IR 05000327/2024004
| ML25024A182 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/28/2025 |
| From: | Louis Mckown NRC/RGN-II/DORS/PB5 |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2024004 | |
| Download: ML25024A182 (14) | |
Text
SUBJECT:
SEQUOYAH - INTEGRATED INSPECTION REPORT 05000327/2024004 AND 05000328/2024004
Dear Delson Erb:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah. On January 22, 2025, the NRC inspectors discussed the results of this inspection with Tom Marshall, Site Vice President 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, Branch Chief Reactor Projects Branch 5 Division of Operating Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000327 and 05000328
License Numbers:
Report Numbers:
05000327/2024004 and 05000328/2024004
Enterprise Identifier:
I-2024-004-0024
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah
Location:
Soddy-Daisey, TN
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
M. Bates, Senior Operations Engineer
W. Deschaine, Senior Project Engineer
J. Hamman, Senior Project Engineer
D. Hardage, Senior Resident Inspector
B. Kellner, Senior Health Physicist
P. Meier, Senior Resident Inspector
M. Mondou, Project Engineer
A. Price, Resident Inspector
M. Rich, Emergency Preparedness Inspector
J. Viera, Senior Operations Engineer
J. Walker, Senior Emergency Preparedness Inspector
Approved By:
Louis J. McKown, II, Chief
Reactor Projects Branch 5
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah, 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 05000328/2024-001-00 LER 2024-001-00 for Sequoyah Nuclear Plant,
Unit 2, Reactor Trip due to an Electrical Trouble Turbine Trip 71153 Closed LER 05000327/2024-001-00 LER 2024-001-00 for Sequoyah Nuclear Plant,
Unit 1, Reactor Trip due to a Turbine Trip 71153 Closed LER 05000327/2024-002-00 LER 2024-002-00 for Sequoyah Nuclear Plant,
Unit 1, Reactor Trip due to a Turbine Trip 71153 Closed
PLANT STATUS
Unit 1 began the inspection period in mode 4 to address repairs related to the main generator. On October 17, 2024, the unit entered mode 3 and progressed to mode 1 on October 19, 2024. The main generator was synchronized to the grid on October 21, 2024. Full rated thermal power (RTP) was achieved on October 27, 2024. Unit 1 remained at approximately 100 percent RTP to the end of the inspection period.
Unit 2 began the inspection period in mode 6. Mode 5 was entered on October 4, 2024, and remained there to the end 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
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures, for the following systems:
- Unit 1 main steam valve vaults during the week of November 11, 2024
- Unit 1 main feedwater flow sensing lines during the week of November 11, 2024
- Unit 1 moisture separator reheaters during the week of November 11, 2024
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Essential raw cooling water system train alignment during a N-B essential cooling water pump planned maintenance outage during the week of November 4 and November 11, 2024
- (2) Unit 1 and unit 2 A train emergency diesel generator start air systems on December 17, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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) Main control room on December 12, 2024
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial written 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." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on December 13, 2024.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
An inspection was performed to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. Each of the following inspection activities was conducted in accordance with IP
===71111.11, Licensed Operator Requalification Program and Licensed Operator Performance.
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on December 13, 2024.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
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 control room during the following evolutions:
- Unit 2 drain down for reactor head installation preparations on October 3, 2024
- Unit 2 during reactor coolant system (RCS) sweeps and vents on October 11, 2024 Licensed Operator Requalification Training/Examinations (IP Section 03.02)===
- (1) The inspectors observed and evaluated a cycle 24-4 crew simulator exam involving a steam generator tube rupture scenario on October 7, 2024 (Segment number OPL273E2441).
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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 2 pressurizer power operated relief valve leakage issues while in mode 5 following the fall 2024 (U2R26) refueling outage (condition report (CR) 1970862)
- (2) Licensee's periodic evaluation in accordance with 10 CFR 50.65(a)(3) covering the period from October 1, 2019, thru March 31, 2021 (Maintenance Rule Sixteenth Periodic Assessment Report Units 1, 2, and Common)
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)
- Unit 2 "A" train centrifugal charging pump element replacement (WO
===123537982)
- Unit 2 "A" train centrifugal charging pump motor replacement (WO 117812692)
- Component cooling system pump C-S motor replacement (WO 117809394)
- Unit 2 "A" train safety injection pump shaft replacement (WO 124313520)
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01)===
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) C-S component cooling water pump motor degraded bearing identified on October 12, 2024, and replaced on October 15, 2024 (CR 1965317; WO 124886055)
- (2) Rising unit 2 pressurizer relief tank level trend during unit 1 startup and power ascension in October 2024 (CR 1966755)
- (3) Unit 2 essential raw cooling water containment spray heat exchanger pipe replacement restoration and impact to unit 1 essential raw cooling water system availability on November 6 through 8, 2024 (WO 123748707)
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 motor driven auxiliary feedwater level control valve failure to control from the control room identified on September 29, 2024 (CR 1962284; CR 1962371)
- (2) Cable spreading room cable tray supporting scaffolding identified on October 22, 2024 (CR 1969522)
- (3) Unit 2 reactor coolant system pressure temperature limitations curve potentially incorrect following an update identified on October 30, 2024 (CR 1969241, 1939921)
- (4) Unit 2 B train containment spray header flow control valve (2-FCV-72-20) leakage identified with the reactor coolant system aligned on residual heat removal identified on November 20, 2024 (CR1974048)
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample; 1 Partial Sample)
- (1) The inspectors evaluated unit 1 forced outage due to main generator issues from September 29, 2024, through October 19, 2024.
(2)
(Partial) The inspectors evaluated the continuing unit 2 forced outage due to unit 2 main generator issues from October 1, 2024, to December 31, 2024.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
- (1) Unit 1 A residual heat removal pump cooler maintenance on October 30, 2024 (WO
===124165109)
- (2) Unit 2 "A" charging pump element replacement during the 2024 fall refueling outage (WO 123537982)
- (3) Unit 2 "A" safety injection pump shaft replacement during the 2024 fall refueling outage (WO 124313520)
- (4) Unit 2 containment electrical penetration 13 replacement impacting power supply to various reactor control rods on December 2, 2024 (WO 124204851)
- (5) Unit 2 loop two steam generator atmospheric relief valve (2-PCV-1-12-B) overhaul on December 17, 2024 (WO123557071; WO123535816)
Surveillance Testing (IP Section 03.01)===
- (1) Unit 1 "A" train reactor trip instrumentation functional test on October 29, 2024 (1-SI-IFT-099-90.8A; WO 124424932)
- (2) Unit 2 component cooling water system supply check valves to reactor coolant pump thermal barriers test on November 25, 2024 (2-SI-SXV-070-202.0; WO 124159447)
- (3) Unit 1 reactor coolant system specific activity surveillance on December 2, 2024 (0-SI-CEM-000-877)
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1 A train containment spray pump on October 29, 2024 (WO 124121217)
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2 ice condenser as left ice weighing surveillance following ice condenser servicing during the 2024 fall refueling outage (WO 123729466)
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the conduct of the biennial emergency plan exercise during the week of December 9, 2024. The exercise scenario began with RCS leakage that caused pressurizer level to lower. The operating crew determined that the leakage was greater than emergency action level (EAL) threshold and declared a notice of unusual event (NOUE). Shortly afterward, a simulated seismic event followed by an aftershock occurred which caused RCS leakage to increase. In response, the operating crew initiated a reactor trip, safety injection initiated, and an Alert was declared. As the scenario progressed the onset of fuel damage began, and with containment radiation monitors increasing above threshold levels a Site Area Emergency was declared. Later in the exercise, another simulated aftershock occurred that inhibited the crews ability to spray containment. When containment pressure increased above EAL threshold, the conditions for declaration of a General Emergency were met and allowed the Offsite Response Organizations to demonstrate their ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of December 9, 2024. This evaluation does not constitute NRC approval.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12)===
- (1) Jul 1, 2023, through Sept 30, 2024.
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) Jul 1, 2023, through Sept 30, 2024.
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) Jul 1, 2023, through Sept 30, 2024.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in degrading maintenance fundamentals that might be indicative of a more significant safety issue (CR1962008).
71153 - Follow Up of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000328/2024-001-00, Unit 2 Reactor Trip due to an Electrical Trouble Turbine Trip (ADAMS Accession No. ML24269A161)
The inspectors did not identify a performance deficiency or violation of NRC requirements.
- (2) LER 05000327/2024-001-00, Unit 1 Reactor Trip due to an Electrical Trouble Turbine Trip on August 23, 2024 (ADAMS Accession No. ML24295A020)
The inspectors did not identify a performance deficiency or violation of NRC requirements.
- (3) LER 05000327/2024-002-00, Unit 1 Reactor Trip due to an Electrical Trouble Turbine Trip on September 29, 2024 (ADAMS Accession No. ML24325A507)
The inspectors did not identify a performance deficiency or violation of NRC requirements.
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 22, 2025, the inspectors presented the integrated inspection results to Tom Marshall, Site Vice President and other members of the licensee staff.
- On December 12, 2024, the inspectors presented the requalification program inspection results to Tom Marshall, Site Vice President and other members of the licensee staff.
- On December 12, 2024, the inspectors presented the emergency preparedness exercise inspection results to Tom Marshall and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 1967396
Door latch could potentially impact closure of a required fire
door
10/22/2024
Corrective Action
Documents
Resulting from
Inspection
CR 1979193
Filter material lying on top of Annunciator Cabinets in MCR
2/12/2024
Corrective Action
Documents
Resulting from
Inspection
CR 1967576
NRC identified PCR: AOP-R.05 RCS leak entry criteria
10/23/2024
EPIP-6
Activation and Operation of the Technical Support Center
Revision 62
Procedures
EPIP-7
Activation and Operation of the Operations Support Center
(OSC)
Revision 39
Engineering
Evaluations
SQS20247
Radiological Emergency Plan Effluent Radiation Monitor
EALs and Radiation Alerts
Revision 3
CECC 2024-009
SQN EPIP-1, Emergency Plan Classification Matrix, Revision
Screening Evaluation Form
04/08/2024
Miscellaneous
CECC 2024-025
SQN EPIP-1, Emergency Plan Classification Matrix, Revision
Screening Evaluation Form
07/24/2024
Procedures
0-TI-328
Design Engineering Numeric Input to the Emergency
Preparedness Program
Revision 1
71151
Corrective Action
Documents
Condition Reports reviewed during the course of the
inspection: CR 1890059, 1890064, 1911947, 1948530, and
1967500.
Various