IR 05000259/2020001
| ML20128H821 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/07/2020 |
| From: | Tom Stephen NRC/RGN-II/DRP/RPB5 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2020001 | |
| Download: ML20128H821 (16) | |
Text
May 5, 2020
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2020001, 05000260/2020001, AND 05000296/2020001
Dear Mr. Barstow:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On April 10, 2020, the NRC inspectors discussed the results of this inspection with Steven M. Bono, Site Vice President 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. 05000259, 05000260, and 05000296 License Nos. DPR-33, DPR-52, and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000259, 05000260, and 05000296 License Numbers: DPR-33, DPR-52, and DPR-68 Report Numbers: 05000259/2020001, 05000260/2020001, and 05000296/2020001 Enterprise Identifier: I-2020-001-0054 Licensee: Tennessee Valley Authority Facility: Browns Ferry Nuclear Plant Location: Athens, Alabama Inspection Dates: January 01, 2020 to March 31, 2020 Inspectors: N. Hobbs, Acting Senior Resident Inspector M. Kirk, Resident Inspector M. Magyar, Reactor Inspector A. Nielsen, Senior Health Physicist N. Peterka, Resident Inspector A. Rosebrook, Senior Reactor Analyst D. Seat, Project Engineer 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 Browns Ferry Nuclear Plant, 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 05000259, 05000260, LER 2019-002-00 for 71153 Closed 05000296/2019-002-00 Browns Ferry Nuclear Plant,
Units 1, 2, and 3,
Unanalyzed Condition Due to Inoperable Security Doors Following a Lightning Strike
PLANT STATUS
Unit 1 operated near rated thermal power until January 3, 2020 when the unit down powered to 50 percent power to perform maintenance on the 1A2 condenser waterbox. The unit returned to rated thermal power on January 8, 2020 and operated at or near this power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On February 13, 2020, the unit was down powered to 78 percent power due to degrading condenser vacuum due to blockages in the 2B1 waterbox. The blockages were cleared, and the unit returned to rated thermal power on February 14, 2020. Unit 2 operated at or near rated thermal power for the remainder of the inspection period.
Unit 3 began the inspection period at rated thermal power. On January 25, 2020, while the unit was in coast down for the scheduled refueling outage, the 3A Recirculation Pump tripped resulting in a rapid down power to approximately 36 percent power. Unit 3 returned to 96 percent power on February 4, 2020 and continued the coast down to the refueling outage. On February 22, 2020, the unit was shut down for a planned refueling outage. On March 25, 2020, Unit 3 began reactor startup and was in the process of power ascension activities to rated thermal power the remainder of the 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.
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 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 and during that time conducted plant status activities as described in IMC 2515, Appendix D; and observed risk significant activities when warranted. 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 the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
- Intake Structure
- Service Water Pump Rooms
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 3, Alternate Decay Heat Removal (ADHR) system on March 3, 2020.
- (2) Unit 1, 2, and 3, Electrical lineup of the 4160V AC system during Unit 3 refueling outage and 3EC and 3ED shutdown boards out of service for maintenance on March 5, 2020.
- (3) Unit 1, 2, and 3, A and B trains of Standby Gas Treatment (SGT) System with C train unavailable on March 11, 2020.
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 Reactor Core Isolation Cooling (RCIC) system on January 15, 2020.
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) Unit 2 Reactor Building Elevation 593 feet and Elevation 565-593 feet Residual Heat Removal (RHR) Heat Exchanger Rooms, Fire Area 02-04 on January 24, 2020.
- (2) Unit 1, 2, and 3, Main Control Rooms, Fire Area 16-A on January 29, 2020.
- (3) Unit 2 Auxiliary Instrument Room #2, Fire Area 16-M on February 14, 2020.
- (4) Unit 1, 2, and 3 Turbine Building, Fire Area 26-A on February 27, 2020.
- (5) Unit 1, 2, and 3, Intake Pumping Station and CCW Pump Deck, Fire Area 25-1 on March 30, 2020.
71111.06 - Flood Protection Measures
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Hand holes 15 and 26 containing safety related underground cables on January 15, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 and 2, C EDG Coolers C1 and C2 on January 17, 2020.
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors evaluated boiling water reactor non-destructive testing by reviewing the following examinations from March 2 - 5, 2020:
1. Ultrasonic Testing (UT)a. KMS-3-055, High Pressure Coolant Injection (HPCI) Tee to Pipe weld, ASME Class 1 (observed)b. N10-SE, Standby Liquid Control (SLC) Nozzle-to-Safe-End weld, ASME Class 1 (observed)c. N10-1, Pipe-to-Tee weld, ASME Class 1, Manual UT (observed)2. Penetrant Testing (PT)a. RFW-3-026-007-C0R1, Reactor Feed Water Check Valve weld, ASME Class 1 (reviewed)
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 following activities:
- Unit 3 shutdown on February 21 and 22, 2020.
- Unit 3 startup activities on March 25, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) Inspectors observed and evaluated licensed operator requalification in the simulator on January 22, 2020.
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:
- (1) Units 1 and 2, C EDG 7 day diesel fuel tank clean and inspection performed every 10 years.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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 associated with extended maintenance outage of C EDG during January 13 to 21, 2020.
- (2) Emergent risk associated with Unit 3 following failure of the 3A Variable Frequency Drive and the 3B Reactor Feedwater (RFW) Pump from January 25 to 31, 2020.
- (3) Emergent risk associated with Unit 3 following loss of 161kV offsite power and normal power supply to Auxiliary Decay Heat Removal while Shutdown Cooling was unavailable on March 3, 2020.
- (4) Planned risk associated with the NFPA 805 High Risk Evolution during Unit 3 reactor cavity flood up, as well as lifting of the drywell and reactor heads on February 23 and 24, 2020.
- (5) Emergent risk associated with Units 1 and 2 entering day 7 of a 7-day shutdown LCO Action Statement for inoperable C Standby Gas Treatment System on March 11, 2020, during Unit 3 Yellow Outage Risk windows for AC Power Sources and Primary/Secondary Containment.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Units 1, 2 and 3, Past operability evaluation of Control Room Emergency Ventilation (CREV) Train B following a failure to start during a surveillance test on January 7, 2020.
- (2) Unit 3, Operability evaluation for RCIC turbine vibration data taken outside of test band on January 29, 2020.
- (3) Units 1, 2, and 3, Operability evaluation of a 4kV load shed relay for Residual Heat Removal Service Water (RHRSW) pumps which was outside of its calibration frequency on February 4, 2020.
- (4) Unit 3, Operability evaluation of 3ED 4kV Shutdown Board following failure of DC power supply to the board on March 3, 2020.
- (5) Unit 3, Operability evaluation of Core Spray (CS) testable check valve, 3-CKV-75-26, upon discovery of difficult operation on March 18, 2020.
- (6) Unit 3, Operability of 3-PCV-001-0023, Main Steam (MS) line B relief valve, after failing to manually cycle on March 25, 2020.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 3, installation of temporary power to Emergency High Pressure Makeup battery charger following failure of 480V control power supply.
- (2) Unit 3, DCN 71507, Foxboro intelligent automation distributed control systems upgrade for the feedwater level control system (FWLC) and reactor recirculation control system (RRCS).
- (3) Unit 2, ECP BFN-20-1115, Modification to Unit 2 Auto Voltage Regulator to eliminate electrical noise spikes, which had potential to cause a turbine trip.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Unit 2, 2-TI-380, Attachment 8, Turbine Stop Valve Testing following a tuning adjustment to the Electro-Hydraulic Control system on January 23, 2020.
- (2) Unit 3, post-maintenance testing following repairs to the Refueling Platform after a relay failure affecting platform movement on February 25, 2020.
- (3) Unit 3, Post maintenance test following repairs to the 3ED 4kV Shutdown Board and associated 3D EDG output breaker on March 11, 2020.
- (4) Unit 3, Post maintenance test following repairs to fix backseated HPCI inboard steam isolation valve (73-2) on March 13, 2020.
- (5) Unit 3, Post maintenance testing following outage maintenance work on the inboard and outboard Main Steam Isolation Valves (MSIVs) on March 19, 2020.
- (6) Unit 3, Post maintenance testing following a design change to the HPCI system inboard discharge valve (73-44) actuator on March 26, 2020.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 3 refueling outage from February 22 until March 26, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
===February 4, 2020.
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)===
- (1) Unit 3, 3-SI-4.7.A.2.g-3/3b, Primary Containment Local Leak Rate Test Reactor Feedwater Line B: Penetration X-9B, RCIC Check Valve 71-40 on March 1, 2020.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill on February 5,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers.
Contamination and Radioactive Material Control (IP Section 03.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors observed surveys of potentially contaminated objects and personnel being released from the Radiologically Controlled Area.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors observed diving activities in the Unit 3 Equipment Pit. This involved the use of significant contamination controls.
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (1 Sample)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 3 Reactor Building, Unit 3 Drywell, and Unit 1 Turbine Building.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===
- (1) Unit 1 - January 1, 2019 - December 31, 2019.
- (2) Unit 2 - January 1, 2019 - December 31, 2019.
- (3) Unit 3 - January 1, 2019 - December 31, 2019.
BI02: RCS Leak Rate Sample (IP Section 02.11) (3 Samples)
- (1) Unit 1 - January 1, 2019 - December 31, 2019.
- (2) Unit 2 - January 1, 2019 - December 31, 2019.
- (3) Unit 3 - January 1, 2019 - December 31, 2019.
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) March 22, 2019 - February 28, 2020
71152 - Problem Identification and Resolution
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) Unit 2 Reactor Protection System received multiple half scram signals on both 'A' and
'B' channels over a multiple month period in 2019 and 2020.
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 05000259/2019-002-00 (ADAMS Accession No. ML19316B896) Unanalyzed Condition Due to Inoperable Security Doors Following a Lightning Strike. 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 did not identify a violation of NRC requirements.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 28, 2020, the inspectors presented the Radiation Protection Baseline Inspection results to S. M. Bono, Site Vice President and other members of the licensee staff.
- On March 5, 2020, the inspectors presented the In-Service Inspection results to S. M.
Bono and other members of the licensee staff.
- On April 10, 2020, the inspectors presented the integrated inspection results to S. M.
Bono and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Corrective Action CR 1570223,
Documents 1580250,
1580253
Miscellaneous BFN Freeze Protection Open WO's, dated January 21, 2020
Procedures 0-GOI-200-1 Freeze Protection Inspection Revision 92
EPI-0-000- Freeze Protection Program for RHRSW Pump Rooms and
FRZ001/2/3 Diesel Generator Bldg Air Plenums
71111.04 Corrective Action CR 1577204,
Documents 1577122,
1577402,
1577997
CR 1591844, CR
1584713
Drawings 0-15E500-1 Key Diagram of Standby Auxiliary Power System Revision 49
0-47E610-72-1 Control Diagram Aux Decay Heat Removal System Sheet 1 Revision 6
0-47E865-11 Flow Diagram Heating and Ventilating Standby Gas Revision 32
Treatment System
2-47E813-1 Flow Diagram reactor Core Isolation Cooling System Revision 60
PIP-02-03 AC Electrical Distribution System Browns Ferry Nuclear 07/30/2019
Plant
Procedures 0-GOI-300-1/ATT- Attachment 12 Outside Operator Round Log Revision 256
0-OI-57A Switchyard and 4160V AC Electrical System Revision 166
0-OI-65 Standby Gas Treatment System Revision 55
0-OI-72 Auxiliary Decay Heat Removal System Revision 65
Work Orders WO 120159976
71111.05 Procedures FPR-Volume 2 Fire Protection Report Volume 2 Revision 65
71111.06 Drawings 0-47E610-72-2 Control Diagram Aux Decay Heat Removal System Sheet 2 Revision 6
71111.07A Engineering Eddy Current Examination Results for Diesel Generator 01/13/2020
Evaluations Coolers 0C1 and 0C2
Heat Exchanger Visual Inspection and Evaluation Form 01/13/2020
71111.12 Miscellaneous Diesel Generator 7 Day Tank 1C Modified API-653 Internal
Inspection Type Designation Description or Title Revision or
Procedure Date
Inspection and Integrity Assessment
71111.13 Procedures BFN-ODM-4.18 Protected Equipment Revision 24
71111.15 Corrective Action CR 1582855,
Documents 1584271,
1591755,
1592393
CR 1595630,
1596262,
1596478,
1597045
CR 1597512,
1598375
Drawings 3-45E724-9 Wiring Diagram 4160V Shutdown Bd 3ED Single Line Revision 36
Engineering U3 RCIC PDO Cancellation Request - CR 1582855
Evaluations
Operability POE for CR
Evaluations 1577322
Procedures 3-SI-3.2.27(I) 3-CKV-75-26 Operability Test Revision 14
3-SR-3.4.3.2 Main Steam Relief Valve Manual Cycle Test Revision 13
NEDP-27 Past Operability Evaluations Revision 5
OPDP-8 Operability Determination Process and Limiting Conditions Revision 25
for Operation Tracking
Work Orders WO 120593810,
21154688
21219529
71111.18 Corrective Action CR 1581261,
Documents 1579772,
1576373
Drawings 3-45E723-5 Wiring Diagram 480V EHPM Distr Bd 3 Connection Diagram Revision 0
Engineering DCN 71507 Upgrade BFN U3 Foxboro I/A System 05/31/2019
Changes ECP BFN-20- Unit 2 Main Generator Voltage Regulator Alarm: GEN
1115 VOLTS PER HERTZ HIGH
Procedures PMTI-71507-2B Reactor Feedwater Level Control System - Startup and Revision 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Power Ascension Testing
PMTI-71507-4B Reactor Recirculation Control System - Pump Operational Revision 0
Testing
Work Orders WO 121044571,
21045025,
21134364
71111.19 Corrective Action CR 1571310
Documents CR 1588781
CR 1589859
CR 1593531,
1594033
Drawings 3-45E714-2 Wiring Diagram 250V DC Reactor MOV Board 3A Schematic Revision 22
Diagram
Engineering DEC 72768
Changes
Procedures 2-TI-380 Power Ascension Turbine Valve Test Revision 6
3-SR-3.6.1.3.6 Main Steam Isolation Fast Closure Test Revision
0015
EPI-3-079- Refueling Platform Inspection Revision 38
CRA001
Work Orders WO 119644420
WO 119966455,
119644438
WO 120020555
21134658
71111.22 Calculations MDQ2075890109 Core Spray Acceptance Criteria for Technical Specification Revision 15
Operability Surveillance
Procedures 3-SI-4.7.A.2.g- Primary Containment Local Leak Rate Test Reactor Revision
3/3b Feedwater Line B: Penetration X-9B 0016
3-SR-3.8.1.9 (3B Diesel Generator 3B Emergency Load Acceptance Test with Revision 20
Inspection Type Designation Description or Title Revision or
Procedure Date
OL) Unit 3 Operating
Work Orders WO 119610636
WO 119644293
71114.06 Miscellaneous BFN February 2020 Training Drill Package 02/05/2020
71124.01 Corrective Action CR 1509096 04/18/2019
Documents
Procedures RCI-1.4 Radiation Protection Particulate CAM Maintenance Rev. 0005
Radiation 0-SI-4.8.E Leak Test, Inventory, and Documentation of Radioactive 08/06/2019
Surveys Sources
AS-228-3 550' Drywell Air Sample 02/24/2020
71152 Corrective Action CR 1542569,
Documents 1585488,
1593265
71153 Corrective Action CR 1548094
Documents
14