IR 05000390/2021002
| ML21216A097 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar |
| Issue date: | 08/04/2021 |
| From: | Tom Stephen NRC/RGN-II |
| To: | Jim Barstow Tennessee Valley Authority |
| T Francis | |
| References | |
| IR 2021002 | |
| Download: ML21216A097 (14) | |
Text
August 04, 2021
SUBJECT:
WATTS BAR - INTEGRATED INSPECTION REPORT 05000390/2021002 AND 05000391/2021002
Dear Mr. Barstow:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar. On July 26, 2021, the NRC inspectors discussed the results of this inspection with Ms. Beth Jenkins 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/
Thomas A. Stephen, Chief Reactor Projects Branch #5 Division of Reactor Projects
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:
05000390/2021002 and 05000391/2021002
Enterprise Identifier: I-2021-002-0019
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar
Location:
Spring City, TN 37381
Inspection Dates:
April 01, 2021 to June 30, 2021
Inspectors:
W. Deschaine, Senior Resident Inspector
M. Magyar, Reactor Inspector
K. Miller, Resident Inspector
D. Simpkins, Sr. Tech Training Program Specialist
Approved By:
Thomas A. Stephen, Chief
Reactor Projects Branch #5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Watts Bar, 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.
PLANT STATUS
Unit 1 operated at or near 100 percent rated thermal power for the entire inspection period.
Unit 2 operated at or near 90 percent rated thermal power for the entire inspection period.
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), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and 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
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on June 15, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 1A emergency diesel generator (EDG) while the 1B-B EDG was out of service (OOS) for an 18-year component outage on April 14, 2021
- (2) Unit 1 1A charging and letdown system with the 1B-B charging pump OOS for maintenance outage on May 12, 2021
- (3) Unit 2 2B safety injection pump and associated equipment on June 4, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 EDG system on June 8, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Intake Pumping Station - Elevations 711', 722' and 741' on April 29, 2021
- (2) Cable Spreading Room - Elevation 729' on May 1, 2021
- (3) Mechanical Equipment and 480V Transformer Rooms Elevation 772' on June 3, 2021
- (4) Unit 1 Control Rod Drive Equipment Room, Pressurizer Heater Transformer Room, and Miscellaneous Equipment Room Elevation 782' on June 3, 2021
- (5) Aux Building Corridor Elevation 676' on June 3, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 and 2 Turbine Driven Auxiliary Feedwater Pump Rooms
===71111.07SIX - Heat Sink Performance
Ultimate Heat Sink Containment Device and Dam (IP Section 03.05)===
- (1) Chickamauga Dam, Watts Bar Dam, and the Intake Channel
71111.07T - Heat Sink Performance Heat Exchanger (Service Water Cooled) (IP Section 03.02)
The inspectors evaluated heat exchanger/sink performance on the following:
- (1) Component Cooling System (CCS) 'B' Heat Exchanger (2-HTX-070-0185) (Train A)
- (2) Diesel Generator Cooler 1A-A (1-HTX-082-0720A1-A)
Ultimate Heat Sink (IP Section 03.04) (1 Sample)
- (1) Emergency Raw Cooling Water (ERCW) System, specifically sections 03.04(d) and 03.04(e)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during surveillance testing on June 15th and 23rd, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification simulator scenario for crew 2 group 2A on May 7, 2021. Additionally, the inspectors observed and evaluated a licensed operator requalification simulator scenario for crew 4 group 4B on June 17, 2021. Together these observations make up one sample.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Maintenance Rule 15th Periodic Report
- (2) System 268 - Unit 2 Hydrogen Mitigation System
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Risk assessment for (week of) April 11, 2021, with the 1B-B EDG out of service for an 18-year component outage.
- (2) Risk assessment for (week of) April 19, 2021, with the spent fuel pool cooling system heat exchanger supply header valve and motor driven auxiliary feedwater pump 1A-A SG1 level control valve (WBN-1-LCV-003-164-A) OOS for planned and emergent maintenance.
- (3) Risk assessment for (week of) April 26, 2021, with the 2B-B EDG out of service for an 18-year component outage.
- (4) Risk assessment for (week of) May 3, 2021, with the 2A CCS and 2A Hotwell Pump both OOS for emergent issues.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (9 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
===1694773 & 1638175
- (2) Oil level at the minimum line for 2B diesel generator (DG) governors; Condition Reports (CR) 1696967 & 1696966
- (3) High temperature in U2 turbine driven auxiliary feedwater pump room; CR 1689986
- (4) Low flow alarm 1A DG heating, ventilation and air condition; CRs 1697577 &
1638605
- (5) Unit 2 steam generator #2 sample containment isolation valve, 2-FCV-43-56D, closing stroke time greater than acceptance criteria; CR 1697034
- (6) Unit 2 reactor coolant system cold leg pipe whip restraints missing required shims; CR 1696511 Prompt Determination of Operability
- (7) Unit 1 Incore Thermocouple (1-TE-94-9) that failed to approximately 85 degrees Fahrenheit
- (8) ERCW pressure indicator was less than calculated during 0-SI-67-906-A; CRs 1695859 & 1679101
- (9) ERCW train A component flow debris testing (TI-67.003) found silt in three areas of the system; CR 1696555
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Temporary Design Change WBN-0-2021-040-001 - Temporary Sump Pump in B-Train Intake Pumping Station (IPS) strainer room (TMOD)
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01)===
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Work Order 122042735, Motor Driven AFW Pump 2A-A SG2 Level, Replace Actuator Diaphragm for WBN-2-LCV-003-156-A. Work Order 122042736 completed AOV diagnostic testing IAW MMTP-154 on April 5, 2021.
- (2) Work Order 122060580, Motor Driven AFW Pump 1A-A SG1 Level, Replace Actuator Diaphragm for WBN-1-LCV-003-164-A. Work Order 122060593 completed AOV diagnostic testing IAW MMTP-154 on April 19, 2021.
- (3) Work Order 121852727, Replace the Woodward Governor Control Unit on EDG 2B-B. Maintenance testing of the governors was completed on 4/30/2021. Performance of 0-SI-82-20-B, 184 Day Fast Start and Load Test DG 2B-B was completed on May 1, 2021.
- (4) Work Order 119409894, WBN-1-RLY-062-010C-B, 30RX Relay for Centrifugal Charing Pump Motor 1B-B. PMT was the performance of Section 6.0, Post Maintenance Test, of the work order attachment A on May 12, 2021.
- (5) Work Order 122213569, Replacement of Main Control Room Intake Radiation Monitor 0-RM-90-126 Air Pump on June 28, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Work Order 121529390, Surveillance Instruction 1-SI-62-901-A, Centrifugal Charging Pump (CCP) 1A-A Quarterly Performance Test, Revision 33.
- (2) Work Order 121717428, Surveillance Instruction 0-SI-82-19-A, 184 Day Fast Start and Load Test EDG 2A-A, Revision 35.
- (3) Work Order 121360406, Surveillance Instruction 0-SI-65-8-B, Emergency Gas Treatment System Filter Train-B Test, Revision 21.
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Work Order 121360635, Surveillance Instructions 1-SI-70-914-B, Component Cooling System Pump 1B-B Comprehensive Pump Test, Revision 7.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The residents observed the site emergency response to a training drill which involved a design basis flood on May 26,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 July 2020 - June 2021
- (2) Unit 2 July 2020 - June 2021
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 July 2020 - June 2021
- (2) Unit 2 July 2020 - June 2021
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 July 2020 - June 2021
- (2) Unit 2 July 2020 - June 2021
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 July 2020 - June 2021
- (2) Unit 2 July 2020 - June 2021
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in operability reviews that might be indicative of a more significant safety issue. None were identified during the past six months.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Failure of Flow Control Valve (0-FCO-30-8-A) on the A train Auxiliary Building Gas Treatment System due to a broken wire on pressure transmitter (0-PDT-30-149) - CR
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 26, 2021, the inspectors presented the integrated inspection results to Ms. Beth Jenkins and other members of the licensee staff.
- On June 24, 2021, the inspectors presented the Exit Meeting inspection results to Tony Williams, Site VP and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
MDN-000-999-
2008-0146
WBN Probabilistic Risk Assessment - Internal Flooding
Assessment Notebook
Corrective Action
Documents
Condition Reports 1678255, 1696331, 1701616, 1702231,1702289
Drawings
Intake Pumping Station
Miscellaneous
Flow Diagrams
47W839-1 Rev. 8, 0-47W840-1, 47W866-9 Rev. 10, 0-
47W845-1 Rev. 21, 1-47W809-1 Rev. 68, 2-47W811-1 Rev.
Wiring Diagrams
0-45W760-21-1 Rev. 1, 0-45W760-18-1 Rev. 6, 0-45W760-
30-22 Rev. 4, 0-45W760-30-23 Rev. 5, 0-45W760-211-4
Rev. 14
Procedures
System Operating
Instructions
0-SOI-82.01 Rev. 17, 0-SOI-82.01 ATT 1P, 0-SOI-82.01 ATT
1V Rev. 12, 0-SOI-67.01 Rev. 32, 0-SOI-67.01 ATT 3V
Rev.32, 0-SOI-67.01 ATT 6V Rev. 32, 1-SOI-62.01 Rev. 21
Corrective Action
Documents
Condition Report
1690437, 1690829, 1690831, 1691621
Fire Plans
WBN Fire Protection Report and WBN Pre-Fire Plans
AUX-0-772-01
WBN-Pre-Fire Plan
Miscellaneous
MDN-000-999-
2008-0146
WBN Probabilistic Risk Assessment - Internal Flooding
Analysis Notebook
WB-DC-40-31.51
Evaluating the Effects of Flooding due to Moderate Energy
Pipe Failures Inside and Outside Containment
MDN-000-999-2008-0146, Rev. 03 - WBN Probabilistic Risk
Assessment - Internal Flooding Analysis Notebook
71111.11Q Miscellaneous
3-OT-SRE-
2104AF
Simulator Exercise Guide - Response to Malfunctions at
Power and Faulted Steam Generator
SEG#3-OT-SRT-
E3-15
Steam Generator Tube Rupture (on SG #1) with Leaking
Pressurizer PORV (334)
Procedures
1-SI-3-902
Turbine Driven Auxiliary Feedwater Pump 1A-S Quarterly
Performance Test
Work Orders
Work Orders
118209547, 121716443
Corrective Action
Condition Report
1361921, 1502501, 1514779, 1651493, 1657600, 1667282,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
1686117, 1686118
Miscellaneous
1570, 1625, 1635, 1712, 1713, 1714
Meeting Minutes
MREP Meeting Numbers 21-01 and 21-04
Procedures
0-TI-119
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10 CFR 50.65
Work Orders
Work Orders
119526883, 19526884
Procedures
0-SI-82-2
Hour Diesel Generator AC Power Source Operability
Verification
0-TI-12.16
Diesel Generator Outage T/S or SR Contingency Actions
1-PI-OPS-1-PE
Protected Equipment
NPG-SPP-07.3
Work Activity Risk Management Process
& 35
Corrective Action
Documents
Condition Reports 1638175, 1638605, 1655897, 1689986, 1694773, 1696511,
1696966, 1696967, 1697034, 1697577, 1702519
Fire Plans
WBN-Pre-fire
Plan
Aux-0-676-01, Aux-0-772-01, Rev. 1, Aux-0-772-02, Rev. 5,
Aux-0-772-03, Rev. 5
Miscellaneous
CAP IR-2021-
6074
TS LCO 3.3.3
Post-Accident Monitoring Instrumentation
WAT-D-12769
Letter
Procedures
NPG-SPP-
09.1.21
Evaluation of Changing Stroke Times for 2-FCV-43-56D
5/27/2021
STS 121657191
2-SI-43-901-B, Valve Full-Stroke Exercising During Plant
Operation - Sampling and Water Quality System (Train B)
Work Orders
Work Orders
119965129, 121384804, 121405622, 121509185,
2159793
Corrective Action
Documents
Condition Reports 1678255, 1701616, 1702231, 1702289
Drawings
0-47W853-11
Station Drainage System
Miscellaneous
WBN-0-2021-
040-001
Design Equivalent Change Package, Temporary Sump
Pump in Tr-B IPS Strainer Rm
Corrective Action
Documents
Condition Reports 1389692, 1526542, 1540886, 1554651, 1617426, 1667839,
1675230, 1683845, 1684247, 1686775, 1687704, 1687846,
1687876, 1704143, 1705541, 1705629
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
0-MI-57.029
HFA Relay Maintenance
Procedures
System Operating
Instructions
0-SOI-82.04 Rev. 17, 0-SOI-62.01 Rev. 21
Work Orders
Work Orders
119409894, 120556901, 120660138, 122042735,
2042736, 122060580, 122060593, 122066791,
21852727, 121414067, 122213956
Miscellaneous
SDD-N3-82-4002
Standby Diesel Generator System
Corrective Action
Documents
Condition Reports 1696570, 1702827
Work Orders
Work Orders
21360406, 121360635, 121529390, 121717428