IR 05000259/2021010

Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010

ML21207A006
Person / Time
Site:	Browns Ferry
Issue date:	07/26/2021
From:	James Baptist Division of Reactor Safety II
To:	Jim Barstow Tennessee Valley Authority
References
EPID I-2021-010-0038 IR 2021010
Download: ML21207A006 (17)

Text

July 26, 2021

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000259/2021010 AND 05000260/2021010 AND 05000296/2021010

Dear Mr. Barstow:

On June 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant and discussed the results of this inspection with Mr. Chris Dunn 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/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and 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: 05000259/2021010, 05000260/2021010 and 05000296/2021010 Enterprise Identifier: I-2021-010-0038 Licensee: Tennessee Valley Authority Facility: Browns Ferry Nuclear Plant Location: Athens, AL Inspection Dates: May 17, 2021 to June 11, 2021 Inspectors: C. Baron, Contractor D. Bollock, Senior Reactor Operations Engineer W. Deschaine, Senior Resident Inspector S. Kobylarz, Contractor R. Patterson, Senior Reactor Inspector J. Winslow, Reactor Systems Engineer Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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

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.

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), inspectors were directed to begin telework. In addition, 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

===71111.21M - 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) 250V DC Reactor Motor Operated Valve (RMOV) Board 2B

• Material condition and configuration (e.g., visual inspection during a walkdown)

• Operating environment

• Consistency between station documentation (e.g. procedures) and vendor specifications

• Maintenance effectiveness

• Corrective maintenance records, and corrective action history

• Panel loading

• Load voltage adequacy

• Overcurrent protection and coordination

(2) Emergency Essential Cooling Water (EECW) Strainers

• Material condition and configuration (e.g., visual inspection during a walkdown by onsite inspector)

• Consistency between station documentation (e.g. procedures and drawings)and vendor specifications

• Corrective maintenance records, and corrective action history

• System Health Reports

• Compliance with UFSAR, TS, and TS Bases

• Normal and emergency operating procedures

• Modifications

• Completed surveillance tests to ensure acceptance criteria have been met

(3) 480V RMOV BD 2D

• Material condition and configuration (e.g., visual inspection during a walkdown)

• Operating environment

• Consistency between station documentation (e.g. procedures) and vendor specifications

• Maintenance and Preventive Maintenance effectiveness

• Corrective maintenance records, and corrective action history

• Breaker short circuit capacity

• BD (MCC) loading

• BD (MCC) voltage adequacy

• Overcurrent protection and coordination

(4) Unit 2 Reactor Core Isolation Cooling (RCIC) System Pump 2B

• Normal and Emergency Operating Procedures

• Surveillance Test Procedures and Recent Results

• Inservice Test Procedures and Recent Results

• Bases for Pump Test Acceptance Criteria

• Calculation of Pump Capacity

• Calculation of Pump NPSH

• Calculation of System Pressure due to Pump Overspeed Condition

• Operation of RCIC under Station Blackout Conditions

• Evaluation of RCIC Pump Suction Transfer

• Material Condition of Pump and Associated Equipment

• Corrective Action History Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===

(1) Unit 2 Automatic Depressurization System (ADS) Valves

• Normal and Emergency Operating Procedures

• Calculation of Instrument Air Supply and Air Accumulator Capacity

• Instrument Air Leakage Test Procedures and Recent Results

• Recent Valve Test Results

• Evaluation of Electrical Control and Power Supplies

• Evaluation of Testing of Backup Electrical Control and Power Supplies

• Corrective Action History

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) DCN 71425, Upgrade Unit 1/2 Emergency Diesel Generator Fuel Oil Piping Configuration

(2) DCN 72338-03, Replacement of 4160V/480V Emergency Shutdown Board 2A & 2B Transformer

(3) BFN-19-918-01-U1, High Pressure Coolant Injection Gland Seal Check Valve Addition

(4) DCN 69466A, Replace Core Spray and Residual Heat Removal Room Cooler Fan Motors, Fans, and Shafts

(5) BFN-1-2020-068-003, Temporary Replacement of Recirculation Loop 1B Flow Measurement (T-Mod)

(6) DCN 70747-71, 480V RMOV BD 2A/15D ALT FDR from SD BD

Review of Operating Experience Issues (IP Section 02.06) (2 Samples)

(1) NRC IN 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify

(2) NRC IN 91-50: A Review of Water Hammer Events After

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On June 29, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Chris Dunn and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations BFN-1-47E859-1 Flow Diagram, Emergency Equipment Cooling Water Rev. 99

CDQ-0067-881511 Seismic Qualification for the Automatic Self-Cleaning Rev. 1

Strainer

CDQ-0067894672 Evaluation and Review of Small Bore Unit 0 Piping and Rev. 12

Supports within the Scope of the System 067 Safe

Shutdown Boundary

CDQ-1067895300 Pipe Stress Analysis of Stress Problem No. 1-67-859-1- Rev. 3

CDQ-2067890748 Strainer Backwash Blowdown Piping at Pumping Station Rev. 2

CDQ0303880436 Assess the RHRSW and the EECW Piping and Rev. 2

Components for the Affects of Tornadic Wind- RHRSW

Pump

CDQ0999910005 Evaluation of Seismic- Induced Spray Hazards at BFN, Rev. 3

Unit 2 and Common

CDQ107320021062 Small Bore Piping and Supports Program System Rev. 6

Calculation for Seismic Class 1 HPCI System (73) Piping

CDQ107320031063 Pipe Stress Analysis of Stress Problem N1-173-67R Rev. 1

EDQ0057920034 4.16KV and 480V Busload, Voltage Drop and Short Rev. 92

Circuit Calculation

EDQ024820020042 250V DC Unit Battery Load Study Rev. 91

EDQ2000870054 Control Circuit Voltage Drop Calculations - 250V DC Rev. 43

circuits

EDQ2000870550 Cable and Bus Protection/Breaker/Fuse Coordination for Rev. 54

250V DC System

EDQ2092900118 Setpoint and Scaling Calculation for Neutron Monitoring Rev. 37

System & Recirculation Flaw Loops

EDQ2999870549 Power Cable Protection Analysis for 480V MCCs Rev. 54

EQD29998801715 Thermal Overload Heater Calculation Rev. 50

MD-N0026-910163 Combustible Load Table Rev. 71

MDQ- MOV 0-FCV-067-0001/0005/0008/0011, Operator Rev. 1

0000672019000460 Requirements and Capabilities

MDQ-0067890059 Analytical Limits for the EECW Strainers and Strainer Rev. 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Drain Valves Start/Stop Controls

MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis Rev. 3

(Pump Water Suction and Discharge)

MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS Rev. 0

Piping

MDQ0032870288 Control Air Volume and Wall Thickness of Accumulators Rev. 14

MDQ0071910235 Reactor Core Isolation Cooling System Design Rev. 12

Pressure/Temperature

MDQ099920040034 Setpoint Controls Parameters Review Calculation for Rev. 17

BFN Category 2 Air Operated Valves (AOVs)

MDQ099920040040 HPCI and RCIC Test Requirements Rev. 11

NDN00099920070032 BFN Probablistic Risk Assessment - Human Reliability Rev. 8

Analysis

Corrective Action 0044691

Documents 0128951

0175232

200183

1648705

1649288

1649610

1652318

1369055

1406271

1499731

1500527

1557241

1606454

1607278

1613986

1614688

1617438

27370

1638651

1655591

Inspection Type Designation Description or Title Revision or

Procedure Date

1656541

1656544

1658162

1658186

1658998

1664478

1665909

1676979

1687954

1688353

1695185

201387

21012

1434874

1435350

1613271

Corrective Action 1695185 A3 RHRSW Lube Oil Strainer Sight Glass

Documents 1695266 Control of HPCI and RCIC System Flow Controller

Resulting from Settings

Inspection 1695742 Danger sign was identified on the top of 480V RMOV

Board 2D

1695748 Review and Evaluate Unit 2 RCIC System CQS Test

Results

1695790 NRC DBAI Inspection - Minor Correction Needed on

FPPCIS for ECP 71425

1695802 NRC DBAI 2021 Inspection - Correction Needed to 1/2-

ARP-9-23A/B/C/D and 0-ARP-25-41A/B/C/D

1696259 Pipe Wrench Laying on Top of the C# EECW Strainers

Gearbox01

1696423 NRC DBAI Inspection - Incorrect M&TE Number

Documented in WO 116092256

1696542 250V Reactor MOV Board 2B board is missing 3

finishing plugs

1696552 480V Reactor MOV board 2A missing 1 finishing plug

Inspection Type Designation Description or Title Revision or

Procedure Date

1696556 480V Reactor MOV board 2D remove RTV from

Finishing Plug hole and install Finishing Plug

1696713 Request PCRs for RCIC Flowrate Procedures

1698638 MDQ0071910235 Evaluation Didnt Account for

Tolerance

1699579 Fire seal label is required at the S25932501 penetration

per MAI-3.4A and is missing

1699961 Fire Seal Penetration R26395139 not conforming to

design output drawing 0-45E830-27

1699971 Fire Seal Penetration R36395359 not conforming to

design output drawing 0-45E830-27

1700011 DP Between RCIC Pump Discharge and RPV

1700151 Response to RCIC Overspeed

1700334 RCIC Surveillance Procedure Non-Conservative with

Respect to TS

1700335 NRC Observation Recirc Temp Mod

Drawings 0-45E830-27 Conduit & Grounding Cable Trays Fire Stop Dets-SH 14 Rev. 7

0-47E392-1 Fire Protection - 10 CFR 50 - NFPA 805 Penetration Rev. 5

Seal Tabular Drawings General Notes and Legend

0-47E840-3 Flow Diagram, Fuel Oil System Rev. 27

0-731E700 One Line Diagram of DC & Instrument Control AC Rev. 8

Systems

1-45E751-3 Wiring Diagram, 480V Reactor MOV Board 1B Rev. 43

2-45E712-2 Wiring Diagram 250V Reactor MOV BD 2B Single Line Rev. 35

2-47E610-1-1 Mechanical Control Diagram - Main Steam System Rev. 43

2-47E610-71-1 Mechanical Control Diagram - RCIC System Rev. 45

2-47E610-71-2 Mechanical Control Diagram - RCIC System Rev. 7

2-47E801-1 Flow Diagram - Main Steam Rev. 34

2-47E813-1 Flow Diagram - Reactor Core Isolation Cooling System Rev. 60

2-47W2392-702 Fire Protection - 10 CFR 50 Appendix R Penetration Rev. 1

Seal Location Drawings Plan View Area I

2-47W2392-708 Fire Protection - 10 CFR 50 Appendix R Penetration Rev. 1

Seal Location Drawings EL 639

Inspection Type Designation Description or Title Revision or

Procedure Date

2-47W2392-716 Fire Protection - 10 CFR 50 Appendix R Penetration Rev. 3

Seal Tabular Drawings EL 639

2-730E929-2 Automatic Blowdown System Rev. 24

2-730E929-3 Elementary Diagram - Automatic Blowdown System Rev. 16

2-730E929-4 Automatic Blowdown System Rev. 18

BFN-0-47E610-67-2 Mechanical Control Diagram, Emergency Equipment Rev. 38

Cooling Water

BFN-1-47E610-67-1 Mechanical Control Diagram, Emergency Equipment Rev. 50

Cooling Water

BFN-1-47E812-1-CC Flow Diagram, High Pressure Coolant Injection System Rev. 48

BFN-2-45E751-1 Wiring Diagram 480V Reactor MOV BD 2A Single Line Rev. 068

BFN-2-45E751-8 Wiring Diagram 480V Reactor MOV BD 2D Single Line Rev. 2

BFN-2-47E812-1-CC Flow Diagram, High Pressure Coolant Injection System Rev. 77

BFN-3-47E812-1-CC, Flow Diagram, High Pressure Coolant Injection System Rev. 73

Engineering DCN 72338-03 Replacement of 4160V/480V Emergency Shutdown

Changes Board 2A & 2B Transformer

EC 71425 Upgrade Unit 1/2 DG Fuel Oil Piping Configuration Rev. A

Miscellaneous System Health Report Scorecard for RHRSW and

EECW (April 2020-September 2020)

System Health Report Scorecard for RHRSW and

EECW (October 2020-March 2021)

Vendor Letter, Instructions for Changing Assembly of dated

DSMM40A Reducer 03/12/02

System Health Report Scorecard for RHRSW and

EECW (October 2019-March 2020)

0-SI-4.5.C.1(A3-COMP) RHRSW Pump A3 IST Comprehensive Pump Test Rev. 16

0-TI-444 Augmented Inservice Testing Program Rev. 12

0-TI-641 Time Critical Operator Actions Rev. 0

0048-0051-LTR-002 BFN HPCI System Waterhammer Evaluation Rev. 0

0048-0065-RPT-001 HPCI and RCIC Systems Overpressure Transient Rev. 0

Technical Review and Development of Mitigation

Options

70747-71 480V RMOV BD 2A/15D ALT FDR from SD BD Rev. A

Inspection Type Designation Description or Title Revision or

Procedure Date

BFN-1-2020-068-003 Rev. 0

BFN-19-918 U1, U2, and U3 HPCI Gland Seal CKV Addition Rev. 1

BFN-19-918-1 U1 HPCI Gland Seal CKV Addition Rev. 0

BFN-50-7071 Design Criteria - Reactor Core Isolation Cooling System Rev. 23

BFN-50-7200C Design Basis Document for the 250V DC Power Rev. 8

Distribution System

BFN-50-720D, 480V 480V Auxiliary System Rev. 12

Auxiliary System

BFN-VTD-D088-0010 Installation, Operation and Maintenance for Delroyd Rev. 2

Double Worm Gear Speed Reducers

BFN-VTD-G080-1440 Vendor Document - Instructions Installation and Rev. 2

Maintenance of 7700 Line Motor Control Center

BFN-VTD-K143-0020 Installation and Maintenance Instructions for Kinney Rev. 8

Automatic Self-Cleaning Strainers Model AV Series

BFN-VTD-K143-0040 Preventative Maintenance Instructions for S.P. Kinney Rev. 0

Strainers

BFN-VTD-K143-0050 Instruction Manual for S.P. Kinney Model AV Series Rev. 0

Motorized Automatic Self-Cleaning Strainers

BFPER971270 BF response to NRC IN 91-50 Supplement 1 Rev. 0

DCN 69466A Replace CS and RHR Room Cooler Fan Motors, Fans, Rev. A

and Shafts

DCN 70747A 50.59 Evaluation Rev. 0

DCN 71376 Increase Rated Speed of RCIC Pump/Turbine to 4650 Rev. A

RPM

EDC 50911 Option for Rotating EECW Strainer Gear Reducer 180 Rev. B

Degrees

Fire Protection

Impairment Permit

(FPIP) # 21-90 - Unit 3

Reactor Building

Elevation 621/638

Fire Protection

Impairment Permit

(FPIP) # 21-91 - Unit 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Reactor Building

Elevation 621/638

General Design Criteria Standby Diesel Generator Rev. 29

Document No. BN-50-

7082

OPL171.051 Emergency Equipment Cooling Water Rev. 9U1

PMCR 1189814 Perform 4 Year Inspection of Stand-by Diesel Engine "C"

PMCR 1189815 Perform 12-Year Inspection of Standby Diesel "C"

Engine "C"

PO 2740686 Spare Part, Engine, QA1 dated

01/19/17

Procedures 0-ARP-25-41C Panel 25-41, 0-XA-55-41C Rev. 16

0-FSS-001 Fire Safe Shutdown Rev. 5

0-FSS-2-2 U-2, RB EL 519', from R14 to a Line 10' West of R11 Rev. 8

0-FSS-2-3 U-2, RB EL593 North of Column Line R Rev. 13

0-GOI-300-1/ATT-12 Outside Operator Round Log Rev. 264

0-OI-57B 480V/240V AC Electrical System Rev. 199

0-OI-57D DC Electrical System Rev. 179

0-OI-67 Emergency Operating Cooling Water System Rev. 126

0-OI-82 Standby Diesel Generator System Rev. 174

0-SI-4.5.C.1(A3) RHRSW Pump A3 IST Group A Quarterly Pump Test Rev. 19

0-SR-3.4.3.1.A Bench Test Relief Valves - As Left Rev. 6

0-TI-346 Maintenance Rule Performance Indicator Monitoring, Rev. 54

Trending, and Reporting - 10CFR50.65

0-TI-362 Inservice Testing Program Rev. 59

0-TI-636RLY Relay Testing and Maintenance Instruction Rev. 2

0-TI-641 Time Critical Operator Actions Rev. 0

1-ARP-9-8C Panel 1-9-8, 1-XA-55-8C Rev. 17

1/2-ARP-9-23C Panel 0-9-23-8, 0-XA-55-23C Rev. 35

2-SR-3.3.5.1.3(E) HPCI Suppression Chamber High Level Calibration and Rev. 21

Functional Test

2-SR-3.3.5.1.6(ADS B) ADS Logic System Functional Test - Bus B Time Delay Rev. 22

Relay Calibration and Bus Power Monitor Test

Inspection Type Designation Description or Title Revision or

Procedure Date

2-SR-3.5.3.3 RCIC System Rated Flow at Normal Operating Pressure dated

01/04/21

2-SR-3.5.3.3 RCIC System Rated Flow at Normal Operating Pressure dated

10/05/09

2-SR-3.5.3.3(COMP) RCIC Comprehensive Pump Test dated

10/10/20

2-SR-3.5.3.4 RCIC System Rated Flow at Low RPV Pressure Rev. 26

ADS Logic System Rev. 17

Functional Test - Bus B

Time Delay Relay

Calibration and Bus

Power Monitor Test

ECI-0-000-BRK008 Testing and Troubleshooting of Molded Case Circuit dated

Breakers and Motor Starter Overload Relays 03/21/15

EII-0-000-TCC106 Troubleshooting, Documentation and Configuration dated

Control of Electrical Activities 03/26/15

EPI-0-000-MCC001 Maintenance and Inspection of 480VAC and 250VDC dated

Motor Control Centers 03/20/15

EPI-0-281-RLY001 Relay Calibration and Functional Tests on 250V DC Rev. 13

Reactor MOV Boards

MAI-3.4A Internal Conduit Seals Rev. 17

MCI-0-001-VLV002 Main Steam Relief Valves Target Rock Model 7567 Rev. 54

Disassembly, Inspection, Repair and Reassembly

MSI-0-071-GOV001 Reactor Core Isolation Cooling (RCIC) Overspeed Trip Rev. 36

Test

MSI-2-001-TST002 Testing of Air Supply System (Drywell Side-East) for Rev. 14

Main Steam Isolation Valves and Automatic

Depressurization System Main Steam Relief Valves

MSI-2-001-TST003 Testing Air Supply System (Drywell Side-West) for Main Rev. 12

Steam Isolation Valves and Automatic Depressurization

System Main Steam Relief Valves

NEDP-10 Rev. 25

NEDP-2 Design Calculation Process Control Rev. 25

NEDP-22 Operability Determinations and Functional Evaluations Rev. 21

Inspection Type Designation Description or Title Revision or

Procedure Date

NPG-SPP-09.3 Plant Modifications and Engineering Change Control Rev. 35

NPG-SPP-22.206 Verification Program Rev. 7

Work Orders 116092256

117821889

117821892

117821901

117821908

118569627

118800332

119041410

21166362

20898561

118571292

118571299

20561899

119698618

20136130

21260764

118571303

119698622

20136126

119189075

119189052

119189076

118323602

115753060

01-012729-000

01-012729-001

01-012729-002

01-012729-003

01-012730-000

01-012730-001

01-012730-002

21325467

Inspection Type Designation Description or Title Revision or

Procedure Date

21331211

21385840

21390551

21504079

21504079

21785957

21808045

119585512

119639739

15