IR 05000259/2022004
| ML23037A849 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/07/2023 |
| From: | Louis Mckown Division Reactor Projects II |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2022004 | |
| Download: ML23037A849 (19) | |
Text
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2022004, 05000260/2022004 AND 05000296/2022004
Dear Mr. Barstow:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On January 26, 2023, the NRC inspectors discussed the results of this inspection with Mr. Joe Quinn and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Louis J. McKown, II, Chief Reactor Projects Branch Division of Reactor Projects Docket Nos. 05000259, 05000260 and 05000296 License Nos. DPR-33, DPR-52 and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000259, 05000260 and 05000296
License Numbers:
Report Numbers:
05000259/2022004, 05000260/2022004 and 05000296/2022004
Enterprise Identifier:
I-2022-004-0013
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
October 01, 2022 to December 31, 2022
Inspectors:
B. Bowker, Reactor Inspector
P. Cooper, Senior Reactor Inspector
S. Downey, Senior Reactor Inspector
N. Karlovich, Resident Inspector
D. Lanyi, Senior Operations Engineer
K. Pfeil, Resident Inspector
M. Schwieg, Senior Reactor Inspector
J. Steward, Senior Resident Inspector
S. Temple, Resident Inspector
J. Vasquez, Construction Inspector
Approved By:
Louis J. McKown, II, Chief
Reactor Projects Branch 5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Browns Ferry Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000259,05000260/20 21-001-01 LER 2021-001-01 for Browns Ferry Nuclear Plant,
Units 1 and 2, 480 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications due to Failed Relay 71153 Closed
PLANT STATUS
Unit 1 began the inspection period in Mode 3 (Hot Shutdown) in support of a planned refueling outage (1R14). The licensee commenced unit startup on October 26, 2022 and returned to 100 percent (full) rated thermal power (RTP) on November 1, 2022. On November 3, 2022, operators down powered the unit to 38 percent RTP for emergent repairs to reactor recirculation loop B variable frequency drive (VFD). On November 4, 2022, operators returned the unit to RTP, where it remained throughout the inspection period.
Unit 2 began the inspection period at RTP. On November 11, 2022, reactor feed pump turbine (RFPT) B tripped which lowering reactor vessel water level resulted in an automatic reactor recirculation system runback to 75 percent. Operators maintained power at approximately 73 percent RTP during the corrective maintenance window. On November 15, 2022, Unit 2 was returned to full RTP and operated there until November 18, 2022, when power was lowered to 85 percent RTP for a control rod adjustment. On November 19, 2022, the unit was returned to full RTP. On November 26, 2022, power was lowered to 70 percent RTP for planned control rod exchange and surveillance testing and was returned to RTP later that day. On December 30, 2022, power was lowered to 74 percent RTP for a planned rod sequence exchange to all rods out configuration in preparation for coastdown to a planned refueling outage (2R22). On December 31, 2022, the unit was returned to full RTP where it operated at or near this level for the remainder of the inspection period.
Unit 3 began the inspection period at full RTP. On December 2, 2022, the unit was taken off-line to commence a planned forced outage (F311) to replace a defective fuel bundle as well as identify the source of increased floor drain leakage inside the drywell observed during the operating cycle. Unit startup commenced on December 10, 2022 and RTP was achieved on December 12, 2022. The unit remained at or near this level throughout 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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs.
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 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe thunderstorms on November 29, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on December 1, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3 Core Spray (CS) Loop 2 while CS Loop 1 was under a planned flow test on November 3, 2022
- (2) Unit 1 Reactor Core Isolation Cooling System while Unit 1 High Pressure Coolant Injection (HPCI) was removed from service for planned maintenance on the gland seal leak off piping on November 17, 2022
- (3) Unit 3 Emergency Diesel Generator (EDG) 3C on December 4, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Area 8, 2B Electric Board Room including 4.16 KV Shutdown Board D, Unit 2 Control Bay 593' Elevation on October 2, 2022
- (2) Fire Areas 01-04 and 01-03, Reactor Water Cleanup Heat Exchanger Room on elevation 593' on October 17, 2022
- (3) Fire Area 02-03 and 02-04, Reactor Building Unit 2 Elevation 593' on October 21, 2022
- (4) Fire Area 03-01, Reactor Building Unit 3 Elevation 519' and 541' NW, SW, NE, and SE quadrants on November 3, 2022
- (5) Fire Area 26, Unit 1 Turbine Building elevation 617' on December 15, 2022
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors evaluated the boiling water reactor non-destructive examinations from October 3, 2022 to October 10, 2022:
Ultrasonic examination on the N-9 reactor vessel penetration weld
Visual examination on the RHR piping supports
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 5, 2022, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on September 27, 2022.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Unit 1 Control Room during reactor startup including control rod withdrawal to achieve criticality following planned refueling outage (1R14) on October 26, 2022
The inspectors observed and evaluated licensed operator performance in the Unit 1 Control Room during reactor startup including control rod withdrawal and reactor mode switch manipulation to shift operating mode from MODE 2 to MODE 1 following planned refueling outage (1R14) on October 26, 2022
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification crew classroom training which reviewed the following topics as part of Cycle 2206, "Welcome to Requal", "Safeguards Event Reporting" and "FLEX Response Instructions" on November 29, 2022
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 1 reactor recirculation pump 1B VFD cooling water line replacement per work order (WO) 123229093 on November 10, 2022
- (2) Unit 3 fuel pool cooling and clean-up pump B motor replacement per WO 122484839 on December 14, 2022
- (3) Common Unit Reactor Floor Crane Sheave Bearings failure and corrective maintenance per condition report (CR) 1821866 on December 15, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Observed emergent work on Unit 1 Turbine Control Valve No 2 per WO 123274163 on October 28, 2022
- (2) Evaluated various activities during yellow (medium) site aggregate risk due to Unit 1 Reactor less than 90 percent RTP while maneuvering reactor power in accordance with 1-GOI-100-12, Power Maneuvering on November 1, 2022
- (3) Unit 3 High Risk Evolution (Yellow Risk) during high decay heat, RPV Head removed and the reactor cavity drained in preparation for vessel flood up per GOI-100-3A, "Refueling Operations (Rx Vessel Disassembly and Floodup)", and 3-OI-2, "Condensate", on December 4, 2022
- (4) Unit 3 Probabilistic (PRA) evaluation for using Technical Specification (TS) Limiting Condition for Operation (LCO) 3.0.4b to justify changing operating modes with TS 3.7.4 unmet going from MODE 4 to MODE 2 to MODE 1 on December 10, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Excessive four fill average boil-off rate for Containment Air Dilution (CAD) Tank B per CR 1792706 on October 5, 2022 (2)3-SR-3.1.7.3, Standby Liquid Control System Enriched Sodium Pentaborate (SPB)
Solution Concentration, Quantity Calculation and Anticipated Transient Without Scram (ATWS) Equivalency Calculation per CRs 1810303 and 1810362 on October 19, 2022
- (3) As left maximum closing thrust exceeded the calculated allowable actuator thrust for the Unit 1 HPCI steam line inboard isolation valve, 1-FCV-073-0002 per CR 1808791 on November 2, 2022
- (4) Emergency Equipment Chill Water (EECW) North Header Supply to northwest CS pump room cooler has packing leak per CR 1804496 on November 8, 2022
- (5) Control Rod Drive Temperature Element at drive location 06-47 went from stable 115 degrees Fahrenheit (F) reading to over 700 degrees F per CR 1822164 on December 15, 2022
- (6) Unit 3 EDG 3D received a Fast Start failure annunciator during surveillance testing per CR 1823305 on December 20, 2022
- (7) C3 EECW pump and strainer unable to be rotated per CR 1804874 on December 30, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 1 temporary modification of recirculation loop 'A' flow measurement instrumentation during outage U1R14 in October 2022
- (2) Unit 1 permanent modification to document the HPCI Gland Seal Piping reroute and evaluate the added pipe supports for seismic qualification per design change package BFN-22-059 on November 25, 2022
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site Severe Accident Management Guidelines were updated in accordance with the BWR generic severe accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 1 HPCI Pump 150 psig test developed head and flowrate testing following overhaul preventive maintenance per WO 122585535 on October 26, 2022
- (2) Unit 1 B reactor recirculation pump VFD A5 power cell replacement due to internal coolant leakage per WO 123279027 on November 8, 2022
- (3) Unit 1 HPCI main and booster pump set developed head and flow rate testing following maintenance performed on gland seal leakoff lines for the auxiliary oil pump per WO 123261303 on November 18, 2022
- (4) Unit 3 CS Pump A control transfer switch, 3-XSW-075-0005, testing after installation of a PK test block was added to the circuit per WO 123315808 on November 22, 2022
- (5) Unit 1 Outer Equipment Access Airlock Doors following replacement of the limit switches for door 229B per WO 123355992 on December 19, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated various activities associated with a planned Unit 1 refueling outage from October 1 through October 27, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1 drywell control air header isolation valves 1-CKV-32-336 and 1-CKV-32-915 and Containment Atmospheric Dilution primary containment isolation valves 1-SHV-84-686 and 1-FSV-84-49 local leak rate tests on October 18, 2022
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) A training drill scenario which included seismic activity, emergency medical response, loss of the B shutdown board, loss of feedwater, and main steam line valve isolation as well as degrading containment conditions requiring implementation of severe accident mitigation guidelines on November 30,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
- (3) Unit 3 (October 1, 2021 through September 30, 2022)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (3 Samples)
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
- (3) Unit 3 (October 1, 2021 through September 30, 2022)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (3 Samples)
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
- (3) Unit 3 (October 1, 2021 through September 30, 2022)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Repairs and corrective actions associated with Unit 2 Reactor Feedwater Pump Turbine tripping on November 11, 2022 due to the Woodward 505 governor failure and a subsequent trip on November 14, 2022, due to a faulty time relay.
- (2) Corrective actions and work orders associated with the setting of the Unit 2 CS pump room cooler 2B flow rate on July 15, 2022, after valve BFN-2-THV-067-0594 was replaced
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated a high temperature condition in the Unit 3 Reactor Water Cleanup Heat Exchanger Room and licensees response on October 16, 2022
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2021-001-01 for Browns Ferry Nuclear Plant, Units 1 and 2, 480 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications due to Failed Relay (ADAMS Accession No. ML22188A133). The inspectors reviewed the updated LER submittal on December 5, 2022. The previous LER submittal was reviewed in Inspection Report 05000259/2022001, 05000260/2022001, and 05000296/2022001 (ADAMS Accession No. ML21117A405). The inspection conclusions associated with this LER are documented in Inspection Report 05000259/2022001,
===05000260/2022001, and 05000296/2022001 (ADAMS Accession No. ML21117A405) under Inspection Results.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 71003 - Post-Approval Site Inspection for License Renewal Post-Approval Site Inspection for License Renewal===
- (1) Carbon Steel/Raw Uncontrolled Water Monitoring Program
Motor Generator Oil Drain Header Check Valve (0-CKV-077-0545)
Motor Generator Oil Drain Header Check Valve (0-CKV-077-0618)
Off-Gas Condenser Drain Sump Pump B Discharge Check Valve (0-CKV-077-0708B)
Unit 1 Reactor Building Floor Drain Pump A Discharge Check Valve (1-CKV-077-0606)
Unit 1 Reactor Building Floor Drain Pump B Discharge Check Valve (1-CKV-077-0609)
Unit 1 Decontamination Drain Header Check Valve (1-CKV-077-0660)
Unit 1 Drywell Equipment Drain Sump Discharge Check Valve (1-CKV-077-0671)
Unit 1 Cleanup Backwash Transfer Discharge Line Check Valve (1-CKV-077-0929)
Unit 3 Sump Pump Discharge Check Valve (3-CKV-077-0670)
Unit 3 Drywell Equipment Drain Sump Discharge Check Valve (3-CKV-077-0671)
- (2) One Time Inspection Program
Diesel Generator 0A (0-ENG-082-000A)
Diesel Generator 3B (3-ENG-082-003B)
Unit 1 Condensate Storage Tank (1-TNK-002-1462)
Unit 2 Condensate Storage Tank (2-TNK-002-1462)
Diesel Generator 3A Seven Day Oil Supply Tank (3-TNK-018-0061)
Diesel Generator 3D Seven Day Oil Supply Tank (3-TNK-018-0064)
High Pressure Fire Pump Diesel Fuel Oil Storage Tank (0-TNK-018-0803)
- (3) Bus Inspection Program
4160 V non-segregated phase bus between USST 1A and Unit Board 1C
4160 V non-segregated phase bus between USST 1B and Unit Boards 1A and 1B
4160 V non-segregated phase bus between USST 2A and Unit Board 2C
4160 V non-segregated phase bus between USST 2B and Unit Boards 2A and 2B
4160 V non-segregated phase bus between USST 3A and Unit Board 3C
4160 V non-segregated phase bus between USST 3B and Unit Boards 3A and 3B
- (4) Structures Monitoring Program and Water-Control Structures
Electrical Cable Tunnel from the Intake Pumping Station to the Powerhouse
Residual Heat Removal Service Water Tunnel
Diesel Generator Buildings
Transformer Yard
Reinforced Concrete Chimney
Intake Pumping Station
Gate Structure No. 2
Gate Structure No. 3
Intake Channel
Discharge Control Structure
North Bank of Cool Water Channel East of Gate Structure No. 2
South Dike of Cool Water Channel Between Gate Structure No.'s 2 and 3
- (5) Inspection of Overhead Heavy Load and Light Load Handling Systems
Reactor Building Crane
Unit 1 RB Recirculating Pump Motor 24-Ton Monorail South
Unit 2 RB Recirculating Pump Motor 24-Ton Monorail North
3A RHR Heat Exchanger 12-Ton Monorail
- (6) Inaccessible Medium Voltage Cables not Subject to EQ
RHRSW Pump D1 Supply
RHRSW Pump C2 Supply
RHRSW Pump A3 Supply
- (7) ASME Section XI Subsection IWE
Unit 2 UT of drywell liner plate near the sand bed region
Unit 1 the steel containment shells and their integral attachments
Unit 2 containment hatches and airlocks
Unit 3 seals, gaskets, and moisture barriers
- (8) Fatigue Monitoring Program
Work Order# 122070299 - Perform fatigue usage monitoring in accordance with 0-Tl-19 for Units 1, 2, and
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 26, 2023, the inspectors presented the integrated inspection results to Mr.
Joe Quinn and other members of the licensee staff.
On October 6, 2022, the inspectors presented the Exit meeting for the Unit 1 ISI inspection results to Manu Sivaraman, Site Vice President and other members of the licensee staff.
On December 8, 2022, the inspectors presented the Exit meeting for licensee renewal phase 4 inspection results to Manu Sivaraman, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1644485
PERFORM REPAIRS ON 4KV BUS BETWEEN USST 1A
& 1B AND THEIR ASSOCIATED BOARDS
10/15/2020
Corrective Action
Documents
CRs (by number)
27663, 330419, 338557, 541116, 679174, 1759254,
1776693
21380
During review of UFSAR Changes to UFSAR Appendix
O.1.29 to support the License
Renewal Phase 4 NRC Inspection, it was identified that
the October 4, 2021 NRC
Submittal of UFSAR Amendment 29 did not include
UFSAR Change 29-01.
2/06/2022
21777
September 2019 FSAR Change 29-001; O.1.29 ASME
Section XI, Subsection IWE Program.
2/07/2022
21827
NRC License Renewal Phase IV observation 1A USST
Transformer 4KV
2/07/2022
21836
NRC License Renewal Phase IV observation 3A USST
4KV Buss Metal Enclosure heating indication light
2/07/2022
Corrective Action
Documents
Resulting from
Inspection
21838
NRC License Renewal Phase IV observation 3B USST
4KV Buss Inspection Cover missing bolt
2/07/2022
0-TI-609
Aging Management Program Basis Document Bus
Inspection Program
Procedures
EPI-0-242-BUS001
Main Transformer, Unit Station Service Transformer and
Associated Bus Work
119415889
BUSS INSP - CSST'A'
10/15/2022
119966703
INSPECTION & PREVENTIVE MAINTENANCE ON U-3
BUSES AS DEFINED IN EPI-0-242-BUS001
10/22/2020
71003
Work Orders
Work Orders (by
number)
111229336, 113261155, 113261159, 114718910,
115483482, 115483484, 115615996, 116239119,
117196191, 117576709, 118504376, 119186207
Calculations
MDQ0999920112
Prevention of Backflow
Rev 4
0-47E830-1-LR
License Renewal Flow Diagram Radwaste
Rev 4
Drawings
0-47E830-9-LR
License Renewal Flow Diagram
Rev 1
Procedures
0-AOI-100-7
Severe Weather
Rev 49
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NPG-SPP-07.1.8
Severe Weather and Natural Disasters
Rev 2
1-47E813-1
Flow Diagram Reactor Core Isolation Cooling System
Rev 42
3-47E610-18-2
Mechanical Control Diagram Fuel Oil System
Rev 22
Drawings
3-47E814-1
Flow Diagram Core Spray System
Rev 35
1-OI-71
Reactor Core Isolation Cooling System
Rev 34
3-OI-75
Core Spray System
Rev 76
3-OI-82
Unit 3 Standby Diesel Generator System
Rev 157
Procedures
3-OI-82/ATT-1C
Unit 3 Standby Diesel Generator 3C Valve Lineup
Checklist
Rev 99
FPR-Volume 2
Fire Protection Report Volume 2
Rev 73
Fire Plans
FPR-Volume 2
Fire Protection Report Volume 2
Rev 74
Miscellaneous
NFPA 805 Fire
Protection Report
Appendix F
Fire Area 03-01
Rev 3
3-OI-82/ATT-3C
Unit 3 Standby Diesel Generator 3C Electrical Lineup
Checklist
Rev 98
NPG-SPP-18.4.7
Control of Transient Combustibles
Rev 16
Procedures
NPG-SPP-18.4.8
Control of Ignition Sources (Hot Work)
Rev 13
R-048
UT examination N9-NV 60deg
10/09/2022
R-048
UT examination N9-NV 20deg
10/09/2022
R-048
UT examination N9-NV 35deg
10/09/2022
R-048
UT examination N9-NV 45deg
10/09/2022
NDE Reports
VE-12-065
Ultrasonic examination of N9-NV reactor vessel
11/08/2012
N-UT-78
PDI Generic Procedure for the Manual Ultasonic
Examination of Reactor Pressure Vessel Welds
PDI-UT-11
Generic Procedure for the Ultasonic Examination of
Reactor Pressure Vessel Nozzle-to Shell Welds
D
Procedures
PDI-UT-6
Generic Procedure for the Ultasonic Examination of
I
OPL173.061
FLEX Requalification Training
Rev 2
OPL173R227
Welcome to Requal
Rev 56
Miscellaneous
OPL175.011
NSDP-1 Safeguards Event Reporting Overview
Rev 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-GOI-100-1A
Unit Startup
Rev 71
1-OI-47
Turbine-Generator System
Rev 74
Procedures
1-SR-3.1.3.5(A)
Control Rod Coupling Integrity Check
Rev 15
Calibration
Records
BFN-22-00001
Investigation of Out of Tolerance M&TE for E36593,
Digital Micro ohmmeter
1/26/2022
1807103
11/10/2022
1813580
11/10/2022
CR 1730569
Corrective Action
Documents
CR 1822227,
1772591, 1444907,
22234
Drawings
3-47E855-1
Flow Diagram Fuel Pool Cooling System
Rev 26
2484848,
2484839
Work Orders
2910385,
2910383
Corrective Action
Documents
1812648
10/27/2022
Engineering
Evaluations
BFN-3-22-105
Probabilistic (PRA) Evaluation Response for the
application of TS LCO 3.0.4b for TS 3.7.4 for BFN-3-
AHU-031-0104 inoperable
2/9/2022
3-GOI-100-3A
Refueling Operations (Rx Vessel Disassembly and
Floodup)
Rev 76
3-OI-2
Condensate
Rev 79
NPG-SPP-09.11.1
Equipment out of service managment
Rev 13
Procedures
NPG-SPP-09.11.2
Risk Assessment Methods for Technical Specifications
Rev 4
Work Orders
23274163
10/27/2022
1792706
10/05/2022
1804496
1810303, 1810362
10/19/2022
Corrective Action
Documents
CR 1808791
Engineering
Evaluations
MDQ107320020058
MOV 1-FCV-073-0002, Operator Requirements and
Capablities
Rev 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3-SR-3.1.7.3
Standby Liquid Control System Enriched Sodium
Pentaborate (SPB) Solution Concentration, Quantity
Calculation, and ATWS Equivalency Calculation
Rev 55
Procedures
NPG-SPP-06.8
Leak Reduction Program
Rev 9
Calculations
EDQ2092900118
Setpoint and Scaling Calculations for Neutron Monitoring
System & Recirculation Flow Loops
Rev 39
Corrective Action
Documents
1803817
Drawings
1-47E610-68-1
Mechanical Control Diagram Reactor Recirculation
System
Rev 26
BFN-1-2202-068-004
Temporary Replacement of Recirculation Loop 1A Flow
Measurement
10/18/2022
Engineering
Changes
BFN-22-059
HPCI Gland Seal Piping Reroute
11/18/2022
Severe Accident Guidelines for Modes 1-4
Rev 4
Severe Accident Guidelines for Refueling Conditions
Rev 4
BWR Owner's Group Technical Support Guidelines
Rev 1
FCR-TVA-2022-1816
Adds new pipe supports based on discovery of existing
flex hoses and documents as constructed piping
configuration
11/17/2022
Miscellaneous
Emergency Procedures Committee Generic Validation of
EPG/SAG Rev. 4 SAGs and Plant-Specific Validation of
SAMGS
Rev 0
1-SAMG-1
RPV and Primary Containment Control Modes 1-4
Rev 4
1-SAMG-1RF
RPV and Primary Containment Level Control Mode 5
Rev 0
1-SAMG-2
RPV, Containment, and Radioactivity Release Control
Modes 1-4
Rev 7
1-SAMG-2RF
RPV, Containment, and Radioactivity Control Mode 5
Rev 0
2-SAMG-1
RPV and Primary Containment Control Modes 1-4
Rev 11
2-SAMG-1RF
RPV and Primary Containment Level Control Mode 5
Rev 0
2-SAMG-2
RPV, Containment, and Radioactivity Release Control
Modes 1-4
Rev 11
2-SAMG-2RF
RPV, Containment, and Radioactivity Control Mode 5
Rev 0
3-SAMG-1
RPV and Primary Containment Control Modes 1-4
Rev 9
Procedures
3-SAMG-1RF
RPV and Primary Containment Level Control Mode 5
Rev 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3-SAMG-2
RPV, Containment, and Radioactivity Release Control
Modes 1-4
Rev 13
3-SAMG-2RF
RPV, Containment, and Radioactivity Control Mode 5
Rev 0
NPG-SPP-18.3.1
Severe Accident Management Guideline Program
Administration
Rev 8
Work Orders
23254158
11/25/2022
Procedures
1-SR-3.5.1.8
HPCI Main and Booster Pump Set Developed Head and
Flow Rate Test at 150 psig Reactor Pressure
Rev 17
2585535,
21882390
10/26/2022
Work Orders
23279027, and
23261303
Engineering
Evaluations
EWR21NSSS069238
Evaluate the requested changes to 1/2/3-OI-78 for RPV
hardening given TSTF-542 and 582 changes to BFN
Technical Specification requirements
10/05/2022
1-OI-74
Residual Heat Removal System
Rev 122
1-OI-78
Fuel Pool Cooling and Cleanup System
Rev 71
Procedures
1-POI-78
Reactor Water Letdown During Refueling Outages
Rev 10
Procedures
1-SI-4.7.A.2.g-3/32b
Primary Containment Local Leak Rate Test Control Air:
Penetration X-22
Rev 8
Work Orders
Miscellaneous
22 BFN November Training Drill Scenario Guide
11/30/2022
Corrective Action
Documents
CR 1798942
BFN Unit 1, 2, and 3
1E01 data by Month
Performance indicator Data for Unit 1, 2, and 3 for 1E01
11/28/2022
Regulatory Assessment Performance Indicator Guideline
Rev 7
71151
Miscellaneous
U1, U2, U3 2022Q3
ROP data and ROP summary documents
11/01/2022
1816156, 1816590,
1816796, 1816240
Corrective Action
Documents
CR 1804818,
1789922
Work Orders
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
1809667
10/17/2022
Work Orders
2933661
10/17/2022