ND-22-0253, Submittal of Preservice Test Plan - Version 4.0

Submittal of Preservice Test Plan - Version 4.0

ML22102A114
Person / Time
Site:	Vogtle
Issue date:	04/07/2022
From:	Chamberlain A Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-22-0253
Download: ML22102A114 (131)

Text

Southern Nuclear Operating Company, Inc.

A Southern Nuclear 3535 Colonnade Parkway Birmingham, AL 35243 Tel 205.992.7079 April 7, 2022 Docket Nos.: 52-025 ND-22-0253 52-026 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 Submittal of Preservice Test Plan - Version 4.0 Ladies and Gentlemen:

In accordance with the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), Subparagraph ISTA-3200, and Southern Nuclear Operating Company (SNC) procedures, SNC is submitting, for your information, a copy of the Vogtle Electric Generating Plant Units 3 and 4 Preservice Test Plan Version 4.0.

This version replaces Version 3.0 of the Preservice Test Plan submitted June 3, 2020 (ADAMS No.

ML20155K908). This version adds a note for MSS-V001, V002, V003, V004, V005, V006, SGS-V040A/B, and V057A/B to clarify testing, revises normal positions of PCS-V042, V044, and V046, adds augmented testing for SFS-V042, V045, and V049, revises designations for snubbers in supports which contain multiple snubbers, and includes revised references, and various editorial and grammatical revisions.

This letter contains no regulatory commitments. This letter has been reviewed and confirmed to contain no security-related information.

Should you have any questions, please contact Ms. Amy Chamberlain at (205) 992-6361.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY Amy C. Chamberlain Manager, Regulatory Affairs Southern Nuclear Operating Company : Vogtle Electric Generating Plant Units 3&4, Preservice Test Plan Version 4.0

U.S. Nuclear Regulatory Commission ND-22-0253 Page 2 of 3 cc:

Southern Nuclear Operating Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosure)

Mr. P. P. Sena III (w/o enclosure)

Mr. H. Nieh (w/o enclosures)

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J. B. Williams Mr. D. L. McKinney (w/o enclosure)

Mr. T. W. Yelverton (w/o enclosure)

Mr. B. H. Whitley Ms. C. A. Gayheart Ms. M. Ronnlund Ms. J. M. Coleman Mr. C. T. Defnall Ms. A. C. Chamberlain Mr. S. Leighty Ms. K. Roberts Mr. J. Haswell Mr. A. S. Parton Mr. A. Nix Mr. T.M. Drouin Document Services RTYPE: VND.LI.L00 File AR.01.02.06 Nuclear Regulatory Commission Mr. M. King (w/o enclosure)

Mr. G. Bowman Ms. M. Bailey (w/o enclosures)

Ms. A. Veil Mr. V. Hall Mr. G.J. Khouri Mr. G. Armstrong Mr. C. Patel Mr. C. Santos Mr. B. Kemker Mr. J. Eargle Mr. C. J. Even Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. M. Webb Mr. B. Gleaves

U.S. Nuclear Regulatory Commission ND-22-0253 Page 3 of 3 Nuclear Regulatory Commission (continued)

Mr. T. Fredette Ms. K. McCurry Mr. B. Davis Mr. J. Parent Mr. B. Griman Mr. P. OBryan State of Georgia Mr. R. Dunn Oglethorpe Power Corporation Mr. M. W. Price Mr. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Mr. L. Oriani (w/o enclosure)

Mr. T. Rubenstein (w/o enclosure)

Mr. M. Corletti Mr. D. Hawkins Ms. S. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. A. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

Southern Nuclear Operating Company ND-22-0253 Enclosure 1 Vogtle Electric Generating Plant Units 3 and 4 Preservice Test Plan Version 4.0 (April 2022)

(This enclosure consists of 127 pages, not including this cover page.)

PRESERVICE TEST PLAN Vogtle Electric Generating Plant Units 3&4 Docket Nos.52-025 & 52-026 License Nos. NPF-91 & 92 March 28, 2022 Commercial Operation dates: TBD (Unit 3)

TBD (Unit 4)

Owner: Southern Nuclear Operating Company Inc.

Post Office Box 1295 Birmingham, AL 35201-1295 Plant Location: 7825 River Road Waynesboro, GA 30830 Southern Nuclear Version 4.0

TABLE OF CONTENTS Section Pages 1.0 PST PROGRAM INTRODUCTION 3-4 2.0 ABBREVIATIONS 5-7 3.0 PROGRAM ALTERNATIVES 8 - 14 4.0 PRESERVICE TESTING OF PUMPS 15 5.0 PRESERVICE TESTING OF VALVES 16 6.0 VALVE NOTES 17 7.0 VEGP-3 VALVE TABLES 18 - 61 8.0 VEGP-4 VALVE TABLES 62 - 105 9.0 PRESERVICE TESTING OF DYNAMIC RESTRAINTS 106 10.0 DYNAMIC RESTRAINTS NOTES 107 11.0 VEGP-3 DYNAMIC RESTRAINTS TABLES 108 - 115 12.0 VEGP-4 DYNAMIC RESTRAINTS TABLES 116 - 123 13.0 REFERENCE LIST 124 - 127 2

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1.0 PST PROGRAM INTRODUCTION 1.1 GENERAL This document describes the Pump, Valve, and Dynamic Restraint Preservice Testing (PST) Plan for the Vogtle Electric Generating Plant (VEGP), Units 3 & 4. Provided below are important dates relative to the PST Plan.

Combined Operating License: February 10, 2012 (Unit 3); February 10, 2012 (Unit 4)

Estimated Commercial Operation: September 2022(Unit 3); February 2023 (Unit 4) 1.2 CODE EDITION This PST Plan is based on the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code 2012 Edition, which was approved for use in 10 CFR 50.55a effective August 17, 2017.

1.3 EFFECTIVE DATE The PST plan will begin on the date of the submittal of this plan and conclude with the initial electrical generation by nuclear heat on each unit, unless federal regulations are revised otherwise.

1.4 SCOPE This document is a description of the PST Plan for Units 3 and 4 at VEGP. This document describes only the PST required by the OM Code for applicable components required to be tested by the OM Code, 10CFR50.55a, and additional components committed to be included in the PST plan in the Updated Final Safety Analysis Report (UFSAR).

To ensure that components that meet the Scope requirements of the OM Code, but may not be required to be constructed to ASME B&PV Code Class 1, 2 or 3, are adequately tested for operational readiness as required by 10CFR50.55a(f)(4), this PST plan includes all Safety Related (AP1000 Quality group A, B, C) pumps, valves and dynamic restraints that meet the Scope of ISTA-1100, and ISTF-1100.

1.5 SUBSEQUENT PLAN REVISIONS It is anticipated that revisions to this document required by changes to the design during the Preservice Test Period will be maintained on site. Any changes which require NRC approval of Alternative testing requirements will be submitted in accordance with 10CFR50.55a(z).

1.6 RESPONSIBILITY Southern Nuclear Operating Company (SNC) bears the overall responsibility for the implementation of the Preservice testing activities contained in this program per the ASME OM Code, Subsection ISTA-1500.

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1.7 RECORDS Records and documentation of information and testing results, which provided the basis for evaluation and which facilitate comparison with results from previous and subsequent tests, will be maintained and available for the active life of the component or system in accordance with the ASME OM Code, Subsection ISTA-9000.

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2.0 ABBREVIATIONS ABBREVIATION DEFINITION A Active (valve table)

A OM Code Category A Valve AC OM Code Categories A and C both apply ADS Automatic Depressurization System AI As-Is Alt Alternative per 10CFR50.55a(z)

AO Air Operated A/P Active/Passive (valve table)

App Appendix App. J Leak rate testing to 10CFR50 Appendix J requirements (CIV)

ASME American Society of Mechanical Engineers ASME OM Code ASME Operation and Maintenance of Nuclear Power Plants Code Aug Augmented scope (not required by ASME OM Code)

B OM Code Category B Valve BA Ball Valve BU Butterfly Valve C OM Code Category C Valve C Close/Closed CAS Compressed Air System Cat Category CC Code Case CCS Component Cooling Water System CFR Code of Federal Regulations CK Check Valve CIV Containment Isolation Valve CKC Check Valve Closed CKO Check Valve Open CKOP Check Valve Partial Opening CMT Core Make-up Tank Co-Ord. Coordinate CVS Chemical and Volume Control System CV Check Valve D OM Code Category D Valve DVI Direct Vessel Injection DWS Demineralized Water System 5

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EH Electro-Hydraulic Operated ETM Exercise Test Manual Valve (Full stroke)

FHS Fuel Handling System FPS Fire Protection System FST Fail-Safe Test GA Gate Valve GL Globe Valve H Hydraulic Snubber IRC Inside Reactor Containment building IRWST In-Containment Refueling Water Storage Tank LC Locked Closed LO Locked Open LT Leak Test MA Manual Operator MO Motor Operated MSS Main Steam System MTS Main Turbine System N No NA Not Applicable O Open ORC Outside Reactor Containment building P Passive (valve basis table)

PCS Passive Containment Cooling System PH Pneumatic/Hydraulic PI Remote Position Indication Verification PIV Pressure Isolation Valve (see UFSAR Table 3.9-18)

PORV Power Operated Relief Valve PL Plug Valve PSS Primary Sampling System PWS Potable Water System PXS Passive Core Cooling System 6

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RCS Reactor Coolant System RD Rupture Disc RNS Normal Residual Heat Removal System RRD Replace Rupture Disc RV Relief Valve RVT Relief Valve Test SA Self-Actuating SC Stop Check valve SDS Sanitary Drainage System SFS Spent Fuel Pool Cooling System SGS Steam Generation System SO Solenoid Operated SQ Squib (explosively actuated) Valve STC Stroke Time Closed test STO Stroke Time Open test VB Vacuum Breaker VBS Nuclear Island Non-Radioactive Ventilation System VE Visual Examination VES Main Control Room Emergency Habitability System VFS Containment Air Filtration System VWS Central Chilled Water System WLS Liquid Radioactive Waste System Y Yes III-3100 MOV capability verification per ASME OM Code App. III-3100 III-3300 MOV Preservice test per ASME OM Code App. III-3300 7

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3.0 PROGRAM ALTERNATIVES 3.1 ALTERNATIVES This section identifies the Alternatives to the requirements of 10CFR50.55a and the OM Code requested under 10 CFR 50.55a(z) and approved by the NRC.

Alternative VEGP 3&4-PST-Alt-01 to the PST plan, regarding charge testing of explosively actuated valves was authorized by the NRC on 3/26/2019 and is attached.

Alternative VEGP 3&4-PST-Alt-02 to the PST plan, regarding testing of Class 1 safety valves before initial electric power generation, was authorized by the NRC on 5/28/2019 and is attached.

3.2 CODE CASES This section identifies the Code Cases, and associated limitations, that are incorporated in this PST plan.

No Code Cases are currently used in this PST plan.

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Alternative VEGP3&4-PST-Alt-01 Vogtle Electric Generating Plant (VEGP) - Units 3 and 4 Plant Site-Unit:

Interval-Interval Applies to the preservice testing period.

Dates:

Approval Date: March 26, 2019.

ASME Code Components ASME Class 1 and 3 Explosively Actuated Valves.

Affected:

Applicable Code Edition and ASME OM Code, 2012 Edition (Code of Record).

Addenda:

ASME OM Code, ISTC-3100(d)(2) requires that for post-2000 plants, Category D explosively actuated valves shall be preservice tested as follows:

Select a sample of at least 20% of the pyrotechnic charges in all valves to be Applicable Code tested. Test each selected charge either in the valve, or a qualified test fixture Requirements: to confirm the capability of each sampled charge to provide the necessary motive force to operate the valve to perform its intended function without damage to the valve body or connected piping. The sampling must include at least one explosively actuated valve from each redundant safety train.

Based on the ASME OM Code definition of preservice test, which states test performed after completion of construction activities related to the Reason for component, and the statement in ISTC-3100(d)(2) that Pyrotechnic Request: charges in all valves, it is implied that the charges must be installed in the valves, and the valves be installed in the system, prior to selection of the charges for testing. Handling of explosive charges exposes personnel to significant risks. Since the charges are fabricated and shipped separately, and the testing will be done by the vendor or another offsite test facility, the current requirements would involve shipping of the charges to the site, installation of the charges in the valves (which would be installed in the 9

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piping, in containment), removal of the charges, and shipment of the charges back to the vendor or other test facility.

To minimize handling and transportation of explosive charges, it is proposed to select the charges after fabrication and retain for testing at the vendor, or in the worst case, ship them from the vendor to a separate facility for testing.

Proposed Alternative:

In lieu of the requirements of ISTC-3100(d)(2), perform the following:

Select a sample of pyrotechnic charges, following fabrication for testing; this may include charges used for qualification of the batch. The sample shall include a quantity of charges equal to at least 20% of the number of charges of each size installed in the plant and shall include at least one from each manufacturer batch. A description of SNCs planned testing relative to the Code requirements is shown in Table 1 below. Each selected charge shall be tested in a qualified test fixture to confirm the capability of each sampled charge to provide the necessary motive force to operate the valve to perform its intended function without damage to the valve body or connected piping.

Proposed Basis for Use:

Alternative and The proposed alternative provides an equivalent level of safety as it ensures Basis for Use: the charges are tested to the same criteria, and that the charges are tested from each batch (manufacturer, lot and size). The allowance of crediting the qualification samples is equivalent to or better than ISTC-5260(d), which only requires test firing of one charge per batch prior to installation as a replacement charge.

The requirement regarding inclusion of one test sample from each train is not applicable, because the charges are selected for testing prior to installation in the valve. However, the selection of charges for installation in valves of each train is random; therefore, the level of testing is equivalent.

The proposed alternative provides improved personnel safety by minimizing the transportation and handling of explosive charges.

Because the proposed alternative tests an equivalent number of pyrotechnic charges to the same criteria, this proposed alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1).

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Duration of Proposed Preservice testing conducted prior to commercial operation.

Alternative:

References:

None.

Table 1: Vogtle 3&4 Planned Explosively Actuated Valve Charge Testing per Purchase Specification Number in plants (number per unit IST Number to Number Batch Charge size x units) (20%) IST (1/train) be Tested Fabricated A 14 valves 8 (4 x 2) 2 4 8 16 B 8 valves - 12 (6 x 2) 3 6 8 20 high C 8 valves - 4 (2 x 2) 1 2 8 12 low Notes:

1. Each charge size is a single batch

2. There are two sizes of charges for the 8 explosively actuated valves, high energy and low energy 11 Southern Nuclear Version 4.0

Alternative VEGP3&4-PST-Alt-02 Plant Site-Unit: Vogtle Electric Generating Plant (VEGP) - Units 3 and 4 Interval-Interval Applies to the preservice testing period.

Dates:

Date Authorized: May 28, 2019 ASME Code Components ASME Class 1 Safety Valves.

Affected:

Applicable Code Edition and ASME OM Code, 2012 Edition (code of record).

Addenda:

ASME OM Code, I-7210 requires Class 1 safety valve testing. Within 6 months before initial reactor criticality, each valve shall have its set-pressure verified.

Applicable Code Set-pressure verification shall be determined by pressurizing the system up to Requirements:

the valve set-pressure and opening the valve, or the valve may be tested at or below normal system operating pressures with an assist device.

The existing Code requirement implies that the safety valves be tested in place. The valves are located on top of the pressurizer. Due to the temperature environment of this location, testing of the safety valves Reason for Request: presents a personnel safety issue to personnel performing the testing as it involves activities such as use of an assist device and installation of a gag on the valve not being tested.

Also, the timing requirement of within 6 months before initial criticality provides potential scheduling issues. If the 6 months expires just before initial criticality, the plant would be in a hot, pressurized condition and would have to be cooled down and depressurized to replace the valves. Tying testing to the fuel load milestone is favorable since, for potential delays that 12 Southern Nuclear Version 4.0

push the fuel load date outside of the proposed 3 month test requirement, the plant would be in a cold and depressurized condition, and the valves could be removed and replaced without having to put a thermal cycle on the plant with the associated time delays of cooling down/depressurizing and subsequent return to normal operating temperature and pressure.

Per discussions with the Appendix I Sub-Group, the purpose of this requirement is to ensure that the plant is started up with safety valves with recently verified setpoints and to ensure that valves do not go an excessive time prior to retesting if initial startup is prolonged. Additionally, they believe that I-7210 was not meant to preclude the use of pretested valves. The use of pretested valves is allowed per I-1320 in lieu of in place testing for routine inservice testing.

Proposed Alternative:

In lieu of performing setpoint testing with the valve installed in the system within 6 months before initial criticality in accordance with I-7210, Class 1 Safety Valves shall be replaced with Pretested valves. The set-pressure test of the valves shall not be more than 3 months prior to the commencement of Initial Fuel loading. The initial testing per I-1320, shall be no longer than 24 months from the date of the set-pressure verification test.

Basis for Use:

The Class 1 safety relief valves are Crosby, model number HB-BP-86. This Proposed manufacturer and model have been commonly used in the nuclear industry in Alternative and this application and have a history of acceptable performance with regards to Basis for Use: setpoint drift.

The proposed alternative provides an equivalent level of safety as it ensures that the safety valves setpoints will be verified recently prior to beginning of fuel loading and subsequent initial startup activities, and that inservice valve testing is not extended past the normal frequency, even if the startup process prior to Initial Generation of Electricity by nuclear heat is prolonged. This alternative provides the additional benefit of improving personnel safety by not having personnel in a heat stress environment to perform in-place testing.

If the schedule of startup activities begins to challenge a testing frequency of 24 months following the preservice test, SNC will evaluate additional setpoint testing prior to startup or performance of a mid-cycle shutdown to ensure inservice testing is performed at the required inservice testing interval. A 13 Southern Nuclear Version 4.0

review was performed of Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) 2.1.02.08a.ii for testing and analysis of safety relief valves in accordance with ASME Section III. This proposed Code alternative does not have any impact on the ITAAC.

Since the proposed alternative is consistent with inservice testing requirements for replacing with pretested valves in accordance with I-1320(b) and the frequency of the first inservice test limits the amount of time between set-pressure verification tests, this proposed alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1).

Duration of Proposed Preservice testing conducted prior to commercial operation.

Alternative:

References:

None.

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4.0 PRESERVICE TESTING OF PUMPS 4.1 GENERAL There are no pumps in the AP1000 design that meet the scoping criteria of ISTF-1100. ISTF-1000 which provides the scoping criteria for pumps to be included in the PST plan, includes only pumps that have an emergency power source. The emergency power source (Class 1E) for the AP1000 is the 1E Vital DC system, and there are no pumps powered from this source.

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5.0 PRESERVICE TESTING OF VALVES 5.1 GENERAL Valves will be tested to meet the PST requirements of the OM Code as outlined in the Valve Tables.

The OM Code identifies exercise testing for valves, where the Code requires additional testing be performed during the valve exercising (e.g. stroke time testing), the exercise test is not separately identified in the Valve Table.

Testing will generally only be performed once during the Preservice Test Period, except when Repair, Replacement, or Maintenance require retesting pursuant to ASME OM ISTC-3100(a)/ISTC-3310/I-7400/III-3400.

5.2 ADDITIONAL TESTING REQUIREMENTS 10CFR50.55a provides conditions to the OM Code with regard to testing of certain valves.

These conditions are met in this PST Plan as outlined below:

5.2.1 To meet the 10CFR50.55a(b)(3)(ii)(D) Condition on MOV stroke time. A stroke time test to the safety position(s) is specified for MOVs in the program.

5.2.2 To meet the 10CFR50.55a(b)(3)(iii)(B) Check valves requiring Licensees must perform bi-directional testing of check valves, is specified in accordance with ISTC-5221 within this PST plan, where practicable.

5.3 SCHEDULE PST will be performed following system turnover from Construction and will be completed prior to initial electrical generation by nuclear heat.

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6.0 VALVE NOTES

1. Valves MSS-V001, V002, V003, V004, V005, V006, SGS-V040A/B, and SGS-V056A/B have two separate solenoid valves from separate safety trains. Stroke time testing is required using each solenoid valve.

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7.0 VEGP-3 VALVE TABLES 18 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: CAS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-CAS-PL-V014 2 N A A 2 BA AO SV3-CAS-M6-005 O C C PI (ISTC-3700)

(F-3) STC FST Instrument Air Containment Isolation Valve LT-App. J SV3-CAS-PL-V015 2 N AC A 2 CK SA SV3-CAS-M6-005 O C/O NA CKC (F-4) CKOP Accommodate thermal expansion Instrument Air Containment Isolation Check Valve LT-App. J SV3-CAS-PL-V204 2 N A P 3 BA MA SV3-CAS-M6-012 LC C C LT-App. J Service Air Containment Isolation Valve (E-5)

SV3-CAS-PL-V205 2 N AC A 3 CK SA SV3-CAS-M6-012 C C/O NA CKC (E-4) CKOP Accommodate thermal expansion Service Air Containment Isolation Check Valve LT-App. J 19 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: CCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-CCS-PL-V200 2 N A A 10 BU MO SV3-CCS-M6-002 O C AI PI (III-3300)

(H-2) STC III-3100 III-3300 Cooling Water Supply Ctmt Isol- ORC LT-App. J SV3-CCS-PL-V201 2 N AC A 10 CK SA SV3-CCS-M6-002 O C/O NA CKC (H-2) CKOP Accommodate thermal expansion Cooling Water Ctmt Supply Check LT-App. J SV3-CCS-PL-V207 2 N A A 10 BU MO SV3-CCS-M6-002 O C AI PI (III-3300)

(B-2) STC III-3100 III-3300 Cooling Water Return Ctmt Isol - IRC LT-App. J SV3-CCS-PL-V208 2 N A A 10 BU MO SV3-CCS-M6-002 O C AI PI (III-3300)

(B-1) STC III-3100 III-3300 Cooling Water Return Ctmt Isol - ORC LT-App. J SV3-CCS-PL-V220 2 N AC A 1 RV SA SV3-CCS-M6-002 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (C-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Ctmt Return CIV Thermal Relief LT-App. J SV3-CCS-PL-V270 3 N C A 4 RV SA SV3-CCS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (H-2) RVT(I-7150(c)) Leak tightness per Vendor test CCS Supply Line to Ctmt Safety/Relief VE(I-7150(a))

SV3-CCS-PL-V271 3 N C A 4 RV SA SV3-CCS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (C-2) RVT(I-7150(c)) Leak tightness per Vendor test CCS Return Line to Ctmt Safety/Relief VE(I-7150(a))

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Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-CVS-PL-V001 1 N B A 3 GA MO SV3-CVS-M6-001 O C AI PI (III-3300)

(G-8) STC III-3100 CVS Purification Stop Valve III-3300 SV3-CVS-PL-V002 1 N B A 3 GA MO SV3-CVS-M6-001 O C AI PI (III-3300)

(G-7) STC III-3100 CVS Purification Stop Valve III-3300 SV3-CVS-PL-V003 3 N B A 3 GL MO SV3-CVS-M6-001 O C AI PI (III-3300)

(G-7) STC III-3100 CVS Purification Stop Valve III-3300 SV3-CVS-PL-V040 2 N A P 2 BA MA SV3-CVS-M6-005 LC C AI LT-App. J Resin Flush Inside Containment Isolation Valve (F-4)

SV3-CVS-PL-V041 2 N A P 2 BA MA SV3-CVS-M6-005 LC C AI LT-App. J Resin Flush Outside Containment Isolation Valve (F-2)

SV3-CVS-PL-V042 2 N AC A 1 RV SA SV3-CVS-M6-005 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (G-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Flush Line Containment Isolation Relief Valve LT-App. J SV3-CVS-PL-V045 2 N A A 2 GL AO SV3-CVS-M6-005 C C C PI (ISTC-3700)

(D-4) STC FST Letdown Line Inside Containment Isolation Valve LT-App. J SV3-CVS-PL-V047 2 N A A 2 GL AO SV3-CVS-M6-005 C C C PI (ISTC-3700)

(D-2) STC FST Letdown Line Outside Containment Isolation Valve LT-App. J 21 Southern Nuclear Version 4.0

System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-CVS-PL-V058 2 N AC A 1 RV SA SV3-CVS-M6-005 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (E-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Letdown Line Relief Thermal Relief Valve LT-App. J SV3-CVS-PL-V064 N N C A 3 CK SA SV3-CVS-M6-005 C O NA CKC Make-up Discharge Header Check Valve (C-5) CKOP Accommodate thermal expansion SV3-CVS-PL-V067 1 N C A 1 CK SA SV3-CVS-M6-001 O C/O NA CKC Makeup Return Line Spring-Assisted Check Valve (F-7) CKOP Accommodate thermal expansion SV3-CVS-PL-V080 3 N C A 3 CK SA SV3-CVS-M6-001 O C/O NA CKC Regen HX Shell Side Outlet Check Valve (G-7) CKOP Accommodate thermal expansion SV3-CVS-PL-V081 1 N BC A 3 SC AO SV3-CVS-M6-001 O C NA PI (ISTC-3700)

(G-7) CKC Purification Return Line Stop Check Valve CKOP SV3-CVS-PL-V082 1 N C A 3 CK SA SV3-CVS-M6-001 O C/O NA CKC RCS Purification Return Line Check Valve (G-8) CKOP Accommodate thermal expansion SV3-CVS-PL-V084 1 N B A 2 GL AO SV3-CVS-M6-001 C C C PI (ISTC-3700)

(F-7) STC Auxiliary Pressurizer Spray Line Isolation Valve FST SV3-CVS-PL-V085 1 N C A 2 CK SA SV3-CVS-M6-001 C C/O NA CKC Auxiliary Pressurizer Spray Line Valve (F-8) CKOP Accommodate thermal expansion SV3-CVS-PL-V090 2 N A A 3 GA MO SV3-CVS-M6-005 O C AI PI (III-3300)

(C-2) STC III-3100 III-3300 Makeup Line Outside Containment Isolation Valve LT-App. J SV3-CVS-PL-V091 2 N A A 3 GA MO SV3-CVS-M6-005 O C AI PI (III-3300)

(C-4) STC III-3100 III-3300 Makeup Line Inside Containment Isolation Valve LT-App. J SV3-CVS-PL-V092 2 N A A 1 GL AO SV3-CVS-M6-003 O C C PI (ISTC-3700)

(F-6) STC FST Zinc Injection Containment Isolation Valve ORC LT-App. J 22 Southern Nuclear Version 4.0

System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-CVS-PL-V094 2 N A A 1 GL AO SV3-CVS-M6-003 O C C PI (ISTC-3700)

(F-7) STC FST Zinc Injection Containment Isolation Valve IRC LT-App.

SV3-CVS-PL-V098 2 N AC A 1 RV SA SV3-CVS-M6-003 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (F-6) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Zinc Injection Ctmt Isol Thermal Relief Valve LT-App. J SV3-CVS-PL-V100 2 N AC A 1 CK SA SV3-CVS-M6-005 O C/O NA CKC (B-4) CKOP Accommodate thermal expansion Makeup Line Containment Isolation Relief LT-App. J SV3-CVS-PL-V136A 3 N B A 2 BU AO SV3-CVS-M6-004 C C C PI (ISTC-3700)

(C-4) STC Demineralized Water System Isolation Valve FST SV3-CVS-PL-V136B 3 N B A 2 BU AO SV3-CVS-M6-004 C C C PI (ISTC-3700)

(C-4) STC Demineralized Water System Isolation Valve FST SV3-CVS-PL-V217 2 N AC A 1/2 CK SA SV3-CVS-M6-003 O C/O NA CKC (D-7) CKOP Accommodate thermal expansion Hydrogen Injection Containment Isolation Check Valve IRC LT-App. J SV3-CVS-PL-V219 2 N A A 1/2 GL AO SV3-CVS-M6-003 O C C PI (ISTC-3700)

(D-6) STC FST Hydrogen Injection Containment Isolation Valve ORC LT-App. J 23 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: DWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-DWS-PL-V241 3 N C A 1 RV SA SV3-DWS-M6-007 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (E-5) RVT(I-7150(c)) Leak tightness per Vendor test Demin Water Supply to Containment Relief VE(I-7150(a))

SV3-DWS-PL-V244 2 N A P 3 BU MA SV3-DWS-M6-007 LC C AI LT-App. J Exercised during Shutdown and leaktest Demin Water Supply Containment Isolation - Outside (E-6)

SV3-DWS-PL-V245 2 N AC A 2 CK SA SV3-DWS-M6-007 C C/O NA CKC (E-6) CKOP Accommodate thermal expansion Demin Water Supply Containment Isolation Check Valve - IRC LT-App. J 24 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: FHS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-FHS-PL-V001 3 N B A 30 GA MA SV3-SFS-M6-001 C C AI ETM Fuel Transfer Tube Isolation Valve (F-6) 25 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: FPS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-FPS-PL-V050 2 N A P 6 BU MA SV3-FPS-M6-004 LC C AI LT-App. J Exercised during Shutdown and leaktest Fire Water Containment Supply Isolation (F-5)

SV3-FPS-PL-V052 2 N AC A 6 CK SA SV3-FPS-M6-004 C C/O NA CKC (F-5) CKOP Accommodate thermal expansion Fire Water Supply Cont Isol Check Valve - IRC LT-App. J SV3-FPS-PL-V702 3 N C A 1 RV SA SV3-FPS-M6-004 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (F/G-5) RVT(I-7150(c)) Leak tightness per Vendor test Fire Water Supply IC Thermal Relief VE(I-7150(a))

26 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: MSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-MSS-PL-V001 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-8) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V002 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-7) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V003 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-6) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V004 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-4) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V005 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-3) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V006 N Y B A 16 GL AO SV3-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-2) STC Note 1 Turbine Bypass Control Valve FST SV3-MSS-PL-V015A N Y B A 10 GL AO SV3-MSS-M6-001 O C C PI (ISTC-3700) Required by TS 3.7.2 (B-6) STC MSR 2ND Stage Reheat Steam AO Isolation Valve FST SV3-MSS-PL-V015B N Y B A 10 GL AO SV3-MSS-M6-001 O C C PI (ISTC-3700) Required by TS 3.7.2 (G-6) STC MSR 2ND Stage Reheat Steam AO Isolation Valve FST 27 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: MTS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-MTS-PL-V001A N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (F-6) STC Main Turbine Stop Valve FST SV3-MTS-PL-V001B N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (C-6) STC Main Turbine Stop Valve FST SV3-MTS-PL-V002A N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (F-6) STC Main Turbine Control Valve FST SV3-MTS-PL-V002B N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (C-6) STC Main Turbine Control Valve FST SV3-MTS-PL-V003A N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (E-6) STC Main Turbine Stop Valve FST SV3-MTS-PL-V003B N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (D-6) STC Main Turbine Stop Valve FST SV3-MTS-PL-V004A N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (E-6) STC Main Turbine Control Valve FST SV3-MTS-PL-V004B N Y B A 28 GL EH SV3-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (D-6) STC Main Turbine Control Valve FST 28 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: PCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PCS-PL-V001A 3 N B A 6 BU AO SV3-PCS-M6-001 C O O PI (ISTC-3700)

(E-4) STO PCS Actuation Valve A FST SV3-PCS-PL-V001B 3 N B A 6 BU AO SV3-PCS-M6-001 C O O PI (ISTC-3700)

(E-6) STO PCS Actuation Valve B FST SV3-PCS-PL-V001C 3 N B A 6 GA MO SV3-PCS-M6-001 C O AI PI (III-3300) This valve has a passive closed function (E-5) STO for Spent fuel make-up.

III-3100 PCS Actuation Valve C III-3300 SV3-PCS-PL-V002A 3 N B A 6 GA MO SV3-PCS-M6-001 O O AI PI III-3300) This valve has a passive closed function (E-4) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve A III-3300 SV3-PCS-PL-V002B 3 N B A 6 GA MO SV3-PCS-M6-001 O O AI PI III-3300) This valve has a passive closed function (E-6) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve B III-3300 SV3-PCS-PL-V002C 3 N B A 6 GA MO SV3-PCS-M6-001 O O AI PI (III-3300) This valve has a passive closed function (E-5) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve C III-3300 SV3-PCS-PL-V005 3 N B A 4 GA MA SV3-PCS-M6-002 O C AI ETM PCS to DWS/FPS Iso Valve (G-5)

SV3-PCS-PL-V009 3 N B A 3 GA MA SV3-PCS-M6-001 C C/O AI ETM Open for Emergency SFP make-up Spent Fuel Pool Emergency Makeup Valve (E-4)

SV3-PCS-PL-V015 3 N B A 1 GL MA SV3-PCS-M6-002 O C AI ETM PCS Long Term supply to Distribution Bucket Drain Valve (G-8)

SV3-PCS-PL-V020 3 N B A 3 GA MA SV3-PCS-M6-002 C O AI ETM PCS Long Term supply to Distribution Bucket Iso Valve (G-7) 29 Southern Nuclear Version 4.0

System: PCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PCS-PL-V023 3 N B A 4 GA MA SV3-PCS-M6-002 O C AI ETM PCS Recirc Pumps to PCCWST Iso Valve (F-7)

SV3-PCS-PL-V039 3 N C A 4 CK SA SV3-PCS-M6-002 C O/C NA CKO PCS/SFS Long Term Make-up Supply Check Valve (F-3) CKC SV3-PCS-PL-V042 3 N B A 1 GL MA SV3-PCS-M6-002 C C AI ETM PCS Long Term Supply from Temp Pump Drain Valve (F-3)

SV3-PCS-PL-V044 3 N B A 4 GA MA SV3-PCS-M6-002

• O AI ETM

• Locked one turn from full open PCS Long Term Supply from Temp Pump Iso Valve (F-4)

SV3-PCS-PL-V045 3 N B A 2 GL MA SV3-PCS-M6-001 C O AI ETM PCS Supply to SFS Make-up Iso Valve (B-3)

SV3-PCS-PL-V046 3 N B A 4 GA MA SV3-PCS-M6-002 LO C AI ETM PCCWST Recirculation Return Isolation Valve (H-7)

SV3-PCS-PL-V049 3 N B A 1 GL MA SV3-PCS-M6-001 O C AI ETM PCCWST Drain Isolation Valve (B-2)

SV3-PCS-PL-V050 3 N B A 2 GL MA SV3-PCS-M6-002 C C/O AI ETM Recirc Header Discharge to SFS Pool Isolation Valve (F-7)

SV3-PCS-PL-V051 3 N B A 2 GL MA SV3-PCS-M6-001 C C/O AI ETM Spent Fuel Pool Emergency Makeup Lower Isolation Valve (B-2) 30 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: PSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PSS-PL-V001A 2 N C A 1/4 GL SO SV3-PSS-M6-001 O O C RVT Thermal Relief function Hot Leg 1 Sample Isolation Valve E-8 SV3-PSS-PL-V001B 2 N C A 1/4 GL SO SV3-PSS-M6-001 C O C RVT Thermal Relief function Hot Leg 2 Sample Isolation Valve D-8 SV3-PSS-PL-V003 2 N C A 1/4 GL SO SV3-PSS-M6-001 C O C RVT Thermal Relief function Pressurizer Sample Isolation Valve G-8 SV3-PSS-PL-V008 2 N A A 5/8 GL SO SV3-PSS-M6-001 O C C PI (ISTC-3700)

(D-7) STC FST Containment Air Sample Containment Isolation Valve IRC LT-App. J SV3-PSS-PL-V010A 2 N A AC 1/4 GL SO SV3-PSS-M6-001 O C/O C PI (ISTC-3700)

(D-7) STC FST RVT Thermal Relief function Liquid Sample Line Containment Isolation Valve IRC LT-App. J SV3-PSS-PL-V010B 2 N A AC 1/4 GL SO SV3-PSS-M6-001 C C/O C PI (ISTC-3700)

(G-7) STC FST RVT Thermal Relief function Liquid Sample Line Containment Isolation Valve IRC LT-App. J SV3-PSS-PL-V011A 2 N A A 1/4 GL AO SV3-PSS-M6-001 O C C PI (ISTC-3700)

(E-6) STC FST Liquid Sample Line Containment Isolation Valve ORC LT-App. J SV3-PSS-PL-V011B 2 N A A 1/4 GL AO SV3-PSS-M6-001 C C C PI (ISTC-3700)

(G-6) STC FST Liquid Sample Line Containment Isolation Valve ORC LT-App. J 31 Southern Nuclear Version 4.0

System: PSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PSS-PL-V023 2 N A A 1 GL AO SV3-PSS-M6-001 O C C PI (ISTC-3700)

(C-6) STC FST Sample Return Line Containment Isolation Valve ORC LT-App. J SV3-PSS-PL-V024 2 N A A 1 GL SO SV3-PSS-M6-001 O C C PI (ISTC-3700)

(C-7) STC FST Sample Return Line Containment Isolation Valve IRC LT-App. J SV3-PSS-PL-V046 2 N A A 5/8 GL AO SV3-PSS-M6-001 O C C PI (ISTC-3700)

(D-6) STC FST Air Sample Line Containment Isolation Valve ORC LT-App. J 32 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: PWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PWS-PL-V418 3 N B A 1 GL MA SV3-PWS-M6-002 O C AI ETM Control Room Boundary Outside Isolation Valve (G-4)

SV3-PWS-PL-V420 3 N B A 1 GL MA SV3-PWS-M6-002 O C AI ETM Control Room Boundary Inside Isolation Valve (F-4)

SV3-PWS-PL-V498 3 N C A 1 VB SA SV3-PWS-M6-002 C O NA VE(I-7170)

(F-4) RVT(I-7270(a)) Actuation to verify open/close Control Room Boundary Vacuum Breaker RVT(I-7270(b)) Leak tightness 33 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PXS-PL-V002A 1 N B P 8 GA MO SV3-PXS-M6-001 O O AI PI (ISTC-3700)

RCS to CMT A Isolation Valve (G/H-5)

SV3-PXS-PL-V002B 1 N B P 8 GA MO SV3-PXS-M6-001 O O AI PI (ISTC-3700)

RCS to CMT B Isolation Valve (G/H-4)

SV3-PXS-PL-V013A 1 N B P 8 GA MA SV3-PXS-M6-001 LO O AI PI (ISTC-3700)

CMT A Discharge Manual Isol Valve (D-6)

SV3-PXS-PL-V013B 1 N B P 8 GA MA SV3-PXS-M6-001 LO O AI PI (ISTC-3700)

CMT B Discharge Manual Isol Valve (D-3)

SV3-PXS-PL-V014A 1 N B A 8 GL AO SV3-PXS-M6-001 C O O PI (ISTC-3700)

(E-7) STO CMT A Outlet Valve FST SV3-PXS-PL-V014B 1 N B A 8 GL AO SV3-PXS-M6-001 C O O PI (ISTC-3700)

(E-3) STO CMT B Outlet Valve FST SV3-PXS-PL-V015A 1 N B A 8 GL AO SV3-PXS-M6-001 C O O PI (ISTC-3700)

(D-7) STO CMT A Outlet Valve FST SV3-PXS-PL-V015B 1 N B A 8 GL AO SV3-PXS-M6-001 C O O PI (ISTC-3700)

(D-3) STO CMT B Outlet Valve FST SV3-PXS-PL-V016A 1 N C A 8 CK SA SV3-PXS-M6-001 O O/C NA CKO CMT A outlet to RCS Check (D-6) CKC SV3-PXS-PL-V016B 1 N C A 8 CK SA SV3-PXS-M6-001 O O/C NA CKO CMT B outlet to RCS Check (D-3) CKC SV3-PXS-PL-V017A 1 N C A 8 CK SA SV3-PXS-M6-001 O O/C NA CKO CMT A outlet to RCS Check (D-6) CKC SV3-PXS-PL-V017B 1 N C A 8 CK SA SV3-PXS-M6-001 O O/C NA CKO CMT B outlet to RCS Check (D-3) CKC SV3-PXS-PL-V021A 3 N B P 1 GL SO SV3-PXS-M6-001 C C C PI (ISTC-3700)

Accumulator A Nitrogen supply Valve (C-7) 34 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PXS-PL-V021B 3 N B P 1 GL SO SV3-PXS-M6-001 C C C PI (ISTC-3700)

Accumulator B Nitrogen supply Valve (C-2)

SV3-PXS-PL-V022A 3 N C A 1 RV SA SV3-PXS-M6-001 C O/C NA VE(I-7150(a))

(C-7) RVT(I-7150(b)) Verify Vendor setpoint Accumulator A Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV3-PXS-PL-V022B 3 N C A 1 RV SA SV3-PXS-M6-001 C O/C NA VE(I-7150(a))

(C-2) RVT(I-7150(b)) Verify Vendor setpoint Accumulator B Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV3-PXS-PL-V027A 3 N B P 8 GA MO SV3-PXS-M6-001 O O AI PI (ISTC-3700)

Accumulator A to RCS Isolation Valve (B-6)

SV3-PXS-PL-V027B 3 N B P 8 GA MO SV3-PXS-M6-001 O O AI PI (ISTC-3700)

Accumulator B to RCS Isolation Valve (B-3)

SV3-PXS-PL-V028A 1 N AC A 8 CK SA SV3-PXS-M6-001 C O/C NA CKO (B-6) CKC Accumulator A outlet to RCS Check LT SV3-PXS-PL-V028B 1 N AC A 8 CK SA SV3-PXS-M6-001 C O/C NA CKO (B-3) CKC Accumulator B outlet to RCS Check LT SV3-PXS-PL-V029A 1 N AC A 8 CK SA SV3-PXS-M6-001 C O/C NA CKO (B-6) CKC Accumulator A outlet to RCS Check LT SV3-PXS-PL-V029B 1 N AC A 8 CK SA SV3-PXS-M6-001 C O/C NA CKO (B-4) CKC Accumulator B outlet to RCS Check LT SV3-PXS-PL-V042 2 N A A 1 GL AO SV3-PXS-M6-001 O C C PI (ISTC-3700)

(D-1) STC FST High Pressure Nitrogen to Containment Isolation Valve LT- App. J SV3-PXS-PL-V043 2 N AC A 1 CK SA SV3-PXS-M6-001 C O/C NA CKOP Accommodate thermal expansion (D-2) CKC High Pressure Nitrogen to Containment IC Check Valve LT- App. J SV3-PXS-PL-V044 N N C A 1 RV SA SV3-PXS-M6-001 C O NA VE(I-7150(a))

(D-2) RVT(I-7150(b)) Verify Vendor setpoint High Pressure Nitrogen to Containment Penetration Thermal Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV3-PXS-PL-V101 1 N B P 14 GA MO SV3-PXS-M6-002 O O AI PI (ISTC-3700)

RCS to PRHR Heat Exchanger Isolation Valve (G -1) 35 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PXS-PL-V108A 1 N B A 14 BA AO SV3-PXS-M6-002 C O O PI (ISTC-3700)

(F-1) STO PRHR Heat Exchanger Outlet Valve to RCS A FST SV3-PXS-PL-V108B 1 N B A 14 BA AO SV3-PXS-M6-002 C O O PI (ISTC-3700)

(E-1) STO PRHR Heat Exchanger Outlet Valve to RCS B FST SV3-PXS-PL-V109 1 N B P 14 GA MA SV3-PXS-M6-002 LO O AI PI (ISTC-3700)

PRHR HX/RCS Return Isol Valve (F-1)

SV3-PXS-PL-V117A 3 N B P 8 GA MO SV3-PXS-M6-002 O O AI PI (ISTC-3700)

Containment Recirculation Sump A to RCS Isolation Valve (E-7)

SV3-PXS-PL-V117B 3 N B P 8 GA MO SV3-PXS-M6-002 O O AI PI (ISTC-3700)

Containment Recirculation Sump B to RCS Isolation Valve (E-5)

SV3-PXS-PL-V118A 3 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (E-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V118B 3 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (E-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V119A 3 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(D-7) CKO Containment Recirc. Sump A outlet to RCS Check CKC SV3-PXS-PL-V119B 3 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(D-5) CKO Containment Recirc. Sump B outlet to RCS Check CKC SV3-PXS-PL-V120A 3 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (D-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V120B 3 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V121A 3 N B P 8 GA MO SV3-PXS-M6-002 O O AI PI (ISTC-3700)

IRWST/Recirc Sump to RCS A Isolation Valve (D-7)

SV3-PXS-PL-V121B 3 N B P 8 GA MO SV3-PXS-M6-002 O O AI PI (ISTC-3700)

IRWST/Recirc Sump to RCS B Isolation Valve (D-5)

SV3-PXS-PL-V122A 1 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-7) CKO IRWST/Recirc Sump to RCS A outlet to RCS Check CKC SV3-PXS-PL-V122B 1 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-5) CKO IRWST/Recirc Sump to RCS B outlet to RCS Check CKC 36 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-PXS-PL-V123A 1 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (C-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V123B 1 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V124A 1 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-7) CKO IRWST/Recirc Sump to RCS A outlet to RCS Check CKC SV3-PXS-PL-V124B 1 N C A 8 CK SA SV3-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-5) CKO IRWST/Recirc Sump to RCS B outlet to RCS Check CKC SV3-PXS-PL-V125A 1 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (C-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V125B 1 N D A 8 SQ SQ SV3-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-PXS-PL-V130A 3 N B A 2 BA AO SV3-PXS-M6-002 O C C PI (ISTC-3700)

(H-7) STC Containment Condensation Collection to Containment Sump Isolation Valve A FST SV3-PXS-PL-V130B 3 N B A 2 BA AO SV3-PXS-M6-002 O C C PI (ISTC-3700)

(H-7) STC Containment Condensation Collection to Containment Sump Isolation Valve B FST SV3-PXS-PL-V208A 2 N A P .375 GL MA SV3-PXS-M6-003 LC C C LT-App. J RNS Suction Leak Test Valve (D-3)

SV3-PXS-PL-V230A 2 N B P 1 GL AO SV3-PXS-M6-003 C C C PI (ISTC-3700)

Core Makeup Tank A Fill Isolation (F-6)

SV3-PXS-PL-V230B 2 N B P 1 GL AO SV3-PXS-M6-003 C C C PI (ISTC-3700)

Core Makeup Tank B Fill Isolation (G-6)

SV3-PXS-PL-V231A 2 N C A 1 CK SA SV3-PXS-M6-003 C C C CKOP Accommodate thermal expansion Core Makeup Tank A Fill Check (F-7) CKC SV3-PXS-PL-V231B 2 N C A 1 CK SA SV3-PXS-M6-003 C C C CKOP Accommodate thermal expansion Core Makeup Tank B Fill Check (G-7) CKC SV3-PXS-PL-V232A 3 N B P 1 GL AO SV3-PXS-M6-003 C C C PI (ISTC-3700)

Accumulator B Fill/Drain Isolation (E-6)

SV3-PXS-PL-V232B 3 N B P 1 GL AO SV3-PXS-M6-003 C C C PI (ISTC-3700)

Accumulator B Fill/Drain Isolation (G-6) 37 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RCS-PL-V001A 1 N B A 4 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(G-5) STO III-3100 ADS Stage 1 Control Valve III-3300 SV3-RCS-PL-V001B 1 N B A 4 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(E-5) STO III-3100 ADS Stage 1 Control Valve III-3300 SV3-RCS-PL-V002A 1 N B A 8 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(G-5) STO III-3100 ADS Stage 2 Control Valve III-3300 SV3-RCS-PL-V002B 1 N B A 8 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(E-5) STO III-3100 ADS Stage 2 Control Valve III-3300 SV3-RCS-PL-V003A 1 N B A 8 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(H-5) STO III-3100 ADS Stage 3 Control Valve III-3300 SV3-RCS-PL-V003B 1 N B A 8 GL MO SV3-RCS-M6-002 C O AI PI (III-3300)

(F-5) STO III-3100 ADS Stage 3 Control Valve III-3300 SV3-RCS-PL-V004A 1 N D A 14 SQ SQ SV3-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (G-6) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-RCS-PL-V004B 1 N D A 14 SQ SQ SV3-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-3) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 38 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RCS-PL-V004C 1 N D A 14 SQ SQ SV3-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-6) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-RCS-PL-V004D 1 N D A 14 SQ SQ SV3-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-3) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV3-RCS-PL-V005A 1 N C A 6 RV SA SV3-RCS-M6-002 C O/C NA PI (I-7110(c)/7310(f)) From Vendor test (H-7) RVT(I-7110(b)) Verify Vendor setpoint RVT(I-7110(d)) Leak tightness per Vendor test VE(I-7110(a))

RVT(I-7210) Setpoint verification (due 6m prior to Initial Pressurizer Safety Valve Criticality) Alternative VEGP 3&4-PST-Alt-02 SV3-RCS-PL-V005B 1 N C A 6 RV SA SV3-RCS-M6-002 C O/C NA PI (I-7110(c)/7310(f)) From Vendor test (F-6) RVT(I-7110(b)) Verify Vendor setpoint RVT(I-7110(d)) Leak tightness per Vendor test VE(I-7110(a))

RVT(I-7210) Setpoint verification (due 6m prior to Initial Pressurizer Safety Valve Criticality) Alternative VEGP 3&4-PST-Alt-02 SV3-RCS-PL-V010A 3 N C A 1 VB SA SV3-RCS-M6-002 C O NA VE(I-7170)

(G-4) RVT(I-7270(a)) Actuation to verify open/close ADS Header Vacuum Breaker RVT(I-7270(b)) Leak tightness SV3-RCS-PL-V010B 3 N C A 1 VB SA SV3-RCS-M6-002 C O NA VE(I-7170)

(E-4) RVT(I-7270(a)) Actuation to verify open/close ADS Header Vacuum Breaker RVT(I-7270(b)) Leak tightness SV3-RCS-PL-V011A 1 N B A 4 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (G-5) STO III-3100 ADS Stage 1 Isolation Valve III-3300 SV3-RCS-PL-V011B 1 N B A 4 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (E-5) STO III-3100 ADS Stage 1 Isolation Valve III-3300 SV3-RCS-PL-V012A 1 N B A 8 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (G-5) STO III-3100 ADS Stage 2 Isolation Valve III-3300 39 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RCS-PL-V012B 1 N B A 8 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (E-5) STO III-3100 ADS Stage 2 Isolation Valve III-3300 SV3-RCS-PL-V013A 1 N B A 8 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (H-5) STO III-3100 ADS Stage 3 Isolation Valve III-3300 SV3-RCS-PL-V013B 1 N B A 8 GA MO SV3-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (F-5) STO III-3100 ADS Stage 3 Isolation Valve III-3300 SV3-RCS-PL-V014A 1 N B P 14 GA MO SV3-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (G-6)

SV3-RCS-PL-V014B 1 N B P 14 GA MO SV3-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-3)

SV3-RCS-PL-V014C 1 N B P 14 GA MO SV3-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-6)

SV3-RCS-PL-V014D 1 N B P 14 GA MO SV3-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-3)

SV3-RCS-PL-V150A 1 N B A 1 GL SO SV3-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC FST Reactor Head Vent Valve RVT Thermal Relief function SV3-RCS-PL-V150B 1 N B A 1 GL SO SV3-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC FST Reactor Head Vent Valve RVT Thermal Relief function SV3-RCS-PL-V150C 1 N B A 1 GL SO SV3-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC Reactor Head Vent Valve FST 40 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RCS-PL-V150D 1 N B A 1 GL SO SV3-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC Reactor Head Vent Valve FST SV3-RCS-PL-V233 3 N B P 2 GL MA SV3-RCS-M6-002 O O AI PI (ISTC-3700) Open only indication RV Head Vent to IRWST Isolation Valve (H-3)

SV3-RCS-PY-K03 3 N D A 10 RD SA SV3-RCS-M6-002 C O NA VE(I-7160/7260)

Pressurizer Relief Valve Discharge Line Rupture Disc (H-8)

SV3-RCS-PY-K04 3 N D A 10 RD SA SV3-RCS-M6-002 C O NA VE(I-7160/7260)

Pressurizer Relief Valve Discharge Line Rupture Disc (F-7) 41 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RNS-PL-V001A 1 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(F-2) STC III-3100 III-3300 RNS Suction from RCS Inner Isolation Valve LT SV3-RNS-PL-V001B 1 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(D-2) STC III-3100 III-3300 RNS Suction from RCS Inner Isolation Valve LT SV3-RNS-PL-V002A 1 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(F-2) STC III-3100 III-3300 LT RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT-App. J SV3-RNS-PL-V002B 1 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(D-2) STC III-3100 III-3300 LT RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT-App. J SV3-RNS-PL-V003A 2 N C A 1 CK SA SV3-RNS-M6-001 C O NA CKOP Accommodate thermal expansion RNS PIV Thermal Relief Valve (G-2) CKC SV3-RNS-PL-V003B 2 N C A 1 CK SA SV3-RNS-M6-001 C O NA CKOP Accommodate thermal expansion RNS PIV Thermal Relief Valve (D-2) CKC SV3-RNS-PL-V011 2 N A A 8 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(F-7) STC III-3100 III-3300 RNS Discharge Header to Containment OC Containment Isolation Valve LT-App. J 42 Southern Nuclear Version 4.0

System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RNS-PL-V012 2 N A A 1 GL MA SV3-RNS-M6-001 C C/O AI ETM Post-Accident Long Term RCS Make-up & Containment Isolation Valve (G-7) LT-App. J SV3-RNS-PL-V013 2 N AC A 8 CK SA SV3-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-7) CKC RNS to Containment IC Containment Isolation Valve LT-App. J SV3-RNS-PL-V015A 1 N AC A 6 CK SA SV3-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Stop Check Valve LT SV3-RNS-PL-V015B 1 N AC A 6 CK SA SV3-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Stop Check Valve LT SV3-RNS-PL-V017A 1 N AC A 6 CK SA SV3-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Check Valve LT SV3-RNS-PL-V017B 1 N AC A 6 CK SA SV3-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Check Valve LT SV3-RNS-PL-V020 2 N AC A 1 RV SA SV3-RNS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (G-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

RNS Suction Relief Valve LT-App. J SV3-RNS-PL-V021 2 N AC A 3 RV SA SV3-RNS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (G-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

RNS Suction Relief Valve LT-App. J SV3-RNS-PL-V022 2 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(F-3) STC III-3100 III-3300 RNS Suction from RCS OC Containment Isolation Valve LT-App. J SV3-RNS-PL-V023 2 N A A 10 GA MO SV3-RNS-M6-001 C C AI PI (III-3300)

(E-3) STC III-3100 III-3300 RNS Suction from IRWST/IC Containment Isolation Valve LT-App. J 43 Southern Nuclear Version 4.0

System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-RNS-PL-V061 2 N A A 3 GL AO SV3-RNS-M6-001 C C C PI (ISTC-3700)

(G-3) STC FST CVS return to RNS Suction/IC Containment Isolation Valve LT-App. J 44 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: SDS Valve ID Valve Actuator Drawing -----------Position----------- Required escription Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SDS-PL-V001 3 N B A 3 BU MO SV3-SDS-M6-001 O C AI PI (III-3300)

(E-5) STC III-3100 MCR SDS (Vent) Isolation Valve III-3300 SV3-SDS-PL-V002 3 N B A 3 BU MO SV3-SDS-M6-001 O C AI PI (III-3300)

(E-5) STC III-3100 MCR SDS (Vent) Isolation Valve III-3300 45 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: SFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SFS-PL-V031 3 N B P 6 BU MA SV3-SFS-M6-001 LO O AI PI (ISTC-3700)

Refueling Cavity Drain to S/G 2 Compartment Isolation Valve (F-7)

SV3-SFS-PL-V033 3 N B P 2 PL MA SV3-SFS-M6-001 LC C AI PI (ISTC-3700)

Refueling Cavity Drain to Containment Sump Isolation Valve (E-7)

SV3-SFS-PL-V034 2 N A A 6 BU MO SV3-SFS-M6-001 C C AI PI (III-3300)

(D-6) STC III-3100 III-3300 Refueling Cavity/IRWST to SFS IC Containment Iso Valve LT-App. J SV3-SFS-PL-V035 2 N A A 6 BU MO SV3-SFS-M6-001 C C AI PI (III-3300)

(D-5) STC III-3100 III-3300 Refueling Cavity/IRWST to SFS OC Containment Iso Valve LT-App. J SV3-SFS-PL-V037 2 N AC A 4 CK SA SV3-SFS-M6-001 C C/O NA CKC (B-6) CKOP Accommodate thermal expansion SFS to Refueling Cavity/IRWST IC Containment Iso Valve LT-App. J SV3-SFS-PL-V038 2 N A A 4 BU MO SV3-SFS-M6-001 C C AI PI (III-3300)

(B-5) STC III-3100 III-3300 SFS to Refueling Cavity/IRWST OC Containment Iso Valve LT-App. J SV3-SFS-PL-V041 3 N B A 6 BU MA SV3-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit Suction Isolation Valve (F-1)

SV3-SFS-PL-V042 3 Y B P 6 BU MA SV3-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit to Pumps Suction Isolation Valve (E-3/4)

SV3-SFS-PL-V045 3 Y B P 4 BU MA SV3-SFS-M6-001 LC C AI ETM SFS Discharge Line to Cask Loading Pit Isolation Valve (D-4)

SV3-SFS-PL-V049 3 Y B P 2 PL MA SV3-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit Drain to WLS Isolation Valve (E-2) 46 Southern Nuclear Version 4.0

System: SFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SFS-PL-V066 3 N B A 2 BA MA SV3-SFS-M6-001 LC C/O AI ETM Spent Fuel Pool Boiloff Makeup Isolation Valve (F-3)

SV3-SFS-PL-V067 2 N AC A 1 RV SA SV3-SFS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (E-6) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Refueling Cavity/IRWST to SFS Penetration Relief Valve LT-App. J SV3-SFS-PL-V068 3 N B A 4 BU MA SV3-SFS-M6-001 LO O AI ETM SFS Cask Washdown Pit Drain Isolation Valve (F-2)

SV3-SFS-PL-V071 3 N C A 6 CK SA SV3-SFS-M6-001 C O/C NA CKO Refueling Cavity/IRWST to SFS Penetration Relief Valve (E-6) CKC SV3-SFS-PL-V072 3 N C A 6 CK SA SV3-SFS-M6-001 C O/C NA CKO Refueling Cavity/IRWST to SFS Penetration Relief Valve (E-6) CKC SV3-SFS-PL-V075 3 N B P 20 BU MA SV3-SFS-M6-001 LO O AI PI (ISTC-3700)

SFS Reactor Cavity Post-Accident Containment Floodup Valve (G-7) 47 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-V027A 2 N B A 12 GL MO SV3-SGS-M6-001 O C AI PI (III-3300)

(G-2) STC III-3100 SG 1 PORV Isolation valve III-3300 SV3-SGS-PL-V027B 2 N B A 12 GL MO SV3-SGS-M6-002 O C AI PI (III-3300)

(G-2) STC III-3100 SG 2 PORV Isolation valve III-3300 SV3-SGS-PL-V030A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4/5) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V030B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4/5) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V031A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test 48 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-V031B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V032A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V032B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V033A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V033B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test 49 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-V034A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V034B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V035A 2 N C A 8X10 RV SA SV3-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V035B 2 N C A 8X10 RV SA SV3-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV3-SGS-PL-V036A 2 N B A 2 GL AO SV3-SGS-M6-001 O C C PI (ISTC-3700)

(G-3) STC SG1 Steam Line Drain Isolation FST SV3-SGS-PL-V036B 2 N B A 2 GL AO SV3-SGS-M6-002 O C C PI (ISTC-3700)

(G-3) STC SG2 Steam Line Drain Isolation FST 50 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-V040A 2 N B A 38 GA PH SV3-SGS-M6-001 O C C PI (ISTC-3700)

(G-1) STC Note 1 SG 1 Main Steam Isolation Valve FST SV3-SGS-PL-V040B 2 N B A 38 GA PH SV3-SGS-M6-002 O C C PI (ISTC-3700)

(G-1) STC Note 1 SG 2 Main Steam Isolation Valve FST SV3-SGS-PL-V057A 2 N B A 20 GA PH SV3-SGS-M6-001 O C C PI (ISTC-3700)

(E-4) STC Note 1 SG 1 Main Feedwater Isolation Valve FST SV3-SGS-PL-V057B 2 N B A 20 GA PH SV3-SGS-M6-002 O C C PI (ISTC-3700)

(E-4) STC Note 1 SG 2 Main Feedwater Isolation Valve FST SV3-SGS-PL-058A 2 N C A 20 CK SA SV3-SGS-M6-001 O C/O NA CKOP Accommodate thermal expansion SG1 Main Feed Check Valve (E-5) CKC SV3-SGS-PL-058B 2 N C A 20 CK SA SV3-SGS-M6-002 O C/O NA CKOP Accommodate thermal expansion SG2 Main Feed Check Valve (E-5) CKC SV3-SGS-PL-V067A 2 N B A 6 GA MO SV3-SGS-M6-001 O C AI PI (III-3300)

(D-5) STC III-3100 SG 1 Startup Feedwater Isolation Valve III-3300 SV3-SGS-PL-V067B 2 N B A 6 GA MO SV3-SGS-M6-002 O C AI PI (III-3300)

(D-5) STC III-3100 SG 2 Startup Feedwater Isolation Valve III-3300 SV3-SGS-PL-V074A 2 N B A 4 GL AO SV3-SGS-M6-001 O C C PI (ISTC-3700)

(C-5) STC SG 1 Blowdown Isolation Valve FST SV3-SGS-PL-V074B 2 N B A 4 GL AO SV3-SGS-M6-002 O C C PI (ISTC-3700)

(C-5) STC SG 2 Blowdown Isolation Valve FST SV3-SGS-PL-V075A 3 N B A 4 GL AO SV3-SGS-M6-001 O C C PI (ISTC-3700)

(C-5) STC SG 1 Blowdown Isolation Valve Second-off FST 51 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-V075B 3 N B A 4 GL AO SV3-SGS-M6-002 O C C PI (ISTC-3700)

(C-5) STC SG 2 Blowdown Isolation Valve Second-off FST SV3-SGS-PL-V086A 3 N B A 2 GL AO SV3-SGS-M6-001 C C C PI (ISTC-3700)

(F-3) STC SG1 Steam Line Drain Level Control FST SV3-SGS-PL-V086B 3 N B A 2 GL AO SV3-SGS-M6-002 C C C PI (ISTC-3700)

(F-3) STC SG2 Steam Line Drain Level Control FST SV3-SGS-PL-V233A 3 N B A 12 GL AO SV3-SGS-M6-001 C C C PI (ISTC-3700)

(H-2) STC SG 1 Power Operated Relief Valve (PORV) FST SV3-SGS-PL-V233B 3 N B A 12 GL AO SV3-SGS-M6-002 C C C PI (ISTC-3700)

(H-2) STC SG 2 Power Operated Relief Valve (PORV) FST SV3-SGS-PL-V240A 2 N B A 3 GL AO SV3-SGS-M6-001 C C C PI (ISTC-3700)

(G-1) STC SG 1 MSIV Bypass Valve FST SV3-SGS-PL-V240B 2 N B A 3 GL AO SV3-SGS-M6-002 C C C PI (ISTC-3700)

(G-1) STC SG 2 MSIV Bypass Valve FST SV3-SGS-PL-V250A 3 N B A 20 GL AO SV3-SGS-M6-001 O C C PI (ISTC-3700)

(E-2/3) STC SG 1 Feedwater Control Valve FST SV3-SGS-PL-V250B 3 N B A 20 GL AO SV3-SGS-M6-002 O C C PI (ISTC-3700)

(E-2/3) STC SG 2 Feedwater Control Valve FST SV3-SGS-PL-V255A 3 N B A 6 GL AO SV3-SGS-M6-001 C C C PI (ISTC-3700)

(D-4) STC SG 1 Startup Feedwater Control Valve FST SV3-SGS-PL-V255B 3 N B A 6 GL AO SV3-SGS-M6-002 C C C PI (ISTC-3700)

(D-4) STC SG 2 Startup Feedwater Control Valve FST 52 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-SGS-PL-256A 2 N C A 6 CK SA SV3-SGS-M6-001 C O NA CKOP Accommodate thermal expansion SG1 Startup Feedwater Check Valve (D-4) CKC SV3-SGS-PL-256B 2 N C A 6 CK SA SV3-SGS-M6-002 C O NA CKOP Accommodate thermal expansion SG2 Startup Feedwater Check Valve (D-4) CKC SV3-SGS-PL-V257A 3 N C A 1 RV SA SV3-SGS-M6-001 C O NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Main Feedwater Thermal Relief VE(I-7150(a))

SV3-SGS-PL-V257B 3 N C A 1 RV SA SV3-SGS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Main Feedwater Thermal Relief VE(I-7150(a))

SV3-SGS-PL-V258A 3 N C A 1 RV SA SV3-SGS-M6-001 C O NA RVT(I-7150(b)) Verify Vendor setpoint (D-4) RVT(I-7150(c)) Leak tightness per Vendor test Startup Feedwater Thermal Relief VE(I-7150(a))

SV3-SGS-PL-V258B 3 N C A 1 RV SA SV3-SGS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint (D-4) RVT(I-7150(c)) Leak tightness per Vendor test Startup Feedwater Thermal Relief VE(I-7150(a))

53 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: VBS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VBS-PL-V186 3 N B A 28 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(F-6) STC III-3100 MCR Supply Air Isolation Valve III-3300 SV3-VBS-PL-V187 3 N B A 28 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(F-6) STC III-3100 MCR Supply Air Isolation Valve III-3300 SV3-VBS-PL-V188 3 N B A 28 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(C-7) STC III-3100 MCR Return Air Isolation Valve III-3300 SV3-VBS-PL-V189 3 N B A 28 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(C-6) STC III-3100 MCR Return Air Isolation Valve III-3300 SV3-VBS-PL-V190 3 N B A 6 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(C-3) STC III-3100 MCR Toilet Exhaust Isolation Valve III-3300 SV3-VBS-PL-V191 3 N B A 6 BU MO SV3-VBS-M6-007 O C AI PI (III-3300)

(C-3) STC III-3100 MCR Toilet Exhaust Isolation Valve III-3300 54 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: VES Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VES-PL-V001 3 N B A 1 GL MA SV3-VES-M6-002 C O/C AI ETM Air Delivery Isolation Valve (D-5)

SV3-VES-PL-V005A 3 N B A 1 GL SO SV3-VES-M6-002 C O O PI (ISTC-3700)

(F-5) STO Air Delivery Isolation Valve A FST SV3-VES-PL-V005B 3 N B A 1 GL SO SV3-VES-M6-002 C O O PI (ISTC-3700)

(E-5) STO Air Delivery Isolation Valve B FST SV3-VES-PL-V018 3 N B A 1 GL MA SV3-VES-M6-002 C O/C AI ETM Temporary Instrumentation-Isolation Valve (F-5)

SV3-VES-PL-V019 3 N B A 1 GL MA SV3-VES-M6-002 C O/C AI ETM Temporary Instrumentation-Isolation Valve (D-5)

SV3-VES-PL-V022A 3 N B A 4 BU AO SV3-VES-M6-002 C O O PI (ISTC-3700)

(C-2) STO Pressure Relief Isolation Valve A FST SV3-VES-PL-V022B 3 N B A 4 BU AO SV3-VES-M6-002 C O O PI (ISTC-3700)

(C-2) STO Pressure Relief Isolation Valve B FST SV3-VES-PL-V040A 3 N C A 1 RV SA SV3-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve A VE(I-7150(a))

SV3-VES-PL-V040B 3 N C A 1 RV SA SV3-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (F-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve B VE(I-7150(a))

SV3-VES-PL-V040C 3 N C A 1 RV SA SV3-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve C VE(I-7150(a))

55 Southern Nuclear Version 4.0

System: VES Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VES-PL-V040D 3 N C A 1 RV SA SV3-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (C-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve D VE(I-7150(a))

SV3-VES-PL-V044 3 N B A 1 GL MA SV3-VES-M6-002 LO O/C AI ETM Eductor Flow Path Isolation Valve (F-4)

SV3-VES-PL-V045 3 N B A 1 GL MA SV3-VES-M6-002 LO O/C AI ETM Eductor Flow Path Isolation Valve (E-3)

SV3-VES-PL-V046 3 N B A 1 GL MA SV3-VES-M6-002 C O/C AI ETM Eductor Bypass Isolation Valve (D-3) 56 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: VFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VFS-PL-V003 2 N A A 16 BU AO SV3-VFS-M6-001 C C C PI (ISTC-3700)

(B-4) STC FST Containment Purge Inlet Containment Isol - ORC LT-App. J SV3-VFS-PL-V004 2 N A A 16 BU AO SV3-VFS-M6-001 C C C PI (ISTC-3700)

(B-3) STC FST Containment Purge Inlet Containment Isol - IRC LT-App. J SV3-VFS-PL-V009 2 N A A 16 BU AO SV3-VFS-M6-001 C C C PI (ISTC-3700)

(D-8) STC FST Containment Purge Discharge Containment Isol- IRC LT-App. J SV3-VFS-PL-V010 2 N A A 16 BU AO SV3-VFS-M6-001 C C C PI (ISTC-3700)

(D-7) STC FST Containment Purge Discharge Containment Isol- ORC LT-App. J SV3-VFS-PL-V800A 2 N A A 6 BU MO SV3-VFS-M6-001 C O/C AI PI (III-3300)

(E-7) STC STO III-3100 III-3300 Containment Vacuum Relief Isolation Valve A - ORC LT-App. J SV3-VFS-PL-V800B 2 N A A 6 BU MO SV3-VFS-M6-001 C O/C AI PI (III-3300)

(E-7) STC STO III-3100 III-3300 Containment Vacuum Relief Isolation Valve B - ORC LT-App. J SV3-VFS-PL-V803A 2 N AC A 6 VB SA SV3-VFS-M6-001 C O/C NA VE(I-7170) Vacuum Relief (E-7) RVT(I-7270(a)) Actuation to verify open/close Containment Vacuum Relief Valve A - IRC LT-App. J Also meets LT requirements of I-7270(b) 57 Southern Nuclear Version 4.0

System: VFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VFS-PL-V803B 2 N AC A 6 VB SA SV3-VFS-M6-001 C O/C NA VE(I-7170) Vacuum Relief (E-7) RVT(I-7270(a)) Actuation to verify open/close Containment Vacuum Relief Valve B - IRC LT-App. J Also meets LT requirements of I-7270(b) 58 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: VWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-VWS-PL-V053 3 N C A 2 RV SA SV3-VWS-M6-003 C O NA RVT(I-7150(b)) Verify Vendor setpoint (B-6) RVT(I-7150(c)) Leak tightness per Vendor test Ctmt Cooling Unit Supply Hdr Relief VE(I-7150(a))

SV3-VWS-PL-V057 3 N C A 2 RV SA SV3-VWS-M6-003 C O NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test Ctmt Cooling Unit Return Hdr Relief VE(I-7150(a))

SV3-VWS-PL-V058 2 N A A 8 BU AO SV3-VWS-M6-003 O C C PI (ISTC-3700)

(B-6) STC FST Chilled Water Inlet Containment Isolation Valve LT App. J SV3-VWS-PL-V062 2 N AC A 8 CK SA SV3-VWS-M6-003 O C/O NA CKC (B-6) CKOP Accommodate thermal expansion Fan Coolers Supply IC Isol Check Valve LT App. J SV3-VWS-PL-V080 2 N AC A 1 RV SA SV3-VWS-M6-003 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Ctmt Cooling Unit Return CIV Relief LT App. J SV3-VWS-PL-V082 2 N A A 8 BU AO SV3-VWS-M6-003 O C C PI (ISTC-3700)

(G-3) STC FST Chilled Water Outlet Containment Isolation Valve LT App. J SV3-VWS-PL-V086 2 N A A 8 BU AO SV3-VWS-M6-003 O C C PI (ISTC-3700)

(G-3) STC FST Chilled Water Outlet Containment Isolation Valve LT App. J 59 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 3 System: WLS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-WLS-PL-V055 2 N A A 2 PL AO SV3-WLS-M6-001 C C C PI (ISTC-3700)

(C-4) STC FST Containment Sump Discharge CIV - IRC LT-App. J SV3-WLS-PL-V057 2 N A A 2 PL AO SV3-WLS-M6-001 C C C PI (ISTC-3700)

(C-3) STC FST Containment Sump Discharge CIV - ORC LT-App. J SV3-WLS-PL-V058 2 N AC A 1 RV SA SV3-WLS-M6-001 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint (C-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Containment Sump Discharge Penetration Thermal Relief LT-App. J SV3-WLS-PL-V067 2 N A A 1 GL AO SV3-WLS-M6-001 C C C PI (ISTC-3700)

(E-3) STC FST RCDT Gas Outlet CIV - IRC LT-App. J SV3-WLS-PL-V068 2 N A A 1 GL AO SV3-WLS-M6-001 C C C PI (ISTC-3700)

(E-3) STC FST RCDT Gas Outlet CIV - ORC LT-App. J SV3-WLS-PL-V071A 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO CVS Compt Floor Drain Check (C-8) CKC SV3-WLS-PL-V071B 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO PXS Compt A Floor Drain Check (F-8) CKC SV3-WLS-PL-V071C 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO PXS Compt B Floor Drain Check (F-8) CKC SV3-WLS-PL-V072A 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO CVS Compt Floor Drain Check (C-7) CKC SV3-WLS-PL-V072B 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO PXS Compt A Floor Drain Check (F-8) CKC 60 Southern Nuclear Version 4.0

System: WLS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV3-WLS-PL-V072C 3 N C A 4 CK SA SV3-WLS-M6-001 C O/C NA CKO PXS Compt B Floor Drain Check (F-8) CKC 61 Southern Nuclear Version 4.0

8.0 VEGP-4 VALVE TABLES 62 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: CAS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-CAS-PL-V014 2 N A A 2 BA AO SV4-CAS-M6-005 O C C PI (ISTC-3700)

(F-3) STC FST Instrument Air Containment Isolation Valve LT-App. J SV4-CAS-PL-V015 2 N AC A 2 CK SA SV4-CAS-M6-005 O C/O NA CKC (F-4) CKOP Accommodate thermal expansion Instrument Air Containment Isolation Check Valve LT-App. J SV4-CAS-PL-V204 2 N A P 3 BA MA SV4-CAS-M6-012 LC C C LT-App. J Service Air Containment Isolation Valve (E-5)

SV4-CAS-PL-V205 2 N AC A 3 CK SA SV4-CAS-M6-012 C C/O NA CKC (E-4) CKOP Accommodate thermal expansion Service Air Containment Isolation Check Valve LT-App. J 63 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: CCS Valve ID Valve Actuator Drawing -----------Position----------- Required escription Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-CCS-PL-V200 2 N A A 10 BU MO SV4-CCS-M6-002 O C AI PI (III-3300)

(H-2) STC III-3100 III-3300 Cooling Water Supply Ctmt Isol- ORC LT-App. J SV4-CCS-PL-V201 2 N AC A 10 CK SA SV4-CCS-M6-002 O C/O NA CKC (H-2) CKOP Accommodate thermal expansion Cooling Water Ctmt Supply Check LT-App. J SV4-CCS-PL-V207 2 N A A 10 BU MO SV4-CCS-M6-002 O C AI PI (III-3300)

(B-2) STC III-3100 III-3300 Cooling Water Return Ctmt Isol - IRC LT-App. J SV4-CCS-PL-V208 2 N A A 10 BU MO SV4-CCS-M6-002 O C AI PI (III-3300)

(B-1) STC III-3100 III-3300 Cooling Water Return Ctmt Isol - ORC LT-App. J SV4-CCS-PL-V220 2 N AC A 1 RV SA SV4-CCS-M6-002 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (C-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Ctmt Return CIV Thermal Relief LT-App. J SV4-CCS-PL-V270 3 N C A 4 RV SA SV4-CCS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (H-2) RVT(I-7150(c)) Leak tightness per Vendor test CCS Supply Line to Ctmt Safety/Relief VE(I-7150(a))

SV4-CCS-PL-V271 3 N C A 4 RV SA SV3-CCS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (C-2) RVT(I-7150(c)) Leak tightness per Vendor test CCS Return Line to Ctmt Safety/Relief VE(I-7150(a))

64 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-CVS-PL-V001 1 N B A 3 GA MO SV4-CVS-M6-001 O C AI PI (III-3300)

(G-8) STC III-3100 CVS Purification Stop Valve III-3300 SV4-CVS-PL-V002 1 N B A 3 GA MO SV4-CVS-M6-001 O C AI PI (III-3300)

(G-7) STC III-3100 CVS Purification Stop Valve III-3300 SV4-CVS-PL-V003 3 N B A 3 GL MO SV4-CVS-M6-001 O C AI PI (III-3300)

(G-7) STC III-3100 CVS Purification Stop Valve III-3300 SV4-CVS-PL-V040 2 N A P 2 BA MA SV4-CVS-M6-005 LC C AI LT-App. J Resin Flush Inside Containment Isolation Valve (F-4)

SV4-CVS-PL-V041 2 N A P 2 BA MA SV4-CVS-M6-005 LC C AI LT-App. J Resin Flush Outside Containment Isolation Valve (F-2)

SV4-CVS-PL-V042 2 N AC A 1 RV SA SV4-CVS-M6-005 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (G-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Flush Line Containment Isolation Relief Valve LT-App. J SV4-CVS-PL-V045 2 N A A 2 GL AO SV4-CVS-M6-005 C C C PI (ISTC-3700)

(D-4) STC FST Letdown Line Inside Containment Isolation Valve LT-App. J SV4-CVS-PL-V047 2 N A A 2 GL AO SV4-CVS-M6-005 C C C PI (ISTC-3700)

(D-2) STC FST Letdown Line Outside Containment Isolation Valve LT-App. J 65 Southern Nuclear Version 4.0

System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-CVS-PL-V058 2 N AC A 1 RV SA SV4-CVS-M6-005 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (E-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Letdown Line Relief Thermal Relief Valve LT-App. J SV4-CVS-PL-V064 N N C A 3 CK SA SV4-CVS-M6-005 C O NA CKC Make-up Discharge Header Check Valve (C-5) CKOP Accommodate thermal expansion SV4-CVS-PL-V067 1 N C A 1 CK SA SV4-CVS-M6-001 O C/O NA CKC Makeup Return Line Spring-Assisted Check Valve (F-7) CKOP Accommodate thermal expansion SV4-CVS-PL-V080 3 N C A 3 CK SA SV4-CVS-M6-001 O C/O NA CKC Regen HX Shell Side Outlet Check Valve (G-7) CKOP Accommodate thermal expansion SV4-CVS-PL-V081 1 N BC A 3 SC AO SV4-CVS-M6-001 O C NA PI (ISTC-3700)

(G-7) CKC Purification Return Line Stop Check Valve CKOP SV4-CVS-PL-V082 1 N C A 3 CK SA SV4-CVS-M6-001 O C/O NA CKC RCS Purification Return Line Check Valve (G-8) CKOP Accommodate thermal expansion SV4-CVS-PL-V084 1 N B A 2 GL AO SV4-CVS-M6-001 C C C PI (ISTC-3700)

(F-7) STC Auxiliary Pressurizer Spray Line Isolation Valve FST SV4-CVS-PL-V085 1 N C A 2 CK SA SV4-CVS-M6-001 C C/O NA CKC Auxiliary Pressurizer Spray Line Valve CKOP Accommodate thermal expansion SV4-CVS-PL-V090 2 N A A 3 GA MO SV4-CVS-M6-005 O C AI PI (III-3300)

(C-2) STC III-3100 III-3300 Makeup Line Outside Containment Isolation Valve LT-App. J SV4-CVS-PL-V091 2 N A A 3 GA MO SV4-CVS-M6-005 O C AI PI (III-3300)

(C-4) STC III-3100 III-3300 Makeup Line Inside Containment Isolation Valve LT-App. J SV4-CVS-PL-V092 2 N A A 1 GL AO SV4-CVS-M6-003 O C C PI (ISTC-3700)

(F-6) STC FST Zinc Injection Containment Isolation Valve ORC LT-App. J 66 Southern Nuclear Version 4.0

System: CVS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-CVS-PL-V094 2 N A A 1 GL AO SV4-CVS-M6-003 O C C PI (ISTC-3700)

(F-7) STC FST Zinc Injection Containment Isolation Valve IRC LT-App. J SV4-CVS-PL-V098 2 N AC A 1 RV SA SV4-CVS-M6-003 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (F-6) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Zinc Injection Ctmt Isol Thermal Relief Valve LT-App. J SV4-CVS-PL-V100 2 N AC A 1 CK SA SV4-CVS-M6-005 O C/O NA CKC (B-4) CKOP Accommodate thermal expansion Makeup Line Containment Isolation Relief LT-App. J SV4-CVS-PL-V136A 3 N B A 2 BU AO SV4-CVS-M6-004 C C C PI (ISTC-3700)

(C-4) STC Demineralized Water System Isolation Valve FST SV4-CVS-PL-V136B 3 N B A 2 BU AO SV4-CVS-M6-004 C C C PI (ISTC-3700)

(C-4) STC Demineralized Water System Isolation Valve FST SV4-CVS-PL-V217 2 N AC A 1/2 CK SA SV4-CVS-M6-003 O C/O NA CKC (D-7) CKOP Accommodate thermal expansion Hydrogen Injection Containment Isolation Check Valve IRC LT-App. J SV4-CVS-PL-V219 2 N A A 1/2 GL AO SV4-CVS-M6-003 O C C PI (ISTC-3700)

(D-6) STC FST Hydrogen Injection Containment Isolation Valve ORC LT-App. J 67 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: DWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-DWS-PL-V241 3 N C A 1 RV SA SV4-DWS-M6-007 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (E-5) RVT(I-7150(c)) Leak tightness per Vendor test Demin Water Supply to Containment Relief VE(I-7150(a))

SV4-DWS-PL-V244 2 N A P 3 BU MA SV4-DWS-M6-007 LC C AI LT-App. J Exercised during Shutdown and leaktest Demin Water Supply Containment Isolation - Outside (E-6)

SV4-DWS-PL-V245 2 N AC A 2 CK SA SV4-DWS-M6-007 C C/O NA CKC (E-6) CKOP Accommodate thermal expansion Demin Water Supply Containment Isolation Check Valve - IRC LT-App. J 68 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: FHS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-FHS-PL-V001 3 N B A 30 GA MA SV4-SFS-M6-001 C C AI ETM Fuel Transfer Tube Isolation Valve (F-6) 69 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: FPS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-FPS-PL-V050 2 N A P 6 BU MA SV4-FPS-M6-004 LC C AI LT-App. J Exercised during Shutdown and leaktest Fire Water Containment Supply Isolation (F-5)

SV4-FPS-PL-V052 2 N AC A 6 CK SA SV4-FPS-M6-004 C C/O NA CKC (F-5) CKOP Accommodate thermal expansion Fire Water Supply Cont Isol Check Valve - IRC LT-App. J SV4-FPS-PL-V702 3 N C A 1 RV SA SV4-FPS-M6-004 C O NA RVT(I-7150(b)) Verify Vendor setpoint, Thermal Relief (F/G-5) RVT(I-7150(c)) Leak tightness per Vendor test Fire Water Supply IC Thermal Relief VE(I-7150(a))

70 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: MSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-MSS-PL-V001 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-8) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V002 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-7) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V003 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-6) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V004 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-4) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V005 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-3) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V006 N Y B A 16 GL AO SV4-MSS-M6-001 C C C PI (ISTC-3700) Required by TS 3.7.2 (H-2) STC Note 1 Turbine Bypass Control Valve FST SV4-MSS-PL-V015A N Y B A 10 GL AO SV4-MSS-M6-001 O C C PI (ISTC-3700) Required by TS 3.7.2 (B-6) STC MSR 2ND Stage Reheat Steam AO Isolation Valve FST SV4-MSS-PL-V015B N Y B A 10 GL AO SV4-MSS-M6-001 O C C PI (ISTC-3700) Required by TS 3.7.2 (G-6) STC MSR 2ND Stage Reheat Steam AO Isolation Valve FST 71 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: MTS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-MTS-PL-V001A N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (F-6) STC Main Turbine Stop Valve FST SV4-MTS-PL-V001B N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (C-6) STC Main Turbine Stop Valve FST SV4-MTS-PL-V002A N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (F-6) STC Main Turbine Control Valve FST SV4-MTS-PL-V002B N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (C-6) STC Main Turbine Control Valve FST SV4-MTS-PL-V003A N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (E-6) STC Main Turbine Stop Valve FST SV4-MTS-PL-V003B N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (D-6) STC Main Turbine Stop Valve FST SV4-MTS-PL-V004A N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (E-6) STC Main Turbine Control Valve FST SV4-MTS-PL-V004B N Y B A 28 GL EH SV4-MTS-M6-002 O C C PI (ISTC-3700) Required by TS 3.7.2 (D-6) STC Main Turbine Control Valve FST 72 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: PCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PCS-PL-V001A 3 N B A 6 BU AO SV4-PCS-M6-001 C O O PI (ISTC-3700)

(E-4) STO PCS Actuation Valve A FST SV4-PCS-PL-V001B 3 N B A 6 BU AO SV4-PCS-M6-001 C O O PI (ISTC-3700)

(E-6) STO PCS Actuation Valve B FST SV4-PCS-PL-V001C 3 N B A 6 GA MO SV4-PCS-M6-001 C O AI PI (III-3300) This valve has a passive closed function (E-5) STO for Spent fuel make-up.

III-3100 PCS Actuation Valve C III-3300 SV4-PCS-PL-V002A 3 N B A 6 GA MO SV4-PCS-M6-001 O O AI PI (III-3300) This valve has a passive closed function (E-4) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve A III-3300 SV4-PCS-PL-V002B 3 N B A 6 GA MO SV4-PCS-M6-001 O O AI PI (III-3300) This valve has a passive closed function (E-6) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve B III-3300 SV4-PCS-PL-V002C 3 N B A 6 GA MO SV4-PCS-M6-001 O O AI PI (III-3300) This valve has a passive closed function (E-5) STO for Spent fuel make-up.

III-3100 PCS Isolation Valve C III-3300 SV4-PCS-PL-V005 3 N B A 4 GA MA SV4-PCS-M6-002 O C AI ETM PCS to DWS/FPS Iso Valve (G-5)

SV4-PCS-PL-V009 3 N B A 3 GA MA SV4-PCS-M6-001 C C/O AI ETM Open for Emergency SFP make-up Spent Fuel Pool Emergency Makeup Valve (E-4)

SV4-PCS-PL-V015 3 N B A 1 GL MA SV4-PCS-M6-002 O C AI ETM PCS Long Term supply to Distribution Bucket Drain Valve (G-8)

SV4-PCS-PL-V020 3 N B A 3 GA MA SV4-PCS-M6-002 C O AI ETM PCS Long Term supply to Distribution Bucket Iso Valve (G-7) 73 Southern Nuclear Version 4.0

System: PCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PCS-PL-V023 3 N B A 4 GA MA SV4-PCS-M6-002 O C AI ETM PCS Recirc Pumps to PCCWST Iso Valve (F-7)

SV4-PCS-PL-V039 3 N C A 4 CK SA SV4-PCS-M6-002 C O/C NA CKO PCS/SFS Long Term Make-up Supply Check Valve (F-3) CKC SV4-PCS-PL-V042 3 N B A 1 GL MA SV4-PCS-M6-002 C C AI ETM PCS Long Term Supply from Temp Pump Drain Valve (F-3)

SV4-PCS-PL-V044 3 N B A 4 GA MA SV4-PCS-M6-002

• O AI ETM

• Locked one turn from full open PCS Long Term Supply from Temp Pump Iso Valve (F-4)

SV4-PCS-PL-V045 3 N B A 2 GL MA SV4-PCS-M6-001 C O AI ETM PCS Supply to SFS Make-up Iso Valve (B-3)

SV4-PCS-PL-V046 3 N B A 4 GA MA SV4-PCS-M6-002 LO C AI ETM PCCWST Recirculation Return Isolation Valve (H-7)

SV4-PCS-PL-V049 3 N B A 1 GL MA SV4-PCS-M6-001 O C AI ETM PCCWST Drain Isolation Valve (B-2)

SV4-PCS-PL-V050 3 N B A 2 GL MA SV4-PCS-M6-002 C C/O AI ETM Recirc Header Discharge to SFS Pool Isolation Valve (F-7)

SV4-PCS-PL-V051 3 N B A 2 GL MA SV4-PCS-M6-001 C C/O AI ETM Spent Fuel Pool Emergency Makeup Lower Isolation Valve (B-2) 74 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: PSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PSS-PL-V001A 2 N C A 1/4 GL SO SV4-PSS-M6-001 O O C RVT Thermal Relief function Hot Leg 1 Sample Isolation Valve E-8 SV4-PSS-PL-V001B 2 N C A 1/4 GL SO SV4-PSS-M6-001 C O C RVT Thermal Relief function Hot Leg 2 Sample Isolation Valve D-8 SV4-PSS-PL-V003 2 N C A 1/4 GL SO SV4-PSS-M6-001 C O C RVT Thermal Relief function Pressurizer Sample Isolation Valve G-8 SV4-PSS-PL-V008 2 N A A 5/8 GL SO SV4-PSS-M6-001 O C C PI (ISTC-3700)

(D-7) STC FST Containment Air Sample Containment Isolation Valve IRC LT-App. J SV4-PSS-PL-V010A 2 N AC A 1/4 GL SO SV4-PSS-M6-001 O C/O C PI (ISTC-3700)

(D-7) STC FST RVT Thermal Relief function Liquid Sample Line Containment Isolation Valve IRC LT-App. J SV4-PSS-PL-V010B 2 N AC A 1/4 GL SO SV4-PSS-M6-001 C C/O C PI (ISTC-3700)

(G-7) STC FST RVT Thermal Relief function Liquid Sample Line Containment Isolation Valve IRC LT-App. J SV4-PSS-PL-V011A 2 N A A 1/4 GL AO SV4-PSS-M6-001 O C C PI (ISTC-3700)

(E-6) STC FST Liquid Sample Line Containment Isolation Valve ORC LT-App. J SV4-PSS-PL-V011B 2 N A A 1/4 GL AO SV4-PSS-M6-001 C C C PI (ISTC-3700)

(G-6) STC FST Liquid Sample Line Containment Isolation Valve ORC LT-App. J 75 Southern Nuclear Version 4.0

System: PSS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PSS-PL-V023 2 N A A 1 GL AO SV4-PSS-M6-001 O C C PI (ISTC-3700)

(C-6) STC FST Sample Return Line Containment Isolation Valve ORC LT-App. J SV4-PSS-PL-V024 2 N A A 1 GL SO SV4-PSS-M6-001 O C C PI (ISTC-3700)

(C-7) STC FST Sample Return Line Containment Isolation Valve IRC LT-App. J SV4-PSS-PL-V046 2 N A A 5/8 GL AO SV4-PSS-M6-001 O C C PI (ISTC-3700)

(D-6) STC FST Air Sample Line Containment Isolation Valve ORC LT-App. J 76 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: PWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PWS-PL-V418 3 N B A 1 GL MA SV4-PWS-M6-002 O C AI ETM Control Room Boundary Outside Isolation Valve (G-4)

SV4-PWS-PL-V420 3 N B A 1 GL MA SV4-PWS-M6-002 O C AI ETM Control Room Boundary Inside Isolation Valve (F-4)

SV4-PWS-PL-V498 3 N C A 1 VB SA SV4-PWS-M6-002 C O NA VE(I-7170)

(F-4) RVT(I-7270(a)) Actuation to verify open/close Control Room Boundary Vacuum Breaker RVT(I-7270(b)) Leak tightness 77 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PXS-PL-V002A 1 N B P 8 GA MO SV4-PXS-M6-001 O O AI PI (ISTC-3700)

RCS to CMT A Isolation Valve (G/H-5)

SV4-PXS-PL-V002B 1 N B P 8 GA MO SV4-PXS-M6-001 O O AI PI (ISTC-3700)

RCS to CMT B Isolation Valve (G/H-4)

SV4-PXS-PL-V013A 1 N B P 8 GA MA SV4-PXS-M6-001 LO O AI PI (ISTC-3700)

CMT A Discharge Manual Isol Valve (D-6)

SV4-PXS-PL-V013B 1 N B P 8 GA MA SV4-PXS-M6-001 LO O AI PI (ISTC-3700)

CMT B Discharge Manual Isol Valve (D-3)

SV4-PXS-PL-V014A 1 N B A 8 GL AO SV4-PXS-M6-001 C O O PI (ISTC-3700)

(E-7) STO CMT A Outlet Valve FST SV4-PXS-PL-V014B 1 N B A 8 GL AO SV4-PXS-M6-001 C O O PI (ISTC-3700)

(E-3) STO CMT B Outlet Valve FST SV4-PXS-PL-V015A 1 N B A 8 GL AO SV4-PXS-M6-001 C O O PI (ISTC-3700)

(D-7) STO CMT A Outlet Valve FST SV4-PXS-PL-V015B 1 N B A 8 GL AO SV4-PXS-M6-001 C O O PI (ISTC-3700)

(D-3) STO CMT B Outlet Valve FST SV4-PXS-PL-V016A 1 N C A 8 CK SA SV4-PXS-M6-001 O O/C NA CKO CMT A outlet to RCS Check (D-6) CKC SV4-PXS-PL-V016B 1 N C A 8 CK SA SV4-PXS-M6-001 O O/C NA CKO CMT B outlet to RCS Check (D-3) CKC SV4-PXS-PL-V017A 1 N C A 8 CK SA SV4-PXS-M6-001 O O/C NA CKO CMT A outlet to RCS Check (D-6) CKC SV4-PXS-PL-V017B 1 N C A 8 CK SA SV4-PXS-M6-001 O O/C NA CKO CMT B outlet to RCS Check (D-3) CKC SV4-PXS-PL-V021A 3 N B P 1 GL SO SV4-PXS-M6-001 C C C PI (ISTC-3700)

Accumulator A Nitrogen supply Valve (C-7) 78 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PXS-PL-V021B 3 N B P 1 GL SO SV4-PXS-M6-001 C C C PI (ISTC-3700)

Accumulator B Nitrogen supply Valve (C-2)

SV4-PXS-PL-V022A 3 N C A 1 RV SA SV4-PXS-M6-001 C O/C NA VE(I-7150(a))

(C-7) RVT(I-7150(b)) Verify Vendor setpoint Accumulator A Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV4-PXS-PL-V022B 3 N C A 1 RV SA SV4-PXS-M6-001 C O/C NA VE(I-7150(a))

(C-2) RVT(I-7150(b)) Verify Vendor setpoint Accumulator B Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV4-PXS-PL-V027A 3 N B P 8 GA MO SV4-PXS-M6-001 O O AI PI (ISTC-3700)

Accumulator A to RCS Isolation Valve (B-6)

SV4-PXS-PL-V027B 3 N B P 8 GA MO SV4-PXS-M6-001 O O AI PI (ISTC-3700)

Accumulator B to RCS Isolation Valve (B-3)

SV4-PXS-PL-V028A 1 N AC A 8 CK SA SV4-PXS-M6-001 C O/C NA CKO (B-6) CKC Accumulator A outlet to RCS Check LT SV4-PXS-PL-V028B 1 N AC A 8 CK SA SV4-PXS-M6-001 C O/C NA CKO (B-3) CKC Accumulator B outlet to RCS Check LT SV4-PXS-PL-V029A 1 N AC A 8 CK SA SV4-PXS-M6-001 C O/C NA CKO (B-6) CKC Accumulator A outlet to RCS Check LT SV4-PXS-PL-V029B 1 N AC A 8 CK SA SV4-PXS-M6-001 C O/C NA CKO (B-4) CKC Accumulator B outlet to RCS Check LT SV4-PXS-PL-V042 2 N A A 1 GL AO SV4-PXS-M6-001 O C C PI (ISTC-3700)

(D-1) STC FST High Pressure Nitrogen to Containment Isolation Valve LT-App. J SV4-PXS-PL-V043 2 N AC A 1 CK SA SV4-PXS-M6-001 C O/C NA CKOP Accommodate thermal expansion (D-2) CKC High Pressure Nitrogen to Containment IC Check Valve LT-App. J SV4-PXS-PL-V044 N N C A 1 RV SA SV4-PXS-M6-001 C O NA VE(I-7150(a))

(D-2) RVT(I-7150(b)) Verify Vendor setpoint High Pressure Nitrogen to Containment Penetration Thermal Relief Valve RVT(I-7150(c)) Leak tightness (from Vendor test)

SV4-PXS-PL-V101 1 N B P 14 GA MO SV4-PXS-M6-002 O O AI PI (ISTC-3700)

RCS to PRHR Heat Exchanger Isolation Valve 79 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PXS-PL-V108A 1 N B A 14 BA AO SV4-PXS-M6-002 C O O PI (ISTC-3700)

(F-1) STO PRHR Heat Exchanger Outlet Valve to RCS A FST SV4-PXS-PL-V108B 1 N B A 14 BA AO SV4-PXS-M6-002 C O O PI (ISTC-3700)

(E-1) STO PRHR Heat Exchanger Outlet Valve to RCS B FST SV4-PXS-PL-V109 1 N B P 14 GA MA SV4-PXS-M6-002 LO O AI PI (ISTC-3700)

PRHR HX/RCS Return Isol Valve (F-1)

SV4-PXS-PL-V117A 3 N B P 8 GA MO SV4-PXS-M6-002 O O AI PI (ISTC-3700)

Containment Recirculation Sump A to RCS Isolation Valve (E-7)

SV4-PXS-PL-V117B 3 N B P 8 GA MO SV4-PXS-M6-002 O O AI PI (ISTC-3700)

Containment Recirculation Sump B to RCS Isolation Valve (E-5)

SV4-PXS-PL-V118A 3 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (E-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V118B 3 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (E-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V119A 3 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(D-7) CKO Containment Recirc. Sump A outlet to RCS Check CKC SV4-PXS-PL-V119B 3 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(D-5) CKO Containment Recirc. Sump B outlet to RCS Check CKC SV4-PXS-PL-V120A 3 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (D-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V120B 3 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V121A 3 N B P 8 GA MO SV4-PXS-M6-002 O O AI PI (ISTC-3700)

IRWST/Recirc Sump to RCS A Isolation Valve (D-7)

SV4-PXS-PL-V121B 3 N B P 8 GA MO SV4-PXS-M6-002 O O AI PI (ISTC-3700)

IRWST/Recirc Sump to RCS B Isolation Valve (D-5)

SV4-PXS-PL-V122A 1 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-7) CKO IRWST/Recirc Sump to RCS A outlet to RCS Check CKC SV4-PXS-PL-V122B 1 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-5) CKO IRWST/Recirc Sump to RCS B outlet to RCS Check CKC 80 Southern Nuclear Version 4.0

System: PXS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-PXS-PL-V123A 1 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (C-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V123B 1 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V124A 1 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-7) CKO IRWST/Recirc Sump to RCS A outlet to RCS Check CKC SV4-PXS-PL-V124B 1 N C A 8 CK SA SV4-PXS-M6-002 C O/C NA PI (ISTC-3700)

(C-5) CKO IRWST/Recirc Sump to RCS B outlet to RCS Check CKC SV4-PXS-PL-V125A 1 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump A to RCS Actuation Squib Valve (C-7) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V125B 1 N D A 8 SQ SQ SV4-PXS-M6-002 C O NA Circuit(ISTC-3100(d)(1))

Containment Recirc. Sump B to RCS Actuation Squib Valve (D-5) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-PXS-PL-V130A 3 N B A 2 BA AO SV4-PXS-M6-002 O C C PI (ISTC-3700)

(H-7) STC Containment Condensation Collection to Containment Sump Isolation Valve A FST SV4-PXS-PL-V130B 3 N B A 2 BA AO SV4-PXS-M6-002 O C C PI (ISTC-3700)

(H-7) STC Containment Condensation Collection to Containment Sump Isolation Valve B FST SV4-PXS-PL-V208A 2 N A P .375 GL MA SV4-PXS-M6-003 LC C C LT-App. J RNS Suction Leak Test Valve (D-3)

SV4-PXS-PL-V230A 2 N B P 1 GL AO SV4-PXS-M6-003 C C C PI (ISTC-3700)

Core Makeup Tank A Fill Isolation (F-6)

SV4-PXS-PL-V230B 2 N B P 1 GL AO SV4-PXS-M6-003 C C C PI (ISTC-3700)

Core Makeup Tank B Fill Isolation (G-6)

SV4-PXS-PL-V231A 2 N C A 1 CK SA SV4-PXS-M6-003 C C C CKOP Accommodate thermal expansion Core Makeup Tank A Fill Check (F-7) CKC SV4-PXS-PL-V231B 2 N C A 1 CK SA SV4-PXS-M6-003 C C C CKOP Accommodate thermal expansion Core Makeup Tank B Fill Check (G-7) CKC SV4-PXS-PL-V232A 3 N B P 1 GL AO SV4-PXS-M6-003 C C C PI (ISTC-3700)

Accumulator B Fill/Drain Isolation (E-6)

SV4-PXS-PL-V232B 3 N B P 1 GL AO SV4-PXS-M6-003 C C C PI (ISTC-3700)

Accumulator B Fill/Drain Isolation (G-6) 81 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RCS-PL-V001A 1 N B A 4 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(G-5) STO III-3100 ADS Stage 1 Control Valve III-3300 SV4-RCS-PL-V001B 1 N B A 4 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(E-5) STO III-3100 ADS Stage 1 Control Valve III-3300 SV4-RCS-PL-V002A 1 N B A 8 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(G-5) STO III-3100 ADS Stage 2 Control Valve III-3300 SV4-RCS-PL-V002B 1 N B A 8 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(E-5) STO III-3100 ADS Stage 2 Control Valve III-3300 SV4-RCS-PL-V003A 1 N B A 8 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(H-5) STO III-3100 ADS Stage 3 Control Valve III-3300 SV4-RCS-PL-V003B 1 N B A 8 GL MO SV4-RCS-M6-002 C O AI PI (III-3300)

(F-5) STO III-3100 ADS Stage 3 Control Valve III-3300 SV4-RCS-PL-V004A 1 N D A 14 SQ SQ SV4-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (G-6) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-RCS-PL-V004B 1 N D A 14 SQ SQ SV4-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-3) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 82 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RCS-PL-V004C 1 N D A 14 SQ SQ SV4-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-6) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-RCS-PL-V004D 1 N D A 14 SQ SQ SV4-RCS-M6-001 C O NA Circuit(ISTC-3100(d)(1))

ADS Stage 4 Valve (F-3) Charge(ISTC-3100(d)(2)) Alternative VEGP 3&4-PST-Alt-01 SV4-RCS-PL-V005A 1 N C A 6 RV SA SV4-RCS-M6-002 C O/C NA PI (I-7110(c)/7310(f)) From Vendor test (H-7) RVT(I-7110(b)) Verify Vendor setpoint RVT(I-7110(d)) Leak tightness per Vendor test VE(I-7110(a))

RVT(I-7210) Setpoint verification (due 6m prior to Initial Pressurizer Safety Valve Criticality) Alternative VEGP 3&4-PST-Alt-02 SV4-RCS-PL-V005B 1 N C A 6 RV SA SV4-RCS-M6-002 C O/C NA PI (I-7110(c)/7310(f)) From Vendor test (F-6) RVT(I-7110(b)) Verify Vendor setpoint RVT(I-7110(d)) Leak tightness per Vendor test VE(I-7110(a))

RVT(I-7210) Setpoint verification (due 6m prior to Initial Pressurizer Safety Valve Criticality) Alternative VEGP 3&4-PST-Alt-02 SV4-RCS-PL-V010A 3 N C A 1 VB SA SV4-RCS-M6-002 C O NA VE(I-7170)

(G-4) RVT(I-7270(a)) Actuation to verify open/close ADS Header Vacuum Breaker RVT(I-7270(b)) Leak tightness SV4-RCS-PL-V010B 3 N C A 1 VB SA SV4-RCS-M6-002 C O NA VE(I-7170)

(E-4) RVT(I-7270(a)) Actuation to verify open/close ADS Header Vacuum Breaker RVT(I-7270(b)) Leak tightness SV4-RCS-PL-V011A 1 N B A 4 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (G-5) STO III-3100 ADS Stage 1 Isolation Valve III-3300 SV4-RCS-PL-V011B 1 N B A 4 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (E-5) STO III-3100 ADS Stage 1 Isolation Valve III-3300 SV4-RCS-PL-V012A 1 N B A 8 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (G-5) STO III-3100 ADS Stage 2 Isolation Valve III-3300 83 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RCS-PL-V012B 1 N B A 8 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (E-5) STO III-3100 ADS Stage 2 Isolation Valve III-3300 SV4-RCS-PL-V013A 1 N B A 8 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (H-5) STO III-3100 ADS Stage 3 Isolation Valve III-3300 SV4-RCS-PL-V013B 1 N B A 8 GA MO SV4-RCS-M6-002 C O/C AI PI (III-3300) Closed safety function is passive (F-5) STO III-3100 ADS Stage 3 Isolation Valve III-3300 SV4-RCS-PL-V014A 1 N B P 14 GA MO SV4-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (G-6)

SV4-RCS-PL-V014B 1 N B P 14 GA MO SV4-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-3)

SV4-RCS-PL-V014C 1 N B P 14 GA MO SV4-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-6)

SV4-RCS-PL-V014D 1 N B P 14 GA MO SV4-RCS-M6-001 O O AI PI (ISTC-3700)

ADS Stage 4 Block Valve (F-3)

SV4-RCS-PL-V150A 1 N B A 1 GL SO SV4-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC FST Reactor Head Vent Valve RVT Thermal Relief function SV4-RCS-PL-V150B 1 N B A 1 GL SO SV4-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC FST Reactor Head Vent Valve RVT Thermal Relief function SV4-RCS-PL-V150C 1 N B A 1 GL SO SV4-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC Reactor Head Vent Valve FST 84 Southern Nuclear Version 4.0

System: RCS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RCS-PL-V150D 1 N B A 1 GL SO SV4-RCS-M6-001 C O/C C PI (ISTC-3700)

(D-4) STO STC Reactor Head Vent Valve FST SV4-RCS-PL-V233 3 N B P 2 GL MA SV4-RCS-M6-002 O O AI PI (ISTC-3700) Open only indication RV Head Vent to IRWST Isolation Valve (H-3)

SV4-RCS-PY-K03 3 N D A 10 RD SA SV4-RCS-M6-002 C O NA VE(I-7160/7260)

Pressurizer Relief Valve Discharge Line Rupture Disc (H-8)

SV4-RCS-PY-K04 3 N D A 10 RD SA SV4-RCS-M6-002 C O NA VE(I-7160/7260)

Pressurizer Relief Valve Discharge Line Rupture Disc (F-7) 85 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RNS-PL-V001A 1 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(F-2) STC III-3100 III-3300 RNS Suction from RCS Inner Isolation Valve LT SV4-RNS-PL-V001B 1 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(D-2) STC III-3100 III-3300 RNS Suction from RCS Inner Isolation Valve LT SV4-RNS-PL-V002A 1 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(F-2) STC III-3100 III-3300 LT RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT-App. J SV4-RNS-PL-V002B 1 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(D-2) STC III-3100 III-3300 LT RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT-App. J SV4-RNS-PL-V003A 2 N C A 1 CK SA SV4-RNS-M6-001 C O NA CKOP Accommodate thermal expansion RNS PIV Thermal Relief Valve (G-2) CKC SV4-RNS-PL-V003B 2 N C A 1 CK SA SV4-RNS-M6-001 C O NA CKOP Accommodate thermal expansion RNS PIV Thermal Relief Valve (D-2) CKC SV4-RNS-PL-V011 2 N A A 8 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(F-7) STC III-3100 III-3300 RNS Discharge Header to Containment OC Containment Isolation Valve LT-App. J 86 Southern Nuclear Version 4.0

System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RNS-PL-V012 2 N A A 1 GL MA SV4-RNS-M6-001 C C/O AI ETM Post-Accident Long Term RCS Make-up & Containment Isolation Valve (G-7) LT- App. J SV4-RNS-PL-V013 2 N AC A 8 CK SA SV4-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-7) CKC RNS to Containment IC Containment Isolation Valve LT- App. J SV4-RNS-PL-V015A 1 N AC A 6 CK SA SV4-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Stop Check Valve LT SV4-RNS-PL-V015B 1 N AC A 6 CK SA SV4-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Stop Check Valve LT SV4-RNS-PL-V017A 1 N AC A 6 CK SA SV4-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Check Valve LT SV4-RNS-PL-V017B 1 N AC A 6 CK SA SV4-RNS-M6-001 C C/O NA CKO Accommodate thermal expansion (F-8) CKC RNS to DVI Check Valve LT SV4-RNS-PL-V020 2 N AC A 1 RV SA SV4-RNS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (G-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

RNS Suction Relief Valve LT-App. J SV4-RNS-PL-V021 2 N AC A 3 RV SA SV4-RNS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (G-2) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

RNS Suction Relief Valve LT-App. J SV4-RNS-PL-V022 2 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(F-3) STC III-3100 III-3300 RNS Suction from RCS OC Containment Isolation Valve LT-App. J SV4-RNS-PL-V023 2 N A A 10 GA MO SV4-RNS-M6-001 C C AI PI (III-3300)

(E-3) STC III-3100 III-3300 RNS Suction from IRWST/IC Containment Isolation Valve LT-App. J 87 Southern Nuclear Version 4.0

System: RNS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-RNS-PL-V061 2 N A A 3 GL AO SV4-RNS-M6-001 C C C PI (ISTC-3700)

(G-3) STC FST CVS return to RNS Suction/IC Containment Isolation Valve LT-App. J 88 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: SDS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SDS-PL-V001 3 N B A 3 BU MO SV4-SDS-M6-001 O C AI PI (III-3300)

(E-5) STC III-3100 MCR SDS (Vent) Isolation Valve III-3300 SV4-SDS-PL-V002 3 N B A 3 BU MO SV4-SDS-M6-001 O C AI PI (III-3300)

(E-5) STC III-3100 MCR SDS (Vent) Isolation Valve III-3300 89 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: SFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SFS-PL-V031 3 N B P 6 BU MA SV4-SFS-M6-001 LO O AI PI (ISTC-3700)

Refueling Cavity Drain to S/G 2 Compartment Isolation Valve (F-7)

SV4-SFS-PL-V033 3 N B P 2 PL MA SV4-SFS-M6-001 LC C AI PI (ISTC-3700)

Refueling Cavity Drain to Containment Sump Isolation Valve (E-7)

SV4-SFS-PL-V034 2 N A A 6 BU MO SV4-SFS-M6-001 C C AI PI (III-3300)

(D-6) STC III-3100 III-3300 Refueling Cavity/IRWST to SFS IC Containment Iso Valve LT-App. J SV4-SFS-PL-V035 2 N A A 6 BU MO SV4-SFS-M6-001 C C AI PI (III-3300)

(D-5) STC III-3100 III-3300 Refueling Cavity/IRWST to SFS OC Containment Iso Valve LT-App. J SV4-SFS-PL-V037 2 N AC A 4 CK SA SV4-SFS-M6-001 C C/O NA CKC (B-6) CKOP Accommodate thermal expansion SFS to Refueling Cavity/IRWST IC Containment Iso Valve LT-App. J SV4-SFS-PL-V038 2 N A A 4 BU MO SV4-SFS-M6-001 C C AI PI (III-3300)

(B-5) STC III-3100 III-3300 SFS to Refueling Cavity/IRWST OC Containment Iso Valve LT-App. J SV4-SFS-PL-V041 3 N B A 6 BU MA SV3-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit Suction Isolation Valve (F-1)

SV4-SFS-PL-V042 3 Y B P 6 BU MA SV4-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit to Pumps Suction Isolation Valve (E-3/4)

SV4-SFS-PL-V045 3 Y B P 4 BU MA SV4-SFS-M6-001 LC C AI ETM SFS Discharge Line to Cask Loading Pit Isolation Valve (D-4)

SV4-SFS-PL-V049 3 Y B P 2 PL MA SV4-SFS-M6-001 LC C AI ETM SFS Cask Loading Pit Drain to WLS Isolation Valve (E-2) 90 Southern Nuclear Version 4.0

System: SFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SFS-PL-V066 3 N B A 2 BA MA SV4-SFS-M6-001 LC C/O AI ETM Spent Fuel Pool Boiloff Makeup Isolation Valve (F-3)

SV4-SFS-PL-V067 2 N AC A 1 RV SA SV4-SFS-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (E-6) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Refueling Cavity/IRWST to SFS Penetration Relief Valve LT-App. J SV4-SFS-PL-V068 3 N B A 4 BU MA SV3-SFS-M6-001 LO O AI ETM SFS Cask Washdown Pit Drain Isolation Valve (F-2)

SV4-SFS-PL-V071 3 N C A 6 CK SA SV4-SFS-M6-001 C O/C NA CKO Refueling Cavity/IRWST to SFS Penetration Relief Valve (E-6) CKC SV4-SFS-PL-V072 3 N C A 6 CK SA SV4-SFS-M6-001 C O/C NA CKO Refueling Cavity/IRWST to SFS Penetration Relief Valve (E-6) CKC SV4-SFS-PL-V075 3 N B P 20 BU MA SV4-SFS-M6-001 LO O AI PI (ISTC-3700)

SFS Reactor Cavity Post-Accident Containment Floodup Valve (G-7) 91 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-V027A 2 N B A 12 GL MO SV4-SGS-M6-001 O C AI PI (III-3300)

(G-2) STC III-3100 SG 1 PORV Isolation valve III-3300 SV4-SGS-PL-V027B 2 N B A 12 GL MO SV4-SGS-M6-002 O C AI PI (III-3300)

(G-2) STC III-3100 SG 2 PORV Isolation valve III-3300 SV4-SGS-PL-V030A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4/5) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V030B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4/5) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V031A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test 92 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-V031B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V032A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V032B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-4) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V033A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V033B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test 93 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-V034A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V034B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V035A 2 N C A 8X10 RV SA SV4-SGS-M6-001 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 1 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V035B 2 N C A 8X10 RV SA SV4-SGS-M6-002 C O/C NA VE(I-7150(a))

(G-3) RVT(I-7150(b)) Verify Vendor setpoint RVT(I-7150(c)) Leak tightness per Vendor test RVT(I-7250(a)(1)) Setpoint verification (due 6m prior to Initial Criticality)

SG 2 Safety Valve RVT(I-7250(a)(2)) Leak tightness verification after set test SV4-SGS-PL-V036A 2 N B A 2 GL AO SV4-SGS-M6-001 O C C PI (ISTC-3700)

(G-3) STC SG1 Steam Line Drain Isolation FST SV4-SGS-PL-V036B 2 N B A 2 GL AO SV4-SGS-M6-002 O C C PI (ISTC-3700)

(G-3) STC SG2 Steam Line Drain Isolation FST 94 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-V040A 2 N B A 38 GA PH SV4-SGS-M6-001 O C C PI (ISTC-3700)

(G-1) STC Note 1 SG 1 Main Steam Isolation Valve FST SV4-SGS-PL-V040B 2 N B A 38 GA PH SV4-SGS-M6-002 O C C PI (ISTC-3700)

(G-1) STC Note 1 SG 2 Main Steam Isolation Valve FST SV4-SGS-PL-V057A 2 N B A 20 GA PH SV4-SGS-M6-001 O C C PI (ISTC-3700)

(E-4) STC Note 1 SG 1 Main Feedwater Isolation Valve FST SV4-SGS-PL-V057B 2 N B A 20 GA PH SV4-SGS-M6-002 O C C PI (ISTC-3700)

(E-4) STC Note 1 SG 2 Main Feedwater Isolation Valve FST SV4-SGS-PL-058A 2 N C A 20 CK SA SV4-SGS-M6-001 O C/O NA CKOP Accommodate thermal expansion SG1 Main Feed Check Valve (E-5) CKC SV4-SGS-PL-058B 2 N C A 20 CK SA SV4-SGS-M6-002 O C/O NA CKOP Accommodate thermal expansion SG2 Main Feed Check Valve (E-5) CKC SV4-SGS-PL-V067A 2 N B A 6 GA MO SV4-SGS-M6-001 O C AI PI (III-3300)

(D-5) STC III-3100 SG 1 Startup Feedwater Isolation Valve III-3300 SV4-SGS-PL-V067B 2 N B A 6 GA MO SV4-SGS-M6-002 O C AI PI (III-3300)

(D-5) STC III-3100 SG 2 Startup Feedwater Isolation Valve III-3300 SV4-SGS-PL-V074A 2 N B A 4 GL AO SV4-SGS-M6-001 O C C PI (ISTC-3700)

(C-5) STC SG 1 Blowdown Isolation Valve FST SV4-SGS-PL-V074B 2 N B A 4 GL AO SV4-SGS-M6-002 O C C PI (ISTC-3700)

(C-5) STC SG 2 Blowdown Isolation Valve FST SV4-SGS-PL-V075A 3 N B A 4 GL AO SV4-SGS-M6-001 O C C PI (ISTC-3700)

(C-5) STC SG 1 Blowdown Isolation Valve Second-off FST 95 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-V075B 3 N B A 4 GL AO SV4-SGS-M6-002 O C C PI (ISTC-3700)

(C-5) STC SG 2 Blowdown Isolation Valve Second-off FST SV4-SGS-PL-V086A 3 N B A 2 GL AO SV4-SGS-M6-001 C C C PI (ISTC-3700)

(F-3) STC SG1 Steam Line Drain Level Control FST SV4-SGS-PL-V086B 3 N B A 2 GL AO SV4-SGS-M6-002 C C C PI (ISTC-3700)

(F-3) STC SG2 Steam Line Drain Level Control FST SV4-SGS-PL-V233A 3 N B A 12 GL AO SV4-SGS-M6-001 C C C PI (ISTC-3700)

(H-2) STC SG 1 Power Operated Relief Valve (PORV) FST SV4-SGS-PL-V233B 3 N B A 12 GL AO SV4-SGS-M6-002 C C C PI (ISTC-3700)

(H-2) STC SG 2 Power Operated Relief Valve (PORV) FST SV4-SGS-PL-V240A 2 N B A 3 GL AO SV4-SGS-M6-001 C C C PI (ISTC-3700)

(G-1) STC SG 1 MSIV Bypass Valve FST SV4-SGS-PL-V240B 2 N B A 3 GL AO SV4-SGS-M6-002 C C C PI (ISTC-3700)

(G-1) STC SG 2 MSIV Bypass Valve FST SV4-SGS-PL-V250A 3 N B A 20 GL AO SV4-SGS-M6-001 O C C PI (ISTC-3700)

(E-2/3) STC SG 1 Feedwater Control Valve FST SV4-SGS-PL-V250B 3 N B A 20 GL AO SV4-SGS-M6-002 O C C PI (ISTC-3700)

(E-2/3) STC SG 2 Feedwater Control Valve FST SV4-SGS-PL-V255A 3 N B A 6 GL AO SV4-SGS-M6-001 C C C PI (ISTC-3700)

(D-4) STC SG 1 Startup Feedwater Control Valve FST SV4-SGS-PL-V255B 3 N B A 6 GL AO SV4-SGS-M6-002 C C C PI (ISTC-3700)

(D-4) STC SG 2 Startup Feedwater Control Valve FST 96 Southern Nuclear Version 4.0

System: SGS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-SGS-PL-256A 2 N C A 6 CK SA SV4-SGS-M6-001 C O NA CKOP Accommodate thermal expansion SG1 Startup Feedwater Check Valve (D-4) CKC SV4-SGS-PL-256B 2 N C A 6 CK SA SV4-SGS-M6-002 C O NA CKOP Accommodate thermal expansion SG2 Startup Feedwater Check Valve (D-4) CKC SV4-SGS-PL-V257A 3 N C A 1 RV SA SV4-SGS-M6-001 C O NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Main Feedwater Thermal Relief VE(I-7150(a))

SV4-SGS-PL-V257B 3 N C A 1 RV SA SV4-SGS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Main Feedwater Thermal Relief VE(I-7150(a))

SV4-SGS-PL-V258A 3 N C A 1 RV SA SV4-SGS-M6-001 C O NA RVT(I-7150(b)) Verify Vendor setpoint (D-4) RVT(I-7150(c)) Leak tightness per Vendor test Startup Feedwater Thermal Relief VE(I-7150(a))

SV4-SGS-PL-V258B 3 N C A 1 RV SA SV4-SGS-M6-002 C O NA RVT(I-7150(b)) Verify Vendor setpoint (D-4) RVT(I-7150(c)) Leak tightness per Vendor test Startup Feedwater Thermal Relief VE(I-7150(a))

97 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: VBS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VBS-PL-V186 3 N B A 28 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(F-6) STC III-3100 MCR Supply Air Isolation Valve III-3300 SV4-VBS-PL-V187 3 N B A 28 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(F-6) STC III-3100 MCR Supply Air Isolation Valve III-3300 SV4-VBS-PL-V188 3 N B A 28 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(C-7) STC III-3100 MCR Return Air Isolation Valve III-3300 SV4-VBS-PL-V189 3 N B A 28 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(C-6) STC III-3100 MCR Return Air Isolation Valve III-3300 SV4-VBS-PL-V190 3 N B A 6 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(C-3) STC III-3100 MCR Toilet Exhaust Isolation Valve III-3300 SV4-VBS-PL-V191 3 N B A 6 BU MO SV4-VBS-M6-007 O C AI PI (III-3300)

(C-3) STC III-3100 MCR Toilet Exhaust Isolation Valve III-3300 98 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: VES Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VES-PL-V001 3 N B A 1 GL MA SV4-VES-M6-002 C O/C AI ETM Air Delivery Isolation Valve (D-5)

SV4-VES-PL-V005A 3 N B A 1 GL SO SV4-VES-M6-002 C O O PI (ISTC-3700)

(F-5) STO Air Delivery Isolation Valve A FST SV4-VES-PL-V005B 3 N B A 1 GL SO SV4-VES-M6-002 C O O PI (ISTC-3700)

(E-5) STO Air Delivery Isolation Valve B FST SV4-VES-PL-V018 3 N B A 1 GL MA SV4-VES-M6-002 C O/C AI ETM Temporary Instrumentation-Isolation Valve (F-5)

SV4-VES-PL-V019 3 N B A 1 GL MA SV4-VES-M6-002 C O/C AI ETM Temporary Instrumentation-Isolation Valve (D-5)

SV4-VES-PL-V022A 3 N B A 4 BU AO SV4-VES-M6-002 C O O PI (ISTC-3700)

(C-2) STO Pressure Relief Isolation Valve A FST SV4-VES-PL-V022B 3 N B A 4 BU AO SV4-VES-M6-002 C O O PI (ISTC-3700)

(C-2) STO Pressure Relief Isolation Valve B FST SV4-VES-PL-V040A 3 N C A 1 RV SA SV4-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve A VE(I-7150(a))

SV4-VES-PL-V040B 3 N C A 1 RV SA SV4-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (F-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve B VE(I-7150(a))

SV4-VES-PL-V040C 3 N C A 1 RV SA SV4-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (E-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve C VE(I-7150(a))

99 Southern Nuclear Version 4.0

System: VES Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VES-PL-V040D 3 N C A 1 RV SA SV4-VES-M6-001 C O/C NA RVT(I-7150(b)) Verify Vendor setpoint (C-4) RVT(I-7150(c)) Leak tightness per Vendor test Air Tank Safety Relief Valve D VE(I-7150(a))

SV4-VES-PL-V044 3 N B A 1 GL MA SV4-VES-M6-002 LO O/C AI ETM Eductor Flow Path Isolation Valve (F-4)

SV4-VES-PL-V045 3 N B A 1 GL MA SV4-VES-M6-002 LO O/C AI ETM Eductor Flow Path Isolation Valve (E-3)

SV4-VES-PL-V046 3 N B A 1 GL MA SV4-VES-M6-002 C O/C AI ETM Eductor Bypass Isolation Valve (D-3) 100 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: VFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VFS-PL-V003 2 N A A 16 BU AO SV4-VFS-M6-001 C C C PI (ISTC-3700)

(B-4) STC FST Containment Purge Inlet Containment Isol - ORC LT-App. J SV4-VFS-PL-V004 2 N A A 16 BU AO SV4-VFS-M6-001 C C C PI (ISTC-3700)

(B-3) STC FST Containment Purge Inlet Containment Isol - IRC LT-App. J SV4-VFS-PL-V009 2 N A A 16 BU AO SV4-VFS-M6-001 C C C PI (ISTC-3700)

(D-8) STC FST Containment Purge Discharge Containment Isol- IRC LT-App. J SV4-VFS-PL-V010 2 N A A 16 BU AO SV4-VFS-M6-001 C C C PI (ISTC-3700)

(D-7) STC FST Containment Purge Discharge Containment Isol- ORC LT-App. J SV4-VFS-PL-V800A 2 N A A 6 BU MO SV4-VFS-M6-001 C O/C AI PI (III-3300)

(E-7) STC STO III-3100 III-3300 Containment Vacuum Relief Isolation Valve A - ORC LT-App. J SV4-VFS-PL-V800B 2 N A A 6 BU MO SV4-VFS-M6-001 C O/C AI PI (III-3300)

(E-7) STC STO III-3100 III-3300 Containment Vacuum Relief Isolation Valve B - ORC LT-App. J SV4-VFS-PL-V803A 2 N AC A 6 VB SA SV4-VFS-M6-001 C O/C NA VE(I-7170) Vacuum Relief (E-7) RVT(I-7270(a)) Actuation to verify open/close Containment Vacuum Relief Valve A - IRC LT-App. J Also meets LT requirements of I-7270(b) 101 Southern Nuclear Version 4.0

System: VFS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VFS-PL-V803B 2 N AC A 6 VB SA SV4-VFS-M6-001 C O/C NA VE(I-7170) Vacuum Relief (E-7) RVT(I-7270(a)) Actuation to verify open/close Containment Vacuum Relief Valve B - IRC LT-App. J Also meets LT requirements of I-7270(b) 102 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: VWS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-VWS-PL-V053 3 N C A 2 RV SA SV4-VWS-M6-003 C O NA RVT(I-7150(b)) Verify Vendor setpoint (B-6) RVT(I-7150(c)) Leak tightness per Vendor test Ctmt Cooling Unit Supply Hdr Relief VE(I-7150(a))

SV4-VWS-PL-V057 3 N C A 2 RV SA SV4-VWS-M6-003 C O NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test Ctmt Cooling Unit Return Hdr Relief VE(I-7150(a))

SV4-VWS-PL-V058 2 N A A 8 BU AO SV4-VWS-M6-003 O C C PI (ISTC-3700)

(B-6) STC FST Chilled Water Inlet Containment Isolation Valve LT App. J SV4-VWS-PL-V062 2 N AC A 8 CK SA SV4-VWS-M6-003 O C/O NA CKC (B-6) CKOP Accommodate thermal expansion Fan Coolers Supply IC Isol Check Valve LT App. J SV4-VWS-PL-V080 2 N AC A 1 RV SA SV4-VWS-M6-003 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint (H-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Ctmt Cooling Unit Return CIV Relief LT App. J SV4-VWS-PL-V082 2 N A A 8 BU AO SV4-VWS-M6-003 O C C PI (ISTC-3700)

(G-3) STC FST Chilled Water Outlet Containment Isolation Valve LT App. J SV4-VWS-PL-V086 2 N A A 8 BU AO SV4-VWS-M6-003 O C C PI (ISTC-3700)

(G-3) STC FST Chilled Water Outlet Containment Isolation Valve LT App. J 103 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Valve Table Unit 4 System: WLS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-WLS-PL-V055 2 N A A 2 PL AO SV4-WLS-M6-001 C C C PI (ISTC-3700)

(C-4) STC FST Containment Sump Discharge CIV - IRC LT-App. J SV4-WLS-PL-V057 2 N A A 2 PL AO SV4-WLS-M6-001 C C C PI (ISTC-3700)

(C-3) STC FST Containment Sump Discharge CIV - ORC LT-App. J SV4-WLS-PL-V058 2 N AC A 1 RV SA SV4-WLS-M6-001 C C/O NA RVT(I-7150(b)) Verify Vendor setpoint (C-4) RVT(I-7150(c)) Leak tightness per Vendor test VE(I-7150(a))

Containment Sump Discharge Penetration Thermal Relief LT-App. J SV4-WLS-PL-V067 2 N A A 1 GL AO SV4-WLS-M6-001 C C C PI (ISTC-3700)

(E-3) STC FST RCDT Gas Outlet CIV - IRC LT-App. J SV4-WLS-PL-V068 2 N A A 1 GL AO SV4-WLS-M6-001 C C C PI (ISTC-3700)

(E-3) STC FST RCDT Gas Outlet CIV - ORC LT-App. J SV4-WLS-PL-V071A 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO CVS Compt Floor Drain Check (C-8) CKC SV4-WLS-PL-V071B 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO PXS Compt A Floor Drain Check (F-8) CKC SV4-WLS-PL-V071C 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO PXS Compt B Floor Drain Check (F-8) CKC SV4-WLS-PL-V072A 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO CVS Compt Floor Drain Check (C-7) CKC SV4-WLS-PL-V072B 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO PXS Compt A Floor Drain Check (F-8) CKC 104 Southern Nuclear Version 4.0

System: WLS Valve ID Valve Actuator Drawing -----------Position----------- Required Description Class Aug. Cat. A/P Size Type Type & Co-ord. Normal Safety Fail-Safe Test Alt/CC Comments/Notes SV4-WLS-PL-V072C 3 N C A 4 CK SA SV4-WLS-M6-001 C O/C NA CKO PXS Compt B Floor Drain Check (F-8) CKC 105 Southern Nuclear Version 4.0

9.0 PRESERVICE TESTING OF DYNAMIC RESTRAINTS 9.1 GENERAL All Dynamic Restraints listed in the Tables of Section 11.0 and 12.0 will receive the following:

a) A Visual examination meeting the requirements of ISTD-4110; b) Testing per ISTD-5120. Note, this testing may have been done at the manufacturer facility as allowed by ISTD-5110; c) Thermal movement examinations to meet the requirements of ISTD-4130.

d) Corrective actions from failures of visual examinations or tests will be performed in accordance with ISTD-4140 or ISTD-5130, as appropriate.

9.2 SCHEDULE a) Testing will be performed prior to installation in the system.

b) Initial Visual Examinations will be performed prior to Hot Functional testing.

c) Visual reexaminations, if required per ISTD-4120, will be performed in conjunction with Initial Thermal Movement examinations.

d) Initial Thermal Movement examinations will be performed during Pre-core Hot Functional testing. Any subsequent Thermal Movement examinations will be done during Post-Core Hot Functional testing.

106 Southern Nuclear Version 4.0

10.0 DYNAMIC RESTRAINTS NOTES None 107 Southern Nuclear Version 4.0

11.0 VEGP-3 DYNAMIC RESTRAINTS TABLES 108 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 3 System: CVS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-CVS-PH-11Y0262-NE 3 H SV3-CVS-PLW-171/D-4 SV3-CVS-PH-11Y0262-NW 3 H SV3-CVS-PLW-171/D-4 SV3-CVS-PH-11Y0268 1 H SV3-CVS-PLW-188/C-4 SV3-CVS-PH-11Y2040 1 H SV3-CVS-PLW-171/C-5 SV3-CVS-PH-11Y2223 1 H SV3-CVS-PLW-171/C-5 SV3-CVS-PH-11Y2224 1 H SV3-CVS-PLW-171/C-4 SV3-CVS-PH-11Y2227 3 H SV3-CVS-PLW-171/C-3 SV3-CVS-PH-11Y2229 1 H SV3-CVS-PLW-182/C-6 SV3-CVS-PH-11Y2263 N H SV3-CVS-PLW-091/C-4 SV3-CVS-PH-11Y2265 N H SV3-CVS-PLW-091/B-6 SV3-CVS-PH-11Y2266 N H SV3-CVS-PLW-091/B-6 SV3-CVS-PH-11Y7074 3 H SV3-CVS-PLW-187/B-5 109 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 3 System: PXS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-PXS-PH-11Y0020 1 H SV3-PXS-PLW-01Q/C-5 SV3-PXS-PH-11Y0578 3 H SV3-PXS-PLW-01Z/C-5 SV3-PXS-PH-11Y2052 3 H SV3-PXS-PLW-02E/C-5/6 SV3-PXS-PH-11Y2057 3 H SV3-PXS-PLW-015/C-5 SV3-PXS-PH-11Y2059 3 H SV3-PXS-PLW-01H/B-6 110 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 3 System: RCS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-RCS-PH-11Y0039 1 H SV3-RCS-PLW-023/B-5 SV3-RCS-PH-11Y0060-NE 1 H SV3-RCS-PLW-023/C-6 SV3-RCS-PH-11Y0060-NW 1 H SV3-RCS-PLW-023/C-6 SV3-RCS-PH-11Y0067 1 H SV3-RCS-PLW-01L/D-4 SV3-RCS-PH-11Y0081-SW 1 H SV3-CVS-PLW-188/D-6 SV3-RCS-PH-11Y0081-NW 1 H SV3-CVS-PLW-188/D-6 SV3-RCS-PH-11Y0082 1 H SV3-RCS-PLW-028/C-5 SV3-RCS-PH-11Y0090 1 H SV3-PXS-PLW-050/C-3 SV3-RCS-PH-11Y0103 1 H SV3-RCS-PLW-043/C-4 SV3-RCS-PH-11Y0112 1 H SV3-RCS-PLW-016/B-5 SV3-RCS-PH-11Y0388 1 H SV3-RCS-PLW-030/D-3 SV3-RCS-PH-11Y0391 1 H SV3-RCS-PLW-03D/D-3 SV3-RCS-PH-11Y0528 1 H SV3-RCS-PLW-01K/D-6 SV3-RCS-PH-11Y0810 1 H SV3-RCS-PLW-080/B-5 SV3-RCS-PH-11Y0811 1 H SV3-RCS-PLW-080/B-4 SV3-RCS-PH-11Y0813 1 H SV3-RCS-PLW-070/B-4 SV3-RCS-PH-11Y1127 1 H SV3-RCS-PLW-021/C-5 SV3-RCS-PH-11Y1130 1 H SV3-RCS-PLW-024/C-4 SV3-RCS-PH-11Y1132 1 H SV3-RCS-PLW-023/B-5 SV3-RCS-PH-11Y1134 1 H SV3-RCS-PLW-023/B-6 SV3-RCS-PH-11Y1140 1 H SV3-RCS-PLW-029/B-6 SV3-RCS-PH-11Y1141 1 H SV3-RCS-PLW-023/C-6 SV3-RCS-PH-11Y1144 1 H SV3-CVS-PLW-182/B-4 SV3-RCS-PH-11Y2005 1 H SV3-RCS-PLW-015/C-5 SV3-RCS-PH-11Y2101 1 H SV3-RCS-PLW-01F/B-5 111 Southern Nuclear Version 4.0

System: RCS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-RCS-PH-11Y2106 1 H SV3-RCS-PLW-03B/D-3 SV3-RCS-PH-11Y2107 1 H SV3-RCS-PLW-03A/D-3 SV3-RCS-PH-11Y2264 1 H SV3-RCS-PLW-028/B-6 SV3-RCS-SS-E03A1 1 H SV3-PH01-V1-001/G-7 & F-4 SV3-RCS-SS-E03A2 1 H SV3-PH01-V1-001/G-7 & F-4 SV3-RCS-SS-E03B1 1 H SV3-PH01-V1-001/G-7 & F-4 SV3-RCS-SS-E03B2 1 H SV3-PH01-V1-001/G-7 & F-4 112 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 3 System: RNS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-RNS-PH-12Y2060 3 H SV3-RNS-PLW-091/C-6 113 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 3 System: SGS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-SGS-PH-11Y0001 2 H SV3-SGS-PLW-020/C-7 SV3-SGS-PH-11Y0002 2 H SV3-SGS-PLW-020/C-7 SV3-SGS-PH-11Y0004 2 H SV3-SGS-PLW-020/C-5 SV3-SGS-PH-11Y0057 2 H SV3-SGS-PLW-010/C-4 SV3-SGS-PH-11Y0058 2 H SV3-SGS-PLW-010/B-7 SV3-SGS-PH-11Y0063 2 H SV3-SGS-PLW-010/B-7 SV3-SGS-PH-11Y0463-LO 2 H SV3-SGS-PLW-030/B-6 SV3-SGS-PH-11Y0463-UP 2 H SV3-SGS-PLW-030/B-6 SV3-SGS-PH-11Y0464 2 H SV3-SGS-PLW-030/A-5 SV3-SGS-PH-11Y0470 2 H SV3-SGS-PLW-040/B-6 SV3-SGS-PH-11Y2002-NW 2 H SV3-SGS-PLW-030/B/C-6 SV3-SGS-PH-11Y2002-SW 2 H SV3-SGS-PLW-030/B/C-6 SV3-SGS-PH-11Y2021-NW 2 H SV3-SGS-PLW-030/B-6 SV3-SGS-PH-11Y2021-NE 2 H SV3-SGS-PLW-030/B-6 SV3-SGS-PH-11Y3101 2 H SV3-SGS-PLW-040/B-5/6 SV3-SGS-PH-11Y3102 2 H SV3-SGS-PLW-040/C-6 SV3-SGS-PH-11Y3121-NW 2 H SV3-SGS-PLW-040/B-6 SV3-SGS-PH-11Y3121-NE 2 H SV3-SGS-PLW-040/B-6 SV3-SGS-PH-11Y7057 2 H SV3-SGS-PLW-040/C-6 SV3-SGS-PH-12Y0108-UP 3 H SV3-SGS-PLW-140/D-4 SV3-SGS-PH-12Y0108-DN 3 H SV3-SGS-PLW-140/D-4 SV3-SGS-PH-12Y0136-UP 3 H SV3-SGS-PLW-130/D-4 SV3-SGS-PH-12Y0136-DN 3 H SV3-SGS-PLW-130/D-4 SV3-SGS-PH-12Y0507-UP 2 H SV3-SGS-PLW-140/C-5 SV3-SGS-PH-12Y0507-DN 2 H SV3-SGS-PLW-140/C-5 114 Southern Nuclear Version 4.0

System: SGS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV3-SGS-PH-12Y0510-UP 2 H SV3-SGS-PLW-130/C-5 SV3-SGS-PH-12Y0510-DN 2 H SV3-SGS-PLW-130/C-5 SV3-SGS-PH-12Y7056 2 H SV3-SGS-PLW-130/B-6 SV3-SGS-PH-12Y7058 2 H SV3-SGS-PLW-140/B-6 115 Southern Nuclear Version 4.0

12.0 VEGP-4 DYNAMIC RESTRAINTS TABLES 116 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 4 System: CVS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-CVS-PH-11Y0262-NE 3 H SV4-CVS-PLW-171/D-4 SV4-CVS-PH-11Y0262-NW 3 H SV4-CVS-PLW-171/D-4 SV4-CVS-PH-11Y0268 1 H SV4-CVS-PLW-188/C-4 SV4-CVS-PH-11Y2040 1 H SV4-CVS-PLW-171/C-5 SV4-CVS-PH-11Y2223 1 H SV4-CVS-PLW-171/C-5 SV4-CVS-PH-11Y2224 1 H SV4-CVS-PLW-171/C-4 SV4-CVS-PH-11Y2227 3 H SV4-CVS-PLW-171/C-3 SV4-CVS-PH-11Y2229 1 H SV4-CVS-PLW-182/C-6 SV4-CVS-PH-11Y2263 N H SV4-CVS-PLW-091/C-4 SV4-CVS-PH-11Y2265 N H SV4-CVS-PLW-091/B-6 .

SV4-CVS-PH-11Y2266 N H SV4-CVS-PLW-091/B-6 SV4-CVS-PH-11Y7074 3 H SV4-CVS-PLW-187/B-5 117 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 4 System: PXS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-PXS-PH-11Y0020 1 H SV4-PXS-PLW-01Q/C-5 SV4-PXS-PH-11Y0578 3 H SV4-PXS-PLW-01Z/C-5 SV4-PXS-PH-11Y2052 3 H SV4-PXS-PLW-02E/C-5/6 SV4-PXS-PH-11Y2057 3 H SV4-PXS-PLW-015/C-5 SV4-PXS-PH-11Y2059 3 H SV4-PXS-PLW-01H/B-6 118 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 4 System: RCS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-RCS-PH-11Y0039 1 H SV4-RCS-PLW-023/B-5 SV4-RCS-PH-11Y0060-NE 1 H SV4-RCS-PLW-023/C-6 SV4-RCS-PH-11Y0060-NW 1 H SV4-RCS-PLW-023/C-6 SV4-RCS-PH-11Y0067 1 H SV4-RCS-PLW-01L/D-4 SV4-RCS-PH-11Y0081-SW 1 H SV4-CVS-PLW-188/D-6 SV4-RCS-PH-11Y0081-NW 1 H SV4-CVS-PLW-188/D-6 SV4-RCS-PH-11Y0082 1 H SV4-RCS-PLW-028/C-5 SV4-RCS-PH-11Y0090 1 H SV4-PXS-PLW-050/C-3 SV4-RCS-PH-11Y0103 1 H SV4-RCS-PLW-043/C-4 SV4-RCS-PH-11Y0112 1 H SV4-RCS-PLW-016/B-5 SV4-RCS-PH-11Y0388 1 H SV4-RCS-PLW-030/D-3 SV4-RCS-PH-11Y0391 1 H SV4-RCS-PLW-03D/D-3 SV4-RCS-PH-11Y0528 1 H SV4-RCS-PLW-01K/D-6 SV4-RCS-PH-11Y0810 1 H SV4-RCS-PLW-080/B-5 SV4-RCS-PH-11Y0811 1 H SV4-RCS-PLW-080/B-4 SV4-RCS-PH-11Y0813 1 H SV4-RCS-PLW-070/B-4 SV4-RCS-PH-11Y1127 1 H SV4-RCS-PLW-021/C-5 SV4-RCS-PH-11Y1130 1 H SV4-RCS-PLW-024/C-4 SV4-RCS-PH-11Y1132 1 H SV4-RCS-PLW-023/B-5 SV4-RCS-PH-11Y1134 1 H SV4-RCS-PLW-023/B-6 SV4-RCS-PH-11Y1140 1 H SV4-RCS-PLW-029/B-6 SV4-RCS-PH-11Y1141 1 H SV4-RCS-PLW-023/C-6 SV4-RCS-PH-11Y1144 1 H SV4-CVS-PLW-182/B-4 SV4-RCS-PH-11Y2005 1 H SV4-RCS-PLW-015/C-5 SV4-RCS-PH-11Y2101 1 H SV4-RCS-PLW-01F/B-5 119 Southern Nuclear Version 4.0

System: RCS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-RCS-PH-11Y2106 1 H SV4-RCS-PLW-03B/D-3 SV4-RCS-PH-11Y2107 1 H SV4-RCS-PLW-03A/D-3 SV4-RCS-PH-11Y2264 1 H SV4-RCS-PLW-028/B-6 SV4-RCS-SS-E03A1 1 H SV4-PH01-V1-001/G-7 & F-4 SV4-RCS-SS-E03A2 1 H SV4-PH01-V1-001/G-7 & F-4 SV4-RCS-SS-E03B1 1 H SV4-PH01-V1-001/G-7 & F-4 SV4-RCS-SS-E03B2 1 H SV4-PH01-V1-001/G-7 & F-4 120 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 4 System: RNS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-RNS-PH-12Y2060 3 H SV4-RNS-PLW-091/C-6 121 Southern Nuclear Version 4.0

Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table Unit 4 System: SGS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-SGS-PH-11Y0001 2 H SV4-SGS-PLW-020/C-7 SV4-SGS-PH-11Y0002 2 H SV4-SGS-PLW-020/C-7 SV4-SGS-PH-11Y0004 2 H SV4-SGS-PLW-020/C-5 SV4-SGS-PH-11Y0057 2 H SV4-SGS-PLW-010/C-4 SV4-SGS-PH-11Y0058 2 H SV4-SGS-PLW-010/B-7 SV4-SGS-PH-11Y0063 2 H SV4-SGS-PLW-010/B-7 SV4-SGS-PH-11Y0463-LO 2 H SV4-SGS-PLW-030/B-6 SV4-SGS-PH-11Y0463-UP 2 H SV4-SGS-PLW-030/B-6 SV4-SGS-PH-11Y0464 2 H SV4-SGS-PLW-030/A-5 SV4-SGS-PH-11Y0470 2 H SV4-SGS-PLW-040/B-6 SV4-SGS-PH-11Y2002-NW 2 H SV4-SGS-PLW-030/B/C-6 SV4-SGS-PH-11Y2002-SW 2 H SV4-SGS-PLW-030/B/C-6 SV4-SGS-PH-11Y2021-NW 2 H SV4-SGS-PLW-030/B-6 SV4-SGS-PH-11Y2021-NE 2 H SV4-SGS-PLW-030/B-6 SV4-SGS-PH-11Y3101 2 H SV4-SGS-PLW-040/B-5/6 SV4-SGS-PH-11Y3102 2 H SV4-SGS-PLW-040/C-6 SV4-SGS-PH-11Y3121-NW 2 H SV4-SGS-PLW-040/B-6 SV4-SGS-PH-11Y3121-NE 2 H SV4-SGS-PLW-040/B-6 SV4-SGS-PH-11Y7057 2 H SV4-SGS-PLW-040/C-6 SV4-SGS-PH-12Y0108-UP 3 H SV4-SGS-PLW-140/D-4 SV4-SGS-PH-12Y0108-DN 3 H SV4-SGS-PLW-140/D-4 SV4-SGS-PH-12Y0136-UP 3 H SV4-SGS-PLW-130/D-4 SV4-SGS-PH-12Y0136-DN 3 H SV4-SGS-PLW-130/D-4 SV4-SGS-PH-12Y0507-UP 2 H SV4-SGS-PLW-140/C-5 SV4-SGS-PH-12Y0507-DN 2 H SV4-SGS-PLW-140/C-5 122 Southern Nuclear Version 4.0

System: SGS Pipe Snubber ID Class Type Iso. Drawing/Co-ord Alt/CC Comments/Notes SV4-SGS-PH-12Y0510-UP 2 H SV4-SGS-PLW-130/C-5 SV4-SGS-PH-12Y0510-DN 2 H SV4-SGS-PLW-130/C-5 SV4-SGS-PH-12Y7056 2 H SV4-SGS-PLW-130/B-6 SV4-SGS-PH-12Y7058 2 H SV4-SGS-PLW-140/B-6 123 Southern Nuclear Version 4.0

13.0 REFERENCE LIST 13.1 General References 13.1.1 ASME Operation and Maintenance of Nuclear Power Plants Code, 2012 Edition (ASME OM-2012) 13.1.2 Vogtle 3&4 Updated Final Safety Analysis Report, Revision 10.1 13.1.3 Appendix A, Vogtle Electric Generating Plant, Units 3 and 4 Technical Specifications, Amendment 72 (Unit 3), Amendment 71 (Unit 4).

13.1.4 LDCR-2017-070, Main Control Room Emergency Habitability System (VES) Changes to Satisfy Post-Actuation Performance Requirements (LAR-17-001) [Design Change Package, APP-GW-GEE-4733, Revision 0]

13.1.5 Corrective Action Request 50001849 13.1.6 Letter from Peter C. Hearn (NRC) to Brian H. Whitley (SNC),

Subject:

VOGTLE ELECTRIC GENERATING PLANT UNITS 3 AND 4 REQUEST FOR ALTERNATIVE: ALTERNATIVE REQUIREMENT FOR PRESERVICE TESTING OF EXPLOSIVELY ACTIVATED VALVES (VEGP 3

& 4-PST-ALT-01) (EPID NO. L-2018-LLA-0498), dated 3/26/2019 13.1.7 Letter from Peter C. Hearn (NRC) to Brian H. Whitley (SNC),

Subject:

VOGTLE ELECTRIC GENERATING PLANT UNITS 3 AND 4 REQUEST FOR ALTERNATIVE: ALTERNATIVE REQUIREMENT FOR PRESERVICE TESTING OF CLASS 1 SAFETY VALVES (VEGP 3 & 4-PST-ALT-02) (EPID L-2019-LLR-0025), dated 5/28/2019 13.1.8 LDCR-2021-001, Changes Required to Close Out As-Designed ASME Section III Overpressure Protection Reports, APP-FSAR-GEF-171, Rev. 0.

13.1.9 CAR 80003783, TS SR 3.7.9.6 Disconnect with IST Program.

13.2 System Specification Documents 13.2.1 SV3-CAS-M3-001, AP1000 Compressed and Instrument Air System (CAS) - System Specification Document, Revision 0 [APP-CAS-M3-001, Rev. 2]

13.2.2 APP-CCS-M3-001, AP1000 Component Cooling Water-System Description Document, Revision 4 13.2.3 APP-CVS-M3-001, AP1000 Chemical and Volume Control System (CVS) System Specification Document, Revision 7 13.2.4 APP-DWS-M3-001, Demineralized Water Transfer and Storage System (DWS), System Specification Document, Revision 0 13.2.5 APP-FHS-M3-001, AP1000 Fuel Handling System - System Specification Document, Revision 3 13.2.6 APP-FPS-M3-001, AP1000 Fire Protection System - System Specification Document, Revision E 13.2.7 APP-MSS-M3-001, AP1000 Main Steam System Specification Document, Revision 3 13.2.8 APP-MTS-M3-001, AP1000 Main Turbine System - System Specification Document, Revision 4 13.2.9 APP-PCS-M3-001, Passive Containment Cooling System - System Specification Document, Revision 7 13.2.10 APP-PSS-M3-001, AP1000 Primary Sampling System - System Specification Document, Revision 5 13.2.11 APP-PWS-M3-001, AP1000 Potable Water System (PWS) - System Specification Document, Revision 1 124 Southern Nuclear Version 4.0

13.2.12 APP-PXS-M3-001, Passive Core Cooling System, System Specification Document, Revision 10 13.2.13 APP-RCS-M3-001, Reactor Coolant System, System Specification Document, Revision 12 13.2.14 APP-RNS-M3-001, Normal Residual Heat Removal System - System Specification Document, Revision 5 13.2.15 APP-SDS-M3-001, Sanitary Drainage System (SDS) System Specification Document, Revision 1 13.2.16 APP-SFS-M3-001, AP1000 Spent Fuel Pool Cooling System - System Specification Document, Revision 7 13.2.17 APP-SGS-M3-001, Steam Generator System (SGS) System Specification Document, Revision 7 13.2.18 APP-VBS-M3-001, Nuclear Island Nonradioactive Ventilation System, System Specification Document, Revision D 13.2.19 APP-VES-M3-001, AP1000 Main Control Room Emergency Habitability System (VES),

System Specification Document, Revision 4 13.2.20 APP-VFS-M3-001, Containment Air Filtration System, System Specification Document, Revision 0 13.2.21 APP-VUS-M3-001, AP1000 Containment Leak Rate Test System - System Specification Document, Revision 2 13.2.22 APP-VWS-M3-001, Central Chilled Water System System Specification Document, Revision D 13.2.23 APP-WLS-M3-001, AP1000 Plant Liquid Radwaste System - System Specification Document, Revision 8 13.3 Piping and Instrumentation Diagrams 13.3.1 SV3-CAS-M6-005, Revision 3 13.3.2 SV3-CAS-M6-012, Revision 3 13.3.3 SV3-CCS-M6-002, Revision 5 13.3.4 SV3-CVS-M6-001, Revision 6 13.3.5 SV3-CVS-M6-003, Revision 6 13.3.6 SV3-CVS-M6-004, Revision 5 13.3.7 SV3-CVS-M6-005, Revision 3 13.3.8 SV3-DWS-M6-007, Revision 2 13.3.9 SV3-FPS-M6-004, Revision 6 13.3.10 SV3-MSS-M6-001, Revision 1 13.3.11 SV3-MTS-M6-002, Revision 4 13.3.12 SV3-PCS-M6-001, Revision 5 13.3.13 SV3-PCS-M6-002, Revision 6 13.3.14 SV3-PCS-M6-003, Revision 2 13.3.15 SV3-PSS-M6-001, Revision 5 13.3.16 SV3-PWS-M6-002, Revision 5 13.3.17 SV3-PXS-M6-001, Revision 3 13.3.18 SV3-PXS-M6-002, Revision 5 13.3.19 SV3-PXS-M6-003, Revision 4 13.3.20 SV3-PXS-M6-004, Revision 2 13.3.21 SV3-PXS-M6-005, Revision 0 13.3.22 SV3-RCS-M6-001, Revision 5 I

125 Southern Nuclear Version 4.0 I

13.3.23 SV3-RCS-M6-002, Revision 7 13.3.24 SV3-RCS-M6-003, Revision 4 13.3.25 SV3-RCS-M6-004, Revision 4 13.3.26 SV3-RCS-M6-005, Revision 1 13.3.27 SV3-RNS-M6-001, Revision 4 13.3.28 SV3-SDS-M6-001, Revision 2 13.3.29 SV3-SFS-M6-001, Revision 6 13.3.30 SV3-SGS-M6-001, Revision 6 13.3.31 SV3-SGS-M6-002, Revision 6 13.3.32 SV3-VBS-M6-002, Revision 6 13.3.33 SV3-VBS-M6-007, Revision 8 13.3.34 SV3-VES-M6-001, Revision 1 13.3.35 SV3-VES-M6-002, Revision 4 13.3.36 SV3-VFS-M6-001, Revision 6 13.3.37 SV3-VUS-M6-001, Revision 2 13.3.38 SV3-VWS-M6-003, Revision 3 13.3.39 SV3-WLS-M6-001, Revision 3 13.3.40 SV3-WLS-M6-007, Revision 5 13.3.41 SV4-CAS-M6-005, Revision 4 13.3.42 SV4-CAS-M6-012, Revision 4 13.3.43 SV4-CCS-M6-002, Revision 5 13.3.44 SV4-CVS-M6-001, Revision 5 13.3.45 SV4-CVS-M6-003, Revision 5 13.3.46 SV4-CVS-M6-004, Revision 4 13.3.47 SV4-CVS-M6-005, Revision 3 13.3.48 SV4-DWS-M6-007, Revision 2 13.3.49 SV4-FPS-M6-004, Revision 6 13.3.50 SV4-MSS-M6-001, Revision 1 13.3.51 SV4-MTS-M6-002, Revision 4 13.3.52 SV4-PCS-M6-001, Revision 5 13.3.53 SV4-PCS-M6-002, Revision 6 13.3.54 SV4-PCS-M6-003, Revision 2 13.3.55 SV4-PSS-M6-001, Revision 5 13.3.56 SV4-PWS-M6-002, Revision 5 13.3.57 SV4-PXS-M6-001, Revision 4 13.3.58 SV4-PXS-M6-002, Revision 6 13.3.59 SV4-PXS-M6-003, Revision 4 13.3.60 SV4-PXS-M6-004, Revision 2 13.3.61 SV4-PXS-M6-005, Revision 0 13.3.62 SV4-RCS-M6-001, Revision 6 13.3.63 SV4-RCS-M6-002, Revision 7 13.3.64 SV4-RCS-M6-003, Revision 4 13.3.65 SV4-RCS-M6-004, Revision 4 13.3.66 SV4-RNS-M6-001, Revision 4 13.3.67 SV4-SDS-M6-001, Revision 2 13.3.68 SV4-SFS-M6-001, Revision 6 126 Southern Nuclear Version 4.0

13.3.69 SV4-SGS-M6-001, Revision 6 13.3.70 SV4-SGS-M6-002, Revision 6 13.3.71 SV4-VBS-M6-002, Revision 6 13.3.72 SV4-VBS-M6-007, Revision 8 13.3.73 SV4-VES-M6-001, Revision 1 13.3.74 SV4-VES-M6-002, Revision 4 13.3.75 SV4-VFS-M6-001, Revision 6 13.3.76 SV4-VUS-M6-001, Revision 2 13.3.77 SV4-VWS-M6-003, Revision 3 13.3.78 SV4-WLS-M6-001, Revision 2 13.3.79 SV4-WLS-M6-007, Revision 4 127 Southern Nuclear Version 4.0