IR 05000390/2020003
| ML20315A195 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/10/2020 |
| From: | Tom Stephen NRC/RGN-II/DRP/RPB5 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2020003 | |
| Download: ML20315A195 (15) | |
Text
November 10, 2020
SUBJECT:
WATTS BAR - INTEGRATED INSPECTION REPORT 05000390/2020003 AND 05000391/2020003
Dear Mr. Barstow:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar. On October 20, 2020, the NRC inspectors discussed the results of this inspection with Mr. Anthony Williams 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:
05000390/2020003 and 05000391/2020003
Enterprise Identifier: I-2020-003-0057
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar
Location:
Spring City, TN 37381
Inspection Dates:
July 01, 2020 to September 30, 2020
Inspectors:
N. Childs, Resident Inspector
W. Deschaine, Senior Resident Inspector
J. Diaz-Velez, Senior Health Physicist
J. Hamman, Reactor Inspector
N. Peterka, Fuel Facility Inspector
W. Pursley, Health Physicist
D. Terry-Ward, Construction Inspector
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 rated thermal power (RTP) from the beginning of the inspection period until September 9, when reactor power was reduced to 13% and the turbine was removed from service to repair a steam leak on the HP turbine casing drain line. The unit was returned to RTP on September 13, 2020, and remained at or near RTP for the remainder of the inspection period.
Unit 2 operated at or near RTP 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 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
71111.04 - 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)2A-A centrifugal charging pump (CCP) while 2B-B CCP was out of service for planned maintenance on July 27, 2020
- (2) Unit 2 auxiliary feedwater train (AFW) A and B on September 10, 2020 (3)1A emergency diesel generator (EDG) on September 9, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 (IPS), elevation 711' & 722', essential raw cooling water (ERCW) strainers A & B trains and electrical equipment room on August 24, 2020
- (3) Auxiliary building, elevation 676', units 1 & 2 residual heat removal (RHR) and containment spray pump (CSP) rooms on September 24, 2020
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 diesel generator building (DGB) and intake pump station on July 01, 2020
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 the Unit 1 main generator start up activities following a forced outage due to a steam leak on September 11, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the licensed operator requalification simulator scenario for crew A's response to a failure of the reactor to manually trip on July 16, 2020. In addition, the inspector observed and evaluated the annual licensed operating exam in the simulator on September 9, 2020. Together, these observations make up one sample.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
- (1) Risk assessment for 2B-B EDG being declared inoperable due to thermocouple failure and high risk activity of flow balancing Unit 2 MFW pumps on July 29, 2020.
- (2) Risk assessment for August 11-13, with the emergency gas treatment system (EGTS)
& 2B RHR Pump out of service (OOS) for maintenance.
- (3) Risk assessment conducted on August 21 due to discovery that portions of the AFW piping are not scoped into the ASME Section XI system pressure test program.
- (4) Risk assessment for September 8-11, U1 downpower due to steam leak, auxiliary building gas treatment system (ABGTS) OOS for planned maintenance, B main control room chiller OOS due to low oil level.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
- (1) Immediate determination of operability for condition report (CR) 1626705 for high indicated exhaust temperature on 2B-B EDG.
(2)2B EDG failed to start during performance of 0-SI-82-12-B (CR 1639097).
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Post-maintenance testing of the 2B-B centrifugal charging pump (CCP) following inspection, cleaning and lubrication of the motor, documented in Work Order (WO)
===120879868
- (2) WO 119402900, Replace solenoid valve 1-LSV-003-0156-A (A Train Auxiliary Feedwater System)
- (3) WO 120926322, Emergency Gas Treatment System coolers fan B-B temperature switch calibration (2-TS-30-207A-B), on August 10, 2020
- (4) WO 121291219, Repair oil leak on Component Cooling Water Pump C-S inboard bearing drain plug on August 10, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) WO 121102852, 0-SI-82-20-B, 184 Day Fast Start And Load Test DG 2B-B, Revision
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02)===
The inspectors evaluated:
- (1) Site emergency response to a training in the simulator on July 16, 2020, which involved a failure of the reactor to manually trip.
- (2) Site emergency response to a training in the simulator on September 23, 2020, which began with a steam generator tube leak and progressed into a steam generator tube rupture.
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Auxiliary Building Ventilation Gaseous Discharge and Radiation Monitor 0-RI-90-101
- (2) Unit 1 Steam Generator Blowdown Liquid System and Radiation Monitor 1-RE-90-120
- (3) Station Sump Liquid Discharge Monitoring System 0-RE-90-212
- (4) Unit 2 Shield Building Gaseous Vent Radiation Monitoring System 2-RE-90-400
- (5) Station Liquid Effluent Release System and Radiation Monitor 0-RE-90-122
Sampling and Analysis (IP Section 03.02) (4 Samples)
- (1) Inspectors evaluated weekly sampling for gaseous tritium in the auxiliary building vent.
- (2) Inspectors evaluated weekly particulate and iodine effluent sampling on the plant auxiliary building vent.
- (3) Inspectors evaluated gaseous effluent release sampling for noble gases at the auxiliary building vent.
- (4) Inspectors evaluated liquid effluent samples at the unit one steam generator blowdown system.
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) The inspectors reviewed gaseous release permits: G-20191227-759-C, G-20191230-755-B, G-20200731-935-C and G-20200731-936-C.
- (2) The inspectors reviewed liquid release permits: L-20191231-669-C, L-20191231-670-C, L-20200804-864-C and L-20200804-865-C.
Abnormal Discharges (IP Section 03.04) (2 Samples)
The inspectors evaluated the following abnormal discharges:
- (1) The inspectors reviewed the 2019 Annual Radioactive Effluent Release Report (and the Unmonitored Spills, Leaks, or Unexpected Liquid/Gaseous Discharges running list-non dated) and reviewed licensee dose calculations for an Unit 2 unmonitored Power-Operated Release Valve (PORV) release reported in the 2nd Quarter.
- (2) The inspectors reviewed preliminary information to be included in the upcoming 2020 Annual Radioactive Effluent Release Report (and the Unmonitored Spills, Leaks, or Unexpected Liquid/Gaseous Discharges running list-non dated) and reviewed licensee dose calculations for an Unit 2 unmonitored Power-Operated Release Valve (PORV) release which occurred in the 2nd Quarter.
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2019 to March 31, 2020)
- (2) Unit 2 (January 1, 2019 to March 31, 2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2019 to March 31, 2020)
- (2) Unit 2 (January 1, 2019 to March 31, 2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2019 to March 31, 2020)
- (2) Unit 2 (January 1, 2019 to March 31, 2020)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) Units 1 and 2, 03/31/2019 - 06/30/2020
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Failure to operate the AFW system during startup in Mode 2 and Mode 1 prior to operation of two main feedwater pumps, Noncompliance with LCO 3.3.2 Function 6.e (Auto start of AFW on trip of all MFPs), (CR 110770).
- (2) Main Feedwater Pump Tech Spec Discrepancies, the TS requires 1 channel of auto auxiliary feedwater (AFW) initiation logic per MFW pump to be operable for the functional purposes of automatic initiation of AFW upon trip of all MFW Pumps in MODES 1 and 2. The MODE 2 applicability requirements of this TS is not consistent with standard plant operating practices (CR 147351).
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 20, 2020, the inspectors presented the integrated inspection results to Mr.
Anthony Williams and other members of the licensee staff.
- On August 17, 2020, the inspectors presented the Debrief with site Mgmt inspection results to Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
0-47W803-2
Flow Diagram, Auxiliary Feedwater
2-47W809-1
Flow Diagram Chemical Volume and Control System
Miscellaneous
0-PI-OPS-17.0
Month Locked Valve Verification
SDD-N3-3B-4002
Auxiliary Feedwater System Unit 1 / Unit 2
Procedures
1-GO-3
Unit Startup From Less Than 4% Reactor Power to 30%
Reactor Power
1-SOI-47.02
Turbo-Generator Startup Operation
2-PI-OPS-1-PE
Protected Equipment
2-SOI-3.02
1V, Auxiliary Feedwater System Valve Checklist
2-3.02-1V
Fire Plans
Intake Pumping Station 728' & 741' ELV
AUX-0-676-01
Auxiliary Building, 676' ELV
IPS-0-711-01
Intake Pumping Station 711' & 722' ELV
Miscellaneous
MDN-000-999-
2008-0146
Watts Bar Nuclear 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
71111.11Q Miscellaneous
3-OT-SRE-2003
Licensed Operator Requalification (LOR) Cycle 2003 Periodic
Simulator Exam Anticipated Transient Without Scram (ATWS)
07/16/2020
Corrective Action
Documents
Condition Reports
1639971, 1640166, 1640579
Work Orders
21616863
Repair of 2-LCV-3-148-B
Miscellaneous
Pressurized Water Reactor Operational Risk Review - RED
SHEET dated July 29, 2020
07/29/2020
Corrective Action
Documents
26705
Condition Report
Miscellaneous
System Description Document Standby Diesel Generator
System Unit 1 / Unit 2
Work Orders
119402900
Replace solenoid valve 1-LSV-003-0156-A (A Train Auxiliary
Feedwater System)
08/31/2020
20879868
PM 620620241 - Centrifugal Charging Pump 2B-B Inspection,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cleaning and Lubrication of Motor
20926322
Emergency Gas Treatment System coolers fan B-B
temperature switch calibration (2-TS-30-207A-B)
08/10/2020
21291219
Repair oil leak on Component Cooling Water Pump C-S
inboard bearing drain plug
08/10/2020
Corrective Action
Documents
26705
Condition Report
Procedures
0-SI-82-20-B
184 Day Fast Start and Load Test DG 2B-B
Work Orders
21102852
Work Order
Procedures
EPIP-1 Wallboard
Hot
Watts Bar Hot Initiating Conditions - Modes 1-2-3-4
Calculations
Gas Release
Permit Reports
G-20191227-759-C, G-20191230-755-B, G-20200731-935-C
and G-20200731-936-C
Various
Liquid Release
Permit Report
L-20191231-669-C, L-20191231-670-C, L-20200804-864-C
and L-20200804-865-C
Various
Corrective Action
Documents
Corrective Action
Reports
CRs 1451457, 1486487, 1487405, 1514745, 1522194,
1542172, 1619144
Various
Miscellaneous
July 2019 Part 61
Analyses for DAW
and CVCS
Part 61 Analysis Report
Various
Results of
Radiochemistry
Cross Check
Program 1 Qtr
20
Radiochemistry Cross Check Program 1 Qtr 2020
05/20/2020
Results of
Radiochemistry
Cross Check
Program 2 Qtr
20
Radiochemistry Cross Check Program 2 Qtr 2020
07/12/2020
Results of
Radiochemistry
Cross Check
Program 3 Qtr
Radiochemistry Cross Check Program 3 Qtr 2019
11/05/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019
Results of
Radiochemistry
Cross Check
Program 4 Qtr
2019
Radiochemistry Cross Check Program 4 Qtr 2019
2/23/2019
Procedures
0-CM-9.7.101
Auxiliary Building Exhaust Effluent Monitor Grab Sampling and
Filter Replacement
0-CM-9.7.132
Service Building Exhaust Effluent Monitor
0-ODI-40-01
Quantification of Nuclide Activity Released From Groundwater
0-ODI-90-1
Liquid Radwaste Tank Release
0-ODI-90-10
Quarterly Analyses On Gaseous And Liquid Effluents
0-ODI-90-11
Monthly Dose Reports
0-ODI-90-12
Monthly Analyses On Gaseous and Liquid Effluents
0-ODI-90-13
Conditional Total Dose From Liquid and Gaseous Effluents
CM-9.09
Effluent Radiation Monitor Alarm Response Guidelines
CM-9.85
OpenEMS Effluent Management System
CM-9.92
Continuous Liquid Release Permit Generation
CM-9.93
Abnormal Release Assessment
CM-9.94
Continuous Gaseous Release Permit Generation
CM-9.97
Manual Liquid Pre-Release Permit Generation
CM-9.98
Manual Gaseous Pre-Release Permit Generation
Calibration
Records
Instruction
Number 450.01-
005
Watts Bar Meteorological Tower Temperature Sensor
Calibration
07/19/2019
Instruction
Number: 450.01-
005
Watts Bar Meteorological Tower Temperature Sensor
Calibration
01/07/2020
Instruction
Number: 450.01-
019
Calibration of Vaisala Ultrasonic Wind Sensor - Nuclear
07/11/2019
Miscellaneous
2019 Annual Radiological Environmental Operating Report
05/01/2020
Meteorological
Nuclear Plant Meteorological Data Recoverability for 1st
04/19/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Data
Quarter 2020
Meteorological
Data
Nuclear Plant Meteorological Data Recoverability for 2019
01/20/2020
Procedures
0-ODI-10-22
Month Channel Calibration Meteorological Monitoring
Instrumentation
0-ODI-999-03
Food Products
0-ODI-999-05
Collection of Radiological Environmental Monitoring Samples
0-ODI-999-07
Land Use Survey
0-PI-CEM-11.0
Groundwater Monitoring
NPG-SPP-05.15
Fleet Groundwater Protection Program
71151
Procedures
NPG-SPP-02.2
Performance Indicator Program
Corrective Action
Documents
110770
Noncompliance with LCO 3.3.2 Function 6.e
2/28/2006
147351
Main Feedwater Pump Tech Spec Discrepancies
08/05/2009