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

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

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

Procedure

Type

Designation

Description or Title

Revision or

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

Strainer

Rev. 1

CDQ-0067894672

Evaluation and Review of Small Bore Unit 0 Piping and

Supports within the Scope of the System 067 Safe

Shutdown Boundary

Rev. 12

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

Components for the Affects of Tornadic Wind-RHRSW

Pump

Rev. 2

CDQ0999910005

Evaluation of Seismic-Induced Spray Hazards at BFN,

Unit 2 and Common

Rev. 3

CDQ107320021062

Small Bore Piping and Supports Program System

Calculation for Seismic Class 1 HPCI System (73) Piping

Rev. 6

CDQ107320031063

Pipe Stress Analysis of Stress Problem N1-173-67R

Rev. 1

EDQ0057920034

4.16KV and 480V Busload, Voltage Drop and Short

Circuit Calculation

Rev. 92

EDQ024820020042

250V DC Unit Battery Load Study

Rev. 91

EDQ2000870054

Control Circuit Voltage Drop Calculations - 250V DC

circuits

Rev. 43

EDQ2000870550

Cable and Bus Protection/Breaker/Fuse Coordination for

250V DC System

Rev. 54

EDQ2092900118

Setpoint and Scaling Calculation for Neutron Monitoring

System & Recirculation Flaw Loops

Rev. 37

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-

0000672019000460

MOV 0-FCV-067-0001/0005/0008/0011, Operator

Requirements and Capabilities

Rev. 1

MDQ-0067890059

Analytical Limits for the EECW Strainers and Strainer

Rev. 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Drain Valves Start/Stop Controls

MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis

(Pump Water Suction and Discharge)

Rev. 3

MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS

Piping

Rev. 0

MDQ0032870288

Control Air Volume and Wall Thickness of Accumulators

Rev. 14

MDQ0071910235

Reactor Core Isolation Cooling System Design

Pressure/Temperature

Rev. 12

MDQ099920040034

Setpoint Controls Parameters Review Calculation for

BFN Category 2 Air Operated Valves (AOVs)

Rev. 17

MDQ099920040040

HPCI and RCIC Test Requirements

Rev. 11

NDN00099920070032

BFN Probablistic Risk Assessment - Human Reliability

Analysis

Rev. 8

Corrective Action

Documents

0044691

28951

0175232

200183

1648705

1649288

1649610

1652318

1369055

1406271

1499731

1500527

1557241

1606454

1607278

1613986

1614688

1617438

27370

1638651

1655591

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1656541

1656544

1658162

1658186

1658998

1664478

1665909

1676979

1687954

1688353

1695185

201387

21012

1434874

1435350

1613271

Corrective Action

Documents

Resulting from

Inspection

1695185

A3 RHRSW Lube Oil Strainer Sight Glass

1695266

Control of HPCI and RCIC System Flow Controller

Settings

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

Procedure

Type

Designation

Description or Title

Revision or

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

Seal Tabular Drawings General Notes and Legend

Rev. 5

0-47E840-3

Flow Diagram, Fuel Oil System

Rev. 27

0-731E700

One Line Diagram of DC & Instrument Control AC

Systems

Rev. 8

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

Seal Location Drawings Plan View Area I

Rev. 1

2-47W2392-708

Fire Protection - 10 CFR 50 Appendix R Penetration

Seal Location Drawings EL 639

Rev. 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2-47W2392-716

Fire Protection - 10 CFR 50 Appendix R Penetration

Seal Tabular Drawings EL 639

Rev. 3

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

Cooling Water

Rev. 38

BFN-1-47E610-67-1

Mechanical Control Diagram, Emergency Equipment

Cooling Water

Rev. 50

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

Changes

DCN 72338-03

Replacement of 4160V/480V Emergency Shutdown

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

DSMM40A Reducer

dated

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

Technical Review and Development of Mitigation

Options

Rev. 0

70747-71

480V RMOV BD 2A/15D ALT FDR from SD BD

Rev. A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

Distribution System

Rev. 8

BFN-50-720D, 480V

Auxiliary System

480V Auxiliary System

Rev. 12

BFN-VTD-D088-0010

Installation, Operation and Maintenance for Delroyd

Double Worm Gear Speed Reducers

Rev. 2

BFN-VTD-G080-1440

Vendor Document - Instructions Installation and

Maintenance of 7700 Line Motor Control Center

Rev. 2

BFN-VTD-K143-0020

Installation and Maintenance Instructions for Kinney

Automatic Self-Cleaning Strainers Model AV Series

Rev. 8

BFN-VTD-K143-0040

Preventative Maintenance Instructions for S.P. Kinney

Strainers

Rev. 0

BFN-VTD-K143-0050

Instruction Manual for S.P. Kinney Model AV Series

Motorized Automatic Self-Cleaning Strainers

Rev. 0

BFPER971270

BF response to NRC IN 91-50 Supplement 1

Rev. 0

DCN 69466A

Replace CS and RHR Room Cooler Fan Motors, Fans,

and Shafts

Rev. A

DCN 70747A

50.59 Evaluation

Rev. 0

DCN 71376

Increase Rated Speed of RCIC Pump/Turbine to 4650

RPM

Rev. A

EDC 50911

Option for Rotating EECW Strainer Gear Reducer 180

Degrees

Rev. B

Fire Protection

Impairment Permit

(FPIP) # 21-90 - Unit 3

Reactor Building

Elevation 621/638

Fire Protection

Impairment Permit

(FPIP) # 21-91 - Unit 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Reactor Building

Elevation 621/638

General Design Criteria

Document No. BN-50-

7082

Standby Diesel Generator

Rev. 29

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,

Trending, and Reporting - 10CFR50.65

Rev. 54

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

Functional Test

Rev. 21

2-SR-3.3.5.1.6(ADS B)

ADS Logic System Functional Test - Bus B Time Delay

Relay Calibration and Bus Power Monitor Test

Rev. 22

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

Functional Test - Bus B

Time Delay Relay

Calibration and Bus

Power Monitor Test

Rev. 17

ECI-0-000-BRK008

Testing and Troubleshooting of Molded Case Circuit

Breakers and Motor Starter Overload Relays

dated

03/21/15

EII-0-000-TCC106

Troubleshooting, Documentation and Configuration

Control of Electrical Activities

dated

03/26/15

EPI-0-000-MCC001

Maintenance and Inspection of 480VAC and 250VDC

Motor Control Centers

dated

03/20/15

EPI-0-281-RLY001

Relay Calibration and Functional Tests on 250V DC

Reactor MOV Boards

Rev. 13

MAI-3.4A

Internal Conduit Seals

Rev. 17

MCI-0-001-VLV002

Main Steam Relief Valves Target Rock Model 7567

Disassembly, Inspection, Repair and Reassembly

Rev. 54

MSI-0-071-GOV001

Reactor Core Isolation Cooling (RCIC) Overspeed Trip

Test

Rev. 36

MSI-2-001-TST002

Testing of Air Supply System (Drywell Side-East) for

Main Steam Isolation Valves and Automatic

Depressurization System Main Steam Relief Valves

Rev. 14

MSI-2-001-TST003

Testing Air Supply System (Drywell Side-West) for Main

Steam Isolation Valves and Automatic Depressurization

System Main Steam Relief Valves

Rev. 12

NEDP-10

Rev. 25

NEDP-2

Design Calculation Process Control

Rev. 25

NEDP-22

Operability Determinations and Functional Evaluations

Rev. 21

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

Procedure

Type

Designation

Description or Title

Revision or

Date

21331211

21385840

21390551

21504079

21504079

21785957

21808045

119585512

119639739