IR 05000390/2019004

Integrated Inspection Report 05000390/2019004, 05000391/2019004 and 07201048/2019001

ML20043F235
Person / Time
Site:	Watts Bar
Issue date:	02/12/2020
From:	Tom Stephen NRC/RGN-II
To:	Jim Barstow Tennessee Valley Authority
References
IR 2019004
Download: ML20043F235 (14)

Text

{{#Wiki_filter:ary 12, 2020

SUBJECT:

WATTS BAR, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000390/2019004, 05000391/2019004 AND 07201048/2019001

Dear Mr. Barstow:

On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar, Units 1 and 2. On January 14, 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, 05000391 and 07201048 License Nos. NPF-90 and NPF-96

Enclosure:

As stated

REGION II== Inspection Report Docket Numbers: 05000390, 05000391 and 07201048 License Numbers: NPF-90 and NPF-96 Report Numbers: 05000390/2019004, 05000391/2019004 and 07201048/2019001 Enterprise Identifier: I-2019-001-0152 Licensee: Tennessee Valley Authority Facility: Watts Bar, Units 1 and 2 Location: Spring City, TN 37381 Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: W. Deschaine, Senior Resident Inspector C. Fontana, Emergency Preparedness Inspector J. Hamman, Resident Inspector D. Lanyi, Senior Operations Engineer S. Ninh, Senior Project Engineer S. Sanchez, Senior Emergency Preparedness Inspector J. Walker, Emergency Response Inspector Approved By: Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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 Type Issue Number Title Report Section Status LER 05000391/2019-001-00 LER 2019-001-00 for Watts 71153 Closed Bar Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed.

LER 05000390/2019-003-00 LER 2019-003-00 for Watts 71153 Closed Bar Nuclear Plant, Unit 1, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed

REPORT DETAILS

PLANT STATUS Unit 1 began the inspection period shutdown for turbine repairs. On October 22, 2019, the unit went critical and returned to rated thermal power on October 24, 2019. Unit 1 remained at or near rated thermal power for the remainder of the inspection period.

Unit 2 operated at or near 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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.02)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures.

External Flooding Sample (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated readiness to cope with external flooding for the following areas:

• Intake Pumping Station
• Emergency Diesel Generator Building

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, A and B motor driven auxiliary feedwater trains, while the turbine driven auxiliary feedwater train was out of service for level control valve trouble shooting and repairs on October 11, 2019.

(2) 1A emergency diesel generator while 1B emergency diesel generator was out of service due to a fire in exciter cubicle on October 30, 2019.

(3) Unit 1 & 2 Auxiliary Control Air System (ACAS) on November 5, 2019.

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configurations during a complete walk down of the Unit 1 and 2 safety injection system on December 30, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Auxiliary building 713.0 elevation on December 30, 2019.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)

(1) The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 23, 2019, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.02, "Requalification Examination Results of IP 71111.11.

The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam and biennial written examination completed on November 18, 2019.

==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 the main control room of Unit 1 during start-up activities coming out of the forced outage on October 21 & 22, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02)==

(1) The inspectors observed simulator scenario 3-OT-SRE-1006, Revision 1, which included a component cooling water pump shaft shear, followed by a hot leg loss of coolant accident with safety injection failing on October 29, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Unit 1 and 2, Function 082-B, Emergency Diesel Generator (a)(1) Evaluation

(2) Unit 1 Function 235-B 120 Vital Instrument Power (a)(1) Evaluation

(3) CR 1556229, Steam Generator #3 Level Control valve, 2-LCV-003-172, stroke time failure on May 22, 2019

(4) Watts Bar Nuclear Plant Units 1 and 2 Maintenance Rule Program (a)(3) Periodic Evaluation

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Risk assessment for week of October 15, with the 1B emergency diesel generator out of service due to a fire in the exciter cubicle

(2) Risk assessment for week of October 28, with the 1B motor driven auxiliary feedwater pump out of service for planned maintenance

(3) Risk assessment for week of November 4, with the A train auxiliary air compressor out of service for planned maintenance

(4) Risk assessment for week of November 18, with the 1A-A emergency diesel generator (EDG) out of service for planned maintenance

(5) Risk assessment for week of December 8, with the Unit 1 Main Steam Loop 4 Pressure Transmitter (1-PT-1-27B) tagged out due to a steam leak and the 1B residual heat removal pump out for planned maintenance

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Operability determination for CR 1561235, failure of lubricating oil pump discharge pressure gauge for 1B-B motor driven auxiliary feedwater pump

(2) Immediate determination of operability for CR 1556746, failure of emergency diesel generator 2A-A room heater

(3) Immediate determination of operability for CR 1556562, abnormal sound in emergency diesel generator engine 2A2 lubrication oil circulation pump

(4) Operability determination for CR 1556571, received window 60-A auxiliary feedwater pump electronic overspeed trip or trouble multiple times

(5) Immediate determination of operability for CR 1541453, excessive seal leakage on E-B essential raw cooling water pump

(6) Immediate determination of operability for CR 1555289, failure of the Unit 2 turbine-driven auxiliary feedwater pump overspeed trip linkage

==71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples) The inspectors evaluated the following temporary or permanent modifications:

(1) Permanent modification design change notice 63820, Addition of a new safety-related auxiliary control air subsystem swing air compressor and air dryer skid

(2) WBN-1-2019-001-001, Temporarily replace flexible hose on 1-PT-1-27B sensing line with a Swagelok fitting to repair a steam leak on December 12, 2019

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

[[IP sample::=

=IP 71111.18|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) WO 120841664, 2-SI-3-16, 18 Month Channel Calibration of Steam Generator 3 Turbine Driven Auxiliary Feed Water Level Control Loop 2-LPL-3-172, following repairs to 2-LCV-003-0172-A on October 11, 2019

(2) WO 120858219, 1-TRI-85-1, Reactivity Control Systems Movable Control Assemblies (Modes 3, 4 AND 5) following circuit card replacement on October 21, 2020

(3) WO 120878153, 1-SI-3-907-B Valve Position Indication (Train B) Auxiliary Feedwater System, following solenoid replacement on 1-LCV-3-148A on October 29, 2019

(4) WO 120289270, post maintenance test run of lubricating oil pump for 1B-B motor driven auxiliary feedwater pump following lube oil pump replacement on October 29, 2019

(5) WO 120846057, emergency diesel generator 1B voltage regulator tuning and postmaintenance testing following the replacement all 3 linear reactors and damaged cables located in the 1B emergency diesel generator exciter cubicle on October 18, 2019

(6) WO 120928508, 0-SI-82-11-A Monthly Diesel Generator Start and Load Test DG 1A-A following emergency diesel generator outage on November 22, 2019

(7) WO 120603491, Postmaintenance testing following replacement of the safety injection pump 1A room cooler coil on October 2, 2019

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) The inspectors evaluated a Unit 1 forced outage due to a unit trip caused by a #2 main feedwater regulating valve failure from August 31, 2019 to October 23, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) WO 118180277, 0-SI-82-7, 10 Year Diesel Generator Interdependence Test

(2) WO 118180277, 0-SI-82-17-A, 184 Day Fast Start And Load Test Diesel Generator 1A-A following Interdependence Test

(3) WO 120452206, 2-SI-3-901-A, Auxiliary Feedwater Pump 2A-A Quarterly Performance Test

(4) WO 120482998, 2-SI-99-10-B, 62 Day Functional Test of SSPS Train B and Reactor Trip Breaker B

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) WO 120450906, 2-SI-68-32 Reactor Coolant System Water Inventory Balance

71114.01 - Exercise Evaluation Inspection Review (IP Section 02.01-02.11)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of November 4, 2019. The exercise scenario simulated an earthquake felt onsite and met the criteria for declaration of an Unusual Event. An aftershock caused the 2B residual heat removal pump to trip and subsequently led to the declaration of an Alert on Unit 2. A loss of condenser vacuum forced the operators to trip the Unit 1 reactor, thereby causing a chain of events that eventually led to a loss of all feedwater and created conditions for declaring a Site Area Emergency. As part of the simulated event response, the operators manually activated safety injection, which in turn created another chain of events that ultimately led to containment pressurization with failure of the containment protection systems. Once radiation levels reached a prescribed threshold, the conditions for a General Emergency were met, and the Offsite Response Organizations were able to demonstrate their ability to implement emergency actions.

71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of November 4, 2019. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation Drill/Training Evolution Observation (IP Section 03.02)

The inspectors evaluated:

(1) The residents observed the site emergency response to a training drill which involved a turbine trip, without an immediate reactor trip, followed by a steam generator tube rupture leading to a general emergency declaration on October 9, 2019.

(2) The residents observed the site emergency response to a training drill which involved a loss-of-coolant accident with a failure of the containment sump recirculation valves to open, on October 30, 2019. The scenario also involved the site emergency response organization using the severe accident mitigation guidelines to try and restore core cooling.

71114.08 - Exercise Evaluation Scenario Review Inspection Review (IP Section 02.01 - 02.04)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below: EP01: Drill/Exercise Performance (IP Section 02.12) ===

(1) EP01: Drill & Exercise Performance for the period October 1, 2018, through September 30, 2019.

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) EP02: Emergency Response Organization Drill Participation for the period October 1, 2018, through September 30, 2019.

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) EP03: Alert & Notification System Reliability for the period October 1, 2018, through September 30, 2019.

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Excessive water found in the 2B motor driven auxiliary feedwater pump outboard bearing oiler due to outboard pump seal leaking a stream of water impacting outboard bearing housing (CR 1444650).

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000390/2019-003-00, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (ADAMS accession: ML19294A010). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

(2) LER 05000391/2019-001-00, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (ADAMS accession: ML19199A085). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated a Unit 1 solid state protection system (SSPS) circuit card failure, with an unexpected reactor trip bypass breaker failure during SSPS troubleshooting, and the licensees performance in response to this issue, on December 31,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

(1) The inspectors evaluated the licensees activates related to long-term operation and monitoring of their independent spent fuel storage installation.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 14, 2020, the inspectors presented the integrated inspection results to Mr.

Anthony Williams and other members of the licensee staff.

• On November 7, 2019, the inspectors presented the Emergency Preparedness Exercise Inspection inspection results to Mr. Tony Williams and other members of the licensee staff.

THIRD PARTY REVIEWS Inspectors reviewed the World Association of Nuclear Operators (WANO) report that was issued for Watts Bar in March 2018.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 60855.1 Procedures 0-SI-79-2 Dry Cask Storage Log Revision 7 71111.01 Corrective Action Condition Reports 1564591, 1562311, 1562302, 1556745, 156746 Documents Miscellaneous 3-OT-STG-084A Flood Mode Boration Makeup System Student Training Revision 8 Guide N3-84-4001 System Description for Flood Mode Boration Makeup Revision 6 System Procedures 0-PI-OPS-1-FP Freeze Protection 21 71111.04S Miscellaneous WBN-SDD-N3- System Description, Safety Injection System Revision 35 63-4001 Procedures 1,2-SOI-63.01 System Operating Instruction for the Safety Injection System Revision 19 71111.05Q Fire Plans AUX-0-713-01 Pre-Fire Plan for Aux Building 713.0 Elevation Revision 1 AUX-0-713-02 Pre-Fire Plan for Aux Building 713.0 Elevation Revision 3 AUX-0-713-03 Pre-Fire Plan for Aux Building 713.0 Elevation Revision 4 71111.12 Miscellaneous Component Deficiency Evaluation 1633 Watts Bar Nuclear Plant Maintenance Rule Expert Panel 11/14/2019 Meeting Minutes 14-PAR-WBN WBN Maintenance Rule Program Fourteenth Periodic Revision 0 Evaluation Assessment Report 10CFR50.65(a)(3) Procedures NPG-SPP-03.4 Maintenance Rule Performance Indicator Monitoring, 3 Trending, and Reporting 71111.13 Miscellaneous Operator's Risk Report 11/18/2019 Procedures 1-PI-OPS-1-PE Protected Equipment 21 NPG-SPP- Equipment Out of Service Management 12 09.11.1 71111.15 Corrective Action Condition Report 1561235, 1556562, 1322853, 1541453, 1454816, 1555289 Documents Miscellaneous SDD-N3-3B-4002 Auxiliary Feedwater System Unit 1 / Unit 2 Revision 29 SDD-N3-82-4002 Standby Diesel Generator System Unit 1 / Unit 2 25 WBN-SDD-N3- Essential Raw Cooling Water System, System 67 Revision 37 67-4002 WBN-VTD-1075- Vendor Manual 27 0080 Inspection Type Designation Description or Title Revision or Procedure Date Procedures 1-SI-0-2B-01 0700-1900 Shift and Daily Surveillance Log Mode 1 87 Work Orders Work Orders 120289270 71111.18 Engineering DCN-63820 Addition of a new safety-related Auxiliary Control Air Revision B Changes Subsystem (ACAS) swing air compressor and air dryer skid WBN-1-2019- Temporarily replace flexible hose on 1-PT-1-27B sense line Revision 0 001-001 with a Swagelok fitting to repair a steam leak 71111.19 Corrective Action Condition Reports 1558700, 1567851 Documents Procedures 0-SI-82-11-A Monthly Diesel Generator Start and Load Test DG 1A-A 54 1-SI-3-907-B Valve Position Indication Verification (Train B) Auxiliary 22 Feedwater System 1-TRI-85-1 Reactivity Control Systems Movable Control Assemblies

                                              (Modes 3, 4 AND 5)

2-SI-3-16 18 Month Channel Calibration of Steam Generator 3 Turbine 10 Driven Auxiliary Feed Water Level Control Loop 2-LPL-3-172 2-SI-3-908 Valve Full Stroke Exercising During Plant Operation Turbine 6 Driven Auxiliary Feedwater Work Orders 120603491 Replacement of the safety injection pump 1A room cooler 10/02/2019 coil 20846057 Replacement all 3 linear reactors and damaged cables 10/18/2019 located in the 1B EDG exciter cubicle Work Orders 120319939, 120841664, 120858219, 120878153, 20193806, 120928508 71111.22 Corrective Action Condition Report 1555433 Documents Procedures 0-SI-82-17-A 184 Day Fast Start And Load Test Diesel Generator 1A-A 29 following Interdependence Test 0-SI-82-7 10 Year Diesel Generator Interdependence Test 14 2-SI-3-901-A Auxiliary Feedwater Pump 2A-A Quarterly Performance Test Revision 10 2-SI-68-32 Reactor Coolant System Water Inventory Balance Revision 5 2-SI-99-10-B 62 Day Functional Test of SSPS Train B and Reactor Trip Revision 11 Breaker B Inspection Type Designation Description or Title Revision or Procedure Date 71114.06 Miscellaneous Watts Bar Nuclear Plant Integrated Training Drill packet 10/09/2019 2019 Watts Bar Nuclear September Training Drill packet 10/30/2019 71153 Corrective Action Condition Reports 1518719, 1284060, 1545537 Documents Miscellaneous 0-IMI-101 Instrument Maintenance Planning and Work Activity Revision 1 Guidelines 0-MI-MVV-003- Maintenance Instruction for Fisher Main Feedwater Revision 19 001.00 Regulating Valve Maintenance WBN-2-MVOP- PM Work Instructions Revision 1 0003-0048 Procedures NPG-SPP-09.20 Vendor Manual Control Revision 8 NPG-SPP-2.5 Vendor Manual Control Revision 0 NPG-SPP-22.500 Operating Experience Program Revision 4 2| ]]