IR 05000259/2024010
| ML24313A193 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/12/2024 |
| From: | James Baptist NRC/RGN-II/DORS/PB4 |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2024010 | |
| Download: ML24313A193 (1) | |
Text
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000259/2024010 AND 05000260/2024010 AND 05000296/2024010
Dear Delson Erb:
On August 29, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant and discussed the results of this inspection with E. Quinn Leonard 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, James B. Baptist, Chief Projects Branch #4 Division of Operating Reactor Safety Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000259, 05000260 and 05000296
License Numbers:
Report Numbers:
05000259/2024010, 05000260/2024010 and 05000296/2024010
Enterprise Identifier:
I-2024-010-0046
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
August 12, 2024 to August 29, 2024
Inspectors:
P. Braxton, Reactor Inspector
L. Day, Reactor Inspector
M. Riley, Senior Project Engineer
A. Ruh, Senior Reactor Inspector
Approved By:
James B. Baptist, Chief
Reactor Projects Branch #3
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Browns Ferry Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.21N.04 - Age-Related Degradation Age-Related Degradation
- (1) Unit 3 diesel generators (2)3C core spray room cooler
- (3) Gould Shawmut fuse holders (BLR554K)
- (4) CR105/109 motor starter/contactors (5)480VAC breaker, BFN-3-BKR-268-003A/03D
- (6) Unit 1 'A' control room air handling unit motor
- (7) Unit 2 reactor core isolation cooling pump
- (8) Unit 3 core spray loop 1 inboard injection valve 3-FCV-075-0025
- (9) Unit 3 suppression pool to drywell vacuum breakers 3-FCV-64-28A-M
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 29, 2024, the inspectors presented the design basis assurance inspection (programs) inspection results to E. Quinn Leonard and other members of the licensee staff.
- On October 8, 2024, the inspectors presented the final inspection results to D. Komm and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EWR22MEB075227
EPRI PPM - MOVs 1/2/3-FCV-75-25 & -53
2/07/2022
MDQ0999980001
MOV Calculation Input Parameters
Calculations
MOV-BFN-3-FCV-
075-0025
MOV Setpoint Datasheet
1000057513
Pressure Transmitter - Absolute
07/17/2001
283363
Force Gage
07/17/2024
Calibration
Records
283374
Force module
07/17/2024
Corrective Action
Documents
CRs (by number)
1668815, 1110412, 1668815, 1681171, 1485342,
20753, 1522117, 1950572, 1950569, 1950566,
1950565, 1950564, 1950561, 1950558, 1871478,
1856299, 1832073, 1835167, 1904609, 1945052,
1951134, 1676748, 1759254, 1002768, 1534609,
1616307, 1696260, 1728343, 1390741, 1721250,
1758438, 1762129, 1397782, 1537520, 1666100,
1809888, 1909408
various
3002000562
Motor Control Center End-of-Expected-Life Guidance
November
2013
3002010628
Nuclear Maintenance Applications Center: Terry
Turbine Maintenance Guide, RCIC Application
October
2017
BFN-0-21-097
PRA evaluation of CR 105/109 motor starters being
moved to maintenance rule a(1)
08/05/2021,
09/25/2024
BFN-50-7064A
Primary Containment System
BFN-VTD-G202-
0030
Assembly and Service Instruction for GPE Control for
GPE Controls 18" Vacuum Breaker Valves Model
Number BD-0240-0030
BFN-VTD-G202-
0040
Instruction Manual for GPE Controls Vacuum Relief
Valve Model Number LF-240-125
Miscellaneous
R40 240229 549
Maintenance Rule 14th Periodic Report, January 2022
to August 2023
0-GOI-300-1/ATT-7
Unit 2 Reactor Building Operator Round Logs
250
0-GOI-300-2
Electrical
219
71111.21N.04
Procedures
0-TI-230T
Thermography Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-TI-362
Inservice Testing Program
0-TI-395
Breaker Testing and Maintenance Program
0-TI-395
Breaker Testing and Maintenance Program
0-TI-636BKR
Breaker Testing and Maintenance Program
3-SR-3.6.1.5.1
Suppression Chamber and Drywell Vacuum Breaker
Position Verification
3-SR-3.6.1.6.3
Drywell Pressure Suppression Chamber Vacuum
Breaker Inspection and Test
FMS-Pump-1
Fleet Maintenance Strategy Pump-Horizontal
MCI-0-071-PMP001
Reactor Core Isolation Cooling Pump Maintenance
NPG-SPP-09.18.14
Bridging or Mitigation Strategy Development
NPG-SPP-09.26.15
Medium and Low Voltage Circuit Breaker Testing and
Maintenance Program
NPG-SPP-09.26.7
Pump Program
03/08/2002
NPG-SPP-22.300
Corrective Action Program
OPDP-7
Fuse Control
Self-
Assessments
28150
Self-Assessment for 2024 Age-Related Degradation
(ARD) Inspection
06/14/2024
Work Orders
Work Orders (by
numbers)
116554978, 117159180, 119966583, 120681941,
21061898, 123287084, 123287089, 123287572,
23796420, 121199953, 117612816, 120503182,
21144610, 120060762, 120066873, 120113744,
20113716, 120141063, 117159180, 121061898,
2684778, 123287084, 123796420, 11454694,
116554852, 116555071, 117575066, 118840757,
116660283, 119696864, 120613297, 121471757,
21471758, 122061770, 123233303, 123233304,
23738443, 123650030, 111026437, 111026441,
119966689, 123234404, 120995026, 120995043, 2002-
011813-000, 2003-009820-000, 2008-717450-000,
various