ML23312A350
| ML23312A350 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/14/2023 |
| From: | Bradley Davis NRC/RGN-II |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2023003 | |
| Download: ML23312A350 (12) | |
Text
November 14, 2023 Jamie Coleman Director, Fleet Regulatory Affairs Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway, BIN 63031 Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 - INTEGRATED INSPECTION REPORT 05200026/2023-003
Dear Jamie Coleman:
On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant (VEGP), Unit 4. On October 24, 2023, the NRC inspectors discussed the results of this inspection with Mr. Glen Chick, VEGP Units 3 & 4 Executive 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 Davis, Bradley on 11/14/23 Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket No. 05200026 License No. NPF-92
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV
ML23312A350]
x Non-Sensitive x Publicly Available X SUNSI Review Sensitive Non-Publicly Available OFFICE RII:DCO RII: DCO RII: DCO NAME C. Even B. Kemker B. Davis DATE 11/9/2023 11/13/2023 11/14/2023 U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 05200026 License Number: NPF-92 Report Number: 05200026/2023003 Enterprise Identifier: I-2023-003-0074 Licensee: Southern Nuclear Operating Company, Inc.
Facility: Vogtle Electric Generating Plant, Unit 4 Location: Waynesboro, GA Inspection Dates: July 01, 2023, to September 30, 2023 Inspectors: B. Kemker, Senior Resident Inspector J. Eargle, Senior Resident Inspector B. Griman, Resident Inspector J. Parent, Resident Inspector J. England, Senior Construction Inspector C. Even, Senior Construction Inspector R. Patel, Senior Construction Inspector Approved By: Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, Unit 4, 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.
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PLANT STATUS On July 28, the NRC staff issued the 10 CFR 52.103(g) finding for Vogtle Unit 4 based on its determination that all of the inspections, tests, analyses, and acceptance criteria in Appendix C of the Vogtle Unit 4 combined license were successfully completed (ML22348A094). This finding allows the licensee to load fuel and begin operation of the unit in accordance with the terms and conditions of the combined license.
On August 17, the licensee began initial fuel load, with Unit 4 entering Mode 6 (Refueling) for the first time when the first fuel assembly entered the reactor vessel. The licensee completed initial fuel load on August 19. On August 25, the licensee completed assembly of the reactor and the unit entered Mode 5 (Cold Shutdown). On September 21, the licensee completed required testing and established conditions to begin plant heat up and the unit entered Mode 4 (Safe Shutdown). On September 25, the licensee completed additional required testing and continued plant heat up for the unit to enter Mode 3 (Hot Standby). On September 29, the 2A reactor coolant pump (RCP) tripped on an instantaneous overcurrent condition.
At the end of this inspection period, the unit was in Mode 3 and the licensee was investigating the cause for the RCP trip and performing pre-critical testing in preparation for plant start up.
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 the adequacy of the overall preparations to protect risk significant systems from impending severe (hot) weather during the week of July 30.
(2) The inspectors evaluated the adequacy of the overall preparations to protect risk significant systems from impending high winds and heavy rainfall on August 30.
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71111.04 - Equipment Alignment Complete Walkdown Sample [AP1000] (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated system configurations during a complete walkdown of the passive core cooling system prior to containment closeout for initial plant start up during the weeks of August 27, September 3, and September 10.
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample [AP1000] (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) Class 1E direct current (DC) and uninterruptible power supply (UPS) system (IDS) division A/B/C/D DC equipment rooms and protection and safety monitoring system (PMS) division A/B/C/D equipment rooms on August 17.
Fire Brigade Drill Performance Sample [AP1000] (IP Section 03.02) (1 Sample)
(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on August 9.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1) The inspectors observed and evaluated licensed operators during evaluated simulator training on July 17.
(2) The inspectors observed and evaluated licensed operators during evaluated simulator training on July 31.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample [AP1000] (IP Section 03.01) (1 Sample)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned work activity to ensure configuration changes and appropriate work controls were addressed:
(1) Reactor coolant system (RCS) drain to reduced inventory for RCS fill and vent following initial fuel load from August 22 to August 23.
71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determination:
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(1) 11009438-Unit 4-ODS, "Missed VES [Main Control Room Emergency Habitability System] Surveillance on Unit 4" 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications [AP1000] (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary modification:
(1) SNC1536874 SV4 Alternate VFS [Containment Air Filtration System] Air Sample Point Location to Support the ODCM [Offsite Dose Calculation Manual]
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1) Unit 4 Initial Fuel Loading and Initial Plant Startup Activities The inspectors evaluated the licensee's conduct of outage activities to assess the control of plant configuration and management of shutdown risk for initial fuel load and initial plant start up activities from entry into Mode 6 through Mode 3.
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) DDS-HS316, cumulative time delay reset handswitch after replacement of fiber optic cable on August 14 (2) 4-PMS-HS040, steam dump stage 2 cooldown division D after cleaning the contacts on August 14 (3) Base metal repairs on the Unit 4 core barrel and upper core plate during the week of August 8 (4) 4-PXS-V014B and V015B, core makeup tank B outlet isolation air-operated valves repairs on September 19 Surveillance Testing (IP Section 03.01) (1 Sample)
(1) 4-IDSB-OTS-06-002, "31 Day Surveillance Test of Station Batteries 4-IDSB-DB-1a and 4-IDSB-DB-1B," on August 9 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1) 4-ECS-OT-17-003, "Ancillary AC Diesel Generator 10 Year Operational Test," on August 7 5
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 24, 2023, the inspectors presented the integrated inspection results to Mr. Glen Chick, VEGP Units 3 & 4 Executive Vice President and other members of the licensee staff.
THIRD PARTY REVIEWS The inspectors reviewed World Association of Nuclear Operators (WANO) Pre-Startup Peer Review Report for Vogtle Unit 4 dated May 2023. During this review, the inspectors did not identify any new safety significant issues.
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DOCUMENTS REVIEWED Inspection Type Designation Description or Title Revision or Procedure Date 71111.01 Corrective Action 10993187 NRC Resident identified that Unit 3 & 4 river water intake Documents structure doors were unlocked.
Resulting from 10993195 NRC Resident identified unattended debris during Unit 3 & 4 Inspection river water intake walkdown CR 11002200 NRC Identified Gap Implementing NMP-OS-017 08/30/2023 Procedures 4-AOP-901 Acts of Nature Version 1 NMP-OS-017 Severe Weather Version 3.1 NMP-OS-020 Station Response to Southern Company System Alert Revision 2 Conditions 71111.04 Miscellaneous 4-PXS-SOP-001, Shutdown Alignment Inside Containment Version 2.0 Attachment 11 Procedures 4-PXS-SOP-001 Passive Core Cooling System Revision 2 71111.05 Fire Plans B-PFP-ENG-001- Pre-Fire Plan - Auxiliary Building Non-RCS El 66'-6" Revision 1 F4110 B-PFP-ENG-001- Pre-Fire Plan - Auxiliary Building Non-RCA El 82'-6" Revision 1 F4111 B-PFP-ENG- Pre-Fire Plan - Auxiliary building Non-RCA El 100'-0" Revision 1 001F4113 71111.11Q Procedures 3-GEN-ITPS-633 100% Load Rejection Startup Test Procedure Version 5.0 3-GEN-ITPS-638 Loss of Offsite Power Startup Test Procedure Version 7.0 71111.13 Corrective Action CR 11000120 Protected Equipment Procedure implementation shortfall 08/24/2023 Documents Resulting from Inspection Drawings APP-FPS-M6-002 Piping and Instrumentation Diagram Fire Protection System Revision 10 Procedures B-ADM-OPS-018 Protected Division and Protected Equipment Program Revision 2 71111.15 Corrective Action 11009438 Missed VES Surveillance on Unit 4 09/23/2023 Documents Procedures 4-VES-OTS Main Control Room Differential Pressure Calibration Version 1.0 001 Work Orders WO 1202930 Perform Component Test on SV4-VES-JE-PDT004A IAW B- Revision 0 GEN-ITPCI-019-457 7
Inspection Type Designation Description or Title Revision or Procedure Date WO 1261930 Perform Component Testing on SV4-VES-JE-PDT004B IAW Revision 0 B-GEN-ITPCI-019-458 71111.18 Corrective Action 10999635 Temp Power Tagging not Present Documents Resulting from Inspection Engineering SNC1535127 Temporary SV4 Alternate VFS Air Sample Point Location to Revision 0 Changes Support ODCM Procedures B-GEN-ENG-038- Vogtle 3 & 4 Temporary Configuration Change Process Revision 1.1 001 NMP-ES-095-002 Temporary Configuration Change Process Revision 2.0 NMP-FLS-003- Temporary Power Revision 5.1 001 Work Orders SNC1536874 Install Temporary SV4 Alternate VFS Air Sample Point Revision 0 Location to Support ODCM 71111.20 Drawings APP-PXS-M6- Piping and Instrumentation Diagram Passive Core Cooling Revision 16 001 System Engineering ND-LI-VNP-002- Nuclear Fuel Assessment of Foreign Material in 4-PXS- Revision 1.0 Evaluations F01 V014B and 4-PXS-V015B (Vogtle 4)
Miscellaneous B-ADM-WCO- Operational Readiness Repetitive Task Management Version 7.0 001-001 NMP-RE-011-F01 Move Sheet Package Cover Sheet Version 1.1 Procedures 4-GEN-ITPS-601 Initial Fuel Loading Startup Test Procedure Version 1.0 4-GEN-ITPS-618 Power Ascension Test Sequence Startup Test Procedure Version 2.0 4-GOP-102 Draining the Reactor Coolant System Version 3.0 4-GOP-205 Plant Cooldown Mode 3 to Mode 5 Version 1.0 4-GOP-301 Mode Change Checklists Version 1.0 4-GOP-303 Plant Heatup Mode 5 to Normal Operating Temperature Version 1.0 4-GOP-304 Refueling to Cold Shutdown Mode 6 to Mode 5 Version 2.0 4-GOP-305 Refueling Mode 6 Version 1.0 4-RCS-OTS Reactor Coolant System Boron Concentration During Version 1.0 004 Refueling 4-RCS-SOP-001 Reactor Coolant System Version 1.0 4-RNS-SOP-001 Normal Residual Heat Removal System Version 8
Inspection Type Designation Description or Title Revision or Procedure Date E=0.4 B-GEN-ENG-032 Containment Cleanliness and Sampling Program Version 1.0 B-GEN-ENG-032- Containment Debris Sampling Version 001 A=0.0 B-GEN-ENG-032- Control of Unattended Temporary Material in Containment in Version 1.1 002 Modes 1-4 B-GEN-OPS-006 Containment Entry Version 3.1 B-RXS-CSP-001 Reactor Vessel Sampling Prior to Fuel Load Version 2.0 71111.24 Corrective Action CR 50179480 SV4-MI01 Upper Core Plate Damage Documents CR 50179667 CR to Document Repairs to Unit 4 Upper Core Plate CR 50179703 There Are Indications of Scratch Marks on the Core Barrel Engineering ESR 5017914 Request IWA to Make Repairs to the Core Barrel Changes ESR 5017916 Request for N&D to Accept the As-Found Condition on the Vessel Upper Internal Miscellaneous Photographs: CoreBarrel11691414376678, CoreBarrel21691414392363, Core Barrel 31691414408232, CoreBarrel41691414422236 NMP-MA-050- Work Planning Clearance Request From for MWO 1306041 Revision 0 F03 NDE Reports Core Barrel Inspection Report Procedures 4-ECS-OTS Ancillary AC Diesel Generator 10 Year Operational Test Revision 1.0 003 4-IDSB-OTS 31 Day Surveillance Test of Station Batteries 4-IDSB-DB-1A Version 1.0 002 and 4-IDSB-DB-1B 4-PMS-OTS Remote Shutdown Workstation 24-Month Surveillance Version 1.0 001 4-PXS-OTS PXS Valve Actuation and Exercise Test Version 1.0 006 Work Orders IWA #1-SV4-ESR50179516 MWO 1306041 Work Package for SV4-RXS-MI-25 SNC 1558695 Disassemble/Inspect/Reassemble Valve 4-PXS-V014B Revision 0 SNC 1558696 Disassemble/Inspect/Reassemble Valve 4-PXS-V015B Revision 0 SNC1490953 9
Inspection Type Designation Description or Title Revision or Procedure Date SNC1490966 10