IR 05000390/2019011
| ML19274C630 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/01/2019 |
| From: | James Baptist NRC/RGN-II, Division of Reactor Safety II |
| To: | James Shea Tennessee Valley Authority |
| Reeder D | |
| References | |
| IR 2019011 | |
| Download: ML19274C630 (23) | |
Text
ber 1, 2019
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000390/2019011 AND 05000391/2019011
Dear Mr. Shea:
On August 29, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar, Units 1 and 2 and discussed the results of this inspection with Mr. Tom Marshall and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000390 and 05000391 License Nos. NPF-90 and NPF-96
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000390 and 05000391 License Numbers: NPF-90 and NPF-96 Report Numbers: 05000390/2019011 and 05000391/2019011 Enterprise Identifier: I-2019-011-0006 Licensee: Tennessee Valley Authority Facility: Watts Bar, Units 1 and 2 Location: Spring City, TN Inspection Dates: August 12, 2019 to August 29, 2019 Inspectors: P. Braxton, Reactor Inspector A. Della Greca, Contractor N. Morgan, Resident Inspector R. Patterson, Senior Reactor Inspector M. Schwieg, Reactor Inspector W. Sherbin, Contractor Approved By: Brian R. Bonser, Chief Engineering Branch 3 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 (teams) inspection at Watts Bar, Units 1 and 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 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.
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) Division II 125VDC Power Bus
- Material condition and configuration (i.e. visual inspection during walkdown)
- Component modification
- Component health reports, corrective action history
- Maximum available fault current
- DC voltage analysis
- Breaker coordination
- (2) Auxiliary Feedwater Motor-Driven Pump Level Control Valve 2-LCV-3-171 & Auxiliary Feedwater Turbine-Driven Pump Level Control Valve 2-LCV-3-175
- Material condition and configuration (i.e., visual inspection during walkdown)
- Maintenance effectiveness
- Component health reports, corrective maintenance records, and corrective action history
- Component modifications
- Surveillance and Inservice testing results
- Procurement and Design Specifications
- (3) Unit 2 6.9 KV Shutdown Board 2A-A [2-BD-211-A-A]
- Compliance with UFSAR, TS, and TS Bases
- Conformance with manufacturer instructions for installation, maintenance, and operation
- Adequacy of corrective action activities
- Material condition and configuration
- System Health Reports accurately reflect current system conditions
- Design requirements (Voltage drop calculations, degraded grid and loss of voltage relays setting, load flow analysis and short circuit calculation, etc.)
- Setting and coordination of protective relays for selected supply and load breakers
- Verification that selected relays calibrations meet intended design requirements
- Design verification of bounding design basis events, including fast bus transfer between offsite power sources and transfer to standby source
- Verification that TS system surveillance requirements demonstrate performance requirements of system and components
- Design basis and adequacy of recent modifications
- Adequacy of instrumentation and operating procedures for system and components performance/operation during normal, abnormal, and accident conditions
- (4) Unit 2 Centrifugal Charging Pump CCP-2A
- Material condition and configuration (e.g., visual inspection during a walkdown)
- Consistency between station documentation (e.g. procedures) and vendor specifications
- Operating procedures and Emergency Procedures
- Training Manual and System Description
- Maintenance effectiveness
- Component health reports, corrective maintenance records, and corrective action history
- Consistency between design bases calculations and test procedure acceptance criteria
- Surveillance and calibration testing and recent test results
- Pump room cooler capability versus cooling load
- Pump horsepower requirements compared to driver motor capability
- Seismic qualification of pump skid and piping attachments (nozzle loads)
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
- (1) Unit 2 Hydrogen Igniters
- Verification of equipment necessary to provide backup power to the hydrogen igniters is available
- Rating of the power supply is adequate to continuously power to the hydrogen igniters and operating time is consistent with commitments
- Verify procedures are established to govern the provision of backup power to the igniters
- Maintenance and testing schedules for the backup power supply is consistent with the vendor recommendation.
- Procedure address the decision to provide backup power to the igniters and the steps required to provide the backup power to the hydrogen igniters
- (2) Unit 2 6.9 KV to 480 V Transformer 2A1-A Including Supply and Load Breakers
- Compliance with UFSAR, TS, and TS Bases
- Conformance with manufacturer instructions for installation, maintenance, and operation
- Adequacy of corrective action activities
- Material condition and configuration
- Verification that System Health Reports accurately reflect current system conditions
- Design requirements (Rating, normal and accident loading, tap setting, etc.)
- Adequacy of supply and load cables
- Seismic qualification of transformer and supply and load shutdown boards
- Setting of upstream protective relays and coordination with downstream breaker
- Verification that protective relays calibrations and breakers maintenance and testing meet intended design requirements Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)
- (1) DCN 58314, Replace Unit 1 Turbine Driven Auxiliary Feed-water (TDAFW) Governor Valve Controller with Digital Controller
- (2) DCN 59007, Replace 1-PCV-003-0122 & -0132 with a Cavitating Venturi
- (3) DCN 60696, Replace Pressurizer Power Operated Relief Valves (PORVs) Due to Current Valves Being Obsolete
- (4) DCN 66471, Modify Solid-state Protection System (SSPS) Turbine Trip on Low Fluid Oil Pressure
- (6) DCN 553785, Swapping Power Sources to Eliminate Loss of Power to Two Pumps When One EDG is Not Available Review of Operating Experience Issues (IP Section 02.06) (3 Samples)
- (1) GL 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional LTOP Protection for PWRs"
- (2) IN 2010-10, Implementation of a Digital Control System Under 10 CFR 50.59
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 29, 2019, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Tom Marshall and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Calculations CEBCAS228 Nozzle Load Qualification for the CCPs Rev. 3
E31920409300 Shutdown Boards Degraded Voltage Relay Settings Rev. 1
EDQ00099920070002 AC Auxiliary Power System Analysis Rev. 067
EDQ00099920080014 Diesel Generator Loading Analysis Rev. 35
EDQ00299920080016 6.9 KV Protection and Coordination Calculation Rev. 12
EPMDLB061193 Adequacy of ERCW Flow to Centrifugal Charging Rev. 5
Pumps 1A-A and 2A-A Oil Coolers
EPMHV0701889 Maximum Brake Horsepower for Centrifugal Rev. 5
Charging Pumps
EPMPKB012191 HVAC Cooling Load and Room Temperature Calc: Rev. 11
TDAFW Pump Room
EPMSHC102789 Main Steam Over Pressure Protection Design Rev. 0
EPMSNM043092 Failure Modes and Effects Analysis for the SI Rev. 0
System
EPMTEC081689 Cooling Load for CCP Room Aux Building Elevation Rev. 5
2-A9 and A10 Under LOCA Conditions
N36232A Summary of Piping Analysis Rev. 9
R03521E31920108300 Shutdown Board 1A-A Feeders to 6900/480V Rev.0
Transformers 1A1-A, 1A2-A, and 1A-A
TDRSYS.211-DS1 Demonstrated Accuracy Calculation Rev. 6
WBNEEBEDQ1999010001 AC Auxiliary Power System Analysis Rev. 96
WBNEEBMST1060029 Degraded Voltage Analysis Rev.38
WBNEEBMST1080008 480V 1E Coordination/Protection Rev. 174
WBNOSG4071 RWST and Containment Sump Safety Limits Rev. 27
WBPE2119202001 6.9KV Shutdown & Logic Boards Undervoltage Rev. 12
Relays Requirement/ Demonstrated Accuracy
Calculation
Calibration Certificate of Calibration for NWS-T-139 & NWS-R- 04/13/19
Inspection Type Designation Description or Title Revision or
Procedure Date
Records 73
Corrective Action 1158981
Documents 1177342
1177660
1181488
1197406
1198767
201099
201726
206585
209629
212101
284810
296987
1359596
1370572
1380308
1381120
1398457
1414582
1419624
26714
1436407
1447534
1447766
1456434
1464817
1472485
1483042
1498200
22586
22957
25931
Inspection Type Designation Description or Title Revision or
Procedure Date
480993
934675
940480
Corrective Action 1540525 2A CCP Oil Leak
Documents 1540541 Calculation References Not Updated
Resulting from 1540660 Multiple Fluorescent Lights in Need Repair
Inspection 1540819 Missed 50.59 Evaluation on Scaffold Installed
Greater Than 90 Days
1542830 2019 Revised Heat loads Missing From Calculation
1542844 0-TI-79.000 Requires Update for frequency
1544436 Revise Calculation WBNEEBMST1060029
Drawings 0-15E500-1 Key Diagram, Aux. Power Station Rev. 8
0-15E500-2 Key Diagram, Aux. Power Station Rev. 0
0-15E500-2 Key Diagram Station Aux Power System Rev. 0
0-15E500-3 Transformer Taps & Voltage Limits, Aux Power Rev. 3
System
0-45W760211-4 Wiring Diagram, 6900V Shutdown Power Schematic Rev.0
Diagram,
0-47W866-8 Heating Cooling and Ventilating Air Flow Flow Rev. 1
Diagram
1-45W600-47-1 Wiring Diagram Turbo- Generator Auxiliaries Rev. 13
Schematic Diagrams
1-47W610-47-1 Electrical Control Diagram Turbo Generator Cont Rev. 40
Sys
1-47W611-99-6 Electrical Logic Diagram Reactor Protection System Rev. 4
2-45W724-3 Wiring Diagrams, 6900V Shutdown Board 2A-A Rev. 18
Single Line
2-45W724-4 Wiring Diagrams, 6900V Shutdown Board 2B-B Rev. 19
Single Line
2-45W749-1 Wiring Diagrams, 480V Shutdown Board 2A1-A Rev. 17
Single Line
2-45W749-2 Wiring Diagrams, 480V Shutdown Board 2A2-A Rev. 14
Single Line
Inspection Type Designation Description or Title Revision or
Procedure Date
2-45W749-3 Wiring Diagrams, 480V Shutdown Board 2B1-B Rev. 15
Single Line
2-45W749-4 Wiring Diagrams, 480V Shutdown Board 2B2-B Rev. 24
Single Line
2-45W760-211-1 , Wiring Diagram, 6900V Shutdown Power Rev. 3
Schematic Diagram
2-45W760-211-12 Wiring Diagram, 6900 V Shutdown Power 2A-A Rev. 2
Schematic Diagrams
2-45W760-211-13 Wiring Diagram, 6900 V Shutdown Power 2A-A Rev. 3
Schematic Diagrams
2-45W760-211-16 Wiring Diagram, 6900 V Shutdown Power Diesel Rev. 1
Loading Logic
2-45W760-211-17 Wiring Diagram, 6900 V Shutdown Power -Train A Rev. 3
And B Schematic Diagram,
2-45W760-211-18 Wiring Diagram, 6900 V Shutdown Power Schematic Rev. 4
Diagram
2-45W760-211-2 Wiring Diagram, 6900V Shutdown Power Schematic Rev. 1
Diagram
2-45W760-211-3 Wiring Diagram, 6900V Shutdown Power Schematic Rev. 2
Diagram
2-45W760-211-5 Wiring Diagram, 6900 V Shutdown Power Schematic Rev. 1
Diagram
2-45W760-211-6 Wiring Diagram, 6900V Shutdown Power Train A Rev. 1
Schematic Diagram
2-45W760-212-1 Wiring Diagram, 480V Shutdown Power Schematic Rev. 1
Diagrams
2-45W760-212-2 Wiring Diagram, 480V Shutdown Power Schematic Rev. 1
Diagrams
2-45W760-268-1 Unit 2 Wiring Diagram Permanent Hydrogen Rev. 4
Mitigation System Schematic Diagrams
2-45W760-63-1 Wiring Diagram, Safety Injection System Schematic Rev. 9
Diagram
2-47W809-1 Flow Diagram CVCS Rev. 46
Inspection Type Designation Description or Title Revision or
Procedure Date
2-47W810-1 Flow Diagram, RHR System Rev. 26
2-47W811-1 Flow Diagram, Safety Injection System Rev. 54
45N1612-2 Turbine Instrumentation & Auxiliaries Connection Rev. 8
Diagrams Wiring Diagram -Sheet 2
8002577-1-1 Unit 1 Schematic Diagram Turbine Driven AFW Rev. 0
Governor
2UU-001-12BB Rev. J
CNL-15-088 TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 - 06/17/15
Application to Revise Technical Specification for
Component Cooling Water and Essential Raw
Cooling Water to Support Dual Unit Operation (TS-
WBN-15-13)
WBN 1190E37 Safety Injection System Process Flow Diagram Rev. 6
Engineering 53785 Swap Power and Control Cables for ERCW Pumps 02/25/16
Changes B-A and C-A (Train A) and F-B & G-B (Train
B), Rev. A
64063 Install Open Phase Protection Relays Rev.A
66471 Modify SSPS Turbine Trip on Low Fluid Oil Pressure Rev. 1
Function To a Trip on Lox Electrohydraulic Control
(EHC ) Oil Pressure
M-08672-A Polychlorinated Byphenyls Risk Reduction for 03/37/92
Transformers
Engineering 1-Sl-3-923-S Auxiliary Feedwater Pump 1A-S Comprehensive Rev. 18
Evaluations Pump Test
EDQ00023620070003 126V DC VITAL BATTERY SYSTEM ANALYSIS Rev. 42
EDQ0010462016000789 Demonstrated Accuracy for TDAFW Time Delay Rev. 2
Relays
EL-20916 EGSCS MARSH Qualification Report Rev. A
EPMJAF112091 Failure Modes and Effects Analysis for the Auxiliary Rev. 12
Feedwater System
Miscellaneous LTOP White Paper Response 08/29/19
Watts Bar Letter that Revises A Commitment in 10/26/95
Inspection Type Designation Description or Title Revision or
Procedure Date
Watts Bar Generic Letter 90-06 Clarification of 12/22/98
Commitment Letter for Testing Pressurizer Power
Operated Relief Valves
Watts Bar Changes to Power Operated Relief Valve 03/01/99
Surveillance Testing Commitment
480V Quarterly System Walkdown Results, 1/15/15- 01/15/15
06/27/19
CCP-2A Oil Sample Trending Analysis, 09/20/2011
to 04/22/2019
Letter from
- R. Gridley, TVA to USNRC, Subject: 02/27/1989
TVAs Response to NRC Bulletin 88-04, Potential
Safety Related Pump Loss
Westinghouse Letter number LTR-SEE-IV-10-25, 04/28/2016
ECCS Analysis Report
CVCS System Health Report, April 2019
Site Engineering Setpoint And Scaling Document Rev. 2
Loop Number1-T-1-17A, AFW Turbine Pump Room
Temperature Detector
Minimum Flows for Safety Related Pumps in Nuclear 09/23/88
Service
Watts Bar Response Letter to GL 90-06 12/21/90
0-TI-100.011 In-service Testing Program Rev. 1
0-TI-79.000 Program for Implementing NRC Generic Letter 89-13 Rev. 5
2010 Magnetic Pickups (MPUs) Rev. C
1-47A630-46-1 TDAFW Governor Configuration Rev. 1
2-SI-211-1-A 18 Month 6.9 KV Shutdown Board 2A-A Automatic 04/21/19
and Manual Transfer Tests
2-SI-211-3-A 18 Month System Functional Rest on 6900V SD BD 06/24/17
2A-A Degraded Voltage and Undervoltage Relays
2-SI-211-3-A 18 Month System Functional Rest on 6900V SD BD 04/21/19
2A-A Degraded Voltage and
Undervoltage Relays
Inspection Type Designation Description or Title Revision or
Procedure Date
2-SI-211-4-A 92 Day Trip Actuating Device Operational Test of UV 03/20/19
Relays for 2A-A 6,9 KV Shutdown Board
2-SI-211-4-A 92 Day Trip Actuating Device Operational Test of UV 06/18/19
Relays for 2A-A 6,9 KV
Shutdown Board
2-SI-211-4-A 92 Day Trip Actuating Device Operational Test of UV 06/18/19
Relays for 2A-A 6,9 KV Shutdown Board
2-SI-211-5-A Channel Calibration Test on Degraded Voltage 09/07/18
Relays for 6.9KV Shutdown Board 2A-A
2-SI-211-5-A Channel Calibration Test on Degraded Voltage 03/20/19
Relays for 6.9KV Shutdown Board 2A-A
2-SI-211-6-A Channel Calibration Test on Loss of Voltage Relays 03/19/18
for 6.9KV Shutdown Board 2A-A
2-SI-211-6-A Channel Calibration Test on Loss of Voltage Relays 09/07/19
for 6.9KV Shutdown Board 2A-A
2-SI-211-7-A Channel Calibration Test on Load Shed and Diesel 09/07/18
Start Undervoltage Relays for
6.9KV Shutdown Board 2A-A
2-SI-211-7-A Channel Calibration Test on Load Shed and Diesel 03/20/19
Start Undervoltage Relays for 6.9KV Shutdown
Board 2A-A
2-SI-211-8-A Channel Calibration Test on Degraded Voltage and 06/24/17
Loss of Voltage Timing
Relays for 6.9KV Shutdown Board 2A-A
Inspection Type Designation Description or Title Revision or
Procedure Date
2-SI-211-8-A Channel Calibration Test on Degraded Voltage and 04/21/19
Loss of Voltage Timing Relays for 6.9KV Shutdown
Board 2A-A
2-SI-262-1A Unit 2 Train A Auto Start Lockout Test 11/18/17
2-SI-262-1A Unit 2 Train A Auto Start Lockout Test 04/24/19
280-RLCU00079-01 Bechtel Power Corporation Test Report, 2.5 RLIJ 11 02/18/11
Stages Pump Serial No. 48592
8002577-01 Qualification Report For Electronic Governor Speed Rev. 0
Control System (EGSCS)
8002577-PTR-1 Panel Temperature Rise Test Procedure Rev. 3
8002577-TR-1 Test Report For Turbine Control System Rev. 0
CNL-15-147 TVA Letter to NRC, Responses to NRC Acceptance 07/14/15
Review Questions for Watts Bar Nuclear Plant Unit 1
Essential Raw Cooling Water and Component
Cooling System License Amendment Request (TAC
No. MF 6376)
CNL-15-153 TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 - 08/03/15
Response to Request for Additional Information
Relate to Application to Revise Technical
Specifications for Component Cooling Water and
Essential Raw Cooling Water to Support Dual Unit
Operation (TAC No. MF6376)
CNL-15-170 TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 - 08/28/15
Responses to NRC Questions for Watts Bae Nuclear
Plant Unit 1Request for Essential Raw Cooling
Water and Component Cooling Water System
License Amendment Request
CNL-15-181 TVA Letter to NRC, Revisions to Watts Bar Nuclear 09/03/15
Inspection Type Designation Description or Title Revision or
Procedure Date
Plant Unit 1 Essential Raw Cooling Water and
Component Cooling System License Amendment
Request, Including Proposed Changes to Auxiliary
Feedwater Pump Suction Transfer Instrumentation
and Reactor Coolant System Loops - Mode 4
EL-21049 Commercial Grade Dedication Report For The Rev. 0
INTROL Positioner PIN 890265-010
LTR-SCS-15-31 Watts Bar Unit 1 PORV Replacement - Cold 01/04/17
Overpressure Mitigation System (COMS) Setpoint
Analysis
PER 265331 Testing Program for Small Oil Filled Transformers 2010
Report No. 9390 PORV Flow Data Analysis Model 82UU-001-12BB Rev. A
SDD-N3-30AB-4001 Auxiliary Building Heating, Ventilation, Air Rev. 45
Conditioning System (30, 31, 44) Unit 1/Unit 2 QA
Record
SDD-N3-32-4002 Compressed Air System Rev. 15
SDD-N3-3B-4002 AUXILIARY FEEDWATER SYSTEM Rev. 28
SDD-N3-62-4001 Chemical and Volume Control System System Rev. 39
Description
SDD-N3-68-4001 Reactor Coolant System Rev. 41
SECL-94-066 Main Steam Safety Valve and Pressurizer Safety 12/27/94
Valve Setpoint Tolerance Increase form +/- 1% to +/-
3% Safety Evaluation
System Health Report 6.9 KV Medium Voltage Switchgear 10/11/18
Summary
System Health Report 6.9 KV Medium Voltage Switchgear 05/29/19
Summary
System Health Report 480V Load Centers 10/20/17
Summary
System Health Report 480V Load Centers 09/18/18
Summary
System Health Report 480V Load Centers 04/01/19
Inspection Type Designation Description or Title Revision or
Procedure Date
Summary
TAC No.MF6376 NRC Letter to TVA, Watts Bar Nuclear Plant Unit 1 - 10/20/15
Issuance of Amendment Regarding Application to
Revise Technical Specifications for Component
Cooling Water and Essential Raw Cooling Water to
Support Dual Unit Operation
WB-DC-30-28 Low and Medium Voltage Power Systems, Unit Rev. 22
1/Unit 2
WBN EEB-MS-T109-0041 Appendix D, Summary of Heat Generated in Each 02/25/10
Room
WBN PM 1-PIPE-067-C Flushing of ERCW Emergency Makeup Supply To Rev. 8
CCP 1A Oil Coolers
WBN-VTD-GE27-0010 Vendor Manual GE Digital Energy Multilin 735 / 737
Feeder Protection Relay Instruction Manual
WBN-VTD-MT02-0040 Vendor Manual: MTU Onsite Energy Model # 3250-
XC6DT2
SERIAL NUMBERS: 350800-1-1-0113 & 350800-1-
2-0113
WBN-VTD-P025-0040 Pacific Pumps IJ Operating and Maintenance Rev. 7
Instructions
WBN-VTD-T020-0550 Target Rock Technical Manual for PORV Model Rev. D
WBN-VTD-W120-2352 Instructions for Westinghouse Rectangular Core and Rev.0
Coil Assembly Type SL Transformers
WBN-VTD-W120-2358 Instructions for Westinghouse Self-Cooled Rev.0
Transformers
WBN-VTD-W120-2624 Technical Bulletin for Pacific Centrifugal Rev.0
Charging/Safety Injection Pumps
WBNEE8SWW0011 Turbine Driven Auxiliary Feedwater Dedication, Rev. 1
Qualification, and Software Verification & Validation
Inspection Type Designation Description or Title Revision or
Procedure Date
Documentation
WBNP-DS-1830-5402- Certification Design Specification for 1,2-PCV-068- 09/16/14
R005 0334-B & -0340A-A
WBT-D-5655 Westinghouse, Watts Bar Nuclear Plant, Unit 2, Rev. 4
Updated ECCS Analysis Report for Flow Test Data
WCG-ACQ-0419 Seismic Qualification of 6.9 KV SD BD Rev. 2
WCG-ACQ-0421 Seismic Qualification of 6900 V Shutdown Boards for Rev. 8
Added Components and Attached Conduits
WCG-ACQ-0424 Seismic Qualification of 6900 V Shutdown Boards Rev. 6
Logic Panels
WCG-ACQ-0460 Equipment Seismic Evaluation of 480V Shutdown Rev. 0
Board Transformers
Operability CR1372641 Prompt determination of operability documentation Rev. 0
Evaluations
Procedures 0-FSI-5.01 Initial Assessment and FLEX Equipment Staging Rev. 8
0-FSI-5.02 6900V FLEX DG Startup and Alignment Rev. 2
0-FSI-5.03 6.9kV & 480V Shutdown Board Initial FLEX Rev.0
Alignment
0-FSI-5.04 6900V FLEX DG Plant Equipment Loading Rev. 05
0-FSI-7 Loss of Vital Instrumentation or Control Power Rev. 3
0-MI-57.027 Initial Testing of Molded Case Circuit Breakers Rev.0
0-MI-57.200 480 Volt Switchgear Inspection Rev. 2
0-SI-82-3 18 Month Loss of Offsite Power With Safety Injection Rev. 68
0-SI-82-5 18 Month Loss of Offsite Power With Safety Injection Rev.43
0-SI-82-5 18 Month Loss of Offsite Power With Safety Injection Rev.47
0-SOI-211.03 System Operating Instructions, 6.9KV Shutdown Rev.5
Board 2A-A,
0-SOI-212.05 System Operating Instructions, 480V Shutdown Rev. 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Board 2A1-A
1-AOI-16 Loss of Normal Feedwater Rev. 8
1-AOI-25.03 Loss of 120V AC Vital Instrument Power Boards 1-III Rev. 5
or 2-III
1-ARI-57-63 Feedwater & Main Steam Rev. 3
1-SI--68-904-A Reactor Coolant System Valve Position Indication 10/10/18
Verification
2-ARI-8-14 Unit 2 Annunciator Response Instructions, Aux Rev. 1
Power
2-E-0 Reactor Trip Or Safety Injection Rev. 8
2-ECA-0.0 Loss of Shutdown Power Rev. 02
2-ES-1.3 Transfer To Containment Sump Rev. 4
2-SI-211-1-A 18 Month 6.9 KV Shutdown Board 2A-A Automatic Rev. 2
and Manual Transfer Tests
2-SI-3-19 18 Month Channel Calibration of Steam Generator 4 Rev. 8
Turbine Driven AFW Level Control Loop 2-LPL-3-
175
2-SI-3-63 18 Month Channel Calibration of Steam Generator 4 Rev. 9
Auxiliary Feedwater Level Control Loop 2-LPL-3-171
2-SI-3-903-B Valve Full Stroke Exercising During Plant Operation Rev. 9
Auxiliary Feedwater (Train B)
2-SI-3-908 Valve Full Stroke Exercising During Plant Operation Rev. 5
Turbine Driven Auxiliary Feedwater
2-SI-3-920 Valve Position Indication Verification Auxiliary Rev. 8
Feedwater System Turbine Driven AFW Train
2-SI-62-901-A Pump CCP 2A-A, Quarterly Performance Test Rev. 1
2-SI-62-916-A Pump CCP2A-A Pre-service Test During Refueling Rev. 4
Outages
2-SOI-268.01 Permanent Hydrogen Mitigation System Rev.1
2-SOI-62.01 CVCS Charging and Letdown Rev. 20
600112315 Preventive Maintenance Work Instructions, 480V Rev.3
Shutdown Board 2A1-A Relay Calibration Tests
600114255-A Preventive Maintenance Preplanned Text, Protective Rev.3A
Inspection Type Designation Description or Title Revision or
Procedure Date
Relay Operability
BTI-EEB-TI-28 Setpoint Calculations Rev.11
NPG-SPP-09.3 Plant Modification and Engineering Chane Control Rev.30
NPG-SPP-12.8 Nuclear Cyber Security Program Rev. 4
NWS-T-139 NWS Technologies Test Procedure for TVA - Watts Rev. 1
Bar Nuclear Plant, Target Rock Power Operated
Relief Valves (PORV)
Self- 2019 DBAI Self-Assessment Report Rev.1
Assessments
Work Orders 113197994
114522319
114522416
114559272
115972327
115972382
117199468
117351335
117761841
117761842
117823686
1178236913693
117828086645
118086653
118134438
118152988
118191476
118439102
118526808
118681437
118801173
Inspection Type Designation Description or Title Revision or
Procedure Date
118801174
118968515
119001477
119001486
119064791
119065107
119065109
119065476
119080284
119174352
119205642
119281674
119297603
119297605
119301437
119307555
119347104
119347106
119381172
119381222
119430432
119440457
119440469
119518459
119526793
119526805
119526810
119527434
119570164
119570240
119582577
119719602
119837841
Inspection Type Designation Description or Title Revision or
Procedure Date
119837862
119837865
119837866
119896530
119897039
119897107
119903710
119903859
20055311
20355623
19347105
21