IR 05000259/2024011
| ML24358A257 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/26/2024 |
| From: | Louis Mckown Division of Operating Reactors |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2024011 | |
| Download: ML24358A257 (10) | |
Text
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000259/2024011, 05000260/2024011, AND 05000296/2024011
Dear Delson Erb:
On November 21, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at Browns Ferry Nuclear Plant and discussed the results of this inspection with Daniel Komm, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
December 26, 2024 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 Projects Branch 5 Division of Operating Reactor Safety 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:
05000259/2024011, 05000260/2024011, and 05000296/2024011
Enterprise Identifier:
I-2024-011-0043
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
November 4, 2024 to November 21, 2024
Inspectors:
L. Colon Fuentes, Construction Project Inspector
W. Deschaine, Senior Project Engineer
R. Easter, Resident Inspector
K. Pfeil, Senior Resident Inspector (Team Lead)
Approved By:
Louis J. McKown, II, Chief
Projects Branch 5
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The inspectors performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees Problem Identification and Resolution program in identifying, prioritizing, evaluating, and correcting problems, including an in-depth corrective action program review of the following systems or portions thereof: Standby Diesel Generators; AC Power system; and High Pressure Coolant Injection system. The inspectors also conducted a five-year review of equipment aging issues. The corrective actions for the following non-cited violations (NCVs) and notice of violation (NOV) were evaluated as part of the assessment: NCV 05000259, 05000260,05000296/2024404-01; NCV 05000259, 05000260,05000296/2024002-02; NCV 05000259, 05000260,05000296/2024002-03; NCV 05000259, 05000260,05000296/2024002-01; NCV 05000259, 05000260,05000296/2024001-02; NCV 05000296/2024001-01; NCV 05000259/2023004-01; NCV 05000259, 05000260,05000296/2023003-02; NCV 05000259/2023003-06; NCV 05000260/2023003-04; NCV 05000296/2023003-01; NCV 05000296/2023003-03; NCV 05000296/2023003-05; NOV 05000259/2023090-01; NCV 05000259, 05000260,05000296/2023044-01; NCV 05000296/2023001-01; NCV 05000259, 05000260, 05000296 /2022011-02; NCV 05000259/2022011-01; NCV 05000259/2022012-01; NCV 05000260/2022401-02; and NCV 05000259,05000260/2022401-01.
- Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience,
- Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Browns Ferry 2024 Problem Identification and Resolution Results 1) Problem Identification and Resolution Effectiveness Problem Identification: Based on a review of the requirements for initiating condition reports as described in licensee procedure NPG-SPP-22.300, "Corrective Action Program," the inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program (which includes the work management system), and there was a low threshold for entering issues into the corrective action program. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.
Problem Prioritization and Evaluation: Based on the review of condition reports, work orders, and work requests, the inspectors determined that problems were prioritized and evaluated in accordance with licensee guidance. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that in general, plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and cause determinations were appropriate, and considered the significance of the issues being evaluated.
Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that generally, corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. The team determined that the licensee was generally effective in developing corrective actions that were appropriately focused to also address the root and contributing causes for significant conditions adverse to quality to preclude repetition. Effectiveness reviews for corrective actions to preclude repetition were sufficient to ensure corrective actions were properly implemented and were effective.
Based on the samples reviewed, the team concluded that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.
2) Operating Experience The team determined that the stations processes for the use of industry and NRC operating experience information were effective and complied with regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented in accordance with applicable procedures.
3) Self-Assessments and Audits The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance. The self-assessments and audits were adequately self-critical and performance-related issues were being appropriately identified. The inspectors verified that action requests were created to document areas for improvement and findings and verified that actions had been completed consistent with those recommendations.
4) Safety-Conscious Work Environment Based on interviews with plant staff and reviews of the latest safety culture survey results, the team found no evidence of challenges to a safety conscious work environment. Employees interviewed appeared willing to raise nuclear safety concerns through at least one of the several means available. Generally, interviewees were familiar with the employee concerns program (ECP), specifically how to raise issues through the ECP, or who to contact on site.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 21, 2024, the inspectors presented the biennial problem identification and resolution inspection results to Daniel Komm, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
1439832, 1499144, 1500734, 1605613, 1718733, 1729940,
1747875, 1752984, 1770599, 1774973, 1776857, 1777369,
1777872, 1777875, 1789217, 1789632, 1794387, 1800115,
1805633, 1808215, 1809666, 1810303, 1811376, 1820207,
20718, 1821216, 1822254, 1822522, 1823305, 1827759,
28655, 1829184, 1829973, 1836572, 1836877, 1837609,
1838246, 1838266, 1838274, 1838716, 1838734, 1838771,
1839082, 1839113, 1839594, 1848668, 1857715, 1858990,
1859005, 1859008, 1859015, 1859017, 1859027, 1859029,
1859520, 1859524, 1859529, 1859534, 1862102, 1862152,
1862853, 1863230, 1865878, 1865879, 1867620, 1870482,
1870990, 1871109, 1876563, 1877946, 1888779, 1889812,
1889837, 1890244, 1890282, 1891412, 1893273, 1893273,
1897813, 1898813, 1903819, 1905254, 1908732, 1910087,
1911382, 1911827, 1911827, 1911827, 1912313, 1912313,
1912324, 1912331, 1912331, 1912342, 1912396, 1913159,
1913606, 1914192, 1915740, 1917265, 1918274, 1918275,
1918276, 1918440, 1918984, 1923873, 1926007, 1926099,
26812, 1927041, 1928605, 1931487, 1932602, 1932915,
1933507, 1934103, 1935812, 1936135, 1936791, 1938456,
1940354, 1941629, 1941972, 1942431, 1942433, 1942846,
1944022, 1946606, 1946611, 1947640, 1947795, 1948529,
1948581, 1949357, 1952331, 1952648, 1953318, 1954797,
1954800, 1955283, 1955695, 1956503, 1959289, 1959727,
1961669, 1962099, 1962179, 1970591
BFN-50-7073
High Pressure Coolant Injection (HPCI) General Design
Criteria Document
Revision 32
RPT-NWM109
Work Orders Requiring Review
11/19/2024
Miscellaneous
SHR-System 073-
24
High Pressure Coolant Injection (HPCI) Health Report
Scorecard
4/30/2024
BFN-ODM-4.7
Operations Work Control Interface
Revision 25
Procedures
NPG-SPP-01.7.1
Employee Concerns Program
Revision 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NPG-SPP-07.1.4
Work Management Prioritization - On Line
Revision 29
NPG-SPP-09.60
License Renewal Program
Revision 1
NPG-SPP-
09.60.01
License Renewal Program Implementation
Revision 1
NPG-SPP-22.102
Self-Assessment and Benchmarking Programs
Revision 14
NPG-SPP-22.300
Corrective Action Program
Revision 25
NPG-SPP-22.500
Operating Experience Program
Revision 17
OPDP-1
Conduct of Operations
Revision 61
L17 230207 800
Audit Report SSA2301 Emergency Preparedness Browns
Ferry Nuclear Plant
2/22/2023
L17 230427 801
Audit Report SSA2302 Plant Operations Browns Ferry
Nuclear Plant
5/4/2023
Self-Assessments
L17 240221 800
Audit Report SSA2402 Radiation Protection and Radioactive
Waste Browns Ferry
2/28/2024
Work Orders
114560684, 114560684, 121335280, 121335280,
2645957, 122718246, 123254158, 123287439,
23287799, 123487635, 123498952, 123514268,
23746374, 123853312, 123888118, 123888119,
24131953, 124132641, 124132641, 124301137,
24316626, 124319425, 124328594