ML23121A320

NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200025/2023010

ML23121A320
Person / Time
Site:	Vogtle
Issue date:	05/04/2023
From:	Bradley Davis NRC/RGN-II/DCP
To:	Coleman J Southern Nuclear Company
References
IR 2023010
Download: ML23121A320 (11)

Text

May 4, 2023 Jamie Coleman Regulatory Affairs Director Southern Nuclear Company 7825 River Road, BIN 63031 Waynesboro, GA 30830

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNIT 3 - NRC INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INTEGRATED INSPECTION REPORT 05200025/2023010

Dear Jamie Coleman:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 3. The enclosed inspection report documents the inspection results, which the inspectors discussed on April 25, 2023, with Mr. Glen Chick, Vogtle Electric Generating Plant, Units 3 & 4 Executive Vice President, and other members of your staff.

The inspection examined a sample of construction activities conducted under your Combined License (COL) as it relates to safety and compliance with the Commissions rules and regulations and with the conditions of these documents. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, no findings of significance were identified In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system ADAMS. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this letter, please contact us.

Sincerely, Signed by Davis, Bradley on 05/04/23 Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket No.: 5200025 License No: NPF-91

Enclosure:

NRC Inspection Report (IR) 05200025/2023010 w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV

ML23121A320 x Non-Sensitive x Publicly Available x SUNSI Review Sensitive Non-Publicly Available OFFICE RII: DCO RII: DCO RII: DCO NAME J. Eargle C. Even B. Davis DATE 05/01/2023 05/03/2023 05/04/2023 U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers: 5200025 License Numbers: NPF-91 Report Numbers: 05200025/2023010 Enterprise Identifier: I-2023-010-0048 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Vogtle Unit 3 Combined License Location: Waynesboro, GA Inspection Dates: January 1, 2023, through March 31, 2023 Inspectors: J. Eargle, Senior Resident Inspector - Testing, Division of Construction Oversight (DCO)

S. Egli, Senior Construction Inspector, DCO J. Parent, Resident Inspector, DCO J. England, Senior Construction Inspector, DCO J. Montgomery, Senior Reactor Inspector, Division of Reactor Safety Approved by: Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight

Enclosure

SUMMARY

OF FINDINGS Inspection Report (IR) 05200025/2023010; January 1 - March 31, 2023; Vogtle Unit 3 Combined License, initial test program and operational programs integrated inspection report.

This report covers a three-month period of announced inspections of startup testing and operational programs by resident and regional inspectors. The significance of most findings is indicated by their color (Green, White, Yellow, or Red), using Inspection Manual Chapter (IMC) 0609, Significance Determination Process. Cross-cutting aspects are determined using IMC 0310, Aspects Withing the Cross-Cutting Areas. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRCs program for oversight of AP1000 start-up activities is described in IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase.

A. NRC-Identified and Self Revealed Findings None B. Licensee-Identified Violations None 2

REPORT DETAILS Summary of Plant Construction Status During this report period for Unit 3, the licensee completed pre-critical testing, and surveillance testing to meet Technical Specification Mode 2 requirements prior to commencing Unit 3 reactor startup. The licensee also completed initial criticality, low power physics testing, and surveillance testing to meet Technical Specification Mode 1 requirements prior to entering power operation.

3. OPERATIONAL READINESS Cornerstones: Operational Programs IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 3P01 Fire Protection Program (FPP)

• 64705-02.01 - Implemented Operational Feature of the FPP

• 64705-02.02 - Adequacy and operational readiness

a. Inspection Scope The inspectors reviewed aspects of the licensees FPP to determine if reasonable assurance existed at the time of the inspection to verify that the reviewed aspects of the program met the requirements of Title 10 of the Code of Federal Regulations, Part 50.48, Fire Protection. The inspectors reviewed the sites FPP document, fire hazards analysis, and fleet and site-specific procedures to determine if the requirements of BTP CMEB 9.5-1 were incorporated into the FPP.

Specifically, the inspectors reviewed various aspects of the FPP to determine if:

• fire protection features were in place to protect safe shutdown (SSD) capability and satisfied the license specific separation requirements;

• adequate operational procedures for SSD of the plant due to fire were in place;

• the licensees alternative shutdown methodology properly identified the systems and components necessary to achieve and maintain SSD conditions for each fire area, room, or zone selected for review;

• personnel required to place and maintain the plant in hot shutdown following a fire using the alternative/dedicated shutdown system were properly trained and available at all times among the onsite shift staff, exclusive of fire brigade; adequate procedures for the use of the alternative shutdown system were in place; and that the licensee conducts periodic operational tests of the alternative shutdown transfer capability and that the tests are adequate to prove the functionality of the alternative shutdown capability;

• communications equipment used by the fire brigade were functional; 3

• manual suppression equipment to be used by the fire brigade was available and functional; and

• the pre-operational and startup testing program for fire protection systems and components provided assurance that the equipment was ready for plant commercial operation.

b. Findings No findings were identified.

IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase 3T01 Initial Test Program (Startup)

a. Inspection Scope The inspectors used appropriate portions of IP 72304 to observe the licensee's performance of the following procedure for demonstrating the performance of the rapid power reduction system, entering Mode 2, achieving initial criticality, and testing to determine moderator temperature coefficient. The inspectors observed the conduct of these procedures to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the Technical Specifications.

• 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Version

• (Ver). 4.0

• B-GEN-RES-004, Low Power Physics Testing, Ver. 7.0

• 3-GEN-ITPS-611, Initial Criticality and Low Power Physics Test Startup Test Procedure, Ver. 3.2

b. Findings No findings were identified.

3T02 Initial Test Program (Startup)

a. Inspection Scope 4

The inspectors used appropriate portions of IP 72304 to review the results of the following procedure used to verify if the operators were capable of transferring controls from the main control room to the remote shutdown workstation in order to bring the plant to hot standby conditions from normal operating pressure and temperature, and place normal residual heat removal system in service to cool the plant an additional 50 degrees Fahrenheit without exceeding cooldown limits. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR.

• 3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Section 4.2, Ver. 3.0

b. Findings No findings were identified.

3T03 Initial Test Program (Startup)

a. Inspection Scope The inspectors used appropriate portions of IP 72304 to review the licensee's results of the following procedures for entering Mode 2, achieving initial criticality, and testing to determine moderator temperature coefficient. The inspectors reviewed the procedures to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the Technical Specifications.

• B-GEN-RES-004, Low Power Physics Testing, Ver. 7

• 3-GEN-ITPS-611, Initial Criticality and Low Power Physics Test Startup Test Procedure, Ver. 3.2

b. Findings No findings were identified.

4. OTHER INSPECTION RESULTS 4OA6 Meetings, Including Exit

.1 Exit Meeting.

On April 25, 2023, the inspectors presented the inspection results to Mr. Glen Chick, Vogtle Electric Generating Plant, Units 3 &4 Executive Vice President, and other licensee and contractor staff members. Proprietary information was reviewed during the inspection period, but was not included in the inspection report.

5

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensees and Contractor Personnel S. Briggs, Testing and Turnover Director A. Nix, ITP Director E. Loehlein, Operations Director J. Coleman, Regulatory Affairs Director R. Nicoletto, NI Manager J. Hartman, Shift Operations Manager D. Trafford, Operations Support Manager C. Parkes, Operations Services Manager S. Leighty, Regulatory Affairs Manager W. Garrett, Licensing Manager C. Houseal, Startup Manager J. Olsen, NI Supervisor F. Bonilla, Startup M. Lindquist, Startup K. Middlebrooks, Startup P. Miner, Startup J. Abshire, Startup J. Andino Valle, Startup M. Easter, Startup LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Type Status Description None LIST OF DOCUMENTS REVIEWED

3. OPERATIONAL READINESS Section 3P01 Procedures 3-AOP-601, Evacuation of Main Control Room, Revision (Rev.) 3 3-AOP-902, Fire Response Emergency, Ver. 2.1 B-GEN-ENG-008, Fire Protection Functionality and Fire Protection Impairments (FPI)

Requirements, Ver. 5 B-FPS-MMM-004, Portable Fire Extinguishers and Fire Hose Stations Visual Inspection, Ver. 5 Miscellaneous SV3-FPS-ITR-800337, Unit 3 Fire Detection Alarm Testing: ITAAC 2.3.04.10, Rev. 0 SV3-PMS-ITR-800543, Unit 3 PMS Transfer of Control Capability from the MCR to the RSW:

ITAAC 2.5.02.08b.ii, Rev. 0 APP-AF01-Z0R-002, Fire Extinguisher Datasheets and Report for Nuclear Island Areas, Rev. 0 6

List of Open Fire Impairment Permits, 1/3/2023 Work Orders SV3-FPS-T0W-1123556, Fire Protection Testing Portable Communication Equipment, Rev. 1 SV3-FPS-T0W-1123549, Periodic Testing of Portable Fire Extinguishers, Rev. 0 SV3-FPS-T0W-1068464, Perform FPS System Pre-Operational Testing Per 3-FPS-ITPP-502, Rev. 0 SV3-FPS-T0W-1058692, Perform 3-FPS-ITPP-501, Motor Driven Fire Pump, Rev. 0 SV3-FPS-T0W-1058419, Component Test on SV3-FPS-MP-01A, Rev. 0 SV3-FPS-T0W-1058435, Perform Component Testing on SV3-FPS-MP-02, Rev. 0 SV3-FPS-T0W-1058427, Component Test on SV3-FPS-MP-01B, Rev. 0 SNC 1341467, (1M-NEIL) 012 - Aux Building (RCA) Fire Extinguisher Inspection, Rev. 0 SNC 1340791, (1M-NEIL) 012 - Aux Building (Non-RCA) Fire Extinguisher Inspection, Rev. 0 Design Changes APP-AF01-GEF-006, Fire Extinguisher Updates, Rev. 0 Condition Reports Reviewed During Inspection TE 45001409, Action: Update Pre-Fire Plans to Reflect Field Walkdowns of As-Built, Equipment Locations, 9/6/2022 Condition Reports Generated During Inspection CR 10938827, UFSAR Table 9.5.1-1 Does Not Accurately Point to Fire Brigades Primary Communication Capability Section 3T01 3-GEN-ITPS-610, Initial Criticality and LPPT Sequence Startup Test Procedure, Ver. 2 NMP-RE-019, Beacon 10 Estimated Critical Condition, Ver. 4.1 3-GOP-302, Reactor Startup Mode 3 to Mode 2, Ver. P=0.15 B-GEN-RES-004, Low Power Physics Testing, Ver. 7 3-RLS-CSP-001, Primary System Sampling Using the RSI Primary Sampling Panel, Ver. 2 NMP-CH-701, Determination of Boron, Ver. 4 Section 3T02 3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver. 3.0 3-GEN-ITPS-606, Post Fuel Load Pre-critical Test Sequence, Ver. 5.1 3-GOP-205, Plant Cooldown from Mode 3 to Mode 5, Ver. L=0.11 3-AOP-601, Evacuation of Control Room, Ver. 3.0 WO 1115729 Section 3T03 NMP-RE-019, Beacon 10 Estimated Critical Condition, Ver. 4.1 3-GOP-302, Reactor Startup Mode 3 to Mode 2, Ver. P=0.15 NMP-RE-008-F01, Detailed Reactivity Management Plan, Power Ascension Testing - Initial Criticality to Completion of 25% RTP Plateau, Ver. 2.1 7