ML23215A082: Difference between revisions

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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.
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.
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). August 4, 2023 J. Coleman 2 Should you have any questions concerning this letter, please contact us.
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).
August 4, 2023
 
J. Coleman 2
Should you have any questions concerning this letter, please contact us.
Sincerely, Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket Nos.: 5200025 License Nos: NPF-91
Sincerely, Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket Nos.: 5200025 License Nos: NPF-91


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NRC Inspection Report (IR) 05200025/2023011 w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV Signed by Davis, Bradley on 08/04/23
NRC Inspection Report (IR) 05200025/2023011 w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV Signed by Davis, Bradley on 08/04/23


ML23215A082
ML23215A082 X
 
SUNSI Review X
X SUNSI Review X Non-Sensitive X Publicly Available Sensitive Non-Publicly Available
Non-Sensitive
 
OFFICE RII/DCO RII/DCO RII/DCO
 
NAME C. Even J. Eargle B. Davis DATE 08/04/2023 08/03/2023 08/04/2023
 
U.S. NUCLEAR REGULATORY COMMISSION Region II
 
Docket Numbers: 5200025
 
License Numbers: NPF-91
 
Report Numbers: 05200025/2023011
 
Enterprise Identifier I-2023-011-0035
 
Licensee: Southern Nuclear Operating Company, Inc.


Facility: Vogtle Unit 3 Combined License
Sensitive X
Publicly Available


Location: Waynesboro, GA
Non-Publicly Available OFFICE RII/DCO RII/DCO RII/DCO NAME C. Even J. Eargle B. Davis DATE 08/04/2023 08/03/2023 08/04/2023


Inspection Dates: April 1, 2023, through June 30, 2023
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers:
5200025 License Numbers:
NPF-91 Report Numbers:
Enterprise Identifier 05200025/2023011 I-2023-011-0035 Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Vogtle Unit 3 Combined License Location:
Waynesboro, GA Inspection Dates:
April 1, 2023, through June 30, 2023 Inspectors:
J. Eargle, Senior Resident Inspector - Testing, Division of Construction Oversight (DCO)
S. Egli, Senior Construction Inspector, DCO B. Kemker, Senior Resident Inspector, DCO Approved by:
Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight


Inspectors: J. Eargle, Senior Resident Inspector - Testing, Division of Construction Oversight (DCO)
2
S. Egli, Senior Construction Inspector, DCO B. Kemker, Senior Resident Inspector, DCO
 
Approved by: Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight
 
Enclosure


==SUMMARY==
==SUMMARY==
OF FINDINGS
OF FINDINGS Inspection Report (IR) 05200025/2023010; April 1 - June 30, 2023; Vogtle Unit 3 Combined License, initial test program and operational programs integrated inspection report.
 
Inspection Report (IR) 05200025/2023010; April 1 - June 30, 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.
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


A. NRC-Identified and Self Revealed Findings
3 REPORT DETAILS Summary of Plant Construction Status During this report period for Unit 3, the licensee completed surveillance testing to meet Technical Specification Mode 1 requirements, and power ascension testing at 25%, 50%, and 75% power plateaus. This testing included remote shutdown room testing, loss of offsite power testing at 25% and 50% power plateaus, and a plant trip from 100% power. Also, the licensee entered a planned maintenance outage at the end of the inspection period.
 
3.
None
OPERATIONAL READINESS Cornerstones: Operational Programs IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase 3T01 Initial Test Program (Startup)
 
: a. Inspection Scope The inspectors used appropriate portions of the inspection procedure (IP) to observe the licensee's performance of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The inspectors observed the conduct of these procedures to verify if they satisfied the applicable quality and technical requirements of the Updated Final Safety Analysis Report (UFSAR) and the Technical Specifications.
B. Licensee-Identified Violations
 
None
 
2 REPORT DETAILS
 
Summary of Plant Construction Status
 
During this report period for Unit 3, the licensee completed surveillance testing to meet Technical Specification Mode 1 requirements, and power ascension testing at 25%, 50%, and 75% power plateaus. This testing included remote shutdown room testing, loss of offsite power testing at 25% and 50% power plateaus, and a plant trip from 100% power. Also, the licensee entered a planned maintenance outage at the end of the inspection period.
: 3. OPERATIONAL READINESS
 
Cornerstones: Operational Programs
 
IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase
 
3T01 Initial Test Program (Startup)
: a. Inspection Scope
 
The inspectors used appropriate portions of the inspection procedure (IP) to observe the licensee's performance of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The inspectors observed the conduct of these procedures to verify if they satisfied the applicable quality and technical requirements of the Updated Final Safety Analysis Report (UFSAR) and the Technical Specifications.


3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.
3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.
3.1
3.1 The inspectors used appropriate portions of the IP to review the test results of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR and Technical Specifications.
 
The inspectors used appropriate portions of the IP to review the test results of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR and Technical Specifications.


3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.
3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.
3.1
3.1
: b. Findings
: b. Findings No findings were identified.
 
No findings were identified.
 
3T02 Initial Test Program (Startup)
3T02 Initial Test Program (Startup)
: a. Inspection Scope
: a. Inspection Scope


3 The inspectors used appropriate portions of the IP to review the results of the following procedure used to verify if in response to a simulated loss of load the rapid power reduction system operated to reduce the nuclear power to a level capable of being handled by the steam dump system for a large load rejection. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR.
4 The inspectors used appropriate portions of the IP to review the results of the following procedure used to verify if in response to a simulated loss of load the rapid power reduction system operated to reduce the nuclear power to a level capable of being handled by the steam dump system for a large load rejection. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR.


3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0
3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0
: b. Findings
: b. Findings No findings were identified.
 
No findings were identified.
 
3T03 Initial Test Program (Startup)
3T03 Initial Test Program (Startup)
: a. Inspection Scope
: a. Inspection Scope The inspectors used appropriate portions of the IP to observe the licensee's performance of the following procedure to verify if Unit 3's automatic control systems had the ability to sustain a manual main generator trip from 100% rated thermal power and to bring the plant to stable conditions following the transient, in addition to assessing the dynamic response of the plant when the turbine was subjected to its maximum overspeed condition. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the Technical Specifications.
 
The inspectors used appropriate portions of the IP to observe the licensee's performance of the following procedure to verify if Unit 3's automatic control systems had the ability to sustain a manual main generator trip from 100% rated thermal power and to bring the plant to stable conditions following the transient, in addition to assessing the dynamic response of the plant when the turbine was subjected to its maximum overspeed condition. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the Technical Specifications.


3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver.
3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver.
2.1
2.1
: b. Findings
: b. Findings No findings were identified.
 
No findings were identified.
 
3T04 Initial Test Program (Startup)
3T04 Initial Test Program (Startup)
: a. Inspection Scope
: a. Inspection Scope The inspectors used the appropriate portions of the IP to review the results of the post fuel load core verification to verify if all fuel assemblies were loaded into the vessel in the correct location and orientation consistent with the prespecified configuration for the initial reactor core. The inspectors reviewed the results to verify if they met the technical and quality requirements of the UFSAR and the Technical Specifications.
 
: b. Findings No findings were identified
The inspectors used the appropriate portions of the IP to review the results of the post fuel load core verification to verify if all fuel assemblies were loaded into the vessel in the correct location and orientation consistent with the prespecified configuration for the initial reactor core. The inspectors reviewed the results to verify if they met the technical and quality requirements of the UFSAR and the Technical Specifications.
: b. Findings
 
No findings were identified


4
5 4.
: 4. OTHER INSPECTION RESULTS
OTHER INSPECTION RESULTS 4OA6 Meetings, Including Exit
 
4OA6 Meetings, Including Exit
.1 Exit Meeting.
.1 Exit Meeting.
On July 11, 2023, the inspectors presented the inspection results to Mr. Glen Chick, VEGP, Units 3 &4 Executive Vice President, and other licensee and contractor staff members.
On July 11, 2023, the inspectors presented the inspection results to Mr. Glen Chick, VEGP, 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.
Proprietary information was reviewed during the inspection period but was not included in the inspection report.


5 SUPPLEMENTAL INFORMATION
6 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 3T01 3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver. 3.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 4.0 3-GOP-202, Plant Shutdown 25% Power To Mode 3, Ver. P=0.15 3-EOP-E-0, Reactor trip or Safeguards Actuation, Ver. 1.1 3-EOP-ES-0.1, Reactor Trip Response, Ver. 1.2 3-AOP-601, Evacuation of Main Control Room, Ver. 3.0 WO# 1115729
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 3T01 3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver. 3.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 4.0 3-GOP-202, Plant Shutdown 25% Power To Mode 3, Ver. P=0.15 3-EOP-E-0, Reactor trip or Safeguards Actuation, Ver. 1.1 3-EOP-ES-0.1, Reactor Trip Response, Ver. 1.2 3-AOP-601, Evacuation of Main Control Room, Ver. 3.0 WO# 1115729
 
6 Section 3T02 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC1 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC2 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC3 WO 1115185 CR 10945112 CR 10945714 CR 10946157 CR 10937936 CR 10939329 CR 10939330 CR 10945549
 
Section 3T03 3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver. 2.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 6 CR 10978042
 
Section 3T04 3-GOP-301, Attachment 24, Initial Fuel Loading Mode 6 Entry Checklist, Ver. K=0.10 NMP-RE-007-F03, Vogtle 3&4 - Core Verification Signoff, Ver. 1 Unit 3 Core, Cycle 1 Core Map, 10/04/2022
 
LIST OF ACRONYMS
 
COL Combined License IMC Inspection Manual Chapter IP inspection procedure IR inspection report NRC Nuclear Regulatory Commission PARS Publicly Available Records UFSARUpdated Final Safety Analysis Report VEGP Vogtle Electric Generating Plant


7}}
7 Section 3T02 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC1 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC2 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC3 WO 1115185 CR 10945112 CR 10945714 CR 10946157 CR 10937936 CR 10939329 CR 10939330 CR 10945549 Section 3T03 3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver. 2.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 6 CR 10978042 Section 3T04 3-GOP-301, Attachment 24, Initial Fuel Loading Mode 6 Entry Checklist, Ver. K=0.10 NMP-RE-007-F03, Vogtle 3&4 - Core Verification Signoff, Ver. 1 Unit 3 Core, Cycle 1 Core Map, 10/04/2022 LIST OF ACRONYMS COL Combined License IMC Inspection Manual Chapter IP inspection procedure IR inspection report NRC Nuclear Regulatory Commission PARS Publicly Available Records UFSAR Updated Final Safety Analysis Report VEGP Vogtle Electric Generating Plant}}

Latest revision as of 02:14, 27 November 2024

(Vego), Unit 3 – Initial Test Program and Operational Programs Integrated 05200025/2023011 Inspection Report
ML23215A082
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 08/04/2023
From: Bradley Davis
NRC/RGN-II
To: Coleman J
Southern Nuclear Company
References
IR 2023011
Download: ML23215A082 (1)


Text

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

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT (VEGP), UNIT 3 - INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INTEGRATED INSPECTION REPORT 05200025/2023011

Dear Jamie Coleman:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at VEGP, Unit 3. The enclosed inspection report documents the inspection results, which the inspectors discussed on July 11, 2023, with Mr. Glen Chick, VEGP 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).

August 4, 2023

J. Coleman 2

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

Sincerely, Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket Nos.: 5200025 License Nos: NPF-91

Enclosure:

NRC Inspection Report (IR) 05200025/2023011 w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV Signed by Davis, Bradley on 08/04/23

ML23215A082 X

SUNSI Review X

Non-Sensitive

Sensitive X

Publicly Available

Non-Publicly Available OFFICE RII/DCO RII/DCO RII/DCO NAME C. Even J. Eargle B. Davis DATE 08/04/2023 08/03/2023 08/04/2023

Enclosure U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers:

5200025 License Numbers:

NPF-91 Report Numbers:

Enterprise Identifier 05200025/2023011 I-2023-011-0035 Licensee:

Southern Nuclear Operating Company, Inc.

Facility:

Vogtle Unit 3 Combined License Location:

Waynesboro, GA Inspection Dates:

April 1, 2023, through June 30, 2023 Inspectors:

J. Eargle, Senior Resident Inspector - Testing, Division of Construction Oversight (DCO)

S. Egli, Senior Construction Inspector, DCO B. Kemker, Senior Resident Inspector, DCO Approved by:

Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight

2

SUMMARY

OF FINDINGS Inspection Report (IR) 05200025/2023010; April 1 - June 30, 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

3 REPORT DETAILS Summary of Plant Construction Status During this report period for Unit 3, the licensee completed surveillance testing to meet Technical Specification Mode 1 requirements, and power ascension testing at 25%, 50%, and 75% power plateaus. This testing included remote shutdown room testing, loss of offsite power testing at 25% and 50% power plateaus, and a plant trip from 100% power. Also, the licensee entered a planned maintenance outage at the end of the inspection period.

3.

OPERATIONAL READINESS Cornerstones: Operational Programs IMC 2514, AP1000 Reactor Inspection Program - Startup Testing Phase 3T01 Initial Test Program (Startup)

a. Inspection Scope The inspectors used appropriate portions of the inspection procedure (IP) to observe the licensee's performance of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The inspectors observed the conduct of these procedures to verify if they satisfied the applicable quality and technical requirements of the Updated Final Safety Analysis Report (UFSAR) and the Technical Specifications.

3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.

3.1 The inspectors used appropriate portions of the IP to review the test results of the following procedure to verify if Unit 3 could be tripped from the remote shutdown workstation and be maintained stable in Hot Standby conditions for at least 30 minutes. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR and Technical Specifications.

3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver.

3.1

b. Findings No findings were identified.

3T02 Initial Test Program (Startup)

a. Inspection Scope

4 The inspectors used appropriate portions of the IP to review the results of the following procedure used to verify if in response to a simulated loss of load the rapid power reduction system operated to reduce the nuclear power to a level capable of being handled by the steam dump system for a large load rejection. The results were reviewed to verify whether the test satisfied the applicable technical and quality requirements of the UFSAR.

3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0

b. Findings No findings were identified.

3T03 Initial Test Program (Startup)

a. Inspection Scope The inspectors used appropriate portions of the IP to observe the licensee's performance of the following procedure to verify if Unit 3's automatic control systems had the ability to sustain a manual main generator trip from 100% rated thermal power and to bring the plant to stable conditions following the transient, in addition to assessing the dynamic response of the plant when the turbine was subjected to its maximum overspeed condition. The inspectors observed the conduct of this procedure to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the Technical Specifications.

3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver.

2.1

b. Findings No findings were identified.

3T04 Initial Test Program (Startup)

a. Inspection Scope The inspectors used the appropriate portions of the IP to review the results of the post fuel load core verification to verify if all fuel assemblies were loaded into the vessel in the correct location and orientation consistent with the prespecified configuration for the initial reactor core. The inspectors reviewed the results to verify if they met the technical and quality requirements of the UFSAR and the Technical Specifications.
b. Findings No findings were identified

5 4.

OTHER INSPECTION RESULTS 4OA6 Meetings, Including Exit

.1 Exit Meeting.

On July 11, 2023, the inspectors presented the inspection results to Mr. Glen Chick, VEGP, 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.

6 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 3T01 3-GEN-ITPS-640, Remote Shutdown Workstation Startup Test Procedure, Ver. 3.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 4.0 3-GOP-202, Plant Shutdown 25% Power To Mode 3, Ver. P=0.15 3-EOP-E-0, Reactor trip or Safeguards Actuation, Ver. 1.1 3-EOP-ES-0.1, Reactor Trip Response, Ver. 1.2 3-AOP-601, Evacuation of Main Control Room, Ver. 3.0 WO# 1115729

7 Section 3T02 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC1 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC2 3-PLS-ITPS-605, Rapid Power Reduction Startup Test Procedure, Ver. 4.0-V3TPC3 WO 1115185 CR 10945112 CR 10945714 CR 10946157 CR 10937936 CR 10939329 CR 10939330 CR 10945549 Section 3T03 3-GEN-ITPS-636, Plant Trip from 100% Power Startup Test Procedure, Ver. 2.1 3-GEN-ITPS-618, Power Ascension Test Sequence Startup Test Procedure, Ver. 6 CR 10978042 Section 3T04 3-GOP-301, Attachment 24, Initial Fuel Loading Mode 6 Entry Checklist, Ver. K=0.10 NMP-RE-007-F03, Vogtle 3&4 - Core Verification Signoff, Ver. 1 Unit 3 Core, Cycle 1 Core Map, 10/04/2022 LIST OF ACRONYMS COL Combined License IMC Inspection Manual Chapter IP inspection procedure IR inspection report NRC Nuclear Regulatory Commission PARS Publicly Available Records UFSAR Updated Final Safety Analysis Report VEGP Vogtle Electric Generating Plant