IR 05000259/2020003

Integrated Inspection Report 05000259/2020003, 05000260/2020003 and 05000296/2020003

ML20315A155
Person / Time
Site:	Browns Ferry
Issue date:	11/10/2020
From:	Tom Stephen NRC/RGN-II
To:	Jim Barstow Tennessee Valley Authority
References
IR 2020003
Download: ML20315A155 (23)

Text

November 10, 2020

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2020003, 05000260/2020003 AND 05000296/2020003

Dear Mr. Barstow:

On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On October 23, 2020, the NRC inspectors discussed the results of this inspection with Mr. Steven M. Bono, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Browns Ferry Nuclear Plant.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Browns Ferry Nuclear Plant. 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:

05000259/2020003, 05000260/2020003 and 05000296/2020003

Licensee:

Tennessee Valley Authority

Facility:

Browns Ferry Nuclear Plant

Location:

Athens, Alabama

Inspection Dates:

July 01, 2020 to September 30, 2020

Inspectors:

S. Downey, Senior Reactor Inspector

C. Fontana, Emergency Preparedness Inspector

M. Kirk, Resident Inspector

N. Lacy, Operations Engineer

H. Lynn, Senior Health Physicist

J. Seat, Senior Resident Inspector

C. Stott, Resident Inspector

J. Viera, Operations Engineer

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 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

Failure to Properly Implement Procedural Requirements to Resolve a Mispositioned Control Rod.

Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000259/2020003-01 Open/Closed

[H.9] - Training 71153 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Technical Specification 5.4.1, Procedures, when the licensee failed to comply with 1-AOI-85-7, Mispositioned Control Rod, by placing a mispositioned control rod in a position not prescribed by procedural requirements.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000296/2020-001-00 LER 2020-001-00 for Browns Ferry Nuclear Plant,

Unit 3, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike 71153 Closed

PLANT STATUS

Unit 1 began the inspection period at rated thermal power (RTP). On July 20, 2020, Unit 1 was down powered and subsequently taken offline on July 21, 2020, due to degraded condenser vacuum caused by eel grass accumulation at the intake pumping station. The Unit was restarted on July 29, 2020 and returned to RTP on August 3, 2020. Unit 1 began its feedwater reduction and coastdown on September 17, 2020 and finished the inspection period at 85 percent RTP.

Unit 2 began the inspection period at RTP. On July 20, 2020, Unit 2 was taken offline due to degraded condenser vacuum caused by eel grass accumulation at the intake pumping station.

The Unit was restarted on July 27, 2020 and returned to RTP on August 2, 2020. On August 4, 2020, Unit 2 began a planned down power to approximately 30 percent RTP for waterbox cleaning and coolant leak repairs on the 2A variable frequency drive (VFD). Unit 2 returned to RTP on August 9, 2020, where it remained for the duration of the inspection period.

Unit 3 began the inspection period at RTP. On July 1, 2020, the Unit was down powered to 67 percent RTP due to a spurious trip of the 3C reactor feed pump (RFP). Following repairs, the Unit was returned to RTP on July 3, 2020. On July 20, 2020, Unit 3 power was reduced to 76 percent RTP due to degraded condenser vacuum caused by eel grass accumulation at the intake pumping station. The Unit returned to RTP on July 22, 2020, where it remained for the duration 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 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Residual heat removal service water (RHRSW) and emergency equipment cooling water (EECW) systems after a large eel grass intrusion to the intake fore bay on July 21, 2020.

(2) High Pressure Coolant Injection (HPCI) system while Reactor Core Isolation Cooling (RCIC) system inoperable for maintenance outage on September 3, 2020.

(3) Unit 3, Standby Liquid Control (SLC) system on September 15, 2020.

(4) Unit 1, Fuel Pool Cooling System (FPC) after an FPC system drain valve was mispositioned (i.e., drain valve for Unit 3's FPC system opened instead of Unit 1's drain valve) on September 22, 2020.

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walk down of the control room emergency ventilation system (CREV) on August 20, 2020.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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, Fire Area 18, Battery and Battery Board Room on August 5, 2020

(2) Unit 1, Fire Area 05, Electric Board Room 1A ('A' 4kV) and 250V Battery Rooms on August 5, 2020

(3) Units 2 and Unit 3, Fire Area 16-A, Spreading Room B on August 21, 2020

(4) Unit 2, Fire Area 02-03, Reactor Building Elevation 593', on September 29, 2020

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on August 25, 2020

===71111.07T - Heat Sink Performance

Triennial Review (IP Section 03.02)===

The inspectors evaluated heat exchanger/sink performance on the following components from July 20, 2020 to July 24, 2020:

(1) Unit 2 Core Spray Room Coolers (2-CLR-064-0072 & 2-CLR-064-0073), Section 02.02c

(2) Residual Heat Removal Pump Seal Heat Exchangers 3A & 3B (3-HEX-074-0005 & 3-HEX-074-0028), 02.02c

(3) Unit Station Service Transformer 2A Oil Coolers (2-OXF-243-0002A), 02.02c

(4) Residual Heat Removal Service Water System, Section 02.02.d. Specifically sections 02.02.d.4 and 02.02.d.5 were completed

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Program (IP Section 03.04)

71111.11B - Licensed Operator Requalification Program and Licensed Operator

Performance

Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)

The inspectors completed an inspection to verify the licensees ability to evaluate the performance of their licensed operators during the conduct of examinations, to assess their ability to properly develop and administer requalification annual operating tests and biennial written examinations, to evaluate the performance of the control room simulator and their testing and maintenance of the simulator, to ensure that licensed individuals satisfy the conditions of their licenses, and to assess their effectiveness in ensuring that operator license conditions are satisfied.

(1) Biennial Requalification Written Examinations

The inspectors evaluated the quality of the licensed operator biennial requalification written examinations administered in November 2019.

Annual Requalification Operating Tests

The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test

The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security

The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.

Remedial Training and Re-examinations

The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.

Operator License Conditions

The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.

Control Room Simulator

The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

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:

• Unit 2 startup following forced outage, F208, on July 27, 2020

• Unit 1 startup following forced outage, F107, on July 29, 2020

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification training in the Unit 2 simulator on July 13, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Unit 1 and 2, Maintenance Rule Function 031, control bay chilled water following unplanned replacement of train B 85-ton compressor during annual maintenance window.

(2) Maintenance Rule Function 075-B, Core Spray system following multiple failures associated with room coolers.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 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) Evaluated risk associated with eel grass intrusion during Unit 1 and Unit 2 restart activities including Operational decision-making issue evaluation (ODMI) on July 29, 2020 and July 27, 2020, respectively.

(2) High site aggregate risk due unplanned maintenance activities associated with 2A reactor protection system (RPS) motor generator (MG) set, B control bay chiller and planned maintenance activities on August 10, 2020.

(3) Unit 1, Review of the outage safety plan for refueling outage 1R13 on September 22, 2020.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Units 1 and 2, "A" Control Bay Chiller following maintenance and due to "B" Control Bay Chiller being inoperable on August 11, 2020.

(2) Units 1 and 2, "B" Diesel Generator following replacement of all cells of the "B" Diesel Battery Bank on August 7, 2020.

(3) Unit 2, Core Spray Room Cooler thermal overloads found tripped during surveillance on May 29, 2020.

(4) Units 1, 2 and 3, Control room envelope due to a degraded frame on 1-DOOR-260-0600 on September 15, 2020.

(5) Unit 3, "A" Diesel Generator following a single battery cell being jumpered out on July 16, 2020.

(6) Unit 1, Gas voids identified on Loop I of residual heat removal piping on August 4, 2020.

(7) Unit 2, Main Steam Bypass Valve 1 following erratic valve position indications on September 25, 2020.

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, Post Maintenance Test per Surveillance Requirement 2-SR-3.7.5.1(Q)performed on #1 Turbine Bypass Valve (TBV) following replacement of LVDT Conditioner, LVDT, and Servo cable on July 29, 2020.

(2) Unit 2, Post maintenance test of 2A recirculation pump following seal replacement on July 26, 2020.

(3) Units 1 and 2, Post Maintenance Test of the "B" Diesel Generator DC subsystem per ECI-0-254-BAT002, Replacement and Cleaning of the 125V DC Diesel Generator Battery Cells, after replacement of all of the cells of the "B" Diesel Battery Bank on July 9, 2020.

(4) Unit 2, Post Maintenance Test of 2A Reactor Protection System MG Set per ECI-0-099-MGZ001, Component Replacement and Maintenance on the RPS M-G Sets, after motor replacement per work order #121510204 on August 12, 2020.

(5) Units 1 and 2, Post Maintenance Test of A Diesel Generator per 0-SR-3.8.1.1(A),

Diesel Generator 'A' Monthly Operability Test after performance of 4-year inspection per work order # 120746589 on August 30-31, 2020.

(6) Unit 1, Post maintenance test of reactor core isolation cooling system following a planned maintenance outage on September 6, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1)3-SR-3.8.1.8, 480V Load Shedding Logic System Functional Test on August 19, 2020.

(2)3-SR-3.5.1.7, HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure, on September 9, 2020.

Inservice Testing (IP Section 03.01) (2 Samples)

(1)2-SR-3.5.1.7(COMP), HPCI Comprehensive Pump Test on September 16, 2020.

(2) 0-SI-4.5.C.1(B2), RHRSW Quarterly Pump Test on September 8, 2020.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspector completed the evaluation of the readiness of the Emergency Response Organization (ERO) on August 24, 2020. This was a continuation of an inspection that was performed remotely during the week of May 4, 2020 but was unable to be completed due to aspects that did not lend themselves to being performed remotely. Inspection Report 2020-002 documented the initial inspection activities.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspector completed the evaluation of the maintenance of the emergency preparedness program on August 24, 2020. This was a continuation of an inspection that was performed remotely during the week of May 4, 2020 but was unable to be completed due to aspects that did not lend themselves to being performed remotely. Inspection Report 2020-002 documented the initial inspection activities.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Classifications and notifications during licensed operator requalification simulator training on July 20,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05)===

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

(3) Unit 3 (July 1, 2019 - June 30, 2020)

MS09: Residual Heat Removal Systems (IP Section 02.08) (3 Samples)

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

(3) Unit 3 (July 1, 2019 - June 30, 2020)

MS10: Cooling Water Support Systems (IP Section 02.09) (3 Samples)

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

(3) Unit 3 (July 1, 2019 - June 30, 2020)

===71153 - Followup of Events and Notices of Enforcement Discretion

Event Followup (IP Section 03.01)===

(1) On July 20-21, 2020, the inspectors evaluated an eel grass intrusion event in the forebay and licensee response that resulted in a scram on Units 1 and 2, and a power reduction on Unit 3.

Event Report (IP Section 03.02) (1 Sample)

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

(1) LER 05000296/2020-001-00, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike, (ADAMS Accession No. ML20125A102)

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.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated licensee's follow-up to a control rod being mispositioned during startup of Unit 1 on July 30,

INSPECTION RESULTS

Failure to Properly Implement Procedural Requirements to Resolve a Mispositioned Control Rod.

Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity

Green NCV 05000259/2020003-01 Open/Closed

[H.9] - Training 71153 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Technical Specification 5.4.1, Procedures, when the licensee failed to comply with 1-AOI-85-7, Mispositioned Control Rod, by placing a mispositioned control rod in a position not prescribed by procedural requirements.

Description:

On July 30, 2020 during control rod withdrawal to support power ascension during startup of Unit 1, the operator-at-the-controls (OATC) withdrew a control rod to position 24 before realizing he had passed the control rod's intended position of 14. The Unit 1 crew entered Abnormal Operating Instruction 1-AOI-85-7, Mispositioned Control Rod. 1-AOI-85-7 requires a control rod that is greater than 2 notches from its intended position to be inserted to position 00 (fully inserted). The Unit 1 nuclear unit senior operator (NUSO) consulted with the observing reactor engineer (RE) and directed the OATC to insert the mispositioned control rod to its intended position, 14, contrary to the 1-AOI-85-7 requirement to place the rod at position 00. The NUSO requested the RE model the event with the rod at position 24 and determined that adequate margin to all thermal limits and pre-conditioning limits had been maintained.

The Unit 1 operators were then relieved. The relief NUSO requested the RE to model the control rod at positions 14 and 00 and requested a control rod movement data sheet (Attachment 1 of 1-SR-3.1.3.5(A), Control Rod Coupling Integrity Check) for moving the control rod to position 00. Approximately 54 minutes after the control rod was mispositioned, it was inserted to position 00 as required by 1-AOI-85-7.

On September 9, 2020, the inspectors met with the developer of the licensee's Level 2 Evaluation Report, which had been completed on September 1, 2020. The inspectors informed the licensee that the Level 2 Evaluation Report did not include any details or evaluation of the fact that the mispositioned control rod was inserted to position 14 before being inserted to position 00 as required by 1-AOI-85-7. The licensee completed a revision of their Level 2 Evaluation Report on September 23, 2020 to analyze the execution of 1-AOI-85-

7. Corrective Actions: The licensee performed stand downs for operating crews to ensure that

appropriate procedures were reviewed prior to reactivity manipulations. The operating crew was prescribed remediation prior to presumption of duties. The licensee completed a revised Level 2 Evaluation Report.

Corrective Action References: Condition Report #1627098

Performance Assessment:

Performance Deficiency: The licensees failure to follow the unit abnormal operating instruction for a mispositioned control rod was a performance deficiency. Specifically, the operators maneuvered a mispositioned control rod to its previously intended position of 14 instead of 00 as prescribed by 1-AOI-85-7.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, procedural requirements intended to minimize challenges to fuel cladding integrity were not implemented correctly. Prior to placing the mispositioned control rod to position 00, the operating crew maneuvered the control rod from position 24 to position 14 for approximately 54 minutes. 1-AOI-85-7 had no provisions for placing the mispositioned control rod at any position other than 00 when a control rod has been mispositioned by greater than two notches.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Barrier Integrity screening questions, the finding was determined to be of very low safety significance (Green)because the fuel cladding integrity was not challenged by the delay in placing the control rod at position 00.

Cross-Cutting Aspect: H.9 - Training: The organization provides training and ensures knowledge transfer to maintain a knowledgeable, technically competent workforce and instill nuclear safety values. The inspectors determined that operator training did not include training specifically for a control rod being mispositioned by more than two notches by an operator.

Enforcement:

Violation: Technical Specification 5.4.1, Procedures, requires in part that written procedures shall be established, implemented, and maintained covering the activities related to procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Regulatory Guide 1.33, Section 6, Procedures for Combating Emergencies and Other Significant Events, includes Mispositioned Control Rod or Rods. 1-AOI-85-7, Mispositioned Control Rod, Revision 6, Section 4.2.[3] states, in part, that if the control rod is greater than two notches from its intended position, then insert the mispositioned rod to 00. Contrary to the above, on July 30, 2020, the operations crew maneuvered the mispositioned control rod to position 14 for approximately 54 minutes while performing other activities before inserting the control rod to position 00.

Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On October 23, 2020, the inspectors presented the integrated inspection results to Mr.

Steven M. Bono, Site Vice President, and other members of the licensee staff.

• On July 24, 2020, the inspectors presented the Triennial Heat Sink Exit Meeting inspection results to S. M. Bono, Site Vice President and other members of the licensee staff.

• On August 28, 2020, the inspectors presented the Management Debrief inspection results to S. Bono, Site VP and other members of the licensee staff.

• On September 29, 2020, the inspectors presented the Requalification Inspection Exit inspection results to S. Bono and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Calculations

MDQ0063920470

Standby Liquid Control System - Boron 10 Requirements

Corrective Action

Documents

CRs 1558895,

1604231,

1611484,

1615183,

1630408

Drawings

0-37W205-5

Mechanical Pumping Station and Water Treatment - Piping

and Equipment

Revision 15

1-47E858-1

Flow Diagram RHR Service Water System

Revision 72

1-47E859-1

Flow Diagram Emergency Equipment Cooling Water

Revision 99

2-47E2865-4

Mechanical Ventilation and Air Conditioning Air Flow

Diagram

Revision 22

3-47E854-1

Flow Diagram Standby Liquid Control System

Procedures

0-OI-31

Control Bay and Off-Gas Treatment Building Air

Conditioning System

Revision 163

3-SR-3.1.7.7

Standby Liquid Control System Functional Test

NFPA 805 Fire

Protection Report

Section 4

Revision 2

71111.05

Corrective Action

Documents

CR 1632219

Miscellaneous

Drill Evaluations from 1/6/2020, 2/20/2020, 2/26/2020,

3/20/2020, 5/14/2020, 5/21/2020, 5/28/2020, 6/12/2020,

5/1/2017, 5/2/2017, 5/10/2017, 5/10/2017, 5/11/2017

Procedures

FPDP-5

Development and Evaluation of Fire Drills

Revision 6

FPR-Volume 2

Fire Protection Report Volume 2

Revision 67

NFPA 805 Fire

Protection Report

Appendix C

Revision 4

TPD-FBT

Fire Brigade Training - Training Program Description

Revision 17

71111.07T

Calculations

MDQ0067880344

EECW System Design Pressure and Temperature Analysis

Revision 011

MDQ0067910008

Flow Requirements for EECW-Fed Components

Revision 017

NDN-000-023-

2007-0026

BFN Probabilistic Risk Assessment - Residual Heat

Removal Service Water System

Revision 004

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

1333219,

24931,

1441556,

1498980,

25473,

1543185,

1563233,

1566676,

21239,

21907

Engineering

Changes

DCN 71313

RHRSW Pump Replacement Modification

Revision A

Procedures

0-AOI-100-4

Breach of Wheeler Dam

Revision

0016

0-AOI-27-1

Component Biofouling

Revision

0012

0-TI-522

Program for Implementing NRC Generic Letter 89-13

Revision

0009

2-TI-134

Core Spray and Residual Heat Removal Room Coolers Air

Flow Verification

Revision

20

CI-137

Raw Water Chemical Treatment

Revision

24

CI-137.5

Raw Water Chemical Treatment Molluscicide Control

Revision

0044

EPI-0-242-

BUS001

Main Transformer, Unit Station Service Transformer and

Associated Bus Work (Major Outage)

Revision

0049

NPG-SPP-09.7.3

Raw Water Corrosion Program

Revision

0005

Work Orders

117679908,

117900738,

119231027,

119598647,

119589130,

119699775,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20012352,

20133867,

20135673,

20136893,

20561301,

20622202

71111.11B

Corrective Action

Documents

CR 1522956

Two licensed operators did not complete all required training

for LOR cycle 1901

9/16/2020

Fire Plans

NPG-SPP-11.8.5

Steady State Drift

Test Unit 2

100% Steady State Drift Test U 2

7/29/2020

Miscellaneous

2019 LOR Exam

C

2019 Licensed Operator Requalification Examination C

Rev 0

2019

Requalification

Training

Attendance

Records

2019 Requalification Training Attendance Records

10/16/2020

20 Cycle 1

Simulator Exam

Failure Records

20 Cycle 1 Simulator Exam Failure Records

10/16/2020

20

Requalification

Training

Attendance

Records

20 Requalification Training Attendance Records

10/16/2020

JPM 141AP U2

JPM 141AP U2

Rev 2

JPM 173TC

Control Room Abandonment (HS6)

Rev 15

JPM 18AP U2

EOI Appendix 5C - Injection System Lineup - RCI

Rev 8

JPM 257A U3

3-EOI Appendix-6D (6E) Injection Subsystem Lineup CS

System I (II)

Rev 2

JPM 265AP U3

Recirculation Pump Recovery with Manual Scram

Rev 2

JPM 324

3-EOI Appendix 16B Bypassing RCIC Test Mode Isolation

Interlocks

Rev 6

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

JPM 345 U3

Alternate RPV Pressure Control HPCI Test Mode

Rev 2

JPM 355 U3

Emergency Venting Primary Containment

Rev 4

JPM 5U3

3-EOI Appendix 2 Defeating ARI Logic Trips

Rev 5

JPM 670A U2

2-EOI Appendix-11F Alternate RPV Pressure Control

Systems: RFPT On Minimum Flow

Rev 3

JPM 711 U1

Bypassing RCIC High Temperature Isolations (Unit 1)

Rev 0

JPM 713

Load Shed of 250V Main Bank Battery 1, 2, 3 (250V RMOV

Board 3B, 3A)

Rev 1

JPM FSS08A

Start RHR Pump 2C per 2-FSS-16-2, Attachment 3, Section

Rev 1

JPM FSS09

Start RHR Pump 2C per 2-FSS-16-2, Attachment 3, Section

Rev 2

JPM FSS23

Align 4kV Shutdown Board C per 0-FSS-2-3, Attachment 2,

Section 1

Rev 0

LOR-EXAM-10

Simulator Scenario LOR-EXAM-10

Rev 7

LOR-EXAM-60A

Simulator Scenario LOR-EXAM-60A

Rev 3

LOR-EXAM-64

Simulator Scenario LOR-EXAM-64

Rev 3

Medical Records

Operator Medical Records (10)

9/16/2020

NPG-SPP-11.8.5

Malfunction Test

Unit 2 CS04

CS Power Logic Failure

2/11/2019

NPG-SPP-11.8.5

Steady State Drift

Test Unit 3

U3 100% SS Drift Test

7/29/2020

NPG-SPP-11.8.5

Transient 1 Unit 3

Manual Scram

7/28/2020

NPG-SPP-11.8.5

Transient 10 Unit

MSIV Isolation & Relief Valve Failure

2/10/2019

NPG-SPP-11.8.5

Transient 2 Unit 2

Unit 2 Simulator - Simultaneous Trip of all FW Pumps

2//2019

NPG-SPP-11.8.5

Transient 3 Unit 3

Simultaneous Closure of all MSIVs

7/28/2020

NPG-SPP-11.8.5

Unit 2 Simulator - Single Recirc Pump Trip

2/5/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Transient 5 Unit 2

NPG-SPP-11.8.5

Transient 6 Unit 3

Turbine Trip <30% Power

7/28/2020

NPG-SPP-11.8.5

Transient 7 Unit 2

Maximum Rate Power Ramp

2/10/2019

NPG-SPP-11.8.5

Transient 9 Unit 3

Maximum Size Unisolable MSL Rupture

7/29/2020

OR-EXAM-21

Simulator Scenario OR-EXAM-21

Rev 6

PG-SPP-11.8.5

Malfunction Test

Unit 2 AD01

Relief Valve Failure

7/29/2020

PG-SPP-11.8.5

Malfunction Test

Unit 2 ED17

Loss of 250 V Battery Bus Board 1,2,3,4,5,6

7/29/2020

PG-SPP-11.8.5

Malfunction Test

Unit 2 FW19

FW Line Break in MS Tunnel

2/11/2019

PG-SPP-11.8.5

Malfunction Test

Unit 2 FW19

Feedwater Line Break in Main Steam Tunnel

2/11/2019

PG-SPP-11.8.5

Malfunction Test

Unit 2 NM05

Variable Failure of IRM Attenuator

2/11/2019

PG-SPP-11.8.5

Malfunction Test

Unit 3 CU04

RWCU System Suction Line Break

7/29/2020

Reactivation

Record

One Reactivation Record

10/16/2020

71111.11Q Procedures

1-GOI-100-1A

Unit Startup

Revision 58

2-GOI-100-1A

Unit Startup and Power Operation

Revision 179

NPG-SPP-17.8.4

Conduct of Simulator Operations

Revision 7

OPDP-1

Conduct of Operations

Revision 46

71111.12

Corrective Action

Documents

CR 1612226,

20331,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20905,

22117

CRs 1629318,

1630063,

1638469,

1638487,

28680

WO 121510085

Miscellaneous

Air Conditioning System 031 (a)(1) Plan

Maintenance Rule Expert Panel Package

09/21/2020

Procedures

0-TI-346

Maintenance Rule Performance Indicator Monitoring,

Trending and Reporting - 10CFR50.65

Revision 53

71111.13

Corrective Action

Documents

CR 1625169

Drawings

2-45#751-3

Wiring Diagram 480V Reactor MOV Bd 2B

Revision 53

2-45E749-4

Wiring Diagram 480V Shutdown Bd 2B Single Line

Revision 53

Miscellaneous

Unit 1 Cycle R13, Outage Safety Plan

09/21/2020

Operational Decision-Making Issue Evaluation Document for

CR 1625169

07/24/2020

Procedures

0-OI-31

Control Bay and Off-Gas Treatment Building Ventilation Air

Conditioning System

Revision 162

2-OI-99

Reactor Protection System

Revision 90

BFN-ODM-4.18

Protected Equipment

Revision 27

OPDP-11

Operational Decision-Making Issue Evaluation Process

Revision 8

71111.15

Corrective Action

Documents

CR 161226

Thermal overloads found tripped for Core Spray room cooler

06/04/2020

CR 1627940,

1435268

CR 1631820,

1615815

CRs 1622321,

22527,

1637208,

1585280,

1587042

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CRs 1640334,

1640153,

26190,

26176,

1610483

Drawings

0-46E401-13

Architectural Control Bay Plans & Details

Revision 6

1-47E811-1

Flow Diagram Residual Heat Removal System

Revision 47

BFN-2-45E602-38 Elementary Diagram Turbine Control

BFN-2-9952-569

sh.20

TVA Browns Ferry Unit #2 Bypass Valve Control Wiring

Miscellaneous

Laboratory

Report 5692

KCR-07: Cracked Jar

2/14/2020

Engineering Work

Request 20-EEB-

047-238

Lift Servo Wires to Disable U2 BPV #1 in the Closed

Position

09/27/2020

TVA-COLR-

BF2C21

Browns Ferry Unit 2 Cycle 21 Core Operating Limits Report

Operability

Evaluations

Past Operability Evaluation Documentation for CR 1612226

06/03/2020

PDO for CR

27940

Procedures

NFPA 805 Fire Protection Requirements Manual

Revision 13

0-SR-3.8.6.2(DG-

B)

Quarterly Check of Diesel Generator B Battery

0-SR-3.8.6.2(DG-

B)

Quarterly Check of Diesel Generator B Battery

1-OI-74

Residual Heat Removal System

Revision 109

2-SI-4.2.B-60FT(I) Core Spray Pump Area Cooler Fan Thermostat Functional

(2-TS-64-72)

Revision

0007

Work Orders

WO 118569273,

117446738

WO 120867970

WOs 121456462,

20134881,

119697369

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

WOs 121619276,

20399540,

21549320,

21363784

71111.19

Corrective Action

Documents

CR 1634674

Drawings

1-47E813-1

Flow Diagram Reactor Core Isolation Cooling System

Revision 42

Procedures

0-TI-106

General Leak Rate Test Procedure

Revision 16

1-SR-3.5.3.3

RCIC System Rated Flow at Normal Operating Pressure

Revision 41

1-SR-

3.6.1.3.5(RCIC)

RCIC System MOV Operability

Revision 17

2-OI-68

Reactor Recirculation System

Revision 159

MMTP-141

Routine Inspection and Maintenance of Limitorque Motor

Actuators

Revision 2

NPG-SPP-06.3

Pre-/Post-Maintenance Testing

Revision 3

NPG-SPP-06.9.1

Conduct of Testing

Revision 12

Work Orders

WO 120896842,

21581151,

20896819.

20943508,

20952882,

209433512,

20943542

WO 121445637

WO 121491094,

21487577,

21487344

71111.22

Corrective Action

Documents

CR 1524175,

29425

Engineering

Evaluations

0-TI-579

RHRSW System Pump Baseline Data Evaluation

Revision 7

Procedures

0-SI-4.5.C.1

RHRSW Pump B2 IST Group A Quarterly Pump Test

Revision 12

Work Orders

WO 120896630

71114.06

Procedures

EPIP-1

Emergency Classification Procedure

Revison 60

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NPG-SPP-17.8.4

Conduct of Simulator Operations

Revision 7

71151

Miscellaneous

Units 1, 2, and 3 Residual Heat Removal system MSPI

Margin and Derivation Reports

07/01/2019 -

06/30/2020

Units 1, 2, and 3 Emergency AC Power System MSPI

Margin and Derivation Reports

07/01/2019 -

06/30/2020

Units 1, 2, and 3 Residual Heat Removal Service Water and

Emergency Equipment Cooling Water systems MSPI Margin

and Derivation Reports

07/01/2019 -

06/30/2020