IR 05000327/2023004
| ML24040A073 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/12/2024 |
| From: | Louis Mckown Division Reactor Projects II |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| EA-24-008 IR 2023004 | |
| Download: ML24040A073 (20) | |
Text
SUBJECT:
SEQUOYAH, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2023004 AND 05000328/2023004 AND APPARENT VIOLATION
Dear James Barstow:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah, Units 1 and 2. On January 30, 2024, the NRC inspectors discussed the results of this inspection with Mr. Tom Marshall and other members of your staff. The results of this inspection are documented in the enclosed report.
Section 71111.15 of the enclosed report discusses a finding with an associated apparent violation for which the NRC has not yet reached a preliminary significance determination.
Sequoyah's failure to adequately establish and implement maintenance instructions and practices was a performance deficiency reasonably within their ability to foresee and prevent.
Specifically, during performance of the exhaust valve lash adjustment in accordance with maintenance instruction PM 063604820; appropriate tightening of an exhaust valve bridge adjuster locknut was not performed and resulted in the failure of 1B emergency diesel generator.
The NRCs significance determination process (SDP) is designed to encourage an open dialogue between your staff and the NRC; however, neither the dialogue nor the written information you provide should affect the timeliness of our final determination. We ask that you promptly provide any relevant information that you would like us to consider in making our determination. We are currently evaluating the significance of this finding and will notify you in a separate correspondence once we have completed our preliminary significance review. You will be given an additional opportunity to provide additional information prior to our final significance determination unless our review concludes that the finding has very low safety significance (i.e.,
Green).
February 12, 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, Lou J. McKown, II, Chief Reactor Projects Branch 5 Division of Reactor Projects 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:
05000327/2023004 and 05000328/2023004
Enterprise Identifier:
I-2023-004-0036
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah Nuclear Plant, Units 1 and 2
Location:
Soddy Daisy, TN
Inspection Dates:
October 01, 2023 to December 31, 2023
Inspectors:
P. Gresh, Operations Engineer
D. Hardage, Senior Resident Inspector
A. Price, Resident Inspector
J. Walker, Sr Emergency Preparedness Inspector
Approved By:
Lou 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 Sequoyah, Units 1 and 2, 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
Failure to establish and implement adequate maintenance procedures on the 1B Diesel Generator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Pending AV 05000327,05000328/2023004-01 Open EA-24-008
[H.12] - Avoid Complacency 71111.15 A self-revealed finding with its safety significance yet to be determined (TBD) and associated Apparent Violation (AV) of Technical Specification (TS) 5.4.1, Procedures, was identified.
The licensees procedures for maintenance on the 1B Diesel Generator (DG) were not adequately prescribed and/or accomplished in accordance with documented instructions and procedures of a type appropriate to the circumstances. Specifically, the licensee failed to adequately establish and implement maintenance instructions and practices that reasonably ensured the reliability, availability, and operability of the 1B DG. The 1B DG failed on September 19, 2023, during a surveillance run due to a piston failure that required the DG to be placed in an emergency shutdown condition. The most probable direct cause of the failure was an improperly tightened rocker arm adjustment screw locknut which resulted in severe damage to the associated power pack.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 operated at or near rated thermal power (RTP) for the entire inspection period.
Unit 2 operated at or near RTP for the entire 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 auxiliary feedwater system (AFW) following surveillance testing on October 26, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 1 and Unit 2 Auxiliary Building, Elevation 653 on December 10, 2023
- (2) Emergency Raw Cooling Water Building on December 12, 2023
- (3) Unit 1 and Unit 2 Auxiliary Building, Elevation 690 on December 20, 2023
- (4) Emergency Diesel Generator Building Elevation 722 on December 27, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on November 6, 2023.
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 Inspection Procedure (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 completed on December 14, 2023.
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 main control room during restoration of the 1A emergency diesel generator (EDG) following a planned maintenance outage on October 18-19, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator examination scenario including a charging pump trip and loss of coolant accident with anticipated transient without scram on November 20, 2023.
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) Maintenance rule functional failure of Vital Battery Room III Ventilation due to failed room exhaust fan (CDE 3222) on October 16, 2023
- (2) Maintenance rule preventable functional failure of 1A 669 penetration room cooler due to age related overheating of a solenoid coil (CDE 3217) on December 26, 2023.
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) Work Order (WO) 123456243 for the replacement of the 1A centrifugal charging pump discharge check valve on December 15, 2023
Aging Management (IP Section 03.03) (1 Sample)
The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:
- (1) Degradation found during internal coatings inspection of B condensate storage water tank (CR 1846214) and an area of possible delamination in A condensate storage water tank coatings (CR 1813227) on November 30, 2023.
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) Week of October 1-6, 2023, including protected equipment reviews for planned maintenance on 2A EDG and 1A component cooling water system pump.
- (2) Week of October 15-20, 2023, including protected equipment reviews for emergent inoperability of protection system rack 2-R-9 and scheduled maintenance on 1A EDG and 2B start bus.
- (3) Week of November 26-30, 2023, including protected equipment reviews for emergent loss of 2C condenser circulating water pump and scheduled maintenance on 2A residual heat removal system pump and 2A start bus.
- (4) Week of December 11-16, 2023, including protected equipment reviews for repairs to motor-driven AFW Loop 1 level control valve 1-LCV-3-164 and review of the associated Risk-Informed Completion Time requirements on December 15, 2023.
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) Scaffold proximity and tie wire attached to fuel oil piping on 2B EDG on Oct 2, 2023.
- (2) Vital battery II tie rod severally corroded, no longer connected on October 4, 2023.
- (3) Past operability evaluation of 1B-B EDG mechanical failure during 24-hour surveillance run on October 18, 2023.
- (4) Seismic restraint for 2-LCV-148 has a lose bolt on the leg bolt to anchor plate on December 19, 2023.
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) (4 Samples)
- (1) WO 123258734, 1-SI-OPS-082-007.A Electrical Power System DG 1A PMT following maintenance outage on October 19, 2023.
- (2) WO 123141020, Measure dimensions of the B Station Air Compressor HP Cylinder bore on November 14, 2023.
- (3) WO 12122527258, 2A Containment Spray Pump high vibration on November 16, 2023.
- (4) WO 123030850 2A Safety Injection Pump Outboard bearing oil leak on December 12, 2023.
Surveillance Testing (IP Section 03.01) (3 Samples)
(1)0-SI-SXI-003-300.7, Leakage Test of the Auxiliary Feedwater System Outside Containment on October 25, 2023.
(2)1-SI-MIN-061-108.0, Ice Condenser Intermediate Deck Door Weekly Inspection on November 2, 2023.
(3)0-SI-NUC-000-133.0, Quadrant Power Tilt Ratio on December 24, 2023.
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
(1)1-SI-SXP-003-202.B, Motor Driven Auxiliary Feedwater Pump 1B-B Comprehensive Performance Test on October 25, 2023.
(2)2-SI-SXP-072-201.B, Containment Spray Pump 2B-B Performance Test on November 22, 2023.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of October 16, 2023.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization during the week of October 16, 2023.
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 October 16, 2023. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of October 16, 2023.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (1) Emergency preparedness training drill including a faulted/ruptured steam generator and a fuel failure which resulted in a general emergency on November 1, 2023.
- (2) Emergency preparedness training drill including loss of condenser vacuum, turbine trip, Anticipated Transient Without Scram, and a ruptured steam generator on November 21,
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) July 1, 2022 through June 30, 2023 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) July 1, 2022 through June 30, 2023 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) July 1, 2022 through June 30, 2023
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)2A-A EDG breaker tripped open due to loss of control of 2A-A MVARs on October 6, 2023.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends with AFW level control valve failures on December 22, 2023.
71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) The inspectors evaluated reported fire in Unit 2 rod control 5 KVA voltage regulator 2-90-85-2 and licensees performance on October 20, 2023.
- (2) The inspectors evaluated loss of the A common station service transformer and 2A start bus and licensee performance on November 13, 2023.
- (3) The inspectors evaluated a steam leak in Unit 2 turbine building and licensee performance on November 28,
INSPECTION RESULTS
Failure to establish and implement adequate maintenance procedures on the 1B Diesel Generator Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Pending AV 05000327,05000328/2023004-01 Open EA-24-008
[H.12] - Avoid Complacency 71111.15 A self-revealed finding with its safety significance yet to be determined (TBD) and associated Apparent Violation (AV) of Technical Specification (TS) 5.4.1, Procedures, was identified.
The licensees procedures for maintenance on the 1B Diesel Generator (DG) were not adequately prescribed and/or accomplished in accordance with documented instructions and procedures of a type appropriate to the circumstances. Specifically, the licensee failed to adequately establish and implement maintenance instructions and practices that reasonably ensured the reliability, availability, and operability of the 1B DG. The 1B DG failed on September 19, 2023, during a surveillance run due to a piston failure that required the DG to be placed in an emergency shutdown condition. The most probable direct cause of the failure was an improperly tightened rocker arm adjustment screw locknut which resulted in severe damage to the associated power pack.
Description:
On September 19, 2023, Sequoyah was performing a scheduled 24-hour run of the 1B DG. 1B DG was started at 1121 and at approximately 1544, operations received multiple Main Control Room and local annunciator alarms including high crankcase pressure followed by low jacket water level. The operator performed an emergency stop of the 1B DG in accordance with the annunciator response procedure.
Sequoyah units 1 and 2 entered LCO 3.8.1 Condition B for one Train B DG inoperable.
Sequoyah Units 1 and 2 TS 3.8.1 requires four DGs capable of supplying the onsite Class 1E AC Electrical Power Distribution System, to be operable in modes 1-4; if a DG is inoperable, it shall be returned to operable status within 7 days or in accordance with the Risk Informed Completion Time Program. The DGs must demonstrate the capability to run continuously at full load for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in order to ensure that they can support safety related plant equipment independently of offsite electrical power sources.
As part of the failure investigation, inspection of the 1B2 engine discovered water leaking into cylinder #14. Further inspection showed an approximately 3-inch diameter hole in the piston associated with cylinder #14. The cylinder #14 exhaust valve bridge adjusting screw locknut nut associated with one pair of the exhaust valves was found loose on top of the head along with valve spring retainer pieces. This condition is consistent with the exhaust valve falling into the cylinder during operation and causing damage to the piston/cylinder head.
Sequoyah had performed the four-year preventative maintenance procedure, PM 063604820, on the 1B DG in January 2023. This maintenance, in part, directs the technicians to check/set the exhaust valve lash settings, which requires the loosening and retightening the exhaust valve bridge adjuster locknut. The failure of the 1B DG resulted from the loss of proper lash adjustment of the rear valve bridge on cylinder #14. During operation of the 1B DG following maintenance, the exhaust valve bridge adjuster locknut on cylinder #14 separated from the adjustment screw, indicating that the locknut was not adequately tightened. The separated locknut allowed the adjuster screw to loosen, significantly increasing the clearance between the rocker arm and the valve bridge. As the adjustment screw loosened further, the valve bridge spring no longer compressed resulting in a loss of the spherical spring seat mating with the cylinder head. This ultimately resulted in a complete loss of retention of the exhaust valve, which then fell into the cylinder causing the observed cylinder damage and loss of jacket water cooling as the loose exhaust valve was struck by the piston head during each stroke.
Corrective Actions: The 1B DG was emergency stopped and Sequoyah units 1 and 2 entered LCO 3.8.1 Condition B for one Train B DG inoperable. Sequoyah performed maintenance on the 1B DG which included replacing power packs and, in subsequent maintenance outages on the remaining station DGs, ensured all exhaust valve rocker arm adjusting screw locknuts were torqued in accordance with vendor recommendations. The licensee ordered a failure analysis of the failed cylinder to be completed and ensured that the latest vendor recommendations for exhaust valve bridge lash adjustment were incorporated into the station's 4, 6, and 12 year preventative maintenance instructions.
Corrective Action References: CRs 1881328, 1882753, 1900849
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensee's failure to adequately establish and implement maintenance instructions and practices was a performance deficiency reasonably within their ability to foresee and prevent. Specifically, during performance of exhaust valve lash adjustment in accordance with maintenance instruction PM 063604820, appropriate tightening of the exhaust valve bridge adjuster locknut on DG 1B2 cylinder #14 was not performed. This resulted in the loss of retention of the exhaust valve while in service causing damage to the associated cylinder and loss of jacket water cooling.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to properly implement adequate maintenance instructions and practices contributed to the failure of the 1B DG.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors reviewed IMC 0609, Attachment 4, Initial Characterization of Findings, and determined that the finding affects the Mitigating Systems cornerstone. The finding does not screen to Green in IMC 0609 Appendix A because it represents a loss of the PRA function of one train of a multi-train TS system for greater than its TS allowed outage time. Therefore, a detailed risk assessment is required to determine the significance of this event.
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. In this case and as associated with this finding, the licensee failed to ensure that error reduction tools appropriate to the situation were implemented during the performance of PM 063604820.
Enforcement:
Violation: Sequoyah Unit 1 TS 5.4.1 requires that written procedures shall be established, implemented, and maintained as recommended by Appendix A of Regulatory Guide 1.33, Revision 2. Appendix A section 9.a requires procedures for performing maintenance that can affect the performance of safety-related equipment to be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
Sequoyah PM 063604820 includes adjustment of the safety related DG exhaust valve bridge adjuster locknut.
Sequoyah Units 1 and 2 TS 3.8.1 requires four DGs capable of supplying the onsite Class 1E AC Electrical Power Distribution System, to be operable in modes 1-4; if a DG is inoperable, it shall be returned to operable status within 7 days or in accordance with the Risk Informed Completion Time Program.
Contrary to the above, the licensee failed to establish, implement, and maintain Sequoyah PM 063604820 as recommended by Regulatory Guide 1.33 Revision 2, Appendix A, section 9.a. Specifically, the preventive maintenance instructions were not implemented to tighten the rear exhaust valve bridge adjuster locknut on the 1B2 DG cylinder #14.
Hence, further, contrary to the above, from January 25, 2023, through September 29, 2023, the licensee failed to provide four operable DGs capable of supplying the onsite Class 1E AC Electrical Power Distribution System. Specifically, given performance of the inadequate preventive maintenance activity in January 2023, the 1B DG was unable to support design basis events for the required mission time.
Enforcement Action: This violation is being treated as an apparent violation pending a final significance (enforcement) determination.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
- On January 30, 2024, the inspectors presented the integrated inspection results to Mr.
Tom Marshall and other members of the licensee staff.
- On October 19, 2023, the inspectors presented the Emergency Preparedness Program Inspection Exit inspection results to M. Augustin and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Corrective Action
Documents
Resulting from
Inspection
CR 1900162
DG CO2 tank not reaching normal pressure following
compressor run
2/27/2023
Fire Plans
AUX-0-653-00
Fire Protection Pre-Fire Plan - Auxiliary Building elevation
653.
Revision 9
Fire Plans
DGB-0-722-00
Fire Protection Pre-Fire Plan - Diesel Generator Building
elevation 722.
Revision 7
Fire Plans
ERCW-0-688-
Fire Protection Pre-Fire Plan - ERCW Pump Station
elevation 688.
Revision 2
Fire Plans
ERCW-0-704-
Fire Protection Pre-Fire Plan - ERCW Pump Station
elevation 704
Revision 2
Fire Plans
ERCW-0-720-
Fire Protection Pre-Fire Plan - ERCW Pump Station
elevation 720.
Revision 3
Corrective Action
Documents
CAR 1868693-
2
Create PMCR to replace ERCW solenoid valves
08/04/2023
Corrective Action
Documents
CR 1868693
669 Pen room cooler 1A failed to start
07/18/2023
Corrective Action
Documents
CR 1880726
Vital Battery Room III Exhaust Fan 2A2-B causing ground
09/16/2023
Corrective Action
Documents
Resulting from
Inspection
CR 1897185
Water found on top of vital battery III cell 29
2/10/2023
Engineering
Evaluations
EWR 22-EPG-
2-150
Licensing Renewal Inspection of the Unit 1 Condensate
Storage Tank
11/01/2022
Miscellaneous
Cause
Determination
Evaluation
(CDE) 3222
Functional Failure of 125V Vital Battery Room III Exhaust
Fan 2A2-B
10/05/2023
Procedures
TVA-NQA-
PLN89-A
Nuclear Quality Assurance Plan
Revision 42
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Work Orders
Delamination found in Condensate Storage Tank B
04/03/2023
Work Orders
2A1-A Battery Room III Exhaust Fan is loud
09/18/2023
Work Orders
Replacement of 1A CCP Discharge Check Valve
09/14/2023
Corrective Action
Documents
CR 1897684
Steam Generator #1 MDAFW 1-LCV-3-164 clamshell leaking
air
2/12/2023
Corrective Action
Documents
CR 1898542
Phoenix Risk Importance clarification
2/17/2023
Corrective Action
Documents
Resulting from
Inspection
CR 1883838
NRC identified scaffold proximity to 2B diesel generator
10/02/2023
Procedures
MMTP-102
Erection of Scaffolds/Temporary Work Platforms and
Ladders
Revision 23
Work Orders
Steam Generator #1 MDAFW 1-LCV-3-164 troubleshoot and
repair
2/13/2023
Corrective Action
Documents
CR 1878716
Vital Battery II severely corroded tie rod
09/05/2023
Corrective Action
Documents
CR 1881328
Unit 1 received unexpected alarms resulting in emergency
stopping 1B EDG
09/19/2023
Corrective Action
Documents
CR 1883838
NRC identified scaffold proximity to 2B diesel generator
10/02/2023
Corrective Action
Documents
CR 1889418
Request Site Engineering to perform an evaluation for
foreign material in 1B EDG
9/20/2023
Corrective Action
Documents
Resulting from
Inspection
CR 1884247
NRC identified error in Vital Battery II evaluation
10/03/2023
Corrective Action
Documents
Resulting from
Inspection
CR 1898795
Loose bolt on structural support for 2-LCV-3-148
2/18/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Engineering
Evaluations
Civil Evaluation for Vital Battery II tie rod degradation
Revision 1
Engineering
Evaluations
SCG4M00894
Seismic Qualification of Batteries and Battery Racks in Vital
Battery Rooms I, II, III, and IV
Revision 0
Corrective Action
Documents
CR 1891542
B SAC failed to start during PMT
11/09/2023
Corrective Action
Documents
Resulting from
Inspection
CR 1888481
Suction tell tale leakage increased significantly during full
flow testing of 1B AFW pump
10/25/2023
Procedures
0-PI-SXI-000-
300.0
ASME Section XI Inservice Pressure Test Scheduling and
Tracking
Revision 16
Work Orders
2A-A Containment Spray Pump vibration
11/16/2023
Work Orders
1-SI-OPS-082-007.A Electrical Power System DG 1A
Revision 74
Work Orders
2B-B Containment Spray Pump Comprehensive Section XI
Test
11/22/2023
Work Orders
B SAC temperature switch failed high preventing start
11/13/2023
Corrective Action
Documents
CR 1835817
Siren 0-PNS-901-104 failed silent test on 3/2/2022
Miscellaneous
Evaluation and Analysis of the Alert and Notification System
for Sequoyah Nuclear Plant
07/09/2019
Corrective Action
Documents
CR 1763332
3-17-22 TEENS Test Notification Issue
Procedures
REP-Appendix
B
Sequoyah Nuclear Plant Radiological Emergency Plan
Rev. 109
Procedures
REP-Generic
Radiological Emergency Plan
Rev. 116
Corrective Action
Documents
Resulting from
Inspection
CR 1887031
NRC Identified SQN 2023 Baseline Inspection CECC 2023-
014 50.54Q
Miscellaneous
CECC 2023-
Screening Evaluation Form for EPIP-2, Appendix B, Optional
2/09/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
001
TSC, OSC, and CECC Activation for Notification of Unusual
Event, Revision 53
Miscellaneous
CECC 2023-
001
Effectiveness Evaluation Form for EPIP-2, Appendix B,
Optional TSC, OSC, and CECC Activation for Notification of
Unusual Event, Revision 53
2/09/2023
Miscellaneous
CECC 2023-
2
Screening Evaluation Form for EPIP-2, Revision 53, Section
3.1[7] Substeps
2/09/2023
Miscellaneous
CECC 2023-
2
Effectiveness Evaluation Form for EPIP-2, Revision 53,
Section 3.1[7] Substeps
2/09/2023
Miscellaneous
CECC 2023-
017
Screening Evaluation Form for REP-Generic, Revision 116
05/25/2023
Miscellaneous
CECC 2023-
017
Effectiveness Evaluation Form for REP-Generic, Revision
116
05/25/2023
Miscellaneous
22 SQN Graded Exercise Report
9/14/22
Miscellaneous
23 SQN February Training Drill Report
2/8/23
Miscellaneous
Memorial Hixon 2022 Medical Services Drill Report
9/23/22
Miscellaneous
Erlanger 2022 Medical Services Drill Report
11/7/22
Miscellaneous
23 PASS Drill Report
2/13/22
Miscellaneous
22 PASS Drill Report
2/13/22
Miscellaneous
23 SQN NRC Baseline Inspection Readiness
7/31/23
Miscellaneous
Sequoyah 2023 Population Update Analysis
9/7/23
Miscellaneous
21-2023 eSoms EITER equipment records
Miscellaneous
LOA letter CHI Memorial Hixson
1/23/23
Miscellaneous
LOA letter Erlanger Health System
1/23/23
Miscellaneous
LOA letter Hamilton County EMA
1/5/23
Miscellaneous
LOA letter Soddy Daisy FD
1/13/23
Miscellaneous
8/15/22
Miscellaneous
23 SQN May Training Drill Report
5/24/23
Miscellaneous
CECC 2023-
014
50.54 Screening and Evaluation Form for CCEC EPIP-1,
EPIP-5
4/4/23
Miscellaneous
L63 220728
001
Event Report Sequoyah Nuclear Plant NOUE
7/11/22
Miscellaneous
SQN 2022-017
50.54 (q) Screening and Evaluation Form for EPIP-3 Alert,
10/13/22
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
EPIP-4 SAE, EPIP-5 R56
Miscellaneous
SQN 2022-018
50.54 (q) Screening and Evaluation Form for EPIP-2 UE,
EPIP-3 Alert, EPIP-4 SAE, EPIP-5 R56
10/13/22
Miscellaneous
SQN 2023-001
50.54 (q) Screening and Evaluation Form for EPIP-13 Dose
Assessment, Rev 23
Miscellaneous
SQN-2023-002
50.54 (q) evaluation form for EPIP-13 Dose Assessment,
Rev 23
Procedures
EPIP-1
SQN Hot and Cold Condition EALs
Rev. 61
Procedures
EPIP-13
Dose Assessment
Rev. 24
Procedures
EPIP-2
Notification of Unusual Event
Rev. 42
Procedures
EPIP-3
Alert
Rev. 44
Procedures
EPIP-4
Site Area Emergency
Rev. 46
Procedures
EPIP-5
General Emergency
Rev. 57
Self-Assessments
L17 230215
801
Audit Report SSA2301 Emergency Preparedness QA Audit
Report
2/16/23
Corrective Action
Documents
CR 1884794
Loss of control of 2A-A DG MVARs
10/06/20203
Corrective Action
Documents
CR 1884974
ACMP tracking for 2A DG MVAR condition
10/07/2023
Corrective Action
Documents
CR 1885578
PCR Urgent Changes for 2B DG runs
10/11/2023
Corrective Action
Documents
CR 1898761
Negative Trend CR - Diaphragm leaks of 1-LCV-3-164 prior
to restoration
2/18/2023
Corrective Action
Documents
CR 1887545
5KVA Rod Control Voltage Regulator Overheating
10/20/2023
Corrective Action
Documents
CR 1887558
PCR: Revise 1,2-AR-M4-B B-6 to take rod control to manual
10/21/2023
Corrective Action
Documents
CR 1887619
Unit 2 CRDM room phone needs to be replaced
10/21/2023
Corrective Action
Documents
CR 1887692
Offsite Fire Response during AOP-N.01 Plant Fire
10/22/2023
Corrective Action
Documents
CR 1892160
2A start bus normal feeder breaker failed to trip when the 'A'
CSST failed
11/13/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Corrective Action
Documents
CR 1892196
PCB 994 and 998 tripped open, deenergizing CSST A
11/13/2023
Corrective Action
Documents
CR 1894795
Received unexpected annunciator on 2-XA-55-2A window
A5 - Turbine Gland Seal Steam Pressure Abnormal
11/28/2023
Miscellaneous
SQN Fire
Brigade
Leader's
Report
Smoke coming from cabinet in Unit 2 CRDM room
10/21/2023
Procedures
Steam or Feedwater Leak
Revision 23