ML23199A089

(Vegp), Unit 4 Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2023007

ML23199A089
Person / Time
Site:	Vogtle
Issue date:	07/18/2023
From:	Bradley Davis NRC/RGN-II
To:	Coleman J Southern Nuclear Operating Co
References
IR 2023007
Download: ML23199A089 (73)

Text

July 18, 2023 Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company 7825 River Road, BIN 63031 Waynesboro, GA 30830

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT (VEGP), UNIT 4 - INITIAL TEST PROGRAM AND OPERATIONAL PROGRAMS INTEGRATED INSPECTION REPORT 05200026/2023007

Dear Jamie Coleman:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at VEGP, Unit 4. 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, one finding of very low safety significance was identified.

This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Vogtle Electric Generating Plant (VEGP), Unit 3.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Vogtle Electric Generating Plant (VEGP), Unit 3.

J. Coleman 2 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 07/18/23 Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Docket No.: 5200026 License No: NPF-92

Enclosure:

NRC Inspection Report (IR) 05200026/2023007 w/attachment: Supplemental Information cc w/ encl: Distribution via LISTSERV

ML23199A089 Cover Letter Only: X Non-Sensitive X Publicly Available X SUNSI Review Sensitive Non-Publicly Available OFFICE RII/DCO RII/DCO RII/DCO NAME C. Even J. Eargle B. Davis DATE 7/18/2023 7/18/2023 7/18/2023 8/

U.S. NUCLEAR REGULATORY COMMISSION Region II Docket Numbers: 5200026 License Numbers: NPF-92 Report Numbers: 05200026/2023007 Licensee: Southern Nuclear Operating Company, Inc Facility: Vogtle Unit 4 Combined License (COL)

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 J. England, Senior Construction Inspector, DCO C. Even, Senior Construction Inspector, DCO B. Griman, Construction Inspector, DCO L. Jones, Senior Reactor Inspector, Division of Reactor Safety (DRS)

B. Kemker, Senior Resident Inspector, DCO R. Mathis, Test Inspector, DCO J. Parent, Resident Inspector, DCO R. Patel, Senior Construction Inspector, DCO R. Patterson, Senior Physical Security Inspector, DRS M. Riley, Senior Project Engineer, Division of Reactor Project (DRP)

D. Strickland, Reactor Inspector, DRS J. Bream, Senior Security Risk Analyst, Nuclear Security and Incident Response Approved by: Bradley J. Davis, Chief Construction Inspection Branch 2 Division of Construction Oversight Enclosure

SUMMARY

OF FINDINGS Inspection Report (IR) 05200026/2023007; April 1 - June 30, 2023; Vogtle Unit 4 COL, initial test program and operational programs integrated inspection report.

This report covers a three-month period of announced inspections of Inspections, Tests, Analysis, and Inspection Criteria (ITAAC), preoperational test program, startup test program, and operational program inspections by resident and regional inspectors. Two findings were determined to be of very low safety significance (Green) by the inspectors. The significance of most findings are indicated by their color (Green, White, Yellow, or Red), using Inspection Manual Chapter (IMC) 2519, Construction Significance Determination Process. Cross-cutting aspects are determined using IMC 0613, Appendix F, Construction Cross-Cutting Areas and Aspects.

All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy and the temporary enforcement guidance outlined in enforcement guidance memorandum 11-006. The NRCs program for overseeing the safe construction of commercial nuclear power reactors is described in IMC 2506, Construction Reactor Oversight Process General Guidance and Basis Document.

A. NRC-Identified and Self Revealed Findings NRC inspectors identified a non-cited violation (NCV) of 10 CFR 73.55(b)(4) for the licensees failure to adequately analyze and identify site-specific conditions, including target sets, that may affect the specific measures needed to implement the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 73.55 and account for these conditions in the design of the physical security protection program. Specifically, the licensee failed to analyze target set locations as required by site procedures. The licensee documented the issue in its corrective action program (CAP) as 50177317.

The inspectors determined the performance deficiency was more than minor because it was associated with the Contingency Response attribute of the Safeguards Programs cornerstone and adversely affected the cornerstone objective to provide assurance that the licensees security programs use a defense-in-depth approach and can protect against the design basis threat of radiological sabotage from internal and external threats. Specifically, the licensees target sets did not account for a specific action in an alternate location. The inspectors assessed the significance of the finding using IMC 2519 Construction Oversite Process Appendix A, Section 4, Step 1, and determined that finding was related to the development and implementation of a security program and should be screened against the appropriate Baseline Security SDP in IMC 0609. Per IMC 0609, Appendix E, Part I, Baseline Security SDP for Power Reactors the issue was determined to be Green. The inspectors determined the finding had a cross-cutting aspect of H.7, Documentation, in the area of Human Performance. (2P02)

B. Licensee-Identified Violations None 2

REPORT DETAILS Summary of Plant Construction Status During this report period for Unit 4, the licensee completed various activities to satisfy aspects of the Vogtle Unit 4 initial test program. The licensee completed hot functional testing activities which included testing the reactor coolant system (RCS), residual heat removal system, passive core cooling system (PXS), passive containment cooling water storage tank, and inspection of reactor internals.

The licensee performed preoperational and component tests of various structures, systems, and components and their control systems, e.g., protection and safety monitoring system (PMS) and PLS. Class 1E direct current and uninterruptible power supply system and electrical distribution system testing was performed to verify the functional capability of those systems to support electrical loads during normal and off-normal conditions. Preoperational testing of safety-related valves was performed for the RCS and PXS, and containment system isolation valves.

1. CONSTRUCTION REACTOR SAFETY Cornerstones: Design/Engineering, Procurement/Fabrication, Construction/Installation, Inspection/Testing IMC 2503, Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) - Related Work Inspections 1A01 (Unit 4) ITAAC Number 2.1.02.08b (30) / Family 06D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.08b (30). The inspectors used the following NRC inspection procedure (IP)/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the reactor coolant pump coastdown provided reactor coolant system flows greater than or equal to the design requirements. The test was observed to verify if it satisfied the applicable quality and technical requirements of the Updated Final Safety Analysis Report (UFSAR) and the ITAAC.

4-RCS-ITPP-506, TPC for Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional, Version (Ver.) 2.0 3

The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the reactor coolant pump coastdown provided reactor coolant system flows greater than or equal to the design requirements. The ITAAC technical report and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-RCS-T2C-5063, Vogtle Unit 4 RCS Flow Coastdown Preoperational Testing Results Validation, Revision (Rev.) 0

b. Findings No findings were identified.

1A02 (Unit 4) ITAAC Number 2.1.02.09a (41) / Family 14D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.09a (41). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensee's performance of the following procedure to verify if the calculated post-fuel load RCS flow rate is > or = 301,670 gallons per minute. The inspectors observed the test to verify if it met the quality and technical requirements of the UFSAR and ITAAC.

4-RCS-ITPP-506, Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional, Ver. 2 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the RCS flow rate was greater than or equal to 301,670 gallons per minute with all four reactor coolant pumps running with the RCS at normal operating temperature and pressure. The ITAAC test results reports, and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-RCS-ITR-800041, Unit 4 Recorded Results of RCS Flow Measurement Test: ITAAC 2.1.02.09a, Rev. 0

b. Findings No findings were identified.

1A03 (Unit 4) ITAAC Number 2.1.02.11a.i (46) / Family 10C 4

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.11a.i (46). The inspectors used the following NRC IP/section to perform this inspection:

65001.C-02.02-Construction Test Observation 65001.C-02.03-Construction Test Record Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the automatic depressurization system stage 4 squib valves received a signal at the valve electrical leads that was capable of actuating the valve from the main control room. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the licensee's test results of the following completion package to verify if the automatic depressurization system stage 4 squib valves received a signal at the valve electrical leads that was capable of actuating the valve from the main control room. The ITAAC test results report and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

2.1.02.11a.i-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings No findings were identified.

1A04 (Unit 4) ITAAC Number 2.1.02.11a.ii (47) / Family 10C

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.11a.ii (47). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to review the following licensee's test results to verify if remotely operated valves performed their active safety function after receiving a signal from the PMS and opened within the required stoke times. The test package was reviewed to verify if the test results satisfied the 5

applicable quality and technical requirements of the UFSAR and the ITAAC.

2.1.02.11a.ii-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings No findings were identified.

1A05 (Unit 4) ITAAC Number 2.1.02.11b.i (48) / Family 10C

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.11b.i (48). The inspectors used the following NRC IP/section to perform this inspection:

65001.C-02.02-Construction Test Observation 65001.C-02.03-Construction Test Record Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the stage 4 automatic depressurization system squib valves received a signal at the valve electrical leads that was capable of actuating the squib valve. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 The inspector used the appropriate portions of the IP to review the following licensee's test results to verify if the stage 4 automatic depressurization system squib valves received a signal at the valve electrical leads that was capable of actuating the squib valve. The ITAAC testing completion package and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

2.1.02.11b.i-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings No findings were identified.

1A06 (Unit 4) ITAAC Number 2.1.02.12a.iii (55) / Family 07D

a. Inspection Scope 6

The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.02.12a.iii (55). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to observe the licensee's performance of the following procedure to verify if the stage 1 and stage 3 automatic depressurization valves changed position under preoperational test conditions. The test was observed to verify if the test satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PXS-ITPP-505, ADS Stage 1-3 MOV Dynamic Test, Ver. 1 The inspector used the appropriate portions of the IP to review the licensee's test results to verify if each stage 1-3 automatic depressurization valve changed position under preoperational test conditions. The ITAAC technical report and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PXS-ITR-800055, Unit 4 Recorded Results of ADS Stages 1-3 MOV Dynamic Test: ITAAC 2.1.02.12a.iii, Rev. 0

b. Findings No findings were identified.

1A07 (Unit 4) ITAAC Number 2.1.03.07.i (78) / Family 05D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.1.03.07.i (78). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the reactor internals withstood the effects of flow induced vibration during hot functional testing. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

WDI-PJF-1324185-EPP-001, Vogtle Unit 4 AP1000, Reactor Vessel Comprehensive Vibration Assessment Examination (CVAP) Program Plan, Rev. 01

b. Findings 7

No findings were identified.

1A08 (Unit 4) ITAAC Number 2.2.01.09 (110) / Family 10A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.09 (110). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the containment isolation valves listed in Table 2.2.1-1 of Appendix C in the Vogtle Unit 4 Combined License could be operated from the main control room to perform their active safety function. The ITAAC technical report and selected references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-CNS-ITR-800110, Unit 4 Inspection Results of: ITAAC 2.2.01.09 (Item 9),

Rev. 0 SV4-CNS-ITR-801110, Unit 4 Inspection Results of: ITAAC 2.2.01.09 (Item 10.a), Rev. 0 SV4-CNS-ITR-802110, Unit 4 Testing Results of Containment Isolation Valves:

ITAAC 2.2.01.09 (Item 10.b), Rev. 0

b. Findings No findings were identified.

1A09 (Unit 4) ITAAC Number 2.2.01.11a.iii (116) / Family 07D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.11a.iii (116). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to review the following licensee's test results to verify if the containment isolation motor operated valves listed in Table 2.2.1-1 of Appendix C in the Vogtle Unit 4 Combined License changed position under preoperational test conditions. The ITAAC testing completion package and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

8

2.2.01.11a.iii-U4-CP, Completion Package for Unit 4 ITAAC 2.2.01.11a.iii

[Index Number 116], Rev. 0

b. Findings No findings were identified.

1A10 (Unit 4) ITAAC Number 2.2.01.11a.iv (117) / Family 07D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.01.11a.iv (117). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Results Review The inspectors used the appropriate portions of the IP to observe the licensee's performance of the following procedures used to verify if check valves 4-VWS-V062 (containment supply containment isolation check valve) and 4-VFS-V803A (containment vacuum relief containment isolation check valve) performed their safety-related function to change position. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-VFS-OTS-17-001, Containment Air Filtration System Vacuum Relief Valve Test and Check Valve Exercise, Ver. 2.0 4-VWS-OTS-10-002, Central Chilled Water System Check Valve Exercise, Ver. 1.1 The inspectors used the appropriate portions of the IP to review the licensee's test results that verified that the check valves listed in Table 2.2.1-1 changed position under preoperational test pressure, temperature and fluid flow conditions required to perform their active safety function.

The ITAAC test results reports, and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-CNS-ITR-800117, Unit 4 Recorded Results of SFS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 SV4-CNS-ITR-801117, Unit 4 Recorded Results of CCS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 SV4-CNS-ITR-802117, Unit 4 Recorded Results of CAS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 SV4-CNS-ITR-803117, Unit 4 Recorded Results of DWS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 SV4-CNS-ITR-804117, Unit 4 Recorded Results of FPS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 9

SV4-CNS-ITR-805117, Unit 4 Recorded Results of VFS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0 SV4-CNS-ITR-806117, Unit 4 Recorded Results of VWS Check Valves Position: ITAAC 2.2.01.11a.iv, Rev. 0

b. Findings No findings were identified.

1A11 (Unit 4) ITAAC Number 2.2.02.07b.i (138) / Family 06D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.02.07b.i (138). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if when water in the passive containment cooling water storage tank uncovered the standpipes at varying levels, the water delivered by one of the three parallel flow paths to the containment shell provided coverage measured between elevation 266' and the spring line that was equal to or greater than the required coverage for that corresponding water level. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the water flow rate from the passive containment cooling water storage tank to the containment shell provided coverage measured at any elevation between elevation 266 and the spring line was equal to or greater than the required coverages. The ITAAC test results reports, and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PCS-ITR-804138, Unit 4 Passive Containment Cooling System Testing:

ITAAC 2.2.02.07b.i, Item 7b.i, Rev. 0

b. Findings No findings were identified.

1A12 (Unit 4) ITAAC Number 2.2.03.08b.01 (175) / Family 06D 10

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.08b.01 (175). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to observe the licensee's performance of the following procedure used to verify if the passive residual heat removal heat exchanger (PRHR HX) heat transfer rate with the design basis number of PRHR HX tubes plugged was = 8.46 x 107 Btu/hr with 250°F hot leg temperature and an initial in-containment refueling water storage tank temperature of 80°F. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PXS-ITPP-504, Passive Core Cooling System Hot Functional Test, Ver. 1 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the passive residual heat removal heat exchanger (PRHR HX) heat transfer rate with the design basis number of PRHR HX tubes plugged was = 8.46 x 107 Btu/hr with 250°F hot leg temperature and an initial in-containment refueling water storage tank temperature of 80°F. The ITAAC test results report and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PXS-T2R-011, Vogtle Unit 4 PXS Hot Functional Test Results Validation for PRHR Performance Summary Report, Rev. 0

b. Findings No findings were identified.

1A13 (Unit 4) ITAAC Number 2.2.03.10 (206) / Family 10A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.10 (206). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the remotely operated valves (other than squib valves) identified in Table 2.2.3-1 in Appendix C of the Vogtle Unit 4 Combined License performed the 11

active function identified in the table after a signal was input from the PMS, that the PXS isolation valves PXS-V014A/B, V015A/B, V108A/B opened within 20 seconds, and that the valves identified in Table 2.2.3-1 assumed the indicated loss of motive power position after a loss of motive power. The ITAAC test results reports, and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PXS-ITR-802206, Unit 4 Inspection Results of: ITAAC 2.2.03.10 (Item 11.b) NRC Index Number:206, Rev. 0 SV4-PXS-ITR-802206, Unit 4 Recorded Results of Remotely Operated PXS Valves Response to Loss of Motive Power; ITAAC 2.2.03.10 (Item 12.b), Rev.

0

b. Findings No findings were identified.

1A14 (Unit 4) ITAAC Number 2.2.03.11b.i (209) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.03.11b.i (209). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if each squib valve received a signal at the valve electrical leads that was capable of actuating the squib valve after a signal was input to the PMS. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the following licensee's test results to verify if the containment recirculation and in-containment refueling water storage tank injection squib valves received a signal at the valve electrical leads that was capable of actuating the squib valve after a signal was input to the PMS. The ITAAC testing results report and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

2.2.03.11b.i-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings 12

No findings were identified.

1A15 (Unit 4) ITAAC Number 2.2.05.07a.i (265) / Family 12D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.05.07a.i (265). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing The inspectors used the appropriate portions of the IP to observe the licensee's performance of the following procedure used to verify if the main control room pressure boundary was pressurized to greater than or equal to 1/8-in. water gauge with respect to the surrounding area, and that air leakage into the main control room was less than or equal to 10 cubic feet per minute. The test was observed to verify if the it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-VES-ITPP-501, Main Control Room Emergency Habitability System PreOperational Test Procedure, Ver. 1

b. Findings No findings were identified.

1A16 (Unit 4) ITAAC Number 2.2.05.07c (270) / Family 12F

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.05.07c (270). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure that collected data needed to verify if the main control room temperature and humidity would remain within limits for reliable human

b. Findings No findings were identified.

13

1A17 (Unit 4) ITAAC Number 2.2.05.09c (877) / Family 08C

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.2.05.09c (877). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to observe the licensee's performance of the following procedure used to verify if the main control room load shed panels performed their active safety function after receiving a signal from the PMS. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PMS-OTS-18-001, Engineered Safeguards Actuation System 25-Month Actuation Device Test, 03/13/2023 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the main control room load shed panels performed their active safety function after receiving a signal from the PMS. The ITAAC technical report and listed references were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-VES-ITR-800877, Unit 4 Recorded Results of Main Control Room Load Shed: ITAAC 2.2.05.09c, NRC Index Number: 877, Rev. 0

b. Findings No findings were identified.

1A18 (Unit 4) ITAAC Number 2.5.02.06a.i (529) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.06a.i (529). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the reactor trip switchgear opened 14

after the test signal reached the specified limit. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR.

4-PMS-ITPP-504, PMS Reactor Trip Breakers, Ver. 1.1 The inspector used the appropriate portions of the IP to review the licensee's test results to verify if the reactor trip switchgear opened after the test signal reached the specified limit. The ITAAC completion package and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

2.5.02.06a.i-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings No findings were identified.

1A19 (Unit 4) ITAAC Number 2.5.02.06a.ii (530) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.06a.ii (530). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if PMS output signals to the reactor trip switchgear are generated after the test signal reaches the specified limit for each automatic reactor trip functions. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR.

4-PMS-ITPP-504, PMS Reactor Trip Breakers, Ver. 1.1 The inspectors used the appropriate portions of the IP to observe the licensees performance of the following component test procedures used to verify if appropriate PMS output signals were generated as the interlock conditions were changed. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

B-GEN-ITPCI-001, PMS Cabinets, Ver. 4.0 B-GEN-ITPCI-001-011, PMS Cabinets - Cabinet Diagnostics, Ver. 2.1 B-GEN-ITPCI-001-012, PMS Cabinets - Division Diagnostics, Ver. 1.0

b. Findings No findings were identified.

15

1A20 (Unit 4) ITAAC Number 2.5.02.06c.i (532) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.06c.i (532). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures to verify if the reactor trip switchgear opened after manual reactor trip controls were actuated. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PMS-ITPP-504, PMS Reactor trip Breakers, Ver. 1.1 4-DDS-ITPP-520, Data Display and Processing System Remote Shutdown Room Preoperational Test Procedure, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the reactor trip switchgear opened after manual reactor trip controls were actuated. The ITAAC test results report and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PMS-ITR-800532, Unit 4 PMS Provides Manual Initiation of Reactor Trip, ITAAC 2.5.02.06c.i, NRC Index Number: 532

b. Findings No findings were identified.

1A21 (Unit 4) ITAAC Number 2.5.02.08a.ii (540) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.08a.ii (540). The inspectors used the following NRC IP/sections to perform this inspection:

65001.C-02.02-Construction Test Observation 65001.C-02.03-Construction Test Record Review The inspectors used the appropriate portions of the IP to observe the licensees performance of the following component test procedures used to verify if plant 16

parameters listed in Table 2.5.2-5 with a "Yes" in the "Alert" column were used to generate visual alerts that identify challenges to critical safety functions, and that the visual alerts actuated in accordance with their correct logic and values. The tests were observed to verify if the test satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

B-GEN-ITPCI-001, PMS Cabinets, Ver. 4.0 B-GEN-ITPCI-001-011, PMS Cabinets - Cabinet Diagnostics, Ver. 2.1 B-GEN-ITPCI-001-012, PMS Cabinets - Division Diagnostics, Ver. 1.0 B-GEN-ITPCI-006, Main Control Room & Remote Shutdown Room, Ver. 4.0 The inspectors used appropriate portions of the IP to review the licensee's test results to verify if the plant parameters listed in Table 2.5.2-5 with a "Yes" in the "Alert" column were used to generate visual alerts that identify challenges to critical safety functions, and that the visual alerts actuated in accordance with their correct logic and values. The test results were reviewed to determine whether they satisfied the technical requirements of the UFSAR and ITAAC acceptance criteria.

ITAAC 2.5.02.08a.ii-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings No findings were identified.

1A22 (Unit 4) ITAAC Number 2.5.02.08b.ii (543) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.5.02.08b.ii (543). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used the appropriate portions of the IP to observe the licensees performance of the following component test procedures used to verify if actuation of each transfer switch resulted in an alarm in the main control room and the remote shutdown workstation, the activation of operator control capability from the remote shutdown workstation, and the deactivation of operator control capability from the main control room for the associated safety-related division and non-safety related control capability. The tests were observed to verify if the test satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

B-GEN-ITPCI-001, PMS Cabinets, Version 4.0 B-GEN-ITPCI-001-011, PMS Cabinets - Cabinet Diagnostics, Version 2.1 17

B-GEN-ITPCI-001-012, PMS Cabinets - Division Diagnostics, Version 1.0 B-GEN-ITPCI-006, Main Control Room & Remote Shutdown Room, Version 4.0 The inspectors used appropriate portions of the IP to review the licensee's test results to verify if the actuation of each transfer switch resulted in an alarm in the main control room and the remote shutdown workstation, the activation of operator control capability from the remote shutdown workstation, and the deactivation of operator control capability from the main control room for the associated safety-related division and non-safety related control capability. The test results were reviewed to determine whether they satisfied the technical requirements of the UFSAR and ITAAC acceptance criteria.

SV4-PMS-ITR-800543, Unit 4 PMS Transfer of Control Capability from the MCR to the RSW: ITAAC 2.5.02.08b.ii [NRC Index Number: 543], Rev. 0

b. Findings No findings were identified.

1A23 (Unit 4) ITAAC Number 2.5.02.09d (548) / Family 10D

a. Inspection Scope The inspectors performed a direct inspection of testing activities associated with ITAAC Number 2.5.02.09d (548). The inspectors used the following NRC IP/sections to perform this inspection:

65001.C-02.02-Construction Test Observation 65001.C-02.03-Construction Test Record Review The inspectors used the appropriate portions of the IP to observe the licensees performance of the following component test procedures used to verify if appropriate PMS output signals were generated as the interlock conditions were changed. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

B-GEN-ITPCI-001, PMS Cabinets, Ver. 4.0 B-GEN-ITPCI-001-011, PMS Cabinets - Cabinet Diagnostics, Ver. 2.1 B-GEN-ITPCI-001-012, PMS Cabinets - Division Diagnostics, Ver. 1.0 The inspectors used appropriate portions of the IP to review the licensee's test results to verify if appropriate PMS output signals were generated as the interlock conditions were changed. The test results were reviewed to determine whether they satisfied the technical requirements of the UFSAR and ITAAC acceptance criteria.

ITAAC 2.5.02.09d-U4-CP, ITAAC Completion Package, Rev. 0

b. Findings 18

No findings were identified.

1A24 (Unit 4) ITAAC Number 2.6.03.04c (603) / Family 08D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.03.04c (603). The inspectors used the following NRC IP/section to perform this inspection:

65001.D-02.02-Test Witnessing The inspectors used the appropriate portions of the IP to observe the Class 1E direct current and uninterruptable power supply system preoperational tests to verify if the:

1) Division B & C 72-hour battery terminal voltage was greater than or equal to 210 V after a period of no less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with an equivalent load that equaled or exceeded the battery bank design duty cycle capacity,

2) Division B 72-hour battery charger provided an output current of at least 150 A with an output voltage in the range of 210 to 280 V, and

3) Division B & C 72-hour inverter supplied a line-to-line output voltage of 208 +/- 2% V at a frequency of 60 +/- 0.5% Hz.

The inspectors observed the test to verify if it met the technical and quality requirements of the UFSAR and ITAAC.

4-IDS-ITPP-506, IDSB Class 1E DC and UPS Preoperational Test, Ver. 1.0 4-IDS-ITPP-507, IDSC Class 1E DC and UPS Preoperational Test, Ver. 1.0 B-GEN-ITPCE-009, Battery Charger Load Test, Ver. 3 4-GEN-ITPCE-011, Class 1E DC Inverter Capacity Test, Static Transfer Switch Test, And Regulating Transformer Capacity Test, Ver. 1

b. Findings No findings were identified.

1A25 (Unit 4) ITAAC Number 2.6.03.04i (609) / Family 08D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.03.04i (609). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Results Revie 19

The inspectors used the appropriate portions of the IP to observe testing to verify if IDS batteries with the battery terminal voltage at 210Vdc could provide a voltage greater than or equal to each motor operated valves' minimum designed voltage while the valves were being stroked. The inspectors observed the test to verify if it met the technical and quality requirements of the UFSAR and the ITAAC.

4-IDS-ITPP-503, Class 1E DC and UPS System MOV Voltage Test, Ver. 1.0 The inspectors used the appropriate portions of the IP to review test results to verify if the IDS batteries with the battery terminal voltage at 210Vdc could provide a voltage greater than or equal to each motor operated valves' minimum designed voltage while the valves were being stroked. The inspectors reviewed the test results to verify if they met the technical and quality requirements of the UFSAR and ITAAC.

ND-23-0447, Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.6.03.04i [Index Number 609], 06/17/2023

b. Findings No findings were identified.

1A26 (Unit 4) ITAAC Number 2.6.09.05a (644) / Family 17D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.09.05a (644). The inspectors used the following NRC IP to perform this inspection:

IP 65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures used to test if (a) security alarm annunciation and video assessment information is displayed concurrently in the central alarm station and secondary alarm station, and the video image recording with real time playback capability provides assessment of activities before and after alarm annunciation within the perimeter barrier, and (b) the intrusion detection system concurrently provides visual displays and audible annunciation of alarms in both the central and secondary alarm stations. Specifically, the tests were observed and test acceptance documents reviewed to verify if the tests met the technical and quality requirements of the Vogtle 4 security plan, and the ITAAC.

4-SES-ITAAC 644-FEP05- Intrusion Detection/Video Assessment FEP05-Revision 1.1 4-SES-ITAAC 644-FEP06- Intrusion Detection/Video Assessment FEP06-Revision 1.0 4-SES-ITAAC 644-FEP07- Intrusion Detection/Video Assessment FEP07-Revision 1.1 20

4-SES-ITAAC 644-FEP08- Intrusion Detection/Video Assessment FEP08-Revision 1.1 4-SES-ITAAC 644-FEP09- Intrusion Detection/Video Assessment FEP09-Revision 1.1 4-SES-ITAAC 644-FEP10- Intrusion Detection/Video Assessment FEP10-Revision 1.1 4-SES-ITAAC 644-FEP11- Intrusion Detection/Video Assessment FEP11-Revision 1.1

b. Findings No findings were identified.

1A27 (Unit 4) ITAAC Number 2.6.09.06 (647) / Family 17A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.09.06 (647). The inspectors used the following NRC IP to perform this inspection:

IP 65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to verify if the vehicle barrier system will protect against the design basis threat (DBT) vehicle bombs based upon the stand-off distance of the system. Specifically, the test procedures, acceptance testing documents, vehicle barrier system analysis, blast analysis and observations of the vehicle barrier system were reviewed to verify if they satisfied the applicable quality and technical requirements of the manufacturers specifications, Vogtle 4 security plan, and the ITAAC.

b. Findings No findings were identified.

1A28 (Unit 4) ITAAC Number 2.6.09.08 (650) / Family 17C

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.09.08 (650). The inspectors used the following NRC IP to perform this inspection:

IP 65001.17-Inspection of ITAAC-related structures, systems, and components 21

The inspectors used appropriate portions of the IP to determine if the illumination in isolation zones and exterior areas within the protected area was .02-foot candles measured horizontally at ground level or, alternatively, sufficient to permit observation.

Specifically, the inspectors reviewed acceptance testing documents and conducted walkdowns during testing of the Vogtle 4 lighting to verify if the tests satisfied the technical and quality requirements of the manufacturers specifications, Vogtle 4 security plan, and the ITAAC.

b. Findings No findings were identified.

1A29 (Unit 4) ITAAC Number 2.6.09.15a (655) / Family 17D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 2.6.09.15a (655). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors reviewed appropriate portions of the IP to determine if (a) a report existed and concluded that security alarm devices, including transmission lines to annunciators, were tamper indicating and self-checking (e.g., an automatic indication is provided when failure of the alarm system or a component occurs, or when the system is on standby power) and that alarm annunciation indicated the type of alarm (e.g., intrusion alarms and emergency exit alarms) and location, and (b) a report existed and concluded that equipment was capable of recording each onsite security alarm annunciation, including the location of the alarm, false alarm, alarm check, and tamper indication; and the type of alarm, location, alarm circuit, date, and time.

Specifically, the inspectors reviewed acceptance testing documents and conducted intrusion detection system testing to verify if the tests met the quality and technical requirements of the Vogtle 4 security plan, and the ITAAC.

4-SES-ITAAC 655-FEP-U4 FEP Alarm & Circuit Supervision Test- Revision 1 4-SES-ITAAC 655-4SCP02, 4SCP02 Alarm & Circuit Supervision Test-Revision 1 4-SES-ITAAC 655-4SCP03, 4SCP03 Alarm & Circuit Supervision Test-Revision 1 4-SES-ITAAC 655-4SCP04, 4SCP04 Alarm & Circuit Supervision Test-Revision 1 4-SES-ITAAC 655-4SCP05, 4SCP05 Alarm & Circuit Supervision Test-Revision 1 4-SES-ITAAC 655-4SCP06, 4SCP06 Alarm & Circuit Supervision Test-Revision 1

b. Findings 22

No findings were identified.

1A30 (Unit 4) ITAAC Number 3.3.00.10.i (815) / Family 06D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number 3.3.00.10.i (815). The inspectors used the following NRC IP/sections to perform this inspection:

65001.D-02.02-Test Witnessing 65001.D-02.03-Test Results Review The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the total water flow from the PCCWST leak chase collection system did not exceed 10 gal/hr. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if the total water flow from the PCCWST leak chase collection system did not exceed 10 gal/hr. The ITAAC test results report and listed references were reviewed to verify that the test results satisfied the applicable quality and technical requirements of the UFSAR and the ITAAC.

SV4-PCS-ITR-800815, Unit 4 Test Results for PCCWST Leakage into the Leak Chase Collection System: ITACC 3.3.00.10.i, Rev. 0

b. Findings No findings were identified.

1A31 (Unit 4) ITAAC Number C.2.6.09.02 (659) / Family 17A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.02 (659). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components 23

The inspectors used appropriate portions of the IP to observe the licensees performance of the following walkdown used to test if the physical barriers at the perimeter of the protected area are separated from any other barriers designated as a vital area barrier. Specifically, the walkdowns were observed and acceptance documents were reviewed to verify if the physical barriers at the perimeter of the protected area were separated from any other barriers designated as a vital area barrier and if they satisfied the manufactures requirements, Vogtle 4 security plan, and the ITAAC.

SV4-SES-ITR-800659 - Unit 4 659 Walkdown Inspection- ITAAC C.2.6.09.04-Revision 0

b. Findings No findings were identified.

1A32 (Unit 4) ITAAC Number C.2.6.09.03a (660) / Family 17A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.03a (660). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to review acceptance testing documents and determine if the isolation zones existed in outdoor areas adjacent to the physical barrier at the perimeter of the protected area that allowed 20 feet of observation and assessment of the activities of people on either side of the barrier.

Specifically, walkdowns were performed and test acceptance documents were reviewed to verify if they satisfied the applicable quality and technical requirements of the manufactures requirements, Vogtle 4 security plan, and the ITAAC.

SV4-SES-ITR-800660, Unit 4 ITAAC 660 Walkdown Inspection: ITAAC C.2.6.09.03a, Rev 0

b. Findings No findings were identified.

1A33 (Unit 4) ITAAC Number C.2.6.09.03b (661) / Family 17A

a. Inspection Scope 24

The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.03b (661). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures used to test if the isolation zones were equipped with intrusion detection equipment that provided the capability to detect and assess unauthorized persons. That the intrusion detection and assessment equipment at the protected area perimeter (a) detected penetration or attempted penetration of the protected area barrier and concurrently alarmed in the central alarm station and secondary alarm station and (b) remained operable from an uninterruptable power supply in the event of the loss of normal power. The tests were observed and the acceptance documents were reviewed to verify if the tests me the quality and technical requirements of the Vogtle 4 security plan, and the ITAAC.

4-SES-ITAAC 644-FEP05-Intrusion Detection/Video Assessment-FEP05-Revision 1.1 4-SES-ITAAC 644-FEP06-Intrusion Detection/Video Assessment-FEP06-Revision 1 4-SES-ITAAC 644-FEP07-Intrusion Detection/Video Assessment-FEP07-Revision 1.1 4-SES-ITAAC 644-FEP08-Intrusion Detection/Video Assessment-FEP08-Revision 1.1 4-SES-ITAAC 644-FEP09-Intrusion Detection/Video Assessment-FEP09-Revision 1.1 4-SES-ITAAC 644-FEP10-Intrusion Detection/Video Assessment-FEP10-Revision 1.1 4-SES-ITAAC 644-FEP11-Intrusion Detection/Video Assessment-FEP11-Revision 1.1

b. Findings No findings were identified.

1A34 (Unit 4) ITAAC Number C.2.6.09.05a (664) / Family 17A

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.05a (664). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and component 25

The inspectors used appropriate portions of the IP to determine if the access control points for the protected area: a) were configured to control personnel and vehicle access and b) included detection equipment that is capable of detecting firearms, incendiary devices, and explosives at the protected area personnel access point. The primary personnel access portal is common to both Unit 3 and 4 and was inspected with Unit 3, the results were documented in SV3-SES-ITR-800664. Specifically, the walkdowns were observed and test acceptance documents were reviewed to verify if they satisfied the applicable quality and technical requirements of the manufactures requirements, Vogtle 4 security plan, and the ITAAC.

b. Findings No findings were identified.

1A35 (Unit 4) ITAAC Number C.2.6.09.06 (666) / Family 17D

a. Inspection Scope The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.06 (666). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures used to test if an access control system with numbered picture badges was installed for use by individuals who were authorized access to protected areas and vital areas without escort and that the access control system required a numbered picture badge with the right access level to enter the protected and vital areas. The tests were observed, and test acceptance documents were reviewed to verify if the tests met the technical and quality requirements of the Vogtle 4 security plan, and the ITAAC.

SV4-SES-ITR-800666 - Unit 4 ITAAC 666 Access Authorization Test: ITAAC C.2.6.09.06 Rev 0 SVB-SES-ITR-800666- Unit 3 ITAAC 666 ITAAC 666 Access Authorization Test C.6.09.06 Rev 0 4-SES-ITAAC 666, WO: SNC 1476070 Access Control System Test Version 1.0

b. Findings No findings were identified.

1A36 (Unit 4) ITAAC Number C.2.6.09.09 (670) / Family 17D

a. Inspection Scope 26

The inspectors performed a direct inspection of construction activities associated with ITAAC Number C.2.6.09.09 (670). The inspectors used the following NRC IP to perform this inspection:

65001.17-Inspection of ITAAC-related structures, systems, and components The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures used to test if emergency exits through the protected area perimeter were alarmed and secured by locking devices that allow prompt egress during an emergency and the emergency exits through the vital were locked, alarmed, and equipped with a crash bar to allow for emergency egress.

Specifically, the tests were observed, and test acceptance documents were reviewed to verify if the tests met the quality and technical requirements of the Vogtle 4 security plan, and the ITAAC.

SV4-SES-ITR-800670 - Unit 4 670 Access Authorization Test- ITAAC C.2.6.09.09.

SV4-SES ITR-800670- Protected Area Perimeter and Vital Area Boundary Emergency Exit Test, Rev 0 (SRI) 4 SES-ITAAC-670-VA-INTRO 1, WO SNC 1476419 VA Emergency Exit Alarm Test. Version 1.0

b. Findings No findings were identified.

IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 1P01 Pre-operational Testing 70702-02.04 - Test Witnessing

a. Inspection Scope The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedures for performing data collection and measurements to monitor thermal expansion, dynamic effects, and vibration of piping and components during hot functional testing. The tests were observed to verify if they satisfied the applicable quality and technical requirements of the UFSAR.

4-GEN-ITPP-507, Thermal Expansion, Sections 4.1-4.3, Ver. 1 27

4-GEN-ITPP-509, Reactor Coolant System Dynamic Effects and Vibration Testing, Ver. 1 4-GEN-ITPP-511, Passive Core Cooling System Dynamic Effects and Vibration, Ver. 1 4-GEN-ITPP-512, Chemical and Volume Control System Dynamic Effects and Vibration Testing Ver. 1 4-GEN-ITPP-515, Steam Generator System Dynamic Effects and Vibration Testing Ver. 1

b. Findings No findings were identified.

1P02 Pre-operational Testing 70702-02.05 - Test Results Review

a. Inspection Scope The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if proper calibration and operation of the following safety-related instrumentation, controls, actuation signals and interlocks was performed. The test packages were reviewed to verify if the test results satisfied the applicable technical and quality requirements of the UFSAR.

SV4-RCS-T0W-1192329, Perform Component Test on SV4-RCS-JE-FT101B and FT102B, Rev. 0 SV4-RCS-T0W-1192347, Perform Component Test on SV4-RCS-JE-LT160A &

LT160B, Rev. 0 SV4-RCS-T0W-1192358, Perform Component Testing on RCS WR Pressure Transmitters SV4-RCS-JE-PT140A per B-GENITPCI-019-363, Rev. 0 SV4-RCS-T0W-1192380, Perform Component Testing on SV4-RCS-JE-ST284, Rev. 1 SV4-RCS-T0W-1245189, Perform ITAAC PMS CIM SV4-RCS-PL-V150B Component Test, Rev. 0 SV4-RCS-T0W-1261883, Perform component testing (sensor input to PMS), IA W B-GEN-ITPCI-019-407 for SV 4-RCS-JE-TE211B, Rev. 0 SV4-RCS-T0W-1261769, Perform Component Testing on Pressurizer Pressure Transmitter SV4-RCS-JE-PT191D, Rev. 0 SV 4-RCS-T0W-1261760, Perform sensor calibration for SV4-RCS-JE-LT195D using B-GEN-ITPCI-019-362, Rev. 0

b. Findings No findings were identified.

1P03 Pre-operational Testing 28

70702-02.05 - Test Results Review

a. Inspection Scope The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if proper calibration and operation of the safety-related instrumentation, controls, actuation signals and interlocks was performed. The test packages were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR.

SV4-PXS-T0W-1191422, Perform Component Testing on CMT A Upper NR Level Transmitters SV4-PXS-JE-LT011A and SV4- PXS-JE-LT011C, Rev. 0 SV4-PXS-T0W-1191429, Perform Component testing on CMT B Lower NR Level transmitters 4-PXS-JE-LT014B and 4-PXS-JELT014D, Rev. 0 SV4-PXS-T0W-1191434, Perform Component Testing on 4-PXS-LT047, Rev.

0

b. Findings No findings were identified.

1P04 Pre-operational Testing 70702-02.04 - Test Witnessing 70702-02.05 - Test Results Review

a. Inspection Scope The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure for demonstrating proper PCS system flow rates by draining the passive containment cooling system water storage tank for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR.

4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 The inspectors used the appropriate portions of the IP to review the licensee's test results to verify if PCS system flow rates were consistent with the design basis analyses by draining the passive containment cooling system water storage tank for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The test packages were reviewed to verify if the test results satisfied the applicable quality and technical requirements of the UFSAR.

SV4-PCS-T0W-1199655, (ITAAC) 4-PCS-ITPP-502 PCCWST Preoperational Test, Rev. 0

b. Findings 29

No findings were identified.

1P05 Pre-operational Testing 70702-02.04 - Test Witnessing

a. Inspection Scope The inspectors used appropriate portions of the IP to observe the licensees performance of the following procedure to verify if the core makeup tank (CMT) cold leg balance line piping water temperature at various locations was recorded to verify if the water in the line was sufficiently heated to initiate recirculation flow through the CMTs. The test was observed to verify if it satisfied the applicable quality and technical requirements of the UFSAR.

4-PXS-ITPP-504, Passive Core Cooling System Hot Functional Test, Sections 4.3, Ver. 1.0

b. Findings No findings were identified.

2. SAFEGUARDS PROGRAMS Cornerstones: Security Programs for Construction Inspection and Operations IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 2P01 Security (operational)

a. Inspection Scope The inspectors reviewed aspects of the security plan to verify if the licensee had developed and was prepared to implement securitys access control program. The inspectors performed four samples of access control walkdowns to verify if the licensee had established measures to observe all vehicle search functions (OCA and PA) in a manner that enabled the initiation of a response, OCA vehicle access control points were equipped with video surveillance equipment that was monitored by an individual capable of initiating a response, the licensee had established access control portals (personnel, material, and vehicle) outside of, or concurrent with, the physical barrier system (OCA, PA, and VA) through which it controls access, and the licensee had established access control portals with locking devices, intrusion detection equipment, and surveillance equipment consistent with the intended function in accordance with the security plan.

30

The inspectors reviewed the licensee's security procedures, internal and perimeter intrusion detection systems, alarm stations and communications systems, vehicle and physical barriers, weapons maintenance program, and the evaluation program to determine whether the licensee had developed and was prepared to implement all aspects of securitys equipment performance, testing, and maintenance program.

b. Findings No findings were identified.

2P02 Security (operational)

a. Inspection Scope The inspectors completed 7 samples through interviews and plant walkdowns to verify the licensee had developed and was prepared to implement all aspects of the security target set development and maintenance program.

b. Findings Introduction NRC inspectors identified a non-cited violation (NCV) of 10 CFR 73.55(b)(4) for the licensees failure to adequately analyze and identify site-specific conditions, including target sets, that may affect the specific measures needed to implement the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 73.55 and account for these conditions in the design of the physical security protection program. Specifically, the licensee failed to analyze target set locations as required by site procedures.

Description Licensee procedures established the requirements, responsibilities, and administrative process for identification, analysis, revision, and maintenance of their target set program to meet the requirements in 10 CFR 73.55(b)(4) and 10 CFR 73.55(f).

In review of site procedures and calculations the inspectors identified an alternate location where a target set element could be compromised. The licensee concurred that the identified vulnerability existed.

The licensee documented the issue in its corrective action program (CAP) as 50177317.

31

Analysis The inspectors determined the performance deficiency was more than minor because it was associated with the Contingency Response attribute of the Safeguards Programs cornerstone and adversely affected the cornerstone objective to provide assurance that the licensees security programs use a defense-in-depth approach and can protect against the design basis threat of radiological sabotage from internal and external threats. Specifically, the licensees target sets did not account for a specific action in an alternate location.

The inspectors assessed the significance of the finding using IMC 2519 Construction Oversite Process Appendix A, Section 4, Step 1, and determined that finding was related to the development and implementation of a security program and should be screened against the appropriate Baseline Security SDP in IMC 0609. Per IMC 0609, Appendix E, Part I, Baseline Security SDP for Power Reactors the issue was determined to be Green.

The inspectors determined the finding had a cross-cutting aspect of H.7, Documentation, in the area of Human Performance. (2P02)

Enforcement 10 CFR 73.55(b)(4) states that the licensee shall analyze and identify site-specific conditions, including target sets, that may affect the specific measures needed to implement the requirements of this section and shall account for these conditions in the design of the physical protection program.

Contrary to the above, the licensee failed to adequately implement the requirements of 10 CFR 73.55(b)(4). Specifically, on June 15, 2023, the licensee failed to analyze the effects of adversary actions in an alternate location effecting target sets.

The licensee entered this issue into the CAP as CR 50177317. Because this violation was not repetitive or willful, was of very low safety significance (Green), and was entered into the licensees CAP, this violation is being treated as a NCV consistent with Section 2.3.2.a of the NRC Enforcement Policy (NCV 05200026/2023007-01, Failure to Analyze Target Set Locations).

3. OPERATIONAL READINESS Cornerstones: Operational Programs IMC 2504, Construction Inspection Program - Inspection of Construction and Operational Programs 3P01 Motor-Operated Valves

a. Inspection Scope The inspectors met with the Southern Nuclear Company program owner to verify that no changes were made to the Unit 4 program since the Unit 3 program inspection.

32

b. Findings No findings were identified.

3P02 Preservice Testing

a. Inspection Scope The inspectors met with the Southern Nuclear Company program owner to verify that no changes were made to the Unit 4 program since the Unit 3 program inspection.

b. Findings No findings were identified.

3P03 Reactor Vessel Material Surveillance IP 50054 - Reactor Vessel Material Surveillance Program

a. Inspection Scope The inspectors used appropriate portions of the IP to observe the license's performance of the following procedure to verify if the capsule brackets and vessel material were installed in accordance with design drawings. The inspectors observed these activities to verify if they met the technical and quality requirements of the reactor vessel material surveillance program.

4-RXS-ITPP-501, Pre- and Post-Hot Functional Test Inspection of Reactor Vessel Internals, Ver. 1.0

b. Findings No findings were identified.

4. OTHER INSPECTION RESULTS 4OA6 Meetings, Including Exit

.1 Exit Meeting.

On July 11, 2023, the inspectors presented the inspection results to Mr. G. Chick, Vogtle 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.

33

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 S. Leighty, Regulatory Affairs Manager W. Garrett, Licensing Manager T. Takats, Electrical Manager K. Roberts, ITAAC Manager J. Olsen, NI Supervisor D. Johnson, Maintenance Supervisor G. Bauer, Electrical Supervisor LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Type Status Description 05200026/2023007-01 NCV Open/Closed Failure to Analyze Target Set Locations LIST OF DOCUMENTS REVIEWED Section 1 Section 1A01 2.1.02.08b-U4-CP, ITAAC Completion Package, Rev. 0 SV4-RCS-T0W-1192131, Perform Pre-Op Test 4-RCS-ITPP-506, Rev. 0 4-RCS-ITPP-506, Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional, Ver. 2.0-01 SV4-RCS-ITR-800030, Unit 4 Recorded Results of RCS Flow Coastdown Measurement Test: ITAAC 2.1.02.08b, Rev. 0 SV4-RCS-T2C-5063, Vogtle Unit 4 RCS Flow Coastdown Preoperational Testing Results Validation, Rev. 0 WO# 1192131 Section 1A02 4-GEN-ITPP-517, Pre-Core Hot Functional Testing (HFT) Sequence Procedure, Ver. 1.0 2.1.02.09a-U4-CP, ITAAC Completion Package, Rev. 0 4-RCS-ITPP-506, Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional, Ver. 2.0-01 SV4-RCS-T0W-1192134, Perform RCP Cold and Hot Precore Hot Functional Test per procedure 4-RCS-ITPP-506, Rev. 0 34

SV4-RCS-T2R-5061, Vogtle Unit 4 Hot Functional Testing - Reactor Coolant System Flow Summary Report, Rev. 0 SV4-RCS-T2C-5061, Component, Hot Leg Elbow, and Cold Leg Bend Differential Pressure Flow Calculations from Vogtle Unit 4 Hot Functional Testing, Rev. 0 Technical Evaluation 60048951 WO# 1192134 Section 1A03 4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 SV4-RCS-ITR-800046, ITAAC Technical Report, Unit 4 Testing Results of RCS Squib Valve MCR Controls: ITAAC 2.1.02.11a.i, NRC Index Number: 46, Rev. 0 SV4-PMS-T0W-1199997, (ITAAC) Perform preop testing per 4-PMSITPP- 522, Squib Valve Controller Test, Rev. 0 SV4-RCS-T0W-1192630, RCS-PL-V004A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244663, RCS-PL-V004A-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244674, RCS-PL-V004B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244678, RCS-PL-V004B-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244730, RCS-PL-V004C-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244738, RCS-PL-V004C-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244767, RCS-PL-V004D-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244771, RCS-PL-V004D-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 WO # 1199997, 1192630, 1244663, 1244674, 1244678, 1244730, 1244738, 1244767 &

1244771 CR 50173418 Section 1A04 2.1.02.11a.ii[Item 11.aii]-U0-PRF, APP/SV3/SV4-PMST2R-009, Rev. 0 SV4-RCS-ITR-800047, Unit 4 Recorded Results of Remotely Operated RCS Valves Controlled by PMS Listed in Table 2.1.2-1 Perform Active Safety Function: ITAAC 2.1.02.11a.ii Item 11.a) and 11.b) NRC Index Number: 47, Rev. 0 SV4-RCS-ITR-801047, Unit 4 Recorded Results of Remotely Operated RCS Valves Response to Loss of Motive Power: ITAAC 2.1.02.11a.ii Item 12.b) NRC Index Number:

47, Rev. 0 V4-RCS-ITR-802047, Unit 4 Reactor Coolant System Safety-Related Displays Verification:

ITAAC 2.1.02.11a.ii Item 10 NRC Index Number: 47, Rev. 0 WO's:

1244621, Perform ITAAC PMS CIM SV4-RCS-PLV001A Component Test, Rev. 0 1244633, Perform ITAAC PMS CIM SV4-RCS-PLV001B Component Test, Rev. 0 1244640, Perform ITAAC PMS CIM SV4-RCS-PLV002A Component Test, Rev. 0 1244647, Perform ITAAC PMS CIM SV4-RCS-PLV002B Component Test, Rev. 0 1244648, Perform ITAAC PMS CIM SV4-RCS-PLV003A Component Test, Rev. 0 35

1244651, Perform ITAAC PMS CIM SV4-RCS-PLV003B Component Test, Rev. 0 1245023, Perform ITAAC PMS CIM SV4-RCS-PLV011A Component Test, Rev. 0 1245027, Perform ITAAC PMS CIM SV4-RCS-PLV011B Component Test, Rev. 0 1254028, Perform ITAAC PMS CIM SV4-RCS-PLV012A Component Test, Rev. 0 1245029, Perform ITAAC PMS CIM SV4-RCS-PLV012B Component Test, Rev. 0 1245033, Perform ITAAC PMS CIM SV4-RCS-PLV013A Component Test, Rev. 0 1245043, Perform ITAAC PMS CIM SV4-RCS-PLV013B Component Test, Rev. 0 1245120, Perform Plant PMS / PLS Interface Test for SV4-RCS-PL-V150A, Rev. 0 1245189, Perform ITAAC PMS CIM SV4-RCS-PLV150B Component Test, Rev. 0 1245204, Perform ITAAC PMS CIM SV4-RCS-PLV150C Component Test, Rev. 0 1245210, Perform ITAAC PMS CIM SV4-RCS-PLV150D Component Test, Rev. 0 Section 1A05 4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 SV4-RCS-ITR-800048, Unit 4 Testing Results of RCS Squib Valve: ITAAC 2.1.02.11b.i, NRC Index Number: 48, Rev. 1 SV4-PMS-T0W-1199997, (ITAAC) Perform preop testing per 4-PMSITPP- 522, Squib Valve Controller Test, Rev. 0 SV4-RCS-T0W-1192630, RCS-PL-V004A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244663, RCS-PL-V004A-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244674, RCS-PL-V004B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244678, RCS-PL-V004B-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244730, RCS-PL-V004C-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244738, RCS-PL-V004C-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244767, RCS-PL-V004D-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-RCS-T0W-1244771, RCS-PL-V004D-I2-A Component Test 2 & 2-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PV98-Z0-001, Pyrotechnic Actuator for ASME Boiler and Pressure Vessel Code,Section III Class 1 Squib Valves (PV70), Rev. 3 SV4-PV98-GNR-000001, AP1000 Nonconformance & Disposition Report, Rev. 0 WO# 800048, 1192630, 1199997, 1244663, 1244674,1244678, 1244730, 1244738, 1244767, 124477 CR# 50174684 CR# 50173418 Section 1A06 ND-23-0325, ITAAC Closure Notification on Completion of 2.1.02.12a.iii [Index Number 55],

05/11/2023 WO 1191262 Section 1A07 Documents:

36

SV4-CVAP-T2R-100, Vogtle Unit 4 Pre-Hot Functional Test Visual Report of AP1000 Reactor Vessel Internals, Rev. 0 WDI-SSP-1339, Visual Examination of Reactor Vessel and Internals for Vogtle Units 3 & 4 AP1000 (CVAP), Rev. 1 Procedures:

4-RXS-ITPP-501, Pre- and Post-Hot Functional Test Inspection of Reactor Vessel Internals, Version 1.0 Section 1A08 SV4-CAS-T0W-1189903, Perform Plant PMS / PLS Interface Test for SV4-CAS-PL-V014, Rev. 0 SV4-CCS-T0W-1190298, Perform Plant PMS / PLS Interface Test for SV4-CCS-PL-V200, Rev. 0 SV4-CCS-T0W-1242824, Perform Plant PMS / PLS Interface Test for SV4-CCS-PL-V207, Rev. 0 SV4-CCS-T0W-1242827, Perform Plant PMS / PLS Interface Test for SV4-CCS-PL-V208, Rev. 0 SV4-SFS-T0W-1191775, Perform Plant PMS / PLS Interface Test for SV4-SFS-PL-V034, Rev. 0 SV4-SFS-T0W-1191780, Perform Plant PMS / PLS Interface Test for SV4-SFS-PL-V035, Rev. 0 SV4-SFS-T0W-1288906, RE-PERFORM Plant PMS / PLS Interface Test for SV4-SFS-PL-V038, Rev. 0 SV4-VFS-T0W-1247640, Perform ITAAC PMS / PLS Interface Test for SV4-VFS-PL-V003, Rev. 0 SV4-VFS-T0W-1247641, Perform (ITAAC) PMS / PLS Interface Test for SV4-VFS-PL-V004-S1, Rev. 0 SV4-VFS-T0W-1291587, Perform Plant PMS / PLS Interface Test for SV4-VFS-PL-V009-S1, Rev. 0 SV4-VFS-T0W-1247664, Perform (ITAAC) Plant PMS / PLS Interface Test for SV4-VFS-PL-V010-S1 Component Test, Rev. 0 SV4-VFS-T0W-1203251, Perform Plant PMS / PLS Interface Test for SV4-VFS-PL-V800A, Rev. 0 SV4-VFS-T0W-1291585, Perform Plant PMS / PLS Interface Test for SV4-VFS-PL-V800B, Rev. 0 SV4-VWS-T0W-1203858, Perform Plant PMS / PLS Interface Test for SV4-VWS-PL-V058, Rev. 0 SV4-VWS-T0W-1247670, Perform ITAAC PMS CIM SV4-VWSPL-V082 Component Test, Rev. 0 SV4-VWS-T0W-1247671, Perform ITAAC PMS/PLS testing SV4- VWS-PL-V086, Rev. 0 SV4-WLS-T0W-1247672, Perform Plant PMS / PLS Interface Test for SV4-WLS-PL-V055, Rev. 0 SV4-WLS-T0W-1247673, Perform Plant PMS / PLS Interface Test for SV4-WLS-PL-V057, Rev. 0 SV4-WLS-T0W-1206405, Perform ITAAC PMS CIM SV4-WLSPL- V067 Component Test and Interface Test, Rev. 0 SV4-WLS-T0W-1206411, Perform PLS / PMS Component Interface Test for SV4-WLS-PL-V068, Rev. 0 WORK ORDERS: 1189903, 1190298, 1242824, 1242827, 1191775, 1191780, 1288906, 1247640, 1247641, 1291587, 1247664, 1203251, 1291585, 1203858, 1247670, 1247671, 1247672, 1247673, 1206405, and 1206411 37

Section 1A09 4-CCS-ITPP-501, Component Cooling Water System Preoperational Test Procedure, Ver.

1.0 4-VFS-ITPP-501, Containment Air Filtration System Preoperational Test Procedure, Ver.

1.0 4-SFS-ITPP-502, TPC for Spent Fuel Pool Cooling System 1.1 Flow Path Preoperational Test Procedure, Ver. 1.1 SV4-SFS-T0W-1191985, (ITAAC) Perform Preop Test 4-SFS- ITPP-502, Rev. 0 SV4-CNS-ITR-800116, Unit 4 Recorded Results of SFS Motor-Operated Valves Change Position as Indicated in Table 2.2.1-1: ITAAC 2.2.01.11a.iii NRC Index Number: 116, Rev.

0 SV4-CCS-T0W-1190017, (ITAAC) Perform Pre-Op Test on CCS System per 4-CCS-ITPP-501, Rev. 0 SV4-CNS-ITR-801116, Unit 4 Recorded Results of CCS Motor-Operated Valves Change Position as Indicated in Table 2.2.1-1: ITAAC 2.2.01.11a.iii NRC Index Number: 116, Rev.

0 SV4-VFS-T0W-1202924, (ITAAC) Perform VFS System Pre-Op Test 4-VFS-ITPP-501, Rev.

0 SV4-CNS-ITR-802116, Rev. 0, Unit 4 Recorded Results of VFS Motor-Operated Valves Change Position as Indicated in Table 2.2.1-1: ITAAC 2.2.01.11a.iii NRC Index Number:

116, Rev. 0 WO# 1191985, 1190017, & 1202924 Section 1A10 Procedures:

4-VFS-OTS-17-001, Containment Air Filtration System Vacuum Relief Valve Test and Check Valve Exercise, Version 2.0 4-VFS-ITPP-501, Containment Air Filtration System Preoperational Test Procedure, Version 1.0 4-VWS-OTS-10-002, Central Chilled Water System Check Valve Exercise, Version 1.1 4-VWS-ITPP-501, Central Chilled Water System Preoperational Test, Version 2.0 Work Orders:

1203429 1495142 Section 1A11 2.2.02.07b.i-U4-CP, ITAAC Completion Package, Rev. 0 4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 SV4-PCS-T2R-001, Vogtle Unit 4 Passive Containment Cooling Water Storage Tank Draindown Test Results Report, Rev. 0 SV4-PCS-T2C-001, Vogtle Unit 4 Passive Containment Cooling Water Storage Tank Draindown Test Results Evaluation, Rev. 0 Temporary Procedure Change (TPC) 4-PCS-ITPP-502-V1.0-0.3 WO# 1199655 CR# 50177372, 50177279, 50177053, 50175476, 50175116, & 5017511 Section 1A12 2.2.03.08b.i-U4-CP, ITAAC Completion Package, Rev. 0 4-PXS-ITPP-504, Passive Core Cooling System Hot Functional Test, Ver. 1.0 38

SV4-PXS-T0W-1191261, (ITAAC) Perform Preop Test 4-PXSITPP-504, Rev. 0 SV4-PXS-T2R-011, Vogtle Unit 4 PXS Hot Functional Test Results Validation for PRHR Performance Summary Report, Rev. 0 SV4-PXS-ITR-800175, Unit 4 Recorded Results of PRHR Heat Exchanger Heat Transfer Rate Test: ITAAC 2.2.03.08b.01, Rev. 0 WO # 1191261 Section 1A13 2.2.03.10-U4-CP, ITAAC Completion Package, Rev. 0 SV4-PXS-T0W-1191835, Perform PLS Plant Interface testing of CMT A Outlet AOV SV4-PXS-PL-V014A, Rev. 0 B-GEN-ITPCI-039-F317, PXS-PL-V014A-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1293823, Retest ITAAC PMS CIM Component Test SV4-PXS-PL-V014B, Rev. 0 B-GEN-ITPCI-039-F318, PXS-PL-V014B-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1191768, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V015A-S1, Rev. 0 B-GEN-ITPCI-039-F319, PXS-PL-V015A-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1191776, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V015B-S1, Rev. 0 B-GEN-ITPCI-039-F320, PXS-PL-V015B-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1243347, Perform Plant PMS / PLS Interface Test for SV4-PXS-PL-V042, Rev. 0 B-GEN-ITPCI-039-F321, PXS-PL-V042 Component Test, Ver. 1.0 SV4-PXS-T0W-1243371, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V108A-S1, Rev. 0 B-GEN-ITPCI-039-F323, PXS-PL-V108A-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1243372, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V108B-S1, Rev. 0 B-GEN-ITPCI-039-F324, PXS-PL-V108B-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1243375, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V130A-S1, Rev. 0 B-GEN-ITPCI-039-F359, PXS-PL-V130A-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1243349, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V130B-S1, Rev. 0 B-GEN-ITPCI-039-F360, PXS-PL-V130B-S1 Component Test, Ver. 1.0 SV4-PXS-T0W-1191720, Perform PMS/PLS Plant Interface test for SV4-PXS-PL-V002A, Rev. 1 SV4-PXS-T0W-1243304, Perform Plant PMS / PLS Interface Test for SV4-PXS-PL-V002B, Rev. 1 SV4-PXS-T0W-1191738, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V014A, Rev. 0 SV4-PXS-T0W-1191747, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V014B, Rev. 0 SV4-PXS-T0W-1191757, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V015A, Rev. 0 SV4-PXS-T0W-1191769, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V015B, Rev. 0 SV4-PXS-T0W-1287982, PLANT INTERFACE RETESTING OF MODULE SV4-PLS-JD-DPU011 REFERENCE VALVE SV4-PXS-PL-V027A, Rev. 0 39

SV4-PXS-T0W-1287984, PLANT INTERFACE RETESTING OF MODULE SV4-PLS-JD-DPU012 REFERENCE VALVE SV4-PXS-PL-V027B, Rev. 0 SV4-PXS-T0W-1191832, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V042, Rev. 0 SV4-PXS-T0W-1243370, Perform ITAAC PMS CIM Component Test SV4-PXS-PL-V101, Rev. 0 SV4-PXS-T0W-1191855, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V108A, Rev. 0 SV4-PXS-T0W-1191858, Perform Initial Setup and Testing on AOV SV4-PXS-PL-V108B, Rev. 0 SV4-PXS-T0W-1243373, Perform Plant PMS / PLS Interface Test for SV4-PXS-PL-V117A, Rev. 0 SV4-PXS-T0W-1243374, Perform Plant PMS / PLS Interface Test for SV4-PXS-PL-V117B, Rev. 0 SV4-PXS-T0W-1192066, (ITAAC) PERFORM INITIAL SETUP AND TESTING ON AOV SV4-PXS-PL-V130A, Rev. 0 SV4-PXS-T0W-1192070, PERFORM INITIAL SETUP AND TESTING ON AOV SV4-PXS-PL-V130B, Rev. 0 B-GEN-ITPCM-017, Air Operated Valve Test, Ver. 8.0 WOs 1191835, 1293823, 1191768, 1191776, 1243347, 1243371, 1243372, 1243375, 1243349, 1191720, 1243304, 1191738, 1191747, 1191757, 1191769, 1287982, 1287984, 1191832, 1243370, 1191855, 1191858, 1243373, 1243374, 1192066, and 1192070 Section 1A14 SV4-PXS-ITR-800209, Unit 4 Testing Results of PXS Squib Valves: ITAAC 2.2.03.11b.i, Rev. 0 SV4-PXS-T0W-1191996, PXS-PL-V118A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244543, PXS-PL-V118B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244546, PXS-PL-V120A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244551, PXS-PL-V120B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244558, PXS-PL-V123A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244572, PXS-PL-V123B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244608, PXS-PL-V125A-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PXS-T0W-1244616, PXS-PL-V125B-I1-A Component Test 2 & 1-F Component Test 2 (ITAAC) PMS CIM Squib, Rev. 0 SV4-PMS-T0W-1199997, (ITAAC) Perform preop testing per 4-PMS-ITPP-522, Squib Valve Controller Test, Rev. 0 4-PMS-ITPP-522, PMS Squib Valve Controller Performance Preoperational Test, Ver. 1.0 CR# 50173418 WO# 1191996,1244543, 1244546, 1244551, 1244558, 1244572, 1244608, & 1244616 Section 1A15 4-VES-ITPP-501, Main Control Room Emergency Habitability System PreOperational Test Procedure, Ver. 1 40

Section 1A16 4-VES-ITPP-501, Main Control Room Emergency Habitability System PreOperational Test Procedure, Ver. 1 Section 1A17 ND-23-0392, ITAAC Closure Notification on Completion of ITAAC 2.2.05.09c [Index Number 877], 05/12/2023 Section 1A18 4-PMS-ITPP-504, PMS Reactor Trip Breakers, Ver. 1.1 SV4-PMS-ITR-800529, Unit 4 Test Results of PMS Automatic Reactor Trip Testing: ITAAC 2.5.02.06a.i, Rev. 0 SV4-PMS-T0W-1200000, (ITAAC) Perform Pre-op Test per 4-PMS-ITPP-504 on Rx Trip Breakers, Rev. 0 Section 1A19 4-PMS-ITPP-504, PMS Reactor Trip Breakers, Ver. 1.1 Section 1A20 4-PMS-ITPP-504, PMS Reactor trip Breakers, Ver. 1.1 2.5.02.06c.i-U4-CP, ITAAC Completion Package, Rev. 0 SV4-PMS-T0W-1200000, (ITAAC) Perform Pre-op Test per 4- PMS-ITPP-504 on Rx Trip Breakers, Rev. 0 SV4-DDS-T0W-1171960, (ITAAC) Perform Preop testing per 4- DDS-ITPP-520 for 4-DDS-JD-MISX01 and DDS-JD-MISX0, Rev. 0 4-DDS-ITPP-520, Data Display and Processing System Remote Shutdown Room Preoperational Test Procedure, Ver. 1.0 WO# 1200000, 1171960 CR# 50137322, 50175095, 50175093 Section 1A21 Miscellaneous ND-23-0301, Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.5.02.08a.ii [Index Number 540],

April 13, 2023 SV4-PMS Cabinet Diagnostic Testing-001, ITAAC Technical Report Unit 4 PMS Cabinet Diagnostic Testing for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557], Revision 0 SV4-PMS Cabinet Software Loading-001, ITAAC Technical Report Unit 4 Software Loading for PMS Cabinets for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557], Revision 0 APP-PMS-T2R-010, AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Report, Dated October 2017 APP-PMS-T5-001, AP1000 Protection and Safety Monitoring System Test Plan, Rev. 5 41

Procedures APP-PMS-T1P-010, AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure, Rev. 4 Drawings APP-PMS-J3-400, AP1000 Detailed Functional Diagram Intermediate Range Neutron Flux and SUR Monitoring, Rev. 6 APP-PMS-J3-413, AP1000 Detailed Functional Diagram Subcriticality CSF Calculation, Rev. 5 APP-PMS-J3-415, AP1000 Detailed Functional Diagram Passive Containment Cooling Water Flow and Visual Alert Enable Monitoring, Rev. 8 APP-PMS-J3-417, AP1000 Detailed Functional Diagram PRHR HX Outlet Temperature and Flow Monitoring, Rev. 8 APP-PMS-J3-423, AP1000 Detailed Functional Diagram Containment CSF Calculation, Rev. 8 APP-PMS-J3-424, AP1000 Detailed Functional Diagram PRHR Flow Path Valve Monitoring, Rev. 6 Section 1A22 Procedures:

B-GEN-ITPCI-001, PMS Cabinets, Version 4.0 B-GEN-ITPCI-001-011, PMS Cabinets - Cabinet Diagnostics, Version 2.1 B-GEN-ITPCI-001-012, PMS Cabinets - Division Diagnostics, Version 1.0 B-GEN-ITPCI-006, Main Control Room & Remote Shutdown Room, Version 4.0 Documents:

ND-23-0378, Southern Nuclear Operating Company, Vogtle Electric Generating Plant Unit 4, ITAAC Closure Notification on Completion of ITAAC 2.5.02.08b.ii [Index Number 543],

Dated: May 8, 2023 Principal Closure Document Summary SV4-PMS Cabinet Diagnostic Testing-001, Unit 4 PMS Cabinet Diagnostic Testing for Multiple ITAACs: ITAAC 2.1.02.011a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557],

Rev. 0 SV4-PMS-ITR-800543, Unit 4 PMS Transfer of Control Capability from the MCR to the RSW: ITAAC 2.5.02.08b.ii [NRC Index Number: 543], Rev. 0 WOs:

1168612 1200056 1236104 1236124 1236136 Section 1A23 WCAP-16096 Software Program Manual for Common Q Systems Revision 4A APP-PMS-T5-001 AP1000 Protection and Safety Monitoring System Test Plan Vogtle U3 and U4 UFSAR Rev 11.2 Chapter 7 SV4-PMS-T1P-008 AP1000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Procedure 42

SV4-PMS-T1P-009 AP1000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure SV4-PMS-T2R-008, Rev. 0, Vogtle Unit 4 AP1000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Report SV4-PMS-T2R-009, Rev. 0, AP1000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report SV4-PMS Cabinet Software Loading-001, Rev 0, Unit 4 Software Loading for PMS Cabinets for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557]

SV4-GW-GCW-740, AP1000 Vogtle 4 PMS Software Installation - Software Release 9.0.0.1 SV4-GW-GCW-848, AP1000 Vogtle 4 PMS Software Installation - Software Release 9.0.0.4 B-GEN-ITPCI-001-011, PMS CABINETS - Cabinet Diagnostics, Rev 2.1 SV4-PMS Cabinet Diagnostic Testing-001, Unit 4 PMS Cabinet Diagnostic Testing for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557], Rev 0 SV4-PMS-T2R-050, Vogtle AP1000 Protection and Safety Monitoring System Fuel Load Regression Test Report, Rev 0 B-GEN-ITPCI-001, PMS CABINETS, Rev. 4 NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52 ITAAC 2.5.02.09d-U4-CP-Rev0, ITAAC Completion Package Section 1A24 4-IDS-ITPP-507, IDSB Class 1E DC and UPS Preoperational Test, Ver. 1.0 4-IDS-ITPP-507, IDSC Class 1E DC and UPS Preoperational Test, Ver. 1.0 WO 1301119 Section 1A25 SV4-IDS-E0R-007, Vogtle Unit 4 IDS System ITAAC 2.6.03.04i MOV Voltage Test Analyses Report, Rev. 0 APP-IDS-E0C-004, IDS Power Cable Sizing and Voltage Drop Analysis, Rev. 6 APP-IDS-E0C-018, MOV Acceptance Voltage During Safety Related DC MOV Field Testing, Rev. 1 Section 1A26 SV4-SES-ITR-800644- Unit 4 Intrusion Detection/Video Assessment Testing: ITAAC 2.6.09.05a- Revision 0 WO:1473502 WO:1473528 WO:1474482 WO:1474487 WO:1474492 WO:1474498 WO:1474500 VEGP Physical Security Plan-R-18-VEGP-2 43

Section 1A27 SV4-SES-ITR-800647- Unit 4 ITAAC 647 Vehicle Barrier System Inspection: ITAAC 2.6.09.06 Revision 0 APP-XV01-ZOC-001- AP 1000 VBS Standoff Distances for a Range of Blast Scenarios Revision 0 SVO-SES-ZOC-8000000- Vogtle Site Security Vehicle Barrier System Analysis, Revision 1 ABS-Consulting Calculation ID 4212670-C-103- VBID Blast Effects Assessment of Security Assets, Revision 0 Thornton Tomasetti Calculation ID-SCAL-001-Kontek MBRE Blast Analysis, Revision 1 SVO-XV01-CC-800002, West Vehicle Barrier Ditch Plan and Profile- Revision 3 SVO-XV01-CC-800003, North Vehicle Barrier Ditch Plan and Profile Sheet 1 of 2- Revision 3

KONTEK, 8x12 50-AP MBRE Finish-Electrical-HVAC, Dwg. No. K17005, Revision A KONTEK, 10'-0" X 10'-0" X 8'-0" B.B.R.E. (BRES #6 & #27), Document No.:

AX1AQ06-20353, Version 2.0 Weidlinger Associates, Inc., Kontek BRE Modular Building Blast Analysis, Calculation Number: 2118-2006-SCAL-001, Revision 4 Thornton Tomasetti, Inc., Kontek MBRE Blast Analyses, Calculation Number:

SCAL-001, Revision 1 Thornton Tomasetti, Inc., Vogtle BBRE Kontek Tower 40' Tower Design, Document:

K18004_Exhibit_E, Issue: A Thornton Tomasetti, Inc., BBRE Kontek Vogtle BBRE 40' Tower Structural Calculations, Document: K18004_Exhibit_F, Revision A Thornton Tomasetti, Inc., Kontek BBRE and Tower- Blast Response, Document:

Document: K18004_Exhibit_G, Revision 0 Westinghouse, BBRE Foundation Location Plan & Schedule, Dwg. No.

SVO-SES-CC-800003, Revision 0 Westinghouse, Vogtle Site Security Vehicle Barrier System Analysis, Doc.

No.SV0-SES-ZOR-800000, Revision 1 ABS Consulting Inc., VBIED Blast Effects Assessments of Security Assets Units 3 and 4, Calculation ID: 4212670-C-103, Revision 0 ABS Consulting Inc., Locations of Security Observation Posts, Security Rooms, CAS, SAS and BBREs, Dwg. No. 4212670-SK-103, Revision 0 WECTEC, Vehicle Barrier Main Ditch Plan and Profile, Dwg. No.

SV0-869-XV-800001, Revision 4 WECTEC, North Vehicle Barrier Ditch Plan and Profile Sheet 1 of 2, Dwg. No. SV0-XV01-CC-800003, Revision 3 WECTEC, North Vehicle Barrier Ditch Plan and Profile Sheet 2 of 2, Dwg. No.

SV0-XV01-CC-800004, Revision 4 WECTEC, West and North Vehicle Barrier Ditch Concrete Sections and Details, Dwg. No. SV0-XV01-CC-800005, Revision 2A WECTEC, West and North Vehicle Barrier Ditch Retaining Wall Elevations, Sections and Details, Dwg. No. SV0-XV01-CC-800006, Revision 2 WECTEC, West and North Vehicle Barrier Ditch Bundled Pipe Array Drainage Structures, Dwg. No. SV0-XV01-CC-800007, Revision 2 WECTEC, West and North Vehicle Barrier Ditch Cross Sections, Sections and Details, Dwg. No. SV0-XV01-CC-800008, Revision 3 WECTEC, North Vehicle Barrier Ditch Plan, Sections and Detail, Dwg. No.

SV0-XV01-CC-800009, Revision 1 Section 1A28 44

SV4-SES-ITR-800650- SES Isolation Zone and Protected Area Illumination: ITAAC 2.6.09.08 Revision 0 V-SSO-2021 ITAAC Test for Protected Area Lighting System- Revision 1 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A29 SV4-SES-ITR-800655- Unit 4 Alarm & Circuit Supervision Testing: ITAAC 2.6.09.15a -

Revision 1 SV4-SES-ITR-800644- Intrusion Detection/Video Assessment Testing: ITAAC 2.6.09.05a-Revision 0 SV4-SES-ITR-800670- Protected Area Perimeter and Vital Area Boundary Emergency Exit Testing- Revision 0 SV0-SES-JOX-800000-Vogtle Plant Security System Database - Revision 9 4-SES-ITAAC-655 FEP-WO: 147915- U4 FEP Alarm & Circuit Supervision Test- Version 1.0 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A30 3.3.00.10.i-U4-CP, ITAAC Completion Package, Rev. 0 4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 SV4-PCS-T0W-1199655, (ITAAC) 4-PCS-ITPP-502 PCCAWST Preoperational Test, Rev. 0 B-GEN-ITPA-011-F02, Component and Preoperational Temporary Procedure Change Prior to 103G, Ver 1.1 (For Section 4.9.2 of 4-PCS-ITPP-502)

WO# 1199655 Section 1A31 AX1D08SA014-2-Security Facilities Layout General Arrangement Delay Features Fencing -

Revision 10 SVO-0000-X2-80012- Vogtle Electric Generating Plant Units 3&4 Permanent Buildings within Protected Area General Arrangement- Revision 6 SVO-0000-X2-80013- Vogtle Electric Generating Plant Units 3&4 Power block General Arrangement- Revision 9 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A32 4-SES-ITAAC-660-Zone-WO: SNC 1476959-Isolation zone Coverage-Version 1.0 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A33 SV4-SES-ITR-800661- Unit 4 ITAAC 661 Walkdown Inspection: ITAAC C.2.6.09.03b-Revision 0 SVO-SES-XF-800018 Vogtle Electric Generating Plant, Plant Security System (SES) Fence Cover Sheet- Revision 4 SVO-SES-E2T[Grid location], Vogtle Electric Generating Plant, Security System Site Grid Equipment Location Plan SV4-SES-ITR-801661- Intrusion Detection/Video Assessment Testing: ITAAC C.2.6.09.03b-Revision 0 SV4-SES-ITR-802661-Uninterruptable Power Supply Testing- ITAAC C.2.6.09.03b-Revision 0 4-SES-ITAAC 661- UPS01-PA IDS/Assessment-UPS01- Version 1 VEGP Physical Security Plan-R-18-VEGP-2 45

Section 1A34 SV4-SES-ITR-800664 - Unit 4 ITAAC 664 Walkdown Inspection- ITAAC C.2.6.09.05a -

Revision 0 SVO-SES-E2-K1004 - Security System Site Grid Equipment Location Plan- Rev 2 SVO-SES-E2-K1103 - Vogtle Electric Generating Plant Security System Site Grid Equipment Location Plan- Rev 5 SV3-SES-ITR-800664 - Unit 3 ITAAC 664 Walkdown Inspection ITAAC C.2.6.09.05a - Rev 1

SVO-SES-ZO-800012- Sliding and Wedge Gates at Vehicle Access Portals - Rev 1 SV4-SES-ITR-801664- Unit 4 Secondary Vehicle Access Portal Vehicle Barrier System Testing: ITAAC C.2.6.09.05a Rev 0 4-SES-FTI-703 WO: 1478927, SVAP Operational Test Version 1.0 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A35 VEGP Physical Security Plan-R-18-VEGP-2 Section 1A36 VEGP Physical Security Plan-R-18-VEGP-2

[2504 Documents]

Section 1P01 4-GEN-ITPP-507, Thermal Expansion, Ver. 1 4-GEN-ITPP-517, Pre-Core Hot Functional Testing (HFT) Sequence Procedure, Ver. 2 4-GEN-ITPP-509, Reactor Coolant System Dynamic Effects and Vibration Testing, Ver. 1 4-GEN-ITPP-515, Steam Generator System Dynamic Effects and Vibration Testing Ver. 1 4-GEN-ITPP-512, Chemical and Volume Control System Dynamic Effects and Vibration Testing Ver. 1 4-GEN-ITPP-511, Passive Core Cooling System Dynamic Effects and Vibration, Ver. 1 Section 1P02 B-GEN-ITPCI-350, PMS Channel Calibration Test for 4-RCS-FT101B, Ver. 1.1 B-GEN-ITPCl-019-357, PMS Channel Calibration Test for 4-RCS-L T160A, Ver. 2.0 B-GEN-ITPCl-019-358, PMS Channel Calibration Test for 4-RCS-L T160B, Ver. 2.0 B-GEN-ITPCl-019-363, PMS Channel Calibration Test for 4-RCS-PT140A, Ver. 1.0 B-GEN-ITPCl-019-374, PMS Channel Calibration Test For 4-RCS-ST284, Ver. 2.0 B-GEN-ITPCl-039-F410, RCS-PL-V150B Component Test, Ver. 1.0 B-GEN-ITPCI-019-407, PMS-Channel Calibration Test for 4-RCS-TE211B, Ver. 2.0 B-GEN-ITPCl-019-370, PMS Channel Calibration Test for 4-RCS-PT191D, Ver. 1.0 B-GEN-ITPCl-019-362, PMS Channel Calibration Test for 4-RCS-LT195D, Ver. 1.0 WO# 1192329, 1192347, 1192358, 1192380, 1245189, 261883, 1261769, & 1261760 Section 1P03 B-GEN-ITPCl-019-327, PMS Channel Calibration Test for 4-PXS-LT011A and 4-PXS-L T011C, Ver. 1.0 B-GEN-ITPCl-019-334, PMS Channel Calibration Test for 4-PXS-LT0148 and 4-PXS-LT014D, Ver. 1.0 B-GEN-ITPCl-019-336, PMS Channel Calibration Test for 4-PXS-LT047, Ver. 1.0 WO#: 1191422, 1191429, 1191434 46

Section 1P04 4-PCS-ITPP-502, Passive Containment Cooling System PCCWST Preoperational Test Procedure, Ver. 1.0 SV4-PCS-ITR-800138, Unit 4 Passive Containment Cooling System Testing: ITAAC 2.2.02.

07b.i Items 7a.i, 7a.ii, 7d, & 7e.ii, NRC Index Number: 138, Rev. 0 SV4-PCS-T2R-001, Vogtle Unit 4 Passive Containment Cooling Water Storage Tank Draindown Test Results Report, Rev. 0 SV4-PCS-T2C-001, Vogtle Unit 4 Passive Containment Cooling Water Storage Tank Draindown Test Results Evaluation, Rev. 0 WO 1199655 CRs 50177372, 50177279, 50177053, 50175476, 50175116, & 5017511 Section 1P05 4-PXS-ITPP-504, Passive Core Cooling System Hot Functional Test, Version 1.0 4-GEN-ITPP-517, Pre-Core Hot Functional Testing (HFT) Sequence Procedure, Version 2.0 WO 1191261 SAFEGUARDS PROGRAMS

[2504 Documents]

Section 2P01 Vogtle Unit 4 Security Plan

3. OPERATIONAL READINESS

[2504 Documents]

Section 3P01 Documents:

SV0-RXS-TI-501, Reactor System Preoperational Test Specification, Rev. 1 Drawings:

APP-MI01-V3-123, AP1000 Reactor Internals Upper Core Plate Insert and Head and Vessel Alignment Pin Fit Up, Rev. 4 Procedure:

4-RXS-ITPP-501, Pre- and Post-Hot Functional Test Inspection of Reactor Vessel Internals, Version 1.0 Work Orders:

1192570 49

LIST OF ACRONYMS 10 CFR Title 10 of the Code of Federal Regulations CAP corrective action program COL Combined License DCO Division of Construction Oversight DRS Division of Reactor Safety IMC inspection manual chapter IP inspection procedure IR inspection report ITAAC inspections, tests, analyses, and acceptance criteria NCV noncited violation NRC Nuclear Regulatory Commission PMS protection and safety monitoring system PRHR HX passive residual heat removal heat exchanger PXS passive core cooling system RCS reactor coolant system Rev. revision UFSAR Updated Final Safety Analysis Report VEGP Vogtle Electric Generating Plant Ver. version 49

ITAAC INSPECTED No. ITAAC No. Design Inspections, Tests, Analysis Acceptance Criteria Commitment 30 2.1.02.08b 8.b) The RCPs A test will be performed to The pump flow have a rotating determine the pump flow coastdown will inertia to provide coastdown curve. provide RCS flows RCS flow greater than or equal coastdown on loss to the flow shown in of power to the Figure 2.1.2-2, Flow pumps. Transient for Four Cold Legs in Operation, Four Pumps Coasting Down.

41 2.1.02.09a 9.a) The RCS Testing and analysis to The calculated post-provides measure RCS flow with four fuel load RCS flow circulation of reactor coolant pumps rate is > 301,670 coolant to remove operating at noload RCS gpm.

heat from the core. pressure and temperature conditions will be performed. Analyses will be performed to convert the measured pre-fuel load flow to postfuel load flow with 10percent steam generator tube plugging.

46 2.1.02.11a.i 11.a) Controls i) Testing will be performed i) Controls in the exist in the MCR to on the squib valves MCR operate to cause the remotely identified in Table 2.1.2-1 cause a signal at the operated valves using controls in the MCR squib valve electrical identified in Table without stroking the valve. leads which is 2.1.2-1 to perform capable of actuating active functions. the squib valve.

49

47 2.1.02.11a.ii 10. Safety-related Inspection will be Safety-related displays identified in performed for displays identified in Table 2.1.2-1 can be retrievability of the Table 2.1.2-1 can retrieved in the MCR. safety-related displays be retrieved in the 11.a) Controls exist in in the MCR. ii) Stroke MCR. ii) Controls the MCR to cause the testing will be in the MCR operate remotely operated performed on the other to cause the valves identified in remotely operated remotely operated Table 2.1.2-1 to perform valves listed in Table valves (other than active functions. 11.b) 2.1.2-1 using controls squib valves) to The valves identified in in the MCR. ii) perform active Table 2.1.2-1 as having Testing will be functions. ii) The PMS control perform an performed on the other other remotely active safety function remotely operated operated valves after receiving a signal valves identified in identified in Table from the PMS. 12.b) Table 2.1.2-1 using 2.1.2-1 as having After loss of motive real or simulated PMS control power, the remotely signals into the PMS. perform the active operated valves iii) Testing will be function identified in identified in Table 2.1.2- performed to the table after 1 assume the indicated demonstrate that receiving a signal loss of motive power remotely operated from PMS. iii) position. RCS valves These valves open RCSV001A/B, within the following V002A/B, V003A/B, times after receipt V011A/B, V012A/B, of an actuation V013A/B open within signal: V001A/B <

the required response 40 sec V002A/B, times. Testing of the V003A/B < 100 sec remotely operated V011A/B < 30 sec valves will be V012A/B, V013A/B performed under the < 60 sec Upon loss conditions of loss of of motive power, motive power. each remotely operated valve identified in Table 2.1.2-1 assumes the indicated loss of motive power position.

48 2.1.02.11b.i 11.b) The valves i) Testing will be i) The squib valves identified in Table 2.1.2- performed on the receive a signal at 1 as having PMS control squib valves identified the valve electrical perform an active safety in Table 2.1.2-1 using leads that is function after receiving a real or simulated capable of actuating signal from the PMS. signals into the PMS the squib valve.

without stroking the valve.

50

55 2.1.02.12a.iii 12.a) The automatic iii) Tests of the motor- iii) Each motor-depressurization valves operated valves will be operated valve identified in Table 2.1.2- performed under pre- changes position as 1 perform an active operational flow, indicated in Table safety-related function differential pressure 2.1.2-1 under pre-to change position as and temperature operational test indicated in the table. conditions. conditions.

78 2.1.03.07.i 7. The reactor internals i) Not used per i) Not used per will withstand the effects Amendment No. 150. Amendment No.

of flow induced ii) A pre-test 150. ii) The as-vibration. 10. The inspection, a flow test built reactor reactor lower internals and a post-test internals have no assembly is equipped inspection will be observable damage with holders for at least conducted on the as- or loose parts. At eight capsules for built reactor internals. least eight capsules storing material Inspection of the are in the reactor surveillance specimens. reactor lower internals lower internals assembly for the assembly.

presence of capsules will be performed.

110 2.2.01.09 9. Safety-related Inspection will be Safety-related displays identified in performed for displays identified in Table 2.2.1-1 can be retrievability of the Table 2.2.1-1 can retrieved in the MCR. safety-related displays be retrieved in the 10.a) Controls exist in in the MCR. Stroke MCR. Controls in the MCR to cause those testing will be the MCR operate to remotely operated performed on remotely cause remotely valves identified in operated valves operated valves Table 2.2.1-1 to perform identified in Table identified in Table active functions. 10.b) 2.2.1-1 using the 2.2.1-1 to perform The valves identified in controls in the MCR. active safety Table 2.2.1-1 as having Testing will be functions. The PMS control perform an performed on remotely remotely operated active safety function operated valves listed valves identified in after receiving a signal in Table 2.2.1-1 using Table 2.2.1-1 as from the PMS. real or simulated having PMS control signals into the PMS. perform the active function identified in the table after receiving a signal from PMS.

51

116 2.2.01.11a.iii 11.a) The motor- iii) Tests of the motor- iii) Each motor-operated and check operated valves will be operated valve valves identified in performed under changes position as Table 2.2.1-1 perform preoperational flow, indicated in Table an active safety- differential pressure, 2.2.1-1 under pre-related function to and temperature operational test change position as conditions. conditions.

indicated in the table.

117 2.2.01.11a.iv 11.a) The motor- iv) Exercise testing of iv) Each check valve operated and check the check valves with changes position as valves identified in active safety functions indicated in Table Table 2.2.1-1 perform identified in Table 2.2.11.

an active safety- 2.2.11 will be related function to performed under change position as preoperational test indicated in the table. pressure, temperature and fluid flow conditions.

138 2.2.02.07b.i 7.a) The PCS i) Testing will be i) When tested, each delivers water from performed to measure one of the three flow the PCCWST to the the PCCWST delivery paths delivers water outside, top of the rate from each one of at greater than or containment vessel. the three parallel flow equal to: - 469.1 7.b) The PCS wets paths. ii) Testing and gpm at a PCCWST the outside surface of or analysis will be water level of 27.4 ft the containment performed to + 0.2, - 0.0 ft above vessel. The inside demonstrate the the tank floor - 226.6 and the outside of the PCCWST inventory gpm when the containment vessel provides 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of PCCWST water level above the operating adequate water flow. i) uncovers the first (i.e.

deck are coated with Testing will be tallest) standpipe -

an inorganic zinc performed to measure 176.3 gpm when the material. 7.c) The the outside wetted PCCWST water level PCS provides air flow surface of the uncovers the second over the outside of containment vessel with tallest standpipe -

the containment one of the three parallel 144.2 gpm when the vessel by a natural flow paths delivering PCCWST water level circulation air flow water to the top of the uncovers the third path from the air containment vessel. ii) tallest standpipe - or inlets to the air Inspection of the a report exists and discharge structure. containment vessel concludes that the 7.d) The PCS drains exterior coating will be as-measured flow the excess water conducted. iii) rates delivered by the from the outside of Inspection of the PCCWST to the containment vessel containment vessel interior coating will be 52

the containment conducted. Inspections provides sufficient vessel through the of the air flow path heat removal two upper annulus segments will be capability such that drains. 7.e) The performed. Testing will the limiting PCS provides a flow be performed to verify containment pressure path for long-term the upper annulus drain and temperature water makeup to the flow performance. ii) values are not PCCWST. 9. Safety- Testing will be affected and the PCS related displays performed to measure is able to perform its identified in Table the delivery rate from safety function to 2.2.2-1 can be the long-term makeup remove heat from retrieved in the MCR. connection to the containment to 10.a) Controls exist PCCWST. Inspection maintain plant safety.

in the MCR to cause will be performed for ii) When tested the remotely operated retrievability of the and/or analyzed with valves identified in safety-related displays all flow paths Table 2.2.2-1 to in the MCR. Stroke delivering and an perform active testing will be initial water level at functions. 10.b) The performed on the 27.4 + 0.2, 0.00 ft, valves identified in remotely operated the PCCWST water Table 2.2.2-1 as valves identified in inventory provides having PMS control Table 2.2.2-1 using the greater than or equal perform an active controls in the MCR. to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of flow, safety function after Testing will be and the flow rate at receiving a signal performed on the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is greater from the PMS. 11.a) remotely operated than or equal to 100.7 The motor-operated valves in Table 2.2.2-1 gpm or a report exists valves identified in using real or simulated and concludes that Table 2.2.2-1 perform signals into the PMS. the as-measured flow an active safety- iii) Tests of the motor- rates delivered by the related function to operated valves will be PCCWST to the change position as performed under containment vessel indicated in the table. preoperational flow, provides sufficient 11.b) After loss of differential pressure, heat removal motive power, the and temperature capability such that remotely operated conditions. Testing of the limiting valves identified in the remotely operated containment pressure Table 2.2.2-1 assume valves will be and temperature the indicated loss of performed under the values are not motive power conditions of loss of affected and the PCS position. motive power. is able to perform its safety function to remove heat from containment to maintain plant safety.

i) A report exists and concludes that when the water in the PCCWST uncovers 53

the standpipes at the following levels, the water delivered by one of the three parallel flow paths to the containment shell provides coverage measured at the spring line that is equal to or greater than the stated coverages. - 24.1 +/-

0.2 ft above the tank floor; at least 90% of the perimeter is wetted. - 20.3 +/- 0.2 ft above the tank floor; at least 72.9% of the perimeter is wetted. -

16.8 +/- 0.2 ft above the tank floor; at least 59.6% of the perimeter is wetted.

ii) A report exists and concludes that the containment vessel exterior surface is coated with an inorganic zinc coating above elevation 135'3". iii)

A report exists and concludes that the containment vessel interior surface is coated with an inorganic zinc coating above the operating deck. Flow paths exist at each of the following locations: -

Air inlets - Base of the outer annulus -

Base of the inner annulus - Discharge structure With a water level within the upper annulus 10" +

1" above the annulus drain inlet, the flow rate through each 54

drain is greater than or equal to 525 gpm. ii)

With a water supply connected to the PCS long-term makeup connection, each PCS recirculation pump delivers greater than or equal to 100 gpm when tested separately. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the MCR.

Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.2-1 to perform active functions. The remotely operated valves identified in Table 2.2.2-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS. iii)

Each motor-operated valve changes position as indicated in Table 2.2.2-1 under preoperational test conditions. After loss of motive power, each remotely operated valve identified in Table 2.2.2-1 assumes the indicated loss of motive power position.

55

175 2.2.03.08b.01 8.b) The PXS 1. A heat removal 1. A report exists and provides core decay performance test and concludes that the heat removal during analysis of the PRHR PRHR HX heat design basis events. HX will be performed transfer rate with the to determine the heat design basis number transfer from the HX. of PRHR HX tubes For the test, the plugged is: 8.46 x reactor coolant hot leg 107 Btu/hr with 250°F temperature will be HL Temp and an initial initially at 350°F with IRWST temperature of the reactor coolant 80°F. The heat pumps running. The transfer rate measured IRWST water level for in the test should be the test will be above adjusted to account for the top of the HX. The differences in the HL test will continue until and IRWST the hot leg temperatures and the temperature is number of tubes 250°F. plugged.

56

206 2.2.03.10 10. Safety-related Inspection will be Safety-related displays displays of the performed for the identified in Table parameters identified retrievability of the 2.2.3-1 can be in Table 2.2.31 can safety-related displays retrieved in the MCR.

be retrieved in the in the MCR. ii) ii) Controls in the MCR. 11.a) Stroke testing will be MCR operate to cause Controls exist in the performed on remotely operated MCR to cause the remotely operated valves other than squib remotely operated valves other than valves to perform their valves identified in squib valves identified active functions. ii)

Table 2.2.3-1 to in Table 2.2.3-1 using Remotely operated perform their active the controls in the valves other than squib function(s). 11.b) MCR. ii) Testing will valves perform the The valves identified be performed on the active function in Table 2.2.3-1 as remotely operated identified in the table having PMS control valves other than after a signal is input to perform their active squib valves identified the PMS. iii) These function after in Table 2.2.3-1 using valves open within 20 receiving a signal real or simulated seconds after receipt from the PMS. 12.b) signals into the PMS. of an actuation signal.

After loss of motive iii) Testing will be After loss of motive power, the remotely performed to power, each remotely operated valves demonstrate that operated valve identified in Table remotely operated identified in Table 2.2.3-1 assume the PXS isolation valves 2.2.3-1 assumes the indicated loss of PXS-V014A/B, indicated loss of motive power V015A/B, V108A/B motive power position.

position. 13. open within the Displays identified in Displays of the required response Table 2.2.3-3 can be parameters identified times. Testing of the retrieved in the MCR.

in Table 2.2.3-3 can remotely operated be retrieved in the valves will be MCR. performed under the conditions of loss of motive power.

Inspection will be performed for retrievability of the displays identified in Table 2.2.3-3 in the MCR.

209 2.2.03.11b.i 11.b) The valves i) Testing will be i) Squib valves receive identified in Table performed on the an electrical signal at 2.2.3-1 as having squib valves identified the valve electrical PMS control perform in Table 2.2.3-1 using leads that is capable of their active function real or simulated actuating the valve after receiving a signals into the PMS after a signal is input to signal from the PMS. without stroking the the PMS.

valve.

57

265 2.2.05.07a.i 7.a) The VES i) Testing will be i) The air flow rate provides a 72-hour performed to confirm from the VES is at supply of breathable that the required least 60 scfm and not quality air for the amount of air flow is more than 70 scfm.

occupants of the delivered to the MCR. iii) The MCR air is of MCR. 7.b) The VES iii) MCR air samples breathable quality. i) maintains the MCR will be taken during The MCR pressure pressure boundary at VES testing and boundary is a positive pressure analyzed for quality. i) pressurized to greater with respect to the Testing will be than or equal to 1/8-in.

surrounding areas. performed with VES water gauge with 7.d) The system flow rate between 60 respect to the provides a passive and 70 scfm to confirm surrounding area. ii) recirculation flow of that the MCR is Air leakage into the MCR air to maintain capable of maintaining MCR is less than or main control room the required equal to 10 cfm. The dose rates below an pressurization of the air flow rate at the acceptable level pressure boundary. ii) outlet of the MCR during VES operation. Air leakage into the passive filtration

8. Safety-related MCR will be measured system is at least 600 displays identified in during VES testing cfm greater than the Table 2.2.5-1 can be using a tracer gas. flow measured by retrieved in the MCR. Testing will be VES-003A/B. Safety-9.a) Controls exist in performed to confirm related displays the MCR to cause that the required identified in Table remotely operated amount of air flow 2.2.5-1 can be valves identified in circulates through the retrieved in the MCR.

Table 2.2.5-1 to MCR passive filtration Controls in the MCR perform their active system. Inspection will operate to cause functions. 9.b) The be performed for remotely operated valves identified in retrievability of the valves identified in Table 2.2.5-1 as safety-related displays Table 2.2.5-1 to having PMS control in the MCR. Stroke perform their active perform their active testing will be safety functions. The safety function after performed on remotely remotely operated receiving a signal from operated valves valves identified in the PMS. 10. After identified in Table Table 2.2.5-1 as loss of motive power, 2.2.5-1 using the having PMS control the remotely operated controls in the MCR. perform the active valves identified in Testing will be safety function Table 2.2.5-1 assume performed on remotely identified in the table the indicated loss of operated valves listed after receiving a signal motive power position. in Table 2.2.5-1 using from the PMS. After

11. Displays of the real or simulated loss of motive power, parameters identified signals into the PMS. each remotely in Table 2.2.5-3 can Testing of the remotely operated valve be retrieved in the operated valves will be identified in Table MCR. 12. The performed under the 2.2.5-1 assumes the background noise conditions of loss of indicated loss of level in the MCR does motive power. motive power position.

not exceed 65 dB(A) Inspection will be The displays identified 58

at the operator performed for in Table 2.2.5-3 can workstations when retrievability of the be retrieved in the VES is operating. parameters in the MCR. MCR. The The as-built VES will be background noise operated, and level in the MCR does background noise not exceed 65 dB(A) levels in the MCR will at the operator work be measured at the stations when the operator work stations VES is operating.

with the plant not operating.

270 2.2.05.07c 7.c) The heat loads An analysis will be A report exists and within the MCR, the performed to determine concludes that: the I&C equipment rooms, that the heat loads from heat loads within and the Class 1E dc as-built equipment rooms identified in equipment rooms are within the rooms Table 2.2.5-4 are less within design basis identified in Table than or equal to the assumptions to limit 2.2.5-4 are less than or specified values or the heatup of the equal to the design that an analysis report rooms identified in basis assumptions. exists that concludes:

Table 2.2.54. - The temperature and humidity in the MCR remain within limits for reliable human performance for the 72hour period.

- The maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 120°F. -

The maximum temperature for the 72-hour period for the Class 1E dc equipment rooms is less than or equal to 120°F.

529 2.5.02.06a.i 6.a) The PMS An operational test of i) The reactor trip initiates an automatic the as-built PMS will be switchgear opens reactor trip, as performed using real or after the test signal identified in Table simulated test signals. reaches the specified 2.5.22, when plant limit. This only needs process signals reach to be verified for one specified limits. automatic reactor trip function.

59

530 2.5.02.06a. 6.a) The PMS An operational test of ii) PMS output signals ii initiates an automatic the as-built PMS will to the reactor trip reactor trip, as be performed using switchgear are identified in Table real or simulated test generated after the 2.5.22, when plant signals. An test signal reaches the process signals reach operational test of the specified limit. This specified limits. 6.b) as-built PMS will be needs to be verified for The PMS initiates performed using real each automatic reactor automatic actuation or simulated test trip function.

of engineered safety signals. An Appropriate PMS features, as identified operational test of the output signals are in Table 2.5.2-3, as-built PMS will be generated after the when plant process performed using the test signal reaches the signals reach PMS manual actuation specified limit. These specified limits. 6.c) controls. i) An output signals remain The PMS provides inspection will be following removal of manual initiation of performed for the test signal. Tests reactor trip and retrievability of plant from the actuation selected engineered parameters in the signal to the actuated safety features as MCR. iii) An device(s) are identified in Table operational test of the performed as part of 2.5.2-4. 8.a) The asbuilt system will be the system-related PMS provides for the performed using each inspection, test, minimum inventory of MCR fixed position analysis, and displays, visual alerts, control. Inspection will acceptance criteria.

and fixed position be performed for ii) PMS output signals controls, as identified retrievability of are generated for in Table 2.5.2-5. The displays of the reactor trip and plant parameters open/closed status of selected engineered listed with a "Yes" in the reactor trip safety features as the "Display" column breakers in the MCR. identified in Table and visual alerts An operational test of 2.5.2-4 after the listed with a "Yes" in the as-built PMS will manual initiation the "Alert" column be performed using controls are actuated.

can be retrieved in real or simulated test i) The plant the MCR. The fixed signals. An parameters listed in position controls operational test of the Table 2.5.2-5 with a listed with a "Yes" in as-built PMS will be "Yes" in the "Display" the "Control" column performed. An column, can be are provided in the operational test of the retrieved in the MCR.

MCR. 8.c) Displays as-built PMS will be iii) For each test of an of the open/closed performed. With one as-built fixed position status of the reactor channel in bypass, an control listed in Table trip breakers can be attempt will be made 2.5.2-5 with a "Yes" in retrieved in the MCR. to place a redundant the "Control" column, 9.a) The PMS channel in bypass. an actuation signal is automatically generated. Tests from removes blocks of the actuation signal to reactor trip and the actuated device(s) engineered safety are performed as part features actuation of the system-related 60

when the plant inspection, test, approaches analysis and conditions for which acceptance criteria.

the associated Displays of the function is designed open/closed status of to provide protection. the reactor trip These blocks are breakers can be identified in Table retrieved in the MCR.

2.5.2-6. 9.b) The The PMS blocks are PMS two-out-of-four automatically removed initiation logic reverts when the test signal to a two-out-of-three reaches the specified coincidence logic if limit. The PMS two-one of the four out-of-four initiation channels is logic reverts to a two-bypassed. All out-of-three bypassed channels coincidence logic if are alarmed in the one of the four MCR. 9.c) The channels is bypassed.

PMS does not allow All bypassed channels simultaneous bypass are alarmed in the of two redundant MCR. The redundant channels. channel cannot be placed in bypass.

532 2.5.02.06c. 6.c) The PMS An operational test of i) The reactor trip i provides manual the as-built PMS will switchgear opens after initiation of reactor be performed using manual reactor trip trip and selected the PMS manual controls are actuated.

engineered safety actuation controls.

features as identified in Table 2.5.2-4.

540 2.5.02.08a. 8.a) The PMS ii) An inspection and ii) The plant ii provides for the test will be performed parameters listed in minimum inventory of to verify that the plant Table 2.5.2-5 with a displays, visual alerts, parameters are used "Yes" in the "Alert" and fixed position to generate visual column are used to controls, as identified alerts that identify generate visual alerts in Table 2.5.2-5. The challenges to critical that identify challenges plant parameters safety functions. to critical safety listed with a "Yes" in functions. The visual the "Display" column alerts actuate in and visual alerts accordance with their listed with a "Yes" in correct logic and values.

61

the "Alert" column can be retrieved in the MCR. The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR.

543 2.5.02.08b. 8.b) The PMS ii) An operational test ii) Actuation of each ii provides for the of the as-built system transfer switch results transfer of control will be performed to in an alarm in the capability from the demonstrate the MCR and RSW, the MCR to the RSW transfer of control activation of operator using multiple capability from the control capability from transfer switches. MCR to the RSW. the RSW, and the Each individual deactivation of transfer switch is operator control associated with only capability from the a single safety- MCR for the related group or with associated safety-nonsafety-related related division and control capability. nonsafety-related control capability.

548 2.5.02.09d 9.d) The PMS An operational test of Appropriate PMS provides the interlock the as-built PMS will output signals are functions identified in be performed using generated as the Table 2.5.2-7. real or simulated test interlock conditions signals. are changed.

603 2.6.03.04c 4.c) Each IDS 24- Testing of each 24- The battery terminal hour battery bank hour asbuilt battery voltage is greater than supplies a dc bank will be performed or equal to 210 V after switchboard bus load by applying a a period of no less for a period of 24 simulated or real load, than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with an hours without or a combination of equivalent load that recharging. 4.d) simulated or real loads equals or exceeds the Each IDS 72-hour which envelope the battery bank design battery bank supplies battery bank design duty cycle capacity.

a dc switchboard bus duty cycle. The test The battery terminal load for a period of 72 will be conducted on a voltage is greater than hours without battery bank that has or equal to 210 V after recharging. 4.e) The been fully charged and a period of no less IDS spare battery has been connected to than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with an bank supplies a dc a battery charger equivalent load that load equal to or maintained at 270+/-2 V equals or exceeds the greater than the most for a period of no less battery bank design severe switchboard than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to duty cycle capacity.

bus load for the the test. Testing of The battery terminal required period each 72-hour as-built battery bank will be 62

without recharging. performed by applying voltage is greater than 4.f) Each IDS 24-hour a simulated or real or equal to 210 V after inverter supplies its load, or a combination a period with a load ac load. 4.g) Each of simulated or real and duration that IDS 72-hour inverter loads which envelope equals or exceeds the supplies its ac load. the battery bank most severe battery 4.h) Each IDS 24- design duty cycle. The bank design duty cycle hour battery charger test will be conducted capacity. Each 24-provides the PMS on a battery bank that hour inverter supplies with two loss-of-ac has been fully charged a line-to-line output input voltage signals. and has been voltage of 208 +/- 2% V 5.a) Each IDS 24- connected to a battery at a frequency of 60 +/-

hour battery charger charger maintained at 0.5% Hz. Each 72-supplies a dc 270+/-2 V for a period of hour inverter supplies switchboard bus load no less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a line-to-line output while maintaining the prior to the test. voltage of 208 +/- 2% V corresponding battery Testing of the as-built at a frequency of 60 +/-

charged. 5.b) Each spare battery bank will 0.5% Hz. Two PMS IDS 72-hour battery be performed by input signals exist from charger supplies a dc applying a simulated each 24-hour battery switchboard bus load or real load, or a charger indicating loss while maintaining the combination of of ac input voltage corresponding battery simulated or real loads when the loss-of-input charged. 5.c) Each which envelope the voltage condition is IDS regulating most severe of the simulated. Each 24-transformer supplies division batteries hour battery charger an ac load when design duty cycle. The provides an output powered from the 480 test will be conducted current of at least 150 V MCC. 6. Safety- on a battery bank that A with an output related displays has been fully charged voltage in the range identified in Table and has been 210 to 280 V. Each 2.6.3-1 can be connected to a battery 72-hour battery retrieved in the MCR. charger maintained at charger provides an

11. Displays of the 270+/-2 V for a period of output current of at parameters identified no less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> least 125 A with an in Table 2.6.3-2 can prior to the test. output voltage in the be retrieved in the Testing of each 24- range 210 to 280 V.

MCR. hour as-built inverter Each regulating will be performed by transformer supplies a applying a simulated line-to-line output or real load, or a voltage of 208 +/- 2% V.

combination of Safety-related displays simulated or real identified in Table loads, equivalent to a 2.6.3-1 can be resistive load greater retrieved in the MCR.

than 12 kW. The Displays identified in inverter input voltage Table 2.6.3-2 can be will be no more than retrieved in the MCR.

63

210 Vdc during the test. Testing of each 72-hour as-built inverter will be performed by applying a simulated or real load, or a combination of simulated or real loads, equivalent to a resistive load greater than 7 kW. The inverter input voltage will be no more than 210 Vdc during the test. Testing will be performed by simulating a loss of input voltage to each 24-hour battery charger. Testing of each as-built 24-hour battery charger will be performed by applying a simulated or real load, or a combination of simulated or real loads. Testing of each 72-hour as-built battery charger will be performed by applying a simulated or real load, or a combination of simulated or real loads. Testing of each as-built regulating transformer will be performed by applying a simulated or real load, or a combination of simulated or real loads, equivalent to a resistive load greater than 30 kW when powered from the 480 V MCC. Inspection will be performed for retrievability of the safety-related displays 64

in the MCR.

Inspection will be performed for retrievability of the displays identified in Table 2.6.3-2 in the MCR.

609 2.6.03.04i 4.i) The IDS supplies Testing will be A report exists and an operating voltage performed by concludes that IDS at the terminals of the measuring the voltage can provide a voltage Class 1E motor during motor starting greater than or equal operated valves at both the IDS battery to each valve's identified in and motoroperated minimum design subsections 2.1.2, valve motor terminals voltage to the motor 2.2.1, 2.2.2, 2.2.3, while each terminals of each 2.2.4, 2.3.2, 2.3.6, motoroperated valve motoroperated valve and 2.7.1 that is is stroked. Analyses when power is greater than or equal will be performed to supplied under design to the minimum verify that the voltage conditions from IDS design voltage. at the motoroperated batteries with battery valve motor terminals terminal voltage at 210 is greater than or Vdc while each equal to the minimum motoroperated valve design voltage of each is stroked.

motoroperated valve with an IDS battery terminal voltage of 210 Vdc.

65

644 2.6.09.05a 5.a) Security alarm Test, inspection, or a Security alarm annunciation and combination of test annunciation and video assessment and inspections of the video assessment information is installed systems will information is displayed be performed. Tests displayed concurrently concurrently in the will be performed on in the central alarm central alarm station intrusion detection and station and the and the secondary assessment secondary alarm alarm station, and the equipment. station, and the video video image image recording with recording with real real time playback time playback capability provides capability can provide assessment of assessment of activities before and activities before and after alarm after each alarm annunciation within the annunciation within perimeter barrier. The the perimeter area intrusion detection barrier. 15.b) system concurrently Intrusion detection provides visual and assessment displays and audible systems concurrently annunciations of provide visual alarms in both the displays and audible central and secondary annunciation of alarm stations.

alarms in the central and secondary alarm stations.

647 2.6.09.06 6. The vehicle barrier Inspections and The vehicle barrier system is installed analysis will be system will protect and located at the performed for the against the DBT necessary stand-off vehicle barrier system. vehicle bombs based distance to protect upon the stand-off against the DBT distance of the vehicle bombs. system.

650 2.6.09.08 8. Isolation zones and Inspection of the The illumination in exterior areas within illumination in the isolation zones and the protected area isolation zones and exterior areas within are provided with external areas of the the protected area is illumination to permit protected area will be 0.2 foot candles observation of performed. measured horizontally abnormal presence or at ground level or, activity of persons or alternatively, sufficient vehicles. to permit observation.

66

655 2.6.09.15a 15.a) Security alarm A test will be A report exists and devices, including performed to verify concludes that security transmission lines to that security alarms, alarm devices, annunciators, are including transmission including transmission tamper indicating and lines to annunciators, lines to annunciators, self-checking (e.g., are tamper indicating are tamper indicating an automatic and selfchecking and selfchecking indication is provided (e.g., an automatic (e.g., an automatic when failure of the indication is provided indication is provided alarm system or a when failure of the when failure of the component occurs, or alarm system or a alarm system or a when on standby component occurs, or component occurs, or power). Alarm when on standby when the system is on annunciation shall power) and that alarm standby power) and indicate the type of annunciation indicates that alarm alarm (e.g., intrusion the type of alarm (e.g., annunciation indicates alarms and intrusion alarms and the type of alarm (e.g.,

emergency exit emergency exit intrusion alarms and alarm) and location. alarms) and location. emergency exit

16. Equipment exists Test, analysis, or a alarms) and location.

to record onsite combination of test A report exists and security alarm and analysis will be concludes that annunciation, performed to ensure equipment is capable including the location that equipment is of recording each of the alarm, false capable of recording onsite security alarm alarm, alarm check, each onsite security annunciation, including and tamper alarm annunciation, the location of the indication; and the including the location alarm, false alarm, type of alarm, of the alarm, false alarm check, and location, alarm circuit, alarm, alarm check, tamper indication; and date, and time. and tamper indication; the type of alarm, and the type of alarm, location, alarm circuit, location, alarm circuit, date, and time.

date, and time.

659 C.2.6.09.0 2. Physical barriers An inspection of the Physical barriers at the 2 for the protected area protected area perimeter of the perimeter are not part perimeter barrier will protected area are of vital area barriers. be performed. separated from any other barrier designated as a vital area barrier.

67

660 C.2.6.09.0 3.a) Isolation zones Inspections will be Isolation zones exist in 3a exist in outdoor areas performed of the outdoor areas adjacent to the isolation zones in adjacent to the physical barrier at the outdoor areas physical barrier at the perimeter of the adjacent to the perimeter of the protected area that physical barrier at the protected area and allows 20 feet of perimeter of the allow 20 feet of observation on either protected area. observation and side of the barrier. assessment of the Where permanent activities of people on buildings do not allow either side of the a 20foot observation barrier. Where distance on the inside permanent buildings of the protected area, do not allow a 20foot the building walls are observation and immediately adjacent assessment distance to, or an integral part on the inside of the of, the protected area protected area, the barrier. building walls are immediately adjacent to, or an integral part of, the protected area barrier and the 20foot observation and assessment distance does not apply.

68

661 C.2.6.09.0 3.b) The isolation Inspections will be The isolation zones 3b zones are monitored performed of the areThe isolation zones with intrusion intrusion detection are equipped with detection equipment equipment within the intrusion detection that provides the isolation zones. Tests, equipment that capability to detect inspections or a provides the capability and assess combination of tests to detect and assess unauthorized and inspections of the unauthorized persons.

persons. 4. The intrusion detection and The intrusion detection intrusion detection assessment and assessment and assessment equipment at the equipment at the equipment at the protected area protected area protected area perimeter and its perimeter: a) detects perimeter: a) detects uninterruptible power penetration or penetration or supply will be attempted penetration attempted penetration performed. Tests, of the protected area of the protected area inspections or a barrier and barrier and combination of tests concurrently alarms in concurrently alarms and inspections of the the Central Alarm in both the Central intrusion detection and Station and Secondary Alarm Station and assessment Alarm Station; b)

Secondary Alarm equipment at the remains operable from Station; b) remains protected area an uninterruptible operable from an perimeter and its power supply in the uninterruptible power uninterruptible power event of the loss of supply in the event of supply will be normal power.

the loss of normal performed. equipped with power. intrusion detection equipment that provides the capability to detect and assess unauthorized persons.

664 C.2.6.09.0 5. Access control Tests, inspections, or The access control 5a points are established combination of tests points for the to: a) control and inspections of protected area: a) are personnel and vehicle installed systems and configured to control access into the equipment at the personnel and vehicle protected area. b) access control points access. b) include detect firearms, to the protected area detection equipment explosives, and will be performed. that is capable of incendiary devices at Tests, inspections, or detecting firearms, the protected area combination of tests incendiary devices, personnel access and inspections of and explosives at the points. installed systems and protected area equipment at the personnel access access control points points.

to the protected area will be performed.

69

666 C.2.6.09.0 6. An access control A test of the access The access 6 system with control system with authorization system numbered picture numbered picture with numbered picture badges is installed for badges will be badges can identify use by individuals performed. and authorize who are authorized protected area and access to protected vital area access only areas and vital areas to those personnel without escort. with unescorted access authorization.

670 C.2.6.09.0 9. Emergency exits Tests, inspections, or Emergency exits 9 through the protected a combination of tests through the protected area perimeter are and inspections of area perimeter are alarmed and secured emergency exits alarmed and secured with locking devices through the protected by locking devices that to allow for area perimeter will be allow prompt egress emergency egress. performed. Test, during an emergency.

9. Emergency exits inspection, or a The emergency exits through the vital area combination of tests through the vital area boundaries are and inspections of the boundaries are locked, locked, alarmed, and emergency exits alarmed, and equipped with a crash through the vital area equipped with a crash bar to allow for boundaries will be bar to allow for emergency egress. performed. emergency egress.

815 3.3.00.10.i 10. The shield i) A test will be i) A report exists and building roof and PCS performed to measure concludes that total storage tank support the leakage from the water flow from the and retain the PCS PCS storage tank leak chase collection water sources. The based on measuring system does not PCS storage tank has the water flow out of exceed 10 gal/hr.

a stainless steel liner the leak chase which provides a collection system.

barrier on the inside surfaces of the tank.

Leak chase channels are provided on the tank boundary liner welds.

877 2.2.05.09c 9.c) The MCR Load Testing will be The MCR Load Shed Shed Panels performed on the MCR Panels identified in identified in Table Load Shed Panels Table 2.2.5-1 perform 2.2.5-1 perform their listed in Table 2.2.5-1 their active safety active safety function using real or simulated function identified in after receiving a signals into the PMS. the table after signal from the PMS. receiving a signal from the PMS.

70