ND-22-0254, Submittal of Inservice Testing Program Plan - 1st Interval, Version 2.0
| ML22097A331 | |
| 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-22-0254 | |
| Download: ML22097A331 (141) | |
Text
Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243 Tel 205.992.7079 April 7, 2022 Docket Nos.: 52-025 ND-22-0254 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 Inservice Testing Program Plan - 1st Interval, Version 2.0 Ladies and Gentlemen:
In accordance with the 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 a copy of the Vogtle Electric Generating Plant Units 3 and 4 Inservice Testing Program Plan - 1st Interval (Version 2.0). This IST Plan is based on the ASME OM Code 2012 Edition. In accordance with 10 CFR 50.55a(f)(4)(i), the 2012 Edition was the most recent edition in 10CFR50.55a on November 23, 2019 (which was 12 months prior to the scheduled Unit 3 fuel load date at the time of initial plan submittal to the NRC). An Alternative per 10CFR50.55a(z) (IST-Alt-01) was authorized by the NRC to allow Unit 4 to use the same Code Edition as Unit 3, provided Unit 4 initial fuel load commences prior to November 23, 2022 (Reference 15.1.6).
This version replaces the initial issuance of the Inservice Testing Program Plan submitted May 21, 2020 (ADAMS No. ML20142A358). This version clarifies testing for MSS-V001, V002, V003, V004, V005, V006, SGS-V040A/B, and V057A/B, clarifies fail safe actions for turbine stop and control valves and SGS-V040A/B and SGS-V057A/B, adds cold shutdown justifications and testing for MTS-V001A/B, V002A/B, V003A/B, V004A/B, for SFS-V037, and for SGS-V256A/B, revises normal positions of PCS-V042, V044, and V046, revises testing for PXS-V122A/B and V124A/B to disassembly, 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.
A Southern Nuclear
U.S. Nuclear Regulatory Commission ND-22-0254 Page 2 of 4 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 Generation Plant Units 3&4, Inservice Testing Program Plan -
1st Interval, Version 2.0 Amy C. Chamberlain
U.S. Nuclear Regulatory Commission ND-22-0254 Page 3 of 4 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-22-0254 Page 4 of 4 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-22-0254 Vogtle Electric Generating Plant Units 3 and 4 Inservice Testing Program Plan - 1st Interval Version 2.0 (This enclosure consists of 136 pages, not including this cover page.)
Southern Nuclear Version 2.0 INSERVICE TESTING PROGRAM PLAN - 1st INTERVAL 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 Post Office Box 1295 Birmingham, AL 35201-1295 Plant Location: 7825 River Road Waynesboro, GA 30830
i Southern Nuclear Version 2.0 TABLE OF CONTENTS Section Pages 1.0 IST PROGRAM INTRODUCTION 1-1 - 1-2 2.0 ABBREVIATIONS 2-1 - 2-3 3.0 PROGRAM ALTERNATIVES 3-1 - 3-4 4.0 INSERVICE TESTING OF PUMPS 4-1 5.0 INSERVICE TESTING OF VALVES 5-1 6.0 VALVE NOTES 6-1 7.0 VEGP-3 VALVE TABLES 7-1 - 7-38 8.0 VEGP-4 VALVE TABLES 8-1 - 8-38 9.0 COLD SHUTDOWN JUSTIFICATIONS 9-1 - 9-20 10.0 REFUELING OUTAGE JUSTIFICATIONS 10 10-7 11.0 INSERVICE TESTING OF DYNAMIC RESTRAINTS 11-1 12.0 DYNAMIC RESTRAINTS NOTES 12-1 13.0 VEGP-3 DYNAMIC RESTRAINTS TABLES 13 13-6 14.0 VEGP-4 DYNAMIC RESTRAINTS TABLES 14 14-6
15.0 REFERENCES
15 15-5
1-1 Southern Nuclear Version 2.0 1.0 IST PROGRAM INTRODUCTION 1.1 GENERAL This document describes the Pump, Valve, and Dynamic Restraint Inservice Testing (IST)
Program Plan for the First 10-year Interval at Vogtle Electric Generating Plant (VEGP), Units 3 &
- 4. Provided below are important dates relative to the IST Plan.
Combined Operating License: February 10, 2012 (Unit 3); February 10, 2012 (Unit 4)
Scheduled Fuel Load: April 26, 2022 (Unit 3); October 4, 2022 (Unit 4)
Commercial Operation: TBD (Unit 3); TBD (Unit 4) 1.2 CODE EDITION This IST Plan is based on the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code 2012 Edition. This the most recent edition in 10CFR50.55a on 11/23/2019 (12 months prior to the scheduled Unit 3 fuel load date at the time of initial plan submittal to the NRC). An Alternative per 10CFR50.55a(z) (IST-Alt-01) was authorized by the NRC to allow Unit 4 to use the same Code Edition as Unit 3, provided Unit 4 initial fuel load commences prior to November 23, 2022 (Reference 15.1.6).
1.3 EFFECTIVE DATE The IST Program for the 1st 10-year Interval will begin with the initial electrical generation by nuclear heat on each unit, and end after 10 years, unless federal regulations are revised otherwise.
1.4 SCOPE This document is a description of the IST Program Plan for Units 3 and 4 at VEGP. This document describes only the IST 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 IST Program Plan in the Updated Final Safety Analysis Report (UFSAR).
To ensure that components which 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 IST plan includes all Safety Related (AP1000 Quality group A, B, C) pumps, valves and dynamic restraints that meet the Scope of ISTA-1100, ISTC-1200 and ISTF-1100.
1-2 Southern Nuclear Version 2.0 1.5 SUBSEQUENT PROGRAM PLAN REVISIONS It is anticipated that revisions to this document required by changes to the design prior to or during the First 10-year Inservice Interval will be maintained by Southern Nuclear and submitted to the NRC as required by the OM Code and 10CFR50.55a. Any changes which require NRC approval of Alternative testing requirements will be submitted in accordance with 10CFR50.55a(z).
Additionally, this document will be reviewed and revised near the end of the 120-month interval, to the requirements of 10CFR50.55a for the next 120-month interval.
1.6 RESPONSIBILITY Southern Nuclear Operating Company (SNC) bears the overall responsibility for the implementation of the Inservice testing activities contained in this program per the ASME OM Code 2012 Edition, Subsection ISTA-1500.
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 2012 Edition, Subsection ISTA-9000.
1.8 METHODS OF TESTING The method of testing applicable to the components will be contained in the plant specific procedures which have not been finalized at this time and are not referenced in this document.
The procedures are being developed in accordance with OM Code requirements and NRC conditions. The OM Code does not stipulate any specific training/certification requirements for personnel involved in OM Code testing. At Plant Vogtle Units 3&4, all testing is performed by operations, maintenance, engineering or contract personnel who have been trained to perform specific testing tasks.
1.9 STANDARDS FOR TESTING EVALUATION The acceptance criteria applicable for the components to be tested will initially be developed based on Preservice testing results, and calculation limitations in the accident analyses, in accordance with OM Code requirements. Analysis limits, where applicable are provided in the IST Basis documents. Acceptance criteria for specific tests will be contained in the applicable surveillance testing procedures which will be available for review at the plant site.
2-1 Southern Nuclear Version 2.0 2.0 ABBREVIATIONS ABBREVIATION DEFINITION A
Active (valve table)
A OM Code Category A Valve (see OM Code)
AC OM Code Categories A and C both apply (see OM Code)
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. II Check valve testing to Appendix II (Condition Monitoring)
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 (see OM Code)
BC OM Code Categories B and C both apply (see OM Code)
BA Ball Valve BU Butterfly Valve C
OM Code Category C Valve (see OM Code)
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 CS Cold Shutdown frequency CSJ Cold Shutdown Justification CVS Chemical and Volume Control System CV Check Valve
2-2 Southern Nuclear Version 2.0 D
OM Code Category D Valve (see OM Code)
DTPG Defined Test Plan Group (snubbers)
DVI Direct Vessel Injection DWS Demineralized Water System 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
2-3 Southern Nuclear Version 2.0 PL Plug Valve PSS Primary Sampling System PWS Potable Water System PXS Passive Core Cooling System RCS Reactor Coolant System RD Rupture Disc RNS Normal Residual Heat Removal System RO Refueling Outage frequency ROJ Refueling Outage Justification 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 y
Year(s)
III-3300 MOV performance test per ASME OM Code App. III-3300 III-3600 MOV exercise test per ASME OM Code App. III-3600
3-1 Southern Nuclear Version 2.0 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.
See IST-Alt-01 for using the same Code Edition for Unit 4 as Unit 3, which was authorized 3/2/2020 (Reference 15.1.6).
3.2 CODE CASES This section identifies the Code Cases, and associated limitations, that are incorporated in this IST plan.
Code Case OMN-20, Inservice Code Frequency is used for all components in the plan in establishing testing frequency, as authorized by 10CFR50.55a(b)(3)(x). Only the base frequency will be shown in the component tables.
3-2 Southern Nuclear Version 2.0 Alternative VEGP 3&4-IST-ALT-01 Plant Site-Unit:
Vogtle Electric Generating Plant (VEGP) - Unit 4 Interval-Interval Dates:
Applies to the initial inservice test (IST) interval for Unit 4.
ASME Code Components Affected:
All components in the IST program.
Applicable Code Edition and Addenda:
ASME Operation and Maintenance of Nuclear Power Plants (OM) Code, 2012 Edition for 1st Inservice Test Interval.
Applicable Code Requirements:
10 CFR 50.55a(f)(4)(i) requires the ASME OM Code edition and addenda for the initial IST interval be the latest edition and addenda incorporated by reference in 10 CFR 50.55a(a)(1)(iv) 12 months before the date scheduled for initial loading of fuel under a combined license under 10 CFR part 52.
The OM Code, ISTA-3200 has the same requirements for establishing the Code Edition for the Initial Inservice Test Interval (in ISTA-3200(f)(2)).
Reason for Request:
With a one year gap between the scheduled fuel loadings of Vogtle Unit 3 and Unit 4, there is the possibility that the Code Edition required for the Inservice Test program plan will be different between the two units. Because the two units are nearly identical, the Combined License application was for both units, and both units share a common UFSAR, it would create inconsistencies between the two units that would increase the complexity of the UFSAR and testing programs that would increase the probability of human error in developing and implementing two different programs.
3-3 Southern Nuclear Version 2.0 To minimize the problems of developing and implementing two separate IST Programs, it would be preferable to have both IST Programs be developed to the Code Edition and Addenda required for the lead unit (Unit 3).
Based on the current scheduled initial loading of fuel for Unit 3 being November 23, 2020, and the current schedule for addition of ASME OM Code Editions to 10 CFR 50.55a being late February 2020, the current latest edition of the OM Code listed in 10 CFR 50.55a (2012 Edition) would be used for establishing the initial 120-month interval IST Programs for Vogtle 3 & 4.
Proposed Alternative and Basis for Use:
Proposed Alternative:
In lieu of the requirements of 10 CFR 50.55a(f)(4)(i), for establishing the ASME OM Code edition and addenda for the initial Inservice Test interval, and the equivalent requirements in ISTA-3200(f)(2), it is proposed that the Code Edition for the initial Unit 4 IST Interval be the same edition and/or addenda as established for the associated initial Unit 3 Interval (which will be established in accordance with 10 CFR 50.55a(f)(4)(i)).
Basis for Use:
Having both units on the same Code Edition for their initial intervals allows both IST programs to be developed utilizing the same edition of the applicable Codes, which will make it less complicated for involved personnel to become familiar with the Code requirements, will ensure a greater degree of consistency for IST between the units, and will reduce the effort associated with surveillance procedure revisions for the program update and for maintenance of the program documents.
The Code of Record established for Unit 3 is in accordance with the 10 CFR 50.55a requirements and represents requirements established by the NRC to ensure the equipment is adequately tested to ensure safe plant operation. Applying a common Code edition to both Unit 3 and Unit 4 would establish common requirements which would minimize potential errors caused by having to maintain two separate program requirements for the 2 units. Additionally, based on the version of the Code anticipated for Unit 3 IST program, the units will use the same Code Edition as that used for Preservice testing, which will ensure consistency of Preservice to Inservice testing.
Per NUREG-1482, Rev. 2, Basis for 3.3.2, Concurrent Intervals states The staff believes that conducting IST programs for multiple unit sites using the same Code edition could provide an improvement in program effectiveness.
3-4 Southern Nuclear Version 2.0 Based on the above, the proposed alternative provides an equivalent level of quality and safety in accordance with 10 CFR 50.55a(z)(1).
Duration of Proposed Alternative:
Through the end of the first Vogtle Unit 4 IST interval.
References:
- 1. Vogtle 1 & 2 General Relief Request RR-G-2 (Legacy Accession Number 9608200192).
- 2. NRC Approval letter for RR-G-1 & RR-G-2, dated 11/27/1996 (Legacy Accession Number 9612020101)
- 3. NUREG-1482, Rev. 2, Section 3.3.2, Concurrent Intervals.
4-1 Southern Nuclear Version 2.0 4.0 INSERVICE 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 IST plan, includes only pumps that have an emergency power source. The emergency power source (Class 1E) for the AP1000 is the Class 1E DC Distribution system, and there are no pumps are powered from this source.
5-1 Southern Nuclear Version 2.0 5.0 INSERVICE TESTING OF VALVES 5.1 GENERAL Valves in this program are identified by the component number in tables for Units 3 and 4 respectively, and will be tested in accordance with the OM Code and 10CFR50.55a conditions, unless otherwise specified in this program.
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 IST Program 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 all active 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 IST Program Plan, where practicable.
5.2.3 To meet the 10CFR50.55a(b)(3)(xi) condition on Valve Position Indication, all designated PI testing will include verification of disc position or supplemental verification to ensure the position indication is indicating disc position. The testing to confirm disc position may not be performed simultaneously with the remote position indication verification.
6-1 Southern Nuclear Version 2.0 6.0 VALVE NOTES
- 1. For all active Power Operated Valves there is a requirement for exercise testing, and stroke timing of the valve in the direction required to perform the safety function of the valve. For the purpose of this plan, the exercising requirement is not called out separately, only the stroke time test, which includes exercising of the valve, is shown in the valve table.
- 2. Squib valve charges, a minimum of 20% are tested every outage (2y), with a minimum of one from each safety train. Circuit testing to verify proper electrical parameters (voltage, current) to actuate squib charge to be performed on valves selected for squib testing.
- 3. Squib valves disassembly/inspection is performed on one valve of each size each outage (2y),
but each valve must be disassembled/inspected every 10 years.
- 4. Stop check with manual operator for maintenance only. Operates as a check valve.
- 5. SFS-V071 & SFS-V072 are exercised per ISTC-5221(c), one valve disassembled/stroke verified each refueling outage.
- 6. PXS-V122A/B & PXS-V124A/B are exercised per ISTC-5221(c), one valve disassembled/stroke verified each refueling outage.
- 7. These valves have 2 skid-mounted solenoid valves each supporting the valves required function. Stroke time testing to be done using each solenoid separately.
- 8. MTS-V001A/B, V002A/B, V003A/B V004A/B fail closed on loss of hydraulic pressure, but not on loss of electrical power to the fast-acting solenoid valves.
- 9. The steam and feedwater isolation valves (SGS-V040A/B & V057A/B) are hydraulic operated valves that fail closed on loss of hydraulic fluid. The solenoid valves (skid-mounted) that dump the hydraulic fluid fail closed on loss of power, not fail-safe, and hence redundant solenoid valves are provided. Stroke time testing of the valves will be done from each solenoid valve.
- 10. MSS-V001, V002, V003, V004, V005, V006, have two solenoid valves to trip the valves closed to perform their safety function. This test is to exercise and time the valve using each of the safety function solenoids.
7-1 Southern Nuclear Version 2.0 7.0 VEGP-3 VALVE TABLES
7-2 Southern Nuclear Version 2.0 VOGTLE UNIT 3 CAS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-CAS-PL-V014 2
N A
A 2
BA AO SV3-CAS-M6-005 O
C C
PI 2y F-3 STC RO ROJ-CAS-1 FST RO ROJ-CAS-1 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 RO ROJ-CAS-1 F-4 CKOP RO ROJ-CAS-1 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
AI 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 CS CSJ-CAS-1 E-4 CKOP CS CSJ-CAS-1 Thermal Expansion Service Air Containment Isolation Check Valve LT App.J
7-3 Southern Nuclear Version 2.0 VOGTLE UNIT 3 CCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-CCS-PL-V200 2
N A
A 10 BU MO SV3-CCS-M6-002 O
C AI PI 2RO/3y H-2 STC/III-3600 2y III-3300 2RO/3y 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 RO ROJ-CCS-1 H-2 CKOP RO ROJ-CCS-1 Thermal Expanison 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 2RO/3y B-2 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y B-1 STC/III-3600 2y III-3300 2RO/3y Cooling Water Returny Ctmt Isol - ORC LT App.J SV3-CCS-PL-V220 2
N AC A
1 RV SA SV3-CCS-M6-002 C
O/C NA RVT 10y Thermal Relief Ctmt Return CIV Thermal Relief C-2 LT App.J SV3-CCS-PL-V270 3
N C
A 4
RV SA SV3-CCS-M6-002 C
O NA RVT 4y/10y CCS Supply Line to Ctmt Safety/Relief H-2 SV3-CCS-PL-V271 3
N C
A 4
RV SA SV3-CCS-M6-002 C
O NA RVT 4y/10y CCS Return Line to Ctmt Safety/Relief C-2
7-4 Southern Nuclear Version 2.0 VOGTLE UNIT 3 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-CVS-PL-V001 1
N B
A 3
GA MO SV3-CVS-M6-001 O
C AI PI 2RO/3y G-8 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV3-CVS-PL-V002 1
N B
A 3
GA MO SV3-CVS-M6-001 O
C AI PI 2RO/3y G-7 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV3-CVS-PL-V003 3
N B
A 3
GL MO SV3-CVS-M6-001 O
C AI PI 2RO/3y G-7 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV3-CVS-PL-V040 2
N A
P 2
BA MA SV3-CVS-M6-005 LC C
AI LT App.J Resin Flush IRC 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 ORC Isolation Valve F-4 SV3-CVS-PL-V042 2
N AC A
1 RV SA SV3-CVS-M6-005 C
O/C NA RVT 10y Thermal Relief Flush Line Containment Isolation Relief Valve G-4 LT App.J SV3-CVS-PL-V045 2
N A
A 2
GL AO SV3-CVS-M6-005 C
C C
FST Q
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
FST Q
Letdown Line Outside Containment Isolation Valve LT App.J SV3-CVS-PL-V058 2
N AC A
1 RV SA SV3-CVS-M6-005 C
O/C NA RVT 10y Thermal Relief Letdown Line to De-gassifier Containment Isolation Thermal Relief Valve E-4 LT App.J SV3-CVS-PL-V064 N
N C
A 3
CK SA SV3-CVS-M6-005 C
O NA CKOP CS CSJ-CVS-2 Thermal Expansion Make-up Discharge Header Check Valve C-5 CKC CS CSJ-CVS-2 SV3-CVS-PL-V067 1
N C
A 1
CK SA SV3-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion Make-up Return Line Spring-Assisted Check Valve F-7 CKC CS CSJ-CVS-1 SV3-CVS-PL-V080 3
N C
A 3
CK SA SV3-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion Regen HX Shell Side Outlet Check Valve G-7 CKC CS CSJ-CVS-1 SV3-CVS-PL-V081 1
N BC A
3 SC AO SV3-CVS-M6-001 O
C NA CKOP CS CSJ-CVS-1 Purification Return Line Stop Check Valve G-7 CKC CS CSJ-CVS-1 SV3-CVS-PL-V082 1
N C
A 3
CK SA SV3-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion RCS Purification Return Line Check Valve G-8 CKC CS CSJ-CVS-1
7-5 Southern Nuclear Version 2.0 VOGTLE UNIT 3 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-CVS-PL-V084 1
N B
A 2
GL AO SV3-CVS-M6-001 C
C C
PI 2y F-7 STC RO ROJ-CVS-1 Auxiliary Pressurizer Spray Line Isolation Valve FST RO ROJ-CVS-1 SV3-CVS-PL-V085 1
N C
A 2
CK SA SV3-CVS-M6-001 C
C/O NA CKC RO ROJ-CVS-1 Auxiliary Pressurizer Spray Line Check Valve F-8 CKOP RO ROJ-CVS-1 Thermal Expansion SV3-CVS-PL-V090 2
N A
A 3
GA MO SV3-CVS-M6-005 O
C AI PI 2RO/3y C-2 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y C-4 STC/III-3600 2y III-3300 2RO/3y 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
FST Q
Zinc Injection Containment Isolation Valve ORC LT App.J SV3-CVS-PL-V094 2
N A
A 1
GL AO SV3-CVS-M6-003 O
C C
FST Q
Zinc Injection Containment Isolation Valve IRC LT App.J SV3-CVS-PL-V098 2
N AC A
1 RV SA SV3-CVS-M6-003 C
O/C NA RVT 10y Thermal Relief Zinc Injection Ctmt Isol Thermal Relief Valve F-6 LT App.J SV3-CVS-PL-V100 2
N AC A
1 CK SA SV3-CVS-M6-005 C
C/O NA CKC CS CSJ-CVS-2 B-4 CKOP CS CSJ-CVS-2 Thermal Expansion Makeup Line Containment Isolation Relief LT App.J SV3-CVS-PL-V136A 3
N B
A 3
C C
Demineralized Water System Isolation Valve FST Q
SV3-CVS-PL-V136B 3
N B
A 3
C C
Demineralized Water System Isolation Valve FST Q
SV3-CVS-PL-V217 2
N AC A
1/2 CK SA SV3-CVS-M6-003 O
C/O NA CKC Q
D-7 CKOP Q
Thermal Expansion Hydrogen Injection Containment Isolation Check Valve IRC LT App.J
7-6 Southern Nuclear Version 2.0 VOGTLE UNIT 3 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-CVS-PL-V219 2
N A
A 1/2 GL AO SV3-CVS-M6-003 O
C C
FST Q
Zinc Injection Containment Isolation Valve IRC LT App.J
7-7 Southern Nuclear Version 2.0 VOGTLE UNIT 3 DWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-DWS-PL-V241 3
N C
A 1
RV SA SV3-DWS-M6-007 C
O NA RVT 10y Thermal Relief Demin Water Supply to Containment Relief E-5 SV3-DWS-PL-V244 2
N A
P 3
AI LT App.J Demin Water Supply Containment Isolation Valve - Outside E-6 SV3-DWS-PL-V245 2
N AC A
2 CK SA SV3-DWS-M6-007 C
C/O NA CKC CS CSJ-DWS-1 E-6 CKOP CS CSJ-DWS-1 Thermal Expansion Demin Water Supply Containment Isolation Check Valve - IRC LT App.J
7-8 Southern Nuclear Version 2.0 VOGTLE UNIT 3 FHS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-FHS-PL-V001 3
N B
A 30 GA MA SV3-SFS-M6-012 C
C AI ETM 2y Fuel Transfer Tube Isolation Valve F-6
7-9 Southern Nuclear Version 2.0 VOGTLE UNIT 3 FPS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-FPS-PL-V050 2
N A
P 6
AI LT App.J Fire Water Containment Supply Isolation F-4 SV3-FPS-PL-V052 2
N AC A
6 CK SA SV3-FPS-M6-004 C
C/O NA CKC CS CSJ-FPS-1 F-5 CKOP CS CSJ-FPS-1 Thermal Expansion Fire Water Supply Ctmt 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 10y Thermal Relief Fire Water Supply IC Thermal Relief F/G-5
7-10 Southern Nuclear Version 2.0 VOGTLE UNIT 3 MSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-MSS-PL-V001 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V002 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V003 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V004 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V005 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V006 N
Y B
A 16 GL AO SV3-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV3-MSS-PL-V015A N Y
B A
10 GL AO SV3-MSS-M6-001 O
C C
PI 2y B-6 STC CS CSJ-MSS-1 MSR 2nd Stage Reheat Steam AO Isolation Valve FST CS CSJ-MSS-1 SV3-MSS-PL-V015B N
Y B
A 10 GL AO SV3-MSS-M6-001 O
C C
PI 2y G-6 STC CS CSJ-MSS-1 MSR 2nd Stage Reheat Steam AO Isolation Valve FST CS CSJ-MSS-1
7-11 Southern Nuclear Version 2.0 VOGTLE UNIT 3 MTS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-MTS-PL-V001A N Y
B A
28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 F-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #1 FST Q
SV3-MTS-PL-V001B N
Y B
A 28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 C-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #3 FST Q
SV3-MTS-PL-V002A N Y
B A
28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 F-6 STC Q
STC CS CSJ-MTS-1 Control Valve #1 FST Q
SV3-MTS-PL-V002B N
Y B
A 28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 C-6 STC Q
STC CS CSJ-MTS-1 Control Valve #3 FST Q
SV3-MTS-PL-V003A N Y
B A
28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 E-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #2 FST Q
SV3-MTS-PL-V003B N
Y B
A 28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 D-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #4 FST Q
SV3-MTS-PL-V004A N Y
B A
28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 E-6 STC Q
STC CS CSJ-MTS-1 Control Valve #2 FST Q
SV3-MTS-PL-V004B N
Y B
A 28 GL EH SV3-MTS-M6-002 O
C C*
PI 2y
- Note 8 D-6 STC Q
STC CS CSJ-MTS-1 Control Valve #4 FST Q
7-12 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PCS-PL-V001A 3
N B
A 6
O O
PI 2y E-4 STO Q
PCS Actuation Valve A FST Q
SV3-PCS-PL-V001B 3
N B
A 6
O O
PI 2y E-6 STO Q
PCS Actuation Valve B FST Q
SV3-PCS-PL-V001C 3
N B
A 6
GA MO SV3-PCS-M6-001 C
O AI PI 2RO/3y E-5 STO/III-3600 Q PCS Actuation Valve C III-3300 2RO/3y SV3-PCS-PL-V002A 3
N B
A 6
GA MO SV3-PCS-M6-001 O
O AI PI 2RO/3y E-4 STO/III-3600 2y PCS Isolation Valve A III-3300 2RO/3y SV3-PCS-PL-V002B 3
N B
A 6
GA MO SV3-PCS-M6-001 O
O AI PI 2RO/3y E-6 STO/III-3600 2y PCS Isolation Valve B III-3300 2RO/3y SV3-PCS-PL-V002C 3
N B
A 6
GA MO SV3-PCS-M6-001 O
O AI PI 2RO/3y E-5 STO/III-3600 2y PCS Isolation Valve C III-3300 2RO/3y SV3-PCS-PL-V005 3
N B
A 4
GA MA SV3-PCS-M6-002 O
C AI ETM 2y PCS to DWS/FPS Iso Valve G-5 SV3-PCS-PL-V009 3
N B
A 3
GA MA SV3-PCS-M6-001 C
O/C AI ETM 2y 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 2y 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 2y PCS Long Term Supply to Distribution Bucket Iso Valve E-4 SV3-PCS-PL-V023 3
N B
A 4
GA MA SV3-PCS-M6-002 O
C AI ETM 2y 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
C/O NA CKC App. II PCS/SFS Long Term Make-up Supply Check Valve F-4 CKO App. II SV3-PCS-PL-V042 3
N B
A 1
GL MA SV3-PCS-M6-002 C
C AI ETM 2y 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 2y
- Locked one turn from full open.
PCS Long Term Supply from Temp Pump Iso Valve F-4
7-13 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PCS-PL-V045 3
N B
P 2
GL MA SV3-PCS-M6-001 C
O AI ETM 2y 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 2y 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 2y PCCWST Drain Isolation Valve C-2 SV3-PCS-PL-V050 3
N B
A 2
GL MA SV3-PCS-M6-002 C
C/O AI ETM 2y 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 2y Spent Fuel Pool Emergency Makeup Lower Isolation Valve B-2
7-14 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PSS-PL-V001A 2
N C
A 1/4 GL SO SV3-PSS-M6-003 O
O C
RVT 10y Thermal Relief Hot Leg 1 Sample Isolation E-8 SV3-PSS-PL-V001B 2
N C
A 1/4 GL SO SV3-PSS-M6-003 C
O C
RVT 10y Thermal Relief Hot Leg 2 Sample Isolation D-8 SV3-PSS-PL-V003 2
N C
A 1/4 GL SO SV3-PSS-M6-003 C
O C
RVT 10y Thermal Relief Pzr Sample Isolation G-8 SV3-PSS-PL-V008 2
N A
A 5/8 GL SO SV3-PSS-M6-001 O
C C
FST Q
Containment Air Sample Containment Isolation Valve IRC LT App.J SV3-PSS-PL-V010A 2
N AC A
1/4 GL SO SV3-PSS-M6-001 O
C C
FST Q
LT App.J Liquid Sample Line Containment Isolation Valve A IRC RVT 10y Thermal Relief SV3-PSS-PL-V010B 2
N AC A
1/4 GL SO SV3-PSS-M6-001 C
C C
FST Q
LT App.J Liquid Sample Line Containment Isolation Valve B IRC RVT 10y Thermal Relief SV3-PSS-PL-V011A 2
N A
A 1/4 GL AO SV3-PSS-M6-001 O
C C
FST Q
Liquid Sample Line Containment Isolation Valve A ORC LT App.J SV3-PSS-PL-V011B 2
N A
A 1/4 GL AO SV3-PSS-M6-001 C
C C
FST Q
Liquid Sample Line Containment Isolation Valve B ORC LT App.J SV3-PSS-PL-V023 2
N A
A 1
GL AO SV3-PSS-M6-001 O
C C
FST Q
Ctmt Air Sample Return Isolation Valve LT App.J
7-15 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PSS-PL-V024 2
N A
A 1
GL SO SV3-PSS-M6-001 O
C C
FST Q
Ctmt Liquid and Air Sample Return IRC Isol Valve LT App.J SV3-PSS-PL-V046 2
N A
A 5/8 GL AO SV3-PSS-M6-001 O
C C
FST Q
Air Sample Line Ctmt Isol ORC Valve LT App.J
7-16 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PWS-PL-V418 3
N B
A 1
GL MA SV3-PCS-M6-002 O
C AI ETM 2y Control Room Boundary Outside Isolation Valve G-4 SV3-PWS-PL-V420 3
N B
A 1
GL MA SV3-PCS-M6-002 O
C AI ETM 2y Control Room Boundary Inside Isolation Valve F-4 SV3-PWS-PL-V498 3
N C
A 1
O NA VB 2y Vacuum Breaker Ctmt Return CIV Thermal Relief F-4
7-17 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PXS-PL-V002A 1
N B
P 8
GA MO SV3-PXS-M6-001 O
O AI PI 2y 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 2y 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 2y CMT A Discharge Manual Isol Valve D/E-6 SV3-PXS-PL-V013B 1
N B
P 8
GA MA SV3-PXS-M6-001 LO O
AI PI 2y CMT B Discharge Manual Isol Valve D/E-3 SV3-PXS-PL-V014A 1
N B
A 8
GL AO SV3-PXS-M6-001 C
O O
PI 2y E-7 STO Q
CMT A Outlet Valve FST Q
SV3-PXS-PL-V014B 1
N B
A 8
GL AO SV3-PXS-M6-001 C
O O
PI 2y E-3 STO Q
CMT B Outlet Valve FST Q
SV3-PXS-PL-V015A 1
N B
A 8
GL AO SV3-PXS-M6-001 C
O O
PI 2y D-7 STO Q
CMT A Outlet Valve FST Q
SV3-PXS-PL-V015B 1
N B
A 8
GL AO SV3-PXS-M6-001 C
O O
PI 2y D-3 STO Q
CMT B Outlet Valve FST Q
SV3-PXS-PL-V016A 1
N C
A 8
CK SA SV3-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT A Outlet Check Valve D/E-6 CKC RO ROJ-PXS-1 SV3-PXS-PL-V016B 1
N C
A 8
CK SA SV3-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT B Outlet Check Valve D/E-3 CKC RO ROJ-PXS-1 SV3-PXS-PL-V017A 1
N C
A 8
CK SA SV3-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT A Outlet Check Valve D/E-6 CKC RO ROJ-PXS-1 SV3-PXS-PL-V017B 1
N C
A 8
CK SA SV3-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT B Outlet Check Valve D/E-3 CKC RO ROJ-PXS-1 SV3-PXS-PL-V021A 3
N B
P 1
GL SO SV3-PXS-M6-001 C
C C
PI 2y Accumulator A Nitrogen Supply Valve C-7 SV3-PXS-PL-V021B 3
N B
P 1
GL SO SV3-PXS-M6-001 C
C C
PI 2y 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 RVT 4y/10y Accumulator A Relief Valve C-7
7-18 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PXS-PL-V022B 3
N C
A 1
RV SA SV3-PXS-M6-001 C
O/C NA RVT 4y/10y Accumulator B Relief Valve C-2 SV3-PXS-PL-V027A 3
N B
P 8
GA MO SV3-PXS-M6-001 O
O AI PI 2y 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 2y 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 CKC RO ROJ-PXS-2 B-6 CKO RO ROJ-PXS-2 Accumulator A Outlet to RCS Check LT 2y PIV SV3-PXS-PL-V028B 1
N AC A
8 CK SA SV3-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-3 CKO RO ROJ-PXS-2 Accumulator B Outlet to RCS Check LT 2y PIV SV3-PXS-PL-V029A 1
N AC A
8 CK SA SV3-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-6 CKO RO ROJ-PXS-2 Accumulator A Outlet to RCS Check LT 2y PIV SV3-PXS-PL-V029B 1
N AC A
8 CK SA SV3-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-4 CKO RO ROJ-PXS-2 Accumulator B Outlet to RCS Check LT 2y PIV SV3-PXS-PL-V042 2
N A
A 1
GL AO SV3-PXS-M6-001 O
C C
FST Q
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 CKC Q
D-2 CKOP Q
Thermal Expansion 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 RVT 10y Thermal Relief High Pressure Nitrogen to Containment Penetration Thermal Relief Valve D-2 SV3-PXS-PL-V101 1
N B
P 14 GA MO SV3-PXS-M6-002 O
O AI PI 2y RCS to PRHR Heat Exchanger Isolation Valve G-1 SV3-PXS-PL-V108A 1
N B
A 14 BA AO SV3-PXS-M6-002 C
O O
PI 2y G-1 STO CS CSJ-PXS-1 PRHR Heat Exchanger Outlet Valve to RCS A FST CS CSJ-PXS-1 SV3-PXS-PL-V108B 1
N B
A 14 BA AO SV3-PXS-M6-002 C
O O
PI 2y F-1 STO CS CSJ-PXS-1 PRHR Heat Exchanger Outlet Valve to RCS B FST CS CSJ-PXS-1
7-19 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PXS-PL-V109 1
N B
P 14 GA MA SV3-PXS-M6-001 LO O
AI PI 2y RCS to PRHR Heat Exchanger Isolation Valve F-1 SV3-PXS-PL-V117A 3
N B
P 8
GA MO SV3-PXS-M6-002 O
O AI PI 2y Containment Recirculation 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 2y Containment Recirculation B to RCS Isolation Valve E-5 SV3-PXS-PL-V118A 3
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y E-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump A to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V118B 3
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y E-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump B to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V119A 3
N C
A 8
CK NA SV3-PXS-M6-002 C
O/C NA PI 2y E-7 CKC RO ROJ-PXS-3 Containment Recirc. Sump A Outlet to RCS Check CKO RO ROJ-PXS-3 SV3-PXS-PL-V119B 3
N C
A 8
CK NA SV3-PXS-M6-002 C
O/C NA PI 2y E-5 CKC RO ROJ-PXS-3 Containment Recirc. Sump A Outlet to RCS Check CKO RO ROJ-PXS-3 SV3-PXS-PL-V120A 3
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y E-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump A to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V120B 3
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y E-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump B to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V121A 3
N B
P 8
GA MO SV3-PXS-M6-002 O
O AI PI 2y 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 2y IRWST/Recirc. Sump to RCS B Isolation Valve D-7 SV3-PXS-PL-V122A 1
N C
A 8
CK SA SV3-PXS-M6-002 C
O/C NA PI 2y C-7 CKC RO*
- Note 6 IRWST Injection Line A Check Valve CKO RO*
7-20 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PXS-PL-V122B 1
N C
A 8
CK SA SV3-PXS-M6-002 C
O/C NA PI 2y C-5 CKC RO*
- Note 6 IRWST Injection Line B Check Valve CKO RO*
SV3-PXS-PL-V123A 1
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y C-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection A Isolation Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V123B 1
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y C-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection B Isolation Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V124A 1
N C
A 8
CK NA SV3-PXS-M6-002 C
O/C NA PI 2y C-7 CKC RO*
- Note 6 IRWST Injection Line A Check Valve CKO RO*
SV3-PXS-PL-V124B 1
N C
A 8
CK NA SV3-PXS-M6-002 C
O/C NA PI 2y C-5 CKC RO*
- Note 6 IRWST Injection Line B Check Valve CKO RO*
SV3-PXS-PL-V125A 1
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y C-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection A Isolation Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V125B 1
N D
A 8
SQ SQ SV3-PXS-M6-002 C
O AI Remote Insp 2y C-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection B Isolation Valve Disass. Insp 10y Note 3 SV3-PXS-PL-V130A 3
N B
A 2
BA AO SV3-PXS-M6-002 O
C C
IRWST Gutter Isolation A Valve FST Q
SV3-PXS-PL-V130B 3
N B
A 2
BA AO SV3-PXS-M6-002 O
C C
IRWST Gutter Isolation B Valve FST Q
SV3-PXS-PL-V208A 2
N A
P 3/8 GL MA SV3-PXS-M6-003 LC C
AI 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 2y Core Makeup Tank A Fill Isolation F-6
7-21 Southern Nuclear Version 2.0 VOGTLE UNIT 3 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-PXS-PL-V230B 2
N B
P 1
GL AO SV3-PXS-M6-003 C
C C
PI 2y Core Makeup Tank B Fill Isolation G-6 SV3-PXS-PL-V231A 2
N C
A 1
CK SA SV3-PXS-M6-003 C
O NA CKOP CS CSJ-PXS-3 Thermal Expansion CMT A Fill Check Valve F-7 CKC CS CSJ-PXS-3 SV3-PXS-PL-V231B 2
N C
A 1
CK SA SV3-PXS-M6-003 C
O NA CKOP CS CSJ-PXS-3 Thermal Expansion CMT B Fill Check Valve G-7 CKC CS CSJ-PXS-3 SV3-PXS-PL-V232A 2
N B
P 1
GL AO SV3-PXS-M6-003 C
C C
PI 2y Accumulator A Fill/Drain Isolation E-6 SV3-PXS-PL-V232B 2
N B
P 1
GL AO SV3-PXS-M6-003 C
C C
PI 2y Accumulator B Fill/Drain Isolation G-6
7-22 Southern Nuclear Version 2.0 VOGTLE UNIT 3 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-RCS-PL-V001A 1
N B
A 4
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Control Valve III-3300 2RO/3y SV3-RCS-PL-V001B 1
N B
A 4
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Control Valve III-3300 2RO/3y SV3-RCS-PL-V002A 1
N B
A 8
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Control Valve III-3300 2RO/3y SV3-RCS-PL-V002B 1
N B
A 8
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Control Valve III-3300 2RO/3y SV3-RCS-PL-V003A 1
N B
A 8
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y H-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Control Valve III-3300 2RO/3y SV3-RCS-PL-V003B 1
N B
A 8
GL MO SV3-RCS-M6-002 C
O AI PI 2RO/3y F-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Control Valve III-3300 2RO/3y SV3-RCS-PL-V004A 1
N D
A 14 SQ SQ SV3-RCS-M6-001 C
O AI Remote Insp 2y G-6 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV3-RCS-PL-V004B 1
N D
A 14 SQ SQ SV3-RCS-M6-001 C
O AI Remote Insp 2y F-3 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV3-RCS-PL-V004C 1
N D
A 14 SQ SQ SV3-RCS-M6-001 C
O AI Remote Insp 2y F-6 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV3-RCS-PL-V004D 1
N D
A 14 SQ SQ SV3-RCS-M6-001 C
O AI Remote Insp 2y F-3 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3
7-23 Southern Nuclear Version 2.0 VOGTLE UNIT 3 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-RCS-PL-V005A 1
N C
A 6
RV SA SV3-RCS-M6-002 C
O/C NA RVT 2y/5y Includes PI Pressurizer Safety Valve H-7 SV3-RCS-PL-V005B 1
N C
A 6
RV SA SV3-RCS-M6-002 C
O/C NA RVT 2y/5y Includes PI Pressurizer Safety Valve F-6 SV3-RCS-PL-V010A 3
N C
A 1
O NA VB 2y ADS Header Vacuum Breaker G-4 SV3-RCS-PL-V010B 3
N C
A 1
O NA VB 2y ADS Header Vacuum Breaker E-4 SV3-RCS-PL-V011A 1
N B
A 4
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V011B 1
N B
A 4
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V012A 1
N B
A 8
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V012B 1
N B
A 8
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V013A 1
N B
A 8
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V013B 1
N B
A 8
GA MO SV3-RCS-M6-002 C
O AI PI 2RO/3y F-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Isolation Valve III-3300 2RO/3y SV3-RCS-PL-V014A 1
N B
P 14 GA MO SV3-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve G-6 SV3-RCS-PL-V014B 1
N B
P 14 GA MO SV3-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-3 SV3-RCS-PL-V014C 1
N B
P 14 GA MO SV3-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-6 SV3-RCS-PL-V014D 1
N B
P 14 GA MO SV3-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-3
7-24 Southern Nuclear Version 2.0 VOGTLE UNIT 3 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-RCS-PL-V150A 1
N BC A
1 GL SO SV3-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 FST CS CSJ-RCS-2 Reactor Head Vent Valve RVT 10y Thermal relief SV3-RCS-PL-V150B 1
N BC A
1 GL SO SV3-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 FST CS CSJ-RCS-2 Reactor Head Vent Valve RVT 10y Thermal relief SV3-RCS-PL-V150C 1
N B
A 1
GL SO SV3-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 Reactor Head Vent Valve FST CS CSJ-RCS-2 SV3-RCS-PL-V150D 1
N B
A 1
GL SO SV3-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 Reactor Head Vent Valve FST CS CSJ-RCS-2 SV3-RCS-PL-V233 3
N B
P 2
GL MA SV3-RCS-M6-002 LO O
AI PI 2y 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 RRD 5y Safety Valve Discharge Chamber Rupture Disk H-8 SV3-RCS-PY-K04 3
N D
A 10 RD SA SV3-RCS-M6-002 C
O NA RRD 5y Safety Valve Discharge Chamber Rupture Disk F-7
7-25 Southern Nuclear Version 2.0 VOGTLE UNIT 3 RNS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-RNS-PL-V001A 1
N A
A 10 GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y F-2 STC/III-3600 2y III-3300 2RO/3y RNS Suction from RCS Inner Isolation Valve LT 2y PIV SV3-RNS-PL-V001B 1
N A
A 10 GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y D-2 STC/III-3600 2y III-3300 2RO/3y RNS Suction from RCS Inner Isolation Valve LT 2y PIV SV3-RNS-PL-V002A 1
N A
A 10 GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y F-2 STC/III-3600 2y III-3300 2RO/3y LT 2y PIV RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT AppJ SV3-RNS-PL-V002B 1
N A
A 10 GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y D-2 STC/III-3600 2y III-3300 2RO/3y LT 2y PIV RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT AppJ SV3-RNS-PL-V003A 1
N C
A 1
CK SA SV3-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 RNS PIV Thermal Relief Valve G-2 CKOP CS CSJ-RNS-1 Thermal Expansion SV3-RNS-PL-V003B 1
N C
A 1
CK SA SV3-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 RNS PIV Thermal Relief Valve D-2 CKOP CS CSJ-RNS-1 Thermal Expansion SV3-RNS-PL-V011 2
N A
A 8
GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y F-7 STC/III-3600 2y III-3300 2RO/3y RNS Discharge Header to Containment OC Containment Isolation Valve LT AppJ SV3-RNS-PL-V012 2
N A
A 1
GL MA SV3-RNS-M6-001 LC C/O AI ETM 2y 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 NA CKC CS CSJ-RNS-1 F-7 CKO CS CSJ-RNS-1 Thermal Expansion 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
- Note 4 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Stop Check Valve LT 2y PIV
7-26 Southern Nuclear Version 2.0 VOGTLE UNIT 3 RNS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-RNS-PL-V015B 1
N AC A
6 CK*
SA*
SV3-RNS-M6-001 C
- Note 4 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Stop Check Valve LT 2y PIV SV3-RNS-PL-V017A 1
N AC A
6 CK SA SV3-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Check Valve LT 2y PIV SV3-RNS-PL-V017B 1
N AC A
6 CK SA SV3-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Check Valve LT 2y PIV SV3-RNS-PL-V020 2
N AC A
1 RV SA SV3-RNS-M6-001 C
O/C NA RVT 4y/10y RNS Suction Relief Valve G-2 LT App.J SV3-RNS-PL-V021 2
N AC A
3 RV SA SV3-RNS-M6-001 C
O/C NA RVT 4y/10y RNS Suction Relief Valve G-2 LT App.J SV3-RNS-PL-V022 2
N A
A 10 GA MO SV3-RNS-M6-001 C
C AI PI 2RO/3y F-3 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y E-3 STC/III-3600 2y III-3300 2RO/3y RNS Suction from IRWST/IC Containment Isolation Valve LT App J SV3-RNS-PL-V061 2
N A
A 3
GL AO SV3-RNS-M6-001 C
C C
FST Q
CVS Return to RNS Suction/IC Containment Isolation Valve LT App.J
7-27 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SDS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SDS-PL-V001 3
N B
A 3
BU MO SV3-SDS-M6-001 O
C AI PI 2RO/3y E-5 STC/III-3600 2y MCR SDS (Vent) Isolation Valve III-3300 2RO/3y SV3-SDS-PL-V002 3
N B
A 3
BU MO SV3-SDS-M6-001 O
C AI PI 2RO/3y E-5 STC/III-3600 2y MCR SDS (Vent) Isolation Valve III-3300 2RO/3y
7-28 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SFS-PL-V031 3
N B
P 6
AI PI 2y 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 2y 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 2RO/3y D-6 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y D-5 STC/III-3600 2y III-3300 2RO/3y 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 CS CSJ-SFS-1 B-6 CKOP CS CSJ-SFS-1 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 2RO/3y D-5 STC/III-3600 2y III-3300 2RO/3y SFS to Refueling Cavity/IRWST OC Containment Iso Valve LT App.J SV3-SFS-PL-V041 3
N B
A 6
AI ETM 2y SFS Cask Loading Pit Suction Isolation Valve F-1 SV3-SFS-PL-V042 3
Y B
P 6
AI ETM 2y SFS Cask Loading Pit to Pumps Suction Isolation Valve E-3/4 SV3-SFS-PL-V045 3
Y B
P 4
AI ETM 2y 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 2y SFS Cask Loading Pit Drain to WLS Isolation Valve E-2 SV3-SFS-PL-V066 3
N B
A 8
BA MA SV3-SFS-M6-001 LC O/C AI ETM 2y Spent Fuel Pool Boiloff Makeup Isolation Valve G-3 SV3-SFS-PL-V067 2
N AC A
1 RV SA SV3-SFS-M6-001 C
O/C NA RVT 10y Thermal Relief Refueling Cavity/IRWST to SFS Penetration Relief Valve E-6 LT App.J SV3-SFS-PL-V068 3
N B
A 6
AI ETM 2y SFS Cask Washdown Pit Drain Isolation Valve F-2
7-29 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SFS-PL-V071 3
N C
A 6
CK SA SV3-SFS-M6-001 C
O/C NA CKC RO*
- Note 5 Refueling Cavity Side Drain to S/G 2 Compartment Valve F-7 CKO RO*
SV3-SFS-PL-V072 3
N C
A 6
CK SA SV3-SFS-M6-001 C
O/C NA CKC RO*
- Note 5 Refueling Cavity Side Drain to S/G 2 Compartment Valve F-7/8 CKO RO*
SV3-SFS-PL-V075 3
N B
P 20 BU MA SV3-SFS-M6-001 LO O
AI PI 2y SFS Reactor Cavity Post-Accident Containment Flood-up Valve G-7
7-30 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SGS-PL-V027A 2
N B
A 12 GL MO SV3-SGS-M6-001 O
C AI PI 2RO/3y G-4/5 STC/III-3600 2y SG1 PORV Isolation Valve III-3300 2RO/3y SV3-SGS-PL-V027B 2
N B
A 12 GL MO SV3-SGS-M6-002 O
C AI PI 2RO/3y G-5 STC/III-3600 2y SG2 PORV Isolation Valve III-3300 2RO/3y SV3-SGS-PL-V030A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-4 SV3-SGS-PL-V030B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-4 SV3-SGS-PL-V031A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV3-SGS-PL-V031B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV3-SGS-PL-V032A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV3-SGS-PL-V032B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV3-SGS-PL-V033A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV3-SGS-PL-V033B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV3-SGS-PL-V034A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-2 SV3-SGS-PL-V034B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-2 SV3-SGS-PL-V035A 2
N C
A 8
RV SA SV3-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-2 SV3-SGS-PL-V035B 2
N C
A 8
RV SA SV3-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-2 SV3-SGS-PL-V036A 2
N B
A 2
GL AO SV3-SGS-M6-001 O
C C
Steam Line Condensate Drain Isolation FST Q
7-31 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SGS-PL-V036B 2
N B
A 2
GL AO SV3-SGS-M6-002 O
C C
Steam Line Condensate Drain Isolation FST Q
SV3-SGS-PL-V040A 2
N B
A 38 GA PH SV3-SGS-M6-001 O
C C*
PI 2y
N B
A 38 GA PH SV3-SGS-M6-002 O
C C*
PI 2y
N B
A 20 GA PH SV3-SGS-M6-001 O
C C*
PI 2y
- Note 9 E-4 STC CS CSJ-SGS-1 Note 7 Main Feedwater Line Isolation FST CS CSJ-SGS-1 SV3-SGS-PL-V057B 2
N B
A 20 GA PH SV3-SGS-M6-002 O
C C*
PI 2y
- Note 9 E-4 STC CS CSJ-SGS-1 Note 7 Main Feedwater Line Isolation FST CS CSJ-SGS-1 SV3-SGS-PL-V058A 2
N C
A 20 CK SA SV3-SGS-M6-001 O
C/O NA CKC CS CSJ-SGS-2 SG 1 Main Feed Check Valve E-5 CKOP CS CSJ-SGS-2 Thermal Expansion SV3-SGS-PL-V058B 2
N C
A 20 CK SA SV3-SGS-M6-002 O
C/O NA CKC CS CSJ-SGS-2 SG 2 Main Feed Check Valve E-5 CKOP CS CSJ-SGS-2 Thermal Expansion SV3-SGS-PL-V067A 2
N B
A 6
GA MO SV3-SGS-M6-001 O
C AI PI 2RO/3y D-5 STC/III-3600 2y Startup Feedwater Isolation III-3300 2RO/3y SV3-SGS-PL-V067B 2
N B
A 6
GA MO SV3-SGS-M6-002 O
C AI PI 2RO/3y D-5 STC/III-3600 2y Startup Feedwater Isolation III-3300 2RO/3y SV3-SGS-PL-V074A 2
N B
A 4
GL AO SV3-SGS-M6-001 O
C C
SG 1 Blowdown Isolation Valve FST Q
SV3-SGS-PL-V074B 2
N B
A 4
GL AO SV3-SGS-M6-002 O
C C
SG 2 Blowdown Isolation Valve FST Q
SV3-SGS-PL-V075A 3
N B
A 4
GL AO SV3-SGS-M6-001 O
C C
SG 1 Blowdown Isolation Valve FST Q
7-32 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SGS-PL-V075B 3
N B
A 4
GL AO SV3-SGS-M6-002 O
C C
SG 2 Blowdown Isolation Valve FST Q
SV3-SGS-PL-V086A 3
N B
A 2
GL AO SV3-SGS-M6-001 C
C C
SG 1 Steam Line Drain Level Control FST Q
SV3-SGS-PL-V086B 3
N B
A 2
GL AO SV3-SGS-M6-002 C
C C
SG 2 Steam Line Drain Level Control FST Q
SV3-SGS-PL-V233A 3
N B
A 12 GL AO SV3-SGS-M6-001 C
C C
PI 2y H-4/5 STC RO Per ISTC-3510 FST RO Per ISTC-3510 SG1 Steam Line Power Operated Relief Valve LT 2y Per I-8200 SV3-SGS-PL-V233B 3
N B
A 12 GL AO SV3-SGS-M6-002 C
C C
PI 2y H-5 STC RO Per ISTC-3510 FST RO Per ISTC-3510 SG2 Steam Line Power Operated Relief Valve LT 2y Per I-8200 SV3-SGS-PL-V240A 2
N B
A 3
GL AO SV3-SGS-M6-001 C
C C
SV3-SGS-PL-V240B 2
N B
A 3
GL AO SV3-SGS-M6-002 C
C C
SV3-SGS-PL-V250A 3
N B
A 20 GL AO SV3-SGS-M6-001 O
C C
PI 2y E-2/3 STC CS CSJ-SGS-1 Main Feedwater Control Valve FST CS CSJ-SGS-1 SV3-SGS-PL-V250B 3
N B
A 20 GL AO SV3-SGS-M6-002 O
C C
PI 2y E-2/3 STC CS CSJ-SGS-1 Main Feedwater Control Valve FST CS CSJ-SGS-1 SV3-SGS-PL-V255A 3
N B
A 6
GL AO SV3-SGS-M6-001 C
C C
Startup Feedwater Control Valve FST Q
SV3-SGS-PL-V255B 3
N B
A 6
GL AO SV3-SGS-M6-002 C
C C
Startup Feedwater Control Valve FST Q
7-33 Southern Nuclear Version 2.0 VOGTLE UNIT 3 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-SGS-PL-V256A 3
N C
A 6
CK SA SV3-SGS-M6-001 C
O NA CKC CS CSJ-SGS-3 SG 1 Startup Feed Check Valve D-4 CKOP CS Thermal Expansion SV3-SGS-PL-V256B 3
N C
A 6
CK SA SV3-SGS-M6-002 C
O NA CKC CS CSJ-SGS-3 SG 2 Startup Feed Check Valve D-4 CKOP CS Thermal Expansion SV3-SGS-PL-V257A 3
N C
A 1
RV SA SV3-SGS-M6-001 C
O NA RVT 10y Thermal Relief Main Feedwater Thermal Relief E-4 SV3-SGS-PL-V257B 3
N C
A 1
RV SA SV3-SGS-M6-002 C
O NA RVT 10y Thermal Relief Main Feedwater Thermal Relief E-4 SV3-SGS-PL-V258A 3
N C
A 1
RV SA SV3-SGS-M6-001 C
O NA RVT 10y Thermal Relief Startup Feedwater Thermal Relief D-4 SV3-SGS-PL-V258B 3
N C
A 1
RV SA SV3-SGS-M6-002 C
O NA RVT 10y Thermal Relief Startup Feedwater Thermal Relief D-4
7-34 Southern Nuclear Version 2.0 VOGTLE UNIT 3 VBS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-VBS-PL-V186 3
N B
A 28 BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y F-6 STC/III-3600 2y MCR Supply Air Isolation Valve III-3300 2RO/3y SV3-VBS-PL-V187 3
N B
A 28 BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y F-6 STC/III-3600 2y MCR Supply Air Isolation Valve III-3300 2RO/3y SV3-VBS-PL-V188 3
N B
A 28 BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y C-7 STC/III-3600 2y MCR Return Air Isolation Valve III-3300 2RO/3y SV3-VBS-PL-V189 3
N B
A 28 BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y C-6 STC/III-3600 2y MCR Return Air Isolation Valve III-3300 2RO/3y SV3-VBS-PL-V190 3
N B
A 6
BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y C-3 STC/III-3600 2y MCR Toilet Exhaust Isolation Valve III-3300 2RO/3y SV3-VBS-PL-V191 3
N B
A 6
BU MO SV3-VBS-M6-007 O
C AI PI 2RO/3y C-3 STC/III-3600 2y MCR Toilet Exhaust Isolation Valve III-3300 2RO/3y
7-35 Southern Nuclear Version 2.0 VOGTLE UNIT 3 VES Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-VES-PL-V001 3
N B
A 1
GL MA SV3-VES-M6-002 C
O/C AI ETM 2y 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 2y F-5 STO Q
Air Delivery Isolation Valve A FST Q
SV3-VES-PL-V005B 3
N B
A 1
GL SO SV3-VES-M6-002 C
O O
PI 2y E-5 STO Q
Air Delivery Isolation Valve B FST Q
SV3-VES-PL-V018 3
N B
A 1
GL MA SV3-VES-M6-002 C
O/C AI ETM 2y Temporary Insturmentation Isolation Valve F-5 SV3-VES-PL-V019 3
N B
A 1
GL MA SV3-VES-M6-002 C
O/C AI ETM 2y Temporary Insturmentation Isolation Valve E-5 SV3-VES-PL-V022A 3
N B
A 4
O O
PI 2y C-2 STO Q
Pressure Relief Isolation Valve A FST Q
SV3-VES-PL-V022B 3
N B
A 4
O O
PI 2y C-2 STO Q
Pressure Relief Isolation Valve B FST Q
SV3-VES-PL-V040A 3
N C
A 1
RV SA SV3-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve A H-4 SV3-VES-PL-V040B 3
N C
A 1
RV SA SV3-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve B F-4 SV3-VES-PL-V040C 3
N C
A 1
RV SA SV3-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve C D/E-4 SV3-VES-PL-V040D 3
N C
A 1
RV SA SV3-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve D C-4 SV3-VES-PL-V044 3
N B
A 1
GL MA SV3-VES-M6-002 LO O/C AI ETM 2y Main Air Flowpath Isolation Valve F-4 SV3-VES-PL-V045 3
N B
A 1
GL MA SV3-VES-M6-002 LO O/C AI ETM 2y Eductor Supply Isolation Valve E-3 SV3-VES-PL-V046 3
N B
A 1
GL MA SV3-VES-M6-002 C
C/O AI ETM 2y Eductor Bypass Isolation Valve D-3
7-36 Southern Nuclear Version 2.0 VOGTLE UNIT 3 VFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-VFS-PL-V003 2
N A
C C
FST Q
Containment Purge Inlet Containment Isol - ORC LT App.J SV3-VFS-PL-V004 2
N A
C C
FST Q
Containment Purge Inlet Containment Isol - IRC LT App.J SV3-VFS-PL-V009 2
N A
C C
FST Q
Containment Purge Discharge Containment Isol - IRC LT App.J SV3-VFS-PL-V010 2
N A
C C
FST Q
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
C/O AI PI 2RO/3y E-7 STC/III-3600 2y STO/III-3600 2y III-3300 2RO/3y 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
C/O AI PI 2RO/3y E-7 STC/III-3600 2y STO/III-3600 2y III-3300 2RO/3y Containment Vacuum Relief Isolation Valve B - ORC LT App.J SV3-VFS-PL-V803A 2
N AC A
O/C NA VB 2y Containment Vacuum Relief Valve A - IRC E-7 LT App.J SV3-VFS-PL-V803B 2
N AC A
O/C NA VB 2y Containment Vacuum Relief Valve B - IRC E-7 LT App.J
7-37 Southern Nuclear Version 2.0 VOGTLE UNIT 3 VWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-VWS-PL-V053 3
N C
A 2
RV SA SV3-VWS-M6-003 C
O NA RVT 10y Thermal Relief Ctmt Cooling Unit Supply Hdr Relief B-6 SV3-VWS-PL-V057 3
N C
A 2
RV SA SV3-VWS-M6-003 C
O NA RVT 10y Thermal Relief Ctmt Cooling Unit Return Hdr Relief H-4 SV3-VWS-PL-V058 2
N A
A 8
C C
FST Q
Chilled Water Inlet Containment Isol Valve LT App.J SV3-VWS-PL-V062 2
N AC A
8 CK SA SV3-VWS-M6-003 O
C/O NA CKC CS CSJ-VWS-1 B-6 CKOP CS CSJ-VWS-1 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
O/C NA RVT 10y Thermal Relief Ctmt Cooling Unit Return CIV Relief H-4 LT App.J SV3-VWS-PL-V082 2
N A
A 8
C C
FST Q
Chilled Water Outlet Containment Isolation Valve LT App.J SV3-VWS-PL-V086 2
N A
A 8
C C
FST Q
Chilled Water Outlet Containment Isolation Valve LT App.J
7-38 Southern Nuclear Version 2.0 VOGTLE UNIT 3 WLS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV3-WLS-PL-V055 2
N A
A 2
PL AO SV3-WLS-M6-001 C
C C
FST Q
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
FST Q
Containment Sump Discharge CIV - ORC LT App.J SV3-WLS-PL-V058 2
N AC A
1 RV SA SV3-WLS-M6-001 C
O/C NA RVT 10y Thermal Relief Containment Sump Discharge Penetration Thermal Relief C-4 LT App.J SV3-WLS-PL-V067 2
N A
A 1
GL AO SV3-WLS-M6-001 C
C C
FST Q
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
FST Q
RCDT Gas Outlet CIV - ORC LT App.J SV3-WLS-PL-V071A 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 CVS Compt Floor Drain Check C-8 CKO CS CSJ-WLS-1 SV3-WLS-PL-V071B 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt A Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV3-WLS-PL-V071C 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt B Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV3-WLS-PL-V072A 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 CVS Compt Floor Drain Check C-7 CKO CS CSJ-WLS-1 SV3-WLS-PL-V072B 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt A Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV3-WLS-PL-V072C 3
N C
A 4
CK SA SV3-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt B Floor Drain Check G-8 CKO CS CSJ-WLS-1
8-1 Southern Nuclear Version 2.0 8.0 VEGP-4 VALVE TABLES
8-2 Southern Nuclear Version 2.0 VOGTLE UNIT 4 CAS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-CAS-PL-V014 2
N A
A 2
BA AO SV4-CAS-M6-005 O
C C
PI 2y F-3 STC RO ROJ-CAS-1 FST RO ROJ-CAS-1 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 RO ROJ-CAS-1 F-4 CKOP RO ROJ-CAS-1 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
AI 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 CS CSJ-CAS-1 E-4 CKOP CS CSJ-CAS-1 Thermal Expansion Service Air Containment Isolation Check Valve LT App.J
8-3 Southern Nuclear Version 2.0 VOGTLE UNIT 4 CCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-CCS-PL-V200 2
N A
A 10 BU MO SV4-CCS-M6-002 O
C AI PI 2RO/3y H-2 STC/III-3600 2y III-3300 2RO/3y 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 RO ROJ-CCS-1 H-2 CKOP RO ROJ-CCS-1 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 2RO/3y B-2 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y B-1 STC/III-3600 2y III-3300 2RO/3y Cooling Water Returny Ctmt Isol - ORC LT App.J SV4-CCS-PL-V220 2
N AC A
1 RV SA SV4-CCS-M6-002 C
O/C NA RVT 10y Thermal Relief Ctmt Return CIV Thermal Relief C-2 LT App.J SV4-CCS-PL-V270 3
N C
A 4
RV SA SV4-CCS-M6-002 C
O NA RVT 4y/10y CCS Supply Line to Ctmt Safety/Relief H-2 SV4-CCS-PL-V271 3
N C
A 4
RV SA SV4-CCS-M6-002 C
O NA RVT 4y/10y CCS Return Line to Ctmt Safety/Relief C-2
8-4 Southern Nuclear Version 2.0 VOGTLE UNIT 4 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-CVS-PL-V001 1
N B
A 3
GA MO SV4-CVS-M6-001 O
C AI PI 2RO/3y G-8 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV4-CVS-PL-V002 1
N B
A 3
GA MO SV4-CVS-M6-001 O
C AI PI 2RO/3y G-7 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV4-CVS-PL-V003 3
N B
A 3
GL MO SV4-CVS-M6-001 O
C AI PI 2RO/3y G-7 STC/III-3300 2y CVS Purification Stop Valve III-3300 2RO/3y SV4-CVS-PL-V040 2
N A
P 2
BA MA SV4-CVS-M6-005 LC C
AI LT App.J Resin Flush IRC 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 ORC Isolation Valve F-4 SV4-CVS-PL-V042 2
N AC A
1 RV SA SV4-CVS-M6-005 C
O/C NA RVT 10y Thermal Relief Flush Line Containment Isolation Relief Valve G-4 LT App.J SV4-CVS-PL-V045 2
N A
A 2
GL AO SV4-CVS-M6-005 C
C C
FST Q
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
FST Q
Letdown Line Outside Containment Isolation Valve LT App.J SV4-CVS-PL-V058 2
N AC A
1 RV SA SV4-CVS-M6-005 C
O/C NA RVT 10y Thermal Relief Letdown Line to De-gassifier Containment Isolation Thermal Relief Valve E-4 LT App.J SV4-CVS-PL-V064 N
N C
A 3
CK SA SV4-CVS-M6-005 C
O NA CKOP CS CSJ-CVS-2 Thermal Expansion Make-up Discharge Header Check Valve C-5 CKC CS CSJ-CVS-2 SV4-CVS-PL-V067 1
N C
A 1
CK SA SV4-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion Make-up Return Line Spring-Assisted Check Valve F-7 CKC CS CSJ-CVS-1 SV4-CVS-PL-V080 3
N C
A 3
CK SA SV4-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion Regen HX Shell Side Outlet Check Valve G-7 CKC CS CSJ-CVS-1 SV4-CVS-PL-V081 1
N BC A
3 SC AO SV4-CVS-M6-001 O
C NA CKOP CS CSJ-CVS-1 Purification Return Line Stop Check Valve G-7 CKC CS CSJ-CVS-1 SV4-CVS-PL-V082 1
N C
A 3
CK SA SV4-CVS-M6-001 O
C/O NA CKOP CS CSJ-CVS-1 Thermal Expansion RCS Purification Return Line Check Valve G-8 CKC CS CSJ-CVS-1
8-5 Southern Nuclear Version 2.0 VOGTLE UNIT 4 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-CVS-PL-V084 1
N B
A 2
GL AO SV4-CVS-M6-001 C
C C
PI 2y F-7 STC RO ROJ-CVS-1 Auxiliary Pressurizer Spray Line Isolation Valve FST RO ROJ-CVS-1 SV4-CVS-PL-V085 1
N C
A 2
CK SA SV4-CVS-M6-001 C
C/O NA CKC RO ROJ-CVS-1 Auxiliary Pressurizer Spray Line Check Valve F-8 CKOP RO ROJ-CVS-1 Thermal Expansion SV4-CVS-PL-V090 2
N A
A 3
GA MO SV4-CVS-M6-005 O
C AI PI 2RO/3y C-2 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y C-4 STC/III-3600 2y III-3300 2RO/3y 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
FST Q
Zinc Injection Containment Isolation Valve ORC LT App.J SV4-CVS-PL-V094 2
N A
A 1
GL AO SV4-CVS-M6-003 O
C C
FST Q
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
O/C NA RVT 10y Thermal Relief Zinc Injection Ctmt Isol Thermal Relief Valve F-6 LT App.J SV4-CVS-PL-V100 2
N AC A
1 CK SA SV4-CVS-M6-005 C
C/O NA CKC CS CSJ-CVS-2 B-4 CKOP CS CSJ-CVS-2 Thermal Expansion Makeup Line Containment Isolation Relief LT App.J SV4-CVS-PL-V136A 3
N B
A 3
C C
Demineralized Water System Isolation Valve FST Q
SV4-CVS-PL-V136B 3
N B
A 3
C C
Demineralized Water System Isolation Valve FST Q
SV4-CVS-PL-V217 2
N AC A
1/2 CK SA SV4-CVS-M6-003 O
C/O NA CKC Q
D-7 CKOP Q
Thermal Expansion Hydrogen Injection Containment Isolation Check Valve IRC LT App.J
8-6 Southern Nuclear Version 2.0 VOGTLE UNIT 4 CVS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-CVS-PL-V219 2
N A
A 1/2 GL AO SV4-CVS-M6-003 O
C C
FST Q
Zinc Injection Containment Isolation Valve IRC LT App.J
8-7 Southern Nuclear Version 2.0 VOGTLE UNIT 4 DWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-DWS-PL-V241 3
N C
A 1
RV SA SV4-DWS-M6-007 C
O NA RVT 10y Thermal Relief Demin Water Supply to Containment Relief E-5 SV4-DWS-PL-V244 2
N A
P 3
AI LT App.J Demin Water Supply Containment Isolation Valve - Outside E-6 SV4-DWS-PL-V245 2
N AC A
2 CK SA SV4-DWS-M6-007 C
C/O NA CKC CS CSJ-DWS-1 E-6 CKOP CS CSJ-DWS-1 Thermal Expansion Demin Water Supply Containment Isolation Check Valve - IRC LT App.J
8-8 Southern Nuclear Version 2.0 VOGTLE UNIT 4 FHS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-FHS-PL-V001 3
N B
A 30 GA MA SV4-SFS-M6-012 C
C AI ETM 2y Fuel Transfer Tube Isolation Valve F-6
8-9 Southern Nuclear Version 2.0 VOGTLE UNIT 4 FPS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-FPS-PL-V050 2
N A
P 6
AI LT App.J Fire Water Containment Supply Isolation F-4 SV4-FPS-PL-V052 2
N AC A
6 CK SA SV4-FPS-M6-004 C
C/O NA CKC CS CSJ-FPS-1 F-5 CKOP CS CSJ-FPS-1 Thermal Expansion Fire Water Supply Ctmt 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 10y Thermal Relief Fire Water Supply IC Thermal Relief F/G-5
8-10 Southern Nuclear Version 2.0 VOGTLE UNIT 4 MSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-MSS-PL-V001 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V002 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V003 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V004 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V005 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V006 N
Y B
A 16 GL AO SV4-MSS-M6-001 C
C C
STC CS CSJ-MSS-2 Note 7 Turbine Bypass Control Valve FST Q
SV4-MSS-PL-V015A N Y
B A
10 GL AO SV4-MSS-M6-001 O
C C
PI 2y B-6 STC CS CSJ-MSS-1 MSR 2nd Stage Reheat Steam AO Isolation Valve FST CS CSJ-MSS-1 SV4-MSS-PL-V015B N
Y B
A 10 GL AO SV4-MSS-M6-001 O
C C
PI 2y G-6 STC CS CSJ-MSS-1 MSR 2nd Stage Reheat Steam AO Isolation Valve FST CS CSJ-MSS-1
8-11 Southern Nuclear Version 2.0 VOGTLE UNIT 4 MTS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-MTS-PL-V001A N Y
B A
28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 F-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #1 FST Q
SV4-MTS-PL-V001B N
Y B
A 28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 C-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #3 FST Q
SV4-MTS-PL-V002A N Y
B A
28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 F-6 STC Q
STC CS CSJ-MTS-1 Control Valve #1 FST Q
SV4-MTS-PL-V002B N
Y B
A 28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 C-6 STC Q
STC CS CSJ-MTS-1 Control Valve #3 FST Q
SV4-MTS-PL-V003A N Y
B A
28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 E-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #2 FST Q
SV4-MTS-PL-V003B N
Y B
A 28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 D-6 STC Q
STC CS CSJ-MTS-1 Main Stop Valve #4 FST Q
SV4-MTS-PL-V004A N Y
B A
28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 E-6 STC Q
STC CS CSJ-MTS-1 Control Valve #2 FST Q
SV4-MTS-PL-V004B N
Y B
A 28 GL EH SV4-MTS-M6-002 O
C C*
PI 2y
- Note 8 D-6 STC Q
STC CS CSJ-MTS-1 Control Valve #4 FST Q
8-12 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PCS-PL-V001A 3
N B
A 6
O O
PI 2y E-4 STO Q
PCS Actuation Valve A FST Q
SV4-PCS-PL-V001B 3
N B
A 6
O O
PI 2y E-6 STO Q
PCS Actuation Valve B FST Q
SV4-PCS-PL-V001C 3
N B
A 6
GA MO SV4-PCS-M6-001 C
O AI PI 2RO/3y E-5 STO/III-3600 Q PCS Actuation Valve C III-3300 2RO/3y SV4-PCS-PL-V002A 3
N B
A 6
GA MO SV4-PCS-M6-001 O
O AI PI 2RO/3y E-4 STO/III-3600 2y PCS Isolation Valve A III-3300 2RO/3y SV4-PCS-PL-V002B 3
N B
A 6
GA MO SV4-PCS-M6-001 O
O AI PI 2RO/3y E-6 STO/III-3600 2y PCS Isolation Valve B III-3300 2RO/3y SV4-PCS-PL-V002C 3
N B
A 6
GA MO SV4-PCS-M6-001 O
O AI PI 2RO/3y E-5 STO/III-3600 2y PCS Isolation Valve C III-3300 2RO/3y SV4-PCS-PL-V005 3
N B
A 4
GA MA SV4-PCS-M6-002 O
C AI ETM 2y PCS to DWS/FPS Iso Valve G-5 SV4-PCS-PL-V009 3
N B
A 3
GA MA SV4-PCS-M6-001 C
O/C AI ETM 2y 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 2y 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 2y PCS Long Term Supply to Distribution Bucket Iso Valve E-4 SV4-PCS-PL-V023 3
N B
A 4
GA MA SV4-PCS-M6-002 O
C AI ETM 2y 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
C/O NA CKC App. II PCS/SFS Long Term Make-up Supply Check Valve F-4 CKO App. II SV4-PCS-PL-V042 3
N B
A 1
GL MA SV4-PCS-M6-002 C
C AI ETM 2y 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 2y
- One turn from full open PCS Long Term Supply from Temp Pump Iso Valve F-4
8-13 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PCS-PL-V045 3
N B
A 2
GL MA SV4-PCS-M6-001 C
O AI ETM 2y 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 2y 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 2y PCCWST Drain Isolation Valve C-2 SV4-PCS-PL-V050 3
N B
A 2
GL MA SV4-PCS-M6-002 C
C/O AI ETM 2y 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 2y Spent Fuel Pool Emergency Makeup Lower Isolation Valve B-2
8-14 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PSS-PL-V001A 2
N C
A 1/4 GL SO SV4-PSS-M6-003 O
O C
RVT 10y Thermal Relief Hot Leg 1 Sample Isolation E-8 SV4-PSS-PL-V001B 2
N C
A 1/4 GL SO SV4-PSS-M6-003 C
O C
RVT 10y Thermal Relief Hot Leg 2 Sample Isolation D-8 SV4-PSS-PL-V003 2
N C
A 1/4 GL SO SV4-PSS-M6-003 C
O C
RVT 10y Thermal Relief Pzr Sample Isolation G-8 SV4-PSS-PL-V008 2
N A
A 5/8 GL SO SV4-PSS-M6-001 O
C C
FST Q
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 C
FST Q
LT App.J Liquid Sample Line Containment Isolation Valve A IRC RVT 10y Thermal Relief SV4-PSS-PL-V010B 2
N AC A
1/4 GL SO SV4-PSS-M6-001 C
C C
FST Q
LT App.J Liquid Sample Line Containment Isolation Valve B IRC RVT 10y Thermal Relief SV4-PSS-PL-V011A 2
N A
A 1/4 GL AO SV4-PSS-M6-001 O
C C
FST Q
Liquid Sample Line Containment Isolation Valve A ORC LT App.J SV4-PSS-PL-V011B 2
N A
A 1/4 GL AO SV4-PSS-M6-001 C
C C
FST Q
Liquid Sample Line Containment Isolation Valve B ORC LT App.J SV4-PSS-PL-V023 2
N A
A 1
GL AO SV4-PSS-M6-001 O
C C
FST Q
Ctmt Air Sample Return Isolation Valve LT App.J
8-15 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PSS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PSS-PL-V024 2
N A
A 1
GL SO SV4-PSS-M6-001 O
C C
FST Q
Ctmt Liquid and Air Sample Return IRC Isol Valve LT App.J SV4-PSS-PL-V046 2
N A
A 5/8 GL AO SV4-PSS-M6-001 O
C C
FST Q
Air Sample Line Ctmt Isol ORC Valve LT App.J
8-16 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PWS-PL-V418 3
N B
A 1
GL MA SV4-PCS-M6-002 O
C AI ETM 2y Control Room Boundary Outside Isolation Valve G-4 SV4-PWS-PL-V420 3
N B
A 1
GL MA SV4-PCS-M6-002 O
C AI ETM 2y Control Room Boundary Inside Isolation Valve F-4 SV4-PWS-PL-V498 3
N C
A 1
O NA VB 2y Vacuum Breaker Ctmt Return CIV Thermal Relief F-4
8-17 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PXS-PL-V002A 1
N B
P 8
GA MO SV4-PXS-M6-001 O
O AI PI 2y 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 2y 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 2y CMT A Discharge Manual Isol Valve D/E-6 SV4-PXS-PL-V013B 1
N B
P 8
GA MA SV4-PXS-M6-001 LO O
AI PI 2y CMT B Discharge Manual Isol Valve D/E-3 SV4-PXS-PL-V014A 1
N B
A 8
GL AO SV4-PXS-M6-001 C
O O
PI 2y E-7 STO Q
CMT A Outlet Valve FST Q
SV4-PXS-PL-V014B 1
N B
A 8
GL AO SV4-PXS-M6-001 C
O O
PI 2y E-3 STO Q
CMT B Outlet Valve FST Q
SV4-PXS-PL-V015A 1
N B
A 8
GL AO SV4-PXS-M6-001 C
O O
PI 2y D-7 STO Q
CMT A Outlet Valve FST Q
SV4-PXS-PL-V015B 1
N B
A 8
GL AO SV4-PXS-M6-001 C
O O
PI 2y D-3 STO Q
CMT B Outlet Valve FST Q
SV4-PXS-PL-V016A 1
N C
A 8
CK SA SV4-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT A Outlet Check Valve D/E-6 CKC RO ROJ-PXS-1 SV4-PXS-PL-V016B 1
N C
A 8
CK SA SV4-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT B Outlet Check Valve D/E-3 CKC RO ROJ-PXS-1 SV4-PXS-PL-V017A 1
N C
A 8
CK SA SV4-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT A Outlet Check Valve D/E-6 CKC RO ROJ-PXS-1 SV4-PXS-PL-V017B 1
N C
A 8
CK SA SV4-PXS-M6-001 O
O/C NA CKO RO ROJ-PXS-1 CMT B Outlet Check Valve D/E-3 CKC RO ROJ-PXS-1 SV4-PXS-PL-V021A 3
N B
P 1
GL SO SV4-PXS-M6-001 C
C C
PI 2y Accumulator A Nitrogen Supply Valve C-7 SV4-PXS-PL-V021B 3
N B
P 1
GL SO SV4-PXS-M6-001 C
C C
PI 2y 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 RVT 4y/10y Accumulator A Relief Valve C-7
8-18 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PXS-PL-V022B 3
N C
A 1
RV SA SV4-PXS-M6-001 C
O/C NA RVT 4y/10y Accumulator B Relief Valve C-2 SV4-PXS-PL-V027A 3
N B
P 8
GA MO SV4-PXS-M6-001 O
O AI PI 2y 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 2y 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 CKC RO ROJ-PXS-2 B-6 CKO RO ROJ-PXS-2 Accumulator A Outlet to RCS Check LT 2y PIV SV4-PXS-PL-V028B 1
N AC A
8 CK SA SV4-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-3 CKO RO ROJ-PXS-2 Accumulator B Outlet to RCS Check LT 2y PIV SV4-PXS-PL-V029A 1
N AC A
8 CK SA SV4-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-6 CKO RO ROJ-PXS-2 Accumulator A Outlet to RCS Check LT 2y PIV SV4-PXS-PL-V029B 1
N AC A
8 CK SA SV4-PXS-M6-001 C
O/C NA CKC RO ROJ-PXS-2 B-4 CKO RO ROJ-PXS-2 Accumulator B Outlet to RCS Check LT 2y PIV SV4-PXS-PL-V042 2
N A
A 1
GL AO SV4-PXS-M6-001 O
C C
FST Q
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 CKC Q
D-2 CKOP Q
Thermal Expansion 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 RVT 10y Thermal Relief High Pressure Nitrogen to Containment Penetration Thermal Relief Valve D-2 SV4-PXS-PL-V101 1
N B
P 14 GA MO SV4-PXS-M6-002 O
O AI PI 2y RCS to PRHR Heat Exchanger Isolation Valve G-1 SV4-PXS-PL-V108A 1
N B
A 14 BA AO SV4-PXS-M6-002 C
O O
PI 2y G-1 STO CS CSJ-PXS-1 PRHR Heat Exchanger Outlet Valve to RCS A FST CS CSJ-PXS-1 SV4-PXS-PL-V108B 1
N B
A 14 BA AO SV4-PXS-M6-002 C
O O
PI 2y F-1 STO CS CSJ-PXS-1 PRHR Heat Exchanger Outlet Valve to RCS B FST CS CSJ-PXS-1
8-19 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PXS-PL-V109 1
N B
P 14 GA MA SV4-PXS-M6-001 LO O
AI PI 2y RCS to PRHR Heat Exchanger Isolation Valve F-1 SV4-PXS-PL-V117A 3
N B
P 8
GA MO SV4-PXS-M6-002 O
O AI PI 2y Containment Recirculation 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 2y Containment Recirculation B to RCS Isolation Valve E-5 SV4-PXS-PL-V118A 3
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y E-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump A to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V118B 3
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y E-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump B to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V119A 3
N C
A 8
CK NA SV4-PXS-M6-002 C
O/C NA PI 2y E-7 CKC RO ROJ-PXS-3 Containment Recirc. Sump A Outlet to RCS Check CKO RO ROJ-PXS-3 SV4-PXS-PL-V119B 3
N C
A 8
CK NA SV4-PXS-M6-002 C
O/C NA PI 2y E-5 CKC RO ROJ-PXS-3 Containment Recirc. Sump A Outlet to RCS Check CKO RO ROJ-PXS-3 SV4-PXS-PL-V120A 3
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y E-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump A to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V120B 3
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y E-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge Containment Recirc.Sump B to RCS Actuation Squib Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V121A 3
N B
P 8
GA MO SV4-PXS-M6-002 O
O AI PI 2y 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 2y IRWST/Recirc. Sump to RCS B Isolation Valve D-7 SV4-PXS-PL-V122A 1
N C
A 8
CK SA SV4-PXS-M6-002 C
O/C NA PI 2y C-7 CKC RO*
- Note 6 IRWST Injection Line A Check Valve CKO RO*
8-20 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PXS-PL-V122B 1
N C
A 8
CK SA SV4-PXS-M6-002 C
O/C NA PI 2y C-5 CKC RO*
- Note 6 IRWST Injection Line B Check Valve CKO RO*
SV4-PXS-PL-V123A 1
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y C-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection A Isolation Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V123B 1
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y C-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection B Isolation Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V124A 1
N C
A 8
CK NA SV4-PXS-M6-002 C
O/C NA PI 2y C-7 CKC RO*
- Note 6 IRWST Injection Line A Check Valve CKO RO*
SV4-PXS-PL-V124B 1
N C
A 8
CK NA SV4-PXS-M6-002 C
O/C NA PI 2y C-5 CKC RO*
- Note 6 IRWST Injection Line B Check Valve CKO RO*
SV4-PXS-PL-V125A 1
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y C-7 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection A Isolation Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V125B 1
N D
A 8
SQ SQ SV4-PXS-M6-002 C
O AI Remote Insp 2y C-5 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge IRWST Injection B Isolation Valve Disass. Insp 10y Note 3 SV4-PXS-PL-V130A 3
N B
A 2
BA AO SV4-PXS-M6-002 O
C C
IRWST Gutter Isolation A Valve FST Q
SV4-PXS-PL-V130B 3
N B
A 2
BA AO SV4-PXS-M6-002 O
C C
IRWST Gutter Isolation B Valve FST Q
SV4-PXS-PL-V208A 2
N A
P 3/8 GL MA SV4-PXS-M6-003 LC C
AI 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 2y Core Makeup Tank A Fill Isolation F-6
8-21 Southern Nuclear Version 2.0 VOGTLE UNIT 4 PXS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-PXS-PL-V230B 2
N B
P 1
GL AO SV4-PXS-M6-003 C
C C
PI 2y Core Makeup Tank B Fill Isolation G-6 SV4-PXS-PL-V231A 2
N C
A 1
CK SA SV4-PXS-M6-003 C
O NA CKOP CS CSJ-PXS-3 Thermal expansion CMT A Fill Check Valve F-7 CKC CS CSJ-PXS-3 SV4-PXS-PL-V231B 2
N C
A 1
CK SA SV4-PXS-M6-003 C
O NA CKOP CS CSJ-PXS-3 Thermal expansion CMT B Fill Check Valve G-7 CKC CS CSJ-PXS-3 SV4-PXS-PL-V232A 2
N B
P 1
GL AO SV4-PXS-M6-003 C
C C
PI 2y Accumulator A Fill/Drain Isolation E-6 SV4-PXS-PL-V232B 2
N B
P 1
GL AO SV4-PXS-M6-003 C
C C
PI 2y Accumulator B Fill/Drain Isolation G-6
8-22 Southern Nuclear Version 2.0 VOGTLE UNIT 4 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-RCS-PL-V001A 1
N B
A 4
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Control Valve III-3300 2RO/3y SV4-RCS-PL-V001B 1
N B
A 4
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Control Valve III-3300 2RO/3y SV4-RCS-PL-V002A 1
N B
A 8
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Control Valve III-3300 2RO/3y SV4-RCS-PL-V002B 1
N B
A 8
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Control Valve III-3300 2RO/3y SV4-RCS-PL-V003A 1
N B
A 8
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y H-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Control Valve III-3300 2RO/3y SV4-RCS-PL-V003B 1
N B
A 8
GL MO SV4-RCS-M6-002 C
O AI PI 2RO/3y F-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Control Valve III-3300 2RO/3y SV4-RCS-PL-V004A 1
N D
A 14 SQ SQ SV4-RCS-M6-001 C
O AI Remote Insp 2y G-6 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV4-RCS-PL-V004B 1
N D
A 14 SQ SQ SV4-RCS-M6-001 C
O AI Remote Insp 2y F-3 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV4-RCS-PL-V004C 1
N D
A 14 SQ SQ SV4-RCS-M6-001 C
O AI Remote Insp 2y F-6 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3 SV4-RCS-PL-V004D 1
N D
A 14 SQ SQ SV4-RCS-M6-001 C
O AI Remote Insp 2y F-3 Charge 2y/10y Note 2 Circuit 2y/10y Tested when testing charge ADS Stage 4 Valve Disass. Insp 10y Note 3
8-23 Southern Nuclear Version 2.0 VOGTLE UNIT 4 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-RCS-PL-V005A 1
N C
A 6
RV SA SV4-RCS-M6-002 C
O/C NA RVT 2y/5y Includes PI Pressurizer Safety Valve H-7 SV4-RCS-PL-V005B 1
N C
A 6
RV SA SV4-RCS-M6-002 C
O/C NA RVT 2y/5y Includes PI Pressurizer Safety Valve F-6 SV4-RCS-PL-V010A 3
N C
A 1
O NA VB 2y ADS Header Vacuum Breaker G-4 SV4-RCS-PL-V010B 3
N C
A 1
O NA VB 2y ADS Header Vacuum Breaker E-4 SV4-RCS-PL-V011A 1
N B
A 4
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V011B 1
N B
A 4
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 1 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V012A 1
N B
A 8
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V012B 1
N B
A 8
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y E-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 2 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V013A 1
N B
A 8
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y G-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V013B 1
N B
A 8
GA MO SV4-RCS-M6-002 C
O AI PI 2RO/3y F-5 STO/III-3600 CS CSJ-RCS-1 ADS Stage 3 Isolation Valve III-3300 2RO/3y SV4-RCS-PL-V014A 1
N B
P 14 GA MO SV4-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve G-6 SV4-RCS-PL-V014B 1
N B
P 14 GA MO SV4-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-3 SV4-RCS-PL-V014C 1
N B
P 14 GA MO SV4-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-6 SV4-RCS-PL-V014D 1
N B
P 14 GA MO SV4-RCS-M6-001 O
O AI PI 2y ADS Stage 4 Isolation Valve F-3
8-24 Southern Nuclear Version 2.0 VOGTLE UNIT 4 RCS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-RCS-PL-V150A 1
N BC A
1 GL SO SV4-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 FST CS CSJ-RCS-2 Reactor Head Vent Valve RVT 10y Thermal relief SV4-RCS-PL-V150B 1
N BC A
1 GL SO SV4-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 FST CS CSJ-RCS-2 Reactor Head Vent Valve RVT 10y Thermal relief SV4-RCS-PL-V150C 1
N B
A 1
GL SO SV4-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 Reactor Head Vent Valve FST CS CSJ-RCS-2 SV4-RCS-PL-V150D 1
N B
A 1
GL SO SV4-RCS-M6-001 C
O/C C
PI 2y D-4 STO CS CSJ-RCS-2 STC CS CSJ-RCS-2 Reactor Head Vent Valve FST CS CSJ-RCS-2 SV4-RCS-PL-V233 3
N B
P 2
GL MA SV4-RCS-M6-002 LO O
AI PI 2y 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 RRD 5y Safety Valve Discharge Chamber Rupture Disk H-8 SV4-RCS-PY-K04 3
N D
A 10 RD SA SV4-RCS-M6-002 C
O NA RRD 5y Safety Valve Discharge Chamber Rupture Disk F-7
8-25 Southern Nuclear Version 2.0 VOGTLE UNIT 4 RNS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-RNS-PL-V001A 1
N A
A 10 GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y F-2 STC/III-3600 2y III-3300 2RO/3y RNS Suction from RCS Inner Isolation Valve LT 2y PIV SV4-RNS-PL-V001B 1
N A
A 10 GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y D-2 STC/III-3600 2y III-3300 2RO/3y RNS Suction from RCS Inner Isolation Valve LT 2y PIV SV4-RNS-PL-V002A 1
N A
A 10 GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y F-2 STC/III-3600 2y III-3300 2RO/3y LT 2y PIV RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT AppJ SV4-RNS-PL-V002B 1
N A
A 10 GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y D-2 STC/III-3600 2y III-3300 2RO/3y LT 2y PIV RNS Suction from RCS Outer Isolation /IC Containment Isolation Valve LT AppJ SV4-RNS-PL-V003A 1
N C
A 1
CK SA SV4-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 RNS PIV Thermal Relief Valve G-2 CKOP CS CSJ-RNS-1 Thermal Expansion SV4-RNS-PL-V003B 1
N C
A 1
CK SA SV4-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 RNS PIV Thermal Relief Valve D-2 CKOP CS CSJ-RNS-1 Thermal Expansion SV4-RNS-PL-V011 2
N A
A 8
GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y F-7 STC/III-3600 2y III-3300 2RO/3y RNS Discharge Header to Containment OC Containment Isolation Valve LT AppJ SV4-RNS-PL-V012 2
N A
A 1
GL MA SV4-RNS-M6-001 LC C/O AI ETM 2y 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 NA CKC CS CSJ-RNS-1 F-7 CKO CS CSJ-RNS-1 Thermal Expansion 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
- Note 4 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Stop Check Valve LT 2y PIV
8-26 Southern Nuclear Version 2.0 VOGTLE UNIT 4 RNS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-RNS-PL-V015B 1
N AC A
6 CK*
SA*
SV4-RNS-M6-001 C
- Note 4 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Stop Check Valve LT 2y PIV SV4-RNS-PL-V017A 1
N AC A
6 CK SA SV4-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Check Valve LT 2y PIV SV4-RNS-PL-V017B 1
N AC A
6 CK SA SV4-RNS-M6-001 C
C/O NA CKC CS CSJ-RNS-1 F-8 CKO CS CSJ-RNS-1 Thermal Expansion RNS to DVI Check Valve LT 2y PIV SV4-RNS-PL-V020 2
N AC A
1 RV SA SV4-RNS-M6-001 C
O/C NA RVT 4y/10y RNS Suction Relief Valve G-2 LT App.J SV4-RNS-PL-V021 2
N AC A
3 RV SA SV4-RNS-M6-001 C
O/C NA RVT 4y/10y RNS Suction Relief Valve G-2 LT App.J SV4-RNS-PL-V022 2
N A
A 10 GA MO SV4-RNS-M6-001 C
C AI PI 2RO/3y F-3 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y E-3 STC/III-3600 2y III-3300 2RO/3y RNS Suction from IRWST/IC Containment Isolation Valve LT App J SV4-RNS-PL-V061 2
N A
A 3
GL AO SV4-RNS-M6-001 C
C C
FST Q
CVS Return to RNS Suction/IC Containment Isolation Valve LT App.J
8-27 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SDS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SDS-PL-V001 3
N B
A 3
BU MO SV4-SDS-M6-001 O
C AI PI 2RO/3y E-5 STC/III-3600 2y MCR SDS (Vent) Isolation Valve III-3300 2RO/3y SV4-SDS-PL-V002 3
N B
A 3
BU MO SV4-SDS-M6-001 O
C AI PI 2RO/3y E-5 STC/III-3600 2y MCR SDS (Vent) Isolation Valve III-3300 2RO/3y
8-28 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SFS-PL-V031 3
N B
P 6
AI PI 2y 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 2y 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 2RO/3y D-6 STC/III-3600 2y III-3300 2RO/3y 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 2RO/3y D-5 STC/III-3600 2y III-3300 2RO/3y 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 CS CSJ-SFS-1 B-6 CKOP CS CSJ-SFS-1 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 2RO/3y D-5 STC/III-3600 2y III-3300 2RO/3y SFS to Refueling Cavity/IRWST OC Containment Iso Valve LT App.J SV4-SFS-PL-V041 3
N B
A 6
AI ETM 2y SFS Cask Loading Pit Suction Isolation Valve F-1 SV4-SFS-PL-V042 3
Y B
P 6
AI ETM 2y SFS Cask Loading Pit to Pumps Suction Isolation Valve E-3/4 SV4-SFS-PL-V045 3
Y B
P 4
AI ETM 2y 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 2y SFS Cask Loading Pit Drain to WLS Isolation Valve E-2 SV4-SFS-PL-V066 3
N B
A 8
BA MA SV4-SFS-M6-001 LC O/C AI ETM 2y Spent Fuel Pool Boiloff Makeup Isolation Valve G-3 SV4-SFS-PL-V067 2
N AC A
1 RV SA SV4-SFS-M6-001 C
O/C NA RVT 10y Thermal Relief Refueling Cavity/IRWST to SFS Penetration Relief Valve E-6 LT App.J SV4-SFS-PL-V068 3
N B
A 6
AI ETM 2y 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 CKC RO*
- Note 5 Refueling Cavity Side Drain to S/G 2 Compartment Valve F-7 CKO RO*
8-29 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SFS-PL-V072 3
N C
A 6
CK SA SV4-SFS-M6-001 C
O/C NA CKC RO*
- Note 5 Refueling Cavity Side Drain to S/G 2 Compartment Valve F-7/8 CKO RO*
SV4-SFS-PL-V075 3
N B
P 20 BU MA SV4-SFS-M6-001 LO O
AI PI 2y SFS Reactor Cavity Post-Accident Containment Flood-up Valve G-7
8-30 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SGS-PL-V027A 2
N B
A 12 GL MO SV4-SGS-M6-001 O
C AI PI 2RO/3y G-4/5 STC/III-3600 2y SG1 PORV Isolation Valve III-3300 2RO/3y SV4-SGS-PL-V027B 2
N B
A 12 GL MO SV4-SGS-M6-002 O
C AI PI 2RO/3y G-5 STC/III-3600 2y SG2 PORV Isolation Valve III-3300 2RO/3y SV4-SGS-PL-V030A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-4 SV4-SGS-PL-V030B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-4 SV4-SGS-PL-V031A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV4-SGS-PL-V031B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV4-SGS-PL-V032A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV4-SGS-PL-V032B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV4-SGS-PL-V033A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-3 SV4-SGS-PL-V033B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-3 SV4-SGS-PL-V034A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-2 SV4-SGS-PL-V034B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-2 SV4-SGS-PL-V035A 2
N C
A 8
RV SA SV4-SGS-M6-001 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 01 G-2 SV4-SGS-PL-V035B 2
N C
A 8
RV SA SV4-SGS-M6-002 C
O/C NA RVT 2y/5y Includes PI Main Steam Safety Valve Steam Generator 02 G-2 SV4-SGS-PL-V036A 2
N B
A 2
GL AO SV4-SGS-M6-001 O
C C
Steam Line Condensate Drain Isolation FST Q
8-31 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SGS-PL-V036B 2
N B
A 2
GL AO SV4-SGS-M6-002 O
C C
Steam Line Condensate Drain Isolation FST Q
SV4-SGS-PL-V040A 2
N B
A 38 GA PH SV4-SGS-M6-001 O
C C*
PI 2y
N B
A 38 GA PH SV4-SGS-M6-002 O
C C*
PI 2y
N B
A 20 GA PH SV4-SGS-M6-001 O
C C*
PI 2y
- Note 9 E-4 STC CS CSJ-SGS-1 Note 7 Main Feedwater Line Isolation FST CS CSJ-SGS-1 SV4-SGS-PL-V057B 2
N B
A 20 GA PH SV4-SGS-M6-002 O
C C*
PI 2y
- Note 9 E-4 STC CS CSJ-SGS-1 Note 7 Main Feedwater Line Isolation FST CS CSJ-SGS-1 SV4-SGS-PL-V058A 2
N C
A 20 CK SA SV4-SGS-M6-001 O
C/O NA CKC CS CSJ-SGS-2 SG 1 Main Feed Check Valve E-5 CKOP CS CSJ-SGS-2 Thermal Expansion SV4-SGS-PL-V058B 2
N C
A 20 CK SA SV4-SGS-M6-002 O
C/O NA CKC CS CSJ-SGS-2 SG 2 Main Feed Check Valve E-5 CKOP CS CSJ-SGS-2 Thermal Expansion SV4-SGS-PL-V067A 2
N B
A 6
GA MO SV4-SGS-M6-001 O
C AI PI 2RO/3y D-5 STC/III-3600 2y Startup Feedwater Isolation III-3300 2RO/3y SV4-SGS-PL-V067B 2
N B
A 6
GA MO SV4-SGS-M6-002 O
C AI PI 2RO/3y D-5 STC/III-3600 2y Startup Feedwater Isolation III-3300 2RO/3y SV4-SGS-PL-V074A 2
N B
A 4
GL AO SV4-SGS-M6-001 O
C C
SG 1 Blowdown Isolation Valve FST Q
SV4-SGS-PL-V074B 2
N B
A 4
GL AO SV4-SGS-M6-002 O
C C
SG 2 Blowdown Isolation Valve FST Q
SV4-SGS-PL-V075A 3
N B
A 4
GL AO SV4-SGS-M6-001 O
C C
SG 1 Blowdown Isolation Valve FST Q
8-32 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SGS-PL-V075B 3
N B
A 4
GL AO SV4-SGS-M6-002 O
C C
SG 2 Blowdown Isolation Valve FST Q
SV4-SGS-PL-V086A 3
N B
A 2
GL AO SV4-SGS-M6-001 C
C C
SG 1 Steam Line Drain Level Control FST Q
SV4-SGS-PL-V086B 3
N B
A 2
GL AO SV4-SGS-M6-002 C
C C
SG 2 Steam Line Drain Level Control FST Q
SV4-SGS-PL-V233A 3
N B
A 12 GL AO SV4-SGS-M6-001 C
C C
PI 2y H-4/5 STC RO Per ISTC-3510 FST RO Per ISTC-3510 SG1 Steam Line Power Operated Relief Valve LT 2y Per I-8200 SV4-SGS-PL-V233B 3
N B
A 12 GL AO SV4-SGS-M6-002 C
C C
PI 2y H-5 STC RO Per ISTC-3510 FST RO Per ISTC-3510 SG2 Steam Line Power Operated Relief Valve LT 2y Per I-8200 SV4-SGS-PL-V240A 2
N B
A 3
GL AO SV4-SGS-M6-001 C
C C
SV4-SGS-PL-V240B 2
N B
A 3
GL AO SV4-SGS-M6-002 C
C C
SV4-SGS-PL-V250A 3
N B
A 20 GL AO SV4-SGS-M6-001 O
C C
PI 2y E-2/3 STC CS CSJ-SGS-1 Main Feedwater Control Valve FST CS CSJ-SGS-1 SV4-SGS-PL-V250B 3
N B
A 20 GL AO SV4-SGS-M6-002 O
C C
PI 2y E-2/3 STC CS CSJ-SGS-1 Main Feedwater Control Valve FST CS CSJ-SGS-1 SV4-SGS-PL-V255A 3
N B
A 6
GL AO SV4-SGS-M6-001 C
C C
Startup Feedwater Control Valve FST Q
SV4-SGS-PL-V255B 3
N B
A 6
GL AO SV4-SGS-M6-002 C
C C
Startup Feedwater Control Valve FST Q
8-33 Southern Nuclear Version 2.0 VOGTLE UNIT 4 SGS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-SGS-PL-V256A 3
N C
A 6
CK SA SV4-SGS-M6-001 C
O NA CKC CS CSJ-SGS-3 SG 1 Startup Feed Check Valve D-4 CKOP CS Thermal Expansion SV4-SGS-PL-V256B 3
N C
A 6
CK SA SV4-SGS-M6-002 C
O NA CKC CS CSJ-SGS-3 SG 2 Startup Feed Check Valve D-4 CKOP CS Thermal Expansion SV4-SGS-PL-V257A 3
N C
A 1
RV SA SV4-SGS-M6-001 C
O NA RVT 10y Thermal Relief Main Feedwater Thermal Relief E-4 SV4-SGS-PL-V257B 3
N C
A 1
RV SA SV4-SGS-M6-002 C
O NA RVT 10y Thermal Relief Main Feedwater Thermal Relief E-4 SV4-SGS-PL-V258A 3
N C
A 1
RV SA SV4-SGS-M6-001 C
O NA RVT 10y Thermal Relief Startup Feedwater Thermal Relief D-4 SV4-SGS-PL-V258B 3
N C
A 1
RV SA SV4-SGS-M6-002 C
O NA RVT 10y Thermal Relief Startup Feedwater Thermal Relief D-4
8-34 Southern Nuclear Version 2.0 VOGTLE UNIT 4 VBS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-VBS-PL-V186 3
N B
A 28 BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y F-6 STC/III-3600 2y MCR Supply Air Isolation Valve III-3300 2RO/3y SV4-VBS-PL-V187 3
N B
A 28 BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y F-6 STC/III-3600 2y MCR Supply Air Isolation Valve III-3300 2RO/3y SV4-VBS-PL-V188 3
N B
A 28 BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y C-7 STC/III-3600 2y MCR Return Air Isolation Valve III-3300 2RO/3y SV4-VBS-PL-V189 3
N B
A 28 BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y C-6 STC/III-3600 2y MCR Return Air Isolation Valve III-3300 2RO/3y SV4-VBS-PL-V190 3
N B
A 6
BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y C-3 STC/III-3600 2y MCR Toilet Exhaust Isolation Valve III-3300 2RO/3y SV4-VBS-PL-V191 3
N B
A 6
BU MO SV4-VBS-M6-007 O
C AI PI 2RO/3y C-3 STC/III-3600 2y MCR Toilet Exhaust Isolation Valve III-3300 2RO/3y
8-35 Southern Nuclear Version 2.0 VOGTLE UNIT 4 VES Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-VES-PL-V001 3
N B
A 1
GL MA SV4-VES-M6-002 C
O/C AI ETM 2y 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 2y F-5 STO Q
Air Delivery Isolation Valve A FST Q
SV4-VES-PL-V005B 3
N B
A 1
GL SO SV4-VES-M6-002 C
O O
PI 2y E-5 STO Q
Air Delivery Isolation Valve B FST Q
SV4-VES-PL-V018 3
N B
A 1
GL MA SV4-VES-M6-002 C
O/C AI ETM 2y Temporary Insturmentation Isolation Valve F-5 SV3-VES-PL-V019 3
N B
A 1
GL MA SV3-VES-M6-002 C
O/C AI ETM 2y Temporary Insturmentation Isolation Valve E-5 SV4-VES-PL-V022A 3
N B
A 4
O O
PI 2y C-2 STO Q
Pressure Relief Isolation Valve A FST Q
SV4-VES-PL-V022B 3
N B
A 4
O O
PI 2y C-2 STO Q
Pressure Relief Isolation Valve B FST Q
SV4-VES-PL-V040A 3
N C
A 1
RV SA SV4-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve A H-4 SV4-VES-PL-V040B 3
N C
A 1
RV SA SV4-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve B F-4 SV4-VES-PL-V040C 3
N C
A 1
RV SA SV4-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve C D/E-4 SV4-VES-PL-V040D 3
N C
A 1
RV SA SV4-VES-M6-001 C
O/C NA RVT 4y10y Air Tank Safety Relief Valve D C-4 SV4-VES-PL-V044 3
N B
A 1
GL MA SV4-VES-M6-002 LO O/C AI ETM 2y Main Air Flowpath Isolation Valve F-4 SV4-VES-PL-V045 3
N B
A 1
GL MA SV4-VES-M6-002 LO O/C AI ETM 2y Eductor Supply Isolation Valve E-3 SV4-VES-PL-V046 3
N B
A 1
GL MA SV4-VES-M6-002 C
C/O AI ETM 2y Eductor Bypass Isolation Valve D-3
8-36 Southern Nuclear Version 2.0 VOGTLE UNIT 4 VFS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-VFS-PL-V003 2
N A
C C
FST Q
Containment Purge Inlet Containment Isol - ORC LT App.J SV4-VFS-PL-V004 2
N A
C C
FST Q
Containment Purge Inlet Containment Isol - IRC LT App.J SV4-VFS-PL-V009 2
N A
C C
FST Q
Containment Purge Discharge Containment Isol - IRC LT App.J SV4-VFS-PL-V010 2
N A
C C
FST Q
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
C/O AI PI 2RO/3y E-7 STC/III-3600 2y STO/III-3600 2y III-3300 2RO/3y 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
C/O AI PI 2RO/3y E-7 STC/III-3600 2y STO/III-3600 2y III-3300 2RO/3y Containment Vacuum Relief Isolation Valve B - ORC LT App.J SV4-VFS-PL-V803A 2
N AC A
O/C NA VB 2y Containment Vacuum Relief Valve A - IRC E-7 LT App.J SV4-VFS-PL-V803B 2
N AC A
O/C NA VB 2y Containment Vacuum Relief Valve B - IRC E-7 LT App.J
8-37 Southern Nuclear Version 2.0 VOGTLE UNIT 4 VWS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-VWS-PL-V053 3
N C
A 2
RV SA SV4-VWS-M6-003 C
O NA RVT 10y Thermal Relief Ctmt Cooling Unit Supply Hdr Relief B-6 SV4-VWS-PL-V057 3
N C
A 2
RV SA SV4-VWS-M6-003 C
O NA RVT 10y Thermal Relief Ctmt Cooling Unit Return Hdr Relief H-4 SV4-VWS-PL-V058 2
N A
A 8
C C
FST Q
Chilled Water Inlet Containment Isol Valve LT App.J SV4-VWS-PL-V062 2
N AC A
8 CK SA SV4-VWS-M6-003 O
C/O NA CKC CS CSJ-VWS-1 B-6 CKOP CS CSJ-VWS-1 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
O/C NA RVT 10y Thermal Relief Ctmt Cooling Unit Return CIV Relief H-4 LT App.J SV4-VWS-PL-V082 2
N A
A 8
C C
FST Q
Chilled Water Outlet Containment Isolation Valve LT App.J SV4-VWS-PL-V086 2
N A
A 8
C C
FST Q
Chilled Water Outlet Containment Isolation Valve LT App.J
8-38 Southern Nuclear Version 2.0 VOGTLE UNIT 4 WLS Valve ID Valve Valve Act.
Drawing
Position-------------- Required Description Class Aug Cat. A/P Size Type Type & Coord Normal Safety Fail-Safe Test Freq Code Dev.
Plan Notes SV4-WLS-PL-V055 2
N A
A 2
PL AO SV4-WLS-M6-001 C
C C
FST Q
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
FST Q
Containment Sump Discharge CIV - ORC LT App.J SV4-WLS-PL-V058 2
N AC A
1 RV SA SV4-WLS-M6-001 C
O/C NA RVT 10y Thermal Relief Containment Sump Discharge Penetration Thermal Relief C-4 LT App.J SV4-WLS-PL-V067 2
N A
A 1
GL AO SV4-WLS-M6-001 C
C C
FST Q
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
FST Q
RCDT Gas Outlet CIV - ORC LT App.J SV4-WLS-PL-V071A 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 CVS Compt Floor Drain Check C-8 CKO CS CSJ-WLS-1 SV4-WLS-PL-V071B 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt A Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV4-WLS-PL-V071C 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt B Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV4-WLS-PL-V072A 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 CVS Compt Floor Drain Check C-7 CKO CS CSJ-WLS-1 SV4-WLS-PL-V072B 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt A Floor Drain Check G-8 CKO CS CSJ-WLS-1 SV4-WLS-PL-V072C 3
N C
A 4
CK SA SV4-WLS-M6-001 C
C/O NA CKC CS CSJ-WLS-1 PXS Compt B Floor Drain Check G-8 CKO CS CSJ-WLS-1
9-1 Southern Nuclear Version 2.0 9.0 COLD SHUTDOWN TESTING JUSTIFICATIONS
9-2 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-CAS-1 SYSTEM:
Compressed Air (Service)
VALVE(S):
SV3/4-CAS-PL-V205 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve closes to perform containment isolation.
QUARTERLY TEST REQUIREMENT:
Exercise valve, partial open check valve, close check valve.
PARTIAL QUARTERLY STROKE TESTING:
None COLD SHUTDOWN JUSTIFICATION:
This valve is closed during operation due to service air to containment being isolated by the manual valve outside containment being locked closed for Containment Isolation, per Tech. Specs. Check valve cannot be exercised without violating Tech. Specs. by opening manual valve.
9-3 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ -CVS-1 SYSTEM:
Chemical Volume & Control VALVE(S):
SV3/4-CVS-PL-V067, V080, V081 & V082 CATEGORY:
C CLASS:
1, 3(V080)
FUNCTION:
These valves provide the flow path from the CVS demins back to the RCS, and provide RCS pressure boundary isolation by preventing backflow from the RCS to the non-safety related CVS piping.
QUARTERLY TEST REQUIREMENT:
Exercise check valve part open and closed.
COLD SHUTDOWN JUSTIFICATION:
Testing of these valves during normal power operation would require an entry into containment, and interruption of CVS purification flow, and a potential thermal transient on the CVS purification system and piping when placing the system back into service at power.
QUARTERLY PARTIAL STROKE TESTING:
None. No indication of obturator position to verify partial stroking of valves.
CVS purification flow confirms flow through the valves, but not obturator function.
COLD SHUTDOWN TESTING:
Exercise check valve part open and closed.
9-4 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-CVS-2 SYSTEM:
Chemical Volume & Control VALVE(S):
SV3/4-CVS-PL-V064, V100 CATEGORY:
AC CLASS:
2 FUNCTION:
These valves are in the make-up flow path from the CVS make-up pumps to the RCS and provide a path to accommodate thermal expansion of water in the containment penetration. V100 also provides containment pressure boundary isolation by preventing backflow.
QUARTERLY TEST REQUIREMENT:
Exercise check valve part open and closed.
COLD SHUTDOWN JUSTIFICATION:
Testing of these valves during normal power operation would require an entry into containment to isolate of the make-up line, and install and operate a hydro pump.
QUARTERLY PARTIAL STROKE TESTING:
None. No indication of obturator position to verify partial stroking of valve. CVS make-up flow confirms flow through the valves, but not obturator function.
COLD SHUTDOWN TESTING:
Exercise check valve part open and closed.
9-5 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-DWS-1 SYSTEM:
Demineralized Water VALVE(S):
SV3/4-DWS-PL-V245 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve closes to perform containment isolation.
QUARTERLY TEST REQUIREMENT:
Exercise valve, partial open check valve, close check valve.
PARTIAL QUARTERLY STROKE TESTING:
None COLD SHUTDOWN JUSTIFICATION:
This valve is closed during operation due to demineralized water to containment being isolated by the manual valve outside containment being locked closed for Containment Isolation, per Tech. Specs. Check valve cannot be exercised without violating Tech. Specs. by opening manual valve.
9-6 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-FPS-1 SYSTEM:
Fire Protection VALVE(S):
SV3/4-FPS-PL-V052 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve closes to perform containment isolation.
QUARTERLY TEST REQUIREMENT:
Exercise valve, partial open check valve, close check valve.
PARTIAL QUARTERLY STROKE TESTING:
None COLD SHUTDOWN JUSTIFICATION:
This valve is closed during operation due to fire water to containment being isolated by the manual valve outside containment being locked closed for Containment Isolation, per Tech. Specs. Check valve cannot be exercised without violating Tech. Specs. by opening manual valve.
9-7 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-MSS-1 SYSTEM:
Main Steam VALVE(S):
SV3/4-MSS-PL-V015A/B CATEGORY:
B CLASS:
N FUNCTION:
This valve closes to isolate main steam in the event of an MSIV failure.
QUARTERLY TEST REQUIREMENT:
Stroke time closed, fail-safe.
PARTIAL QUARTERLY STROKE TESTING:
None. Valves do not have partial open control feature.
COLD SHUTDOWN JUSTIFICATION:
These valves supply main steam to the MSRs during power operation to remove moisture from the reheat steam going through the low-pressure turbines.
Operating these valves at power would result in a secondary thermal transient, and erosion damage to the low-pressure turbine blades.
9-8 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-MSS-2 SYSTEM:
Main Steam VALVE(S):
SV3/4-MSS-PL-V001, V002, V003, V004, V005, V006 CATEGORY:
B CLASS:
N FUNCTION:
These valves close to provide a backup to the MSIVs QUARTERLY TEST REQUIREMENT:
Exercise and stroke time closed.
COLD SHUTDOWN JUSTIFICATION:
The valves are exercised quarterly using the non-safety controls of the valve.
However, the skid-mounted safety related solenoid valves used to perform the credited function of closing these valves to back up the MSIVs cannot be tested at power, as the input signal to these valves would require the safety function be disabled on all MSIV backup isolation valves not being tested.
QUARTERLY PARTIAL STROKE TESTING:
None. The safety related solenoid valves do not have the capability for partial stroking.
COLD SHUTDOWN TESTING:
Exercise and stroke closed the turbine bypass valve using each of the safety related solenoid valves.
9-9 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-MTS-1 SYSTEM:
Main Turbine VALVE(S):
SV3/4-MTS-PL-V001A/B, V002A/B, V003A/B, V004A/B CATEGORY:
B CLASS:
N FUNCTION:
These valves close to provide a backup to the MSIVs QUARTERLY TEST REQUIREMENT:
Exercise and stroke time closed.
COLD SHUTDOWN JUSTIFICATION:
The valves are exercised quarterly using the non-safety turbine valve test controls. This test circuit does not include, the skid-mounted fast acting solenoid valves credited to perform the required function of closing these valves to back up the MSIVs. The fast-acting solenoid valves cannot be tested at power, as the turbine controls design assumed these valves would be tested on a Cold Shutdown frequency as documented in Table 3.9-16 of the DCD, and therefore does not support testing of the fast-acting solenoids as part of the on-line valve testing capability. Operation of the fast-acting solenoids at power would result in a turbine trip.
QUARTERLY PARTIAL STROKE TESTING:
None. The safety function solenoid valves do not have the capability for partial stroking.
COLD SHUTDOWN TESTING:
Exercise and stroke time closed the turbine bypass valves using the fast-acting solenoid valves.
9-10 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-PXS-1 SYSTEM:
Passive Core Cooling VALVE(S):
SV3/4-PXS-PL-V108A/B CATEGORY:
B CLASS:
1 FUNCTION:
These valves are located at the discharge of the PRHR heat exchanger to the RCS. They are closed during normal operation and shutdown, and open on a PRHR HX actuation signal, to initiate PRHR HX heat removal in order to mitigate design basis accidents.
QUARTERLY TEST REQUIREMENT:
Exercise valve and stroke time open, fail-safe test.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power, as a reactor trip is generated if they are not closed.
QUARTERLY PARTIAL STROKE TESTING:
None.
COLD SHUTDOWN TESTING:
Exercise valve and stroke time open, fail-safe test.
9-11 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-PXS-2 SYSTEM:
Passive Core Cooling DELETED
9-12 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-PXS-3 SYSTEM:
Passive Core Cooling VALVE(S):
SV3/4-PXS-PL-V231A/B CATEGORY:
C CLASS:
2 FUNCTION:
These valves open to allow filling of the CMTs from the Make-up pumps. The safety function of these valves is to allow flow from the trapped liquid between the check valve and the air operate fill valve in the event of thermal expansion due to heat-up of the area.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
COLD SHUTDOWN JUSTIFICATION:
A containment entry is required to be able to closure test these check valves.
PARTIAL QUARTERLY EXERCISE:
None. No indication of obturator position to verify partial stroking of the valves.
Routine filling/make-up of the CMTs confirms flow through the valves, but not obturator function.
COLD SHUTDOWN TESTING:
Verification of check valve partial opening and closing will be performed.
9-13 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-RCS-1 SYSTEM:
Reactor Coolant VALVE(S):
SV3/4-RCS-PL-V001A/B, V002A/B, V003A/B, V011A/B, V012A/B, V013A/B CATEGORY:
B CLASS:
1 FUNCTION:
These valves are located on the pressurizer and open to reduce the pressure in the RCS during loss-of-coolant accidents in order to permit safety injection by PXS.
QUARTERLY TEST REQUIREMENT:
Exercise valve and stroke time open, due to being High Safety Significant MOVs.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power as they are required to be closed to meet the requirements of 10CFR50.2, and to provide assurance that inadvertent RCS depressurization does not occur due to the mis-positioning of a single valve.
An ADS TEST MODE signal is generated by the operators to allow this testing via Primary DSP soft controls. The signal requires that all of the isolation valves associated with the ADS valve being tested (including test valves V007A/B) be closed while the stroke testing of the ADS valve is done. The RCS HL must also be below 200°F (93°C). This ensures that inadvertent RCS depressurization does not occur during this process.
QUARTERLY PARTIAL STROKE TESTING:
None.
COLD SHUTDOWN TESTING:
Exercise valve and stroke time open.
9-14 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-RCS-2 SYSTEM:
Reactor Coolant VALVE(S):
SV3/4-RCS-PL-V150A/B/C/D CATEGORY:
B CLASS:
1 FUNCTION:
These valves are the reactor head vent valves which can remove non-condensable gases or steam from the reactor vessel head to mitigate a possible condition of inadequate core cooling or impaired natural circulation through the steam generators resulting from the accumulation of non-condensable gases in the reactor coolant system. The reactor vessel head vent valves can also be operated from the main control room to provide an emergency letdown path which is used to prevent pressurizer overfill following long-term loss of heat sink events.
QUARTERLY TEST REQUIREMENT:
Exercise valve and stroke time open and closed, fail-safe test.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power, as exercising them would put the plant at risk of a loss of reactor coolant and RCS depressurization due to the mis-positioning of a single valve.
QUARTERLY PARTIAL STROKE TESTING:
None.
COLD SHUTDOWN TESTING:
Exercise valve and stroke time open and closed, fail-safe test.
9-15 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-RNS-1 SYSTEM:
Normal Residual Heat Removal VALVE(S):
SV3/4-RNS-PL-V003A/B, V013, V015A/B, V017A/B CATEGORY:
C CLASS:
1, 2 FUNCTION:
These valves are in the flow path for RNS, and provide closure for RCS pressure boundary, or containment isolation (V013), and open to provide a path to accommodate thermal expansion of water isolated between valves, in the event of environmental heatup.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power as they are located in containment and would require containment entry and set up of temporary test equipment in containment to test at power. Additionally, RNS cannot overcome RCS pressure during normal operation, and the suction flowpath is required to be isolated above 450 psig RCS pressure.
QUARTERLY PARTIAL STROKE TESTING:
None.
COLD SHUTDOWN TESTING:
Exercise check valve.
9-16 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-SFS-1 SYSTEM:
Spent Fuel Pool Cooling VALVE(S):
SV3/4-SFS-PL-V037 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve closes to perform containment isolation, and partially opens to accommodate thermal expansion of water in the containment penetration.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power as the configuration of the piping inside containment (piping enters IRWST above water line) does not provide an adequate water source on the valve for closure testing. As a result, testing this valve requires entry into containment, to manipulate valves and install a test pump.
QUARTERLY PARTIAL STROKE TESTING:
None. Closed testing of these valves cannot be achieved as noted above.
COLD SHUTDOWN TESTING:
Exercise check valve partially open and closed.
9-17 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-SGS-1 SYSTEM:
Steam Generator VALVE(S):
SV3/4-SGS-PL-V040A/B, V057A/B, V250A/B CATEGORY:
B CLASS:
2 (V040A/B, V057A/B), 3 (V250A/B)
FUNCTION:
These valves isolate feedwater to, or steam from, the steam generators in the event of an accident in order to minimize mass release from the steam generators.
QUARTERLY TEST REQUIREMENT:
Exercise and stroke time closed, Fail-safe test.
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power as closing them would result in a reactor trip due to the isolation of steam from, or feedwater to, the steam generator.
QUARTERLY PARTIAL STROKE TESTING:
None. The main steam and feedwater isolation valves do not have controls for partial stroke capability. Feedwater control valves, due to their control function are constantly stroking very small amounts, and more during power reductions.
Since these are constantly in motion, no specific part stroke testing is called out but will be documented quarterly.
COLD SHUTDOWN TESTING:
Stroke time closed, and failsafe test.
9-18 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-SGS-2 SYSTEM:
Steam Generator VALVE(S):
SV3/4-SGS-PL-V058A/B CATEGORY:
B CLASS:
2 FUNCTION:
These valves isolate feedwater from the steam generators in the event of an accident in order to minimize mass release from the steam generators. They partially open to allow for thermal expansion of water between these and the feedwater isolation valves.
QUARTERLY TEST REQUIREMENT:
Exercise check valve (partial open and closed).
COLD SHUTDOWN JUSTIFICATION:
These valves cannot be tested at power as it would require isolation of feedwater to the steam generator to perform the closed test, which would result in a reactor trip. Note that normal operation validates the open portion of the stroke.
QUARTERLY PARTIAL STROKE TESTING:
None. No indication of obturator position to verify partial stroking of the valves.
Feedwater flow during power operation confirms flow through the valves, but not obturator function.
COLD SHUTDOWN TESTING:
Exercise check valve partially open and closed.
9-19 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-SGS-3 SYSTEM:
Steam Generation VALVE(S):
SV3/4-SGS-PL-V256A/B CATEGORY:
C CLASS:
3 FUNCTION:
These valves partially open to relieve thermal expansion between this valve and the startup feedwater control valve.
QUARTERLY TEST REQUIREMENT:
Exercise partially open and closed.
COLD SHUTDOWN JUSTIFICATION:
The closed portion testing of these valves on-line exposes the operators performing the test to unacceptable hazards. The valves are protected from high temperature and pressure feedwater by a single automatic control valve.
Because the valves are located in the lower level of the main steam valve rooms, operators attempting to test these valves are subject to hazardous conditions in that the area could quickly fill with steam with no ready evacuation route in the event of actuation of the startup feed control valves during testing.
QUARTERLY PARTIAL STROKE TESTING:
None. Closed testing of these valves cannot be achieved as noted above.
COLD SHUTDOWN TESTING:
Exercise check valves partially open and closed.
9-20 Southern Nuclear Version 2.0 COLD SHUTDOWN JUSTIFICATION CSJ-VWS-1 SYSTEM:
Chilled Water VALVE(S):
SV3/4-VWS-PL-V062 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve performs the function of containment isolation, and opens to accommodate thermal expansion of water trapped in the containment penetration following isolation.
QUARTERLY TEST REQUIREMENT:
Exercise check valve partially open and closed.
COLD SHUTDOWN JUSTIFICATION:
This valve cannot be tested at power, as it would require entry into containment to either install and monitor non-intrusive equipment or to install a means to provide back pressure against the valve to confirm closure. This would result in personnel hazard and/or long-term suspension of cooling to containment, which can result in containment temperatures exceeding allowable limits.
QUARTERLY PARTIAL STROKE TESTING:
None. No indication of obturator position to verify partial stroking of the valve.
Flow during normal operation confirms flow through the valve, but not obturator function.
COLD SHUTDOWN TESTING:
Exercise check valve partially open and closed.
10-1 Southern Nuclear Version 2.0 10.0 REFUELING OUTAGE TESTING FREQUENCY JUSTIFICATONS
10-2 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-CAS-1 SYSTEM:
Compressed Air (Instrument)
VALVE(S):
3-CAS-PL-V014, V015 CATEGORY:
A, AC CLASS:
2 FUNCTION:
These valves close to perform containment isolation.
QUARTERLY TEST REQUIREMENT:
Stroke time exercise closed, exercise check valve closed.
BASIS FOR JUSTIFICATION:
These valves are open during operation to provide instrument air to containment. Closing these valves during operation or cold shutdown would interrupt instrument air to containment. During operation this would result in PRHR heat exchanger outlet valves opening resulting in a Reactor Trip. During Cold Shutdown interrupting Instrument Air to containment would result in loss of control of air operated valves required to maintain control of the plant.
PARTIAL QUARTERLY EXERCISE:
None. AOV does not have partial open control feature, check valve does not have ability to monitor obturator position while in service though normal operation confirms flow through the valve.
REFUELING SHUTDOWN TESTING:
Exercise check valve, partial open, closed, which may be performed in conjunction with leak rate testing.
Stroke time closed, and Fail-Safe verification of AOV.
10-3 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-CCS-1 SYSTEM:
Component Cooling Water VALVE(S):
SV3/4-CCS-PL-V201 CATEGORY:
AC CLASS:
2 FUNCTION:
This valve closes to perform containment isolation, and partially opens to accommodate thermal expansion of water in the containment penetration.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
BASIS FOR JUSTIFICATION:
This valve is open during operation due to supply Component cooling water to containment for RCP and Letdown heat exchanger cooling. Check valve cannot be exercised without interrupting cooling water flow to containment, which would interrupt cooling flow to the reactor coolant pumps resulting in a Reactor Coolant Pump Trip on high bearing water temperature, and subsequent Reactor Trip. Additionally, it would require an entry into containment to set-up equipment and test the valve.
Reactor coolant pumps are operated during Cold Shutdown if a bubble is maintained in the pressurizer, as the RCP is the preferred source of spray for Pressurizer Pressure control. Closure of this valve for testing would likely result in an RCP trip on high bearing water outlet temperature.
PARTIAL QUARTERLY EXERCISE:
None. No indication of obturator position to verify partial stroking of valve.
Normal CCS flow confirms flow through the valve, but not obturator function.
REFUELING SHUTDOWN TESTING:
Verification of check valve closure. This may be done in conjunction with Local Leak rate testing. Partial open verification is demonstrated by normal operation and return to service following the closure test.
10-4 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-CVS-1 SYSTEM:
Chemical Volume & Control VALVE(S):
SV3/4-CVS-PL-V084 & V085 CATEGORY:
B (V084), C (V085)
CLASS:
1 FUNCTION:
These valves are in the Auxiliary Spray supply line from CVS to the Pressurizer spray nozzle, and isolate the Reactor Coolant Pressure boundary.
QUARTERLY TEST REQUIREMENT:
V084 - stroke time closed and fail-safe test; V085 -Exercise check valve (part open, closed).
BASIS FOR JUSTIFICATION:
Testing of these valves during power operation, or COLD SHUTDOWN with the RCS pressurized, would result in a pressure transient in the RCS due to actuation of Auxiliary spray.
PARTIAL QUARTERLY EXERCISE:
None REFUELING SHUTDOWN TESTING:
V084 - stroke time closed and fail-safe test; V085 -Exercise check valve (part open, closed).
10-5 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-PXS-1 SYSTEM:
Passive Core Cooling VALVE(S):
SV3/4-PXS-PL-V016A/B, V017A/B CATEGORY:
C CLASS:
1 FUNCTION:
These valves remain open in a CMT actuation to provide flow from the CMT to the RCS. It is required to close to prevent reverse flow from the Accumulators through the CMT for large cold leg LOCA events, with a break either in the cold leg near the CMT pressure balance line or in the pressure balance line upstream of the CMT isolation valves, and subsequently reopen.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
BASIS FOR JUSTIFICATION:
Testing of these valves requires initiation of significant reverse flow to the DVI line which is not practical during operation due to the pressure of other systems supplying the DVI line and the normal operating pressure of the CMTs.
Additionally, even if reverse flow could be achieved, flow to the CMT prior to the check valves seating would dilute the boron concentration of the CMT.
Since the check valves are in series there is no way to determine that both check valves closed. Testing requires that test connection lines on each valve be utilized and position indicators be inserted into the valves, which requires the RCS depressurized.
PARTIAL QUARTERLY EXERCISE:
None REFUELING SHUTDOWN TESTING:
Verification of check valve closure on backflow conditions, and reopens following cessation of reverse flow.
10-6 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-PXS-2 SYSTEM:
Passive Core Cooling VALVE(S):
SV3/4-PXS-PL-V028A/B, V029A/B CATEGORY:
AC CLASS:
1 FUNCTION:
These valves are normally closed to provide isolation of the RCS from the lower design pressure accumulators, and are required to open during any event during which the Accumulators must provide injection flow, and will close if there is reverse flow.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
BASIS FOR JUSTIFICATION:
Testing of these valves at power cannot be performed as the accumulators are at a lower pressure than the RCS, seating the check valves. These valves cannot be tested at Cold Shutdown due to the need for volume in the RCS to accept the injection flow. These valves need to be tested with the reactor head removed and the vessel in communication with the refueling cavity.
PARTIAL QUARTERLY EXERCISE:
None REFUELING SHUTDOWN TESTING:
Verification of check valve opening and injection to the RCS with the RCS open to the refueling cavity, and recloses on cessation of flow. The valves are further verified closed during the PIV leak test following pressurization of the RCS.
10-7 Southern Nuclear Version 2.0 REFUELING OUTAGE JUSTIFICATION ROJ-PXS-3 SYSTEM:
Passive Core Cooling VALVE(S):
SV3/4-PXS-PL-V119A/B CATEGORY:
C CLASS:
3 FUNCTION:
These valves are normally closed as there is no flow path during normal operations. These valves are required to open during any event during which the Containment Recirculation Sump must provide injection flow to the RCS, and will close if there is reverse flow.
QUARTERLY TEST REQUIREMENT:
Exercise check valve.
BASIS FOR JUSTIFICATION:
Testing of these valves at power cannot be performed as there is no water source, and the flow path is isolated by a squib valve. Testing requires opening the piping and using a mechanical exerciser to manipulate the valve. Since the valve is in containment and requires bypassing the recirculation sump screen, it will be performed during refueling outages.
PARTIAL QUARTERLY EXERCISE:
None REFUELING SHUTDOWN TESTING:
Verification of check valve opening and closing will be performed with a mechanical exerciser and visual examination.
11-1 Southern Nuclear Version 2.0 11.0 INSERVICE TESTING OF DYNAMIC RESTRAINTS The VEGP 3&4 Inservice Testing Program for Dynamic Restraints (Snubbers) meets the requirements of Subsections ISTA and ISTD of the ASME OM Code 2012 Edition.
Snubber visual examination are performed in accordance with ISTD-4200, on the schedule established by ISTD-4250.
For testing the snubber population is divided into two Defined Test Plan Groups (DTPGs) for each Unit.
One DTPG consists of all large bore snubbers attached to the steam generators (none are attached to the Reactor Coolant Pumps), and the second containing the balance of the snubbers. Both DTPGs will be tested in accordance with ISTD-5200, at the frequency specified by ISTD-5240, using the 10% Sample Plan in accordance with ISTD-5300.
Service Life monitoring will be performed for all snubbers in accordance with ISTD-6000.
12-1 Southern Nuclear Version 2.0 12.0 DYNAMIC RESTRAINTS NOTES
13-1 Southern Nuclear Version 2.0 13.0 VEGP-3 DYNAMIC RESTRAINTS TABLES
13-2 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 3 DTPG 1 Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes SV3-RCS-SS-E03A1 1
H SV3-PH01-V1-001/G-7 & F-4 N
SV3-RCS-SS-E03A2 1
H SV3-PH01-V1-001/G-7 & F-4 N
SV3-RCS-SS-E03B1 1
H SV3-PH01-V1-001/G-7 & F-4 N
SV3-RCS-SS-E03B2 1
H SV3-PH01-V1-001/G-7 & F-4 N
13-3 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 3 DTPG 2 Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes CVS SV3-CVS-PH-11Y0262-NE 3 H
SV3-CVS-PLW-171/D-4 N
SV3-CVS-PH-11Y0262-NW 3 H
SV3-CVS-PLW-171/D-4 N
SV3-CVS-PH-11Y0268 1
H SV3-CVS-PLW-188/C-4 N
SV3-CVS-PH-11Y2040 1
H SV3-CVS-PLW-171/C-5 N
SV3-CVS-PH-11Y2223 1
H SV3-CVS-PLW-171/C-5 N
SV3-CVS-PH-11Y2224 1
H SV3-CVS-PLW-171/C-4 N
SV3-CVS-PH-11Y2227 3
H SV3-CVS-PLW-171/C-3 N
SV3-CVS-PH-11Y2229 1
H SV3-CVS-PLW-182/C-6 N
SV3-CVS-PH-11Y2263 N
H SV3-CVS-PLW-091/C-4 N
SV3-CVS-PH-11Y2265 N
H SV3-CVS-PLW-091/B-6 N
SV3-CVS-PH-11Y2266 N
H SV3-CVS-PLW-091/B-6 N
SV3-CVS-PH-11Y7074 3
H SV3-CVS-PLW-187/B-5 N
PXS SV3-PXS-PH-11Y0020 1
H SV3-PXS-PLW-01Q/C-5 N
SV3-PXS-PH-11Y0578 3
H SV3-PXS-PLW-01Z/C-5 N
SV3-PXS-PH-11Y2052 3
H SV3-PXS-PLW-02E/C-5/6 N
SV3-PXS-PH-11Y2057 3
H SV3-PXS-PLW-015/C-5 N
SV3-PXS-PH-11Y2059 3
H SV3-PXS-PLW-01H/B-6 N
13-4 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 3 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes RCS SV3-RCS-PH-11Y0039 1
H SV3-RCS-PLW-023/B-5 N
SV3-RCS-PH-11Y0060-NE 1
H SV3-RCS-PLW-023/C-6 N
SV3-RCS-PH-11Y0060-NW 1 H
SV3-RCS-PLW-023/C-6 N
SV3-RCS-PH-11Y0067 1
H SV3-RCS-PLW-01L/D-4 N
SV3-RCS-PH-11Y0081-SW 1
H SV3-CVS-PLW-188/D-6 N
SV3-RCS-PH-11Y0081-NW 1 H
SV3-CVS-PLW-188/D-6 N
SV3-RCS-PH-11Y0082 1
H SV3-RCS-PLW-028/C-5 N
SV3-RCS-PH-11Y0090 1
H SV3-PXS-PLW-050/C-3 N
SV3-RCS-PH-11Y0103 1
H SV3-RCS-PLW-043/C-4 N
SV3-RCS-PH-11Y0112 1
H SV3-RCS-PLW-016/B-5 N
SV3-RCS-PH-11Y0388 1
H SV3-RCS-PLW-030/D-3 N
SV3-RCS-PH-11Y0391 1
H SV3-RCS-PLW-03D/D-3 N
SV3-RCS-PH-11Y0528 1
H SV3-RCS-PLW-01K/D-6 N
SV3-RCS-PH-11Y0810 1
H SV3-RCS-PLW-080/B-5 N
SV3-RCS-PH-11Y0811 1
H SV3-RCS-PLW-080/B-4 N
SV3-RCS-PH-11Y0813 1
H SV3-RCS-PLW-070/B-4 N
SV3-RCS-PH-11Y1127 1
H SV3-RCS-PLW-021/C-5 N
SV3-RCS-PH-11Y1130 1
H SV3-RCS-PLW-024/C-4 N
SV3-RCS-PH-11Y1132 1
H SV3-RCS-PLW-023/B-5 N
SV3-RCS-PH-11Y1134 1
H SV3-RCS-PLW-023/B-6 N
SV3-RCS-PH-11Y1140 1
H SV3-RCS-PLW-029/B-6 N
SV3-RCS-PH-11Y1141 1
H SV3-RCS-PLW-023/C-6 N
SV3-RCS-PH-11Y1144 1
H SV3-CVS-PLW-182/B-4 N
SV3-RCS-PH-11Y2005 1
H SV3-RCS-PLW-015/C-5 N
13-5 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 3 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes RCS (cont.)
SV3-RCS-PH-11Y2101 1
H SV3-RCS-PLW-01F/B-5 N
SV3-RCS-PH-11Y2106 1
H SV3-RCS-PLW-03B/D-3 N
SV3-RCS-PH-11Y2107 1
H SV3-RCS-PLW-03A/D-3 N
SV3-RCS-PH-11Y2264 1
H SV3-RCS-PLW-028/B-6 N
RNS SV3-RNS-PH-12Y2060 3
H SV3-RNS-PLW-091/C-6 Y
SGS SV3-SGS-PH-11Y0001 2
H SV3-SGS-PLW-020/C-7 N
SV3-SGS-PH-11Y0002 2
H SV3-SGS-PLW-020/C-7 N
SV3-SGS-PH-11Y0004 2
H SV3-SGS-PLW-020/C-5 N
SV3-SGS-PH-11Y0057 2
H SV3-SGS-PLW-010/C-4 N
SV3-SGS-PH-11Y0058 2
H SV3-SGS-PLW-010/B-7 N
SV3-SGS-PH-11Y0063 2
H SV3-SGS-PLW-010/B-7 N
SV3-SGS-PH-11Y0463-LO 2
H SV3-SGS-PLW-030/B-6 N
SV3-SGS-PH-11Y0463-UP 2
H SV3-SGS-PLW-030/B-6 N
SV3-SGS-PH-11Y0464 2
H SV3-SGS-PLW-030/A-5 N
SV3-SGS-PH-11Y0470 2
H SV3-SGS-PLW-040/B-6 N
SV3-SGS-PH-11Y2002-NW 2 H
SV3-SGS-PLW-030/B/C-6 N
SV3-SGS-PH-11Y2002-SW 2
H SV3-SGS-PLW-030/B/C-6 N
SV3-SGS-PH-11Y2021-NW 2 H
SV3-SGS-PLW-030/B-6 N
SV3-SGS-PH-11Y2021-NE 2
H SV3-SGS-PLW-030/B-6 N
SV3-SGS-PH-11Y3101 2
H SV3-SGS-PLW-040/B-5/6 N
13-6 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 3 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes SGS (cont)
SV3-SGS-PH-11Y3102 2
H SV3-SGS-PLW-040/C-6 N
SV3-SGS-PH-11Y3121-NW 2 H
SV3-SGS-PLW-040/B-6 N
SV3-SGS-PH-11Y3121-NE 2 H
SV3-SGS-PLW-040/B-6 N
SV3-SGS-PH-11Y7057 2
H SV3-SGS-PLW-040/C-6 N
SV3-SGS-PH-12Y0108-UP 3 H
SV3-SGS-PLW-140/D-4 Y
SV3-SGS-PH-12Y0108-DN 3 H
SV3-SGS-PLW-140/D-4 Y
SV3-SGS-PH-12Y0136-UP 3 H
SV3-SGS-PLW-130/D-4 Y
SV3-SGS-PH-12Y0136-DN 3 H
SV3-SGS-PLW-130/D-4 Y
SV3-SGS-PH-12Y0507-UP 2 H
SV3-SGS-PLW-140/C-5 Y
SV3-SGS-PH-12Y0507-DN 2 H
SV3-SGS-PLW-140/C-5 Y
SV3-SGS-PH-12Y0510-UP 2 H
SV3-SGS-PLW-130/C-5 Y
SV3-SGS-PH-12Y0510-DN 2 H
SV3-SGS-PLW-130/C-5 Y
SV3-SGS-PH-12Y7056 2
H SV3-SGS-PLW-130/B-6 Y
SV3-SGS-PH-12Y7058 2
H SV3-SGS-PLW-140/B-6 Y
14-1 Southern Nuclear Version 2.0 14.0 VEGP-4 DYNAMIC RESTRAINTS TABLES
14-2 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 4 DTPG 1 Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes SV4-RCS-SS-E03A1 1
H SV4-PH01-V1-001/G-7 & F-4 N
SV4-RCS-SS-E03A2 1
H SV4-PH01-V1-001/G-7 & F-4 N
SV4-RCS-SS-E03B1 1
H SV4-PH01-V1-001/G-7 & F-4 N
SV4-RCS-SS-E03B2 1
H SV4-PH01-V1-001/G-7 & F-4 N
14-3 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 4 DTPG 2 Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes CVS SV4-CVS-PH-11Y0262-NE 3 H
SV4-CVS-PLW-171/D-4 N
SV4-CVS-PH-11Y0262-NW 3 H
SV4-CVS-PLW-171/D-4 N
SV4-CVS-PH-11Y0268 1
H SV4-CVS-PLW-188/C-4 N
SV4-CVS-PH-11Y2040 1
H SV4-CVS-PLW-171/C-5 N
SV4-CVS-PH-11Y2223 1
H SV4-CVS-PLW-171/C-5 N
SV4-CVS-PH-11Y2224 1
H SV4-CVS-PLW-171/C-4 N
SV4-CVS-PH-11Y2227 3
H SV4-CVS-PLW-171/C-3 N
SV4-CVS-PH-11Y2229 1
H SV4-CVS-PLW-182/C-6 N
SV4-CVS-PH-11Y2263 N
H SV4-CVS-PLW-091/C-4 N
SV4-CVS-PH-11Y2265 N
H SV4-CVS-PLW-091/B-6 N
SV4-CVS-PH-11Y2266 N
H SV4-CVS-PLW-091/B-6 N
SV4-CVS-PH-11Y7074 3
H SV4-CVS-PLW-187/B-5 N
PXS SV4-PXS-PH-11Y0020 1
H SV4-PXS-PLW-01Q/C-5 N
SV4-PXS-PH-11Y0578 3
H SV4-PXS-PLW-01Z/C-5 N
SV4-PXS-PH-11Y2052 3
H SV4-PXS-PLW-02E/C-5/6 N
SV4-PXS-PH-11Y2057 3
H SV4-PXS-PLW-015/C-5 N
SV4-PXS-PH-11Y2059 3
H SV4-PXS-PLW-01H/B-6 N
14-4 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 4 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes RCS SV4-RCS-PH-11Y0039 1
H SV4-RCS-PLW-023/B-5 N
SV4-RCS-PH-11Y0060-NE 1
H SV4-RCS-PLW-023/C-6 N
SV4-RCS-PH-11Y0060-NW 1 H
SV4-RCS-PLW-023/C-6 N
SV4-RCS-PH-11Y0067 1
H SV4-RCS-PLW-01L/D-4 N
SV4-RCS-PH-11Y0081-SW 1
H SV4-CVS-PLW-188/D-6 N
SV4-RCS-PH-11Y0081-NW 1 H
SV4-CVS-PLW-188/D-6 N
SV4-RCS-PH-11Y0082 1
H SV4-RCS-PLW-028/C-5 N
SV4-RCS-PH-11Y0090 1
H SV4-PXS-PLW-050/C-3 N
SV4-RCS-PH-11Y0103 1
H SV4-RCS-PLW-043/C-4 N
SV4-RCS-PH-11Y0112 1
H SV4-RCS-PLW-016/B-5 N
SV4-RCS-PH-11Y0388 1
H SV4-RCS-PLW-030/D-3 N
SV4-RCS-PH-11Y0391 1
H SV4-RCS-PLW-03D/D-3 N
SV4-RCS-PH-11Y0528 1
H SV4-RCS-PLW-01K/D-6 N
SV4-RCS-PH-11Y0810 1
H SV4-RCS-PLW-080/B-5 N
SV4-RCS-PH-11Y0811 1
H SV4-RCS-PLW-080/B-4 N
SV4-RCS-PH-11Y0813 1
H SV4-RCS-PLW-070/B-4 N
SV4-RCS-PH-11Y1127 1
H SV4-RCS-PLW-021/C-5 N
SV4-RCS-PH-11Y1130 1
H SV4-RCS-PLW-024/C-4 N
SV4-RCS-PH-11Y1132 1
H SV4-RCS-PLW-023/B-5 N
SV4-RCS-PH-11Y1134 1
H SV4-RCS-PLW-023/B-6 N
SV4-RCS-PH-11Y1140 1
H SV4-RCS-PLW-029/B-6 N
SV4-RCS-PH-11Y1141 1
H SV4-RCS-PLW-023/C-6 N
SV4-RCS-PH-11Y1144 1
H SV4-CVS-PLW-182/B-4 N
SV4-RCS-PH-11Y2005 1
H SV4-RCS-PLW-015/C-5 N
14-5 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 4 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes RCS (cont.)
SV4-RCS-PH-11Y2101 1
H SV4-RCS-PLW-01F/B-5 N
SV4-RCS-PH-11Y2106 1
H SV4-RCS-PLW-03B/D-3 N
SV4-RCS-PH-11Y2107 1
H SV4-RCS-PLW-03A/D-3 N
SV4-RCS-PH-11Y2264 1
H SV4-RCS-PLW-028/B-6 N
RNS SV4-RNS-PH-12Y2060 3
H SV4-RNS-PLW-091/C-6 Y
SGS SV4-SGS-PH-11Y0001 2
H SV4-SGS-PLW-020/C-7 N
SV4-SGS-PH-11Y0002 2
H SV4-SGS-PLW-020/C-7 N
SV4-SGS-PH-11Y0004 2
H SV4-SGS-PLW-020/C-5 N
SV4-SGS-PH-11Y0057 2
H SV4-SGS-PLW-010/C-4 N
SV4-SGS-PH-11Y0058 2
H SV4-SGS-PLW-010/B-7 N
SV4-SGS-PH-11Y0063 2
H SV4-SGS-PLW-010/B-7 N
SV4-SGS-PH-11Y0463-LO 2 H
SV4-SGS-PLW-030/B-6 N
SV4-SGS-PH-11Y0463-UP 2 H
SV4-SGS-PLW-030/B-6 N
SV4-SGS-PH-11Y0464 2
H SV4-SGS-PLW-030/A-5 N
SV4-SGS-PH-11Y0470 2
H SV4-SGS-PLW-040/B-6 N
SV4-SGS-PH-11Y2002-NW 2 H
SV4-SGS-PLW-030/B/C-6 N
SV4-SGS-PH-11Y2002-SW 2 H
SV4-SGS-PLW-030/B/C-6 N
SV4-SGS-PH-11Y2021-NW 2 H
SV4-SGS-PLW-030/B-6 N
SV4-SGS-PH-11Y2021-NE 2 H
SV4-SGS-PLW-030/B-6 N
SV4-SGS-PH-11Y3101 2
H SV4-SGS-PLW-040/B-5/6 N
14-6 Southern Nuclear Version 2.0 Vogtle Electric Generating Plant - Units 3&4 Dynamic Restraint Table -Unit 4 DTPG 2 (cont)
Pipe Snubber ID Class Type Iso. Drawing/Co-ord Accessible Alt/CC Comments/Notes SGS (cont)
SV4-SGS-PH-11Y3102 2
H SV4-SGS-PLW-040/C-6 N
SV4-SGS-PH-11Y3121-NW 2 H
SV4-SGS-PLW-040/B-6 N
SV4-SGS-PH-11Y3121-NE 2 H
SV4-SGS-PLW-040/B-6 N
SV4-SGS-PH-11Y7057 2
H SV4-SGS-PLW-040/C-6 N
SV4-SGS-PH-12Y0108-UP 3 H
SV4-SGS-PLW-140/D-4 Y
SV4-SGS-PH-12Y0108-DN 3 H
SV4-SGS-PLW-140/D-4 Y
SV4-SGS-PH-12Y0136-UP 3 H
SV4-SGS-PLW-130/D-4 Y
SV4-SGS-PH-12Y0136-DN 3 H
SV4-SGS-PLW-130/D-4 Y
SV4-SGS-PH-12Y0507-UP 2 H
SV4-SGS-PLW-140/C-5 Y
SV4-SGS-PH-12Y0507-DN 2 H
SV4-SGS-PLW-140/C-5 Y
SV4-SGS-PH-12Y0510-UP 2 H
SV4-SGS-PLW-130/C-5 Y
SV4-SGS-PH-12Y0510-DN 2 H
SV4-SGS-PLW-130/C-5 Y
SV4-SGS-PH-12Y7056 2
H SV4-SGS-PLW-130/B-6 Y
SV4-SGS-PH-12Y7058 2
H SV4-SGS-PLW-140/B-6 Y
15-1 Southern Nuclear Version 2.0
15.0 REFERENCES
15.1 General References 15.1.1 ASME Operation and Maintenance of Nuclear Power Plants Code, 2012 Edition (ASME OM-2012) 15.1.2 Vogtle 3&4 Updated Final Safety Analysis Report, Revision 10.1 15.1.3 Appendix A, Vogtle Electric Generating Plant, Units 3 and 4 Technical Specifications, Amendment 172 (Unit 3), Amendment 170 (Unit 4).
15.1.4 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]
15.1.5 Corrective Action Request 50001849 15.1.6 Letter from Victor E. Hall (NRC) to Brian Whitley (SNC) dated March 2, 2020,VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 - REQUEST FOR ALTERNATIVE UNDER TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, SECTION 50.55a(z)(1): ALTERNATIVE REQUIREMENTS FOR INSERVICE TEST INTERVAL CODE EDITION, UNIT 4 (IST-ALT-01), ADAMS Ascension No.
15.1.7 LDCR-2021-001, Changes Required to Close Out As-Designed ASME Section III Overpressure Protection Reports, APP-FSAR-GEF-171, Rev. 0.
15.1.8 CAR 80003783, TS SR 3.7.9.6 Disconnect with IST Program.
15.2 System Specification Documents 15.2.1 SV3-CAS-M3-001, AP1000 Compressed and Instrument Air System (CAS) -
System Specification Document, Revision 0 [APP-CAS-M3-001, Rev. 2]
15.2.2 SV4-CAS-M3-001, AP1000 Compressed and Instrument Air System (CAS) -
System Specification Document, Revision 0 [APP-CAS-M3-001, Rev. 2]
15.2.3 APP-CCS-M3-001, AP1000 Component Cooling Water-System Description Document, Revision 5 15.2.4 APP-CNS-M3-001, Containment System: System Specification Document, Revision 6 15.2.5 APP-CVS-M3-001, AP1000 Chemical and Volume Control System (CVS) System Specification Document, Revision 9 15.2.6 SV3-DWS-M3-001, Demineralized Water Transfer and Storage System (DWS),
System Specification Document, Revision 1 [APP-DWS-M3-001, Rev. 2]
15.2.7 SV4-DWS-M3-001, Demineralized Water Transfer and Storage System (DWS),
System Specification Document, Revision 1 [APP-DWS-M3-001, Rev. 2]
15.2.8 APP-FHS-M3-001, AP1000 Fuel Handling System - System Specification Document, Revision 4 15.2.9 SV3-FPS-M3-001, AP1000 Fire Protection System - System Specification Document, Revision 0 [APP-FPS-M3-001, Rev. 0]
15-2 Southern Nuclear Version 2.0 15.2.10 SV4-FPS-M3-001, AP1000 Fire Protection System - System Specification Document, Revision 0 [APP-FPS-M3-001, Rev. 0]
15.2.11 APP-MSS-M3-001, AP1000 Main Steam System Specification Document, Revision 4 15.2.12 APP-MTS-M3-001, AP1000 Main Turbine System - System Specification Document, Revision 4 15.2.13 APP-PCS-M3-001, Passive Containment Cooling System - System Specification Document, Revision 11 15.2.14 APP-PSS-M3-001, AP1000 Primary Sampling System - System Specification Document, Revision 5 15.2.15 SV3-PWS-M3-001, AP1000 Potable Water System (PWS) - System Specification Document, Revision 0 [APP-PWS-M3-001, Rev. 2]
15.2.16 SV4-PWS-M3-001, AP1000 Potable Water System (PWS) - System Specification Document, Revision 0 [APP-PWS-M3-001, Rev. 2]
15.2.17 APP-PXS-M3-001, Passive Core Cooling System, System Specification Document, Revision 10 15.2.18 APP-RCS-M3-001, Reactor Coolant System, System Specification Document, Revision 12 15.2.19 APP-RNS-M3-001, Normal Residual Heat Removal System - System Specification Document, Revision 7 15.2.20 APP-SDS-M3-001, Sanitary Drainage System (SDS) System Specification Document, Revision 1 15.2.21 APP-SFS-M3-001, AP1000 Spent Fuel Pool Cooling System - System Specification Document, Revision 12 15.2.22 APP-SGS-M3-001, Steam Generator System (SGS) System Specification Document, Revision 8 15.2.23 SV3-VBS-M3-001, Nuclear Island Nonradioactive Ventilation System, System Specification Document, Revision 2 [APP-VBS-M3-001, Rev. 2]
15.2.24 SV4-VBS-M3-001, Nuclear Island Nonradioactive Ventilation System, System Specification Document, Revision 2 [APP-VBS-M3-001, Rev. 2]
15.2.25 SV3-VES-M3-001, AP1000 Main Control Room Emergency Habitability System (VES) - System Specification Document, Revision 4 [APP-VES-M3-001, Rev. 8]
15.2.26 SV4-VES-M3-001, AP1000 Main Control Room Emergency Habitability System (VES) - System Specification Document, Revision 4 [APP-VES-M3-001, Rev. 8]
15.2.27 SV3-VFS-M3-001, Containment Air Filtration System - System Specification Document, Revision 0 [APP-VFS-M3-001, Rev. 1]
15.2.28 SV4-VFS-M3-001, Containment Air Filtration System - System Specification Document, Revision 0 [APP-VFS-M3-001, Rev. 1]
15.2.29 APP-VUS-M3-001, AP1000 Containment Leak Rate Test System - System Specification Document, Revision 6 15.2.30 SV3-VWS-M3-001, Central Chilled Water System - System Specification Document, Revision 1 [APP-VWS-M3-001, Rev. 0]
15-3 Southern Nuclear Version 2.0 15.2.31 SV4-VWS-M3-001, Central Chilled Water System - System Specification Document, Revision 1 [APP-VWS-M3-001, Rev. 0]
15.2.32 SV3-WLS-M3-001, AP1000 Plant Liquid Radwaste System - System Specification Document, Revision 0 [APP-WLS-M3-001, Rev. 9]
15.2.33 SV4-WLS-M3-001, AP1000 Plant Liquid Radwaste System - System Specification Document, Revision 0 [APP-WLS-M3-001, Rev. 9]
15.2.34 SV3-WWS-M3-001, Waste Water System (WWS) - System Specification Document, Revision 1 [APP-WWS-M3-001, Rev. 4]
15.2.35 SV4-WWS-M3-001, Waste Water System (WWS) - System Specification Document, Revision 1 [APP-WWS-M3-001, Rev. 4]
15.3 Piping and Instrumentation Diagrams - Unit 3 15.3.1 SV3-CAS-M6-005, Revision 5 15.3.2 SV3-CAS-M6-012, Revision 4 15.3.3 SV3-CCS-M6-002, Revision 6 15.3.4 SV3-CNS-M6-001, Revision 0 15.3.5 SV3-CNS-M6-002, Revision 0 15.3.6 SV3-CVS-M6-001, Revision 6 15.3.7 SV3-CVS-M6-003, Revision 7 15.3.8 SV3-CVS-M6-004, Revision 5 15.3.9 SV3-CVS-M6-005, Revision 3 15.3.10 SV3-DWS-M6-007, Revision 2 15.3.11 SV3-FPS-M6-004, Revision 6 15.3.12 SV3-MSS-M6-001, Revision 2 15.3.13 SV3-MTS-M6-002, Revision 4 15.3.14 SV3-PCS-M6-001, Revision 5 15.3.15 SV3-PCS-M6-002, Revision 6 15.3.16 SV3-PCS-M6-003, Revision 2 15.3.17 SV3-PSS-M6-001, Revision 6 15.3.18 SV3-PWS-M6-002, Revision 5 15.3.19 SV3-PXS-M6-001, Revision 6 15.3.20 SV3-PXS-M6-002, Revision 9 15.3.21 SV3-PXS-M6-003, Revision 5 15.3.22 SV3-PXS-M6-004, Revision 3 15.3.23 SV3-PXS-M6-005, Revision 0 15.3.24 SV3-RCS-M6-001, Revision 7 15.3.25 SV3-RCS-M6-002, Revision 9 15.3.26 SV3-RCS-M6-003, Revision 4 15.3.27 SV3-RCS-M6-004, Revision 4 15.3.28 SV3-RCS-M6-005, Revision 1 15.3.29 SV3-RNS-M6-001, Revision 4 15.3.30 SV3-SDS-M6-001, Revision 2
15-4 Southern Nuclear Version 2.0 15.3.31 SV3-SFS-M6-001, Revision 6 15.3.32 SV3-SGS-M6-001, Revision 7 15.3.33 SV3-SGS-M6-002, Revision 7 15.3.34 SV3-VBS-M6-002, Revision 7 15.3.35 SV3-VBS-M6-007, Revision 9 15.3.36 SV3-VES-M6-001, Revision 1 15.3.37 SV3-VES-M6-002, Revision 4 15.3.38 SV3-VFS-M6-001, Revision 8 15.3.39 SV3-VUS-M6-001, Revision 2 15.3.40 SV3-VWS-M6-003, Revision 3 15.3.41 SV3-WLS-M6-001, Revision 4 15.3.42 SV3-WLS-M6-007, Revision 5 15.3.43 SV3-WWS-M6-005, Revision 6 15.4 Piping and Instrumentation Diagrams - Unit 4 15.4.1 SV4-CAS-M6-005, Revision 6 15.4.2 SV4-CAS-M6-012, Revision 5 15.4.3 SV4-CCS-M6-002, Revision 6 15.4.4 SV4-CNS-M6-001, Revision 0 15.4.5 SV4-CNS-M6-002, Revision 0 15.4.6 SV4-CVS-M6-001, Revision 5 15.4.7 SV4-CVS-M6-003, Revision 6 15.4.8 SV4-CVS-M6-004, Revision 4 15.4.9 SV4-CVS-M6-005, Revision 3 15.4.10 SV4-DWS-M6-007, Revision 2 15.4.11 SV4-FPS-M6-004, Revision 6 15.4.12 SV4-MSS-M6-001, Revision 2 15.4.13 SV4-MTS-M6-002, Revision 4 15.4.14 SV4-PCS-M6-001, Revision 5 15.4.15 SV4-PCS-M6-002, Revision 6 15.4.16 SV4-PCS-M6-003, Revision 3 15.4.17 SV4-PSS-M6-001, Revision 6 15.4.18 SV4-PWS-M6-002, Revision 6 15.4.19 SV4-PXS-M6-001, Revision 6 15.4.20 SV4-PXS-M6-002, Revision 9 15.4.21 SV4-PXS-M6-003, Revision 5 15.4.22 SV4-PXS-M6-004, Revision 3 15.4.23 SV4-PXS-M6-005, Revision 0 15.4.24 SV4-RCS-M6-001, Revision 7 15.4.25 SV4-RCS-M6-002, Revision 9 15.4.26 SV4-RCS-M6-003, Revision 4 15.4.27 SV4-RCS-M6-004, Revision 4
15-5 Southern Nuclear Version 2.0 15.4.28 SV4-RNS-M6-001, Revision 4 15.4.29 SV4-SDS-M6-001, Revision 2 15.4.30 SV4-SFS-M6-001, Revision 6 15.4.31 SV4-SGS-M6-001, Revision 7 15.4.32 SV4-SGS-M6-002, Revision 7 15.4.33 SV4-VBS-M6-002, Revision 7 15.4.34 SV4-VBS-M6-007, Revision 9 15.4.35 SV4-VES-M6-001, Revision 1 15.4.36 SV4-VES-M6-002, Revision 4 15.4.37 SV4-VFS-M6-001, Revision 8 15.4.38 SV4-VUS-M6-001, Revision 2 15.4.39 SV4-VWS-M6-003, Revision 3 15.4.40 SV4-WLS-M6-001, Revision 3 15.4.41 SV4-WLS-M6-007, Revision 4 15.4.42 SV4-WWS-M6-005, Revision 4