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
October 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:
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
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
Procedure
Type
Designation
Description or Title
Revision or
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
Pumps 1A-A and 2A-A Oil Coolers
Rev. 5
EPMHV0701889
Maximum Brake Horsepower for Centrifugal
Charging Pumps
Rev. 5
EPMPKB012191
HVAC Cooling Load and Room Temperature Calc:
TDAFW Pump Room
Rev. 11
EPMSHC102789
Main Steam Over Pressure Protection Design
Rev. 0
EPMSNM043092
Failure Modes and Effects Analysis for the SI
System
Rev. 0
EPMTEC081689
Cooling Load for CCP Room Aux Building Elevation
2-A9 and A10 Under LOCA Conditions
Rev. 5
N36232A
Summary of Piping Analysis
Rev. 9
R03521E31920108300
Shutdown Board 1A-A Feeders to 6900/480V
Transformers 1A1-A, 1A2-A, and 1A-A
Rev.0
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
Relays Requirement/ Demonstrated Accuracy
Calculation
Rev. 12
Calibration
Certificate of Calibration for NWS-T-139 & NWS-R-
04/13/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Records
Corrective Action
Documents
1158981
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
Procedure
Type
Designation
Description or Title
Revision or
Date
480993
934675
940480
Corrective Action
Documents
Resulting from
Inspection
1540525
2A CCP Oil Leak
1540541
Calculation References Not Updated
1540660
Multiple Fluorescent Lights in Need Repair
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
System
Rev. 3
0-45W760211-4
Wiring Diagram, 6900V Shutdown Power Schematic
Diagram,
Rev.0
0-47W866-8
Heating Cooling and Ventilating Air Flow Flow
Diagram
Rev. 1
1-45W600-47-1
Wiring Diagram Turbo-Generator Auxiliaries
Schematic Diagrams
Rev. 13
1-47W610-47-1
Electrical Control Diagram Turbo Generator Cont
Sys
Rev. 40
1-47W611-99-6
Electrical Logic Diagram Reactor Protection System
Rev. 4
2-45W724-3
Wiring Diagrams, 6900V Shutdown Board 2A-A
Single Line
Rev. 18
2-45W724-4
Wiring Diagrams, 6900V Shutdown Board 2B-B
Single Line
Rev. 19
2-45W749-1
Wiring Diagrams, 480V Shutdown Board 2A1-A
Single Line
Rev. 17
2-45W749-2
Wiring Diagrams, 480V Shutdown Board 2A2-A
Single Line
Rev. 14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-45W749-3
Wiring Diagrams, 480V Shutdown Board 2B1-B
Single Line
Rev. 15
2-45W749-4
Wiring Diagrams, 480V Shutdown Board 2B2-B
Single Line
Rev. 24
2-45W760-211-1
, Wiring Diagram, 6900V Shutdown Power
Schematic Diagram
Rev. 3
2-45W760-211-12
Wiring Diagram, 6900 V Shutdown Power 2A-A
Schematic Diagrams
Rev. 2
2-45W760-211-13
Wiring Diagram, 6900 V Shutdown Power 2A-A
Schematic Diagrams
Rev. 3
2-45W760-211-16
Wiring Diagram, 6900 V Shutdown Power Diesel
Loading Logic
Rev. 1
2-45W760-211-17
Wiring Diagram, 6900 V Shutdown Power -Train A
And B Schematic Diagram,
Rev. 3
2-45W760-211-18
Wiring Diagram, 6900 V Shutdown Power Schematic
Diagram
Rev. 4
2-45W760-211-2
Wiring Diagram, 6900V Shutdown Power Schematic
Diagram
Rev. 1
2-45W760-211-3
Wiring Diagram, 6900V Shutdown Power Schematic
Diagram
Rev. 2
2-45W760-211-5
Wiring Diagram, 6900 V Shutdown Power Schematic
Diagram
Rev. 1
2-45W760-211-6
Wiring Diagram, 6900V Shutdown Power Train A
Schematic Diagram
Rev. 1
2-45W760-212-1
Wiring Diagram, 480V Shutdown Power Schematic
Diagrams
Rev. 1
2-45W760-212-2
Wiring Diagram, 480V Shutdown Power Schematic
Diagrams
Rev. 1
2-45W760-268-1
Unit 2 Wiring Diagram Permanent Hydrogen
Mitigation System Schematic Diagrams
Rev. 4
2-45W760-63-1
Wiring Diagram, Safety Injection System Schematic
Diagram
Rev. 9
2-47W809-1
Flow Diagram CVCS
Rev. 46
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-47W810-1
Flow Diagram, RHR System
Rev. 26
2-47W811-1
Flow Diagram, Safety Injection System
Rev. 54
Turbine Instrumentation & Auxiliaries Connection
Diagrams Wiring Diagram -Sheet 2
Rev. 8
8002577-1-1
Unit 1 Schematic Diagram Turbine Driven AFW
Governor
Rev. 0
Rev. J
CNL-15-088
TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 -
Application to Revise Technical Specification for
Component Cooling Water and Essential Raw
Cooling Water to Support Dual Unit Operation (TS-
WBN-15-13)
06/17/15
WBN 1190E37
Safety Injection System Process Flow Diagram
Rev. 6
Engineering
Changes
53785
Swap Power and Control Cables for ERCW Pumps
B-A and C-A (Train A) and F-B & G-B (Train
B), Rev. A
2/25/16
64063
Install Open Phase Protection Relays
Rev.A
66471
Modify SSPS Turbine Trip on Low Fluid Oil Pressure
Function To a Trip on Lox Electrohydraulic Control
(EHC ) Oil Pressure
Rev. 1
M-08672-A
Polychlorinated Byphenyls Risk Reduction for
Transformers
03/37/92
Engineering
Evaluations
1-Sl-3-923-S
Auxiliary Feedwater Pump 1A-S Comprehensive
Pump Test
Rev. 18
EDQ00023620070003
26V DC VITAL BATTERY SYSTEM ANALYSIS
Rev. 42
EDQ0010462016000789
Demonstrated Accuracy for TDAFW Time Delay
Relays
Rev. 2
EL-20916
EGSCS MARSH Qualification Report
Rev. A
EPMJAF112091
Failure Modes and Effects Analysis for the Auxiliary
Feedwater System
Rev. 12
Miscellaneous
LTOP White Paper Response
08/29/19
Watts Bar Letter that Revises A Commitment in
10/26/95
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Watts Bar Generic Letter 90-06 Clarification of
Commitment Letter for Testing Pressurizer Power
Operated Relief Valves
2/22/98
Watts Bar Changes to Power Operated Relief Valve
Surveillance Testing Commitment
03/01/99
480V Quarterly System Walkdown Results, 1/15/15-
06/27/19
01/15/15
CCP-2A Oil Sample Trending Analysis, 09/20/2011
to 04/22/2019
Letter from
- R. Gridley, TVA to USNRC, Subject:
TVAs Response to NRC Bulletin 88-04, Potential
Safety Related Pump Loss
2/27/1989
Westinghouse Letter number LTR-SEE-IV-10-25,
ECCS Analysis Report
04/28/2016
CVCS System Health Report, April 2019
Site Engineering Setpoint And Scaling Document
Loop Number1-T-1-17A, AFW Turbine Pump Room
Temperature Detector
Rev. 2
Minimum Flows for Safety Related Pumps in Nuclear
Service
09/23/88
Watts Bar Response Letter to GL 90-06
2/21/90
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
Month 6.9 KV Shutdown Board 2A-A Automatic
and Manual Transfer Tests
04/21/19
2-SI-211-3-A
Month System Functional Rest on 6900V SD BD
2A-A Degraded Voltage and Undervoltage Relays
06/24/17
2-SI-211-3-A
Month System Functional Rest on 6900V SD BD
2A-A Degraded Voltage and
Undervoltage Relays
04/21/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-SI-211-4-A
Day Trip Actuating Device Operational Test of UV
Relays for 2A-A 6,9 KV Shutdown Board
03/20/19
2-SI-211-4-A
Day Trip Actuating Device Operational Test of UV
Relays for 2A-A 6,9 KV
Shutdown Board
06/18/19
2-SI-211-4-A
Day Trip Actuating Device Operational Test of UV
Relays for 2A-A 6,9 KV Shutdown Board
06/18/19
2-SI-211-5-A
Channel Calibration Test on Degraded Voltage
Relays for 6.9KV Shutdown Board 2A-A
09/07/18
2-SI-211-5-A
Channel Calibration Test on Degraded Voltage
Relays for 6.9KV Shutdown Board 2A-A
03/20/19
2-SI-211-6-A
Channel Calibration Test on Loss of Voltage Relays
for 6.9KV Shutdown Board 2A-A
03/19/18
2-SI-211-6-A
Channel Calibration Test on Loss of Voltage Relays
for 6.9KV Shutdown Board 2A-A
09/07/19
2-SI-211-7-A
Channel Calibration Test on Load Shed and Diesel
Start Undervoltage Relays for
6.9KV Shutdown Board 2A-A
09/07/18
2-SI-211-7-A
Channel Calibration Test on Load Shed and Diesel
Start Undervoltage Relays for 6.9KV Shutdown
Board 2A-A
03/20/19
2-SI-211-8-A
Channel Calibration Test on Degraded Voltage and
Loss of Voltage Timing
Relays for 6.9KV Shutdown Board 2A-A
06/24/17
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-SI-211-8-A
Channel Calibration Test on Degraded Voltage and
Loss of Voltage Timing Relays for 6.9KV Shutdown
Board 2A-A
04/21/19
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
Stages Pump Serial No. 48592
2/18/11
8002577-01
Qualification Report For Electronic Governor Speed
Control System (EGSCS)
Rev. 0
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
Review Questions for Watts Bar Nuclear Plant Unit 1
Essential Raw Cooling Water and Component
Cooling System License Amendment Request (TAC
No. MF 6376)
07/14/15
CNL-15-153
TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 -
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)
08/03/15
CNL-15-170
TVA Letter to NRC, Watts Bar Nuclear Plant Unit 1 -
Responses to NRC Questions for Watts Bae Nuclear
Plant Unit 1Request for Essential Raw Cooling
Water and Component Cooling Water System
License Amendment Request
08/28/15
CNL-15-181
TVA Letter to NRC, Revisions to Watts Bar Nuclear
09/03/15
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
INTROL Positioner PIN 890265-010
Rev. 0
LTR-SCS-15-31
Watts Bar Unit 1 PORV Replacement - Cold
Overpressure Mitigation System (COMS) Setpoint
Analysis
01/04/17
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
Conditioning System (30, 31, 44) Unit 1/Unit 2 QA
Record
Rev. 45
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
Description
Rev. 39
SDD-N3-68-4001
Rev. 41
SECL-94-066
Main Steam Safety Valve and Pressurizer Safety
Valve Setpoint Tolerance Increase form +/- 1% to +/-
3% Safety Evaluation
2/27/94
System Health Report
Summary
6.9 KV Medium Voltage Switchgear
10/11/18
System Health Report
Summary
6.9 KV Medium Voltage Switchgear
05/29/19
System Health Report
Summary
480V Load Centers
10/20/17
System Health Report
Summary
480V Load Centers
09/18/18
System Health Report
480V Load Centers
04/01/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Summary
NRC Letter to TVA, Watts Bar Nuclear Plant Unit 1 -
Issuance of Amendment Regarding Application to
Revise Technical Specifications for Component
Cooling Water and Essential Raw Cooling Water to
Support Dual Unit Operation
10/20/15
WB-DC-30-28
Low and Medium Voltage Power Systems, Unit
1/Unit 2
Rev. 22
WBN EEB-MS-T109-0041
Appendix D, Summary of Heat Generated in Each
Room
2/25/10
Flushing of ERCW Emergency Makeup Supply To
CCP 1A Oil Coolers
Rev. 8
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
Instructions
Rev. 7
WBN-VTD-T020-0550
Target Rock Technical Manual for PORV Model
Rev. D
WBN-VTD-W120-2352
Instructions for Westinghouse Rectangular Core and
Coil Assembly Type SL Transformers
Rev.0
WBN-VTD-W120-2358
Instructions for Westinghouse Self-Cooled
Transformers
Rev.0
WBN-VTD-W120-2624
Technical Bulletin for Pacific Centrifugal
Charging/Safety Injection Pumps
Rev.0
WBNEE8SWW0011
Turbine Driven Auxiliary Feedwater Dedication,
Qualification, and Software Verification & Validation
Rev. 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documentation
WBNP-DS-1830-5402-
R005
Certification Design Specification for 1,2-PCV-068-
0334-B & -0340A-A
09/16/14
WBT-D-5655
Westinghouse, Watts Bar Nuclear Plant, Unit 2,
Updated ECCS Analysis Report for Flow Test Data
Rev. 4
WCG-ACQ-0419
Seismic Qualification of 6.9 KV SD BD
Rev. 2
WCG-ACQ-0421
Seismic Qualification of 6900 V Shutdown Boards for
Added Components and Attached Conduits
Rev. 8
WCG-ACQ-0424
Seismic Qualification of 6900 V Shutdown Boards
Logic Panels
Rev. 6
WCG-ACQ-0460
Equipment Seismic Evaluation of 480V Shutdown
Board Transformers
Rev. 0
Operability
Evaluations
CR1372641
Prompt determination of operability documentation
Rev. 0
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
Alignment
Rev.0
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
Month Loss of Offsite Power With Safety Injection
Rev. 68
0-SI-82-5
Month Loss of Offsite Power With Safety Injection
Rev.43
0-SI-82-5
Month Loss of Offsite Power With Safety Injection
Rev.47
0-SOI-211.03
System Operating Instructions, 6.9KV Shutdown
Board 2A-A,
Rev.5
0-SOI-212.05
System Operating Instructions, 480V Shutdown
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
or 2-III
Rev. 5
1-ARI-57-63
Rev. 3
1-SI--68-904-A
Reactor Coolant System Valve Position Indication
Verification
10/10/18
2-ARI-8-14
Unit 2 Annunciator Response Instructions, Aux
Power
Rev. 1
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
Month 6.9 KV Shutdown Board 2A-A Automatic
and Manual Transfer Tests
Rev. 2
2-SI-3-19
Month Channel Calibration of Steam Generator 4
Turbine Driven AFW Level Control Loop 2-LPL-3-
175
Rev. 8
2-SI-3-63
Month Channel Calibration of Steam Generator 4
Auxiliary Feedwater Level Control Loop 2-LPL-3-171
Rev. 9
2-SI-3-903-B
Valve Full Stroke Exercising During Plant Operation
Auxiliary Feedwater (Train B)
Rev. 9
2-SI-3-908
Valve Full Stroke Exercising During Plant Operation
Turbine Driven Auxiliary Feedwater
Rev. 5
2-SI-3-920
Valve Position Indication Verification Auxiliary
Feedwater System Turbine Driven AFW Train
Rev. 8
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
Outages
Rev. 4
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
Shutdown Board 2A1-A Relay Calibration Tests
Rev.3
600114255-A
Preventive Maintenance Preplanned Text, Protective
Rev.3A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Bar Nuclear Plant, Target Rock Power Operated
Relief Valves (PORV)
Rev. 1
Self-
Assessments
2019 DBAI Self-Assessment Report
Rev.1
Work Orders
113197994
114522319
114522416
114559272
115972327
115972382
117199468
117351335
117761841
117761842
117823686
1178236913693
117828086645
118086653
118134438
118152988
118191476
118439102
118526808
118681437
118801173
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Procedure
Type
Designation
Description or Title
Revision or
Date
119837862
119837865
119837866
119896530
119897039
119897107
119903710
119903859
20055311
20355623
19347105