IR 05000259/2019001
| 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
May 7, 2019
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):
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
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 Aspect Report Section Occupational Radiation Safety Green NCV 05000259/2019001-01 Closed
[H.11] -
Challenge the Unknown 71124.01 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 Aspect Report Section Occupational Radiation Safety Green NCV 05000259/2019001-02 Closed
[H.12] - Avoid Complacency 71124.01
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 Aspect Report Section Not Applicable Severity Level IV NCV 05000259, 296/2019001-03 Closed Not Applicable 71152 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 Section Status URI 05000259/2018050
-02 Potential failure to maintain 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.
71124.01 Closed URI 05000296/2019001
-04 Unit 3 notice of unusual event (NOUE) caused by of a loss of offsite power (LOOP) resulting in a reactor scram.
71153 Open LER 05000259/2018-004-01 LER 2018-004-01 for Browns Ferry Nuclear Plant, Unit 1, high pressure coolant injection declared inoperable due to steam supply valve Isolation.
71153 Closed
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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) (6 Samples)
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.) (1 Sample)
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.
- (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) (1 Sample)
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) (2 Samples)
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) (7 Samples)
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) (6 Samples)
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) (7 Samples)
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) (2 Samples)
- (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) (1 Sample)
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) (1 Sample)
The inspectors evaluated an emergency preparedness drill on February 13,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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) (1 Sample)
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
Sample. (IP Section 02.16) (1 Sample)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)
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)
- (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 Aspect Report Section Occupational Radiation Safety
Green NCV 05000259/2019001-01 Closed
[H.11] -
Challenge the Unknown 71124.01 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 Aspect Report Section Occupational Radiation Safety
Green NCV 05000259/2019001-02 Closed
[H.12] - Avoid Complacency 71124.01
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 Aspect Report Section Not Applicable Severity Level IV NCV 05000259, 296/2019001-03 Closed
Not Applicable 71152 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 (Open)
Unit 3 Notice of Unusual Event (NOUE) Caused by of a Loss of Offsite Power (LOOP) Resulting in a Reactor Scram 05000296/2019001-04 71153
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 1466957
Corrective Action
Documents
CR 1474188
Corrective Action
Documents
CR 1480259
Miscellaneous
BFN Freeze Protection
Open WO's
Procedures
0-GOI-200-1
Freeze Protection Inspection
Revision 88
Procedures
EPI-0-000-FRZ001
Freeze Protection Program for RHRSW Pump Rooms
and Diesel Generator Bldg Air Plenums
Revision 26
Procedures
NPG-SPP-07.1.8
Severe Weather and Natural Disasters
Revision 1
Corrective Action
Documents
CR 1496966
Corrective Action
Documents
CR 1491715
Corrective Action
Documents
CR 1498426
Corrective Action
Documents
CR 1498851
Drawings
0-47E873-1
Flow Diagram Aux Decay Heat Removal System,
Revision 8
Procedures
0-OI-72,
Auxiliary Decay Heat Removal, Revision 65
Revision 65
Corrective Action
Documents
CR 1495317
Corrective Action
Documents
CR 1495554
Drawings
0-47E216-118
Ignition Source Drawings Plan EL. 604.0
Revision 4
Procedures
FPDP-1
Conduct of Fire Operations
Revision 9
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,
Fire Risk Evaluations
Revision 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Calculations
NDN0009992012000012
TVA Fire PRA - Task 7.14: Fire Risk Quantification
Revision 5
71111.05Q Corrective Action
Documents
CR 1479783
71111.05Q Corrective Action
Documents
CR 1479784
71111.05Q Corrective Action
Documents
CR 1488504
71111.05Q Corrective Action
Documents
CR 1490302
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 &
21.25
Revision 2
71111.05Q Fire Plans
FPR-Volume 2
Fire Protection Report Volume 2, Attachments 4, 5
and 6
Revision 63
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
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
Protection Report
Section 4
Revision 1
71111.05Q Miscellaneous
NFPA 805 Fire
Protection Requirements
Manual
Revision 7
71111.05Q Miscellaneous
NFPA 805, Fire
Protection Report
Appendix F, Fire Area 16
Revision 3
71111.05Q Miscellaneous
NFPA 805, Fire
Protection Report
Appendix F, Fire Area 26
Revision 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Procedures
1-FSS-16-2,
Unit 1 Abandonment Control Building EL 593, 606,
617 and 635
Revision 5
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
Procedures
BFN-0-PMP-040-072
Operability Check, Plant Sump Pumps for Handholes
and 26
Revision 4
71111.08G Corrective Action
Documents
CR-1326804
Transmit BWRVIP -183-A to the BRWVIP Executive
Committee
8/10/17
71111.08G Corrective Action
Documents
Resulting from
Inspection
CR 1496837
U2R20 ISI NRC Inspection-NRC Identified Snubber
Walked On
3/7/19
71111.08G Drawings
2-ISI-0415-C
Browns Ferry Nuclear Plant, Unit 2, Reactor Vessel
Supports
Rev. 1
71111.08G Drawings
ISI-0351-A
Browns Ferry Nuclear Plant Unit-2, Instrumentation
Nozzles Wels Locations
Rev. 00
71111.08G Miscellaneous
1.M.1.2-5
G.W.
- P.S. 1.M.1.2, Attachment B, Weld Joint Detail,
Open Butt, Single Vee Butt Weld
Rev. 4
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,
Drawing. or Weld Map
CRD-2-010-1
Radiographic Examination Report
2/16/19
71111.08G Miscellaneous
CRD-2-010-015, C0R0,
Weld Map CRD-2-010-2
MMDP-10, Category I/II Weld Data Sheet
2/6/19
71111.08G Miscellaneous
CRD-2-010-015,
Drawing No. or Weld
Map CRD-2-010-2
Radiographic Examination Report
2/16/19
71111.08G Miscellaneous
DWPS GT11-O-1-N
G29 Detailed Welding Procedure Specification
(DWPS)
ASME/ANSI - GWPS 1.M.1.2
Rev.2
71111.08G Miscellaneous
JHH1373
IHI Southwest Technologies, Certificate of
Qualification, Magnetic Particle (MT)
6/19/18
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.08G Miscellaneous
RNP90YKE1
Welder Qualification Continuity Record
3/5/19
71111.08G Miscellaneous
Ultrasonic Qualification,
D. Maclean
Ultrasonic Hands On Practical Documentation
1/16/19
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
2/30/87
71111.08G Miscellaneous
ZQ7YP17AG
Welder Qualification Continuity Record
3/5/19
0-TI-417, Attachment 1
Inspection of Service Level I, II, III Protective Coatings,
Moisture Seal Barrier, Condensate Storage Tanks and
ECCS Suction Strainers. (Completed for Unit-2
Moisture Barrier on 3/16/19)
Rev. 27,
3/18/19
BFNU2R19, Form OAR-
Owners Activity Report, ASME Section XI, Subsection
IWE, Examination Category E-A, Item E1.30,
Component ID: MSB-2-1 Moisture Seal Barrier
6/23/17
NDE Report No. R056
Record of Magnetic Particle Examination of
Component ID, RPV-Supp-2-1-IA, Browns Ferry
Nuclear Unit-2, Reactor Vessel Support
5/27/09
R-075
Magnetic Particle Examination RPV-SUPP-2.1-1A,
Vessel to Skirt Weld
3/15/19
R055
VT-3 of Component ID No. RPV-Supp-2-1, Reactor
Vessel Support
5/27/09
Report No. R-040
Ultrasonic Calibration-Examination Record, N-16A-1
3/7/19
Report No. R-170,
Summary No. 00739-
IWE-BFN-2
Visual Examination (VT-1) of the repaired Area of the
Moisture Seal Barrier
3/18/17
Summary No. BFN-2-TG
000 Aligner Pin, Socket
Location 2-3_D40
EVT-1 Examination Results, BFN-2-TG 000 Aligner
Pin, Socket Location 2-3_D40
3/20/19
Summary No. BFN-2-TG
000 Aligner Pin, Socket
Location 2-3_D40_90
Deg.
EVT-1 Examination Results, TG 000 Aligner Pin,
Socket Location 2-3_D40_90 Deg.
3/20/19
Summary No. BNF2-TG
EVT-1 Examination Results, TG 090 Aligner Pin,
3/20/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
090 Aligner Pin, Socket
Location 2-3_D40
Socket Location 2-3_D40
Summary No. BNF2-TG
090 Aligner Pin, Socket
Location 2-3_D40_90
Deg.
EVT-1 Examination Results, TG 090 Aligner Pin,
Socket Location 2-3_D40_ 90 Deg.
3/20/19
Summary No. BNF2-TG
180 Aligner Pin, Socket
Location 2-3_D40
EVT-1 Examination Results, TG 180 Aligner Pin,
Socket Location 2-3_D40
3/20/19
Summary No. BNF2-TG
180 Aligner Pin, Socket
Location 2-3_D40_90
Deg.
EVT-1 Examination Results, TG 180 Aligner Pin,
Socket Location 2-3_D40_90 Deg.
3/20/19
Summary No. BNF2-TG
270 Aligner Pin, Socket
Location 2-3_D40
EVT-1 Examinations Results, TG 270 Aligner Pin,
Socket Location 2-3_D40
3/20/18
Summary No. BNF2-TG
270 Aligner Pin, Socket
Location 2-3_D40_90
Deg.
EVT-1 Examination Results, TG 270 Aligner Pin,
Socket Location 2-3_D40_90 Deg.
3/20/19
71111.08G Procedures
GEH-VT-204
Procedure for In-Vessel Visual Inspection (IVVI) of
Version No.
71111.08G Procedures
N-MT-6
Magnetic Particle Examination for ASME and ANSI
Code Components and Welds
Rev. 0036
71111.08G Procedures
N-UT-64
Generic Procedure for the Ultrasonic Examination of
Austenitic Pipe Welds
Rev. 0016
71111.08G Self-
Assessments
CRP-ENG-FSA-17-004
Browns Ferry Nuclear, ASME Section XI, ISI, IWE,
System Pressure Test and Repair Replacement
Programs Assessment
7/24/17 thru
8/4/17
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Shutdown and Reductions in Power During Power
Operations
111
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
Corrective Action
Documents
CR 1131914
Corrective Action
Documents
CR 1372873
Corrective Action
Documents
CR 1436003
Corrective Action
Documents
CR 1471106
Corrective Action
Documents
CR 1473957
Corrective Action
Documents
CR 923412
Miscellaneous
(a)(1) Evaluation for
Function 074-B, RHR
Low Pressure Coolant
Injection (LPCI)
Miscellaneous
System Health Report
for RHR System
Procedures
0-TI-346
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10CFR50.65
Revision 51
Procedures
0-TI-395
Breaker Testing and Maintenance Program
Revision 12
Procedures
ECI-0-000-BKR008
Testing and Troubleshooting of Molded Case Circuit
Breakers and Motor Starter Overload Relays
Revision
107
Procedures
EPI-0-000-MCC001
Maintenance and Inspection of 480VAC and 250VDC
Motor Control Centers
Revision 82
Procedures
NPG-SPP 03.4
Maintenance Rule Performance Indicator Monitoring,
Trending and Reporting - 10CFR50.65
Revision 3
Procedures
NPG-SPP 22.500
Operating Experience Program
Revision 7
Work Orders
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Corrective Action
Documents
CR 1494904
Corrective Action
Documents
CR 1495306
Corrective Action
Documents
CR 1499057
Corrective Action
Documents
CR 1499381
Drawings
2-47E803-5
Flow Diagram Reactor Feedwater System
Revision 32
Miscellaneous
Unit 2 Cycle R20
Outage Safety Plan
Revision 1
Procedures
0-AOI-72-1
Auxiliary Decay Heat Removal System Failures
Revision 23
Procedures
0-TPP-FPP-011
BFN NFPA 805 Non-Power Operations Fire Risk
Management
Revision 4
Procedures
2-GOI-100-3A
Refueling Operations (Rx Vessel Disassembly and
Floodup)
Revision 57
Procedures
2-OI-75
Core Spray System
Revision
114
Procedures
2-POI-200.5
Operations with Potential for Draining the Reactor
Vessel/Cavity
Revision 20
Procedures
BFN-ODM-4.18
Protected Equipment
Revision 21
Procedures
NPG-SPP-07.2.11
Shutdown Risk Management
Revision 12
Procedures
NPG-SPP-09.11.1
Equipment Out of Service Management
Revision 12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NPG-SPP-10.6
Infrequently Performed Test or Evolutions
Revision 1
Calculations
MDQ007420020025
Residual Heat Removal System (RHR) Modes of
Operation
Revision 6
Calculations
MDQ107420020078
MOV 1-FCV-074-0059 & MOV 1-FCV-074-0073,
Operator Requirements and Capabilities
Revision 3
Corrective Action
Documents
CR 1117364
Corrective Action
Documents
CR 1334534
Corrective Action
Documents
CR 1335322
Corrective Action
Documents
CR 1474167
Corrective Action
Documents
CR 1474340
Corrective Action
Documents
CR 1480006
Corrective Action
Documents
CR 1480744
Corrective Action
Documents
CR 1481629
Drawings
3-45E724-9
Wiring Diagram 4160V Shutdown Bd 3ED Single Line
Revision 34
Drawings
3-45E732-5
Wiring Diagram 480V Diesel Aux Bd 3EA Single Line
Revision 30
Drawings
3-45E766-15
Wiring Diagram 4160V Shutdown Aux Power
Schematic Diagrams
Revision 13
Drawings
3-45E771-8
Wiring Diagram 480V Diesel Aux Power Schematic
Diagram
Revision 31
Miscellaneous
Operations Work Around
3-071-OWA-2019-0002
Miscellaneous
Operator Logs dated
2/10/2019 - 12/11/2019
Operability
Evaluations
Prompt Determination of
Operability for CR
1474340
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability
Evaluations
Prompt Determination of
Operability for CR
1497454
Procedures
0-GOI-300-2
Electrical
Revision
150
Procedures
3-OI-71
Reactor Core Isolation Cooling System
Revision 61
Procedures
3-SR-3.8.1.9(3D OL)
Diesel Generator 3D Emergency Load Acceptance
Test with Unit 3 Operating
Revision 18
Procedures
OPDP-8
Operability Determination Process and Limiting
Conditions for Operation Tracking
Revision 24
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Calculations
EDN2003920049
Setpoint and Scaling Calculation for 2-P-3-204A, -
204B, -204C, and -204D
Revisions 5,
& 7
Corrective Action
Documents
CR 1273615
Miscellaneous
Detailed Design Criteria
Document, BFN-50-7085
Control Rod Drive System
Revision 14
Procedures
2-SR-3.3.4.2.3(A)
Anticipated Transient Without Scram(ATWS) -
Recirculation Pump Trip(RPT) System Reactor High
Pressure Channel A Calibration 2-P-3-204A
Revision 14
Procedures
2-SR-3.3.4.2.3(B)
Anticipated Transient Without Scram(ATWS) -
Recirculation Pump Trip(RPT) System Reactor High
Pressure Channel B Calibration 2-P-3-204B
Revision 15
Procedures
2-SR-3.3.4.2.3(C)
Anticipated Transient Without Scram(ATWS) -
Recirculation Pump Trip(RPT) System Reactor High
Pressure Channel C Calibration 2-P-3-204C
Revision 12
Procedures
2-SR-3.3.4.2.3(D)
Anticipated Transient Without Scram(ATWS) -
Recirculation Pump Trip(RPT) System Reactor High
Pressure Channel A Calibration 2-P-3-204C
Revision 11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
2-TI-700/ATT-16
Required EPU Unit-2 R-20 Modifications
Revision 0
Work Orders
Work Orders
Work Orders
Work Orders
Procedures
1-TI-130
Main Steam Pressure Control
Revision 3
Procedures
1-TI-131
Feedwater Level Control System
Revision 2
Procedures
1-TI-700
EPU Master Startup Test Instruction
Revision 0
Procedures
2-SI-3.3.1.A
ASME Section XI System Leakage Test of the Reactor
Pressure Vessel and Associated Piping (ASME
Section III, Class 1 and 2)
Revision 41
Procedures
2-TI-358
ASME Section XI Hydrostatic Primary System
Pressure Test Boundary
Revision 17
Procedures
3-SI-4.4.A.1
Standby Liquid Control Pump Functional Test
Revision 60
Procedures
3-SR-3.3.1.1.8(9)
Turbine Control Valve Fast Closure, or Turbine Trip
and RPT Initiate Logic
Revision 33
Procedures
3-SR-3.8.1.1(3B)
Diesel Generator 3B Monthly Operability Test
Revision 57
Procedures
3-TI-130
Main Steam Pressure Control
Revision 6
Procedures
3-TI-380
Power Ascension Turbine Valve Test
Revision 4
Procedures
ECI-0-000-RLY003
Replacement of Relays
Revision 28
Procedures
PMTI-71400-002
EHPM Pump RPV Injection Test at Low Pressure
Conditions
Revision 0
Corrective Action
Documents
CR 1316896
Corrective Action
Documents
CR 1469446
Corrective Action
Documents
CR 1491233
Drawings
1-47E812-1
Flow Diagram High Pressure Coolant Injection System
Revision 47
Drawings
1-47E812-2
Flow Diagram HPCI Oil System
Revision 5
Miscellaneous
Unit 3 Leakrate Data
Procedures
0-SI-4.11.G.2
Semiannual Fire Door Inspection
Revision 31
Procedures
0-SR-3.8.1.9(B)
Diesel Generator B Emergency Unit 2 Load
Revision 21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Acceptance Test
Procedures
0-TI-298
Diesel Generator Operating Data Acquisition
Revision 21
Procedures
1-SR-3.5.1.7
HPCI Main and Booster Pump Set Developed Head
and Flow Rate Test at Rated Reactor Pressure
Revision 40
Procedures
2-SR-3.6.1.3.10 (A-
Primary Containment Local Leak Rate Test Main
Steam Line A Outboard: Penetration X-7A
Revision 9
Procedures
2-SR-3.6.1.3.10 (B-
Primary Containment Local Leak Rate Test Main
Steam Line B Outboard: Penetration X-7B
Revision 9
Procedures
2-SR-3.6.1.3.10 (C-
Primary Containment Local Leak Rate Test Main
Steam Line C Outboard: Penetration X-7C
Revision 10
Procedures
2-SR-3.6.1.3.10 (D-
Primary Containment Local Leak Rate Test Main
Steam Line D Outboard: Penetration X-7D
Revision 9
Procedures
3-SR-2
Instrument Checks and Observations
Revision 80
Procedures
3-TI-275A
Drywell Leak Investigation Temperature
Revision 6
Procedures
3-TI-275B
Drywell Leak Investigation - Radwaste Sumps
Revision 1
Procedures
3-TI-275C
Drywell Leak Investigation - Primary Containment
Leak Detection CAM, 3-RM-90-256
Revision 0
Procedures
3-TI-275D
Drywell Leak Investigation - Chemistry
Revision 8
Procedures
3-TI-275E
Drywell Leak Investigation Analysis
Revision 9
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
Work Orders
ALARA Plans
APR 18-0135, APR 18-
0136, and APR 18-0137
ALARA Plans
ALARA Plans
U2R20 Outage Steam
U2R20 Outage Steam Dryer Replacement ALARA
February 25,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dryer Replacement
ALARA Plan
Plan
2019
Corrective Action
Documents
1399079, 1485534,
1442072, 1449875,
1411376, 1415753,
1442073, 1485534,
1392795, 1398535,
1463225, and 1500332
Corrective Action Reports
Corrective Action
Documents
1464279
Root Cause Analysis - Refuel Floor Diving
Miscellaneous
0-TI-540
Storage Material in the Spent Fuel Storage Pool
(SFSP) and Transfer Canal (U1)
July 18,
2018
Miscellaneous
0-TI-540
Storage Material in the Spent Fuel Storage Pool
(SFSP) and Transfer Canal (U2)
August 23,
2018
Miscellaneous
0-TI-540
Storage Material in the Spent Fuel Storage Pool
(SFSP) and Transfer Canal (U3)
August 23,
2018
Miscellaneous
Clearance Folder:
Tagout 1-TO-1R12-
00HO, Clearance
Section: 1-069-0003
NPG-SPP-10.2, Clearance Folder: Tagout 1-TO-
1R12-00HO, Clearance Section: 1-069-0003 (TVA
Form 17982)
March 13,
2019
Miscellaneous
CR 1460752
Level 2 Evaluation Report, Unit 1 entered 1-EOI-3
Secondary Containment Control due to a high
radiation condition in the reactor building
December
11, 2018
Miscellaneous
U2R20 Outage Steam
Dryer Replacement Pre-
Job Brief
U2R20 Outage Steam Dryer Replacement Pre-Job
Brief
Procedures
0-SI-4.8.E
Leak Test, Inventory and Documentation of
Radioactive Sources
Rev. 0020
Procedures
1-OI-69
Reactor Water Cleanup System
Rev. 0072
and Rev.
0073
Procedures
NISP-RP-02
Radiation and Contamination Surveys
Rev. 0000
Procedures
NISP-RP-04
Radiological Posting and Labeling
Rev. 0000
Procedures
NISP-RP-05
Access Controls for High Radiation Areas
Rev. 0000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NISP-RP-06
Personnel Contamination Monitoring
Rev. 0000
Procedures
NISP-RP-10
Radiological Job Coverage
Rev. 0000
Procedures
NISP-RP-11
Radiation Protection Fundamentals
Rev. 0000
Procedures
NPG-SPP-05.01
Radiological Controls
Rev. 0010
Procedures
NPG-SPP-05.16
Administrative Controls for Performance of
Radiography Operations
Rev. 0008
Procedures
NPG-SPP-05.18
Radiation Work Permits
Rev. 0007
Procedures
NPG-SPP-05.2.6
Radiological Risk Management
Rev. 0003
Procedures
NPG-SPP-10.2
Clearance Procedure to Safely Control Energy
Rev. 0021
Procedures
RCDP-10
Personnel Contamination Event Documentation
Rev. 0008
Procedures
RCDP-17
Radiological Postings
Rev. 0001
Procedures
RCDP-22
Control of High Radiation Areas and Very High
Radiation Areas
Rev. 0000
Procedures
RCDP-23
Control of Radioactive Material
Rev. 0000
Procedures
RCI-1.1
Radiation Operations Program Implementation
Rev. 0172
Procedures
RCI-1.2
Radiation, Contamination, and Airborne Surveys
Rev. 0041
Procedures
RCI-17
Control of High Radiation Areas and Very High
Radiation Areas
Rev. 0091
Procedures
RCI-33
Diving Operations on the Refuel Floor
Rev. 0016
and Rev.
0017
Procedures
RCI-47
Diving Operations in the Radiologically Controlled
Area
Rev. 0006
and Rev.
0007
Radiation
Surveys
M-20190304-23, M-
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-
Surveys
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Work Orders
119360280 (0-SI-4.8.E)
Leak Test, Inventory and Documentation of
Radioactive Sources
Miscellaneous
19-0015
Temporary Shielding Request Form - U2R20 Reactor
Building refuel Floor Cavity Outer Bellows
Miscellaneous
Station ALARA
Committee
Meeting Minutes
3/20/19,
1/16/19,
2/19/18
Miscellaneous
U2 BRAC Point Data
Recirculation Piping
2017 - 2019
Miscellaneous
U2R20
Daily Outage Report
3/4/19 -
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3/22/19
Procedures
NPG-SPP-05.2.1
Operational ALARA Planning and Controls
Rev. 7
Radiation Work
Permits (RWPs)
280042
U2R20 Drywell Insulator Support
Rev. 0
Self-
Assessments
BFN-RP-SA-19-002
RP Compliance Self-assessment
Corrective Action
Documents
21611, 1380889, and
1330866
Corrective Action Reports
Miscellaneous
Compressor Sn: 115722
Grade D (or better) Air/Gas Quality Report &
Certificate
January 28,
2019
Miscellaneous
Compressor Sn: 115723
Grade D (or better) Air/Gas Quality Report &
Certificate
January 23,
2019
Miscellaneous
HEPA 626
RCI-35, DOP Testing of Vacuum Cleaners and
Portable HEPA Filters
December
8, 2018
Miscellaneous
JZ157568, JZ173983,
JZ173976, ACZ165443,
ACZ165921, and
ACZ170685
Maintenance Records (SCBA Regulators)
Procedures
0-SR-3.7.3.2(B VFTP)
Control Room Emergency Ventilation Unit B Flow Rate
and Filter Testing
Rev. 0018
Procedures
FP-0-000-INS027
Self-Contained Breathing Apparatus (SCBA)
Rev. 0018
Procedures
NISP-RP-03
Radiological Air Sampling
Rev. 0000
Procedures
NISP-RP-08
Use and Control HEPA Filtration and Vacuum
Equipment
Rev. 0000
Procedures
NPG-SPP-05.1.1
Alpha Radiation Monitoring Program
Rev. 0007
Procedures
NPG-SPP-05.10
Radiological Respiratory Protection Program
Rev. 0005
Procedures
RCDP-21
Radiological Air Sampling
Rev. 0000
Procedures
RCDP-24
Maintenance and Field Setup of HEPA Units and
Vacuums
Rev. 0001
Procedures
RCI-1.2
Radiation, Contamination, and Airborne Surveys
Rev. 0041
Procedures
RCI-11.2
Radiation Protection Airborne Instrument Maintenance
Rev. 0010
Procedures
RCI_35
DOP Testing of Vacuum Cleaners and Portable HEPA
Filters
Rev. 0007
Procedures
RCTP-101
Operation of the Mask Fit System
Rev. 0009
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SMP-0632G
Annual Self Contained Breathing Apparatus (SCBA)
and Air Purifying Respirator Fit Testing
Rev. 0000
Radiation
Surveys
19-20114-2, 19-20097,
19-20100-4, 1920108-1,
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
(NISP-RP-03-A1) Airborne Radioactivity Calculation
Worksheets
Work Orders
118059857, 118059858,
117446719, 118059859,
118059860, 119459150,
119459152, and
119687258
Work Orders
Calculations
Neutron Characterization Site-specific Neutron Field Characterization
2/12/17
Corrective Action
Documents
1456560
Miscellaneous
Database
Alpha Level 2 and 3 Plant Area List
10/10/16
Miscellaneous
Dosimeter Trend
Area Dosimeter Trend Report
2016 - 2017
Miscellaneous
NVLAP Certificate of Accreditation, Landauer Inc.
1/1/18 -
2/31/18
Miscellaneous
Radionuclide Library
Whole Body Counter Nuclide Library - Inhalation
Miscellaneous
Radionuclide Report
Annual Radionuclide Trending and Assessment
Report
6/21/18
Procedures
NPG-SPP-05.1.1
Alpha Radiation Monitoring Program
Rev. 7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
RCI-8.1
Internal Dosimetry Program Implementation
Rev. 51
Calibration
Records
2018 Certification /
Calibration
Western Area Radiological Laboratory (WARL) High
Level Cs-137 Source Range
6/20/18
Calibration
Records
ORTEC Whole Body
Counter Calibration
Report
5/25/17 and
4/18/18
Calibration
Records
SN 1008-203
Calibration of the Canberra Argos 5AB Personnel
Contamination Monitor
2/14/17
and
2/12/18
Calibration
Records
TVA # 860955
Calibration Data Sheets, Mirion Telepole WR
3/21/17 and
1/30/19
Calibration
Records
24
Calibration of the Canberra GEM-5 Personnel Monitor
5/10/17
Calibration
Records
TVA Tag No. 860067
INST-51-Small Article Monitor (SAM 11) Calibration
Form
1/31/18 and
1/30/19
Calibration
Records
Drywell Radiation Monitor 3-RE-90-272A Channel
Calibration
4/18/17
Corrective Action
Documents
CR 1441400
Change in source check frequency for Large Article
Monitor (LAM)
Corrective Action
Documents
Resulting from
Inspection
CR 1497034
Calibration record could not be located
Corrective Action
Documents
Resulting from
Inspection
CR 1497127
Portable instrument source check failures
Miscellaneous
Instrument Failure
Reports
2nd Quarter
2018 - 1st
Quarter
2019
Procedures
RCI-11.1
Radiation Protection Instrument Program
Implementation
Rev 77
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
RCI-11.13
Counting Equipment Calibration and Performance
Tests
Rev 7
Procedures
RCI-11.3
Radiation Protection Radiation / Contamination
Instrument Maintenance
Rev 44
71151
Miscellaneous
4th QTR Semiannual
Radioactive Effluent
Release Report2018
(YTD Doses)
4th QTR Semiannual Radioactive Effluent Release
Report2018 (YTD Doses)
71151
Miscellaneous
Electronic Dosimeter
Alarms
List of Dose and Dose Rate Alarms
3/1/18 -
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-
Assessments
BFN-RP-FSA-17-001
Focused Self-Assessment Report
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
Corrective Action
Documents
CR 1268719
Corrective Action
Documents
CR 1331735
Corrective Action
Documents
CR 1483742
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 969607
Drawings
2-47E872-1-APPJ
Appendix J Testing Boundary for Primary Containment
Revision 2
Miscellaneous
Browns Ferry Unit 1
License DPR-33,
Amendment 306
Miscellaneous
Browns Ferry Unit 2
License DPR-52,
Amendment 329
Miscellaneous
Browns Ferry Unit 3
License DPR-68,
Amendment 289
Miscellaneous
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
Miscellaneous
S - Modifications and Implementation
Items for the Original NPFA 805 License Amendment
Miscellaneous
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
Miscellaneous
S - Modifications and Implementation
Items Revision requested by TVA
Procedures
1-SI-4.7.A.2.g-2/ELa
Primary Containment Local Leak Rate Test: Electrical
Revision 12
Procedures
2-SI-4.7.A.2.g-2/ELa
Primary Containment Local Leak Rate Test: Electrical
Revision 21
Work Orders
Work Orders
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
Corrective Action
Documents
CR 1497448
Corrective Action
Documents
CR 1497454
Corrective Action
Documents
CR 1500823
Drawings
PIP-02-03
AC Electrical Distribution System Browns Ferry
Nuclear Plant, dated July 21, 2015
Miscellaneous
Control room logs for
Unit 3 from March 9 - 10,
2019
Miscellaneous
Miscellaneous
LER 05000259/2018-
004-01
High Pressure Coolant Injection Declared Inoperable
due to Steam Supply Valve Isolation
Miscellaneous
Operator 4.0 Critique for
CR 1500823
Miscellaneous
Troubleshooting Plan for
Unit 3 Auto-voltage
Regulator dated March
10, 2019
Miscellaneous
Unit 3 Scram Report
from the March 9, 2019
event
Procedures
0-OI-57A
Switchyard and 4160V AC Electrical System
Revision
165
Procedures
0-OI-57B
480V/240V AC Electrical System
Revision
198
Procedures
3-OI-47
Turbine-Generator System
Revision
117