IR 05000259/2019001

NRC Integrated Inspection Report 05000259/2019001, 05000260/2019001 and 05000296/2019001

ML19129A276
Person / Time
Site:	Browns Ferry
Issue date:	05/07/2019
From:	Lopez O NRC/RGN-II/DRP/RPB5
To:	James Shea Tennessee Valley Authority
Omar Lopez-Santiago
References
EPID I-2019-001-0065 IR 2019001
Download: ML19129A276 (44)

Text

{{#Wiki_filter:==SUBJECT:== BROWNS FERRY UNITS 1, 2, AND 3 - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000259/2019001, 05000260/2019001 AND 05000296/2019001

Dear Mr. Shea:

On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Browns Ferry Units 1, 2, and 3. On April 26, 2019, the NRC inspectors discussed the results of this inspection with Lang Hughes, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

NRC inspectors documented two findings of very low safety significance (Green) in this report.

These findings involved violations of NRC requirements. Additionally, NRC inspectors documented one Severity Level IV violation with no associated finding. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violations or significance or severity of the violations 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.

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.

2 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Omar R. Lopez-Santiago, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 05000259 and 05000260 and 05000296 License Nos.: DPR-33 and DPR-52 and DPR-68

Enclosure:

Inspection Report 05000259/2019001, 05000260/2019001 and 05000296/2019001

Inspection Report

Docket Number(s): 05000259, 05000260 and 05000296 License Number(s): DPR-33, DPR-52 and DPR-68 Report Number(s): 05000259/2019001, 05000260/2019001 and 05000296/2019001 Enterprise Identifier: I-2019-001-0065 Licensee: Tennessee Valley Authority Facility: Browns Ferry, Units 1, 2 and 3 Location: Corner of Shaw and Nuclear Plant Road Athens, AL 35611 Inspection Dates: January 01, 2019 to March 31, 2019 Inspectors: A. Butcavage, Reactor Inspector W. Deschaine, Project Engineer J. Diaz-Velez, Senior Health Physicist N. Hobbs, Resident Inspector R. Kellner, Senior Health Physicist M. Kirk, Resident Inspector A. Nielsen, Senior Health Physicist J. Rivera, Health Physicist T. Stephen, Senior Resident Inspector Approved By: Omar R. Lopez-Santiago, 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 a First Quarter Integrated Report inspection at Browns Ferry Units 1, 2 and 3 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations Failure To Backwash And Drain RWCU Demineralizers Prior To Performing A System Breach.

Cornerstone Significance Cross-cutting Report Aspect Section Occupational Green [H.11] - 71124.01 Radiation Safety NCV 05000259/2019001-01 Challenge the Closed Unknown A self-revealed, Green, non-cited violation (NCV) of technical specification (TS) 5.4.1.a, Procedures was identified for failure to implement procedure NPG-SPP-10.2, Clearance Procedure to Safely Control Energy. Specifically, the licensee failed to verify that both Unit 1 reactor water cleanup (RWCU) demineralizers were backwashed and drained prior to breaching the system. This resulted in a high radiation area when contaminated water and resin was spilled from the RWCU system.

Failure To Establish And Implement Adequate Procedures For Diving Activities And The Underwater Storage Of Highly Radioactive Materials.

Cornerstone Significance Cross-cutting Report Aspect Section Occupational Green [H.12] - Avoid 71124.01 Radiation Safety NCV 05000259/2019001-02 Complacency Closed A self-revealed, Green, non-cited violation of technical specification 5.4.1.a, Procedures, was identified for multiple examples of the failure to establish and implement adequate procedures for the control of diving activities and the storage of radioactive materials underwater. Specifically, during diving activities in the Unit 1 equipment pit, the licensee failed to follow radiological control procedures which resulted in a diver encountering unexpected high dose rates and receiving unplanned dose near a spent filter storage rack.

Failure to Implement a Required NFPA 805 Modification in the Timeframe Described in the Operating License Cornerstone Significance Cross-cutting Report Aspect Section Not Applicable Severity Level IV Not Applicable 71152 NCV 05000259, 296/2019001-03 Closed An NRC identified severity level (SL) IV non-Cited violation (NCV) of the renewed operating license for Units 1 (DPR-33) and 3 (DPR-68) was identified for the failure to implement a required modification to the main transformers, unit station service transformers (USSTs), and common station service transformers (CSSTs) as described in NFPA 15-2001 before the end of the second refueling outage.

Additional Tracking Items Type Issue number Title Report Status Section URI 05000259/2018050 Potential failure to maintain 71124.01 Closed-02 and implement adequate work and radiological control procedures for the control of diving activities, control of high radiation areas and very high radiation areas, and the control of highly radioactive materials.

URI 05000296/2019001 Unit 3 notice of unusual event 71153 Open-04 (NOUE) caused by of a loss of offsite power (LOOP) resulting in a reactor scram.

LER 05000259/2018- LER 2018-004-01 for Browns 71153 Closed 004-01 Ferry Nuclear Plant, Unit 1, high pressure coolant injection declared inoperable due to steam supply valve Isolation.

PLANT STATUS

Unit 1 operated near rated thermal power until January 31, 2019 when the unit completed extended power uprate (EPU) testing and achieved 100 percent rated thermal power. The unit operated at this power for the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power. On February 19, 2019, while the unit was in coast down to the outage, it was down powered from 90 percent to 58 percent to maintain condenser vacuum due to an issue with the steam jet air ejectors. Later that morning, condenser vacuum was restored and the unit returned to 90 percent power. On March 2, 2019, the unit was shutdown for a planned refueling outage and remained shutdown through the remainder of the inspection period.

Unit 3 began the inspection period at rated thermal power. On March 9, 2019, the unit experienced a generator load reject which resulted in a unit scram. The unit also experienced a loss of offsite power (LOOP) which necessitated declaration of a notice of unusual event (NOUE) (EN 53922). The unit was restarted on March 14, 2019 and operated at or near rated thermal power for 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.

71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.03)

The inspectors evaluated readiness for impending adverse weather conditions for a winter storm on January 28, 2019.

Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures on January 9, 2019.

71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains: Unit 2, Loop II of the residual heat removal (RHR) system while aligned for shutdown cooling as a backup to alternate decay heat removal (ADHR) on March 14, 2019.

71111.04S - Equipment Alignment Complete Walkdown (IP Section 02.02)

The inspectors evaluated the ADHR system while it was in service for the Unit 2 refueling outage during a complete walkdown on March 14, 2019.

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

The inspectors evaluated fire brigade performance on March 4, 2019. The Browns Ferry fire brigade responded to the report of smoke coming from the Unit 2 condenser vacuum pump room.

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

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

(1) Units 1, 2 and 3, main control rooms, fire area 16-A on January 8, 2019

(2) Units 1, 2 and 3, fire area 16, control bay 30 minute route on February 12, 2019

(3) Unit 1, Fire Area 01-04, RHR heat exchanger rooms on February 21, 2019

(4) Units 1, 2, and 3, fire area 16M, auxiliary instrument room number 2 on February 22, 2019.

(5) Units 1, 2 and 3, turbine building (TB), fire area 26-A on March 4, 2019.

(6) Units 1, 2, and 3, switchyard and main transformers on March 15, 2019.

71111.06 - Flood Protection Measures Inspection Activities - Underground Cables (IP Section 02.02c.)

The inspectors evaluated cable submergence protection in: The residents reviewed the licensee's verification of handholes 15 and 26 on January 14, 2019.

===71111.08G - Inservice Inspection Activities (BWR) BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) ===

The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 4, 2019 to March 8, 2019: 03.01.a - Nondestructive Examination and Welding Activities.

(1) Ultrasonic examination of nozzle N16At-1, to safe end weld (observed)

(2) Weld No. CRD-2-010-001, C0R0, System No. 85, control rod drive piping, butt weld (reviewed)

(3) Weld No. CRD-2-010-015, C0R0, System No. 85, control rod drive piping, butt weld (reviewed)

(4) Magnetic particle examination (MT), reactor vessel support skirt (reviewed)

(5) Dry well moisture barrier examination (partial walk-down and reviewed)03.01.b - Augmented License Renewal or Industry Initiative Examinations

(1) BWRVIP-26-A, Top Guide (TG) Group, Aligner Pins, Component ID's: (Discussed and Reviewed)

• TG 000 aligner pin, socket location 2-3_D40
• TG 000 aligner pin, socket location 2-3_D40_90 Deg.
• TG 090 aligner pin, socket location 2-3_D40
• TG 090 aligner pin, socket location 2-3_D40_90 Deg.
• TG 180 aligner pin, socket location 2-3_D40
• TG 180 aligner pin, socket location 2-3_D40_90 Deg.
• TG 270 aligner pin, socket location 2-3_D40
• TG 270 aligner pin, socket location 2-3_D40_ 90 Deg.

(2) Browns Ferry Operating Experience, BWRVIP-183-A

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

The inspectors observed and evaluated licensed operator performance in the Control Room during:

• Unit 1 power changes associated with EPU on January 14, 25 and 31.
• Unit 1 EPU flow induced vibration data acquired at 91.9, 96.2 and 100 percent power.
• Unit 1 main steam pressure control data acquired at 98 percent power.
• Unit 2 shutdown for refueling outage 2R20 on March 2, 2019.
• Unit 3 startup on March 14, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample) The inspectors observed and evaluated a license operator requalification simulator exercise on February 11, 2019.

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

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

(1) Unit 1, 2, and 3 evaluation of required maintenance for the spent fuel pool siphon breaks on the suction and discharge lines.

(2) Unit 3, Function 074-B, low pressure coolant injection (LPCI) following failure of breaker associated with LPCI suction valve.

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

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

(1) Unit 3, Emergent risk associated with 3D emergency diesel generator (EDG) operable but degraded with 3A control bay chiller out of service, during heavy adverse weather conditions on February 20, 2019.

(2) Unit 2, review of outage safety plan for cycle 2R20.

(3) Unit 2, yellow outage risk due to high decay heat load on March 2, 2019.

(4) Unit 2, planned risk associated with time from mode 5 (refueling) entry until the completion of reactor vessel and cavity flood up on March 3-4, 2019.

(5) Unit 2, planned shutdown risk associated with operation with the potential to drain the reactor vessel (OPDRV) for replacement of 8 local power range monitors (LPRM) on March 12, 2019.

(6) Units 1, 2, and 3 emergent risk due to a tornado watch on March 14, 2019.

(7) Unit 2, planned yellow shutdown risk with both loops of RHR system unavailable for shutdown cooling and the ADHR system providing cooling for decay heat removal on March 20, 2019.

71111.15 - Operability Determinations and Functionality Assessments Sample Selection (IP Section 02.01)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Units 1, 2, and 3, RHR test valves operability following a revised weak leak analysis report from vendor on January 23, 2019.

(2) Unit 3, operability associated with an intermittent ground identified on 3A EDG on January 11, 2019.

(3) Unit 3, operability evaluation of 4kV shutdown board 3ED following a failure of the normal feeder breaker to close during EDG testing.

(4) Unit 1 and 2, operability evaluation of the combined accident signal logic due to a failed breaker blocking time delay relay 0-RLY-211-BBTDA on February 13, 2019.

(5) Unit 3, reactor core isolation cooling (RCIC) operability evaluation after abnormal indications identified following Unit 3 reactor scram on March 9, 2019.

(6) Unit 3, Operability associated with missed in-service testing surveillance on 3A1 chiller expansion tank relief valve on March 14, 2019.

==71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample) The inspectors evaluated the following temporary or permanent modifications: Unit 2, DCN 72642, design change to anticipated transient without scram (ATWS)/alternate rod insertion (ARI) pressure setpoint related to EPU

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

[[IP sample::=

=IP 71111.18|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) Unit 3, post maintenance testing following repairs to fix a coolant leak on the 3B EDG on January 7, 2019.

(2) Unit 3, post maintenance testing following replacement of the accumulator for the 3A standby liquid control (SLC) pump on January 22, 2019.

(3) Various Unit 1 integrated systems testing per 1-TI-700, 1-TI-130 and 1-TI-131 at EPU conditions from January 1 to January 31, 2019 when the unit achieved the new licensed operating power of 3952MWt.

(4) Unit 2, emergency high pressure makeup (EHPM) pump injection test during reactor pressure vessel flood up on March 4, 2019.

(5) Unit 3, post maintenance testing following relay replacement on RHR 3-FCV-74-52 valve breaker on March 13, 2019.

(6) Unit 3, post maintenance testing of control valves following gain curve adjustments to lower turbine control valve (TCV) oscillations.

(7) Unit 2, hydrostatic testing of reactor pressure vessel and associated piping at rated pressure following outage drywell maintenance on March 31, 2019.

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

(1) The inspectors evaluated Unit 2 refueling outage activities from March 2, 2019 through March 31, 2019. The refueling outage has not yet completed and inspection will continue into the second quarter.

(2) The inspectors evaluated the Unit 3 forced outage due to a scram from March 9 to 14, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Containment Isolation Valve (ISO) (IP Section 03.01)

Unit 2, Local leak rate testing of the outboard main steam isolation valves (MSIV) on March 5, 2019.

Reactor Coolant System (RCS) Leak Detection (IP Section 03.01) (1 Sample) Unit 3, Increasing trend in unidentified RCS leakage the week of February 25, 2019.

Surveillance Testing (IP Section 03.01) (5 Samples)

(1) Unit 1, 1-SR-3.5.1.7, high pressure coolant injection (HPCI) main and booster pump set developed head and flow rate test at rated reactor pressure, on January 16, 2019.

(2) Unit 1, 2, and 3, 0-SI-4.11.G.2, semiannual fire door inspection, on February 15, 2019.

(3) Unit 1, 2, and 3, 0-SR-3.8.1.6, common accident signal logic testing from February 13-15, 2019.

(4) Unit 2, 2-SR-3.6.1.3.5(CS II CSD), core spray loop II valves tested during cold shutdown on March 2, 2019.

(5) Unit 1 and 2, 0-SR-3.8.1.9(B), EDG B emergency Unit 2 load acceptance test on March 7, 2019.

71114.06 - Drill Evaluation Emergency Preparedness (EP) Drill (IP Section 02.01)

The inspectors evaluated an emergency preparedness drill on February 13,

71124.01 - Radiological Hazard Assessment and Exposure Controls Contamination and Radioactive Material Control (IP Section 02.03)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors verified the following sealed sources are accounted for and are intact: Sealed sources in use

• Sources in J.L. Sheppard survey instrument calibrator; containing sources (Sn:

83CS25 and 8812GM)

• Sources in J.L. Sheppard survey instrument calibrator, containing sources (Sn:

0307GY and KR-4099) Sealed sources in extended storage

• BFN # 66 High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

The inspectors evaluated risk-significant high radiation area and very high radiation area controls.

Instructions to Workers (IP Section 02.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas: Radiation work packages

• RWP-19280042, RWP-19280212, RWP-19270142, RWP-19290033, RWP-

===19270112, and RWP-1920037.

Electronic alarming dosimeter alarms

• Electronic dosimeter alarm log, March 1, 2018 - March 1, 2019 Labeling of containers
• Containers in Unit 2 reactor building, radwaste area, Unit 2 refuel floor, independent spent fuel storage installation (ISFSI).

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) ===

The inspectors evaluated radiation worker performance and radiation protection technician proficiency.

Radiological Hazard Assessment (IP Section 02.01) (1 Sample)

The inspectors evaluated radiological hazards assessments and controls. The inspectors reviewed the following: Radiological surveys

• Reviewed RWP-19280042, RWP-19280212, RWP-19270142, RWP-19290033, RWP-19270112, and RWP-1920037.

Risk significant radiological work activities

• Spent fuel pool diving, barricade installation for industrial radiography, Unit 2 drywell, Unit 2 turbine building, and Unit 2 reactor building.

Air sample survey records

• Surveys 18-20167, 18-20615, 18-20620, and 18-20661.

Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample) The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

Radiological work package for areas with airborne radioactivity:

• RWPs 19270897 (U2 RXB RWCU HX Room), 19270502 (M0174 U2 RXB 621' Holding Pump RWCU By-pass Line Drilling), 19260011 (U2 TB Deck CIV 2A Platform)

71124.02 - Occupational ALARA Planning and Controls Implementation of ALARA and Radiological Work Controls (IP Section 02.03)

The inspectors reviewed ALARA practices and radiological work controls by reviewing the following activities:

• Under-vessel maintenance
• Refuel floor activities

Radiation Worker Performance (IP Section 02.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance during under-vessel maintenance activities.

Radiological Work Planning (IP Section 02.01) (1 Sample)

The inspectors evaluated the licensees radiological work planning by reviewing the following activities:

• U2R20 refuel floor work
• U2R20 steam dryer replacement
• U2R20 under-vessel maintenance
• U2R20 drywell insulation remove/replace Verification of Dose Estimates and Exposure Tracking Systems (IP Section 02.02) (1 Sample)

The inspectors evaluated dose estimates and exposure tracking. The inspectors reviewed the following ALARA planning documents:

• ALARA Plan 19-0226
• ALARA Plan 19-0219
• ALARA Plan 19-0230
• ALARA Plan 19-0204
• ALARA Plan 19-0209 Additionally, the inspectors reviewed the following radiological outcome evaluations:
• ALARA Work In Progress Review 19-201
• ALARA Work In Progress Review 19-0213
• ALARA Work In Progress Review 19-0222
• ALARA Work In Progress Review 19-0227

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Engineering Controls (IP Section 02.01)

The inspectors evaluated airborne controls and radioactive monitoring. The inspectors reviewed the following: Installed ventilation systems

• Control room emergency ventilation systems (train a and b)

Temporary ventilation system setup

• HEPA #626 Portable or installed monitoring systems
• AMS-4 continuous air monitors Self-Contained Breathing Apparatus (SCBA) for Emergency Use (IP Section 02.03) (1 Sample)

The inspectors evaluated SCBA program implementation.

Status and surveillance records for SCBAs staged in-plant

• Unit 1 control room (JZ157568, ACZ165443, cylinder 38424 - May 2014)
• Unit 2 control room (JZ173983, ACZ156921, cylinder 29924 - October 2014)
• Unit 3 electric board room (JZ173976, ACZ170685, cylinder 20519 - September 2014)
• Work Order #119459150, 119459152 Capability to refill SCBA air bottles
• Two 5-stage air compressors on-site
• Air quality certified grade E level SCBA fit for on-shift operators
• Two Unit 1 on-shift operators interviewed, reviewed fit testing and training received.

SCBA maintenance check

• First/second stage regulators JZ157568, ACZ165443, JZ173983, ACZ156921, JZ173976, and ACZ170685.

Stocking of control room SCBA face-pieces

• Multiple mask sizes observed in Unit 1, Unit 2, and Unit 3 control rooms.

Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample) The inspectors evaluated respiratory protection. The inspectors reviewed the following: Evaluations for the use of respiratory protection

• TEDE-ALARA Evaluation Worksheet, RWP 19358007, Under-vessel Troubleshooting Respiratory protection use during work activities
• No observations were available during this inspection period.

Medical fitness for use of respiratory protection devices

• Individuals in RP, Operations and Maintenance reviewed.

Observation of donning, doffing and functional test

• No donning or doffing observations were available during this inspection period. Functional test of SCBA observed.

Respiratory protection device evaluation

• Pureflo PF60ESM

71124.04 - Occupational Dose Assessment External Dosimetry (IP Section 02.02)

The inspectors evaluated the external dosimetry program implementation.

Internal Dosimetry (IP Section 02.03) (1 Sample)

The inspectors evaluated the internal dosimetry program implementation.

Whole Body Counts

• Multiple whole body counts associated with a low-level contamination event on October 15, 2018.

In-vitro internal monitoring

• Multiple excreta sample records of tritium intakes for underwater divers.

Dose assessments performed using air sampling and DAC-hr monitoring

• None were available during this inspection.

Source Term Categorization (IP Section 02.01) (1 Sample)

The inspectors evaluated the licensees characterization of the source term and use of scaling factors for the use of hard-to-detect radionuclide activity.

Special Dosimetric Situations (IP Section 02.04) (1 Sample)

The inspectors evaluated special dosimetric situations.

Declared pregnant workers

• Multiple declared pregnant worker dosimetry records from March 2017 - March 2019.

EDEX exposures

• None were available during this inspection.

Shallow Dose Equivalent

• None were available during this inspection.

Neutron Dose Assessment

• None were available during this inspection.

71124.05 - Radiation Monitoring Instrumentation Calibration and Testing Program (IP Section 02.02)

The inspectors evaluated the calibration and testing program implementation. The inspectors specifically assessed the following types of instruments and equipment:

(1) Laboratory instrumentation

(2) Whole body counter

(3) Post-accident monitoring instrumentation

(4) Portal monitors, personnel contamination monitors, and small article monitors

(5) Portable survey instruments, area radiation monitors, and air samplers / continuous air monitors

(6) Instrument calibrator

(7) Calibration and check sources

(8) Electronic alarming dosimeters

Walk Downs and Observations (IP Section 02.01) (1 Sample)

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns to include the following:

(1) Portable survey instruments

(2) Area radiation monitors and continuous air monitors

(3) Personnel contamination monitors, portal monitors and small article monitors

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) (3 Samples)

(1) Unit 1 - January 1, 2018 through December 31, 2018.

(2) Unit 2 - January 1, 2018 through December 31, 2018.

(3) Unit 3 - January 1, 2018 through December 31, 2018.

BI02: RCS Leak Rate Sample (IP Section 02.11) ===

(1) Unit 1 - January 1, 2018 through December 31, 2018.

(2) Unit 2 - January 1, 2018 through December 31, 2018.

(3) Unit 3 - January 1, 2018 through December 31, 2018.

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample) March 1, 2018 - March 1, 2019 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences

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

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

(1) Unit 1 and 2, nitrogen pressure indication on safety related primary containment electrical penetrations not indicating correct pressure.

(2) Unit 1, 2, and 3, loss of the trinity 161kV line while closing cooling tower switchgear D supply breaker.

(3) Unit 1 and 3, failure to complete a NFPA 805 required modification by the second refueling outage.

71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

The inspectors evaluated the Unit 3 scram due to loss of offsite power (LOOP) that necessitated declaration of a Notice of Unusual Event (NOUE) and licensees response on March 9-10, 2019.

Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event reports which can be accessed at: https://lersearch.inl.gov/LERSearchCriteria.aspx LER 05000259/2018-004-01, High Pressure Coolant Injection Declared Inoperable due to Steam Supply Valve Isolation (ADAMS accession: ML19015A071): The inspectors reviewed the updated LER submittal. No new violations were provided in this LER. The previous LER submittal was reviewed in Inspection Report 05000259, 260, 296/2018-004.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

71004 - Power Uprate Summary of Power Uprate Inspection Samples Contained in this Report: Power Uprate

(1) Integrated Plant Operations at the Uprated Power Level (Unit 1)

• Power ascension above previous thermal power limits and flow induced vibration data reviews (Section 71111.11)

(2) Plant Modifications (Unit 2)

• ATWS/ARI pressure setpoint change for EPU conditions per DCN 72642 (Section 71111.18)

(3) Monitor Major Integrated Tests (Unit 1)

• Unit 1 integrated systems testing per 1-TI-700, 1-TI-130 and 1-TI-131 at EPU conditions from January 1 to January 31, 2019 (Section 71111.19)

INSPECTION RESULTS

Failure To Backwash And Drain RWCU Demineralizers Prior To Performing A System Breach.

Cornerstone Significance Cross-cutting Report Aspect Section Occupational Green [H.11] - 71124.01 Radiation Safety NCV 05000259/2019001-01 Challenge the Closed Unknown A self-revealed, Green, Non-cited Violation (NCV) of Technical Specification (TS) 5.4.1.a, Procedures was identified for failure to implement procedure NPG-SPP-10.2, Clearance Procedure to Safely Control Energy. Specifically, the licensee failed to verify that both Unit 1 Reactor Water Clean Up (RWCU) demineralizers were backwashed and drained prior to breaching the system. This resulted in a high radiation area when contaminated water and resin was spilled from the RWCU system.

Description:

On October 28, 2018, workers breached the Unit 1 RWCU system precoat inlet pipeline as part of implementation of DCN 72302-Rev. A modification, Install Integrated Flow Distributors and Slow Pressurization Capabilities. When the system was breached, radioactive water and resin leaked into the RWCU holding pump area creating a high radiation area with dose rates up to 10 rem/hour. A review of the event identified that the clearance instructions for this job required that both Unit 1 RWCU demineralizers be backwashed and drained prior to performing the planned work on the system. Licensee personnel implementing the clearance did not understand the scope of the work to be performed and failed to verify that both Unit 1 demineralizers were backwashed and drained. This left the piping full of water and used resin. The inspectors noted that the licensee personnel received 7.5 rem of additional collective exposure as a result of cleanup and recovery from the event.

Corrective Action(s): The licensee entered the problem in the corrective action program and performed immediate corrective actions, including a stand-down with the Operations Group to discuss event and reinforce proper behaviors, conducted a Performance Review Board meeting, and revised operations shift orders to include expectations going forward with placement of clearances.

Corrective Action Reference(s): Condition Reports 1460752 and 1463225.

Performance Assessment:

Performance Deficiency: Licensees failure to verify that both Unit 1 RWCU demineralizers were backwashed and drained as required by NPG-SPP-10.2, Clearance Procedure to Safely Control Energy was identified as a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Program & Process attribute of the Occupational Radiation Safety cornerstone.

Significance: The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The finding is more than minor because the performance deficiency was associated with the Occupational Radiation Safety cornerstone attribute of Program & Process and it adversely affected the associated cornerstone objective - to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. Specifically, the failure to ensure systems are drained prior to breaching them led to an unplanned collective exposure.

Cross-cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. The individual placing the clearance did not stop work and challenge the placement instructions to understand the scope of work and ensure the correct actions were taken.

Enforcement:

Violation: Technical Specification 5.4.1.a, Procedures, required that the procedures recommended in NRCs Regulatory Guide 1.33, Rev. 2, be implemented, including procedures for shutdown, draining and changing modes of operation for several plant systems including the RWCU system. Procedure NPG-SPP-10.2, Clearance Procedure to Safely Control Energy established standard requirements for group tag out to safely control hazardous energy. Consequently, placement instructions for Tag Out 1-TO-1R12-00HO required the licensee to verify that both Unit 1 RWCU system demineralizers be backwashed and drained prior to placing the clearance.

Contrary to the above, on October 28, 2018, the licensee placed Tag Out 1-TO-1R12-00HO clearance without verifying that both demineralizers in the Unit 1 RWCU system were backwashed and drained prior to placing the clearance.

Enforcement Action: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.

Failure To Establish And Implement Adequate Procedures For Diving Activities And The Underwater Storage Of Highly Radioactive Materials.

Cornerstone Significance Cross-cutting Report Aspect Section Occupational Green [H.12] - Avoid 71124.01 Radiation Safety NCV 05000259/2019001-02 Complacency Closed A self-revealed, Green, Non-cited Violation of Technical Specification 5.4.1.a, Procedures, was identified for multiple examples of the failure to establish and implement adequate procedures for the control of diving activities and the storage of radioactive materials underwater. Specifically, during diving activities in the Unit 1 Equipment Pit, the licensee failed to follow radiological control procedures which resulted in a diver encountering unexpected high dose rates and receiving unplanned dose near a spent filter storage rack.

Description:

On October 19, 2018, the licensee began diving operations on the Unit 1 (U1) refuel floor (elevation 664) in the Equipment Pit to dismantle the old steam dryer. On November 7, 2018, a diver came within close proximity of two highly radioactive Tri Nuclear underwater filter/vacuum filters and received multiple electronic dosimeter dose rate alarms, with the highest being 71.7 Rem/hr. Although the diver encountered high dose rates, the duration of exposure was brief due to a quick response by the dive team and Radiation Protection (RP)personnel. No regulatory limits were exceeded.

During the November, 2018 Special Inspection (Inspection Report 05000259/2018050) to gather information surrounding the November 7, 2018 dive event, Unresolved Item (URI)05000259/2018050-02 was opened by the NRC. The purpose of the URI was for NRC to review the results of the licensees root cause evaluation to determine if; 1) performance deficiencies existed regarding procedural shortfalls related to work control and coordination between workgroups, and control of underwater movement and storage of highly radioactive, non-fuel, items in the spent fuel pool/equipment pit areas; and 2) if procedural inadequacies were a root or contributing cause of the event.

The licensee's investigation determined that the Root Cause of the dive event was that RP staff failed to apply appropriate standards and fundamentals to control the high radiological risk diving evolution. The identified failures included: 1) spent Tri Nuclear filters and filter storage racks were not controlled in accordance with NISP-RP-04, Radiological Posting and Labeling, and RCDP-17, Radiological Postings in that no tags identifying the filter storage racks as radioactive material were in place and the racks were not locked or controlled by RP at the time; and 2) dedicated RP oversight for the diving evolution was not provided as required by NPG-SPP-05.2.6, Radiological Risk Management. Two Contributing Causes were also identified including; 1) No procedural requirement to document the location of spent Tri Nuclear filters existed; and 2) RP Personnel relied on the guidance in RCI-33, Diving Operations on the Refuel Floor, and failed to implement other applicable RP procedures.

Corrective Action(s): Corrective actions taken by the licensee included revision of RCI-33 to require the Radiation Protection Manager (RPM) to verify the proper controls are in place for the high radiological risk diving activity prior to each dive; revision of NPG-SPP-05.2.6 to include the RP Outage Radiological Risk Management Plan; revision of RCDP-17, to include guidance for underwater survey and control requirements, and change-out criteria for Tri Nuclear underwater vacuum units; and revision of the RP Underwater Diving Operations Briefing to include lessons learned from the dive event. Additional actions included, methodology developed and a procedure written for inventory and control of highly radioactive materials stored in the spent fuel pool/reactor cavity/equipment pit, and implementation of an RP Procedure Knowledge Assessment to test RP supervisor and technician ability to apply RP procedures and radiological fundamentals.

Corrective Action Reference(s): Condition report 1464279

Performance Assessment:

Performance Deficiency: The licensees failure to establish and implement adequate procedures for the control of diving activities and storage of radioactive materials underwater, as required by TS, was determined to be a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Program & Process attribute of the Occupational Radiation Safety cornerstone. The failure to follow procedures for the control of diving activities and storage of radioactive materials underwater could result in potentially significant exposure events.

Significance: The inspectors assessed the significance of the finding using Appendix C, Occupational Radiation Safety SDP. The finding was not related to As Low As Reasonably Achievable planning, nor did it involve an overexposure or substantial potential for overexposure, and the ability to assess dose was not compromised. Therefore, the inspectors determined the finding to be of very low safety significance (Green).

Cross-cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. The licensee failed to follow all procedure requirements needed to ensure a safe diving evolution while relying solely on RCI-33, thereby fostering an environment where diving operations were considered routine.

Enforcement:

Violation: Technical Specification 5.4.1.a, Procedures, required that the procedures recommended in Regulatory Guide 1.33, Rev. 2, be established and implemented, including procedures for Radiation Protection.

Contrary to this, on November 7, 2018, the licensee failed to establish and implement adequate procedural requirements for radiation protection. Specifically, procedures NISP-RP-04, RCDP-17, and NPG-SPP-05.2.6 were not implemented to control diving activities in the U1 Equipment Pit. In addition, no procedural guidance was established to document the location of spent Tri Nuclear filters. These actions resulted in a diver encountering unexpected high dose rates and receiving unplanned dose near a spent filter storage rack.

Enforcement Action: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.

The disposition of this finding and associated violation closes URI: 05000259/2018050-02.

Failure to Implement a Required NFPA 805 Modification in the Timeframe Described in the Operating License Cornerstone Severity Cross-cutting Report Aspect Section Not Applicable Severity Level IV Not 71152 NCV 05000259, 296/2019001-03 Applicable Closed A NRC identified Severity Level (SL) IV Non-Cited Violation (NCV) of the renewed operating license for Units 1 (DPR-33) and 3 (DPR-68) was identified for the failure to implement a required modification to the Main transformers, Unit Station Service Transformers (USSTs),and Common Station Service Transformers (CSSTs) as described in NFPA 15-2001 before the end of the second refueling outage.

Description:

Browns Ferry was approved to transition to the fire protection requirements described in NFPA-805 by a license amendment on October 28, 2015. One of the new license conditions required a series of modifications to the plant that were described in Table S-2, Plant Modifications, of Tennessee Valley Authority letter CNL-17-024, dated June 7, 2017 that were due to be completed prior to the end of the second refueling outage. Table S-2, Plant Modifications described modification 102 as a change to the Main transformer, USST and CSST water spray systems such that the circuits are supervised per NFPA 15-2001, 6.5.3.1.1. There were multiple challenges experienced by the licensee in implementing this modification and they were unable to complete it on time. The licensee also misunderstood the required completion time and thought they had until the end of the second Unit 2 refueling outage which is scheduled to be completed in April 2019. The licensee submitted a license amendment request extending the due date of this modification for all three units until August 14, 2019. By letter dated April 2, 2019, the NRC approved a license amendment that included extension to the due date for Modification 102 for Units 1, 2, and 3 effective on the amendments issuance date.

Corrective Action(s): Corrective actions were submission of a License Amendment Request (LAR) dated October 18, 2018 that requested a change to the Browns Ferrys approved fire protection program. Specifically, TVA requested to change the due date for Modification 102, which was applicable to Units 1, 2, and 3, in Table S-2 to no later than August 14, 2019 for all Browns Ferry units. By the supplement to the LAR dated February 13, 2019, TVA requested a change to Table S-2, Modification 102 unit from 1, 2, and 3 to common as found in the original LAR. The licensee is also redesigning their planned modification to allow it to be completed before the new required completion time.

Corrective Action Reference(s): Condition Report 1494570

Performance Assessment:

This violation is being documented without an associated finding because the violation only pertains to license required modification completion times. The Main transformer, USST, and CSST spray systems did not require this modification to perform their required function.

Enforcement:

The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non-compliance.

Severity: This violation was dispositioned as a severity level (SL) IV violation because it is similar to Enforcement Policy section 6.1, Reactor Operations example d.1. A failure to comply with a technical specification action requirement demonstrates misapplication of the conventions in technical specifications Section 1.0, Use and Application, or the allowances for LCO and surveillance requirement applicabilities in technical specifications Section 3.0.

Violation: Renewed License No. DPR-33 Section 2.C.(13).Transition License Conditions.2 and Renewed License No. DPR-68 Section 2.C.(7).Transition License Conditions.2 required, in part, that the licensee shall implement modifications to its facility, as described in Table S-2, Plant Modifications, of Tennessee Valley Authority letter CNL-17-024, dated June 7, 2017, to complete the transition to full compliance with 10 CFR 50.48(c) no later than the end of the second refueling outage (for each unit) following issuance of the NFPA 805 license amendment dated October 28, 2015. Table S-2, Plant Modifications, required, in part, that plant modification 102 will be completed on Units 1, 2, and 3 to modify the actuation for the Main transformer, USST and CSST water spray systems such that the circuits are supervised per NFPA 15-2001, 6.5.3.1.1. By letter dated April 2, 2019, the NRC approved license amendments that included extension to the due date for Modification 102 for Units 1, 2, and 3 effective on the amendments issuance date.

Contrary to the above, Units 1 and 3 plant modification 102 for the Main transformer, USST and CSST water spray systems were not completed to comply with NFPA 15-2001, 6.5.3.1.1 prior to the end of their second refueling outages. Therefore, Unit 1 was in violation from November 20, 2018 (the end of its second refueling outage) until April 2, 2019 and Unit 3 was in violation from April 6, 2018 (the end of its second refueling outage) until April 2, 2019.

Enforcement Action: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.

Unresolved Item Unit 3 Notice of Unusual Event (NOUE) Caused by of a 71153 (Open) Loss of Offsite Power (LOOP) Resulting in a Reactor Scram 05000296/2019001-04

Description:

The loss of excitation due to operation of the auto-voltage regulator (AVR) in manual on the Browns Ferry unit 3 main generator caused the main generator output and 500kV switchyard breakers to open due to a sudden increase in output current. Additional inspection is required to determine if there are performance deficiencies associated with this event.

Planned Closure Action(s): Follow up inspection using Inspection Procedure (IP) 71111.01 Adverse Weather Protection is required to review the electrical lineup that resulted in the loss of offsite power (LOOP). Follow up inspection using IP 71152 Problem Identification and Resolution is required to review the licensees causal analysis for this event. Follow up inspection using IP 71153 Follow up of Events and Notices of Enforcement Discretion is required to review the Licensee Event Report (LER) associated with this event.

Licensee Action(s): The licensee restored offsite power to the Unit 3 4kV shutdown boards to exit the NOUE. The licensee removed the two reactor operators on watch during the event from licensed duties. The licensee placed the reactor in Mode 4 cold shutdown while reviewing the events that led to the emergency declaration and scram.

Corrective Action Reference(s): Condition Report

EXIT MEETINGS AND DEBRIEFS

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

On April 26, 2019, the inspectors presented the inspection results to Lang Hughes, Site Vice President and other members of the licensee staff.

THIRD PARTY REVIEWS The inspectors reviewed the WANO Peer Review report from July 2018 that was issued during the inspection period.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 71111.01 Corrective Action CR 1466957 Documents 71111.01 Corrective Action CR 1474188 Documents 71111.01 Corrective Action CR 1480259 Documents 71111.01 Miscellaneous BFN Freeze Protection Open WO's 71111.01 Procedures 0-GOI-200-1 Freeze Protection Inspection Revision 88 71111.01 Procedures EPI-0-000-FRZ001 Freeze Protection Program for RHRSW Pump Rooms Revision 26 and Diesel Generator Bldg Air Plenums 71111.01 Procedures NPG-SPP-07.1.8 Severe Weather and Natural Disasters Revision 1 71111.04S Corrective Action CR 1496966 Documents 71111.04S Corrective Action CR 1491715 Documents 71111.04S Corrective Action CR 1498426 Documents 71111.04S Corrective Action CR 1498851 Documents 71111.04S Drawings 0-47E873-1 Flow Diagram Aux Decay Heat Removal System, Revision 8 71111.04S Procedures 0-OI-72, Auxiliary Decay Heat Removal, Revision 65 Revision 65 71111.05A Corrective Action CR 1495317 Documents 71111.05A Corrective Action CR 1495554 Documents 71111.05A Drawings 0-47E216-118 Ignition Source Drawings Plan EL. 604.0 Revision 4 71111.05A Procedures FPDP-1 Conduct of Fire Operations Revision 9 71111.05A Procedures FPDP-4 Fire Emergency Response Revision 7 71111.05Q Calculations MDN0003332012000102 BFN Main Control Room Analysis Revision 11 71111.05Q Calculations MDN0009992012000100 Browns Ferry Nuclear Power Plant, Units 1, 2, and 3, Revision 8 Fire Risk Evaluations Inspection Type Designation Description or Title Revision or Procedure Date 71111.05Q Calculations NDN0009992012000012 TVA Fire PRA - Task 7.14: Fire Risk Quantification Revision 5 71111.05Q Corrective Action CR 1479783 Documents 71111.05Q Corrective Action CR 1479784 Documents 71111.05Q Corrective Action CR 1488504 Documents 71111.05Q Corrective Action CR 1490302 Documents 71111.05Q Drawings 0-47E216-107 Ignition Source Drawings Plan EL. 617.0 & 621.25 Revision 3 71111.05Q Drawings 0-47E216-108 Ignition Source Drawings Plan E

L. 606.0, 617.0 & Revision 2

21.25 71111.05Q Fire Plans FPR-Volume 2 Fire Protection Report Volume 2, Attachments 4, 5 Revision 63 and 6 71111.05Q Fire Plans FPR-Volume 2 Fire Protection Report Volume 2 Revision 64 71111.05Q Miscellaneous Fire Protection Impairment Permit 13- 4035 71111.05Q Miscellaneous Fire Protection Impairment Permit 16- 5465 71111.05Q Miscellaneous ML16190A242 Revision to NFPA 805 Interim Compensatory Measures Commitments Regarding Fire Watches and Voluntary Commitment to Notify NRC of Commitment Revisions 71111.05Q Miscellaneous NFPA 805 Fire Section 4 Revision 1 Protection Report 71111.05Q Miscellaneous NFPA 805 Fire Revision 7 Protection Requirements Manual 71111.05Q Miscellaneous NFPA 805, Fire Appendix F, Fire Area 16 Revision 3 Protection Report 71111.05Q Miscellaneous NFPA 805, Fire Appendix F, Fire Area 26 Revision 4 Protection Report Inspection Type Designation Description or Title Revision or Procedure Date 71111.05Q Procedures 1-FSS-16-2, Unit 1 Abandonment Control Building EL 593, 606, Revision 5 617 and 635 71111.05Q Procedures FP-0-000-INS012 Fire Watch Expectations Revision 3 71111.05Q Procedures NPG-SPP-18.4.6 Control of Fire Protection Impairments Revision 10 and 13 71111.05Q Procedures NPG-SPP-18.4.7 Control of Transient Combustibles Revision 12 71111.06 Procedures BFN-0-PMP-040-072 Operability Check, Plant Sump Pumps for Handholes Revision 4 and 26 71111.08G Corrective Action CR-1326804 Transmit BWRVIP -183-A to the BRWVIP Executive 8/10/17 Documents Committee 71111.08G Corrective Action CR 1496837 U2R20 ISI NRC Inspection-NRC Identified Snubber 3/7/19 Documents Walked On Resulting from Inspection 71111.08G Drawings 2-ISI-0415-C Browns Ferry Nuclear Plant, Unit 2, Reactor Vessel Rev. 1 Supports 71111.08G Drawings ISI-0351-A Browns Ferry Nuclear Plant Unit-2, Instrumentation Rev. 00 Nozzles Wels Locations 71111.08G Miscellaneous 1.M.1.2-5 G.W.

P.S. 1.M.1.2, Attachment B, Weld Joint Detail, Rev. 4

Open Butt, Single Vee Butt Weld 71111.08G Miscellaneous CRD-2-010-001, C0R0 MMDP-10, Category I/II Welds Data Sheet 2/6/19 71111.08G Miscellaneous CRD-2-010-001, Radiographic Examination Report 2/16/19 Drawing. or Weld Map CRD-2-010-1 71111.08G Miscellaneous CRD-2-010-015, C0R0, MMDP-10, Category I/II Weld Data Sheet Weld Map CRD-2-010-2 2/6/19 71111.08G Miscellaneous CRD-2-010-015, Radiographic Examination Report 2/16/19 Drawing No. or Weld Map CRD-2-010-2 71111.08G Miscellaneous DWPS GT11-O-1-N G29 Detailed Welding Procedure Specification Rev.2

                                                (DWPS)

ASME/ANSI - GWPS 1.M.1.2 71111.08G Miscellaneous JHH1373 IHI Southwest Technologies, Certificate of 6/19/18 Qualification, Magnetic Particle (MT) Inspection Type Designation Description or Title Revision or Procedure Date 71111.08G Miscellaneous RNP90YKE1 Welder Qualification Continuity Record 3/5/19 71111.08G Miscellaneous Ultrasonic Qualification, Ultrasonic Hands On Practical Documentation 1/16/19 D. Maclean 71111.08G Miscellaneous WPQR No. GT11-0-1A Welding Procedure Qualification Record 11/6/03 71111.08G Miscellaneous WPQR No. GT11-SPEC- Welding Procedure Qualification Record 12/30/87 71111.08G Miscellaneous ZQ7YP17AG Welder Qualification Continuity Record 3/5/19 71111.08G NDE Reports 0-TI-417, Attachment 1 Inspection of Service Level I, II, III Protective Coatings, Rev. 27, Moisture Seal Barrier, Condensate Storage Tanks and 3/18/19 ECCS Suction Strainers. (Completed for Unit-2 Moisture Barrier on 3/16/19) 71111.08G NDE Reports BFNU2R19, Form OAR- Owners Activity Report, ASME Section XI, Subsection 6/23/17 IWE, Examination Category E-A, Item E1.30, Component ID: MSB-2-1 Moisture Seal Barrier 71111.08G NDE Reports NDE Report No. R056 Record of Magnetic Particle Examination of 5/27/09 Component ID, RPV-Supp-2-1-IA, Browns Ferry Nuclear Unit-2, Reactor Vessel Support 71111.08G NDE Reports R-075 Magnetic Particle Examination RPV-SUPP-2.1-1A, 3/15/19 Vessel to Skirt Weld 71111.08G NDE Reports R055 VT-3 of Component ID No. RPV-Supp-2-1, Reactor 5/27/09 Vessel Support 71111.08G NDE Reports Report No. R-040 Ultrasonic Calibration-Examination Record , N-16A-1 3/7/19 71111.08G NDE Reports Report No. R-170, Visual Examination (VT-1) of the repaired Area of the 3/18/17 Summary No. 00739- Moisture Seal Barrier IWE-BFN-2 71111.08G NDE Reports Summary No. BFN-2-TG EVT-1 Examination Results, BFN-2-TG 000 Aligner 3/20/19 000 Aligner Pin, Socket Pin, Socket Location 2-3_D40 Location 2-3_D40 71111.08G NDE Reports Summary No. BFN-2-TG EVT-1 Examination Results, TG 000 Aligner Pin, 3/20/19 000 Aligner Pin, Socket Socket Location 2-3_D40_90 Deg. Location 2-3_D40_90 Deg. 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examination Results, TG 090 Aligner Pin, 3/20/19 Inspection Type Designation Description or Title Revision or Procedure Date 090 Aligner Pin, Socket Socket Location 2-3_D40 Location 2-3_D40 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examination Results, TG 090 Aligner Pin, 3/20/19 090 Aligner Pin, Socket Socket Location 2-3_D40_ 90 Deg. Location 2-3_D40_90 Deg. 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examination Results, TG 180 Aligner Pin, 3/20/19 180 Aligner Pin, Socket Socket Location 2-3_D40 Location 2-3_D40 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examination Results, TG 180 Aligner Pin, 3/20/19 180 Aligner Pin, Socket Socket Location 2-3_D40_90 Deg. Location 2-3_D40_90 Deg. 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examinations Results, TG 270 Aligner Pin, 3/20/18 270 Aligner Pin, Socket Socket Location 2-3_D40 Location 2-3_D40 71111.08G NDE Reports Summary No. BNF2-TG EVT-1 Examination Results, TG 270 Aligner Pin, 3/20/19 270 Aligner Pin, Socket Socket Location 2-3_D40_90 Deg. Location 2-3_D40_90 Deg. 71111.08G Procedures GEH-VT-204 Procedure for In-Vessel Visual Inspection (IVVI) of Version No. BWR 4 RPV Internals 17 71111.08G Procedures N-MT-6 Magnetic Particle Examination for ASME and ANSI Rev. 0036 Code Components and Welds 71111.08G Procedures N-UT-64 Generic Procedure for the Ultrasonic Examination of Rev. 0016 Austenitic Pipe Welds 71111.08G Self- CRP-ENG-FSA-17-004 Browns Ferry Nuclear, ASME Section XI, ISI, IWE, 7/24/17 thru Assessments System Pressure Test and Repair Replacement 8/4/17 Programs Assessment 71111.11Q Miscellaneous Simulator Exercise Guide #: OPL175S103 71111.11Q Procedures 2-AOI-100-1 Reactor Scram Revision 108 71111.11Q Procedures 2-GOI-100-12A Unit Shutdown from Power Operation to Cold Revision Inspection Type Designation Description or Title Revision or Procedure Date Shutdown and Reductions in Power During Power 111 Operations 71111.11Q Procedures 2-SR-3.4.9.1(1) Reactor Heatup and Cooldown Rate Monitoring Revision 29 71111.11Q Procedures NPG-SPP-17.8.4 Conduct of Simulator Operations Revision 6 71111.11Q Work Orders WO 118873724 71111.12 Corrective Action CR 1131914 Documents 71111.12 Corrective Action CR 1372873 Documents 71111.12 Corrective Action CR 1436003 Documents 71111.12 Corrective Action CR 1471106 Documents 71111.12 Corrective Action CR 1473957 Documents 71111.12 Corrective Action CR 923412 Documents 71111.12 Miscellaneous (a)(1) Evaluation for Function 074-B, RHR Low Pressure Coolant Injection (LPCI) 71111.12 Miscellaneous System Health Report for RHR System 71111.12 Procedures 0-TI-346 Maintenance Rule Performance Indicator Monitoring, Revision 51 Trending, and Reporting - 10CFR50.65 71111.12 Procedures 0-TI-395 Breaker Testing and Maintenance Program Revision 12 71111.12 Procedures ECI-0-000-BKR008 Testing and Troubleshooting of Molded Case Circuit Revision Breakers and Motor Starter Overload Relays 107 71111.12 Procedures EPI-0-000-MCC001 Maintenance and Inspection of 480VAC and 250VDC Revision 82 Motor Control Centers 71111.12 Procedures NPG-SPP 03.4 Maintenance Rule Performance Indicator Monitoring, Revision 3 Trending and Reporting - 10CFR50.65 71111.12 Procedures NPG-SPP 22.500 Operating Experience Program Revision 7 71111.12 Work Orders WO 111380463 Inspection Type Designation Description or Title Revision or Procedure Date 71111.12 Work Orders WO 116508685 71111.12 Work Orders WO 117625327 71111.12 Work Orders WO 117625328 71111.12 Work Orders WO 117625329 71111.12 Work Orders WO 117625330 71111.12 Work Orders WO 117625331 71111.12 Work Orders WO 117625332 71111.12 Work Orders WO 119302092 71111.12 Work Orders WO 119774766 71111.12 Work Orders WO 119774793 71111.12 Work Orders WO 120267007 71111.13 Corrective Action CR 1494904 Documents 71111.13 Corrective Action CR 1495306 Documents 71111.13 Corrective Action CR 1499057 Documents 71111.13 Corrective Action CR 1499381 Documents 71111.13 Drawings 2-47E803-5 Flow Diagram Reactor Feedwater System Revision 32 71111.13 Miscellaneous Unit 2 Cycle R20 Outage Safety Plan Revision 1 71111.13 Procedures 0-AOI-72-1 Auxiliary Decay Heat Removal System Failures Revision 23 71111.13 Procedures 0-TPP-FPP-011 BFN NFPA 805 Non-Power Operations Fire Risk Revision 4 Management 71111.13 Procedures 2-GOI-100-3A Refueling Operations (Rx Vessel Disassembly and Revision 57 Floodup) 71111.13 Procedures 2-OI-75 Core Spray System Revision 114 71111.13 Procedures 2-POI-200.5 Operations with Potential for Draining the Reactor Revision 20 Vessel/Cavity 71111.13 Procedures BFN-ODM-4.18 Protected Equipment Revision 21 71111.13 Procedures NPG-SPP-07.2.11 Shutdown Risk Management Revision 12 71111.13 Procedures NPG-SPP-09.11.1 Equipment Out of Service Management Revision 12 Inspection Type Designation Description or Title Revision or Procedure Date 71111.13 Procedures NPG-SPP-10.6 Infrequently Performed Test or Evolutions Revision 1 71111.15 Calculations MDQ007420020025 Residual Heat Removal System (RHR) Modes of Revision 6 Operation 71111.15 Calculations MDQ107420020078 MOV 1-FCV-074-0059 & MOV 1-FCV-074-0073, Revision 3 Operator Requirements and Capabilities 71111.15 Corrective Action CR 1117364 Documents 71111.15 Corrective Action CR 1334534 Documents 71111.15 Corrective Action CR 1335322 Documents 71111.15 Corrective Action CR 1474167 Documents 71111.15 Corrective Action CR 1474340 Documents 71111.15 Corrective Action CR 1480006 Documents 71111.15 Corrective Action CR 1480744 Documents 71111.15 Corrective Action CR 1481629 Documents 71111.15 Drawings 3-45E724-9 Wiring Diagram 4160V Shutdown Bd 3ED Single Line Revision 34 71111.15 Drawings 3-45E732-5 Wiring Diagram 480V Diesel Aux Bd 3EA Single Line Revision 30 71111.15 Drawings 3-45E766-15 Wiring Diagram 4160V Shutdown Aux Power Revision 13 Schematic Diagrams 71111.15 Drawings 3-45E771-8 Wiring Diagram 480V Diesel Aux Power Schematic Revision 31 Diagram 71111.15 Miscellaneous Operations Work Around 3-071-OWA-2019-0002 71111.15 Miscellaneous Operator Logs dated 2/10/2019 - 12/11/2019 71111.15 Operability Prompt Determination of Evaluations Operability for CR 1474340 Inspection Type Designation Description or Title Revision or Procedure Date 71111.15 Operability Prompt Determination of Evaluations Operability for CR 1497454 71111.15 Procedures 0-GOI-300-2 Electrical Revision 150 71111.15 Procedures 3-OI-71 Reactor Core Isolation Cooling System Revision 61 71111.15 Procedures 3-SR-3.8.1.9(3D OL) Diesel Generator 3D Emergency Load Acceptance Revision 18 Test with Unit 3 Operating 71111.15 Procedures OPDP-8 Operability Determination Process and Limiting Revision 24 Conditions for Operation Tracking 71111.15 Work Orders WO 116874646 71111.15 Work Orders WO 119014950 71111.15 Work Orders WO 119105140 71111.15 Work Orders WO 120067967 71111.15 Work Orders WO 120156779 71111.15 Work Orders WO 120160577 71111.18 Calculations EDN2003920049 Setpoint and Scaling Calculation for 2-P-3-204A, - Revisions 5, 204B, -204C, and -204D 6&7 71111.18 Corrective Action CR 1273615 Documents 71111.18 Miscellaneous Detailed Design Criteria Control Rod Drive System Revision 14 Document, BFN-50-7085 71111.18 Procedures 2-SR-3.3.4.2.3(A) Anticipated Transient Without Scram(ATWS) - Revision 14 Recirculation Pump Trip(RPT) System Reactor High Pressure Channel A Calibration 2-P-3-204A 71111.18 Procedures 2-SR-3.3.4.2.3(B) Anticipated Transient Without Scram(ATWS) - Revision 15 Recirculation Pump Trip(RPT) System Reactor High Pressure Channel B Calibration 2-P-3-204B 71111.18 Procedures 2-SR-3.3.4.2.3(C) Anticipated Transient Without Scram(ATWS) - Revision 12 Recirculation Pump Trip(RPT) System Reactor High Pressure Channel C Calibration 2-P-3-204C 71111.18 Procedures 2-SR-3.3.4.2.3(D) Anticipated Transient Without Scram(ATWS) - Revision 11 Recirculation Pump Trip(RPT) System Reactor High Pressure Channel A Calibration 2-P-3-204C Inspection Type Designation Description or Title Revision or Procedure Date 71111.18 Procedures 2-TI-700/ATT-16 Required EPU Unit-2 R-20 Modifications Revision 0 71111.18 Work Orders WO 118850178 71111.18 Work Orders WO 118850179 71111.18 Work Orders WO 118850180 71111.18 Work Orders WO 118850181 71111.19 Procedures 1-TI-130 Main Steam Pressure Control Revision 3 71111.19 Procedures 1-TI-131 Feedwater Level Control System Revision 2 71111.19 Procedures 1-TI-700 EPU Master Startup Test Instruction Revision 0 71111.19 Procedures 2-SI-3.3.1.A ASME Section XI System Leakage Test of the Reactor Revision 41 Pressure Vessel and Associated Piping (ASME Section III, Class 1 and 2) 71111.19 Procedures 2-TI-358 ASME Section XI Hydrostatic Primary System Revision 17 Pressure Test Boundary 71111.19 Procedures 3-SI-4.4.A.1 Standby Liquid Control Pump Functional Test Revision 60 71111.19 Procedures 3-SR-3.3.1.1.8(9) Turbine Control Valve Fast Closure, or Turbine Trip Revision 33 and RPT Initiate Logic 71111.19 Procedures 3-SR-3.8.1.1(3B) Diesel Generator 3B Monthly Operability Test Revision 57 71111.19 Procedures 3-TI-130 Main Steam Pressure Control Revision 6 71111.19 Procedures 3-TI-380 Power Ascension Turbine Valve Test Revision 4 71111.19 Procedures ECI-0-000-RLY003 Replacement of Relays Revision 28 71111.19 Procedures PMTI-71400-002 EHPM Pump RPV Injection Test at Low Pressure Revision 0 Conditions 71111.22 Corrective Action CR 1316896 Documents 71111.22 Corrective Action CR 1469446 Documents 71111.22 Corrective Action CR 1491233 Documents 71111.22 Drawings 1-47E812-1 Flow Diagram High Pressure Coolant Injection System Revision 47 71111.22 Drawings 1-47E812-2 Flow Diagram HPCI Oil System Revision 5 71111.22 Miscellaneous Unit 3 Leakrate Data 71111.22 Procedures 0-SI-4.11.G.2 Semiannual Fire Door Inspection Revision 31 71111.22 Procedures 0-SR-3.8.1.9(B) Diesel Generator B Emergency Unit 2 Load Revision 21 Inspection Type Designation Description or Title Revision or Procedure Date Acceptance Test 71111.22 Procedures 0-TI-298 Diesel Generator Operating Data Acquisition Revision 21 71111.22 Procedures 1-SR-3.5.1.7 HPCI Main and Booster Pump Set Developed Head Revision 40 and Flow Rate Test at Rated Reactor Pressure 71111.22 Procedures 2-SR-3.6.1.3.10 (A- Primary Containment Local Leak Rate Test Main Revision 9 OUTBD) Steam Line A Outboard: Penetration X-7A 71111.22 Procedures 2-SR-3.6.1.3.10 (B- Primary Containment Local Leak Rate Test Main Revision 9 OUTBD) Steam Line B Outboard: Penetration X-7B 71111.22 Procedures 2-SR-3.6.1.3.10 (C- Primary Containment Local Leak Rate Test Main Revision 10 OUTBD) Steam Line C Outboard: Penetration X-7C 71111.22 Procedures 2-SR-3.6.1.3.10 (D- Primary Containment Local Leak Rate Test Main Revision 9 OUTBD) Steam Line D Outboard: Penetration X-7D 71111.22 Procedures 3-SR-2 Instrument Checks and Observations Revision 80 71111.22 Procedures 3-TI-275A Drywell Leak Investigation Temperature Revision 6 71111.22 Procedures 3-TI-275B Drywell Leak Investigation - Radwaste Sumps Revision 1 71111.22 Procedures 3-TI-275C Drywell Leak Investigation - Primary Containment Revision 0 Leak Detection CAM, 3-RM-90-256 71111.22 Procedures 3-TI-275D Drywell Leak Investigation - Chemistry Revision 8 71111.22 Procedures 3-TI-275E Drywell Leak Investigation Analysis Revision 9 71111.22 Work Orders WO 117448290 71111.22 Work Orders WO 118061038 71111.22 Work Orders WO 118061039 71111.22 Work Orders WO 118849950 71111.22 Work Orders WO 118860745 71111.22 Work Orders WO 118970833 71111.22 Work Orders WO 118970845 71111.22 Work Orders WO 118970850 71111.22 Work Orders WO 118970875 71111.22 Work Orders WO 119360064 71111.22 Work Orders WO 120250867 71124.01 ALARA Plans APR 18-0135, APR 18- ALARA Plans 0136, and APR 18-0137 71124.01 ALARA Plans U2R20 Outage Steam U2R20 Outage Steam Dryer Replacement ALARA February 25, Inspection Type Designation Description or Title Revision or Procedure Date Dryer Replacement Plan 2019 ALARA Plan 71124.01 Corrective Action 1399079, 1485534, Corrective Action Reports Documents 1442072, 1449875, 1411376, 1415753, 1442073, 1485534, 1392795, 1398535, 1463225, and 1500332 71124.01 Corrective Action 1464279 Root Cause Analysis - Refuel Floor Diving Documents 71124.01 Miscellaneous 0-TI-540 Storage Material in the Spent Fuel Storage Pool July 18,

                                                   (SFSP) and Transfer Canal (U1)                    2018

71124.01 Miscellaneous 0-TI-540 Storage Material in the Spent Fuel Storage Pool August 23,

                                                   (SFSP) and Transfer Canal (U2)                    2018

71124.01 Miscellaneous 0-TI-540 Storage Material in the Spent Fuel Storage Pool August 23,

                                                   (SFSP) and Transfer Canal (U3)                    2018

71124.01 Miscellaneous Clearance Folder: NPG-SPP-10.2, Clearance Folder: Tagout 1-TO- March 13, Tagout 1-TO-1R12- 1R12-00HO, Clearance Section: 1-069-0003 (TVA 2019 00HO, Clearance Form 17982) Section: 1-069-0003 71124.01 Miscellaneous CR 1460752 Level 2 Evaluation Report, Unit 1 entered 1-EOI-3 December Secondary Containment Control due to a high 11, 2018 radiation condition in the reactor building 71124.01 Miscellaneous U2R20 Outage Steam U2R20 Outage Steam Dryer Replacement Pre-Job Dryer Replacement Pre- Brief Job Brief 71124.01 Procedures 0-SI-4.8.E Leak Test, Inventory and Documentation of Rev. 0020 Radioactive Sources 71124.01 Procedures 1-OI-69 Reactor Water Cleanup System Rev. 0072 and Rev. 0073 71124.01 Procedures NISP-RP-02 Radiation and Contamination Surveys Rev. 0000 71124.01 Procedures NISP-RP-04 Radiological Posting and Labeling Rev. 0000 71124.01 Procedures NISP-RP-05 Access Controls for High Radiation Areas Rev. 0000 Inspection Type Designation Description or Title Revision or Procedure Date 71124.01 Procedures NISP-RP-06 Personnel Contamination Monitoring Rev. 0000 71124.01 Procedures NISP-RP-10 Radiological Job Coverage Rev. 0000 71124.01 Procedures NISP-RP-11 Radiation Protection Fundamentals Rev. 0000 71124.01 Procedures NPG-SPP-05.01 Radiological Controls Rev. 0010 71124.01 Procedures NPG-SPP-05.16 Administrative Controls for Performance of Rev. 0008 Radiography Operations 71124.01 Procedures NPG-SPP-05.18 Radiation Work Permits Rev. 0007 71124.01 Procedures NPG-SPP-05.2.6 Radiological Risk Management Rev. 0003 71124.01 Procedures NPG-SPP-10.2 Clearance Procedure to Safely Control Energy Rev. 0021 71124.01 Procedures RCDP-10 Personnel Contamination Event Documentation Rev. 0008 71124.01 Procedures RCDP-17 Radiological Postings Rev. 0001 71124.01 Procedures RCDP-22 Control of High Radiation Areas and Very High Rev. 0000 Radiation Areas 71124.01 Procedures RCDP-23 Control of Radioactive Material Rev. 0000 71124.01 Procedures RCI-1.1 Radiation Operations Program Implementation Rev. 0172 71124.01 Procedures RCI-1.2 Radiation, Contamination, and Airborne Surveys Rev. 0041 71124.01 Procedures RCI-17 Control of High Radiation Areas and Very High Rev. 0091 Radiation Areas 71124.01 Procedures RCI-33 Diving Operations on the Refuel Floor Rev. 0016 and Rev. 0017 71124.01 Procedures RCI-47 Diving Operations in the Radiologically Controlled Rev. 0006 Area and Rev. 0007 71124.01 Radiation M-20190304-23, M- Surveys Surveys 20190305-54, M- 20190303-14, M- 20190303-26, M- 20190305-17, M- 20190305-55, M- 20181028-18, M- 20181028-22, M- 20181028-28, M- 20181028-11, M- Inspection Type Designation Description or Title Revision or Procedure Date 20181028-46, M- 20181028-17, M- 20181028-19, M- 20181028-24, M- 20181028-27, M- 20181028-32, M- 20181028-44, M- 20190103-20, M- 20181206-15, M- 20190304-7, M- 20190302-42, M- 20190302-64, M- 20190312-58, M- 20181027-21, M- 20181003-14, M- 20190128-17, M- 2019131-4, M- 20181129-9, M- 20181013-12, M- 20181028-32, M- 20181113-8, M- 20181031-47, M- 20181102-38, O- 20190129-1, and O- 2905-15 71124.01 Work Orders 119360280 (0-SI-4.8.E) Leak Test, Inventory and Documentation of Radioactive Sources 71124.02 Miscellaneous 19-0015 Temporary Shielding Request Form - U2R20 Reactor Building refuel Floor Cavity Outer Bellows 71124.02 Miscellaneous Station ALARA Meeting Minutes 3/20/19, Committee 1/16/19, 2/19/18 71124.02 Miscellaneous U2 BRAC Point Data Recirculation Piping 2017 - 2019 71124.02 Miscellaneous U2R20 Daily Outage Report 3/4/19 - Inspection Type Designation Description or Title Revision or Procedure Date 3/22/19 71124.02 Procedures NPG-SPP-05.2.1 Operational ALARA Planning and Controls Rev. 7 71124.02 Radiation Work 19280042 U2R20 Drywell Insulator Support Rev. 0 Permits (RWPs) 71124.02 Self- BFN-RP-SA-19-002 RP Compliance Self-assessment Assessments 71124.03 Corrective Action 1321611, 1380889, and Corrective Action Reports Documents 1330866 71124.03 Miscellaneous Compressor Sn: 115722 Grade D (or better) Air/Gas Quality Report & January 28, Certificate 2019 71124.03 Miscellaneous Compressor Sn: 115723 Grade D (or better) Air/Gas Quality Report & January 23, Certificate 2019 71124.03 Miscellaneous HEPA 626 RCI-35, DOP Testing of Vacuum Cleaners and December Portable HEPA Filters 8, 2018 71124.03 Miscellaneous JZ157568, JZ173983, Maintenance Records (SCBA Regulators) JZ173976, ACZ165443, ACZ165921, and ACZ170685 71124.03 Procedures 0-SR-3.7.3.2(B VFTP) Control Room Emergency Ventilation Unit B Flow Rate Rev. 0018 and Filter Testing 71124.03 Procedures FP-0-000-INS027 Self-Contained Breathing Apparatus (SCBA) Rev. 0018 71124.03 Procedures NISP-RP-03 Radiological Air Sampling Rev. 0000 71124.03 Procedures NISP-RP-08 Use and Control HEPA Filtration and Vacuum Rev. 0000 Equipment 71124.03 Procedures NPG-SPP-05.1.1 Alpha Radiation Monitoring Program Rev. 0007 71124.03 Procedures NPG-SPP-05.10 Radiological Respiratory Protection Program Rev. 0005 71124.03 Procedures RCDP-21 Radiological Air Sampling Rev. 0000 71124.03 Procedures RCDP-24 Maintenance and Field Setup of HEPA Units and Rev. 0001 Vacuums 71124.03 Procedures RCI-1.2 Radiation, Contamination, and Airborne Surveys Rev. 0041 71124.03 Procedures RCI-11.2 Radiation Protection Airborne Instrument Maintenance Rev. 0010 71124.03 Procedures RCI_35 DOP Testing of Vacuum Cleaners and Portable HEPA Rev. 0007 Filters 71124.03 Procedures RCTP-101 Operation of the Mask Fit System Rev. 0009 Inspection Type Designation Description or Title Revision or Procedure Date 71124.03 Procedures SMP-0632G Annual Self Contained Breathing Apparatus (SCBA) Rev. 0000 and Air Purifying Respirator Fit Testing 71124.03 Radiation 19-20114-2, 19-20097, (NISP-RP-03-A1) Airborne Radioactivity Calculation Surveys 19-20100-4, 1920108-1, Worksheets 19-20100-5, 19-20089-1, 19-20108-2, 19-20114-1, 19-20100-1, 19-20116-8, 19-20123-2, 19-20128-1, 19-20109-6, 19-20099-6, 19-20123-7, 19-20119-8, 19-20123-4, 19-20119-3, 19-20119-2, 19-20119-4, 19-20119-6, 19-20119-5, 19-20119-7, 19-20116-9, 19-20123-1, 19-20119-1, 19-20128-5, 19-20085-1, 19-20109-7, 19-20109-4, and 19-20109-5 71124.03 Work Orders 118059857, 118059858, Work Orders 117446719, 118059859, 118059860, 119459150, 119459152, and 119687258 71124.04 Calculations Neutron Characterization Site-specific Neutron Field Characterization 12/12/17 71124.04 Corrective Action 1456560 Documents 71124.04 Miscellaneous Database Alpha Level 2 and 3 Plant Area List 10/10/16 71124.04 Miscellaneous Dosimeter Trend Area Dosimeter Trend Report 2016 - 2017 71124.04 Miscellaneous NVLAP NVLAP Certificate of Accreditation, Landauer Inc. 1/1/18 - 2/31/18 71124.04 Miscellaneous Radionuclide Library Whole Body Counter Nuclide Library - Inhalation 71124.04 Miscellaneous Radionuclide Report Annual Radionuclide Trending and Assessment 6/21/18 Report 71124.04 Procedures NPG-SPP-05.1.1 Alpha Radiation Monitoring Program Rev. 7 Inspection Type Designation Description or Title Revision or Procedure Date 71124.04 Procedures RCI-8.1 Internal Dosimetry Program Implementation Rev. 51 71124.05 Calibration 2018 Certification / Western Area Radiological Laboratory (WARL) High 6/20/18 Records Calibration Level Cs-137 Source Range 71124.05 Calibration ORTEC Whole Body 5/25/17 and Records Counter Calibration 4/18/18 Report 71124.05 Calibration SN 1008-203 Calibration of the Canberra Argos 5AB Personnel 12/14/17 Records Contamination Monitor and 2/12/18 71124.05 Calibration TVA # 860955 Calibration Data Sheets, Mirion Telepole WR 3/21/17 and Records 1/30/19 71124.05 Calibration TVA Number 0MON-90- Calibration of the Canberra GEM-5 Personnel Monitor 5/10/17 Records 0124 71124.05 Calibration TVA Tag No. 860067 INST-51- Small Article Monitor (SAM 11) Calibration 1/31/18 and Records Form 1/30/19 71124.05 Calibration WO 117452777 Drywell Radiation Monitor 3-RE-90-272A Channel 4/18/17 Records Calibration 71124.05 Corrective Action CR 1441400 Change in source check frequency for Large Article Documents Monitor (LAM) 71124.05 Corrective Action CR 1497034 Calibration record could not be located Documents Resulting from Inspection 71124.05 Corrective Action CR 1497127 Portable instrument source check failures Documents Resulting from Inspection 71124.05 Miscellaneous Instrument Failure 2nd Quarter Reports 2018 - 1st Quarter 2019 71124.05 Procedures RCI-11.1 Radiation Protection Instrument Program Rev 77 Implementation Inspection Type Designation Description or Title Revision or Procedure Date 71124.05 Procedures RCI-11.13 Counting Equipment Calibration and Performance Rev 7 Tests 71124.05 Procedures RCI-11.3 Radiation Protection Radiation / Contamination Rev 44 Instrument Maintenance 71151 Miscellaneous 4th QTR Semiannual 4th QTR Semiannual Radioactive Effluent Release Radioactive Effluent Report2018 (YTD Doses) Release Report2018

                            (YTD Doses)

71151 Miscellaneous Electronic Dosimeter List of Dose and Dose Rate Alarms 3/1/18 - Alarms 3/1/19 71151 Miscellaneous List of electronic dosimeter alarms, 3/1/18

                            - 3/1/19

71151 Miscellaneous OpenEMS Toolkit 1.23a Dose Summary Report (Gas Releases) December 31, 2018 71151 Miscellaneous Units 1, 2, and 3 Reactor Coolant System Leakage logs January 1 to December 31, 2018 71151 Miscellaneous Units 1, 2, and 3 Reactor Coolant System activity logs January 1 to December 31, 2018 71151 Procedures NPG-APP-02.2 Performance Indicator Program Rev. 0010 71151 Self- BFN-RP-FSA-17-001 Focused Self-Assessment Report Assessments 71151 Work Orders 119360218 0-SI-4.8.A.5-1 - Appendix I Dose Calculations - Liquid Effluents 71151 Work Orders 119360273 S-SI-4.8.B.3 - Appendix I Dose Calculations - Airborne Effluents 71152 Corrective Action CR 1268719 Documents 71152 Corrective Action CR 1331735 Documents 71152 Corrective Action CR 1483742 Documents Inspection Type Designation Description or Title Revision or Procedure Date 71152 Corrective Action CR 969607 Documents 71152 Drawings 2-47E872-1-APPJ Appendix J Testing Boundary for Primary Containment Revision 2 Penetrations 71152 Miscellaneous Browns Ferry Unit 1 License DPR-33, Amendment 306 71152 Miscellaneous Browns Ferry Unit 2 License DPR-52, Amendment 329 71152 Miscellaneous Browns Ferry Unit 3 License DPR-68, Amendment 289 71152 Miscellaneous ML18295A109 TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Tables S-2 and B-1 71152 Miscellaneous ML18295A110 Attachment S - Modifications and Implementation Items for the Original NPFA 805 License Amendment 71152 Miscellaneous ML19044A708 Supplement to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Tables S-2 and B-1 71152 Miscellaneous ML18295A111 Attachment S - Modifications and Implementation Items Revision requested by TVA 71152 Procedures 1-SI-4.7.A.2.g-2/ELa Primary Containment Local Leak Rate Test: Electrical Revision 12 Penetrations 71152 Procedures 2-SI-4.7.A.2.g-2/ELa Primary Containment Local Leak Rate Test: Electrical Revision 21 Penetrations 71152 Work Orders WO 116427986 71152 Work Orders WO 118578603 Inspection Type Designation Description or Title Revision or Procedure Date 71152 Work Orders WO 118981404 71153 Corrective Action CR 1497448 Documents 71153 Corrective Action CR 1497454 Documents 71153 Corrective Action CR 1500823 Documents 71153 Drawings PIP-02-03 AC Electrical Distribution System Browns Ferry Nuclear Plant, dated July 21, 2015 71153 Miscellaneous Control room logs for Unit 3 from March 9 - 10, 2019 71153 Miscellaneous EN 53922 71153 Miscellaneous LER 05000259/2018- High Pressure Coolant Injection Declared Inoperable 004-01 due to Steam Supply Valve Isolation 71153 Miscellaneous Operator 4.0 Critique for CR 1500823 71153 Miscellaneous Troubleshooting Plan for Unit 3 Auto-voltage Regulator dated March 10, 2019 71153 Miscellaneous Unit 3 Scram Report from the March 9, 2019 event 71153 Procedures 0-OI-57A Switchyard and 4160V AC Electrical System Revision 165 71153 Procedures 0-OI-57B 480V/240V AC Electrical System Revision 198 71153 Procedures 3-OI-47 Turbine-Generator System Revision 117 2| ]]