IR 05000424/2023003
| ML23291A304 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/27/2023 |
| From: | Alan Blamey NRC/RGN-II/DRP/RPB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2023003 | |
| Download: ML23291A304 (1) | |
Text
October 27, 2023
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2023003 AND 05000425/2023003
Dear Jamie Coleman:
On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On October 26, 2023, the NRC inspectors discussed the results of this inspection with Sonny Dean, 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, Signed by Blamey, Alan on 10/27/23 Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects 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: 05000424/2023003 and 05000425/2023003 Enterprise Identifier: I-2023-003-0028 Licensee: Southern Nuclear Operating Company, Inc.
Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA Inspection Dates: July 01, 2023 to September 30, 2023 Inspectors: J. Bell, Senior Health Physicist B. Bowker, Reactor Inspector J. Bundy, Senior Operations Engineer B. Caballero, Senior Operations Engineer M. Magyar, Reactor Inspector T. Morrissey, Senior Resident Inspector A. Nielsen, Senior Health Physicist B. Truss, Resident Inspector A. Wang, Resident Inspector Approved By: Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure
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
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On August 22, 2023, heater drain pump #2 tripped and the unit was manually tripped by the operators after the standby condensate pump failed to start. The unit was restarted on August 24, 2023 and power was raised to approximately 50 percent RTP limited by having one circulating water pump out of service for maintenance. On August 28, 2023, the second circulating water pump was placed in service. The unit was returned to RTP on August 29, 2023. The unit remained at or near RTP for the remainder of the inspection period.
Unit 2 began the inspection period at RTP. On September 10, 2023, the unit was shutdown for a planned refueling outage. The unit was restarted on September 30, 2023 and was approximately 20 percent RTP at 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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated licensee readiness for impending adverse weather conditions due to Hurricane Idalia approaching the site on August 30, 2023. The site was under a tropical storm warning, however, tropical storm force winds were not experienced on site.
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 2, train "A" emergency diesel generator (EDG) while train "B" EDG was out of service (OOS) on July 3-7, 2023
- (2) Unit 1, B" auxiliary feedwater (AFW) pump and turbine driven AFW pump trains with 1A EDG OOS for planned governor replacement, on July 12-19, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) Unit 2, nuclear service cooling water (NSCW) system on August 17-22, 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) Fire Zones 125A/126A/179/135/153/178/180, Unit 1 control building level 3, engineered safety features (ESF) chiller and normal air conditioner rooms
- (2) Fire Zone 139, spent fuel pool floor on July 20, 2023
- (3) Fire Zones 4/5/9/10, Unit 2 containment spray and residual heat removal pump rooms on July 25, 2023
- (4) Fire Zones 140A/B/C/E, Unit 2 containment building on September 18, 2023
===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 from September 11, 2023 to September 14, 2023.
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
- Weld 21201-051-5RB, 2" tee to pipe, ASME Class 1
- Weld 21205-008-10RHR, 8" pipe to tee, MRP192
- Weld 21205-008-16RHR, 8" pipe to tee, MRP192 Visual Examination
- 21201B6-001B01 - B32, SG1 primary manway bolting, ASME Class 1
- 21201B6-002B01 - B32, SG2 primary manway bolting, ASME Class 1
- 21201B6-003B01 - B32, SG3 primary manway bolting, ASME Class 1
- 21201B6-004B01 - B32, SG4 primary manway bolting, ASME Class 1
- Bare metal visual of the Reactor Vessel Closure Head, N729-6 Liquid Penetrant Examination
- Post weld PT for 1499881W1 - Main Steam Isolation Valve (MSIV) cylinder top plate 2 pipe cap Welding Activities
- Gas Tungsten Arc Welding o 1499881W1, MSIV cylinder top plate 2 pipe cap, Risk-Informed Safety Class (RISC)3 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- Bare metal visual of the Reactor Vessel Closure Head, N729-6 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
- Boric Acid Walkdown - September 11, 2023
- CR10973058 / TE1128854
- CR10982666 / TE1133254
- CR10992008 / TE1134152
- CR10999143 / TE1135390
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Partial)
(1) (Partial)
Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on November 3, 2022.
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) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 1 startup on August 25, 2023 following the unplanned outage that began on August 22, 2023.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 2 shutdown for the 2R23 refueling outage on September 10, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator annual exam scenario consisting of a loss of main feed pump, a large break loss of coolant accident and loss of one 4.16-kilovolt "1E" bus resulting in an Alert declaration, on July 31, 2023.
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 (SSCs) remain capable of performing their intended function:
- (1) Unit1, "A" EDG exceeded system 2403 performance criteria, on August 17, 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) Unit 2, elevated risk due to train "B" EDG OOS due to emergent work to address uncontrolled loading during surveillance testing, on July 3-7, 2023
19, 2023
- (3) Unit 1, elevated risk with the turbine driven AFW pump OOS for emergent maintenance August 31 - September 2, 2023
- (4) Unit 2, elevated risk with the reactor coolant system in a lowered inventory condition to support reactor head removal, on September 12, 2023 and reactor head installation on September 22, 2023
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) Condition report (CR) 10990139, Unit 2 train "B" ESF chiller condenser pressure below rounds limit, on July 28, 2023
- (2) CR 10984893, Unit 2, "B" train EDG uncontrolled loading during monthly operability test, on August 1, 2023
- (3) CR 10988636, Unit 1, "A" train EDG failure to excite during functional testing on July 31, 2023
- (4) CR 10973565, Unit 2, "B" train 1E battery corrosion and cracked lids, on August 24, 2023
- (5) CR 10995449, Control room habitability envelope penetration breach review, on September 7, 2023
- (6) CR 10998999, Hilti TZ2 anchor bolt not fully torqued on September 7, 2023
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 2 cycle 23 refueling outage (2R23) from September 10, 2023 to October 1, 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)
- (1) Unit 1, 13150A1, "Train A Nuclear Service Cooling Water System" operability run for pump 1, following maintenance on July 11, 2023; Work Orders (WOs) SNC949493 and SNC1135276
- (2) Unit 1, Functional Test #2, "DG1A On-Engine Setup Woodward 2301A Speed Control System for U1 Emergency Diesel Generator 701 Governor" and #3, "DG1A Final Acceptance Testing Woodward 2301A Speed Control System for U1 Emergency Diesel Generator 701 Governor" on train "A" EDG following governor modification from July 12 - 19, 2023; WOs SNC1138349 and SNC1138350
- (3) Unit 2, 14802A2, "Train A NSCW Pump / Check Valve Inservice Testing (IST) and Response Time Test" for pump 5, following maintenance on July 20, 2023; WOs SNC1129415, 1155120 and 1160052
- (4) Unit 2, 14904B2, "Safety Injection Pump B Inservice and Response Time Test,"
following maintenance; WOs SNC142466 and SNC1437450, on August 3, 2023
- (5) Unit 2, 14810-2, "TDAFW Pump & Check Valve IST Response Time Test" operability run following a system outage; WOs SNC1347857, 1432106, 1433898, 1430750,
===1434010 on August 7, 2023
- (6) Unit 2, 14805B2, "Train B Residual Heat Removal Pump IST and Response Time Test" operability run following a system outage on August 3, 2023; WOs SNC1108966, 1037283 and 1037284
- (7) Unit 2, 14825-2 "Quarterly Inservice Valve Test" and 14806B2 "Train B Containment Spray Pump Operability and Response Time Test" operability run, post system outage on August 23, 2023; WOs SNC1108968, 1150674, 1219963, 1172125
- (8) Unit 1, 14810-1, "TDAFW Pump & Check Valve IST Response Time Test," following governor replacement; WO SNC1555101, on September 2, 2023
and WO SNC1415865, "MSIV Hot Functional Test, Train B, DCP SNC1046657,"
following MSIV modifications on September 28, 2023 Surveillance Testing (IP Section 03.01) ===
- (1) Unit 2, 14980A2, "Diesel Generator 2A Operability Test" operability run on July 20, 2023
- (2) Unit 2, 14804A2, "Safety Injection Pump A Inservice and Response Time Tests" surveillance on August 10, 2023
- (3) Unit 1 & 2, 28680C, "Control Room Habitability Tracer Gas Testing" surveillance on August 1 - 3, 2023
- (4) Unit 2, 28210C "Main Steam Line Code Safety Valve Setpoint Verification" on Unit 2 SG2 Safety Relief valves on August 30, 2023
- (5) Unit 2, 14667-2, "Train B Diesel Generator and Engineering Safety Feature Actuation System (ESFAS) Test" on September 25 - 27, 2023
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) Unit 1, 14807B1, "Train B Motor Driven Auxiliary Feedwater Pump / Check Valve Inservice and Response Time Test" on July 6, 2023
- (2) Unit 2, 14808B2, "Train B Centrifugal Charging Pump and Check Valve IST and Response Time Test" on July 25, 2023
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, 14377-2, "Containment Penetration No. 77 Reactor Coolant Drain Tank Discharge Local Leak Rate Test" on September 12,
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) Workers exiting the containment contaminated area during the Unit 2 outage
- (2) Workers exiting the radiological controlled area during the Unit 2 outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 2 reactor vessel head lift
- (2) Entries into the locked high radiation area (LHRA) under the unit 2 reactor vessel head
- (3) In service inspection activities in the unit 2 'B' residual heat removal heat exchanger room
- (4) Engineering inspection activities inside the unit 2 bioshield 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 and very high radiation areas (VHRAs):
- (1) Unit 2 letdown regenerative heat exchanger LHRA
- (2) Unit 2 chemical and volume control system demineralizer valve gallery LHRA
- (3) Locked high radiation area around Unit 2 refueling cavity during reactor vessel head lift
- (4) Locked high radiation area under the unit 2 reactor vessel head
- (5) Unit 1 containment 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.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Radioactive material containers in various auxiliary building locations
Radioactive Waste System Walkdown (IP Section 03.02) (3 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Resin transfer equipment in the Radwaste Processing Facility
- (2) Hot trash storage area in the Alternate Radwaste Building
- (3) Unit 1 recycle evaporator package room (abandoned)
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
- (1) 2022 Unit 2 Reactor Coolant System Filters 10 CFR 61 sample
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (2) RVRS22-001, Resin, LSA
- (3) RVRS23-013, Resin, Type B
- (4) RVRS22-002, Resin, Type B
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, 2022 - June 30, 2023)
- (2) Unit 2 (July 1, 2022 - June 30, 2023)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2022 - June 30, 2023)
- (2) Unit 2 (July 1, 2022 - June 30, 2023)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2022 - June 30, 2023)
- (2) Unit 2 (July 1, 2022 - June 30, 2023)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2022 through August 23, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) April 1, 2022 through August 23, 2023
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)
- (1) The inspectors evaluated operator and equipment performance in response to a Unit 1 manual reactor trip initiated when a heater drain pump tripped and the standby condensate pump failed to start on August 22,
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 26, 2023, the inspectors presented the integrated inspection results to Sonny Dean, Site Vice President, and other members of the licensee staff.
- On September 14, 2023, the inspectors presented the Inservice Inspection (ISI) Exit Meeting inspection results to Sonny Dean, Site Vice President (VP) and other members of the licensee staff.
- On September 15, 2023, the inspectors presented the Radiation Protection Inspection Exit Meeting inspection results to R. Norris and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed the Institute of Nuclear Power Operations (INPO) Continuum Site Visit Report regarding a review performed in May 2023
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.15 Procedures 13744B2 Train B Essential Chilled Water System 11/19/2022
71111.24 Engineering DCP SNC953976 U1 Emergency Diesel Generator 701 Governor DCP
Changes
71111.24 Engineering Control Room Habitability Tracer Gas Leak Testing at Alvin
Evaluations W. Vogtle 1 & 2
71111.24 Procedures 00432C Penetration Seal Control Rev 11.2
71111.24 Procedures 54048C Control Room Envelope Habitability Program Rev 1
71124.01 Procedures NMP-HP204 ALARA Planning and Job Review Version 10.4
71124.01 Procedures NMP-HP302 Restricted Area Classification, Postings, and Access Control Version
2.11
71124.01 Radiation Survey #263897 1FHB-C 07/12/2023
Surveys
71124.01 Radiation Work 23-2620 2R23 Thermal Sleeve Metrology in Locked High Rad Areas Rev. 0
Permits (RWPs) Underneath the Reactor Head
71124.08 Procedures NMP-HP408 Solid Radioactive Waste Scaling Factor Determination and Version 2.1
Implementation and Waste Classification
71124.08 Procedures NMP-SE018-003 Physical Protection of Cat 1 or Cat 2 Quantities of
Radioactive Material at Vogtle Electric Generating Plant
71124.01 Procedures NMP-HP-404 Release of Material from the RCA and Protected Area Version 4.7
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