) # 21-91 - Unit 2  
Inspection Type       Designation             Description or Title                                   Revision or
 
Procedure                                                                                            Date
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Reactor Building
Reactor Building
Elevation 621/638
Elevation 621/638
General Design Criteria Standby Diesel Generator                                Rev. 29
General Design Criteria
Document No. BN-50-
Document No. BN-50-
7082
7082
OPL171.051             Emergency Equipment Cooling Water                       Rev. 9U1
Standby Diesel Generator
PMCR 1189814           Perform 4 Year Inspection of Stand-by Diesel Engine "C"
Rev. 29
PMCR 1189815           Perform 12-Year Inspection of Standby Diesel "C"
OPL171.051
Emergency Equipment Cooling Water
Rev. 9U1
PMCR 1189814
Perform 4 Year Inspection of Stand-by Diesel Engine "C"
PMCR 1189815
Perform 12-Year Inspection of Standby Diesel "C"
Engine "C"
Engine "C"
PO 2740686             Spare Part, Engine, QA1                                 dated
PO 2740686
Spare Part, Engine, QA1
dated
01/19/17
01/19/17
Procedures 0-ARP-25-41C           Panel 25-41, 0-XA-55-41C                               Rev. 16
Procedures
0-FSS-001               Fire Safe Shutdown                                     Rev. 5
0-ARP-25-41C
0-FSS-2-2               U-2, RB EL 519', from R14 to a Line 10' West of R11     Rev. 8
Panel 25-41, 0-XA-55-41C
0-FSS-2-3               U-2, RB EL593 North of Column Line R                   Rev. 13
Rev. 16
0-GOI-300-1/ATT-12     Outside Operator Round Log                             Rev. 264
0-FSS-001
0-OI-57B               480V/240V AC Electrical System                         Rev. 199
Fire Safe Shutdown
0-OI-57D               DC Electrical System                                   Rev. 179
Rev. 5
0-OI-67                 Emergency Operating Cooling Water System               Rev. 126
0-FSS-2-2
0-OI-82                 Standby Diesel Generator System                         Rev. 174
U-2, RB EL 519', from R14 to a Line 10' West of R11
0-SI-4.5.C.1(A3)       RHRSW Pump A3 IST Group A Quarterly Pump Test           Rev. 19
Rev. 8
0-SR-3.4.3.1.A         Bench Test Relief Valves - As Left                     Rev. 6
0-FSS-2-3
0-TI-346               Maintenance Rule Performance Indicator Monitoring,     Rev. 54
U-2, RB EL593 North of Column Line R
Rev. 13
0-GOI-300-1/ATT-12
Outside Operator Round Log
Rev. 264
0-OI-57B
480V/240V AC Electrical System
Rev. 199
0-OI-57D
DC Electrical System
Rev. 179
0-OI-67
Emergency Operating Cooling Water System
Rev. 126
0-OI-82
Standby Diesel Generator System
Rev. 174
0-SI-4.5.C.1(A3)
RHRSW Pump A3 IST Group A Quarterly Pump Test
Rev. 19
0-SR-3.4.3.1.A
Bench Test Relief Valves - As Left
Rev. 6
0-TI-346
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10CFR50.65
Trending, and Reporting - 10CFR50.65
0-TI-362               Inservice Testing Program                               Rev. 59
Rev. 54
0-TI-636RLY             Relay Testing and Maintenance Instruction               Rev. 2
0-TI-362
0-TI-641               Time Critical Operator Actions                         Rev. 0
Inservice Testing Program
1-ARP-9-8C             Panel 1-9-8, 1-XA-55-8C                                 Rev. 17
Rev. 59
1/2-ARP-9-23C           Panel 0-9-23-8, 0-XA-55-23C                             Rev. 35
0-TI-636RLY
2-SR-3.3.5.1.3(E)       HPCI Suppression Chamber High Level Calibration and     Rev. 21
Relay Testing and Maintenance Instruction
Rev. 2
0-TI-641
Time Critical Operator Actions
Rev. 0
1-ARP-9-8C
Panel 1-9-8, 1-XA-55-8C
Rev. 17
1/2-ARP-9-23C
Panel 0-9-23-8, 0-XA-55-23C
Rev. 35
2-SR-3.3.5.1.3(E)
HPCI Suppression Chamber High Level Calibration and
Functional Test
Functional Test
2-SR-3.3.5.1.6(ADS B)   ADS Logic System Functional Test - Bus B Time Delay     Rev. 22
Rev. 21
2-SR-3.3.5.1.6(ADS B)
ADS Logic System Functional Test - Bus B Time Delay
Relay Calibration and Bus Power Monitor Test
Relay Calibration and Bus Power Monitor Test
Inspection Type Designation             Description or Title                                   Revision or
Rev. 22
Procedure                                                                                      Date
 
2-SR-3.5.3.3           RCIC System Rated Flow at Normal Operating Pressure   dated
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-SR-3.5.3.3
RCIC System Rated Flow at Normal Operating Pressure
dated
01/04/21
01/04/21
2-SR-3.5.3.3           RCIC System Rated Flow at Normal Operating Pressure   dated
2-SR-3.5.3.3
RCIC System Rated Flow at Normal Operating Pressure
dated
10/05/09
10/05/09
2-SR-3.5.3.3(COMP)     RCIC Comprehensive Pump Test                           dated
2-SR-3.5.3.3(COMP)
RCIC Comprehensive Pump Test
dated
10/10/20
10/10/20
2-SR-3.5.3.4           RCIC System Rated Flow at Low RPV Pressure             Rev. 26
2-SR-3.5.3.4
ADS Logic System       Rev. 17
RCIC System Rated Flow at Low RPV Pressure
Rev. 26
ADS Logic System
Functional Test - Bus B
Functional Test - Bus B
Time Delay Relay
Time Delay Relay
Calibration and Bus
Calibration and Bus
Power Monitor Test
Power Monitor Test
ECI-0-000-BRK008       Testing and Troubleshooting of Molded Case Circuit     dated
Rev. 17
Breakers and Motor Starter Overload Relays             03/21/15
ECI-0-000-BRK008
EII-0-000-TCC106       Troubleshooting, Documentation and Configuration       dated
Testing and Troubleshooting of Molded Case Circuit
Control of Electrical Activities                       03/26/15
Breakers and Motor Starter Overload Relays
EPI-0-000-MCC001       Maintenance and Inspection of 480VAC and 250VDC       dated
dated
Motor Control Centers                                 03/20/15
03/21/15
EPI-0-281-RLY001       Relay Calibration and Functional Tests on 250V DC     Rev. 13
EII-0-000-TCC106
Troubleshooting, Documentation and Configuration
Control of Electrical Activities
dated
03/26/15
EPI-0-000-MCC001
Maintenance and Inspection of 480VAC and 250VDC
Motor Control Centers
dated
03/20/15
EPI-0-281-RLY001
Relay Calibration and Functional Tests on 250V DC
Reactor MOV Boards
Reactor MOV Boards
MAI-3.4A               Internal Conduit Seals                                 Rev. 17
Rev. 13
MCI-0-001-VLV002       Main Steam Relief Valves Target Rock Model 7567       Rev. 54
MAI-3.4A
Internal Conduit Seals
Rev. 17
MCI-0-001-VLV002
Main Steam Relief Valves Target Rock Model 7567
Disassembly, Inspection, Repair and Reassembly
Disassembly, Inspection, Repair and Reassembly
MSI-0-071-GOV001       Reactor Core Isolation Cooling (RCIC) Overspeed Trip   Rev. 36
Rev. 54
MSI-0-071-GOV001
Reactor Core Isolation Cooling (RCIC) Overspeed Trip
Test
Test
MSI-2-001-TST002       Testing of Air Supply System (Drywell Side-East) for   Rev. 14
Rev. 36
MSI-2-001-TST002
Testing of Air Supply System (Drywell Side-East) for
Main Steam Isolation Valves and Automatic
Main Steam Isolation Valves and Automatic
Depressurization System Main Steam Relief Valves
Depressurization System Main Steam Relief Valves
MSI-2-001-TST003       Testing Air Supply System (Drywell Side-West) for Main Rev. 12
Rev. 14
MSI-2-001-TST003
Testing Air Supply System (Drywell Side-West) for Main
Steam Isolation Valves and Automatic Depressurization
Steam Isolation Valves and Automatic Depressurization
System Main Steam Relief Valves
System Main Steam Relief Valves
NEDP-10                 Rev. 25
Rev. 12
NEDP-2                 Design Calculation Process Control                     Rev. 25
NEDP-10
NEDP-22                 Operability Determinations and Functional Evaluations Rev. 21
Rev. 25
Inspection Type       Designation   Description or Title                               Revision or
NEDP-2
Procedure                                                                                Date
Design Calculation Process Control
NPG-SPP-09.3   Plant Modifications and Engineering Change Control Rev. 35
Rev. 25
NPG-SPP-22.206 Verification Program                               Rev. 7
NEDP-22
Work Orders 116092256
Operability Determinations and Functional Evaluations
117821889
Rev. 21  
117821892
 
117821901
Inspection
117821908
Procedure
118569627
Type
118800332
Designation
Description or Title
Revision or
Date
NPG-SPP-09.3
Plant Modifications and Engineering Change Control
Rev. 35
NPG-SPP-22.206
Verification Program
Rev. 7
Work Orders
116092256  
 
117821889  
 
117821892  
 
117821901  
 
117821908  
 
118569627  
 
118800332  
 
119041410
119041410
21166362
21166362
Line 449: Line 829:
01-012730-001
01-012730-001
01-012730-002
01-012730-002
21325467
21325467  
Inspection Type Designation Description or Title Revision or
 
Procedure                                        Date
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21331211
21331211
21385840
21385840
Line 459: Line 845:
21785957
21785957
21808045
21808045
119585512
119585512  
 
119639739
119639739
15
}}
}}

Revision as of 07:12, 29 November 2024

Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010
ML21207A006
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/26/2021
From: James Baptist
Division of Reactor Safety II
To: Jim Barstow
Tennessee Valley Authority
References
EPID I-2021-010-0038 IR 2021010
Download: ML21207A006 (17)
v • d • e


Text

July 26, 2021

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000259/2021010 AND 05000260/2021010 AND 05000296/2021010

Dear Mr. Barstow:

On June 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant and discussed the results of this inspection with Mr. Chris Dunn 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. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000259, 05000260 and 05000296

License Numbers:

DPR-33, DPR-52 and DPR-68

Report Numbers:

05000259/2021010, 05000260/2021010 and 05000296/2021010

Enterprise Identifier: I-2021-010-0038

Licensee:

Tennessee Valley Authority

Facility:

Browns Ferry Nuclear Plant

Location:

Athens, AL

Inspection Dates:

May 17, 2021 to June 11, 2021

Inspectors:

C. Baron, Contractor

D. Bollock, Senior Reactor Operations Engineer

W. Deschaine, Senior Resident Inspector

S. Kobylarz, Contractor

R. Patterson, Senior Reactor Inspector

J. Winslow, Reactor Systems Engineer

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 (teams) inspection at Browns Ferry Nuclear Plant, 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

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

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 a 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

===71111.21M - Design Bases Assurance Inspection (Teams)

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

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)

(1)250V DC Reactor Motor Operated Valve (RMOV) Board 2B

  • Material condition and configuration (e.g., visual inspection during a walkdown)
  • Operating environment
  • Consistency between station documentation (e.g. procedures) and vendor specifications
  • Maintenance effectiveness
  • Corrective maintenance records, and corrective action history
  • Panel loading
  • Load voltage adequacy
  • Overcurrent protection and coordination
(2) Emergency Essential Cooling Water (EECW) Strainers
  • Material condition and configuration (e.g., visual inspection during a walkdown by onsite inspector)
  • Consistency between station documentation (e.g. procedures and drawings)and vendor specifications
  • Corrective maintenance records, and corrective action history
  • System Health Reports
  • Compliance with UFSAR, TS, and TS Bases
  • Normal and emergency operating procedures
  • Modifications
  • Completed surveillance tests to ensure acceptance criteria have been met

(3)480V RMOV BD 2D

  • Material condition and configuration (e.g., visual inspection during a walkdown)
  • Operating environment
  • Consistency between station documentation (e.g. procedures) and vendor specifications
  • Maintenance and Preventive Maintenance effectiveness
  • Corrective maintenance records, and corrective action history
  • Breaker short circuit capacity
  • BD (MCC) loading
  • BD (MCC) voltage adequacy
  • Overcurrent protection and coordination
(4) Unit 2 Reactor Core Isolation Cooling (RCIC) System Pump 2B
  • Normal and Emergency Operating Procedures
  • Surveillance Test Procedures and Recent Results
  • Inservice Test Procedures and Recent Results
  • Bases for Pump Test Acceptance Criteria
  • Calculation of Pump Capacity
  • Calculation of Pump NPSH
  • Calculation of System Pressure due to Pump Overspeed Condition
  • Operation of RCIC under Station Blackout Conditions
  • Evaluation of RCIC Pump Suction Transfer
  • Material Condition of Pump and Associated Equipment
  • Corrective Action History

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

Main article: IP 71111.21
(1) Unit 2 Automatic Depressurization System (ADS) Valves
  • Normal and Emergency Operating Procedures
  • Calculation of Instrument Air Supply and Air Accumulator Capacity
  • Instrument Air Leakage Test Procedures and Recent Results
  • Recent Valve Test Results
  • Evaluation of Electrical Control and Power Supplies
  • Evaluation of Testing of Backup Electrical Control and Power Supplies
  • Corrective Action History

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

(1) DCN 71425, Upgrade Unit 1/2 Emergency Diesel Generator Fuel Oil Piping Configuration
(2) DCN 72338-03, Replacement of 4160V/480V Emergency Shutdown Board 2A & 2B Transformer
(3) BFN-19-918-01-U1, High Pressure Coolant Injection Gland Seal Check Valve Addition
(4) DCN 69466A, Replace Core Spray and Residual Heat Removal Room Cooler Fan Motors, Fans, and Shafts
(5) BFN-1-2020-068-003, Temporary Replacement of Recirculation Loop 1B Flow Measurement (T-Mod)
(6) DCN 70747-71, 480V RMOV BD 2A/15D ALT FDR from SD BD

Review of Operating Experience Issues (IP Section 02.06) (2 Samples)

(1) NRC IN 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify
(2) NRC IN 91-50: A Review of Water Hammer Events After

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On June 29, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Chris Dunn and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

BFN-1-47E859-1

Flow Diagram, Emergency Equipment Cooling Water

Rev. 99

CDQ-0067-881511

Seismic Qualification for the Automatic Self-Cleaning

Strainer

Rev. 1

CDQ-0067894672

Evaluation and Review of Small Bore Unit 0 Piping and

Supports within the Scope of the System 067 Safe

Shutdown Boundary

Rev. 12

CDQ-1067895300

Pipe Stress Analysis of Stress Problem No. 1-67-859-1-

Rev. 3

CDQ-2067890748

Strainer Backwash Blowdown Piping at Pumping Station

Rev. 2

CDQ0303880436

Assess the RHRSW and the EECW Piping and

Components for the Affects of Tornadic Wind-RHRSW

Pump

Rev. 2

CDQ0999910005

Evaluation of Seismic-Induced Spray Hazards at BFN,

Unit 2 and Common

Rev. 3

CDQ107320021062

Small Bore Piping and Supports Program System

Calculation for Seismic Class 1 HPCI System (73) Piping

Rev. 6

CDQ107320031063

Pipe Stress Analysis of Stress Problem N1-173-67R

Rev. 1

EDQ0057920034

4.16KV and 480V Busload, Voltage Drop and Short

Circuit Calculation

Rev. 92

EDQ024820020042

250V DC Unit Battery Load Study

Rev. 91

EDQ2000870054

Control Circuit Voltage Drop Calculations - 250V DC

circuits

Rev. 43

EDQ2000870550

Cable and Bus Protection/Breaker/Fuse Coordination for

250V DC System

Rev. 54

EDQ2092900118

Setpoint and Scaling Calculation for Neutron Monitoring

System & Recirculation Flaw Loops

Rev. 37

EDQ2999870549

Power Cable Protection Analysis for 480V MCCs

Rev. 54

EQD29998801715

Thermal Overload Heater Calculation

Rev. 50

MD-N0026-910163

Combustible Load Table

Rev. 71

MDQ-

0000672019000460

MOV 0-FCV-067-0001/0005/0008/0011, Operator

Requirements and Capabilities

Rev. 1

MDQ-0067890059

Analytical Limits for the EECW Strainers and Strainer

Rev. 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Drain Valves Start/Stop Controls

MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis

(Pump Water Suction and Discharge)

Rev. 3

MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS

Piping

Rev. 0

MDQ0032870288

Control Air Volume and Wall Thickness of Accumulators

Rev. 14

MDQ0071910235

Reactor Core Isolation Cooling System Design

Pressure/Temperature

Rev. 12

MDQ099920040034

Setpoint Controls Parameters Review Calculation for

BFN Category 2 Air Operated Valves (AOVs)

Rev. 17

MDQ099920040040

HPCI and RCIC Test Requirements

Rev. 11

NDN00099920070032

BFN Probablistic Risk Assessment - Human Reliability

Analysis

Rev. 8

Corrective Action

Documents

0044691

28951

0175232

200183

1648705

1649288

1649610

1652318

1369055

1406271

1499731

1500527

1557241

1606454

1607278

1613986

1614688

1617438

27370

1638651

1655591

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1656541

1656544

1658162

1658186

1658998

1664478

1665909

1676979

1687954

1688353

1695185

201387

21012

1434874

1435350

1613271

Corrective Action

Documents

Resulting from

Inspection

1695185

A3 RHRSW Lube Oil Strainer Sight Glass

1695266

Control of HPCI and RCIC System Flow Controller

Settings

1695742

Danger sign was identified on the top of 480V RMOV

Board 2D

1695748

Review and Evaluate Unit 2 RCIC System CQS Test

Results

1695790

NRC DBAI Inspection - Minor Correction Needed on

FPPCIS for ECP 71425

1695802

NRC DBAI 2021 Inspection - Correction Needed to 1/2-

ARP-9-23A/B/C/D and 0-ARP-25-41A/B/C/D

1696259

Pipe Wrench Laying on Top of the C# EECW Strainers

Gearbox01

1696423

NRC DBAI Inspection - Incorrect M&TE Number

Documented in WO 116092256

1696542

250V Reactor MOV Board 2B board is missing 3

finishing plugs

1696552

480V Reactor MOV board 2A missing 1 finishing plug

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1696556

480V Reactor MOV board 2D remove RTV from

Finishing Plug hole and install Finishing Plug

1696713

Request PCRs for RCIC Flowrate Procedures

1698638

MDQ0071910235 Evaluation Didnt Account for

Tolerance

1699579

Fire seal label is required at the S25932501 penetration

per MAI-3.4A and is missing

1699961

Fire Seal Penetration R26395139 not conforming to

design output drawing 0-45E830-27

1699971

Fire Seal Penetration R36395359 not conforming to

design output drawing 0-45E830-27

1700011

DP Between RCIC Pump Discharge and RPV

1700151

Response to RCIC Overspeed

1700334

RCIC Surveillance Procedure Non-Conservative with

Respect to TS

1700335

NRC Observation Recirc Temp Mod

Drawings

0-45E830-27

Conduit & Grounding Cable Trays Fire Stop Dets-SH 14

Rev. 7

0-47E392-1

Fire Protection - 10 CFR 50 - NFPA 805 Penetration

Seal Tabular Drawings General Notes and Legend

Rev. 5

0-47E840-3

Flow Diagram, Fuel Oil System

Rev. 27

0-731E700

One Line Diagram of DC & Instrument Control AC

Systems

Rev. 8

1-45E751-3

Wiring Diagram, 480V Reactor MOV Board 1B

Rev. 43

2-45E712-2

Wiring Diagram 250V Reactor MOV BD 2B Single Line

Rev. 35

2-47E610-1-1

Mechanical Control Diagram - Main Steam System

Rev. 43

2-47E610-71-1

Mechanical Control Diagram - RCIC System

Rev. 45

2-47E610-71-2

Mechanical Control Diagram - RCIC System

Rev. 7

2-47E801-1

Flow Diagram - Main Steam

Rev. 34

2-47E813-1

Flow Diagram - Reactor Core Isolation Cooling System

Rev. 60

2-47W2392-702

Fire Protection - 10 CFR 50 Appendix R Penetration

Seal Location Drawings Plan View Area I

Rev. 1

2-47W2392-708

Fire Protection - 10 CFR 50 Appendix R Penetration

Seal Location Drawings EL 639

Rev. 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2-47W2392-716

Fire Protection - 10 CFR 50 Appendix R Penetration

Seal Tabular Drawings EL 639

Rev. 3

2-730E929-2

Automatic Blowdown System

Rev. 24

2-730E929-3

Elementary Diagram - Automatic Blowdown System

Rev. 16

2-730E929-4

Automatic Blowdown System

Rev. 18

BFN-0-47E610-67-2

Mechanical Control Diagram, Emergency Equipment

Cooling Water

Rev. 38

BFN-1-47E610-67-1

Mechanical Control Diagram, Emergency Equipment

Cooling Water

Rev. 50

BFN-1-47E812-1-CC

Flow Diagram, High Pressure Coolant Injection System

Rev. 48

BFN-2-45E751-1

Wiring Diagram 480V Reactor MOV BD 2A Single Line

Rev. 068

BFN-2-45E751-8

Wiring Diagram 480V Reactor MOV BD 2D Single Line

Rev. 2

BFN-2-47E812-1-CC

Flow Diagram, High Pressure Coolant Injection System

Rev. 77

BFN-3-47E812-1-CC,

Flow Diagram, High Pressure Coolant Injection System

Rev. 73

Engineering

Changes

DCN 72338-03

Replacement of 4160V/480V Emergency Shutdown

Board 2A & 2B Transformer

EC 71425

Upgrade Unit 1/2 DG Fuel Oil Piping Configuration

Rev. A

Miscellaneous

System Health Report Scorecard for RHRSW and

EECW (April 2020-September 2020)

System Health Report Scorecard for RHRSW and

EECW (October 2020-March 2021)

Vendor Letter, Instructions for Changing Assembly of

DSMM40A Reducer

dated

03/12/02

System Health Report Scorecard for RHRSW and

EECW (October 2019-March 2020)

0-SI-4.5.C.1(A3-COMP)

RHRSW Pump A3 IST Comprehensive Pump Test

Rev. 16

0-TI-444

Augmented Inservice Testing Program

Rev. 12

0-TI-641

Time Critical Operator Actions

Rev. 0

0048-0051-LTR-002

BFN HPCI System Waterhammer Evaluation

Rev. 0

0048-0065-RPT-001

HPCI and RCIC Systems Overpressure Transient

Technical Review and Development of Mitigation

Options

Rev. 0

70747-71

480V RMOV BD 2A/15D ALT FDR from SD BD

Rev. A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

BFN-1-2020-068-003

Rev. 0

BFN-19-918

U1, U2, and U3 HPCI Gland Seal CKV Addition

Rev. 1

BFN-19-918-1

U1 HPCI Gland Seal CKV Addition

Rev. 0

BFN-50-7071

Design Criteria - Reactor Core Isolation Cooling System

Rev. 23

BFN-50-7200C

Design Basis Document for the 250V DC Power

Distribution System

Rev. 8

BFN-50-720D, 480V

Auxiliary System

480V Auxiliary System

Rev. 12

BFN-VTD-D088-0010

Installation, Operation and Maintenance for Delroyd

Double Worm Gear Speed Reducers

Rev. 2

BFN-VTD-G080-1440

Vendor Document - Instructions Installation and

Maintenance of 7700 Line Motor Control Center

Rev. 2

BFN-VTD-K143-0020

Installation and Maintenance Instructions for Kinney

Automatic Self-Cleaning Strainers Model AV Series

Rev. 8

BFN-VTD-K143-0040

Preventative Maintenance Instructions for S.P. Kinney

Strainers

Rev. 0

BFN-VTD-K143-0050

Instruction Manual for S.P. Kinney Model AV Series

Motorized Automatic Self-Cleaning Strainers

Rev. 0

BFPER971270

BF response to NRC IN 91-50 Supplement 1

Rev. 0

DCN 69466A

Replace CS and RHR Room Cooler Fan Motors, Fans,

and Shafts

Rev. A

DCN 70747A

50.59 Evaluation

Rev. 0

DCN 71376

Increase Rated Speed of RCIC Pump/Turbine to 4650

RPM

Rev. A

EDC 50911

Option for Rotating EECW Strainer Gear Reducer 180

Degrees

Rev. B

Fire Protection

Impairment Permit

(FPIP) # 21-90 - Unit 3

Reactor Building

Elevation 621/638

Fire Protection

Impairment Permit

(FPIP) # 21-91 - Unit 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Reactor Building

Elevation 621/638

General Design Criteria

Document No. BN-50-

7082

Standby Diesel Generator

Rev. 29

OPL171.051

Emergency Equipment Cooling Water

Rev. 9U1

PMCR 1189814

Perform 4 Year Inspection of Stand-by Diesel Engine "C"

PMCR 1189815

Perform 12-Year Inspection of Standby Diesel "C"

Engine "C"

PO 2740686

Spare Part, Engine, QA1

dated

01/19/17

Procedures

0-ARP-25-41C

Panel 25-41, 0-XA-55-41C

Rev. 16

0-FSS-001

Fire Safe Shutdown

Rev. 5

0-FSS-2-2

U-2, RB EL 519', from R14 to a Line 10' West of R11

Rev. 8

0-FSS-2-3

U-2, RB EL593 North of Column Line R

Rev. 13

0-GOI-300-1/ATT-12

Outside Operator Round Log

Rev. 264

0-OI-57B

480V/240V AC Electrical System

Rev. 199

0-OI-57D

DC Electrical System

Rev. 179

0-OI-67

Emergency Operating Cooling Water System

Rev. 126

0-OI-82

Standby Diesel Generator System

Rev. 174

0-SI-4.5.C.1(A3)

RHRSW Pump A3 IST Group A Quarterly Pump Test

Rev. 19

0-SR-3.4.3.1.A

Bench Test Relief Valves - As Left

Rev. 6

0-TI-346

Maintenance Rule Performance Indicator Monitoring,

Trending, and Reporting - 10CFR50.65

Rev. 54

0-TI-362

Inservice Testing Program

Rev. 59

0-TI-636RLY

Relay Testing and Maintenance Instruction

Rev. 2

0-TI-641

Time Critical Operator Actions

Rev. 0

1-ARP-9-8C

Panel 1-9-8, 1-XA-55-8C

Rev. 17

1/2-ARP-9-23C

Panel 0-9-23-8, 0-XA-55-23C

Rev. 35

2-SR-3.3.5.1.3(E)

HPCI Suppression Chamber High Level Calibration and

Functional Test

Rev. 21

2-SR-3.3.5.1.6(ADS B)

ADS Logic System Functional Test - Bus B Time Delay

Relay Calibration and Bus Power Monitor Test

Rev. 22

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2-SR-3.5.3.3

RCIC System Rated Flow at Normal Operating Pressure

dated

01/04/21

2-SR-3.5.3.3

RCIC System Rated Flow at Normal Operating Pressure

dated

10/05/09

2-SR-3.5.3.3(COMP)

RCIC Comprehensive Pump Test

dated

10/10/20

2-SR-3.5.3.4

RCIC System Rated Flow at Low RPV Pressure

Rev. 26

ADS Logic System

Functional Test - Bus B

Time Delay Relay

Calibration and Bus

Power Monitor Test

Rev. 17

ECI-0-000-BRK008

Testing and Troubleshooting of Molded Case Circuit

Breakers and Motor Starter Overload Relays

dated

03/21/15

EII-0-000-TCC106

Troubleshooting, Documentation and Configuration

Control of Electrical Activities

dated

03/26/15

EPI-0-000-MCC001

Maintenance and Inspection of 480VAC and 250VDC

Motor Control Centers

dated

03/20/15

EPI-0-281-RLY001

Relay Calibration and Functional Tests on 250V DC

Reactor MOV Boards

Rev. 13

MAI-3.4A

Internal Conduit Seals

Rev. 17

MCI-0-001-VLV002

Main Steam Relief Valves Target Rock Model 7567

Disassembly, Inspection, Repair and Reassembly

Rev. 54

MSI-0-071-GOV001

Reactor Core Isolation Cooling (RCIC) Overspeed Trip

Test

Rev. 36

MSI-2-001-TST002

Testing of Air Supply System (Drywell Side-East) for

Main Steam Isolation Valves and Automatic

Depressurization System Main Steam Relief Valves

Rev. 14

MSI-2-001-TST003

Testing Air Supply System (Drywell Side-West) for Main

Steam Isolation Valves and Automatic Depressurization

System Main Steam Relief Valves

Rev. 12

NEDP-10

Rev. 25

NEDP-2

Design Calculation Process Control

Rev. 25

NEDP-22

Operability Determinations and Functional Evaluations

Rev. 21

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NPG-SPP-09.3

Plant Modifications and Engineering Change Control

Rev. 35

NPG-SPP-22.206

Verification Program

Rev. 7

Work Orders

116092256

117821889

117821892

117821901

117821908

118569627

118800332

119041410

21166362

20898561

118571292

118571299

20561899

119698618

20136130

21260764

118571303

119698622

20136126

119189075

119189052

119189076

118323602

115753060

01-012729-000

01-012729-001

01-012729-002

01-012729-003

01-012730-000

01-012730-001

01-012730-002

21325467

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

21331211

21385840

21390551

21504079

21504079

21785957

21808045

119585512

119639739

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