IR 05000424/2024003
| ML24296A052 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/30/2024 |
| From: | Alan Blamey NRC/RGN-II/DORS/PB3 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2024003 | |
| Download: ML24296A052 (1) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2024003 AND 05000425/2024003
Dear Jamie Coleman:
On September 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On October 9, 2024, the NRC inspectors discussed the results of this inspection with J. Weissinger, 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, Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000424 and 05000425 License Nos. NPF-68 and NPF-81
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000424 and 05000425 License Numbers:
NPF-68 and NPF-81 Report Numbers:
05000424/2024003 and 05000425/2024003 Enterprise Identifier:
I-2024-003-0018 Licensee:
Southern Nuclear Operating Company, Inc Facility:
Vogtle Electric Generating Plant, Units 1 and 2 Location:
Waynesboro, GA Inspection Dates:
July 01, 2024 to September 30, 2024 Inspectors:
A. Alen Arias, Senior Project Engineer J. Bell, Senior Health Physicist S. Downey, Senior Reactor Inspector T. Morrissey, Senior Resident Inspector A. Nielsen, Senior Health Physicist J. Parent, Resident Inspector D. Restrepo, Health Physicist J. Vasquez, Reactor Inspector Approved By:
Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000425/2024-001-00 LER 2024-001-00 for Vogtle Electric Generating Plant (VEGP), Unit 2, Manual Actuation of the Reactor Protection System due to a Rod Control fuse opening causing a misaligned Shutdown Rod 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On August 14, 2024, power was reduced to approximately 90 percent RTP due to main generator control valve #4 oscillations. After repairs, the unit was returned to RTP on August 14, 2024. On September 8, 2024, the unit was shut down for a planned refueling outage (1R25) and remained shut down for the remainder of the inspection period.
Unit 2 began the inspection period at RTP. On September 5, 2024, power was reduced to approximately 92 percent RTP to perform a planned turbine valve surveillance. The unit remained at or near RTP for 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) (2 Samples)
- (1) The inspectors evaluated licensee readiness for impending adverse weather conditions due to Tropical Storm Debby approaching the site on August 5-6, 2024. The site was under a flood warning; however, flooding and tropical storm winds were not experienced on site.
- (2) The inspectors evaluated licensee readiness for impending adverse weather conditions due to Hurricane Helene approaching the site on September 24-28, 2024. The site was under a tropical storm warning. Tropical storm winds were experienced on site however, they did not impact plant operation.
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) Unit 1, train "A" residual heat removal (RHR) while train "B" RHR was out-of-service (OOS) for planned maintenance on July 30, 2024
- (2) Unit 1, trains "A" and "B" auxiliary feedwater (AFW) while the "C" train turbine-driven AFW (TDAFW) pump was OOS for a planned and emergent maintenance on August 22-September 8, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the safety injection (SI) system including the SI accumulators on September 20, 2024.
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) Fire zones 54, 55, 148, 172, 147. Unit 2 trains A and B component cooling water heat exchanger rooms, switchgear room, and piping penetration mechanical filtration rooms, July 2, 2024
- (2) Fire zones 87, 88, 89, 90, 93, 102, 158, 159. Unit 2 control building level "A", on July 10, 2024
- (3) Fire zones 105, 106, 183A and 601. Units 1 and 2 main control room, technical support center (TSC), and TSC battery room, on July 31, 2024
- (4) Fire zones 140 A/B/C/E. Unit 1 containment building, on September 12, 2024
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1, emergency diesel generator (EDG) train A" jacket water heat exchanger, (work orders (WOs) SNC1133875, Jacket Water Cooler, Periodic Inspection; and SNC1152221, Eddy Current Test PM for Unit 1 Diesel Generator Jacket Water Cooler) on September 14, 2024
71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage 1R25 from September 16 to September 20, 2024 PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
===11201-029-18-RB, 4 pipe to elbow weld, American Society of Mechanical Engineers (ASME) Class 1
- 11201-031-3-RB, 2 elbow to pipe weld, ASME Class 1
- 11201-042-3-RB, 2 elbow to pipe weld, ASME Class 1
- 11201-051-3-RB, 2 elbow to pipe weld, ASME Class 1
- 11204-125-14-RB, 10 elbow to pipe weld, ASME Class 1 Visual Examination
- Bare metal visual examination of 11201-V6-BMI-BMV, reactor vessel bottom head exterior and bottom-mounted instrumentation nozzles, ASME Class 1 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)===
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- Bare metal visual examination of 11201-V6-CRDM, reactor vessel closure head exterior, ASME Class 1 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors evaluated the licensees boric acid control program performance, which included the following activities:
(1)
- Boric acid walkdown on September 17, 2024
- Review of the following boric acid evaluations (by technical evaluation [TE]
number):
o TE1149102 o
TE1161344
- Review of the following corrective actions performed for evidence of boric acid leaks that were identified (by condition report [CR] number):
o CR10968584 o
CR11051159 o
CR10982666 o
CR11052506 o
CR10982709 o
CR11095211 o
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 a planned power reduction, shutdown, and cooldown of Unit 1 to support refueling outage 1R25 on September 7-8, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator training scenario consisting of a seismic event, a misaligned control rod, a dropped control rod, a faulted steam generator outside containment and a steam generator tube leak, on August 7, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Unit 2 nuclear service cooling water (NSCW) system, on August 18, 2024
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:
- (3) Unit 1, elevated risk with the TDAFW pump OOS for planned and emergent maintenance, on August 22 - September 8, 2024
- (4) Unit 1, elevated shutdown risk (yellow) due to lowered reactor coolant system inventory and one DC (direct-current) vital bus OOS, on September 10-11, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) CR 11091343. Unit 1 train A EDG relay 164X (field ground) annunciator actuated during monthly surveillance, on July 9, 2024
- (2) CR 11095692. Unit 2 bypass feed isolation valve, 2HV15197, dual position indication, on August 7, 2024
- (3) CR 11101211. Unit 1 containment spray (CS) train "A", impact from packing leakage into the CS encapsulation vessel from CS recirculation valve, 1HV-9002A, on August 13, 2024
- (4) CR 11101211. Unit 1 containment leakage due to CS train "A" recirculation valve, 1HV-9002A, degraded packing with the valve's encapsulation vessel head removed, on August 12-15, 2024
- (5) CR 11108446. Unit 2 train A EDG lube oil heater exchanger oil leak (20 drops-per-minute) while in operation, on September 7, 2024
- (6) CR 11109611. Unit 1 train B centrifugal charging pump differential pressure below required action limit, on September 19, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary modification:
- (1) SNC1569163. Design equivalent change package for addition of valve upstream of Unit 2 pressurizer loop seal drain header valve
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Unit 1 cycle 25 refueling outage (1R25) from September 8, 2024, to September 30, 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) (6 Samples)
- (1) Procedure 14805B-1, "Train B Residual Heat Removal Pump IST and Response Time Test," on July 31, 2024; WOs SNC1713090, SNC1716787, and SNC1716821
- (2) SP-ENG-2024-01, "NSCW Transfer Pump (1-1202-P4-008) Functional Test, following pump refurbishment and motor replacement, on July 25, 2024; WOs SNC1914915 and SNC1843386
- (3) SP-ENG-2024-02, "Unit 2 Train A NSCW Pump 3 Functional Test," following pump refurbishment and motor replacement, on August 21, 2924; WOs SNC131627, SNC1325784 (4)
14379-1, "Containment Penetration No. 79 Reactor Coolant Drain Tank Vent and Hydrogen Supply Local Leak Rate Test," on September 18, 2024; WOs SNC2036193, SNC1463499, and SNC1134040 (5)13150A-1, "Train A Nuclear Service Cooling Water," following NSCW tower bypass to basin valve, 1HV1668B, maintenance on September 24, 2024; WOs SNC 1373831 and SNC1131741 (6)14980A-1, "Diesel Generator 1A Operability Test," following periodic jacket water cooler cleaning, eddy current inspection, and replacement of the jacket water heater on September 22, 2024; WO SNC1726215 Surveillance Testing (IP Section 03.01)
(1)
14690A-2, "Train A Centrifugal Charging Pump and Check Valve IST with K601 and K608 Train A SSPS Safety Injection Slave Relay Tests," on July 9, 2024 (2)14666-1, "Train A Diesel Generator and ESFAS Test," on September 30, 2024 Inservice Testing (IST) (IP Section 03.01)
(1)
===14802A-1, "Train A NSCW Pump and Check Valve IST, and Response Time Test,"
on July 11, 2024 Containment Isolation Valve (CIV) Testing (IP Section 03.01)===
(1)
14381-1, "Containment Penetration No. 81 Containment Instrument Air Supply Line Local Leak Rate Test," on September 15, 2024 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02)
- (1) WO SNC1603263, Perform Operational Test on Boron Injection Pumps (pumps 8-10) and RCS Makeup Pumps (pumps 11-13), on July 22,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Personnel exiting the radiological controlled area (RCA).
- (2) Personnel exiting the Unit 1 containment contaminated area during refueling outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Reactor vessel component inspection activities including guide tube and baffle bolts.
- (2) Metrology activities under Unit 1 reactor vessel head.
- (3) Reactor vessel head lift (reassembly).
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 1 fuel transfer tube room VHRA
- (2) Unit 1 under vessel VHRA
- (3) Unit 1 regen heat exchanger room locked high radiation area (LHRA)
- (4) Unit 1 chemical and volume control system mixed bed demineralizer valve gallery LHRA
- (5) Unit 1 floor plugs removed for infrequent inspection activities in pipe chase LHRA Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Unit 1 trains A and B control room emergency filtration system (CREFS)
- (2) Unit 2 trains A and B CREFS
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) High efficiency particulate air (HEPA) filtration unit 500-HU-11 at the reactor upper internals lift rig
- (2) HEPA filtration unit 500-HU-09 at the top of the reactor coolant system (RCS)pressurizer cubicle
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the following internal dose assessments:
- (1) Internal contamination event, CR 10955502, dated March 12, 2023
- (2) Internal contamination event, CR 11113505, dated September 25, 2024
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) Declared pregnant workers, April 22, 2022, thru September 24, 2024
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Portable telescoping survey meters stored as 'ready for use'
- (2) Portable ion chambers stored as ready for use
- (3) Area radiation monitors in the auxiliary building
- (4) Portal monitors at the RCA exit point
- (5) Small article monitors at the RCA exit point
- (6) Personnel contamination monitors at the RCA exit point
- (7) High-purity germanium detectors in the count room
- (8) Liquid scintillation detectors in the count room
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Unit 1 containment high range area radiation monitor, 1RE-0005, March 18, and May 13, 2023
- (2) Unit 1 containment high range area radiation monitor, 1RE-0006, March 18, 2023, and July 2, 2024
- (3) Post-accident containment purge filtration, filter/charcoal testing, October 17, 2023
- (4) Unit 1 control room area radiation monitor, 1RE-0001, June 10, 2024
- (5) GEM-5 portal monitor VEGP-HP-1488, October 26, 2022, and November 9, 2023
- (6) GEM-5 portal monitor VEGP-HP-1490, October 26, 2022, and November 9, 2023
- (7) CHRONOS small article monitor VEGP-HP-2007, December 14, 2022, and December 14, 2023
- (8) ARGOS personnel contamination monitor VEGP-HP-1489, November 1, 2022, and November 28, 2023
- (9) Ludlum 177 frisker VEGP-HP-1544, August 28, 2023, and August 7, 2024
- (10) Telepole VEGP-HP-1713, December 1, 2023, and March 14, 2024
- (11) AMS-4 continuous air monitor VEGP-HP-1499, August 20, 2024
- (12) Mirion Fastscan whole body counting system, May 14, 2024
- (13) High-purity germanium detector # 1, bottle geometry, August 15, 2022 Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 1 plant vent monitor gas, 1RE-12444C, D, E, April 3, and June 15, 2024
- (2) Liquid waste monitor, 0RE-0018, April 11 and 27,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (July 1, 2023 - June 30, 2024)
- (2) Unit 2 (July 1, 2023 - June 30, 2024)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2023 - June 30, 2024)
- (2) Unit 2 (July 1, 2023 - June 30, 2024)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2023 - June 30, 2024)
- (2) Unit 2 (July 1, 2023 - June 30, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 16, 2023 - September 5, 2024
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) CR 11046997. Unit 2 nuclear instrument surveillance (14925) not scheduled and performed during refueling outage 2R23, and CR 11083800, Unit 1 train "A" RCS sample valve IST surveillance not completed within surveillance frequency.
- (2) CRs 10981359 and 11001851. Unit 1 TDAFW controller output reading low.
- (3) CR 11087257 and corrective action report (CAR) 713339. Unit 2 reactor operators' response to a control rod deviation alarm, following a lift-circuit failure of shutdown control rod J13, resulted in larger than expected control rod misalignment during reactor startup preparations following refueling outage 2R23, on June 22, 2024.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
The inspectors evaluated the following events and/or degraded conditions for plant status and mitigating actions; and provided input to NRC management to determine whether an incident investigation, augmented inspection, or special inspection team (IIT, AIT, or SIT)was warranted.
- (1) On August 13, 2024, at 12:00 pm, with Unit 2 at RTP, the licensee declared an Alert emergency per emergency action level (EAL) SA9 due to a fire that caused visible damage to a safety system component needed for the current operating mode. A fire alarm came in at 11:46 am. The fire was confirmed at 11:49 am and was extinguished at 11:51 am. The fire was in a safety-related 480-volt regulating transformer that supplies power to the Unit 2 train B engineered safety features chiller. The Alert emergency declaration was terminated on August 13, 2024, at 2:46 pm.
This event resulted in a 1-hour notification to the NRC Headquarters Operation Officer (HOO) in accordance with 10 CFR 50.72(a)(1)(i) due to the Alert emergency declaration (see NRC Event Notification 57270). The inspectors evaluated the licensee's response and verified the event was appropriately classified. Also, the inspectors evaluated this event in accordance with NRC Management Directive (MD)8.3 and determined that no follow-up inspection was necessary.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs) to verify the accuracy and completeness of the information provided and the appropriateness of the corrective actions.
- (1) LER 2024-001-00, Manual Actuation of the Reactor Protection System due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod," (ADAMS Accession No.
ML24222A467). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency or violation of NRC requirements was identified. This LER is Closed.
Reporting (IP Section 03.05) (1 Sample)
The inspectors evaluated the following licensee event reporting determinations to ensure it complied with reporting requirements.
- (1) CRs 11087048 and 11093805. Unit 2 active leak from through-wall crack on a drain line associated with RCS hot leg loop 4 safety injection pipe segment 2-1204-L4-023, identified on June 21, 2024, during the Unit 2 forced outage.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
71003 - Post-Approval Site Inspection for License Renewal Post-Approval Site Inspection for License Renewal
- (1) The inspectors observed the implementation of the following Unit 1 licensing renewal activities (listed by aging management program) from September 16 through September 19, 2024:
Structures Monitoring Program
- Performed a walkdown of the containment and auxiliary building concrete structures.
External Surfaces Monitoring Program
- Performed a walkdown of the containment liner and observed the condition of several structures supporting safety-related components.
Environmental Qualification Program
- Visual inspection of Medium-voltage cable manholes.
o Low voltage switch yard: 1NE7ADKEM39, 1NE7ADKEM40, and o
High voltage switchyard: 1NE96HKEPB01.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 9, 2024, the inspectors presented the integrated inspection results to J. Weissinger, Site Vice President (SVP), and other members of the licensee staff.
- On September 26, 2024, the inspectors presented the radiation protection inspection results to J. Weissinger, SVP, and other members of the licensee staff.
- On September 19, 2024, the inspectors presented the in-service inspection results to Johnny Weissinger, SVP, and other members of the licensee staff.
- On September 19, 2024, the inspectors presented the Unit 1 post-approval license renewal inspection results to Johnny Weissinger, SVP, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 10965146
U1 Aux Building Rm 204 Roof had Calcium Build Up
04/17/2023
CR 11109324
At E
- L. 222', AZ 220, chipped paint was discovered inside
containment building.
09/10/2024
CR 11109928
Overhead structural steel had a white substance indicative of
boric acid were found at the 238' and 263' EL., while
performing a containment coatings inspection
09/12/2024
71003
Corrective Action
Documents
CR 11112983
Pull Box #650 (1NE96HKEPB01) Solar Powered Sum Pump
Not Working
09/23/2024
1X4DB161-1
Auxiliary Feedwater System and Condensate Storage and
Degasifier System (System No. 1302)
46.0
1X4DB161-2
Auxiliary Feedwater System (System No. 1302)
29.0
Drawings
1X4DB168-3
Condensate and Feedwater System (System No. 1305)
Ver. 36.0
Procedures
11610-1
Auxiliary Feedwater System Alignment
Rev. 21
F24VNP1UT007
Ultrasonic Examination of 11201-042-3-RB
09/18/2024
F24VNP1UT008
Ultrasonic Examination of 11201-051-3-RB
09/19/2024
F24VNP1UT009
Ultrasonic Examination of 11201-031-3-RB
09/18/2024
F24VNP1UT026
Ultrasonic Examination of 11201-029-18-RB
09/19/2024
F24VNP1UT037
Ultrasonic Examination of 11204-125-14-RB
09/19/2024
F24VNP1V040
Visual Examination of 11201-V6-BMI-BMV, Reactor Vessel
Bottom Head Exterior & Bottom Mounted Instrumentation
Nozzles
09/10/2024
NDE Reports
F24VNP1V045
Visual Examination of 11201-V6-CRDM, Reactor Vessel
Closure Head Exterior
09/14/2024
ALARA Plans
24-1401
Corrective Action
Documents
Condition Reports
(CR)
11109066, 11111937, 11109689, 11109739
1635-1
Version 24
35006-C
Version 70.5
NMP-HP-300
Version 6.1
Procedures
NMP-HP-302
Version 14
273008
09/18/2024
Radiation
Surveys
273339
09/12/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
273459
09/14/2024
Radiation Work
Permits (RWPs)
RWP Nos.
24-1401, 24-1620
Corrective Action
Documents
Resulting from
Inspection
CR 11113446
Engineering
Evaluations
SNC Prospective Determination for Occupational Exposure
09/28/2017
NMP-HP-107
Individual Radiation Exposure Records and Reports
Version 4.0
NMP-HP-107-F02
Declaration of Pregnancy
Version 1.0
Procedures
NMP-HP-108-001
Instruction for Issuing and Activating Dosimetry and
Updating Dose Records in HIS-20
Version 2.3
Efficiency calibration, Gamma Spectroscopy Detector #1
08/15/2022
Calibration
Records
SNC1171466
1RE0001, Isotopic Channel Calibration - Control Room Rad
Monitor
06/12/2024
CR 10343976
Corrective Action
Documents
TE 1078018
Procedures
24625-1
Containment High Range (1RE-0006) Area monitor 1RX-
0006 Channel Calibration
Version 36.1
CR 11087291
Corrective Action
Documents
Technical
Evaluations (TEs)
1158957, 1158958, 1158959, 1158961, 1158984
2003-1
Reactor Startup (Mode 3 to Mode 2)
Ver. 8
17010-1
Annunciator Response Procedure for ALB 10 on Panel 1C1
on MCB
Ver. 53.1
Procedures
NMP-OS-007-001
Conduct of Operations Standards and Expectations
Ver. 20.2
71152A
Work Orders
SNC1862828
Replace J13 encoder
06/24/2024
Condition Reports
(CRs)
11087257, 11087291
Corrective Action
Documents
TE 1157989
Drawings
2X4DB111
Reactor Coolant System - System No. 1201
Ver. 30.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2X4DB121
Safety Injection System - System No. 1204
Ver. 50.0
Engineering
Evaluations
RER
SNC1866491
Evaluation of Unit 2 safety injection drain line isolation valve
weld flaw effects
7/20/2024
Work Orders
SNC1861090
Active leak repair for 21204X4055