Text

Fourth Ten-Year Interval Inservice Testing Program Update
	ML072280494
Person / Time
Site:	Farley
Issue date:	08/14/2007
From:	George B; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-07-1418
	Download: ML072280494 (266)
	v • d • e

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERNZM COMPANY August 14, 2007 Energy to Se,'ve Your World"*

Docket Nos.: 50-348 NL-07-1418 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Fourth Ten-Year Interval Inservice Testing Program Update Ladies and Gentlemen:

Pursuant to 10CFR50.55a(f)(5)(i), Southern Nuclear Operating Company (SNC) hereby submits the Fourth 10-Year Interval Inservice Testing (IST) Program for Farley Nuclear Plant (FNP) Units 1 and 2 for NRC review and approval. In accordance with 10 CFR 50.55a(f)(4)(ii), the updated IST program was written to meet the requirements of the ASME OM Code 2001 edition though 2003 addenda, except where proposed requests for alternatives and/or proposed requests for relief are documented in the Farley IST Program. The current IST Interval (Third) began on December 1, 1997 and will end on November 30, 2007.

The Fourth IST Interval begins on December 1, 2007 and ends on November 30, 2017.

SNC intends to utilize the guidance provided in NRC NUREG-1482, Revision 1, paragraph 3.3.3 when implementing the updated Fourth Interval IST Program. A phase-in implementation is proposed because update of the IST Program Document results in the required revision of approximately 100 surveillance procedures. Using the NUREG guidance, SNC will phase-out the Third Interval IST requirements and phase-in the Fourth Interval requirements over a 12-month period according to the following schedule.

SNC will revise affected IST surveillance procedures in accordance with Enclosure 2.

- Enclosure 2 includes a listing of all affected procedures for Units 1 and 2.

- This schedule requires approximately 25% of the procedures to be updated and made effective each quarter, beginning December 1, 2007 and ending November 30, 2008.

SNC will begin implementation of the updated IST Program Document on December 1, 2007 using a phased-in approach. /(7

U. S. Nuclear Regulatory Commission NL-07-1418 Page 2

- A combination of existing IST procedures and Fourth Interval procedures will be performed during the phase-in period.

- Existing procedures will be replaced with updated procedures in accordance with the schedule proposed above.

All surveillance procedures will be updated and the Fourth Interval IST Program will be in compliance with the updated IST Program Document by December 1, 2008.

Since phased-in implementation is discussed in NUREG-1482, Revision 1, Section 3.3.3, SNC has determined that relief or exemption is not required. SNC plans to follow the schedule as outlined above and as described in the second paragraph of "NRC Recommendations" in NUREG-1482, Revision 1, Section 3.3.3. The attached phase-in schedule shows that only procedures performed during refueling outages will be updated prior to each unit's outage, as required.

All other procedures will be phased in during the remainder of the phase-in period. If progress of procedure updates fall significantly behind the attached schedule, then SNC will notify the NRC.

Should the NRC staff not agree with this plan for implementation, SNC requests notification by October 1, 2007 due to the significant work load associated with revising procedures prior to December 1, 2007.

This same type of phase-in implementation plan was previously agreed upon by the NRC for the Edwin I. Hatch Nuclear Plant (HNP) in February 2006. The phase-in implementation plan for HNP was documented in SNC letter NL 2304.

This letter contains no NRC commitments. Should you have any questions in this regard, please advise.

Sincerely, B. J. G~g Manager, Nuclear Licensing BJG/JLS/daj

Enclosures:

1. FNP Units 1 and 2 Fourth 10-Year Interval IST Program

2. Detailed Phase-in Schedule for FNP Units 1 & 2 Affected Procedures

U. S. Nuclear Regulatory Commission NL-07-1418 Page 3 cc: Southern Nuclear Operatingq Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; LC# 14625 U. S. Nuclear Regqulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure I FNP Units 1 and 2 Fourth 10-Year Interval IST Program

Joseph M. Farley Nuclear Plant Units 1 & 2 4 th 10-Year Interval Inservice Testing Program V M&IS M&IS M&WS E DATE DESCRIPTION PREEFD REV'D APPV

_ _R BY BY BY 10 06/08/07 Initial issue of program manual to NRC for "da "

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TABLE OF CONTENTS Section Pagtes 1.0 IST PROGRAM INTRODUCTION 1-1 thru 1-3 2.0 ABBREVIATIONS 2-1 thru 2-5 3.0 INSERVICE TESTING OF PUMPS 3-1 &3-2 4.0 PUMP TEST NOTES 4-1 5.0 FNP-1 PUMP TESTING TABLES 5-1 thru 5-7 6.0 FNP-2 PUMP TESTING TABLES 6-1 thru 6-6 7.0 PUMP RELIEF REQUESTS 7-1 thru 7-8 8.0 INSERVICE TESTING OF VALVES 8-1 thru 8-3 9.0 VALVE NOTES 9-1 10.0 FNP- 1 VALVE TABLES 1 thru 72 11.0 FNP-2 VALVE TABLES 1 thru 63 12.0 VALVE RELIEF REQUESTS 12-1 thru 12-3 13.0 VALVE COLD SHUTDOWN JUSTIFICATIONS 13-1 thru 13-23 14.0 VALVE REFUELING OUTAGE JUSTIFICATIONS 14-1 thru 14-52 See Active Page List for complete listing of document contents.

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ACTIVE PAGE LIST PAGE NUMBER VERSION PAGE NUMBER VERSION IST Program 7-6 1.0 Table of Contents 1.0 7-7 1.0 7-8 1.0 Introduction 1-1 1.0 Inservice Testing of Valves 1-2 1.0 8-1 1.0 1-3 1.0 8-2 1.0 8-3 1.0 Abbreviations 2-1 1.0 Valve Notes 2-2 1.0 9-1 1.0 2-3 1.0 2-4 1.0 FNP-I Valve Tables 2-5 1.0 1 1.0 2 1.0 Inservice Testing of Pumps 3 1.0 3-1 1.0 4 1.0 3-2 1.0 5 1.0 6 1.0 Pump Test Notes 7 1.0 4-1 1.0 8 1.0 9 1.0 FNP- 1 Pump Tables 10 1.0 5-1 1.0 11 1.0 5-2 1.0 12 1.0 5-3 1.0 13 1.0 5-4 1.0 14 1.0 5-5 1.0 15 1.0 5-6 1.0 16 1.0 5-7 1.0 17 1.0 18 1.0 FNP-2 Pump Tables 19 1.0 6-1 1.0 20 1.0 6-2 1.0 21 1.0 6-3 1.0 22 1.0 6-4 1.0 23 1.0 6-5 1.0 24 1.0 6-6 1.0 25 1.0 26 1.0 Pump Relief Requests 27 1.0 7-1 1.0 28 1.0 7-2 1.0 29 1.0 7-3 1.0 30 1.0 7-4 1.0 31 1.0 7-5 1.0 32 1.0 actpglst.doc Page 1 of 4 Ver. 1.0

ACTIVE PAGE LIST PAGE NUMBER VERSION PAGE NUMBER VERSION 33 1.0 4 1.0 34 1.0 5 1.0 35 1.0 6 1.0 36 1.0 7 1.0 37 1.0 8 1.0 38 1.0 9 1.0 39 1.0 10 1.0 40 1.0 11 1.0 41 1.0 12 1.0 42 1.0 13 1.0 43 1.0 14 1.0 44 1.0 15 1.0 45 1.0 16 1.0 46 1.0 17 1.0 47 1.0 18 1.0 48 1.0 19 1.0 49 1.0 20 1.0 50 1.0 21 1.0 51 1.0 22 1.0 52 1.0 23 1.0 53 1.0 24 1.0 54 1.0 25 1.0 55 1.0 26 1.0 56 1.0 27 1.0 57 1.0 28 1.0 58 1.0 29 1.0 59 1.0 30 1.0 60 1.0 31 1.0 61 1.0 32 1.0 62 1.0 33 1.0 63 1.0 34 1.0 64 1.0 35 1.0 65 1.0 36 1.0 66 1.0 37 1.0 67 1.0 38 1.0 68 1.0 39 1.0 69 1.0 40 1.0 70 1.0 41 1.0 71 1.0 42 1.0 72 1.0 43 1.0 44 1.0 FNP-2 Valve Tables 45 1.0 1 1.0 46 1.0 2 1.0 47 1.0 3 1.0 48 1.0 actpglst.doc Page 2 of 4 Ver. 1.0

ACTIVE PAGE LIST PAGE NUMBER VERSION PAGE NUMBER VERSION 48 1.0 13-22 1.0 49 1.0 13-23 1.0 50 1.0 51 1.0 Valve Refueling Outage Justifications 52 1.0 14-1 1.0 53 1.0 14-2 1.0 54 1.0 14-3 1.0 55 1.0 14-4 1.0 56 1.0 14-5 1.0 57 1.0 14-6 1.0 58 1.0 14-7 1.0 59 1.0 14-8 1.0 60 1.0 14-9 1.0 61 1.0 14-10 1.0 62 1.0 14-11 1.0 63 1.0 14-12 1.0 14-13 1.0 Valve Relief Requests 14-14 1.0 12-1 1.0 14-15 1.0 12-2 1.0 14-16 1.0 12-3 1.0 14-17 1.0 14-18 1.0 14-19 1.0 Valve Cold Shutdown Justifications 14-20 1.0 13-1 1.0 14-21 1.0 13-2 1.0 14-22 1.0 13-3 1.0 14-23 1.0 13-4 1.0 14-24 1.0 13-5 1.0 14-25 1.0 13-6 1.0 14-26 1.0 13-7 1.0 14-27 1.0 13-8 1.0 14-28 1.0 13-9 1.0 14-29 1.0 13-10 1.0 14-30 1.0 13-11 1.0 14-31 1.0 13-12 1.0 14-32 1.0 13-13 1.0 14-33 1.0 13-14 1.0 14-34 1.0 13-15 1.0 14-35 1.0 13-16 1.0 14-36 1.0 13-17 1.0 14-37 1.0 13-18 1.0 14-38 1.0 13-19 1.0 14-39 1.0 13-20 1.0 14-40 1.0 13-21 1.0 14-41 1.0 actpglst.doc Page 3 of 4 Ver. 1.0

ACTIVE PAGE LIST PAGE NUMBER VERSION PAGE NUMBER VERSION 14-42 1.0 14-43 1.0 14-44 1.0 14-45 1.0 14-46 1.0 14-47 1.0 14-48 1.0 14-49 1.0 14-50 1.0 14-51 1.0 14-52 1.0 actpglst.doc Page 4 of 4 Ver. 1.0

1.0 IST PROGRAM INTRODUCTION 1.1 GENERAL This document describes the Pump and Valve Inservice Testing (IST) Program for the Farley Nuclear Plant (FNP) Units 1 and 2. The IST Program is in accordance with the requirements of 10CFR50.55a and Improved Technical Specification 5.5.8. Provided below are important dates relative to the IST Program.

FNP Unit 1 FNP Unit 2 Construction Permit Issued Date 08/16/72 08/16/72 Commercial Operation 12/01 / 1977 07/30/1981 1st 10-year Interval 12/01/1977 to 11/30/1987 07/30/1981 to 07/29/1991 2nd 10-year Interval 12/01/1987 to 11/30/1997 07/30/1991 to 11/30/1997 3rd 10-year Interval 12/01/1997 to 11/30/2007 12/01/1997 to 11/30/2007 4th 10-year Interval 12/01/2007 to 11/30/2017 12/01/2007 to 11/30/2017 In order to utilize the same Code edition for both units, a relief request was submitted to update FNP Unit 2 at the same time as Unit I for the 2nd 10 year interval. In a letter dated March 20, 1997, the Nuclear Regulatory Commission (NRC) approved an alternative to the requirement of 10CFR50.55a(f)(4)(ii) that changed the date of record by which the Unit 2 program is required to be updated, making it consistent with Unit 1. Therefore, the Code of record for IST for the 4th 10-year interval is the same for both units.

According to 10CFR50.55a(f)(4)(ii), following completion of the first 10-year inspection interval, successive 10-year inspection intervals must comply with the requirements of the latest edition and addenda of the American Society of Mechanical Engineers (ASME) Code incorporated by reference in paragraph (b) of 10CFR50.55a twelve months prior to the start of the 10-year inspection interval. The Edition of 10CFR50.55a in effect 12/01/2006 (October 1, 2004 version) references the ASME OM Code 2001 Edition with Addenda through OMb-2003, as the applicable Code. The OM Code, or the Code, in this document corresponds to the aforementioned Edition and Addenda.

This program document includes IST requirements for safety-related ASME Code Class 1, 2 and 3 pumps and valves. NRC NUREG-1482, Rev.1, was used, to the extent practical, for guidance in the development of this program.

This document includes inservice testing requirements for pumps and valves. The inservice testing of dynamic restraints (snubbers) is not included in this program and at the present time is considered to be part of the Plant Technical Requirements Manual.

1.2 EFFECTIVE DATE The IST Program for the 4th 10-year interval is effective beginning December 1, 2007 and will be utilized through November 30, 2017.

1-1 Version 1.0

1.3 SCOPE 10CFR50.55a(f)(4) and the OM Code, paragraph ISTA- 1100, establish the scope of inservice testing to be Class 1, 2, and 3 pumps, valves, and pressure relief devices which are required in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. More specifically:

Pumps with an emergency power source required to perform the above.

" Active or passive valves required to perform the above.

Pressure relief devices which protect systems or portions of systems that are required to perform the above.

The license safe shutdown condition for FNP Units 1 and 2 is the hot shutdown condition. NRC communications agree that the scope of IST should be commensurate with the licensing basis.

Although the scope of IST components is legally based on bringing the unit to the licensed safe shutdown condition, the implemented scope of IST is based on the cold shutdown condition.

For FNP, SNC considers the total scope of inservice testing to include testing of all safety related Class 1, 2, and 3 pumps and valves.

1.4 COMPONENT UPGRADING Appendix 3A of the FNP Final Safety Analysis Report (FSAR) commits Southern Nuclear Operating Company (SNC) to meet the requirements of Regulatory Guide 1.26 (or Safety Guide 26), dated March 23, 1972. Appendix 3A also permits use of the classification system stated in the August 1970 draft of ANSI N18.2 as an alternative to Safety Guide 26. Several systems which perform a safety-related function, as defined above, are excluded from the criteria of either Safety Guide 26 or ANSI N 18.2 as applied to the Farley Nuclear Plant.

Plant components have been reviewed to determine the appropriate classification for inservice testing. The aforementioned documents were used for guidance in determining component classifications.

Note that the classification of pumps and valves as ASME Class 1, 2, or 3 equivalent for this program does not imply that the components were designed in accordance with ASME requirements.

Pump and valve design remains as stated in the FSAR.

1.5 SUBSEQUENT PROGRAM REVISIONS It is anticipated that this document will be reviewed again near the end of the 10 year inspection interval and compared to a later NRC approved version of the ASME Code applicable for IST. At that time, the program will be modified, if required, to comply to the extent practical with the latest NRC endorsed edition of the Code. Any additional relief requests for impractical requirements will be submitted in accordance with the applicable regulations.

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1.6 RESPONSIBILITY SNC bears the overall responsibility for the implementation of the inservice testing activities contained in this program per the ASME OM Code, Subsection ISTA-1500.

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

1.8 METHODS OF TESTING The method of testing applicable to each pump and valve is listed adjacent to the component identification in the Pump and Valve Tables. The ASME OM Code does not stipulate any specific training/certification requirements for personnel involved in pump or valve testing. At FNP, all pump and valve testing is performed by operations, maintenance or engineering personnel who have been trained to perform specific testing tasks.

1.9 STANDARDS FOR TESTING EVALUATION The acceptance criteria applicable for each pump and valve to be tested have been developed in accordance with the ASME OM Code requirements as modified by any applicable relief requests.

Acceptance criteria are not provided in the IST Program document, but are provided in implementation plans and applicable surveillance testing procedures which are available for review at the plant site.

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2.0 ABBREVIATIONS ABBREVIATION DEFINITION A Active A Angle Valve Accum Accumulator ACCW Auxiliary Component Cooling Water ACT Active Act. Actuation Add Addition Admis Admission AFW Auxiliary Feedwater Al As Is AJ IOCFR50 Appendix J Alt Alternate AO Air Operated AP Active or Passive ARFD As Required, Following Disassembly ARV Atmospheric Steam Relief Valve ASME American Society of Mechanical Engineers AT Actuator Aug Augmented Aux Auxiliary B Butterfly valve BA Boric Acid BDTC Bi-Directional Test Close BDTO Bi-Directional Test Open BI Biennial BIT Boron Injection Tank Bldg Building BTRS Boron Thermal Regeneration System C Close Cat Category Cav Cavity CB Control Building CC Code Classification CCW Component Cooling Water Cent Centrifugal Chg Charging Chem Chemical Chlor Chlorination Chlr Chiller CIV Containment Isolation Valve CK Check valve CL Cold Leg Cond Condensate Coord Coordinate Section 2.0 IST Pgm Abbrev 4thlnt.doc 2-1 Version 1.0

2.0 ABBREVIATIONS ABBREVIATION DEFINITION CPT Comprehensive Pump Test CSD Cold Shutdown CSD/RF Cold Shutdown and Refueling CS] Cold Shutdown Justification CTB Containment Building CTMT Containment Ctrl Control CVCS Chemical and Volume Control System D Diaphragm valve DG Diesel Generator Demin Demineralized Disch Discharge Disp Dispersant Dm Drain EH Electro-Hydraulic EMERG Emergency ESF Engineered Safety Feature Ess Essential ET Exercise Test ETC Exercise Test Close ETO Exercise Test Open ETPO Exercise Test Partial Open ETSP Relief Valve Test Evap Evaporator Exh Exhaust Exp Expansion FCV Flow Control Valve FNP Farley Nuclear Plant FP Fail Position Freq Frequency FS Fail Safe Test FSAR Final Safety Analysis Report FSVC Fail Safe Valve Close FSVO Fail Safe Valve Open FW Main Feedwater GA Gate valve Gen Generator GFFD Gross Failed Fuel Detector GL Globe valve H2 Hydrogen HDR Header Section 2.0 IST Pgm Abbrev 4thlnt.doc 2-2 Version 1.0

2.0 ABBREVIATIONS ABBREVIATION DEFINITION HHSI High Head Safety Injection HL Hot Leg HV Hydraulic Valve HVAC Heating Ventilation and Air Conditioning HX Heat exchanger ID Identification Inbrd Inboard Inj Injection INST Instrument IRC Inside Reactor Containment ISO Isolation IST Inservice Testing Jac Jacket LA Category A Valve Test LHSI Low Head Safety Injection U Appendix J leak rate test only U-C Appendix J type C leak Test LOCA Loss of Coolant Accident LOSP Loss of Offsite Power LT Leakage Test LTA PIV Test Ltdwn Letdown Lub Lubrication M Manual Max Maximum MDAFW Motor Driven Auxiliary Feedwater MFIV Main Feedwater Isolation Valve Min Minimum MO Motor Operated MOV Motor Operated Valve Mot Motor MS Main Steam MSIV Main Steam Isolation Valve N2 Nitrogen NA Not Applicable NP Normal Position NSCW Nuclear Service Cooling Water O Open O/C Open and Close Obrd Outboard Section 2.0 IST Pgm Abbrev 4thlnt.doc 2-3 Version 1.0

2.0 ABBREVIATIONS ABBREVIATION DEFINITION OM O&M - Operation and Maintenance ORC Outside Reactor Containment P Passive Pan Panel PAS Passive PASS Post-Accident Sampling System PC Project Class PCS Partial stroke test exercised Cold Shutdown PDP Positive Displacement Pump Pen Penetration PIT Position Indication Test PID Pipe and Instrumentation Diagram PIV Pressure Isolation Valve PORV Power Operated Relief Valve PFR Penetration Filtration Room Proc Processing Prot Protection PRT Pressurizer Relief Tank PRZR Pressurizer PQ Partial-stoke exercised Quarterly Pur Purification Purif Purification Q Flowrate Q Quarterly RC Reactor Coolant RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump RCS Reactor Coolant System RD Rupture Disk Recirc Recircul at ion Reg Regulating Ret Return RF Refueling RHR Residual Heat Removal RMW Reactor Makeup Water RO Refueling Outage ROJ Refueling Outage Justification RPV Reactor Pressure Vessel RR Relief Request RV Relief valve RWST Refueling Water Storage Tank RX Reactor Section 2.0 IST Pgm Abbrev 4thlnt.doc 2-4 Version 1.0

2.0 ABBREVIATIONS ABBREVIATION DEFINITION S Self actuating Sam Sample SC Stop Check Valve SED System Evaluation Document Ser Service SFP Spent Fuel Pool SFPCPS Spent Fuel Pool Cooling and Purification System SG Steam Generator SI Safety Injection SO Solenoid SP Safety Position SR Safety and Relief Valve STC Stroke Time Close STO Stroke Time Open Suc Suction Sup Supply SW Service Water SYS System T Relief Valve Test Freq TDAFW Turbine Driven Auxiliary Feedwater TC Temperature Control Test Testable TPNS Total Plant Numbering System Tran Transfer TW 3-way valve Vac Vacuum VCT Volume Control Tank Vlv Valve VR Vacuum Relief XCONN Cross Connection 18M 18 Month 2Y 2-Year Section 2.0 IST Pgm Abbrev 4thlnt.doc 2-5 Version 1.0

3.0 INSERVICE TESTING OF PUMPS 3.1 GENERAL The IST Program was developed to comply with the requirements of 10 CFR 50.55a(f), dated October 1, 2004. This section of the IST program delineates the testing requirements for ASME Class 1, 2, and 3 pumps included for inservice testing (IST) at Southern Nuclear Operating Company's (SNC) Farley Nuclear Plant (FNP)

Units I and 2. The Code of record required by 10 CFR 50.55a(b)(3) for 4th Interval IST is the ASME OM Code - 2001 Edition with Addenda trough OMb-2003. The supplemental guidance of NRC NUREG-1482. Rev. 1, has been applied, to the extent practical, in the development of IST of pumps. For pumps which are within the scope of IST, as stipulated in 10 CFR 50.55a, where specific Code requirements can not be meet, relief has been requested from the specific Code requirements.

As required by OM Code, ISTB-1300, pumps within the scope of this program shall be categorized as either Group A or Group B pumps.

Group A pumps are defined as pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operation.

Group B pumps are defined as pumps in standby systems that are not operated routinely except for testing.

Group A and Group B pump testing is required quarterly. In addition to the quarterly Group A or Group B pump tests, the OM Code imposed a biennial Comprehensive Pump Test and a Preservice Pump Test for pumps that are overhauled or replaced.

The IST Program Pump Tables list the parameters measured during Group A, Group B, and Comprehensive Pump Testing.

Preservice Testing is equivalent to Comprehensive Pump Testing, except Preservice Testing requires the development of a five point pump curve for centrifugal and vertical line shaft pumps in which flow and differential pressure is measured.

Vibration measurements are only required to be taken at the reference value(s).

3.2. SCOPE Safety-related ASME Code Class 1, 2 and 3 pumps, meeting the scope criteria of ASME OM Code ISTA- 1100 and falling under the Regulatory Position of Regulatory Guide 1.26 or Safety Guide 26 (March 1972), are included within the scope of this program. Special scope features of the Farley IST Program are discussed below.

It was recognized that 10 CFR 50, Appendix A, General Design Criteria 1, and Appendix B, Criterion XI, intended that all pumps necessary for safe operation of the plant be tested to demonstrate that they will perform satisfactorily in service. The testing is to be performed to a level commensurate with the safety significance of the pump. This testing is generally performed per the requirements of the plant IST Pgm Pumps 4thlnt.doc 3-1 version 1.0

Technical Specifications or other requirements. In cases where Code requirements are impractical for certain pumps, or an alternate testing method is considered an improvement over OM Code requirements, a relief request has been developed.

Pump relief requests are located under a separate tab.

3.2.1 River Water Pumps The service water pond comprises the ultimate heat sink at FNP. The river water pumps provide normal make-up to the service water pond, but the accident analyses indicate that make-up is not required for a period of at least 30-days post accident.

Therefore, the river water pumps do not meet the scope criteria of the OM Code, Subsection ISTA-l 100, and are not required to be included in the IST Program.

3.2.2 Diesel Fuel Oil Transfer Pumps Safety Guide 26 provides criteria for determining the safety classification of nuclear power plant components. Safety Guide 26 is applicable only to water, steam, and radioactive containing components. Therefore, the fuel oil transfer pumps are not within the safety classification scope of Safety Guide 26 and are thus not required to be included within the scope of the IST Program.

FNP has decided to include the diesel generator fuel oil transfer pumps in the IST Program and has designated them as "augmented". The diesel generator fuel oil transfer system was not designed to facilitate inservice testing of the transfer pumps.

System design did not include any flow or pressure measuring instrumentation to allow establishment of reference values for test comparison. The pumps provided have a rated capacity of approximately 20 gpm where as the design capacity requirement is less than 5 gpm. There is significant redundancy in the number of pumps provided to supply fuel to the emergency diesel generators and the possibility of not being able to meet their operating requirements is virtually non-existent.

The fuel oil transfer pumps are tested in conjunction with emergency diesel generator testing to satisfy Technical Specification requirements which provide a level of assurance that the pumps are capable of performing their intended function. The flow rate, differential pressure, and vibration amplitude of each pump is measured or determined every 18-months to evaluate operational readiness and to monitor for potential degradation. This once per operating cycle testing should provide adequate assurance that the emergency diesel generators are capable of being provided with sufficient fuel quantities to meet any accident requirements.

IST Pgm Pumps 4thlnt.doc 3-2 version 1.0

4.0 PUMP TEST NOTES

1. Augmented components do not fall within the scope of the ASME OM Code as implemented by 10 CFR 50.55a (i.e. not ASME Class 1, 2, or 3), are not covered by the Regulatory Position of Regulatory Guide 1.26 (September 1974), and were not designed to facilitate performance of OM Code type pump testing. Therefore, they are only included in this program document to provide a readily accessible, controlled mechanism for testing.

As discussed in Section 3.2 of this document, testing will be performed in a manner similar to that of the OM Code, and such testing should adequately detect degradation.

2. Pumps shared between Units I and 2 such as the Diesel Generator Fuel Oil Transfer Pumps are included in the FNP-1 Pump Test Tables.

4.0 pump notes.doc 4-1 Version 1.0

FNP-1 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameters Freguency RR/Remarks QIE11POO1A Residual Heat Removal D175041 Pd N/A N/A Q1EI IP001B (RHR) G-7; E-7 Q Q N/A Group A V Q N/A N N/A N/A AP Q N/A QIE13POOIA Containment Spray (CS) D175038-3 2 Pd N/A N/A Q1E13POO1B B-8; G-8 Group B Q Q N/A V N/A N/A N N/A NA AP Q N/A Q1E21PO02A Charging/ High Head D175039-6 2 Pd N/A N/A QIE21PO02B Safety Injection (HHSI) F-5; G-5; Q1E21PO02C H-5 Q Q N/A Group A V Q N/A N N/A N/A AP Q N/A pumptbl.doc 5-1 Ver. 1.0

FNP-1 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&IDI/ Code Test Test TPNS Description/Group Coord Class Parameters Frequency RR/Remarks QIE21P005A Boric Acid Transfer (BAT) D 175039-3 3 Pd N/A N/A QIE21P005B G-6; H-6 Group A Q Q RR-P-2 V Q N/A N NA N/A AP Q N/A Q1N23POOIA Motor Driven AFW Pump D175007 3 Pd N/A N/A Q1N23POO1B Auxiliary Feedwater System B-5; E-5 (AFW) Q Q RR-P-3 Group A V Q N/A N N/A N/A AP Q N/A Q 1N23P002 Turbine Driven AFW Pump D175007 3 Pd N/A N/A Auxiliary Feedwater System H-5 (AFW) Q Q N/A Group B V N/A N/A N Q N/A AP Q N/A pumptbl.doc 5-2 Ver. 1.0

FNP-1 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Frequency RR/Remarks QIP16P00IA Service Water Pump D170119-1 3 Pd N/A N/A QIP16P001B 14-3; H-5; QiP16P00IC Group A H-7; H-9; Q Q RR-P-1 QIPI6P001D H-11 QIP16POOIE V Q RR-P- 1 N N/A N/A Q RR-P- I Q1P17POOIA Component Cooling Water D175002-1 3 Pd N/A N/A Q1P17P001B C-2; E-2; QIP17PO01C Group A G-2 Q Q N/A V Q N/A N N/A N/A AP Q N/A pumptbl.doc 5-3 Ver. 1.0

FNP-1 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Frequency RR/Remarks QSY52P501 A Diesel Generator D170060 3 Pd N/A N/A QSY52P501B Fuel Oil Transfer QSY52P503A (Augmented) G-3; G-2; Q 18M Notes 1,2 QSY52P503B G-5: G-4; QSY52P504A Group B V 18M Notes 1, 2 QSY52P504B QIY52P502A G-12;G-11; N N/A N/A QIY52P502B G-10; G-9 AP 18M Notes 1, 2 pumptbl.doc 5-4 Ver. 1.0

FNP-1 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameters Frequency RR/Remarks QIEIlIPOOIA Residual Heat Removal D175041 2 Pd N/A N/A QIEIIPOOIB (RHR) G-7; E-7 Q Biennially N/A Group A V Biennially N/A N N/A N/A AP Biennially N/A QIEI3POO1A Containment Spray (CS) D175038-3 2 Pd N/A N/A QIEl3P001B B-8; G-8 Group B Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A QIE21PO02A Charging Pump (HHSI) D175039-6 2 Pd N/A N/A QIE21PO02B F-5; G-5; QIE21PO02C Group A H-5; Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A pumptbl.doc 5-5 Ver. 1.0

FNP-1 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Freauency RB/Remarks Q 1E2 IPOO5A Boric Acid Transfer Pump D175039-3 3 Pd N/A N/A Q1E21PO05B G-6; H-6 Group A Q Refueling N/A V Refueling N/A N N/A N/A AP Refueling N/A Q1N23POOA Motor Driven AFW Pump D175007 3 QIN23POO1B Pd N/A N/A B-5; E-5; Group A H-5 Q Refueling N/A V Refueling N/A N N/A N/A AP Refueling N/A QIN23P002 Turbine Driven AFW Pump D175007 3 Pd N/A N/A H-5 Group B Q Biennially N/A V Biennially N/A N Biennially N/A AP Biennially N/A pumptbl .doc 5-6 Ver. 1.0

FNP-1 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Freguency RR/Remarks QiP16P001A Service Water Pump D170119-1 3 Pd N/A QIP16POOIB N/A H-3; H-5; QIP16P00IC Group A H-7; H-9; QIP16POOID Q Refueling N/A H-1I Q1P16POOIE V Refueling N/A N N/A N/A AP Refueling N/A Q1P17POO1A Component Cooling Water D175002-1 3 Pd N/A QIPI7POOIB N/A C-2; E-2; Q1P17POO1C Group A G-2 Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A pumptbl.doc 5-7 Ver. 1.0

FNP-2 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameters Frequency RRlRemarks Q2E1I1POOIA Residual Heat Removal D205041 2 Pd N/A N/A Q2EIIPOOIB (RHR) G-7; E-7 Group A Q Q N/A V Q N/A N N/A N/A AP Q N/A Q2E13POOA Containment Spray (CS) D205038-3 2 Pd N/A Q2E13POOIB N/A B-8; G-8 Group B Q Q N/A V N/A N/A N N/A NA AP Q N/A Q2E21POO2A Charging/ High Head D205039-6 2 Pd N/A Q2E21PO02B N/A Safety Injection (HHSI) F-5; G-5; Q2E21PO02C H-5 Q Q N/A Group A V Q N/A N N/A N/A AP Q N/A pumptbl.doc 6-1 Version 1.0

FNP-2 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameters Frequency RR/Remarks Q2E21POO5A Boric Acid Transfer (BAT) D205039-3 3 Pd N/A N/A Q2E21PO05B G-6; H-6 Q Q RR-P-2 Group A V Q N/A N NA N/A AP Q N/A Q2N23POO1A Motor Driven AFW Pump D205007 3 Pd N/A N/A Q2N23POO1B Auxiliary Feedwater System B-5; E-5 (AFW) Q Q RR-P-3 Group A V Q N/A N N/A N/A AP Q N/A Q2N23P002 Turbine Driven AFW Pump D205007 3 Pd N/A N/A Auxiliary Feedwater System H-5 (AFW) Q Q N/A Group B V N/A N/A N Q N/A AP Q N/A pumptbl.doc 6-2 Version 1.0

FNP-2 PUMP TESTING TABLES Quarterly Group A and Group B Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Frequency RR/Remarks Q2Pl6POO1A Service Water Pump D200013-2 3 Pd N/A N/A Q2PI6POO1B H-3; H-5; Q2PI6POOIC Group A H-7; H-9; Q Q RR-P-I Q2P16POO1D H-I1 Q2P16POOIE V Q RR-P- 1 N N/A N/A AP Q RR-P-I Q2PI7POO1A Component Cooling Water D205002-1 3 Pd N/A N/A Q2P17POO1B C-2; E-2; Q2PI7P001C Group A G-2 Q Q N/A V Q N/A N N/A N/A AP Q N/A Q2Y52P505A Diesel Generator D170060 3 Pd N/A N/A Q2Y52P503B Fuel Oil Transfer G-3; G-2; (Augmented) G-5; G-4; Q 18 months Note 1 G-12; G-11; Group B G-10; G-9 V 18 months Note 1 N N/A N/A AP 18 months Note I pumptbl.doc 6-3 Version 1.0

FNP-2 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameters Frequency RR/Remarks Q2E1 IPOOA Residual Heat Removal D205041 2 Pd N/A N/A Q2El1POO1B (RHR) G-7; E-7 Q Biennially N/A Group A V Biennially N/A N N/A N/A AP Biennially N/A Q2EI3POO1A Containment Spray (CS) D205038-3 2 Pd N/A N/A Q2E13P001B B-8; G-8 Group B Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A Q2E21PO02A Charging Pump (HHSI) D205039-6 2 Pd N/A N/A Q2E2 lPO02B F-5; G-5; Q2E21PO02C Group A H-5; Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A pumptbl.doc 6-4 Ver. 1.0

FNP-2 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&IDI/ Code Test Test TPNS Description/Group Coord Class Parameter Frequency RR/Remarks Q2E21PO05A Boric Acid Transfer Pump D205039-3 3 Pd N/A N/A Q2E21PO05B G-6. H-6 Group A Q Refueling N/A V Refueling N/A N N/A N/A AP Refueling N/A Q2N23POOIA Motor Driven AFW Pump D205007 3 Pd N/A N/A Q2N23P001B B-5; E-5; Group A H-5 Q Refueling N/A V Refueling N/A N N/A N/A AP Refueling N/A Q2N23P002 Turbine Driven AFW Pump D205007 3 Pd N/A N/A H-5 Group B Q Biennially N/A V Biennially N/A N Biennially N/A AP Biennially N/A pumptbl.doc 6-5 Ver. 1.0

FNP-2 PUMP TESTING TABLES Biennial Comprehensive Pump Tests P&ID/ Code Test Test TPNS Description/Group Coord Class Parameter Frequency RR/Remarks Q2PI6POOA Service Water Pump D200013-2 3 Pd N/A N/A Q2PI6POO1B H-3; H-5; Q2PI6POOlC Group A H-7; H-9; Q Refueling N/A Q2P16POO1D H-11 Q2PI6P001E V Refueling N/A N N/A N/A AP Refueling N/A Q2P17POOLA Component Cooling Water D205002-1 3 Pd N/A N/A Q2Pl7POOB C-2; E-2; Q2P17P00IC Group A G-2 Q Biennially N/A V Biennially N/A N N/A N/A AP Biennially N/A pumptbl.doc 6-6 Ver. 1.0

7.0 PUMP RELIEF REQUEST LOG Relief Request Component Status RR-P- I QI(2)P16POOIA, B, C, D, E Submitted to NRC for review.

RR-P-2 QI(2)E21PO05A, B Submitted to NRC for review.

RR-P-3 Q1(2)N23POOIA, B Submitted to NRC for review.

IST pgm RRPumps.doc 7-1 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P.1 PLANT/UNIT: Joseph M. Farley Nuclear Plant / Units I and 2.

INTERVAL: 4 'h Interval beginning December 1, 2007 and ending November 30, 2017.

COMPONENTS Q1Pi6POOIA, B, C, D, & E (Vertical Line Shaft Service Water AFFECTED: Pumps) Group A Q2P16P001A, B, C, D, & E (Vertical Line Shaft Service Water Pumps) Group A CODE EDITION ASME OM Code-2001 Edition with Addenda through OMb-2003 AND ADDENDA:

REQUIREMENTS: ISTB-5221 requires a Group A pump test to be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph.

REASON FOR This alternative is a re-submittal of NRC approved 3 rd Interval REQUEST: relief request RR-P-2 that was based on the ASME OM Code-1990 Edition, no addenda. This 4"h Interval request for relief, RR-P-1, is based on the ASME OM Code-2001 Edition with Addenda through OMb-2003. There have been no substantive changes to this alternative, to the OM Code requirements (with the exception of Group A, Group B and Comprehensive tests) or to the basis for use, which would alter the previous NRC Safety Evaluation conclusions. (See References for SER date and TAC numbers associated with 3Yd Interval relief request RR-P-2.)

The Service Water System is designed so that during normal operation there are two pumps in each of the two trains operating, with a standby pump available to swing to either train. Each pump has pressure gages; however flow instrumentation is installed only to measure the flow from each of the two trains.

Since flow instrumentation was not provided for each pump, the only viable means of individually testing these pumps is by removal of one pump from service and measuring flow through the train with only one pump aligned. However, a flow of 32,186 gpm, which requires four pumps (or both trains operable), is required for normal operation per the FSAR. A condition where only one pump is aligned at a time to a train would result in IST pgm RRPumps.doc 7-2 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-1 degraded cooling water flow to essential or safety related equipment and is therefore an unacceptable method of operation.

Furthermore, removal of one pump from the service water train could lead to an isolation of the turbine building service water supply lines due to low flow and potentially cause a plant trip.

Since hydraulic performance of a degrading pump may be masked by the other pump when service water pumps are tested in pairs, FNP has developed analytical methods which can be used to determine individual pump flow rate. These analytical methods involve solving three equations involving dual pump flows for three individual pump flow rates. These analytical methods have proven reliable in determining individual pump operational readiness and monitoring for degradation.

PROPOSED Quarterly combined flow, differential pressure and vibration will ALTERNATIVE be measured and compared to reference values. This request is AND BASIS: not applicable to Comprehensive or Preservice Testing.

Whenever combined flow measurements are not in the acceptable range, individual pump evaluations, which consist of performing three dual pump combination tests at a reference differential pressure and solving analytical equations for individual flows, will be performed. If three pumps are not immediately available to support this testing, then tests will be performed as soon as three pumps are available. For the case in which three pumps are not immediately available to support testing, and flow is in the ALERT Range, dual pump testing of the two pumps in the ALERT Range will be performed at double the required frequency until three pumps are available. Corrective action will be taken on the individual pumps as a result of the evaluation in accordance with ISTB-6200.

Individual service water pump testing will be performed during the Comprehensive pump test at least once every two years.

Individual pump testing will consist of monitoring pump flow, differential pressure, and vibration and comparison of test data to reference values for each parameter.

The above proposed alternative provides reasonable assurance that the mechanical condition of the pumps demonstrated during the quarterly Group A tests support operational readiness. Based on the determination that compliance with the Code requirements IST pgm RRPumps.doc 7-3 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-1 results in a hardship without a compensating increase in the level of quality and safety, this proposed alternative should be granted pursuant to 10 CFR 50.55a(a)(3)(ii).

DURATION: 4"h IST Interval, December 1, 2007 through November 30, 2017.

PRECEDENTS: This Relief Request was approved as RR-P-2 for the Third 10 Year IST Interval.

REFERENCES:

NRC Safety Evaluation dated October 29, 1998 - TAC Nos.

M99186 and M99187.

STATUS: Submitted for NRC review.

IST pgm RRPumps.doc 7-4 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-2 PLANT/UNIT: Joseph M. Farley Nuclear Plant / Units 1 and 2.

INTERVAL: 4"h Interval beginning December 1, 2007 and ending November 30, 2017.

COMPONENTS QIE21PO05A, B (Horizontal Centrifugal Boric Acid Transfer AFFECTED: Pumps) Group A Q2E21PO05A, B (Horizontal Centrifugal Boric Acid Transfer Pumps) Group A CODE EDITION ASME OM Code-2001 Edition with Addenda through OMb-2003 AND ADDENDA:

REQUIREMENTS: ISTB-5121 requires a Group A pump test to be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph. Table ISTB-3000-1 identifies flow rate as a required test parameter.

REASON FOR This alternative is a re-submittal of NRC approved 3 rd Interval REQUEST: relief request RR-P-4 that was based on the ASME OM Code-1990 Edition, no addenda. This 4 " Interval request for relief, RR-P-2, is based on the ASME OM Code-2001 Edition with Addenda through OMb-2003. There have been no substantive changes to this alternative, to the OM Code requirements (with the exception of Group A, Group B and Comprehensive tests) or to the basis for use, which would alter the previous NRC Safety Evaluation conclusions. (See References for SER date and TAC numbers associated with 3rd Interval relief request RR-P-4.)

Quarterly Group A pump testing is performed using the orificed pump discharge test line which runs back to the boric acid storage tank. This line does not have any installed flow measuring instrumentation. To utilize the system flow meter would require a test flow path which would transfer highly concentrated boric acid from the boric acid tank into the CVCS and into the RCS through the operating CVCS charging pump. The addition of concentrated boric acid to the RCS during normal operations would adversely affect the boric acid concentration in the RCS and could cause a forced plant shutdown.

IST pgm RRPumps.doc 7-5 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-2 PROPOSED Pump differential pressure and vibration readings will be ALTERNATIVE measured on a quarterly basis during the Group A pump test.

AND BASIS: This request is not applicable to Comprehensive or Preservice Testing.

Since it is not feasible to measure the flow rate during the quarterly Group A test due to lack of flow instrumentation in the recirculation line, the above proposed alternative provides reasonable assurance that the mechanical condition of the pumps demonstrated during the quarterly Group A tests support operational readiness. Based on the determination that compliance with the Code requirements results in a hardship without a compensating increase in the level of quality and safety, this proposed alternative should be granted pursuant to 10 CFR 50.55a(a)(3)(ii).

DURATION: 4 th IST Interval, December 1, 2007 through November 30, 2017.

PRECEDENTS: This Relief Request was approved as RR-P-4 for the Third 10 Year IST Interval.

REFERENCES:

NRC Safety Evaluation dated October 29, 1998 - TAC Nos.

M99186 and M99187.

STATUS: Submitted for NRC review.

IST pgm RRPumps.doc 7-6 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-3 PLANT/UNIT: Joseph M. Farley Nuclear Plant / Units I and 2.

INTERVAL: 41h Interval beginning December 1, 2007 and ending November 30, 2017.

COMPONENTS Q IN23POO1A, B (Horizontal Centrifugal Motor Driven Auxiliary AFFECTED: Feedwater (AFW) Pumps) Group A Q2N23P001A, B (Horizontal Centrifugal Motor Driven Auxiliary Feedwater (AFW) Pumps) Group A CODE EDITION ASME OM Code-2001 Edition with Addenda through OMb-2003 AND ADDENDA:

REQUIREMENTS: ISTB-5121 requires a quarterly Group A pump IST with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded. Table ISTB-3000-1 identifies flow rate as a required test parameter. (This relief request is not applicable to biennial Comprehensive or Preservice pump IST.)

REASON FOR This alternative is similar to NRC approved 3 rd Interval Relief REQUEST: Request RR-P-5 that was based on the ASME OM Code-1990 Edition, no addenda. This 4h Interval request for relief is based on the ASME OM Code-2001 Edition with Addenda through OMb-2003.

ISTB-5121 requires a quarterly Group A pump IST by varying system resistance until either the differential pressure or flow rate equals the corresponding reference value, or by use of a fixed resistance flow path. The only system valve(s) with flow throttling capability is located in the injection line to the steam generators. Use of the injection line(s) is not practical during normal operation because the injection of cold water into the hot steam generators results in a significant thermal shock of the injection nozzles and could result in nozzle cracking.

Use of the 2" minimum flow fixed resistance line limits the flow rate of the 350 gpm AFW pumps to approximately 50 gpm. IST at this significantly low flow rate would provide only minimal data for determining pump operational readiness or monitoring degradation.

Each pump is also provided with a 4" return line to the IST pgm RRPumps.doc 7-7 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM - RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-P-3 Condensate Storage Tank (CST). However, the lines downstream of the first isolation valve are ANSI B31.10, Class III Non-Nuclear and the piping and supports was not designed and installed to be used for full-flow testing of the AFW pumps.

FNP attempted to utilize these 4" return lines for AFW pump IST and experienced significant piping vibration that was considered detrimental to long term component integrity. Redesign and modification of these 4" return lines would result in a significant hardship with minimal increase in the level of quality and safety since each motor driven AFW pump is tested every refueling outage at the design flow rate during the Comprehensive Pump Test (CPT).

PROPOSED The quarterly AFW pump Group A IST will be performed ALTERNATIVE utilizing the 2" fixed resistance minimum flow line (i.e.,

AND BASIS: approximately 50 gpm) with measurement of differential pressure and vibration only.

Quarterly IST on the 2" fixed resistance minimum flow line provides some assurance of pump operational readiness and will also detect gross degradation. This quarterly IST combined with a CPT each refueling outage, at design flow rate, provides adequate test data to evaluate operational readiness and monitor degradation. Based on SNC's conclusion that compliance with the Code requirements results in a hardship without a compensating increase in the level of quality and safety, this proposed alternative should be granted pursuant to 10 CFR 50.55a(a)(3)(ii).

DURATION: 4 th IST Interval, December 1, 2007 through November 30, 2017.

PRECEDENTS: A similar relief request was approved as RR-P-5 for the Third 10 Year IST Interval.

REFERENCES:

NRC Safety Evaluation dated October 29, 1998 - TAC Nos.

M99186 and M99187.

STATUS: Submitted for NRC review.

IST pgm RRPumps.doc 7-8 Version 1.0

8.0 INSERVICE TESTING OF VALVES 8.1. GENERAL This section of the IST Program was developed to comply with the testing provisions of 10 CFR 50.55a(f), dated October 1, 2004, which delineate the testing requirements for ASME Class 1, 2, and 3 valves. The Code of record required by 10 CFR 50.55a (b)(3) for the 4th Interval valve IST is the ASME OM Code-2001 Edition with Addenda through OMb-2003 (hereafter referred to as the OM Code). The supplemental guidance of NRC NUREG- 1482, Revision 1, has been applied to the extent practicable.

Valves in the program are listed by TPNS Number in tables for Units 1 and 2, respectively, and will be tested in accordance with the Code unless otherwise specified in this program.

8.2. SCOPE Safety-related ASME Class 1, 2, and 3 valves covered by the Regulatory Position of Safety Guide 26 (March 1972) are included within the scope of this program and are tested using the provisions of the OM Code. Containment isolation valves located in non-safety related systemrs are considered safety-related for containment purposes, and are, therefore, tested under the provisions of the OM Code and 10 CFR 50, Appendix J, as applicable. In cases where specific Code requirements cannot be met or an alternative testing method is considered an improvement over OM Code requirements, relief has been requested from these requirements. Valve relief requests are located under a separate tab.

It is recognized that 10 CFR 50 Appendix A, GDC- I, and Appendix B, Criterion XI intend that all valves necessary for safe operation of the plant be tested to demonstrate that they will perform satisfactorily in service. This testing is required to be performed at a level commensurate with the safety function of the valve, and is generally performed per the requirements of the plant Technical Specifications or other regulatory requirements.

River Water System The service water pond comprises the ultimate heat sink at FNP. The river water pumps provide normal make-up to the service water pond, but the accident analyses indicate that make-up is not required for a period of at least 30-days post accident.

Therefore, the river water system valves do not meet the scope criteria of the OM Code, Subsection ISTA- 1100, and are not required to be included in the IST Program.

8.3. LEAKAGE RATE TESTING 8.3.1 PRESSURE ISOLATION VALVES (PIV)

Pressure isolation valves (PIVs) are defined as two normally closed valves in series that isolate the Reactor Coolant System (RCS) from the attached low pressure system. Event V pressure isolation valves (WASH 1400) are defined in Section 4.4.4 of NUREG 1482, Revision 1, as "two check valves in series at a low pressure/RCS interface whose failure may result in a LOCA that bypasses containment."

Section 8.0 IST Pgm Valves 4thlnt.doc 8-1 Version 1.0

Pressure isolation valves are not listed in the plant Technical Specifications.

However, they are listed in the FNP Technical Requirements Manual (TRM)

Table 13.4.5-1. Each pressure isolation valve is designated "PIV" in the "Frequency" column in the valve tables. Some valves function as both pressure and containment isolation valves, and are designated as PIV/CIV.

Instrumentation to monitor the leakage upstream of each pressure isolation valve during power operation was not a design requirement at FNP. Also, while it is practical to test several of the valves individually, the ability to isolate and test each valve separately was not a design consideration. Subsequently, all valves can not be practically tested on an individual basis. A leakage test will be performed at least every 2 years per ISTC-3630(a), or per the surveillance requirements specified in plant Technical Specification SR 3.4.14.1 as follows:

a. A valve that serves as a pressure isolation valve is tested at operating differential pressure or at a reduced pressure as allowed by ISTC-3630(b)(4), using water as a test medium. The leakage observed during a reduced pressure test is then adjusted to a "function maximum pressure differential value" as required by ISTC-3630(b)(4). The allowable leakage at operating differential pressure for RCS/low pressure piping interface valves is 0.5 gpm (1892 cc/min) per inch of valve size up to a maximum of 5 gpm.

b. An RCS/low pressure piping interface valve that also functions as a containment isolation valve (CIV) is Appendix J, type C tested using CIV acceptance criteria since this criteria is more stringent. Acceptable leakage for these valves is always less than the PIV criterion of 1892 cc/min per inch of valve size, even when the adjustment to the "function maximum pressure differential value" is performed.

8.3.2 CONTAINMENT ISOLATION VALVES (CIV)

All containment isolation valves that receive a Type C, Appendix J test are included in this Program and are identified as "CIV" in the "Frequency" column in the valve tables. Any changes in the Appendix J, Type C testing scope will be reflected in this document with appropriate changes to the test tables. CIVs that do not require Type C leakage testing have not been included in the Program Tables as Category A valves. CIVs that are Type A tested only are included in the applicable Intregrated Leak Rate Test procedure and CIVs that do no require any leakage testing (e.g., water sealed) are listed as Category B or C valves.

SNC conforms to the requirements of ISTC-3630(e) to the extent practical by assigning a specific leakage limit to each valve or penetration assembly. Limits are based on the type and size of each valve, the number of valves in the test boundary, and historical leakage data.

As a rule, test configurations have the least number of boundary valves practical to perform the Type C test; however, the piping configuration at FNP generally requires the pressurization of a combination of CIVs and block valves simultaneously. In these cases, the leakage limit is applied to each penetration test configuration. During the testing of the penetration, if the measured leakage exceeds the limit for the penetration, causes are investigated and repairs made to specific valves as necessary. The intent of the OM Code to detect degradation (and repair if necessary) of each valve due to service related conditions is therefore met.

Section 8.0 IST Pgm Valves 4thlnt.doc 8-2 Version 1.0

8.3.3 LEAK TEST TYPE AND FREQUENCY DESIGNATION

" All valves that require an Appendix J Type C Leakage Test are designated by "U-C" in the "Test" column of the Valve Test Tables.

" All valves that require a PIV Leakage Test are designated by "U-A" in the "Test" column of the Valve Tables.

" "L" in the "Frequency" column indicates a leakage test frequency in accordance with 10 CFR 50 Appendix J, Option B.

" "LA" in the "Frequency" column indicates a leakage test is required at least every 2-year per ISTC-3630(a) or per TS 3.4.14.1.

8.4 FAIL-SAFE VALVES If normal exercising of a power operated valve also tests the Fail-Safe function per ISTC-3560, then fail-safe testing is not listed in the Valve Tables (i.e., FSTC or FSTO are not listed.) If normal exercising does not test the Fail-Safe function, then fail-safe testing is listed in the tables along with information related to how ISTC-3560 is satisfied.

8.5 PASSIVE POWER OPERATED VALVES A passive power operated valve does not perform a mechanical motion during the course of accomplishing a system safety function. These valves are identified as such in the "Active/Passive" column of the Valve Test Tables. Per Table ISTC-3500-1, passive Category B valves do not require any exercising testing. Verification of the actual valve position is indicated by remote position indication lights every two years and is the only testing required. Passive Category B power operated valves that are de-encrgized in their safety position during power operation will not have remote position indication verification.

8.6 CHECK VALVES It is SNC's position to extend the test frequency of any non safety position tests to refueling outage without a Refueling Outage Justification (ROJ) or without a Cold Shutdown Justification (CSJ).

Section 8.0 IST Pgm Valves 4thlnt.doc 8-3 Version 1.0

9.0 VALVE NOTES

1. This valve is not required to be reopened once it is closed; therefore, stroke timing in the open direction is not required.

Valve notes.doc 9-1 Version 1.0

Joseph M. FarleyNuclear Plant IST Program Unit I Page 1 of 72 B13 - Reactor Coolant PD Valve ID CC Cat. Size Type Act. AP (CoOrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks 0113SV2213A 2 B 1 GL SO A D-175037/1 C O/C C PIT 2Y (HV001) (E-7) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 0IB13SV2213B 2 B 1 GL SO A D-175037/1 C O/C C PIT 2Y (HV003) (E-8) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q1B13SV2214A 2 B 1 GL SO A D-175037/1 C O/C C PIT 2Y (HV002) (E-7) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q1B13SV2214B 2 B 1 GL SO A D-175037/1 C O/C C PIT 2Y (HV004) (E-8) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q1B13V0027A 1 B 3 GA MO A D-175037/2 0 O/C Al PIT 2Y (MOVSOOOA) (D-2) STC 0 PRESSURIZER PORV BLOCK VALVE STO Q QIB13VO027B 1 B 3 GA MO A D-175037/2 0 O/C Al PIT 2Y (MOV8000B) (E-2) STC Q PRESSURIZER PORV BLOCK VALVE STO Q Q0B13V13 31A 1 C 6X6 SR S A D-175037/2 C O/C NA ETSP T (D-5)

PRESSURIZER SAFETY 01B 13V0031B 1 C 6X6 SR S A D-175037/2 C O/C NA ETSP T (D-4)

PRESSURIZER SAFETY OIB13VO031C 1 C 6X6 SR S A D-175037/2 C O/C NA ETSP T (0-3)

PRESSURIZER SAFETY 01B13V0037 2 A 1 D AO A D-175037/2 0 C C PIT 2Y (HV8047) (8-10) Li-C LJ PRT N2 SUPPLY ISO VALVE (PEN 64A) STC Q

Joseph M. Farley Nuclear Plant IST Program Unit 1 Page 2 of 72 B 13 - Reactor Coolant PID Valve ID CC Cat. r q R / S I O e ak Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJRemarks Q1B13V0038 2 AC 3 CK S A D-175037/2 C C NA ETC RF ROJ-V-01 (V8046) (B-10) Li-C LJ RMW TO PRT ISO CHECK VALVE (PEN 30) BDTO Normal Ops Q1B13V0039 2 A 1 D AO A D-175037/2 0 C C PIT 2Y (HV8033) (B-11) STC Q PRT N2 SUPPLY (PEN 64A) Li-C U 01B13V0040 2 A 3 D AO A D-175037/2 C C C PIT 2Y (HV8028) (B-11) STC a RMW TO PRT ISO VALVE (PEN 30) Li-C LJ 0IB13V0053 1 B 3 GL AO A D-175037/2 C O/C C PIT 2Y (PCV445A) (D-2) STO CSD/RF PRESSURIZER PORV STC CSD/RF Q1B13V0054 2 AC 2 CK S A D-175037/2 C O/C NA ETO RF ROJ-V-02 (V8092) (C-6) ETC RF ROJ-V-02 CVCS CHARGING PUMP RELIEF VALVE DISCHARGE TO PRT Li-C Li (PEN 59) - -& -L - AO A D-175037/2 C O/C C 01BI3V0061 1 B 3 GL AO A D-175037/2 C 0/C C PIT 2Y (PCV444B) (E-2) STO CSD/RF PRESSURIZER PORV STC CSD/RF QIB13VOI10 2 AC 3/4X1 SR S A D-175037/2 C O/C NA ETSP T (B-11) Li-C Li REACTOR MAKEUP WATER SYSTEM (PEN 30) RELIEF VALVE

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 3 of 72 El 1 - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks OlE11VO001A 1 A 12 GA MO A D-175041 C O/C Al PIT 2Y (MOV8701 A) (G-3) STO CSD/RF CSJ-V-02 1A RHR PUMP SUCTION FROM RCS (HL) (PEN 16) STC CSD/RF CSJ-V-02 LTA LA

_JU-C U QIE11V0001B 1 A 12 GA MO A D-175041 C O/C Al PIT 2Y (MOV8702A) (E-3) STO CSD/RF CSJ-V-02 1B RHR PUMP SUCTION FROM RCS (HL) (PEN 18) STC CSD/RF CSJ-V-02 LTA LA LU-C U Q1E11V0009A 2 B 8 GA MO A D-175041 C 0 Al PIT 2Y (MOV8706A) (B-8) STO Q/CSD CSJ-V-04 CHG PUMP SUCTION FROM RHR HX A Q1E11VOO09B 2 B 8 GA MO A D-175041 C 0 Al PIT 2Y (MOV8706B) (C-8) STO Q/CSD CSJ-V-04 CHG PUMP SUCTION FROM RHR HX B QIEI1VOO15A 2 C 3X4 SR S A D-175041 C O/C NA ETSP T (V8708A) (G-4)

RHR PUMP SUCTION RELIEF Q1E1IV0015B 2 C 3X4 SR S A D-175041 C O/C NA ETSP T (V8708B) (E-4)

RHR PUMP SUCTION RELIEF QIEI1VOO16A 1 A 12 GA MO A D-175041 C O/C Al STO CSD/RF CSJ-V-02 (MOV8701 B) (G-2) STC CSD/RF CSJ-V-02 1A RHR PUMP SUCTION FROM RCS LOOPS LTA LA PIT 2Y QIEI1V0016B 1 A 12 GA MO A D-175041 C O/C Al PIT 2Y (MOV8702B) (E-2) STC CSD/RF CSJ-V-02 1B RHR PUMP SUCTION LTA LA STO CSD/RF CSJ-V-02

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 4 of 72 Eli -LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (CoOrd) NP SP FP Test Freq RR/CSJIROJ Remarks Q1El1V0021A 1 AC 6 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-05 (E-1) ETC RF ROJ-V-05 RHR PUMP DISCHARGE TO SI(CL) LTA LA Q1ElVO21B 1 AC 6 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-05 (F-1) ETC RF ROJ-V-05 RHR PUMP DISCHARGE TO SI(CL) LTA LA QIE11V0021C 1 AC 6 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-05 (G-1) ETC RF ROJ-V-05 RHR PUMP DISCHARGE TO SI(CL) LTA LA OIE11VOO23A 2 B 10 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8888B) (G-3) STO Q RHR/LHSI DISCHARGE TO RCS(CL) STC Q QIEI1V0023B 2 B 10 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8888A) (F-3) STO Q RHR/LHSI DISCHARGE TO RCS(CL) STC Q Q1E11V0024A 2 B 10 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8887A) (F-4) STO Q RHR/LHSI TO RCS XCONN STC Q Q1ElIV0024B 2 B 10 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8887B) (G-4) STO Q RHR/LHSI TO RCS XCONN STC 0 QIE11V0025A 2 A 14 GA MO A D-175038/2 C O/C Al PIT 2Y (MOV8811A) (J-4) STO a 1A RHR PUMP SUCTION FROM CTMT SUMP (PEN 11) STC a JU-C U 0IE1IVO025B 2 A 14 GA MO A D-175038/2 C O/C Al PIT 2Y (MOV8811 B) (H-4) STO Q 18 RHR PUMP SUCTION FROM CTMT SUMP (PEN 10) STC 0 LJ-C LJ

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 5 of 72 Eli - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1 E11V0026A 2 A 14 GA MO A D-175038/2 C O/C Al STO 0 (MOV8812A) (J-5) STC Q 1A RHR PUMP SUCTION FROM CTMT SUMP (PEN 11) U-C LJ PIT 2Y Q1E1IVO026B 2 A 14 GA MO A D-175038/2 C O/C AI PIT 2Y (MOV8812B) (H-5) STC Q 1B RHR PUMP SUCTION FROM CTMT SUMP (PEN 10) LJ-C LJ STO a Q1E1IV0027A 2 B 14 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8809A) (F-10) STC 0 Note-1 1A RHR PUMP SUCTION FROM RWST 0IEI V0027B 2 B 14 GA MO A D-175038/2 0 O/C Al PIT 2Y (MOV8809B) (G-10) STC Q Note- I 1B RHR PUMP SUCTION FROM RWST Q1E11V0028 2 C 14 CK S A D-175038/2 C O/C NA ETO a (F-1 0) ETC RF ROJ-V-06 RHR PUMP SUCTION FROM RWST O1E11V0032A 2 B 10 B AO P D-175041 0 0 0 PIT 2Y (HCV603A) (B-7)

RHR HEAT EXCHANGER DISCHARGE VALVES QIE1IV0032B 2 B 10 B AO P D-175041 0 0 0 PIT 2Y (HCV603B) (C-7)

RHR HEAT EXCHANGER DISCHARGE VALVES Q1E11V0033A 2 B 8 B AO P D-175041 0 0 0 PIT 2Y (HCV605A) (C-8)

RHR HEAT EXCHANGER BYPASS FLOW CONTROL VALVES QIE11VO033B 2 B 8 B AO F D-175041 0 0 0 PIT 2Y (HCV605B) (D-8)

RHR HEAT EXCHANGER BYPASS FLOW CONTROL VALVES

Joseph M. FarleyNuclear Plant IST Program Unit I Page 6 of 72 El1 - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (CoOrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIE11V0037A 2 B 2 GL MO A D-175041 0 C Al PIT 2Y (FCV602A) (D-5) STC Q 1A RHR PUMP MINIFLOW Q0E11V0037B 2 B 2 GL MO A D-1 75041 0 C Al STC 0 (FCV602B) (D-5) PIT 2Y 18 RHR PUMP MINIFLOW Q1E11VO038A 2 C 10 CK S A D-175041 C O/C NA ETO a (B-5) ETC a 1A RHR DISCHARGE TO RCS OlE11V0038B 2 C 10 CK S A D-175041 C O/C NA ETO 0 (C-5) ETC Q 1B RHR DISCHARGE TO RCS QIE11V0039A 2 AC .75X1 SR S A D-175038/2 C O/C NA ETSP T (G-3) LJ-C LU lB RHR HX DISCHARGE RELIEF (PEN 59) 0IE11VO039B 2 AC .75X1 SR S A D-175038/2 C O/C NA ETSP T (F-3) Li-C U 1A RHR HX DISCHARGE RELIEF (PEN 59)

QIE11VO040 2 AC .75Xl SR S A D-175038/2 C O/C NA ETSP T (F-3) LU-C LU RHR HX DISCHARGE RELIEF (PEN 59)

QlE11V0042A 2 AC 10 CK S A D- 175038/2 C O/C NA ETO CSD/RF ROJ-V-03 (G-2) ETC RF ROJ-V-03 RHR PUMP DISC TO SIS INJECTION CL LTA LA QIEI1V0042B 2 AC 10 CK S A D-175038/2 C O/C NA ETO CSD/RF ROJ-V-03 (E-2) ETC 2Y ROJ-V-03 RHR PUMP DISC TO SIS INJECTION CL LTA LA QEIE1V0044 2 B 10 GA MO A D-175038/2 C O/C Al PIT 2Y (MOV8889) (F-3) STO Q/CSD/RF CSJ-V-03 RHR HX DISCHARGE TO RCS(HL) STC Q/CSD/RF CSJ-V-03

Joseph M. Farley Nuclear Plant IST Program Unit I Page 7 of 72 E11 - LHSI/RHR PID Valve ID CC Cat Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks QIE11V0051A 1 C 6 CK S A D-175038/1 C 0 NA ETO RF ROJ-V-04 (V8998A) (C-2) BDTC RF RCS LOOP LHSI CL QIE11V0051B 1 C 6 CK S A D-175038/1 C 0 NA ETO RF ROJ-V-04 (V8998B) (D-2) BDTC RF RCS LOOP LHSI CL QIE11V0051C 1 C 6 CK S A D-175038/1 C 0 NA ETO RF ROJ-V-04 (V8998C) (D-2) BDTC RF RCS LOOP LHSI CL

Joseph M. Farley Nuclear Plant IST Program Unit 1 Page 8 of 72 E12 - Reactor Cavity Cooling PlD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks O1E12V0001A Aug B 36 8 AO A D-175010/2 0 C C PIT 2Y (HV3999A) (B-10) STC CSD/RF 1ARX CAVITY COOLING SYSTEM Q1EI2V0001B Aug B 36 B AO A D-175010/2 0 C C PIT 2Y (HV3999B) (B-10) STC CSD/RF 1B RX CAVITY COOLING SYSTEM

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 9 of 72 E13 - ContainmentSpray PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E13VO002A 2 C 8 CK S A D-175038/3 C O/C NA ETPO ARFD (V8822A) (C-2) ETO RF ROJ-V-07 1A CTMT SPRAY PUMP DISCHARGE ETC RF ROJ-V-07 Q1E13V0002B 2 C 8 CK S A D-175038/3 C O/C NA ETPO ARFD (V88228) (F-2) ETO RF ROJ-V-07 1B CTMT SPRAY PUMP DISCHARGE ETC RF ROJ-V-07 G1E13VO003A 2 A 12 GA MO A D-175038/3 C O/C Al PIT 2Y (MOVa826A) (H-3) STO Q CTMT SPRAY PUMP 1A SUCTION FROM CTMT SUMP (PEN 94) STC Q LJ-C U QIE13VO003B 2 A 12 GA MO A D-175038/3 C O/C Al PIT 2Y (MOV8826B) (H-3) STO Q CTMT SPRAY PUMP 18 SUCTION FROM CTMT SUMP (PEN 93) STC 0 LU-C UL QIE13VO004A 2 A 12 GA MO A D-175038/3 C O/C Al PIT 2Y (MOV8827A) (H-4) STC Q CTMT SPRAY PUMP IA SUCTION FROM CTMT SUMP (PEN 94) U-C U STO Q Q1E13V0004B 2 A 12 GA MO A D-175038/3 C O/C Al PIT 2Y (MOV8827B) (H-4) STO 0 CTMT SPRAY PUMP 1B SUCTION FROM CTMT SUMP (PEN 93) STC Q U-C U QIE13VOO05A 2 B 8 GA MO A D-175038/3 C O/C At PIT 2Y (MOV8820A) (B-5) STO Q CTMT SPRAY PUMP 1A DISCHARGE STC a QIE13VWO5B 2 B 8 GA MO A D-175038/3 C O/C At PIT 2Y (MOV8820B) (G-5) STO Q CTMT SPRAY PUMP 18 DISCHARGE STC a QIE13VOO12A 2 B 10 GA MO A D-175038/3 0 O/C Al STC Q Note-1 (MOV8817A) (E-10) PIT 2Y CTMT SPRAY PUMP 1A SUCTION FROM RWST

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 10 of 72 E13 - Containment Spray PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E13V0012B 2 B 10 GA MO A D-175038/3 0 O/C Al PIT 2Y (MOV8817B) (G-10) STC a Note-1 CTMT SPRAY PUMP 1B SUCTION FROM RWST Q1E13VO014 2 C 12 CK S A D-175038/3 C O/C N/A ETO RF ROJ-V-08 (V8816) (E-10) ETC RF ROJ-V-08 CTMT SPRAY PUMP SUCTION FROM RWST

Joseph M. Farley Nuclear Plant IST Program Unit 1 Page 11 of 72 E14 - Containment Isolation PID Valve 1D CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01E14HV3657 2 A 1 GL AO A D-175010/2 0 C C PIT 2Y (A-4) STC 0 CTMT AIR SAMPLE FROM R11/R12 (PEN 55) Li-C Li Q1 E14HV3658 2 A 1 GL AO A D-175010/2 0 C C PIT 2Y (B-4) Li-C Li CTMT AIR SAMPLE TO R 1/R12 (PEN 54) STC Q Q1E14VO001 2 AC 1 CK S A D-175010/2 C O/C NA ETO 0 (A-2) ETC RF ROJ-V-09 CTMT AIR SAMPLE (PEN 55) Li-C Li Q1E14V0002 2 A 1 GL MO A D-175010/2 0 C Al PIT 2Y (MOV3660) (B-2) STC 0 CTMT AIR SAMPLE TO R1 1/12 (PEN 54) Li-C LJ Q1EI4V0003 2 A 1 GL MO A D-175010/2 0 C Al PIT 2Y (MOV3318A) (B-2) Li-C Li I'TKAT r 1ENI0r1TIAI Dr-QQcI I IMQTrAI T IPAT IHCr1 ATInKI STC 0 (PEN 70) M_

Q1E14V0004 2 A 1 GL MO A D-175010/2 0 C Al PIT 2Y (MOV3318B) (C-2) STC 0 CTMT DIFFERENTIAL PRESSURE INSTRUMENT ISOLATION U-C Li (PEN 70)

Joseph M. FarleyNuclear Plant1ST Program Unit I Page 12 of 72 E15 - PenetrationRoom Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E15CKDMP002 Aug C 14 CK S A D-175022 C O/C C ETO 0 A (C-2) ETC Q PRF RECIRC FAN IA CHECK DAMPER Q1E15CKDMP002 Aug C 14 CK S A D-1 75022 C O/C C ETO Q B (C-8) ETC 0 PRF RECIRC FAN 1B CHECK DAMPER QIE15CKDMPO03 Aug C 12 CK S A D-175022 C O/C C ETC 0 A (B-2) ETO Q PRF EXHAUST FAN 1A CHECK DAMPER Q1E15CKDMP003 Aug C 12 CK S A D-175022 C O/C C ETO Q B (D-8) ETC Q PRF EXHAUST FAN 1B CHECK DAMPER QIE15VO001A Aug B 18 B MO A D-175022 C 0 Al STO a (MOV3361B) (D-4) PIT 2Y 1B PRF RECIRC FAN DAMPER OIE15VO001B Aug B 18 B MO A D-175022 C 0 Al PIT 2Y (MOV3361A) (D-5) STO a 1A PRF RECIRC FAN DAMPER QIE15VO001C Aug B 18 B MO A D-175022 C 0 Al PIT 2Y (MOV3362B) (D-5) STO Q 1B PRF SUCTION DAMPER Q1E15VOOO1D Aug B 18 B MO A D-175022 C 0 Ai PIT 2Y (MOV3362A) (D-6) STO 0 1A PRF SUCTION DAMPER Q1E15VO002A Aug B 14 B AO A D-175022 C 0 0 PIT 2Y (HV3356A) (C-2) STO 0 1A PRF RECIRC FAN EXHAUST DAMPER Q1E15VO002B Aug B 14 B AO A D-175022 C 0 0 PIT 2Y (HV3356B) (B-8) STO a 1B PRF RECIRC FAN EXHAUST DAMPER

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 13 of 72 E15 - PenetrationRoom Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E15VO003A Aug B 12 a AO A D-175022 C 0 0 PIT 2Y (HV3357A) (A-2) STO 0 1A PRF EXHAUST FAN DISCH DAMPER 01 E15VO003B Aug B 12 B AO A D-175022 C 0 0 PIT 2Y (HV3357B) (D-8) STO 0 1B PRF EXHAUST FAN DISCH DAMPER

Joseph M. FarleyNuclear PlantIST Program Unit I Page 14 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIE21V0016A 2 B 3 GA MO A D-175038/1 C O/C Al PIT 2Y (MOV8803A) (G-7) STC RF ROJ-V-14 HHSI TO RCS (CL) ISO STO RF ROJ-V-14 0IE21V0016B 2 B 3 GA MO A D-175038/1 C O/C Al PIT 2Y (MOV8803B) (G-7) STO RF ROJ-V-14 HHSI TO RCS (CL) ISO STC RF ROJ-V-14 OIE21V0026 2 C 8 CK S A D-175038/1 C O/C NA ETO RF ROJ-V-10 (E-12) ETC RF ROJ-V-10 RWST TO CHG PUMP SUCT Q1E21V0032A 1 AC 12 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-19 (D-2) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA Q1E21V0032B 1 AC 12 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-19 (D-2) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA Q1E21VO032C 1 AC 12 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-19 (E-2) LTA LA ACCUMULATOR TANK DISCH TO RCS(CL) ETC RF ROJ-V-19 Q1E21VO037A 1 AC 12 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-19 (D-3) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA Q1E21VO037B 1 AC 12 CK S A D-175038/2 C O/C NA ETO RF ROJ-V-19 (D-6) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA OIE21V0037C 1 AC 12 CK S A D-17503812 C O/C NA ETO RF ROJ-V-19 (D-8) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA QIE21V0049 2 A 3/4 GL AO A D-175038/2 C C C PIT 2Y (HV8871) (E-9) STC 0 SIS ACCUMULATOR TEST TO RWST (PEN 29) L-C LJ

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 15 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01E21V0050 2 A 3/4 GL AO A D-1 75038/2 C C C PIT 2Y (HV8961) (E-10) STC a SIS ACCUMULATOR TEST TO RWST (PEN 29) Li-C LJ 01 E21V0052 2 AC 1 CK S A D-175038/2 C C N/A ETC RF ROJ-V-11 (D-9) LJ-C LJ SIS ACCUMULATOR FILL (PEN 49) BDTO RF 01E21V0058 2 AC 1 CK S A D-175038/2 C C NA ETC RF ROJ-V-11 (A-9) Li-C LJ NITROGEN SUPPLY TO ACCUMULATOR TANKS (PEN 63) BDTO RF 01E21V0059 2 A 1 GL AO A D-175038/2 C C C PIT 2Y (HV8880) (A-10) STC a NITROGEN SUPPLY Li-C Li TO ACCUMULATOR TANKS (PEN 63)

Q1E21V0062A 1 C 2 CK S A D-175038/1 0 NA BDTC RF (E-3) ETO RF ROJ-V-13 HHSI TO RCS(CL) 01E21V0062B 1 C 2 CK S A D-175038/1 0 NA BDTC RF (E-3) ETO RF ROJ-V- 13 HHSI TO RCS(CL) 01E21V0062C 1 C 2 CK S A D-175038/1 0 NA BDTC RF (F-3) ETO RF ROJ-V-1 3 HHSI TO RCS(CL)

Q1E21V0063 2 B 3 GA MO A D-175038/1 O/C Al PIT 2Y (MOV8886) (8-6) STO RF ROJ-V-14 CHG (HHSI) PUMPS DISCH TO RCS(CL) STC RF ROJ-V-14 QIE21VO066A 1 C 2 CK S A NA BDTC RF D-175038/1 0 (A-4) ETO RF ROJ-V- 13 CHG (HHSI) PUMPS DISCH TO RCS(CL)

QIE21VO066B 1 C 2 CK S NA BDTC RF A D-175038/1 0 (B-4) ETO RF ROJ-V-1 3 CHG (HHSI) PUMPS DISCH TO RCS(CL)

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 16 of 72 E21 - HHSI/CVCS PlD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks OIE21V0066C 1 C 2 CK S A D-175038/1 C 0 NA BDTC RF (C-4) ETO RF ROJ-V-13 CHG (HHSI) PUMPS DISCH TO RCS(CL) 01E21V0068 2 B 3 GA MO A D-175038/1 C O/C Al PIT 2Y (MOV8886) (H-7) STO RF ROJ-V- 14 CHG (HHSI) PUMP DISCH TO RCS(HL) STC RF ROJ-V-14 O1E21V0072 2 B 3 GA MO A D-175038/1 C O/C Al PIT 2Y (MOV8884) (J-6) STO RF ROJ-V-14 CHG (HHSI) PUMP DISCH TO RCS(HL) STC RF ROJ-V-14 Q1E21VO076A 1 AC 6 CK S A D-175038/1 C O/C NA ETO RF ROJ-V-21 (F-4) LTA LA WATER FROM RESIDUAL HX TO SI TO RCS LOOP 1 ETC RF ROJ-V-21 Q1E21V0076B 1 AC 6 CK S A D-175038/1 C O/C NA ETO RF ROJ-V-21 (G-4) ETC RF ROJ-V-21 WATER FROM RESIDUAL HX TO SI TO RCS LOOP 2 LTA LA QIE21VO077A 1 AC 6 CK S A D-175038/1 C O/C NA ETO RF ROJ-V-18 (F-2) ETC RF ROJ-V-18 HHSI/LHSI AND RHR TO RCS HL LOOP 1 LTA LA Q1E21VO077B 1 AC 6 CK S A D-175038/1 C O/C NA ETO RF ROJ-V-18 (G-2) ETC RF ROJ-V-18 HHSI/LHSI AND RHR TO RCS HL LOOP 2 LTA LA 01E21V0077C 1 AC 6 CK S A D-1 75038/1 C O/C NA ETC RF ROJ-V-18 (G-1) LTA LA HHSI/LHSI AND RHR TO RCS HL LOOP 3 ETO RF ROJ-V-18 Q1E21VO078A 1 C 2 CK S A D-175038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL O1E21V0078B 1 C 2 CK S A D-175038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V- 13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 17 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks IE21V0078C 1 C 2 CK S A D-175038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL 0IE21V0079A I C 2 CK S A D-175038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL Q1E21V0079B 1 C 2 CK S A D-175038/1 C 0 NA BDTC RF (G-2) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL QIE21VO079C 1 C 2 CK S A D-1 75038/1 C 0 NA BDTC RF (G-2) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL Q1E21VO091 2 A 1 GL AO A D-175038/2 C C C PIT 2Y (HV8860) (D-10) STC a SIS ACCUMULATOR TANKS FILL (PEN 49) JU-C LJ QIE21VO115A 2 AC 2 CK S A D-175039/1 0 O/C NA ETO a (G-2) LJ-C LT CVCS SEAL INJECTION TO RCP (PEN 27) ETC RF ROJ-V-15 OIE21VO115B 2 AC 2 CK S A D-1 75039/1 0 O/C NA ETO Q (G-2) ETC RF ROJ-V-15 CVCS SEAL INJECTION TO RCP (PEN 25) U-C LT QIE21VO1I5C 2 AC 2 CK S A D-175039/1 0 O/C NA ETO 0 (G-2) ETC RF ROJ-V-15 CVCS SEAL INJECTION TO RCP (PEN 26) LU-C LT 0IE21V0119 2 AC 3 CK S A D-175039/1 0 O/C NA ETO a (B-11) ETC RF ROJ-V-12 CVCS CHARGING PUMP DISCHARGE TO REGENERATIVE HX. U-C U QIE21VO121A 2 C 2 CK S A D-175039/6 O/C O/C NA ETPO ARFO (C-6) ETO RF ROJ-V-23 1A CHG PUMP MIN FLOW LINE CHECK VALVE ETC 0

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 18 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E21VO121B 2 C 2 CK S A D-175039/6 O/C O/C NA ETPO ARFD (E-6) ETO RF ROJ-V-23 1B CHG PUMP MIN FLOW LINE CHECK VALVE ETC Q Q1E21VO121C 2 C 2 CK S A D-175039/6 O/C O/C NA ETPO ARFD (G-6) ETO RF ROJ-V-23 1C CHG PUMP MIN FLOW LINE CHECK VALVE ETC a OIE21V0122A 2 C 3 CK S A D-175039/6 O/C O/C NA ETO RF ROJ-V-16 (C-5) ETC Q 1A CHARGING PUMP DISCHARGE Q1E21V0122B 2 C 3 CK S A D-175039/6 O/C O/C NA ETO RF ROJ-V-16 (E-5) ETC 0 18 CHARGING PUMP DISCHARGE Q1E21V0122C 2 C 3 CK S A D-175039/6 O/C O/C NA ETO RF ROJ-V-16 (G-5) ETC Q 1C CHARGING PUMP DISCHARGE Q1E21VO210 2 C 2 CK S A D-175039/6 C 0 v NA ETO CSD/RF CSJ-V-07 (G-10) BDTC RF CVCS BA FILTER TO CHARGING PUMP SUCTION C

Q1E21V0213 2 AC 3/4 CK S A D-175039/1 C )/C NA ETC RF ROJ-V-20 (D-11) LJ-C Li RCP SEAL TO SEAL WATER HX (PEN 28) ETO RF ROJ-V-20 C C 0IE21V0220A 3 C 2 CK S A D- 175039/3 )/C NA ETO CSD/RF CSJ-V-10 (F-5) ETC 0 BORON TRANSFER PUMP DISCHARGE LINE CHECK VALVE (C

GIE21VO220B 3 C 2 CK S A D- 175039/3 C )/C NA ETO CSD/RF CSJ-V-10 (H-5) ETC a BORON TRANSFER PUMP DISCHARGE LINE CHECK VALVE Q1E21V0249A 2 A 3 GA MO A D-175039/1 0 Al PIT 2Y C

(MOV8112) (C- 1i) STC RF ROJ-V-17 RCP SEAL TO SEAL WATER HX (PEN 28) LJ-C Li

Joseph M. Farley Nuclear PlantIST Program Unit I Page 19 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01E21V02498 2 A 3 GA MO A D-175039/1 0 C Al STC RF ROJ-V-17 (MOV8100) (C-11) Li-C LJ RCP SEAL TO SEAL WATER HX (PEN 28) PIT 2Y 01E21V0251 2 C 2X3 SR S A D-175039/1 C O/C NA ETSP T (C-10)

RCP SEAL WATER RETURN LINE RELIEF QIE21V0253A 2 A 2 GL AO A D-175039/1 O/C C C PIT 2Y (HV8149A) (A-7) STC CSD/RF CSJ-V-06 LETDOWN ORFICE ISO (PEN 23) Li-C Li Q1E21V0253B 2 A 2 GL AO A D-175039/1 O/C C C PIT 2Y (HV81498) (A-7) STC CSD/RF CSJ-V-06 LETDOWN ORIFICE ISO (PEN 23) Li-C Li Q1E21V0253C 2 A 2 GL AO A 0-175039/1 O/C C C PIT 2Y (HV8149C) (A-6) STC CSD/RF CSJ-V-06 LETDOWN ORIFICE ISO (PEN 23) U-C Li QIE21V0254 2 A 3 GL AO A D-175039/1 0 C C PIT 2Y (HV8152) (A-11) STC CSD/RF CSJ-V-08 LETDOWN LINE CTMT ISO (PEN 23) Li-C I_

QIE21V0255 2 AC 2X3 SR S A D-175039/1 C O/C NA ETSP T (A-7) Li-C Li LETDOWN ORIFICE RELIEF (PEN 23)

OIE21V0257 2 A 3 GA MO A 0 0-175039/6 C Al PIT 2Y (MOV8107) (B-1) STC CSD/RF CSJ-V-08 CVCS CHG PUMP DISCH TO REGENERATIVE HX (PEN 24) Li-C Li 01E21V0258 2 A 3 GA MO A D-175039/6 0 C Al STC CSD/RF CSJ-V-08 (MOV8108) (B-2) I_-C Li CVCS CHG PUMP DISCH TO REGENERATIVE HX (PEN 24) PIT 2Y QIE21VO259A 2 B 2 GL MO A D-175039/6 0 o/C Al PIT 2Y (MOV8109A) (B-5) STO 0 CHG PUMP MINI FLOW LINE ISO VALVE STC a

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 20 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIE21V0259B 2 B 2 GL MO A D-175039/6 0 O/C Al STO Q (MOV8109B) (D-5) STC Q CHG PUMP MINI FLOW LINE ISO VALVE PIT 2Y Q1 E21V0259C 2 B 2 GL MO A D- 175039/6 0 O/C Al PIT 2Y (MOV8109C) (F-5) STC Q CHG PUMP MINI FLOW LINE ISO VALVE STO 0 Q1E21V0263A 2 AC 3/4X1 SR S A D-175039/6 C O/C NA ETSP T (C-9) Li-C LJ 0.75 INCH RELIEF SIS-RHR HX TO CHG PUMP SUCTION (PEN 59)

Q1E21V0263B 2 AC 3/4X1 SR S A D-175039/6 C O/C NA ETSP T (H-8) Li-C U 0.75 INCH RELIEF SIS-RHR HX TO CHG PUMP SUCTION (PEN 59)

Q1E21V0264 2 B 2 GL MO A D-175039/6 C O/C Al PIT 2Y (MOV8104) (G-10) STO a EMERGENCY BORATE TO CHG PUMP STC Q 01E21V0265 2 B 3 GL MO A D-175039/2 0 O/C Al PIT 2Y (MOV8106) (H-4) STO CSD/RF CSJ-V-1 1 CHARGING PUMP MINI FLOW COMMON LINE ISO VALVE STC CSD/RF CSJ-V-11 O1E21V0324A 2 B 8 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8130A) (E-8) STO a CHG PUMP SUCTION HEADER ISOLATION VALVE STC Q Q1E21V0324B 2 B 8 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV81306) (E-8) STC 0 CHG PUMP SUCTION HEADER ISOLATION VALVE STO 0 Q1E21V0325A 2 B 8 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8131A) (G-8) STO 0 CHG PUMP SUCTION HEADER ISOLATION VALVE STC a

Joseph M. FarleyNuclear Plant IST Program Unit I Page 21 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR(CSJ/ROJ Remarks 01 E21V0325B 2 B 8 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8131 B) (G-6) STO Q CHG PUMP SUCTION HEADER ISOLATION VALVE STC Q Q1E21V0326A 2 B 4 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8132A) (D-5) STO RF ROJ-V-22 CHG PUMP DISCHARGE STC RF ROJ-V-22 Q1E21V0326B 2 B 4 GA MO A D-175039/6 0 O/C Al STO RF ROJ-V-22 (MOV8132B) (E-5) STC RF ROJ-V-22 CHG PUMP DISCHARGE PIT 2Y OIE21V0327A 2 B 4 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8133A) (F-5) STC RF ROJ-V-22 CHG PUMP DISCHARGE STO RF ROJ-V-22 0IE21V0327B 2 B 4 GA MO A D-175039/6 0 O/C Al PIT 2Y (MOV8133B) (F-5) STO RF ROJ-V-22 CHG PUMP DISCHARGE STC RF ROJ-V-22 01E21V0336A 2 B 8 GA MO A D-175039/6 C O/C Al STC CSD/RF CSJ-V-09 (LCV115B) (D-9) PIT 2Y CHG PUMP SUCTION FROM RWST STO CSD/RF CSJ-V-09 OIE21V0336B 2 B 8 GA MO A D-175039/6 C O/C Al STC CSD/RF CSJ-V-09 (LCV115D) (G-9) PIT 2Y CHG PUMP SUCTION FROM RWST STO CSD/RF CSJ-V-09 GIE21V0376A 2 B 4 GA MO A D-175039/2 0 C Al PIT 2Y (LCV115C) (H-8) STC CSD/RF CSJ-V-09 VCT OUTLET ISO QIE21V0376B 2 B 4 GA MO A D-175039/2 0 C Al PIT 2Y (LCV11SE) (H-8) STC CSD/RF CSJ-V-09 VCT OULTET ISO QIE21V0565A 2 B 3 GL AO A D-175039/1 0 C C PIT 2Y (HV8175A) (A-i10) STC CSD/RF CSJ-V-08 CVCS LETDOWN LINE ISOLATION

JosephM. FarleyNuclear PlantIST Program Unit 1 Page 22 of 72 E21 - HHSI/CVCS PID Valve ID CC Cat Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1E21V0565B 2 B 3 GL AO A D-175039/1 0 C C PIT 2Y (HV8175B) (A-1i01 STC CSD/RF CSJ-V-08 CVCS LETDOWN LINE ISOLATION

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 23 of 72 E22 - Reactor Cavity Post-LOCA Dilution PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP T'est Freq RR/CSJ/ROJ Remarks Q1E22V0001A Aug B 2 1/2 GA MO A D-175019 C 0 Al PIT 2Y (MOV3872A) (D-5) SITO 0 1A RX CAVITY H2 DILUTION FAN DAMPER 01E22VO001B Aug 8 2 1/2" GA MO A D-175019 C 0 AI I'IT 2Y?

(MOV3872B) (E-5) S~TO Q 1B RX CAVITY H2 DILUTION FAN DAMPER

Joseph M. FarleyNuclear Plant IST Program Unit I Page 24 of 72 E23 - Post Accident Ctmt Vent and Sample PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01E23V0002 2 A 6 GL MO A D-175019 LC C Al STC a (MOV3740) (C-10) LU-C LU CTMT POST-LOCA VENT (PEN 103) PIT 2Y QIE23V0003 2 A 6 GL MO A D-175019 LC C Al PIT 2Y (MOV3530) (C-9) STC a CTMT POST-LOCA VENT (PEN 103) U-C LU Q1E23V0022A 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3528A) (B-8) STC 0 CTMT POST-LOCA SAMPLE (PEN 67) LU-C U Q1E23V0022B 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3528B) (C-9) STC Q CTMT POST-LOCA SAMPLE (PEN 67) U-C LJ Q1E23V0022C 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3528C) (D-8) STC Q CTMT POST-LOCA SAMPLE (PEN 61A) U-C U 01E23V0022D 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV35280) (D-9) STC 0 CTMT POST-LOCA SAMPLE (PEN 61A) U-C U 0IE23V0023A 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3739A) (C- 10) STC 0 CTMT AIR SAMPLE (PEN 67) U-C LJ QIE23V0023B 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3739B) (D-10) STC 0 CTMT AIR SAMPLE (PEN 61A) U-C U QIE23V0024A 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3745A) (G-10) STC 0 CTMT AIR SAMPLE RETURN (PEN 66) U-C U Q1E23V0024B 2 A 3/4 GL MO A D-175019 LC C Al STC 0 (MOV3745B) (F-10) U-C U CTMT AIR SAMPLE RETURN (PEN 61B) PIT 2Y

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 25 of 72 E23 - PostAccident Ctmt Vent and Sample PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks 01E23V0025A 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3835A) (G-9) STC Q CTMT POST-LOCA SAMPLE RETURN (PEN 66) LJ-C LJ 0IE23V0025B 2 A 3/4 GL MO A D-175019 LC C Al PIT 2Y (MOV3835B) (F-9) STC a CTMT POST-LOCA SAMPLE RETURN (PEN 61 B) LJ-C U

Joseph M. Farley NuclearPlant IST Program Unit I Page 26 of 72 G21 - Liquid Waste Disposal PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks N1G21V0222 Aug C 3/4X1 SR S A 0-175004/1 C O/C NA ETSP T (H-9)

CTMT SUMP PUMP RELIEF VALVE (PEN 78) 0IG21HV3376 2 A 3 GL AO A D-175004/1 0 C C PIT 2Y (H-8) STC Q CTMT SUMP PUMP DISCHARGE (PEN 78) U-C U Q1G21HV3377 2 A 3 GL AO A D-175004/1 0 C C PIT 2Y (H-8) STC a CTMT SUMP PUMP DISCHARGE (PEN 78) LJ-C LJ 01G21HV3380 2 A 2 GL AO A D-175004/1 0 C C PIT 2Y (G-8) STC Q CTMT SUMP RECIRCULATION (PEN 33) U-C LJ QIG21VO001 2 A 3/4 D AO A D-175042/1 C C C PIT 2Y (HV7150) (B-5) STC 0 REACTOR COOLANT DRAIN TANK VENT TO WASTE GAS U-C LJ SYSTEM(PEN62)

Q1G21VO005 2 A 3 D M P D-175042/1 LC LC N/A Li-C LU (V7135) (C-11)

RCDT PUMP DISCH CONTROL VALVE BYPASS(PEN31)

QIG21V0006 2 A 3 D AO A D-175042/1 0 C C PIT 2Y (HV7136) (C-10) STC 0 RCDT PUMP DISCH TO RECYCLE HOLDUP TANK(PEN31) Li-C U Q1G21V0064 2 A 3 GL AO A D-175042/1 0 C C PIT 2Y (LCV1003) (C-10) STC 0 RCDT PUMP DISCH CONTROL VALVE(PEN 31) U-C Li QIG21V0082 2 A 3/4 D AO A D-175042/1 0 C C PIT 2Y (HV7126) (C-4) STC a RCDT VENT TO WASTE GAS SYSTEM(PEN 62) U-C U 0IG21V0204 2 AC 2 CK S A D-175004/1 O/C O/C N/A ETO RF ROJ-V-24 (G-9) ETC RF ROJ-V-24 CTMT SUMP RECIRC (PEN 33) JU-C LJ

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 27 of 72 G21 - Liquid Waste Disposal PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 0IG21V0291 2 AC 3/4 CK S A D-175004/1 C O/C N/A ETO RF ROJ-V-25 (H-8) ETC RF ROJ-V-25 i.TrAT S' IMP P1 IMAP flI.r*.ARl-,r LU-C U OIG21V0950 2 AC 3/4xl SR S A D-175042 C O/C NA ETSP T (C-9) U-C U WASTE PROCESSING SYSTEM (PEN 31) RELIEF VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 28 of 72 G24 - Steam GeneratorBlowdown PID Valve ID CC Cat. Size Type Act. AP (CoOrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1G24V0003A 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7614A) (E-3) STC a SG BLOWDOWN ISOLATION VALVE Q1G24V00038 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7614B) (G-3) STC Q SG BLOWDOWN ISOLATION VALVE QIG24V0003C 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7614C) (H-3) STC 0 SG BLOWDOWN ISOLATION VALVE Q1G24V0005A 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7697A) (D-4) STC Q SG BLOWDOWN BLOCK VALVE QIG24VO005B 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7698A) (D-4) STC 0 SG BLOWDOWN BLOCK VALVE 01G24V0005C 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7699A) (D-4) STC a SG BLOWDOWN BLOCK VALVE 01G24V0006A 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7697B) (D-4) STC a SG BLOWDOWN ISOLATION VALVE Q1G24V0006B 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7698B) (D-4) STC 0 SG BLOWDOWN ISOLATION VALVE QIG24V0006C 2 B 2 GL AO A D-175071/1 O/C C C PIT 2Y (HV7699B) (D-4) STC 0 SG BLOWDOWN ISOLATION VALVE

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 29 of 72 G31 - Spent Fuel Pool Cooling pin Valve ID CC Cat. Size Type Act. AP (COOrd) NP SP FP 1rest Freq RR/CSJ/ROJ Remarks I

QIG31VO012 2 A 2 D M P D-1 75043 LC C N/A I J-C Li (B-4)

SPENT FUEL POOL CLEAN-UP TO REACTOR CAVITY(PEN 95)

OIG31V0013 2 AC 2 CK S P D-175043 C C N/A Li-C LJ (B-3)

SPENT FUEL POOL CLEAN-UP TO REACTOR CAVITY(PEN 95)

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 30 of 72 Ni1 - Main Steam PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1N11PV3371A 2 B 6 GL AO A D-175033 C O/C C STC CSD/RF (E-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE Q1N11PV3371B 2 B 6 GL AO A D-175033 C O/C C STC CSD/RF (E-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE Q1 N11PV3371C 2 B 6 GL AO A D-175033 C O/C C STC CSD/RF (E-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE QINllVO001A 2 BC 32 CK AO/S A D-175033/1 0 C C BDTO Normal Ops (HV3369A) (G-7) PIT 2Y MAIN STEAM ISOLATION VALVE STC CSD/RF CSJ-V-12 Q1N11VO001B 2 BC 32 CK AO/S A D-175033/1 0 C C PIT 2Y (HV3369B) (E-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops QIN11V0001C 2 BC 32 CK AO/S A D-175033/1 0 C C PIT 2Y (HV3369C) (B-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q1N11VO002A 2 BC 32 CK AO/S A D-175033/1 0 C C PIT 2Y (HV3370A) (G-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q1N11VO002B 2 BC 32 CK AO/S A D-175033/1 0 C C PIT 2Y (HV3370B) (E-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q1N11V0002C 2 BC 32 CK AO/S A D-175033/1 0 C C PIT 2Y (HV3370C) (B-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q1N11V0003A 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3368A) (G-7) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 31 of 72 Nil - Main Steam PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJIROJ Remarks Q1N11VO003B 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3368B) (E-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS OINI1V0003C 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3368C) (C-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS Q1N11VO003D 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3976A) (G-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS O1N11V0003E 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3976B) (E-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS OIN11VO003F 2 B 3 GA AO A D-175033/1 C C C PIT 2Y (HV3976C) (C-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS 01NI1VO010A 2 C 6X 10 SR S A D-175033/1 C O/C NA ETSP T (G-3)

MAIN STEAM SAFETY OINl1V0010B 2 C 6 X10 SR S A D-175033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY 01NIlVO010C 2 C 6 X 10 SR S A D-175033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY _CT S_-PT OQNilVO0IOD 2 C 6 X 10 SR S A D-175033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY QIN11VO010E 2 C 6 X 10 SR S A D-175033/1 C O/C NA ETSP T (G-5)

MAIN STEAM SAFETY

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 32 of 72 N11 - Main Steam PID Valve ID CC Cat. Size Type Act. AP (Coor) NP SP FP Test Freq RR/CSJ/ROJ Remarks QINIlVOOllA 2 C 6X10 SR S A D-175033/1 C ./C NA ETSP T (0-3)

MAIN STEAM SAFETY QIN11VOO118 2 C 6X10 SR A D-175033/1 O/C NA ETSP (0-4)

MAIN STEAM SAFETY Q1N1lVO011C 2 C 6X10 SR A D-175033/1 O/C NA ETSP (D-4)

MAIN STEAM SAFETY QINI1V0011D 2 C 6 X 10 SR A D-1 75033/1 O/C NA ETSP (D-4)

MAIN STEAM SAFETY QIN11VOO11E 2 C 6X10 SR A D-175033/1 O/C NA ETSP (D-5)

MAIN STEAM SAFETY Q1N11VO012A 2 C 6X10 SR A D-175033/1 O/C NA ETSP (B-3)

MAIN STEAM SAFETY Q1N11VO012B 2 C 6X10 SR A D-175033/1 O/C NA ETSP (B-4)

MAIN STEAM SAFETY Q1N11V0012C 2 C 6 X 10 SR A D-175033/1 O/C NA ETSP (B-4)

MAIN STEAM SAFETY QlN11VO012D 2 C 6 X 10 SR A D-175033/1 O/C NA ETSP T (B-4)

MAIN STEAM SAFETY 0

QIN11VO012E 2 C 6X10 SR O/C A D-175033/1 NA ETSP T (B-5)

MAIN STEAM SAFETY

Joseph M. FarleyNucElar PlantIST Program Unil I Page 33 of 72 N12 - Auxili, ry Steam PID Valve ID CC Cat. Size Type Act. AP (Co0rcd NP SP FP 1rest Freq RR/CSJ/ROJ Remarks 0IN12HV3226 3 B 3 GL AO A D-175033/2 C 0 0 PIT 2Y (D-5) 3TO Q MAIN STEAM TO TDAFW PUMP Qt N12HV3234A 2 B 1 GL AO A D-175033/2 O C C PIT 2Y (G-8) STC a MAIN STM LINE TO TDAFW PUMP WARM-UP LINE 01N12HV3234B 2 B 1 GL AO A D-175033/2 O C C PIT 2Y (C-8) 3TC a MAIN STM LINE TO TDAFW PUMP WARM-UP LINE Q1N12MOV3406 3 B 3 GL MO P D-175033/2 O 0 Al PIT 2Y (D-4)

PUMP TURBINE STEAM FLOW THROTTLE AND TRIP 0IN12VO001A 2 BC 3 SC AO/S A D-175033/2 C O/C 0 ETO Q (HV3235A) (E-8) PIT 2Y MAIN STEAM TO TDAFW PUMP SHUTOFF VALVE ETC 0 QIN12VO001B 2 BC 3 SC AO/S A D-175033/2 C 0/C 0 ETC Q (HV3235B) (D-8) PIT 2Y MAIN STEAM TO TDAFW PUMP SHUTOFF VALVE ETO 0 O1N12VO010A 3 C 4 CK S A D-175033/2 C O/C NA ETPO ARFD (E-6) ETO a MAIN STEAM TO TDAFW PUMP TURBINE ETC RF ROJ-V-26 QIN12VO010B 3 C 4 CK S A D-175033/2 C O/C NA ETPO ARFD (C-6) ETO a MAIN STEAM TO TDAFW PUMP TURBINE ETC RF ROJ-V-26

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 34 of 72 N21/C22 - Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJJROJ Remarks 01C22FCV478 Aug B 14 A AO A D-175073 0 C C PIT 2Y (G-5) STC CSD/RF MAIN FEEDWATER REGULATOR Q1C22FCV479 Aug B 6 GA AO A D-1 75073 0 C C PIT 2Y (F-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS Q1C22FCV488 Aug B 14 A AO A D-175073 0 C C PIT 2Y (D-5) STC CSD/RF MAIN FEEDWATER REGULATOR 01C22FCV489 Aug B 6 GA AO A D-1 75073 0 C C PIT 2Y (D-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS 01C22FCV498 Aug B 14 A AO A D-175073 0 C C PIT 2Y (B-5) STC CSD/RF MAIN FEEDWATER REGULATOR O1C22FCV499 Aug B 6 GA AO A D-175073 0 C C PIT 2Y (A-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS O1N21VO001A 2 BC 14 SC MO/S A D-175073 0 C NA PIT 2Y (MOV3232A) (G-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops Q1N21V0001B 2 BC 14 SC MO/S A D-175073 0 C NA PIT 2Y (MOV3232B) (E-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops OIN21VOOIC 2 BC 14 SC MO/S A D-175073 0 C NA PIT 2Y (MOV3232C) (B-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 35 of 72 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks N1N23V0001 Aug C 3 CK S A D-175007 C 0 NA ETO 0 (F-4)

TDAFW PUMP MINI FLOW CHECK VALVE N1N23V0005 Aug C 3 CK S A D-175007 C 0 NA ETO Q (C-6)

MDAFW PUMP MINI FLOW N1N23V0009 Aug C 3 CK S A D-175007 C 0 NA ETO 0 (D-6)

MDAFW PUMP MINI FLOW N1N23V0013 Aug C 6 CK S A D-175007 C 0 NA ETO Q (F-2)

AFW PUMPS TO CONDENSATE STORAGE TANK OQN23HV3227A 3 B 3 GL AO A D-175007 0 0 0 PIT 2Y (B-8) STO a MDAFW PUMP TO SG 1A FCV QIN23HV3227B 3 B 3 GL AO A D-175007 0 0 0 PIT 2Y (D-8) STO a MDAFW PUMP TO SG 1B DISCHARGE FCV Q1N23HV3227C 3 B 3 GL AO A D-175007 0 0 0 PIT 2Y (G-8) STO a MDAFW PUMP TO SG 1C DISCHARGE FCV QIN23HV3228A 3 B 3 GL AO A D-175007 0 0 C PIT 2Y (C-8) STO a TDAFW PUMP TO SG IA FCV O1N23HV3228B 3 B 3 GL AO A D-175007 C C 0 PIT 2Y (F-8) STO a TDAFW PUMP TO SG lB FCV O1N23HV3228C 3 B 3 GL AO A D-1 75007 0 0 C PIT 2Y (H-8) STO a TDAFW PUMP TO SG 1C FCV

Joseph U. FarleyNuclear Plant IST Program Unit 1 Page 36 of 72 N23 -Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1N23VO002A 3 C 4 CK S A D-175007 C O/C NA ETO CSDIRF CSJ-V-15 (B-6) ETC Q MDAFW 1A DISCHARGE TO SG 01N23V0002B 3 C 4 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (E-6) ETC Q MDAFW 16 DISCHARGE TO SG Q1N23VO002C 3 C 4 CK S A D-175007 C 0 NA BDTC RF (B-9) ETO CSD/RF CSJ-V-15 MDAFW DISCHARGE TO SG 1A 01N23V0002D 3 C 4 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (C-9) ETC CSDIRF CSJ-V-16 TDAFW DISCHARGE TO SG 1A 01N23V0002E 3 C 4 CK S A D-175007 C 0 NA BDTC RF (D-9) ETO CSD/RF CSJ-V-15 M DAFW DISCHARG E TO SG IB 0-_CA E_______ ____D17 QIN23V0002F 3 C 4 CK S A 0-175007 C 0/C NA ETC CSD/RFCSJ-V-16 (F-9) ETO CSD/RF CSJ-V-15 TDAFW DISCHARGE TO SG 1B C1N23V0002G 3 C 4 CK S A D-175007 C 0 NA ETO CSD/RF CSJ-V-15 (G-9) BDTC RF MDAFW DISCHARGE TO SG 1C Q1N23VO002H 3 C 4 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (H-9) ETC CSD/RF CSJ-V-16 TDAFW DISCHARGE TO SG 1C Q1N23V0003 3 C 6 CK S A D-175007 C 0 NA BDTC RF (G-6) ETO CSD/RF CSJ-V-15 TDAFW DISCHARGE TO SG 01N23V0006 3 C 8 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (H-3) ETC CSD/RF CSJ-V-17 TDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 37 of 72 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJIROJ Remarks 01N23V0007A 3 C 6 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (B-3) ETC CSD/RF CSJ-V-17 MDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK 0IN23V0007B 3 C 6 CK S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (E-3) ETC CSD/RF CSJ-V-17 MDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK OIN23V0011A 2 C 4 CK MO/S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350A) (B-10) STC Q AUX FEEDWATER TO SG 1A PIT 2Y O1N23VO011B 2 C 4 CK MO/S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350B) (D-10) STC Q AUX FEEDWATER TO SG 1B PIT 2Y Q1N23VO011C 2 C 4 CK MO/S A D-175007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350C) (G-10) STC 0 AUX FEEDWATER TO SG 1C PIT 2Y OIN23V0013A 3 B 6 GA MO A D-175007 C 0 Al PIT 2Y (MOV3210A) (A-3) STO RF ROJ-V-27 MDAFW PUMP SW INLET Q1N23V0013B 3 B 6 GA MO A D-175007 C 0 Al PIT 2Y (MOV32108) (D-3) STO RF ROJ-V-27 MDAFW PUMP SW INLET 01N23V0014A 3 B 8 GA MO A D-175007 C 0 Al PIT 2Y (MOV3209A) (A-2) STO RF ROJ-V-27 MDAFW PUMP SW INLET Q1N23V0014B 3 B 8 GA MO A D-175007 C 0 Al STO RF ROJ-V-27 (MOV3209B) (D-2) PIT 2Y MDAFW PUMP SW INLET Q1N23V0014C 3 B 8 GA MO A D-175007 C 0 Al PIT 2Y (MOV3216) (G-3) STO RF ROJ-V-27 TDAFW PUMP SW INLET

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 38 of 72 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1N23V0025A 3 B 4 GA MO A D-175007 0 C Al PIT 2Y (MOV3764A) (B-7) STC a MDAFW PUMP TO SG 1A Q1N23V0025B 3 B 4 GA MO A D-175007 0 C AI PIT 2Y (MOV3764B) (D-7) STC 0 MDAFW PUMP TO SG 1B 01N23V0025C 3 B 4 GA MO A D-175007 0 C Al PIT 2Y (MOV3764C) (F-7) STC 0 MDAFW PUMP TO SG IC 01N23V0025D 3 B 4 GA MO A D-175007 0 C Al STC Q (MOV3764D) (D-7) PIT 2Y MDAFW PUMP TO SG 1B Q1N23V0025E 3 B 4 GA MO A D-175007 0 C Al PIT 2Y (MOV3764E) (B-7) STC Q MDAFW PUMP TO SG 1A Q1N23V0025F 3 B 4 GA MO A D-1 75007 0 C Al PIT 2Y (MOV3764F) (G-7) STC 0 MDAFW PUMP TO SG 1C QIN23VOO68A 3 C 1.5 SR S A D-175007 C O/C NA ETSP T (PSV2922A) (B-4)

IA MDAFW PUMP SUCTION LINE RELIEF VALVE 01N23V0068B 3 C 1.5 SR S A D-175007 C O/C NA ETSP T (PSV2922B) (D-4) 1B MDAFW PUMP SUCTION LINE RELIEF VALVE Q1N23V0068C 3 C 1.5 SR S A D-175007 C O/C NA ETSP T (PSV2922C) (G-4)

TDAFW PUMP SUCTION LINE RELIEF VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 39 of 72 N25 - Chemical Injection PID Valve ID CC Cat. Size Type Act. AP (COOrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks O1N25VO001A 2 B 1/2 GL AO A D-175000/1 O/C C C PIT 2Y (HV3772A) (B-I 1) STC a CHEMICAL INJECTION INTO FEEDWATER QIN25VO001B 2 B 1/2 GL AO A D-175000/1 O/C C C PIT 2Y (HV3772B) (D-11) STC Q CHEMICAL INJECTION INTO FEEDWATER 0IN25VO001C 2 B 1/2 GL AO A D-175000/1 O/C C C PIT 2Y (HV3772C) (F-11) STC a CHEMICAL INJECTION INTO FEEDWATER

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 40 of 72 P11 - DemineralizedWater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Irest Freq RR/CSJ/ROJ Remarks I

Q1P11VO001 2 A 3 GL AO P D-175047 C C C STC Q (HV3659) (H-10) PIT 2Y DEMIN WATER TO RPV HEAD STORAGE STAND (PEN 82) u-C U Q1P1IVO002 2 AC 3 CK S P D-175047 C C NA Li-C LJ (H-8)

DEMIN WATER TO RPV HEAD STORAGE STAND (PEN 82)

Joseph M. FarleyNuclear Plant IST Program Unit I Page 41 of 72 P13 - ContainmentPurge Plo Valve ID CC Cat. Size Type Act. AP (COOrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1 P13V0281 2 A 48 B AO A D-175010/2 C C C PIT 2Y (HV3198D) (F-3) STC CSD/RF CSJ-V-18 PURGE SUPPLY DAMPER (PEN 12) Ju-C U 01P13V0282 2 A 48 B AO A D-175010/1 C C C PIT 2Y (HV3197) (G-10) STC CSD/RF CSJ-V-18 PURGE SUPPLY DAMPER (PEN 12) u-C U Q1P13V0283 2 A 48 B AO A D-175010/1 C C C PIT 2Y (HV3196) (E-10) U-C Li CTMT PURGE EXHAUST (PEN 13) STC CSD/RF CSJ-V-18 Q1P13V0284 2 A 48 B AO A D-17501012 C C C PIT 2Y (HV3198A) (D-3) STC CSD/RF CSJ-V-18 CTMT PURGE EXHAUST (PEN 13) UI-C U Q1P13VO301 2 A 8 B AO A D-175010/2 0 C C PIT 2Y (HV2866C) (F-3) U-C LU CTMT MINI-PURGE SUPPLY (PEN 12) STC Q 01P13V0302 2 A 8 B AO A D-175010/1 0 C C PIT 2Y (HV2866D) (G-10) STC a CTMT MINI-PURGE SUPPLY (PEN 12) U-C U 01P13V0303 2 A 8 B AO A D-175010/2 0 C C PIT 2Y (HV2867C) (D-3) STC a CTMT MINI-PURGE EXHAUST (PEN 13) U-C U 01P13V0304 2 A 8 B AO A D-175010/1 0 C C PIT 2Y (HV2867D) (E-10) STC 0 CTMT MINI-PURGE EXHAUST (PEN 13) U-C U

Joseph M. FarleyNuclearPlantIST Program Unit 1 Page 42 of 72 P15 - Sampling PID Valve 1D CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01P15HV3179A 2 B 3/8 GL AO A 0-175009/2 O/C C C PIT 2Y IA*STC 0

/A'-11ST SG 1A BLOWDOWN LOWER ISOLATION VALVE Q1P15HV3179C 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (A-3) STC a SG IA BLOWDOWN SAMPLE ISOLATION VALVE Q1P15HV3180A 2 B 3/8 GL AO A D- 175009/2 O/C C C PIT 2Y (G-3) STC a SG IB BLOWDOWN LOWER ISOLATION VALVE Q1P15HV3180C 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (C-3) STC Q SG 1B BLOWDOWN SAMPLE ISOLATION VALVE O1P15HV3181A 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (E-3) STC Q SG 1C BLOWDOWN LOWER ISOLATION VALVE QIP15HV3181C 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (E-3) STC Q SG 1C BLOWDOWN SAMPLE ISOLATION VALVE 0P1P5HV3328 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (A-3) STC Q SG 1A BLOWDOWN SAMPLE ISOLATION VALVE Q1P15HV3329 2 B 3/8 GL AO A D-175009/2 O/C C C PIT 2Y (C-3) STC Q SG 1B BLOWDOWN SAMPLE ISOLATION VALVE OIP15HV3330 2 B 3/8 GL AO A D- 175009/2 O/C C C PIT 2Y (E-3) STC Q SG 1C BLOWDOWN SAMPLE ISOLATION VALVE 0IP15HV3334 2 A 3/8 GL AO A D-175009/1 C C C PIT 2Y (G-5) STC Q ACCUMULATOR TANKS SAMPLE (PEN 50) LJ-C U

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 43 of 72 P15 - Sampling P1D Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP rest Freq RR/CSJ/ROJ Remarks 01P15HV3766 2 A 3/8 GL AO A D-175009/1 C C C PIT 2Y (G-4) TC 0 ACCUMULATOR TANKS SAMPLE (PEN 50) LJ-C U Q1 P15SV3103 2 A 3/8 GL SO A D-175009/1 0 C C PIT 2Y (A-3) 3TC 0 RCS PRESSURIZER LIQUID SAMPLE(PEN 57) LJ-C U 01P15SV3104 2 A 3/8 GL SO A D-175009/2 0 C C PIT 2Y (F-2) 3TC Q PRESSURIZER STEAM SAMPLE TO GFFD(PEN 5'6) 1J-C LJ 0IP15SV3331 2 A 3/8 GL SO A D-175009/2 0 C C PIT 2Y (F-4) iTC 0 PRESSURIZER STEAM SAMPLE LINE CTMT ISO(IPEN 56) L.J-C U 01 P15SV3332 2 A 3/8 GL SO A D-175009/1 0 C C PIT 2Y (A-5) iTC Q PRESSURIZER LIQUID SAMPLE TO GFFD(PEN 577) L_-C LJ QIP15SV3333 2 A 3/8 GL SO A D-175009/1 0 C C PIT 2Y (C-5) iTC Q RCS (HL) SAMPLE TO GFFD(PEN58) J-C LJ Q1P15SV3765 2 A 3/8 GL SO A D-175009/1 0 C C PIT 2Y 3TC (C-4) 0 RCS (HL) SAMPLE TO GFFD (PEN 58) I -J-C LJ

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 44 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks NIP16VO718A Aug C 2.5 VR S A D-170119/4 C O/C C ETO RF (B-10) ETC RF SW VACUUM BREAKERS - TURBINE BLDG HVAC NIP16VO718B Aug C 2.5 VR S A D-170119/4 C O/C C ETO RF (B-10) ETC RF SW VACUUM BREAKERS -TURBINE BLDG HVAC 01P16VO003A 3 B 20 B MO P D-175003/1 0 0 Al PIT 2Y (MOV3130A) (E-2)

SW TO CCW HX INLET LINE ISO VALVE Q1P16VO003B 3 B 20 B MO P D-175003/1 0 0 Al PIT 2Y (MOV3130B) (F-2)

SW TO CCW HX INLET LINE ISO VALVE 01 P16VO003C 3 B 20 B MO P D-175003/1 0 0 Al PIT 2Y (MOV3130C) (H-3)

SW TO CCW HX INLET LINE ISO VALVE QIP16VO010A 2 B 12 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3019A) (A-7) STO 0 SW TO CTMT AIR COOLER LINE ISO VALVE STC 0 Q1P16V0010B 2 B 12 B MO A D-175003/1 0 O/C Al STO a (MOV3019B) (C-7) STC Q SW TO CTMT AIR COOLER LINE ISO VALVE PIT 2Y Q1P16V0010C 2 B 12 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3019C) (E-7) STO Q SW TO CTMT COOLER LINE ISO VALVE STC a 01P16VO010D 2 B 12 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3019D) (F-7) STC Q SW TO CTMT COOLER LINE ISO VALVE STO a Q1P16VO011A 3 C 1 1/2X2 SR S A D-175003/1 C O/C NA ETSP T (PSV3020A) (A-8)

SW SUPPLY TO CTMT COOLERS RELIEF

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 45 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Cooro) NP SP FP Test Freq RRICSJ/ROJ Remarks QIP16V011B 3 C 1 1/2X2 SR S A D-175003/1 C O/C NA ETSP T (PSV3020B) (C-B)

SW SUPPLY TO CTMT COOLERS RELIEF Q1P16V0011C 3 C 1 1/2X2 SR S A D-175003/1 C O/C NA ETSP T (PSV3020C) (E-8)

SW SUPPLY TO CTMT COOLERS RELIEF QIP16VWI1ID 3 C 1 1/2X2 SR S A D-175003/1 C O/C NA ETSP T (PSV3020D) (F-8)

SW SUPPLY TO CTMT COOLERS RELIEF Q1P16V0015A 3 C 3/4 X 1 SR S A D-175003/2 C O/C NA ETSP T (PSV3142A) (B-3)

AFW PUMP ROOM COOLER RELIEF Q1P16V0015B 3 C 3/4 X1 SR S A D-175003/2 C O/C NA ETSP T (PSV3142B) (D-3)

AFW PUMP ROOM COOLER RELIEF Q1P16V0020A 3 C 3/4 X I SR S A D-175003/2 C O/C NA ETSP T (PSV3137A) (B-7)

RHRILHSI PUMP ROOM COOLER RELIEF 01P16V0020B 3 C 3/4X1 SR S A D-175003/2 C 0/C NA ETSP T (PSV31378) (8-7)

RHR/LHSI PUMP ROOM COOLER RELIEF Q1P16VO025A 3 C 3/4 X 1 SR A D-175003/2 C O/C NA ETSP T (PSV3138A) (C-7)

S CCW PUMP ROOM COOLER RELIEF QIP16VO025B 3 C 3/4 X1 SR A D-175003/2 C O/C NA ETSP T (PSV3138B) (D-7)

CCW PUMP ROOM COOLER RELIEF QIP16VO035A 3 C 3/4 X 1 SR S A D-175003/2 C O/C NA ETSP T (PSV3139A) (E-7)

CTMT SPRAY PUMP ROOM COOLER RELIEF

Joseph M. Farley Nuclear Plant IST Program Unit 1 Page 46 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1P16V0035B 3 C 3/4 X 1 SR S A D-175003/2 C O/C NA ETSP T (PSV3139B) (F-7)

CTMT SPRAY PUMP ROOM COOLER RELIEF Q1P16VO043A 2 B 10 B MO A D-175003/1 C O/C Al STO a (MOV3024A) (A-10) STC Q SERVICE WATER EMERG FROM CTMT COOLER 1A PIT 2Y 01P16VO043B 2 B 10 B MO A D-175003/1 C O/C Al PIT 2Y (MOV3024B) (C-10) STO Q SERVICE WATER EMERG FROM CTMT COOLER 1B STC 0 01P16V0043C 2 B 10 B MO A D-175003/1 C O/C Al PIT 2Y (MOV3024C) (E-10) STO Q SERVICE WATER EMERG FROM CTMT COOLER IC STC Q QIP16V0043D 2 B 10 B MO A D-175003/1 C O/C Al PIT 2Y (MOV3024D) (F-10) STO Q SERVICE WATER EMERG FROM CTMT COOLER 1D STC Q Q1P16V0044A 2 B 6 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3023A) (B-10) STO Q SW FROM CTMT AIR COOLERS STC Q GIP16V0044B 2 B 6 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3023B) (D-10) STC a SW FROM CTMT AIR COOLERS STO 0 QIP16VO044C 2 B 6 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3023C) (E-10) STO Q SW FROM CTMT AIR COOLERS STC 0 Q1P16V0044D 2 B 6 B MO A D-175( )03/1 0 O/C Al PIT 2Y (MOV3023D) (G-10) STO Q SW FROM CTMT AIR COOLERS STC 0 Q1P16V0052 3 B 10 B MO A D-175()03/2 0 C Al PIT 2Y (MOV3149) (E-2) STC 0 SW TO SG BLOWDOWN HX AND BTRS CHILLER UNITS

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 47 of 72 P16 - Service Water MD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01P16V0064 3 B 10 B MO A D-175003/2 0 C Al PIT 2Y (MOV3150) (E-4) STC a SW FROM SG BLOWDOWN HX AND BTRS CHILLER UNITS 01P16VO069A 3 C 30 CK S A D-170119/2 0 0 NA ETO 0 (C-10) BDTC RF AUX BLDG SW DISCHARGE LINE CHECK VALVE A TRAIN QIP16V0069B 3 C 30 CK S A D-170119/2 0 0 NA ETO 0 (A-10) BDTC RF AUX BLDG SW DISCHARGE LINE CHECK VALVE B TRAIN Q1 PI6VO070A 3 C 16 CK S A D-175003/1 0 0 NA ETO Q (C-6) BDTC 0 SW TO CTMT COOLERS HEADER CHECK VALVE A TRAIN G1P16VOO70B 3 C 16 CK S A D-175003/1 0 0 NA ETO 0 (E-6) BDTC 0 SW TO CTMT COOLERS HEADER CHECK VALVE B TRAIN QIP16VO071 2 A 6 B MO A D-175003/2 0 C Al PIT 2Y (MOV3135) (B-9) STC 0 SW TO RCP MOTOR COOLERS LI-C LJ Q1P16VO072 2 A 6 B MO A D-175003/2 0 C Al PIT 2Y (MOV3134) (B-12) STC 0 SW RETURN FROM RCP MOTOR COOLERS LJ-C LJ Q1P16V0075 2 AC 6 CK S A D-175003/2 0 C NA ETC RF ROJ-V-28 (B-9) Li-C LI SW TO RCP MOTOR COOLERS BDTO Normal Ops 01P16V0081 2 A 6 B MO A D-175003/2 0 C Al PIT 2Y (MOV3131) (B-12) STC a SW RETURN FROM RCP MOTOR COOLERS LI-C LI 01P16V0203 2 AC 3/4 X 1 SR A D-175003/2 C O/C NA ETSP T (PSV3397) (B-12) LI-C LI CTMT PEN 32 THERMAL RELIEF VALVE

Joseph M. FarleyNuclearPlantIST Program Unit I Page 48 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Cooed) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIP16V0204 2 AC 3/4 X1 SR S A D-175003/2 C O/C NA ETSP T (PSV3401) (B-9) LJ-C Li CTMT PEN 60 THERMAL RELIEF VALVE Q1P16V0206A 2 C 12 CK S A D-175003/1 0 O/C NA ETPO ARFD (A-7) ETO a SW TO CTMT COOLER 1A CHECK VALVE ETC RF ROJ-V-30 QIP16VO206B 2 C 12 CK S A D-175003/1 0 O/C NA ETPO ARFD (C-7) ETO 0 SW TO CTMT COOLER 1B CHECK VALVE ETC RF ROJ-V-30 QIP16VO206C 2 C 12 CK S A D-175003/1 0 O/C NA ETPO ARFD (E-7) ETO 0 SW TO CTMT COOLER 1C CHECK VALVE ETC RF ROJ-V-30 Q1PI6V0206D 2 C 12 CK S A D-175003/1 0 O/C NA ETPO ARFD (F-7) ETO Q SW TO CTMT COOLER 1D CHECK VALVE ETC RF ROJ-V-30 01P16V0207A 2 B 10 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3441A) (A-9) STO Q SW FROM CTMT AIR COOLERS LINE ISO VALVE STC 0 QIP16V0207B 2 B 10 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3441 B) (C-9) STO 0 SW FROM CTMT AIR COOLERS LINE ISO VALVE STC 0 Q1P16V0207C 2 B 10 B MO A D-175003/1 0 O/C Al PIT 2Y (MOV3441C) (E-9) STO 0 SW FROM CTMT AIR COOLERS LINE ISO VALVE STC 0 Q1P16VO207D 2 B 10 B MO A D-175003/1 0 0/C Al PIT 2Y (MOV3441D) (F-9) STO a SW FROM CTMT AIR COOLERS LINE ISO VALVE STC Q Q1 P16VO208A 2 C 1.5 SR S A D-175003/1 C O/C NA ETSP T (PSV3442A) 0 CTMT COOLER SW RETURN RELIEF VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 49 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1116V0208B 2 C 1.5 SR S A D-175003/1 C O/C NA ETSP T (PSV3442B) 0 CTMT COOLER SW RETURN RELIEF VALVE Q1P16VO208C 2 C 1.5 SR S A D-175003/1 C O/C NA ETSP T (PSV3442C) 0 CTMT COOLER SW RETURN RELIEF VALVE Q1P16V0208D 2 C 1.5 SR S A D-175003/1 C O/C NA ETSP T (PSV3442D) 0 CTMT COOLER SW RETURN RELIEF VALVE G1P16V0506 3 B 42 B MO P D-170119/1 Al Al Al PIT 2Y (E-7) 1C SW PUMP TO B HDR ISO Q1P16V0507 3 B 42 B MO P D-170119/1 Al Al Al PIT 2Y (E-4) 1C SW PUMP TO A HDR ISO QIP16V0508 3 B 42 B MO P D-1 70119/1 0 Al PIT 0 2Y (D-11)

SW INLET TO STRAINER LINE ISO VALVE 01QP6V0511 3 B 42 B MO P D-170119/1 0 Al PIT 2Y (D-3)

SW INLET TO STRAINER LINE ISO VALVE 0IP16V0514 3 B 24 B MO A D-170119/2 0 Al STC C CSD/RF CSJ-V-19 (E-6) PIT 2Y SW SUPPLY TO TURBINE BLDG-TRAIN B Q1P16V0515 3 B 24 B MO A D-170119/2 0 C Al PIT 2Y (E-4) STC CSD/RF CSJ-V-19 SW SUPPLY TO TURBINE BLDG-TRAIN A QIP16V0516 3 B 24 B MO A D-170119/2 0 C Al PIT 2Y (D-5) STC CSD/RF CSJ-V-19 SW TRAIN A TO TURBINE BLDG

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 50 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJIROJ Remarks Q1P16V0517 3 B 24 B MO A D-170119/2 0 C Al PIT 2Y (D-4) STC CSD/RF CSJ-V-19 SW TRAIN B TO TURBINE BLDG 01P16V0518 3 B 12 B MO A D-170119/3 0 O/C Al PIT 2Y (B-2) STC 0 Note-1 SW TO DG HEADER-TRAIN B Q1P16V0519 3 B 12 B MO A D-170119/3 0 O/C Al STC 0 Note-1 (B-2) PIT 2Y SW TO DG HEADER-TRAIN A Q1P16V0520 3 B 6 B MO P D-170119/3 0 0 Al PIT 2Y (E-2)

SW TO DG LINE ISO VALVE G1P16V0521 3 B 6 B MO P D-1 70119/3 0 Al PIT 2Y (E-3)

SW TO DG LINE ISO VALVE C

1P16V0522 3 B 8 B MO P D-170119/3 Al PIT 2Y (E-6)

SW TO DG LINE ISO VALVE Q1P16V0523 3 B 8 B MO P D-170119/3 Al PIT 2Y (E-5)

SW TO DG LINE ISO VALVE 0 P

Q1P16V0524 3 B 6 B MO D-170119/3 Al PIT 2Y (E-8)

SW TO DG LINE ISO VALVE 00 P A[

Q1P16V0525 3 B 6 B MO D-1 70119/3 0 PIT 2Y (E-9)

SW TO DG LINE ISO VALVE 0 Q1P16V0526 3 B 8 B MO P D-170119/3 0 Al PIT 2Y (E-11)

SW TO DG LINE ISO VALVE

Joseph M. Farley Nuclear PlantIST Program Unit I Page 51 of 72 P16 - Service Water Pin3 Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks Q1P16V0527 3 B 8 B MO P D 170119/3 0 0 Al PIT 2Y (E-12)

SW TO DG LINE ISO VALVE Q1P16V0528 3 B 6 B MO P D-170119/3 0 0 Al PIT 2Y (F-3)

SW FROM DG LINE ISO VALVE Q1P16V0529 3 B 6 B MO P D-170119/3 0 0 Al PIT 2Y (F-2)

SW FROM DG LINE ISO VALVE Q1P16V0530 3 B 8 B MO P D-170119/3 C C Al PIT 2Y (F-5)

SW FROM DG LINE ISO VALVE 01P16V0531 3 B 8 B MO P D-170119/3 0 0 Al PIT 2Y (F-4)

SW FROM DG LINE ISO VALVE Q1P16V0532 3 B 6 B MO P D-170119/3 0 0 Al PIT 2Y (F-8)

SW FROM DG LINE ISO VALVE Q1P16V0533 3 B 6 B MO P 0-170119/3 0 0 Al PIT 2Y (F-9)

SW FROM DG LINE ISO VALVE Q1P16V0534 3 B 8 B MO P D-170119/3 0 0 Al PIT 2Y (F-Ii)

SW FROM DG LINE ISO VALVE Q1P16V0535 3 B 8 B MO P D-170119/3 0 0 Al PIT 2Y (F-12)

SW FROM DG LINE ISO VALVE 01P16V0536 3 B 12 B MO A D-170119/3 0 O/C Al PIT 2Y (G-2) STC a Note-1 SW FROM DG HEADER-TRAIN B

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 52 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks I

QIP16V0537 3 B 12 B MO A D-170119/3 O/C Al PIT 2Y (G-2) STC a Note-1 SW FROM DG HEADER-TRAIN A 0IP16V0538 3 B 42 B MO A D-170119/2 0 Al PIT 2Y (C-10) STO Q SW HEADER B EMERG RECIRC TO STORAGE POND 01P16V0539 3 B 42 B MO A D-1 70119/2 0 Al PIT 2Y (E-10) STO a SW HEADER A EMERG RECIRC TO STORAGE POND QIP16V0540 3 B 24 B MO A D-170119/2 C Al PIT 2Y (D-9) STC CSD/RF CSJ-V-19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN A QIP16V0541 3 B 24 B MO A Al D-170119/2 C STC CSD/RF CSJ-V- 19 (B-9) PIT 2Y SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN B QIP16V0542 3 B 24 B MO A Al PIT D-170119/2 C 2Y (D-10) STC CSD/RF CSJ-V- 19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN A 01P16V0543 3 B 24 B MO A D-170119/2 Al C PIT 2Y (B-10) STC CSD/RF CSJ-V-19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN B 01P16V0545 3 B 30 B MO A Al STC D-170119/2 C 2 (A-12) PIT SW HEADER B NORMAL DISC HDR ISO 2Y Q1P16V0546 3 B 30 B MO A D-170119/2 C Al PIT 2Y (C-12) STC a SW HEADER A NORMAL DISC HDR ISO QIP16V0549 3 B 30 B MO A D-170119/2 Al C PIT 2Y (E-12) STC a SW RETURN TO STANDPIPE LINE ISO VALVE

Joseph M. Farley NuclearPlantIST Program Unit 1 Page 53 of 72 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1P16V0550 3 B 30 B MO A D-170119/2 0 C Al PIT 2Y (C-13) STC 0 SW RETURN TO CIRC WATER CANAL LINE ISO VALVE 01P16V0552 3 C 20 CK S A O/C NA ETO D-1 70119/1 O/C (H-2) ETC Q SW PUMP 1A DISCHARGE CHECK a 01P16V0553 3 C 20 CK S A O/C NA ETO Q D-1 70119/1 O/C ETC Q (H-4)

SW PUMP 1B DISCHARGE CHECK OIP16V0554 3 C 20 CK S A D-170119/1 O/C NA ETO Q O/C ETC Q (H-6)

SW PUMP IC DISCHARGE CHECK a

Q1P16V0555 3 C 20 CK S A D-1 70119/1 O/C O/C NA ETO Q (H-8) ETC SW PUMP 1D DISCHARGE CHECK NA 2Q Q1P16V0556 3 C 20 CK S A D-170119/1 O/C O/C ETO (H-10) ETC SW PUMP 1E DISCHARGE CHECK Q1P16V0557 3 B 24 B MO P D-1 70119/2 0 0 Al PIT 2Y (F-7)

SW DILUTION BYPASS LINE ISO VALVE QIP16V0558 3 B 24 B MO P D-170119/2 0 0 Al PIT 2Y (E-3)

SW DILUTION BYPASS ISO A TRAIN QIP16V0564 3 C 12 CK S A D-170119/3 0 0 NA ETPO ARFD (G-2) ETO RF ROJ-V-32 DIESEL GENERATORS 'TRAIN B' SERVICE WATER CHE CK BDTC RF VALVE

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 54 of 72 P16 - Service Water Plo Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01P16V0565 3 C 12 CK S A D-170119/3 0 0 NA ETPO ARFD (G-2) ETO RF ROJ-V-32 DIESEL GENERATORS T'RAIN A SERVICE WATER CHECK BDTC RF VALVE Q1P16V0592 3 B 8 B MO P D-170119/3 C C Al PIT 2Y (0-7)

SW TO DG LINE ISO VALVE 01P16V0593 3 B 8 B MO P D-170119/3 C C Al PIT 2Y (F-6) 2B DG SW SUPPLY FROM UNIT 1 O1P16V0635A 3 C 2 CK S A D-170113 C O/C NA ETO RF ROJ-V-29 (E-2) ETC RF ROJ-V-29 NON TREATED SW TO PUMP SEALS AND MOTOR COOLERS Q1P16V0635B 3 C 2 CK S A D-170113 C O/C NA ETO RF ROJ-V-29 (E-11) ETC RF ROJ-V-29 NON TREATED SW TO PUMP SEALS AND MOTOR COOLERS Q1P16V0659 3 C 6 CK S A D-170119/3 0 O/C NA ETPO ARFD (C-3) ETO a UNIT 1 SW SUPPLY TO DG 2C ETC RF ROJ-V-31 QIP16VO660 3 C 6 CK S A D-170119/3 0 O/C NA ETPO ARFD (C-8) ETO 0 UNIT 1 SW SUPPLY TO DG IC ETC RF ROJ-V-31 01P16V0661 3 C 8 CK S A D-170119/3 0 O/C NA ETPO ARFD (C-10) ETO a UNIT 1 SW SUPPLY TO DG 1-2A ETC RF RR-V-01 Q1P16V0679 3 C 8 VR S A D-170119/1 C O/C NA ETO RF (B-10) ETC RF SW HEADER VACUUM BREAKER 01P16V0680 3 C 8 VR S A D-170119/1 C O/C NA ETO RF (B-4) ETC RF SW HEADER VACUUM BREAKER

M. Farley Nuclear PlantIST Program Unit 1 Page 55 of 72 P16 - Service Water I III II lille MD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test F:req RR/CSJIROJ Remarks 0IP16V0721A 3 B 2 GL MO A D-170113 0 C Al PIT 2Y (H-6) STC SW TO CYCLONE SEPARATOR TRAIN A INLET QIP16V07216 3 B 2 GL MO A D-170113 0 C Al PIT 2Y (H-7) STC a SW TO CYCLONE SEPARATOR TRAIN B INLET QSP16VO507 3 B 60 B MO P D-170119 .0 0 Al PIT (G-8)

SW RECIRC LINE DIVERT TO STORAGE POND VALVES QSP16V0508 3 B 60 B MO P D-170119 0 0 Al PIT 2Y (G-8)

SW RECIRC LINE DIVERT TO STORAGE POND VALVES

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 56 of 72 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1P17HV2229 3 B 2 GL AO A D-175002/2 0 C C PIT 2Y (H-2) STC 0 CCW SUPPLY TO SAMPLE COOLERS 01P17HV3045 2 A 3 GL AO A D-175002/2 0 C C PIT 2Y (D-6) STC RF ROJ-V-33 CCW RETURN FROM RCP THERMAL BARRIER (PEN 43) LU-C U Q1P17HV3067 2 A 6 GL AO A D-175002/2 0 C C PIT 2Y (E-6) STC RF ROJ-V-36 CCW RETURN FROM EXCESS LETDOWN HX (PEN 46) U-C U Q1P17HV3095 2 A 6 GL AO A D-175002/2 0 C C PIT 2Y (E-1) STC RF ROJ-V-36 CCW SUPPLY TO EXCESS LETDOWN HX (PEN 45) LU-C U Q1P17HV3096A 3 B 8 B AO A D-175002/2 0 C C PIT 2Y (G-12) STC Q CCW TO RECYCLE SYS, WASTE GAS SYS, HYDROGEN RECOMBINER Q1P17HV3096B 3 B 8 B AO A D-175002/2 0 C C PIT 2Y (F-7) STC a CCW TO RECYCLE SYS, WASTE GAS SYS, HYDROGEN RECOMBINER _ __&_ _PIT Q1P17HV3184 2 A 3 GL AO A 0-175002/2 0 C C PIT 2Y (D-6) STC RF ROJ-V-33 CCW RETURN FROM RCP THERMAL BARRIER (PEN 43) LU-C U QIP17HV3443 2 A 6 GL AO A D-175002/2 0 C C PIT 2Y (E-5) STC RF ROJ-V-36 CCW RETURN FROM EXCESS LETDOWN HEAT EXCHANGER U-C U G1P17RV3028 3 B 2 GL AO A D-175002/1 0 C C PIT 2Y (A-2) STC a CCW SURGE TANK VENT

Joseph M. Farley Nuclear PlantIST Program Unit I Page 57 of 72 P17 - Component Cooling Water PID Valve ID CC CaL Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIP17VOO01A 3 C 18 CK S A D-175002/1 O/C O/C NA ETO a (C-3) ETC Q CCW PUMP DISCHARGE CHECK VALVES QIP17V0001B 3 C 18 CK S A D-175002/1 O/C O/C NA ETO 0 (E-3) ETC Q CCW PUMP DISCHARGE CHECK VALVES Q1P17V0001C 3 C 18 CK S A D-175002/1 O/C O/C NA ETO 0 (G-3) ETC a CCW PUMP DISCHARGE CHECK VALVES QIP17V0006A 3 C 3/4 X1 SR S A D-17500211 C O/C NA ETSP T (PSV3040A) (C-4)

CCW HX RELIEF VALVE QIP17VO006B 3 C 3/4 X 1 SR S A D-175002/1 C O/C NA ETSP T (PSV3040B) (E-4)

CCW HX RELIEF VALVE QIP17VOO6C 3 C 3/4 X 1 SR S A D-175002/1 C O/C NA ETSP T (PSV3040C) (G-4)

CCW HX RELIEF VALVE QIP17VO011A 3 B 10 B MO P D-175002/1 0 0 Al PIT 2Y (MOV3094A) (D-8)

CCW INLET TO SFP CCW HX LINE ISO VALVE QIP17VO011B 3 B 10 B MO P D-17500211 O 0 Al PIT 2Y (MOV3094B) (G-8)

CCW INLET TO SFP CCW HX LINE ISO VALVE Q1P17VOO29A 3 B 14 B MO A D-175002/1 O/C 0 Al STO 0 (MOV3185A) (F-10) PIT 2Y CCW TO RHR HX Q1P17V0029B 3 B 14 B MO A D-175002/1 O/C 0 Al PIT 2Y (MOV3185B) (C-10) STO Q CCW TO RHR HX

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 58 of 72 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIP17V0082 2 A 6 GA MO A D-175002/2 0 C Al PIT 2Y (MOV3052) (C-1) STC RF ROJ-V-33 CCW TO RCP (PEN 42) Li-C LJ 01P17V0083 2 AC 6 CK S A D-175002/2 0 C NA ETC RF ROJ-V-34 (C-2) LJ-C LJ CCW TO RCP (PEN 42) BDTO Normal Ops QIP17V0087A 3 C 2 CK S A D-175002/2 0 C NA ETC RF ROJ-V-35 (B-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE QIP17V0087B 3 C 2 CK S A D-175002/2 0 C NA ETC RF ROJ-V-35 (C-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE 0IP17V0087C 3 C 2 CK S A D-175002/2 0 C NA ETC RF ROJ-V-35 (D-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE Q1P17V0097 2 A 6 GA MO A D-175002/2 0 C Al PIT 2Y (MOV3046) (B-5) Li-C LJ CCW RETURN FROM RCP BEARINGS (PEN 44) STC RF ROJ-V-33 GIP17V0099 2 A 6 GA MO A D-175002/2 0 C Al PIT 2Y (MOV3182) (C-6) STC RF ROJ-V-33 CCW RETURN FROM RCP BEARINGS (PEN 44) Li-C Li Q1P17V0111 3 C 14 CK S A D-175002/1 0 C NA ETC RF ROJ-V-37 (E-1) BDTO Normal Ops CCW PUMP SUCTION CHECK VALVE QIP17V0115 3 C 4X6 SR S A D-175002/1 C O/C NA ETSP T (PSV3029) (A-2)

CCW SURGE TANK RELIEF VALVE Q1P17V0117A 3 B 2 GL MO A D-17500211 C O/C Al PIT 2Y (MOV3031A) (A-5) STO a RMW TO CCW SYSTEM STC Q

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 59 of 72 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks O1P17V0117B 3 B 2 GL MO A D-175002/1 C O/C Al PIT 2Y (MOV30318) (B-5) STO Q RMW TO CCW SYSTEM STC 0 Q1P17V0121A 3 B 2 GL MO A D-175002/1 O/C C Al PIT 2Y (MOV3030A) (A-5) STC 0 DEMIN WATER MAKEUP TO CCW SURGE TANK LINE ISO VALVE QIP17V0121B 3 B 2 GL MO A D-175002/1 O/C C Al PIT 2Y (MOV3030B) (B-5) STC 0 DEMIN WATER MAKEUP TO CCW SURGE TANK LINE ISO VALVE Q1P17VO126A 3 C 1 1/2X2 SR S A D-175002/1 C O/C NA ETSP T (PSV3354A) (E-11)

RHR HX RELIEF VALVE OlP17V01268 3 C 1 1/2X2 SR S A D-175002/1 C O/C NA ETSP T (PSV33548) (B-11)

RHR HX REUEF VALVE Q1P17VO149A 3 C I X 1-1/2 SR S A D-175002/1 C O/C NA ETSP T (PSV3381A) (F-11)

RHR PUMP SEAL COOLER RELIEF Q1P17VO149B 3 C I X 1-1/2, SR S A D-175002/1 C O/C NA ETSP T (PSV3381B) (B-9)

RHR PUMP SEAL COOLER RELIEF 01P17V0153 2 AC 3/4 X I SR S A D-175002/2 C O/C NA ETSP T (PSV3413) (E-2) Li-C Li THERMAL RELIEF VALVE ON CTMT PEN 45 GIP17V0154 2 AC 3/4 X 1 SR S A D-175002/2 C O/C NA ETSP T (PSV3414) (F-6) Li-C Li THERMAL RELIEF VALVE ON CTMT PEN 46

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 60 oa 72 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Cood) NP SP FP 1est Freq RR/CSJ/ROJ Remarks 01 P17Vo055 2 AC 3/4X 1 SR S A D-175002/2 C O/C NA ETSP T (PSV3415) (B-6) L.J-C u THERMAL RELIEF VALVE ON CTMT PEN 44 T

OIP17V0158 2 AC 3/4 X 1 SR S A D-175002/2 C O/C NA ETSP T LI (PSV3444) (C-2) LJ-C u THERMAL RELIEF VALVE ON CTMT PEN 42 01P17V0159 2 AC 6 CK S A D-175002/2 0 C NA ETC RF ROJ-V-34 (E-2) U-C U CCW SUPPLY TO EXCESS LETDOWN HX (PEN 45) BDTO Normal Ops QIP17V0263A 3 C 1 CK S A D-175002/1 C 0 NA ETSP T (A-2)

CCW SURGE TANK VACUUM RELIEF Q1P17V0263B 3 C 1 CK S A D-175002/1 C 0 NA ETSP T (A-2)

CCW SURGE TANK VACUUM RELIEF

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 61 of 72 P18 - Service Air Plo Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q1118V0001 2 A 2 GL M P D-175035/1 LC C NA Li-C LJ (G-7)

SERVICE AIR TO PENETRATION ROOMS AND CONTAINMENT (PEN 47)

Q1P18V0002 2 A 2 GL M P D-175035/1 LC C NA U-C LJ (G-7)

SERVICE AIR TO PENETRATION ROOMS AND CONTAINMENT (PEN 47)

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 62 of 72 P19 - Instrument Air PID Valve ID CC Cat. Size Type Act. AP (Coorcd NP SP FP Test Freq RR/CSJ/ROJ Remarks N1P19PSV2228 Aug C 3/4 SR S A D-175034/1 C 0/C NA ETSP T (C-8)

BACKUP N2 SUPPLY TO PRESS PORVS NIP19V0135 Aug C 3/4 CK S A D-175034/1 C C NA ETC RF (E-8)

INST AIR SUPPLY TO PORVS N1P19V0147A Aug C 1/2 CK S A D-175033/2 O/C C NA ETC RF (E-9)

INST AIR SUPPLY TO AUX STEAM VALVE Q1N12VO01A AIR ACCUM N1P19V0147B Aug C 1/2 CK S A D-175033/2 O/C C NA ETC RF (C-9)

INST AIR SUPPLY TO AUX STEAM VALVE Q1N12VO01B AIR ACCUM Q1P19HV2228 2 A 3/4 GL AO A D-175034/1 C O/C C PIT 2Y (C-9) STO 0 BACKUP NITROGEN SUPPLY TO PRESSURIZER PORV'S (Pen STC a 97B) LJ-C U Q1P19HV3611 2 A 2 GL AO A D-175034/2 0 C C PIT 2Y (E-11) STC RF ROJ-V-40 CTMT INSTRUMENT AIR SUPPLY (PEN 48) u-C Li QIP19VO002 2 AC 2 CK S A D-175034/3 0 C NA ETC RF ROJ-V-38 (D-2) LJ-C LJ CTMT INSTRUMENT AIR SUPPLY (PEN 48) BDTO Normal Ops Q1P19V0004 2 AC 1/2 CK S A D-175034/1 O/C O/C NA ETO CSD/RF CSJ-V-20 (C-10) ETC RF ROJ-V-39 BACKUP AIR SUPPLY TO PRESSURIZER PORV'S Li-C Li 01P19V1099 2 A 3/4 GL M P D-175034/1 LC C NA LJ-C LJ (0-8)

BACKUP NITROGEN SUPPLY BYPASS TO PORVS

Joseph M. Farley NuclearPlantIST Program Unit 1 Page 63 of 72 P23 - Containment Cooling and Purge PIO Valve ID CC Cat. Size Type Act. AP (COOrCd NP SP FP Test Freq RR/CSJ/ROJ Remarks QIP23VO002A 2 A 8 GL MO P D-175010/1 C C Al Li-C Li (MOV3238) (G-2)

CTMT LEAK RATE TEST VALVE Q1P23VO002B 2 A 8 GL MO P D-175010/1 C C Al U-C U (MOV3239) (G-2)

CTMT LEAK RATE TEST VALVE

Joseph M. Farley Nuclear Plant IST Program Unit 1 Page 64 of 72 R43 - Diesel GeneratorAir Start PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 01R43V0519 Aug B 3/8 TW SO A D-170806/1 C 0 Al ETO Q (C-9) 1B DG AIR START SOLENOID Q1R43V0520 Aug B 3/8 TW SO A D-170806/1 C 0 Al ETO 0 (C-9) 1B DG AIR START SOLENOID Q1R43V0532 Aug C 3/4 CK S A D-1 70806/1 O/C C NA ETC Q (F-5) BDTO Normal Ops 1B DG AIR RECEIVER A AIR DRYER CHECK VALVE QIR43V0533 Aug C 3/4 CK S A D-170806/1 O/C C NA ETC 0 (F-9) BDTO Normal Ops 1B DG AIR RECEIVER B AIR DRYER CHECK VALVE Q1R43V0538 Aug C 1/2 SR S A D-170806/1 C O/C NA ETSP T (E-4) lB DG AIR RECEIVER TANK A PRESSURE RELIEF VALVE Q1R43V0539 Aug C 1/2 SR S A D-170806/1 C O/C NA ETSP T (E-8) 1B DG AIR RECEIVER TANK B PRESSURE RELIEF VALVE OSR43V0582 Aug B 3/8 TW SO A D-170806/2 C 0 Al ETO 0 (C-9) 1-2A DG AIR START SOLENOID QSR43VO583 Aug B 3/8 TW SO A D-170806/2 C 0 Al ETO a (C-9) 1-2A DG AIR START SOLENOID QSR43V0595 Aug C 1 CK S A D-170806/2 O/C C NA ETC a (F-5) BDTO Normal Ops 1-2A DG AIR START COMPRESSOR A DISCHARGE CHECK VALVE QSR43V0596 Aug C 1 CK S A D-170806/2 O/C C NA ETC 0 (F-9) BDTO Normal Ops

Joseph M. Farley NuclearPlant IST Program Unit I Page 65 of 72 R43 - Diesel GeneratorAir Start PRD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 1-2A DG AIR START COMPRESSOR B DISCHARGE CHECK VALVE QSR43VO601 Aug C 1/2 SR S A D-170806/2 C O/C NA ETSP T (E-4) 1-2A DG AIR RECEIVER TANK A PRESSURE RELIEF VALVE QSR43V0602 Aug C 1/2 SR S A D-170806/2 C O/C NA ETSP T (E-8) 1-2A DG AIR RECEIVER TANK B PRESSURE RELIEF VALVE QSR43VO610 Aug C 1/2 SR S A D-170807/2 C O/C NA ETSP T (F-5) 2C DG AIR RECEIVER TANK B PRESSURE RELIEF VALVE OSR43V0611 Aug C 1/2 SR S A D-170807/2 C O/C NA ETSP T (F-9) 2C DG AIR RECEIVER TANK A PRESSURE RELIEF VALVE QSR43V0612 Aug C 1/2 SR S A D-170807/1 C O/C NA ETSP T (G-5)

IC DG AIR RECEIVER TANK B PRESSURE RELIEF VALVE QSR43V0613 Aug C 1/2 SR S A D-170807/1 C O/C NA ETSP T (G-9) 1C DG AIR RECEIVER TANK A PRESSURE RELIEF VALVE QSR43V0638 Aug B 3/8 TW SO A D- 170807/2 C 0 Al ETO a (C-6) 2C DG AIR START SOLENOID QSR43V0639 Aug B 3/8 TW SO A D-1 70807/2 C 0 Al ETO a (C-8) 2C DG AIR START SOLENOID QSR43V0640 Aug B 3/8 TW SO A D-1 70807/1 C 0 Al ETO 0 (C-6) 1C DG AIR START SOLENOID

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 66 of 72 R43 - Diesel GeneratorAir Start PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP 1rest Freq RR/CSJ/ROJ Remarks OSR43V0641 Aug B 3/8 TW SO A D-170807/1 C 0 Al EETO a (C-8) 1C DG AIR START SOLENOID 0SR43V0658 Aug C 3/4 CK S A D-170807/2 O/C C NA ETC Q (F-5) BDTO Normal Ops 2C DG AIR RECEIVER B AIR DRYER CHECK VAL\ 1E OSR43V0659 Aug C 3/4 CK S A D-170807/2 O/C C NA ETC Q (F-9) BDTO Normal Ops 2C DG AIR RECEIVER A AIR DRYER CHECK VAL\ IE OSR43V0660 Aug C 3/4 CK S A D-170807/1 O/C C NA ETC Q (G-5) BDTO Normal Ops 1C DG AIR RECEIVER B AIR DRYER CHECK VAL\1E OSR43V0661 Aug C 3/4 CK S A D-170807/1 O/C C NA EETC 0 (G-9) BDTO Normal Ops 1C DG AIR RECEIVER A AIR DRYER CHECK VAL\

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 67 of 72 V47 - Non-Radioactive Vent PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QSV47VO001A Aug B 14 B AO A D-205012 0 C C STC a (HV3624) (F-5) PIT 2Y CONTROL ROOM HVAC QSV47VO001B Aug B 14 B AO A D-205012 0 C C PIT 2Y (HV3625) (G-5) STC a CONTROL ROOM HVAC QSV47VO002A Aug B 20 B AO A D-205012 0 C C STC a (HV3622) (G-3) PIT 2Y COMPUTER ROOM HVAC QSV47VO002B Aug B 20 B AO A D-205012 0 C C PIT 2Y (HV3623) (G-3) STC a COMPUTER ROOM HVAC QSV47VO003A Aug B 24 B AO A D-205012 0 C C STC Q (HV3626) (F-5) PIT 2Y CONTROL ROOM HVAC v

QSV47V00038 Aug B 24 B AO A D-205012 0 C C PIT 2Y (HV3627) (G-5) STC a CONTROL ROOM HVAC

Joseph M. Farley NuclearPlant IST Program Unit 1 Page 68 of 72 V48 - Spent Fuel Pool Vent & Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QIV48VO001A Aug B 16 B AO A D-175022 0 O/C C PIT 2Y (HV3538A) (B- 1i) STO Q SPENT FUEL POOL FILTRATION SYS TO PENETRATION RM STC a FILTER UNIT Q1V48VO001B Aug B 16 B AO A D-175022 0 0/c C STO Q (HV3538B) (D-1 1) STC Q SPENT FUEL POOL FILTRATION SYS TO PENETRATION RM PIT 2Y FILTER UNIT

Joseph K. FarleyNuclear Plant IST Program Unit 1 Page 69 of 72 V49 - Cont. Room HVAC and Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks OSV49CKDMPOO1 Aug C 11 CK S A D-175012 0 O/C NA ETO 18M A (B-2) ETC 18M HVAC PRESS LINE BACKDRAFT DAMPER (CKDMPOO1A-A)

OSV49CKDMPOO1 Aug C 11 CK S A D-205012 0 O/C NA ETC 18M B (B-7) ETO IBM HVAC PRESS LINE BACKDRAFT DAMPER (CKDMPOO1B-B)

OSV49VO001A Aug B 8 B MO A D-175012 C 0 Al PIT 2Y (MOV3478A) (B-7) STO Q CONTROL ROOM HVAC QSV49VO001 B Aug B 8 B MO A D-205012 C 0 Al PIT 2Y (MOV3478B) (B-3) STO Q CONTROL ROOM HVAC QSV49VOO3A Aug B 10 B AO A D-205012 0 C C PIT 2Y (HV3628) (B-10) STC Q CONTROL ROOM EXHAUST ISOLATION VALVE QSV49VO003B Aug B 10 B AO A D-205012 0 C C PIT 2Y (HV3629) (C-10) STC Q CONTROL ROOM EXHAUST ISOLATION VALVE QSV49V0004A Aug B 20 B AO A D-175012 C C C PIT 2Y (HV3649A) (E-6) STC 0 CONTROL ROOM HVAC QSV49VO004B Aug B 20 B AO A D-175012 C C C STC Q (HV3649B) (E-7) PIT 2Y CONTROL ROOM HVAC OSV49VO004C Aug B 20 B AO A D-175012 C C C PIT 2Y (HV3649C) (E-7) STC a CONTROL ROOM HVAC OSV49V0008 Aug B 8 B MO A D-175012 C 0 Al STO a (MOV2769A) (A-8) PIT 2Y CONTROL ROOM HVAC

Joseph M. Farley Nuclear PlantIST Program Unit 1 Page 70 of 72 V49 - Cont. Room HVAC and Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test m Freq RR/CSJ/ROJ Remarks II QSV49V0oo9 Aug B 8 B MO A D-205012 C 0 Al PIT 2Y (MOV2769B) (A-3) STO Q CONTROL ROOM HVAC

Joseph M. FarleyNuclear PlantIST Program Unit 1 Page 71 of 72 Y52 - Diesel GeneratorFuel Oil Transfer PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks QSY52VO506A Aug C 1 1/2 CK S A D-170060 O/C O/C NA ETO 18M (F-2) ETC 18M 1-2A DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO506B Aug C 1 1/2 CK S A D-170060 O/C O/C NA ETO 18M (F-3) ETC 18M 1-2A DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO507A Aug C 1 1/2 CK S A D- 170060 O/C O/C NA ETO 18M (F-5) ETC 18M IC DG FUEL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO507B Aug C 1 1/2 CK S A D-1 70060 O/C O/C NA ETO 18M (F-4) ETC 18M IC DG FUEL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO508A Aug C 1 1/2 CK S A D-1 70060 O/C O/C NA ETO 18M (F-7) ETC 18M 2B DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO508B Aug C 1 1/2 CK S A D-1 70060 O/C O/C NA ETO 18M (F-6) ETC 18M 2B DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE OSY52V0509A Aug C 1 1/2 CK S A D-170060 0/C NA ETO O/C 18M (F-10) ETC 18M 1B DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE QSY52VO509B Aug C 1 1/2 CK S A D-1 70060 0/C O/C NA ETO 18M (F-9) ETC 18M 1B DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE OSY52VO510A Aug C 1 1/2 CK S A D-1 70060 0/C NA O/C ETO 18M (F-13) ETC 18M 2C DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE

Joseph M. FarleyNuclear Plant IST Program Unit 1 Page 72 of 72 Y52 - Diesel GeneratorFuel Oil Transfer liD Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks OSY52V0510B Aug C 1 1/2 CK S A D-170060 O/C O/C NA ETO 18M (F-11) ETC 18M 2C DG FUEL OIL TRANSFER PUMP DISCHARGE CHECK VALVE

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 1 of 63 B 13 - Reactor Coolant PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02B13SV2213A 2 B 1 GL SO A D-205037/1 C O/C C PIT 2Y (HV001) (E-7) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q2B13SV2213B 2 B 1 GL SO A D-205037/1 C O/C C PIT 2Y (HV003) (E-8) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q2B13SV2214A 2 B 1 GL SO A D-205037/1 C O/C C PIT 2Y (HVO02) (E-7) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 02B13SV2214B 2 B 1 GL SO A D-205037/1 C O/C C PIT 2Y (HV004) (E-8) STO CSD/RF CSJ-V-01 REACTOR VESSEL HEAD VENT STC CSD/RF CSJ-V-01 Q2B13V0027A 1 B 3 GA MO A D-205037/2 0 O/C Al STC a (MOV8000A) (D-2) PIT 2Y PRESSURIZER PORV BLOCK VALVE STO a Q2B13VOO27B 1 B 3 GA MO A D-205037/2 0 O/C Al PIT 2Y (MOV80OOB) (E-2) STC a PRESSURIZER PORV BLOCK VALVE STO a 02B13V0031A 1 C 6X6 SR S A D-205037/2 C O/C NA ETSP T (D-5)

PRESSURIZER SAFETY 02B13V00311B 1 C 6X6 SR S A D-205037/2 C O/C NA ETSP T (D-4)

PRESSURIZER SAFETY Q2B13V0031C 1 C 6X6 SR S A D-205037/2 C O/C NA ETSP T (D-3)

PRESSURIZER SAFETY 02B13V0037 2 A 1 D AO A D-205037/2 0 C C PIT 2Y (HV8047) (B-10) STC 0 PRT N2 SUPPLY ISO VALVE (PEN 64A) LJ-C LJ

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 2 of 63 B 13 - Reactor Coolant Ptl Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks Q2B13V0038 2 AC 3 CK S A D-205037/2 C C NA ETC RF ROJ-V-01 (V8046) (B-10) LJ-C U RMW TO PRT ISO CHECK VALVE (PEN 30) BDTO Normal Ops Q2B13V0039 2 A 1 D AO A D-205037/2 0 C C PIT 2Y (HV8033) (B-li) U-C U PRT N2 SUPPLY (PEN 64A) STC Q 02B13V0040 2 A 3 D AO A D-205037/2 C C C PIT 2Y (HV8028) (B-11) STC Q RMW TO PRT ISO VALVE (PEN 30) U-C U Q2B13V0053 1 B 3 GL AO A D-205037/2 C O/C C PIT 2Y (PCV445A) (D-1) STO CSD/RF PRESSURIZER PORV STC CSD/RF 02B13V0054 2 AC 2 CK S A D-205037/2 C O/C NA ETO RF ROJ-V-02 (V8092) (C-6) ETC RF ROJ-V-02 CVCS CHARGING PUMP RELIEF VALVE DISCHARGE TO PRT U-C U (PEN 59)

Q2B13V0061 1 B 3 GL AO A D-205037/2 C O/C C PIT 2Y (PCV444B) (E-1) STO CSD/RF PRESSURIZER PORV STC CSD/RF Q2B13VO110 2 AC 3/4X1 SR S A D-205037/2 C O/C NA ETSP T (B-1l1) LU-C U REACTOR MAKEUP WATER SYSTEM (PEN #30) RELIEF VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 3 of 63 El1 - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E11V0001A 1 A 12 GA MO A D-205041 C O/C Al PIT 2Y (MOV8701A) (G-3) STC CSD/RF CSJ-V-02 2A RHR PUMP SUCTION FROM RCS (HL) (PEN 16) LTA LA STO CSD/RF CSJ-V-02 Li-C Li Q2EIlVO001B 1 A 12 GA MO A D-205041 C O/C Al PIT 2Y (MOV8702A) (E-3) STO CSD/RF CSJ-V-02 2B RHR PUMP SUCTION FROM RCS (HL) (PEN 18) STC CSD/RF CSJ-V-02 LTA LA Li-C Li Q2E11V0009A 2 B 8 GA MO A D-205041 C 0 Al PIT 2Y (MOV8706A) (B-8) STO QICSD CSJ-V-04 CHG PUMP SUCTION FROM RHR HX A Q2E01V0009B 2 B 8 GA MO A D-205041 C 0 Al PIT 2Y (MOV8706B) (C-8) STO Q/CSD CSJ-V-04 CHG PUMP SUCTION FROM RHR HX B Q2E11V0015A 2 C 3X4 SR S A D-205041 C O/C NA ETSP T (V8708A) (G-4)

A RHR PUMP SUCTION RELIEF Q2E11V0015B 2 C 3X4 SR S A D-205041 C O/C NA ETSP T (V8708B) (E-4)

B RHR PUMP SUCTION RELIEF Q2E11VO016A 1 A 12 GA MO A D-205041 C O/C Al PIT 2Y (MOV8701 B) (G-1) STO CSD/RF CSJ-V-02 2A RHR PUMP SUCTION FROM RCS (HL) STC CSD/RF CSJ-V-02 LTA LA Q2E11V0016B 1 A 12 GA MO A D-205041 C O/C Al PIT 2Y (MOV8702B) (E-2) STO CSD/RF CSJ-V-02 2B RHR PUMP SUCTION FROM RCS (HL) STC CSD/RF CSJ-V-02 LTA LA

Joseph M. Farley NuclearPlantIST Program Unit 2 Page 4 of 63 E11-LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E11V0021A 1 AC 6 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-05 (E-1) ETC RF ROJ-V-05 RHR PUMP LHSI DISCHARGE TO (CL) RCS LTA LA 02E11V0021B 1 AC 6 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-05 (F-1) ETC RF ROJ-V-05 RHR PUMP LHSI DISCHARGE TO (CL) RCS LTA LA Q2E11V0021C 1 AC 6 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-05 (G-1) ETC RF ROJ-V-05 RHR PUMP LHSI DISCHARGE TO (CL) RCS LTA LA Q2E11VO023A 2 B 10 GA MO A D-205038/2 0 O/C Al PIT 2Y (MOV8888A) (G-3) STO a 2B HRH HX TO HCS (CL) ISO STC a Q2E11V0023B 2 B 10 GA MO A D-205038/2 0 O/C Al PIT 2Y (MOV8888B) (F-3) STO Q 2A RHR HX TO RCS (CL) ISO STC 0 Q2E11VO024A 2 B 10 GA MO A D-205038/2 0 O/C Al STO Q (MOV8887A) (F-4) STC a RHR TO RCS XCONN PIT 2Y 02E11V0024B 2 B 10 GA MO A D-205038/2 0 O/C Al PIT 2Y (MOV8887B) (G-4) STC 0 RHR TO RCS XCONN STO 0 02E11V0025A 2 A 14 GA MO A D-205038/2 C O/C Al PIT 2Y (MOV881 1A) (J-4) STO 0 2A RHR PUMP SUCTION FROM CTMT SUMP (PEN 11) STC a Li-C Li 02E11V0025B 2 A 14 GA MO A D-205038/2 C O/C Al PIT 2Y (MOV881 16) (H-4) STO a 2B RHR PUMP SUCTION FROM CTMT SUMP (PEN 10) STC 0 Li-C Li

Joseph M. FarleyNuclearPlant IST Program Unit 2 Page 5 o1 63 Eli - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E11V0026A 2 A 14 GA MO A D-205038/2 C O/C Al PIT 2Y (MOV8812A) (J-5) STO Q 2A RHR PUMP SUCTION FROM CTMT SUMP (PEN 11) STC Q U-C U 02E11V0026B 2 A 14 GA MO A D-205038/2 C O/C Al PIT 2Y (MOV881 2B) (H-5) STO Q 26 RHR PUMP SUCTION FROM CTMT SUMP (PEN 10) U-C U STC 0 Q2E11V0027A 2 B 14 GA MO A D-205038/2 0 O/C Al PIT 2Y (MOV8809A) (F-10) STC 0 Note-i 2A RHR PUMP SUCTION FROM RWST 02E11V0027B 2 B 14 GA MO A D-205038/2 0 O/C Al PIT 2Y (MOV8809B) (G-10) STC Q Note-i 2B RHR PUMP SUCTION FROM RWST Q2E11V0028 2 C 14 CK S A D-205038/2 C O/C NA ETO Q (F-10) ETC RF ROJ-V-06 RHR PUMP SUCTION FROM RWST Q2E11V0032A 2 B 10 B AO P D-205041 0 0 0 PIT 2Y (HCV603A) (8-7)

RHR HEAT EXCHANGER DISCHARGE VALVES Q2E11V0032B 2 B 10 B AO P D-205041 0 0 0 PIT 2Y (HCV603B) (C-7)

RHR HEAT EXCHANGER DISCHARGE VALVES Q2E11V0033A 2 B 8 B AO P D-205041 0 0 0 PIT 2Y (HCV605A) (C-8)

RHR HEAT EXCHANGER BYPASS FLOW CONTROL VALVES 02EIlVO033B 2 B 8 B AO P D-205041 0 0 0 PIT 2Y (HCV605B) (D-8)

RHR HEAT EXCHANGER BYPASS FLOW CONTROL VALVES

Joseph M. Farley NuclearPlant IST Program Unit 2 Page 6 of 63 Ell - LHSI/RHR PID Valve ID CC Cat. Size Irype Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2EI1VO037A 2 B 3 GA MO A D-205041 0 C Al PIT 2Y (FCV602A) (D-5) STC Q 2A RHR PUMP MINIFLOW Q2E11V0037B 2 B 3 GA MO A D-205041 C Al PIT 2Y (FCV602B) (D-5) STC 2B RHR PUMP MINIFLOW 02E11V0038A 2 C 10 CK S A D-205041 O/C NA ETO 0 (B-5) ETC 2A RHR DISCHARGE TO RCS Q2E11VO038B 2 C 10 CK S A D-205041 O/C NA ETO ETC T (C-5) 2B RHR DISCHARGE TO RCS u Q2E11VO039A 2 AC .75X1 SR S A D-205038/2 O/C NA ETSP T (G-3) LJ-C 2B RHR HX DISCHARGE RELIEF (PEN 59)

S w 02E11V0039B 2 AC .75X1 SR A D-205038/2 O/C NA ETSP T (F-3) LJ-C LJ T

2A RHR HX DISCHARGE RELIEF (PEN 59) 02E11V0040 2 AC .75X 1 SR S A D-205038/2 ETSP O/C NA (F-3) LJ-C RHR TO HL RELIEF (PEN 59)

Q2E11VOO42A 2 AC 10 CK S A D-205038/2 NA ETC RF O/C ROJ-V-03 (G-2) ETO CSD/RF ROJ-V-03 RHR PUMP DISC TO SIS INJECTION CL LTA LT Q2E11V0042B 2 AC 10 CK S A D-205038/2 C O/C NA ETC RF ROJ-V-03 (E-2) LTA LT RHR PUMP DISC TO SIS INJECTION CL ETO CSD/RF ROJ-V-03 02E11V0044 2 B 10 GA MO A D-205038/2 C O/C Al PIT 2Y (MOV8889) (F-3) STO Q/CSD/RF CSJ-V-03 RHR HX DISCHARGE TO RCS(HL) STO Q/CSD/RF CSJ-V-03

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 7 of 63 El1 - LHSI/RHR PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E1IVOO51A 1 C 6 CK S A D-205038/1 C 0 NA ETO RF ROJ-V-04 (V8998A) (C-2) BDTC RF RCS LOOP LHSI CL Q2E11VO051B 1 C 6 CK S A D-205038/1 C 0 NA ETO RF ROJ-V-04 (V8998B) (D-2) BDTC RF RCS LOOP LHSI CL O2E11VOO5IC 1 C 6 CK S A D-205038/1 C 0 NA ETO RF ROJ-V-04 (V8998C) (D-2) BDTC RF RCS LOOP LHSI CL

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 8 of 63 E 12 - Reactor Cavity Cooling PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E12VO001A Aug B 36 B AO A D-205010/2 0 C C PIT 2Y (HV3999A) (B-10) STC CSD/RF 2A RX CAVITY COOLING DAMPER Q2E12VOO1B Aug B 36 B AO A D-205010/2 0 C C PIT 2Y (HV3999B) (B-10) STC CSD/RF 2B RX CAVITY COOLING DAMPER

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 9 of 63 E13 - Containment Spray PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E13V0002A 2 C 8 CK S A D-205038/3 C O/C NA ETPO ARFD (V8822A) (C-2) ETO RF ROJ-V-07 2A CTMT SPRAY PUMP DISCHARGE ETC RF ROJ-V-07 Q2E13V0002B 2 C 8 CK S A D-205038/3 C O/C NA ETPO ARFD (V8822B) (F-2) ETO RF ROJ-V-07 2B CTMT SPRAY PUMP DISCHARGE ETC RF ROJ-V-07 Q2E13V0003A 2 A 12 GA MO A D-205038/3 C O/C Al PIT 2Y (MOV8826A) (H-3) STC Q CTMT SPRAY PUMP 2A SUCTION FROM CTMT SUMP (PEN 94) Li-C LJ STO 0 Q2E13V0003B 2 A 12 GA MO A D-205038/3 C O/C Al PIT 2Y (MOV8826B) (H-3) STO Q CTMT SPRAY PUMP 2B SUCTION FROM CTMT SUMP (PEN 93) STC Q Li-C Li Q2E13V0004A 2 A 12 GA MO A D-205038/3 C O/C Al PIT 2Y (MOV8827A) (H-4) STO 0 CTMT SPRAY PUMP 2A SUCTION FROM CTMT SUMP (PEN94) STC 0 Li-C Li Q2E13V0004B 2 A 12 GA MO A D-205038/3 C O/C Al STO 0 (MOV8827B) (H-4) STC 0 CTMT SPRAY PUMP 2B SUCTION FROM CTMT SUMP (PEN 93) Li-C Li PIT 2Y Q2E13V0005A 2 B 8 GA MO A D-205038/3 C O/C Al PIT 2Y (MOV8820A) (B-5) STC Q CTMT SPRAY PUMP 2A DISCHARGE STO 0 Q2E13VOO05B 2 B 8 GA MO A D-205038/3 C O/C Al PIT 2Y (MOV8820B) (G-5) STO 0 CTMT SPRAY PUMP 2B DISCHARGE STC a Q2E13V0012A 2 B 10 GA MO A D-205038/3 0 O/C Al PIT 2Y (MOV8817A) (E-10) STC a Note-1 CTMT SPRAY PUMP 2A SUCTION FROM RWST

Joseph M. FarleyNuclearPlantIST Program Unit 2 Page 10 of 63 E13 - Containment Spray PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E13V0012B 2 B 10 GA MO A D-205038/3 0 O/C Al STC 0 Note-1 (MOV8817B) (G-10) PIT 2Y CTMT SPRAY PUMP 2B SUCTION FROM RWST 02E13V0014 2 C 12 CK S A D-205038/3 C O/C N/A ETPO ARFD (V8816) (E-10) ETO RF ROJ-V-08 CTMT SPRAY PUMP SUCTION FROM RWST ETC RF ROJ-V-08

Joseph M. FarleyNuclear PlantlST Program Unit 2 Page 11 of 63 E14 - Containment Isolation PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E14HV3657 2 A 1 GL AO A D-205010/2 0 C C PIT 2Y (A-4) STC 0 CTMT AIR SAMPLE FROM R-1 1/12 DISCH TO CTMT (PEN 55) Li-C Li Q2E14HV3658 2 A 1 GL AO A D-205010/2 0 C C PIT 2Y (B-4) STC a CTMT AIR SAMPLE TO R-1 1/12 (PEN 54) Li-C LJ Q2E14VO001 2 AC 1 CK S A D-205010/2 C O/C NA ETO Q (A-2) ETC RF ROJ-V-09 CTMT AIR SAMPLE (PEN 55) Li-C LJ Q2E14V0002 2 A 1 GL MO A D-205010/2 0 C Al PIT 2Y (MOV3660) (B-2) STC 0 CTMT AIR SAMPLE TO R-1 1/12 (PEN 54) Li-C Li Q2E14V0003 2 A 1 GL MO A D-205010/2 0 C Al PIT 2Y (MOV3318A) (B-2) STC Q CTMT DIFFERENTIAL PRESSURE INSTRUMENT ISOLATION Li-C Li (PEN 70)

Q2E14V0004 2 A 1 GL MO A D-205010/2 0 C Al PIT 2Y (MOV331SB) (C-2) Li-C Li CTMT DIFFERENTIAL PRESSURE INSTRUMENT ISOLATION STC Q (PEN 70)

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 12 of 63 E15 - PenetrationRoom Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRPCSJ/ROJ Remarks Q2E15CKDMP0/2 Aug C 14 CK S A D-205022 C O/C C ETC a A (C-2) ETO Q PRF RECIRC FAN 2A CHECK DAMPER Q2E15CKDMP002 Aug C 14 CK S A D-205022 C O/C C ETO 0 B (C-8) ETC Q PRF RECIRC FAN 2B CHECK DAMPER Q2E15CKDMP003 Aug C 12 CK S A D-205022 C O/C C ETO 0 A (1-2) ETC Q PRF EXHAUST FAN A CHECK DAMPER Q2E15CKDMP003 Aug C 12 CK S A D-205022 C O/C C ETO Q B (D-8) ETC 0 PRF EXHAUST FAN B CHECK DAMPER Q2E15VO001A Aug B 18 B MO A D-205022 C 0 Al PIT 2Y (MOV33618) (D-4) STO Q 2B PRF RECIRC FAN DAMPER Q2E15VO001B Aug B 18 B MO A D-205022 C 0 Al PIT 2Y (MOV3361A) (D-5) STO Q 2A PRF RECIRC FAN DAMPER Q2E15VOO1C Aug B 18 B MO A D-205022 C 0 Al PIT 2Y (MOV3362B) (D-5) STO Q 2B PRF SUCT DAMPER Q2E15VO001D Aug B 18 B MO A D-205022 C 0 Al PIT 2Y (MOV3362A) (D-6) STO Q 2A PRF SUCT DAMPER Q2E15VOOO2A Aug B 14 B AO A D-205022 C 0 0 STO 0 (HV3356A) (C-2) PIT 2Y 2A PRF RECIR FAN EXHAUST DAMPER Q2E15V0002B Aug B 14 B AO A D-205022 C 0 0 PIT 2Y (HV3356B) (B-8) STO 0 2B PRF RECIR FAN EXHAUST DAMPER

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 13 of 63 E15 - PenetrationRoom Filtration PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJIROJ Remarks Q2E15VO003A Aug B 12 B AO A D-205022 C 0 0 STO Q (HV3357A) (A-2) PIT 2Y 2A PRF EXHAUST FAN DISCHARGE DAMPER 02E15V0003B Aug B 12 B AO A D-205022 C 0 0 PIT 2Y (HV3357B) (D-8) STO Q 2B PRF EXHAUST FAN DISCH DAMPER

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 14 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E21V0016A 2 B 3 GA MO A D-205038/1 C O/C Al PIT 2Y (MOV8803A) (G-6) STC RF ROJ-V-14 HHSI TO RCS (CL) ISOLATION STO RF ROJ-V-14 Q2E21VO016B 2 B 3 GA MO A D-205038/1 C O/C Al PIT 2Y (MOV88038) (G-6) STO RF ROJ-V-14 HHSI TO RCS (CL) ISOLATION STC RF ROJ-V-14 Q2E21V0026 2 C 8 CK S A D-205038/1 C O/C NA ETO RF ROJ-V-10 (E-11) ETC RF ROJ-V-10 RWST TO CHG PUMP SUCT Q2E21V0032A 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (D-2) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA Q2E21V0032B 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (D-2) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA 02E21V0032C 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (E-2) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA 02E21V0037A 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (D-3) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA 02E21V0037B 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (D-6) LTA LA ACCUMULATOR TANK DISCH TO RCS(CL) ETC RF ROJ-V-19 02E21V0037C 1 AC 12 CK S A D-205038/2 C O/C NA ETO RF ROJ-V-19 (D-8) ETC RF ROJ-V-19 ACCUMULATOR TANK DISCH TO RCS(CL) LTA LA Q2E21VO049 2 A 3/4 GL AO A D-205038/2 C C C PIT 2Y (HV8871) (E-9) STC 0 SIS ACCUMULATOR TEST TO RWST (PEN 29) LJ-C LJ

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 15 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E21V0050 2 A 3/4 GL AO A D-205038/2 C C C STC 0 (HV8961) (E-10) Li-C LJ SIS ACCUMULATOR TEST TO RWST (PEN 29) PIT 2Y 02E21V0052 2 AC I CK S A D-205038/2 C C N/A ETC RF ROJ-V-1 1 (D-9) Li-C Li SIS ACCUMULATOR FILL (PEN 49) BDTO RF Q2E21V0058 2 AC 1 CK S A D-205038/2 C C NA ETC RF ROJ-V-1 1 (A-10) Li-C Li NITROGEN SUPPLY TO ACCUMULATOR TANKS (PEN 63) BDTO RF Q2E21V0059 2 A 1 GL AO A D-205038/2 C C C PIT 2Y (HV8880) (A-10) STC Q NITROGEN SUPPLY TO ACCUMULATOR TANKS (PEN 63) Li-C Li 02E21V0062A 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (E-3) ETO RF ROJ-V-13 HHSI TO RCS(CL) 02E21VO062B 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (E-3) ETO RF ROJ-V-13 HHSI TO RCS(CL)

Q2E21V0062C 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (F-3) ETO RF ROJ-V-13 HHSI TO RCS(CL) 02E21V0063 2 B 3 GA MO A D-205038/1 C O/C Al PIT 2Y (MOV8885) (B-6) STC RF ROJ-V-14 CHG (HHSI) PUMPS DISCH TO RCS(CL) STO RF ROJ-V-14 02E21V0066A 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (A-4) ETO RF ROJ-V- 13 CHG (HHSI) PUMPS DISCH TO RCS(CL) 02E21V0066B 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (B-4) ETO RF ROJ-V-13 CHG (HHSI) PUMPS DISCH TO RCS(CL)

Joseph M. FarleyNuclearPlantIST Program Unit 2 Page 16 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E21V0066C 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (C-4) ETO RF ROJ-V-13 CHG (HHSI) PUMPS DISCH TO RCS(CL)

Q2E21V0068 2 B 3 GA MO A D-205038/1 O/C Al PIT 2Y (MOVNN6) (H-6) STO RF ROJ-V-14 CHG (HHSI) PUMP DISCH TO RCS(HL) STC RF ROJ-V-14 02E21V0072 2 B 3 GA MO A D-205038/1 O/C Al PIT 2Y (MOV8884) (J-6) STO RF ROJ-V-14 CHG (HHSI) PUMP DISCH TO RCS(HL) STC RF ROJ-V-14 02E21V0076A 1 AC 6 CK S A D-205038/1 O/C NA ETO RF ROJ-V-21 (F-4) ETC RF ROJ-V-21 RHR LHSI TO A RCS HL LTA LA Q2E21V0076B 1 AC 6 CK S A D-205038/1 C O/C NA ETO RF ROJ-V-21 (G-4) ETC RF ROJ-V-21 RHR LHSI TO B RCS HL LTA LA 02E21V0077A 1 AC 6 CK S A D-205038/1 O/C NA ETO RF ROJ-V-18 (F-2) LTA LA HHSI/LHSI AND RHR TO RCS HL LOOP 1 ETC RF ROJ-V-18 02E21V0077B 1 AC 6 CK S A D-205038/1 O/C NA ETO RF ROJ-V-18 (G-2) ETC RF ROJ-V-18 HHSI/LHSI AND RHR TO RCS HL LOOP 2 LTA LA 02E21V0077C 1 AC 6 CK S A D-205038/1 C O/C NA ETO RF ROJ-V-18 (G-2) ETC RF ROJ-V-18 HHSI/LHSI AND RHR TO RCS HL LOOP 3 LTA LA Q2E21V0078A 1 C 2 CK S A D-205038/1 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL 02E21V0078B 1 C 2 CK S A D-205038/1 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 17 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E21VO078C 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL Q2E21V0079A 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (G-3) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL 02E21V0079B 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (G-2) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL Q2E21V0079C 1 C 2 CK S A D-205038/1 C 0 NA BDTC RF (G-2) ETO RF ROJ-V-13 HHSI PUMPS DISCHARGE TO RCS LOOPS HL 02E21V0091 2 A 1 GL AO A D-205038/2 C C C PIT 2Y (HV8860) (D-10) LJ-C Li SIS ACCUMULATOR TANKS FILL (PEN 49) STC 0 02E21V0115A 2 AC 2 CK S A D-205039/1 0 O/C NA ETC RF ROJ-V-15 (G-2) Li-C LT CVCS SEAL INJECTION TO RC PUMP (PEN 27) ETO a 02E21V0115B 2 AC 2 CK S A D-205039/1 0 O/C NA ETO 0 (G-2) ETC RF ROJ-V-15 CVCS SEAL INJECTION TO RC PUMP (PEN 25) LJ-C LT 02E21V0115C 2 AC 2 CK S A D-205039/1 0 O/C NA ETO 0 (G-2) ETC RF ROJ-V-15 CVCS SEAL INJECTION TO RC PUMP (PEN 26) i_-C LT 02E21V0119 2 AC 3 CK S A D-205039/1 0 O/C NA ETO 0 (B-11) ETC RF ROJ-V-12 CVCS CHARGING PUMP DISCHARGE TO REGENERATIVE HX I_-C LJ (PEN 24) 02E21V0121A 2 C 2 CK S A D-205039/6 O/C O/C NA ETPO ARFD (C-6) ETC 0 2A CHG PUMP MIN FLOW LINE CHECK VALVE ETO RF ROJ-V-23

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 18 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E21V0121B 2 C 2 CK S A D-205039/6 O/C O/C NA ETPO ARFD (E-6) ETC 0 2B CHG PUMP MIN FLOW LINE CHECK VALVE ETO RF ROJ-V-23 02E21V0121C 2 C 2 CK S A D-205039/6 O/C O/C NA ETPO ARFD (G-6) ETC 0 2C CHG PUMP MIN FLOW LINE CHECK VALVE ETO RF ROJ-V-23 02E21VO122A 2 C 3 CK S A D-205039/6 O/C O/C NA ETC a (C-6) ETO RF ROJ-V-16 2A CHARGING PUMP DISCHARGE Q2E21VO122B 2 C 3 CK S A D-205039/6 O/C O/C NA ETC 0 (E-4) ETO RF ROJ-V-16 21 CHARGING PUMP DISCHARGE 02E21V0122C 2 C 3 CK S A D-205039/6 O/C O/C NA ETC a (G-5) ETO RF ROJ-V-16 2C CHARGING PUMP DISCHARGE 02E21V0210 2 C 2 CK S A D-205039/6 C 0 NA ETO CSD/RF CSJ-V-07 (G-10) BDTC RF CVCS BA FILTER TO CHARGING PUMP SUCTION 02E21V0213 2 AC 3/4 CK S A D-205039/1 C O/C NA ETO RF ROJ-V-20 (D-11) ETC RF ROJ-V-20 RCP SEAL TO SEAL WATER HX (PEN 28) Li-C LJ 02E21VO220A 3 C 2 CK S A D-205039/3 C O/C NA ETC 0 (F-5) ETO CSD/RF CSJ-V-10 BORON TRANSFER PUMP DISCHARGE LINE CHECK VALVE Q2E21V0220B 3 C 2 CK S A D-205039/3 C O/C NA ETC Q (H-5) ETO CSD/RF CSJ-V-10 BORON TRANSFER PUMP DISCHARGE LINE CHECK VALVE Q2E21V0249A 2 A 3 GA MO A D-205039/1 0 C Al PIT 2Y (MOV8112) (C-11) STC RF ROJ-V-17 RCP SEAL WATER RETURN (PEN 28) Li-C LJ

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 19 of 63 E21 - HHSI/CVCS PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks II I I 02E21V0249B 2 A 3 GA MO A D-205039/1 0 C A[ PIT 2Y (MOV8100) (C-11) STC RF ROJ-V- 17 RCP SEAL WATER RETURN (PEN 28) U-C U 02E21V0251 2 C 2X3 SR S A D-205039/1 C O/C NA ETSP (C-10)

RCP SEAL WATER RETURN LINE RELIEF VALVE 02E21V0253A 2 A 2 GL AO A D-205039/1 O/C C C PIT 2Y (HV8149A) (A-7) STC CSD/RF CSJ-V-06 LETDOWN ORIFICE ISO (PEN 23) U-C LU Q2E21V0253B 2 A 2 GL AO A D-205039/1 O/C C C STC CSD/RF CSJ-V-06 (HV8149B) (A-7) U-C U LETDOWN ORIFICE ISO (PEN 23) PIT 2Y Q2E21V0253C 2 A 2 GL AO A D-205039/1 O/C C C PIT 2Y (HV8149C) (A-6) STC CSD/RF CSJ-V-06 LETDOWN ORIFICE ISO (PEN 23) U-C U Q2E21V0254 2 A 3 GL AO A D-205039/1 0 C C PIT 2Y (HV8152) (A-11) STC CSD/RF CSj-V-08 LETDOWN LINE CTMT ISO (PEN 23) U-C LU Q2E21V0255 2 AC 2X3 SR S D-205039/1 C NA ETSP T A O/C (A-7) U-C lU LETDOWN ORIFICES OULET RELIEF VALVE (PEN 23) 02E21V0257 2 A 3 GA MO A D-205039/6 0 C Al STC CSD/RF CSJ-V-08 (MOV8107) (B-2) U-C U CVCS CHG PUMP DISCH TO REGENERATIVE HX (PEN 24) PIT 2Y Q2E21V0258 2 A 3 GA MO A D-205039/6 0 C Al PIT 2Y (MOVB108) (B-2) STC CSD/RF CSJ-V-08 CVCS CHG PUMP DISCH TO REGENERATIVE HX (PEN 24) U-C LU Q2E21V0259A 2 B 2 GL MO A D-205039/6 0 O/C Al PIT 2Y (MOV8109A) (B-5) STO 0 CHARGING PUMP MINI FLOW LINE ISO VALVE STC 0

Joseph M. Farley NuclearPlant IST Program Unit 2 Page 20 of 63 E21 - HHSI/CVCS PH)

Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2E21V0259B 2 B 2 GL MO A D-205039/6 0 O/C Al PIT 2Y (MOV8109B) (D-6) STO Q CHARGING PUMP MINI FLOW LINE ISO VALVE STC 0 Q2E21V0259C 2 B 2 GL MO A D-205039/6 0 O/C Al PIT 2Y (MOV810gC) (F-6) STO Q CHARGING PUMP MINI FLOW LINE ISO VALVE STC Q 02E21V0263A 2 AC 3/4X1 SR S A D-205039/6 C O/C NA ETSP T (C-9) U-C U 0.75 IN RELIEF-SIS/RHR HX TO CHG PMPS SUCT (PEN 59) 02E21V0263B 2 AC 3/4X1 SR S A D-205039/6 C O/C NA ETSP T (C-9) u-C U 0.75 IN RELIEF-SIS/RHR HX TO CHG PMPS SUCT (PEN 59) 02E21V0264 2 B 2 GL MO A D-205039/6 C O/C Al PIT 2Y (MOV8104) (G-10) STO a EMERGENCY BORATE TO CHG PUMP STC a 02E21V0265 2 B 3 GL MO A D-205039/6 0 O/C Al PIT 2Y (MOV8106) (G-10) STO CSD/RF CSJ-V-11 CHARGING PUMP MINI FLOW COMMON LINE ISO VALVE STC CSD/RF CSJ-V-1 1 02E21V0324A 2 B 8 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8130A) (D-8) STC a CHG PUMP SUCTION HEADER ISOLATION VALVE STO Q 02E21V0324B 2 B 8 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8130B) (E-8) STO 0 CHG PUMP SUCTION HEADER ISOLATION VALVE STC 0 02E21V0325A 2 B 8 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8131A) (F-8) STC a CHG PUMP SUCTION HEADER ISOLATION VALVE STO Q Q2E21V0325B 2 B 8 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8131B) (F-8) STO Q CHG PUMP SUCTION HEADER ISOLATION VALVE STC 0

Joseph M. FarleyNuclearPlant IST Program Unit 2 Page 21 of 63 E21 - HHSI/CVCS PIi Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E21V0326A 2 B 4 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8132A) (D-5) STO RF ROJ-V-22 CHG PUMP DISCHARGE STC RF ROJ-V-22 02E21V0326B 2 B 4 GA MO A D-205039/6 0 O/C Al STO RF ROJ-V-22 (MOV8132B) (D-5) STC RF ROJ-V-22 CHG PUMP DISCHARGE PIT 2Y 02E21V0327A 2 B 4 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8133A) (F-5) STO RF ROJ-V-22 CHG PUMP DISCHARGE STC RF ROJ-V-22 02E21V0327B 2 B 4 GA MO A D-205039/6 0 O/C Al PIT 2Y (MOV8133B) (F-5) STO RF ROJ-V-22 CHG PUMP DISCHARGE STC RF ROJ-V-22 02E21V0336A 2 B 8 GA MO A D-205039/6 C O/C Al STC CSD/RF CSJ-V-09 (LCV115B) (D-9) PIT 2Y CHG PUMP SUCTION FROM RWST STO CSD/RF CSJ-V-09 02E21V0336B 2 B 8 GA MO A D-205039/6 C O/C Al STC CSD/RF CSJ-V-09 (LCV1 15D) (F-9) PIT 2Y CHG PUMP SUCTION FROM RWST STO CSD/RF CSJ-V-09 02E21V0376A 2 B 4 GA MO A D-205039/2 0 C Al PIT 2Y (LCV115C) (H-8) STC CSD/RF CSJ-V-09 VCT OUTLET ISO 02E21V0376B 2 B 4 GA MO A D-205039/2 0 C Al PIT 2Y (LCV115E) (H-8) STC CSD/RF CSJ-V-09 VCT OUTLET ISO 02E21V0565A 2 B 3 GL AO A D-205039/1 0 C C PIT 2Y (HV8175A) (A-10) STC CSD/RF CSJ-V-08 CVCS LETDOWN LINE ISO 02E21VO565B 2 B 3 GL AO A D-205039/1 0 C C STC CSD/RF CSJ-V-08 (HV8175B) (A-10) PIT 2Y CVCS LETDOWN LINE PENE RM ISO

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 22 of 63 E22 - Reactor Cavity Post-LOCA Dilution PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E22V0001A Aug B 10 GA MO A D-205019 C 0 Al PIT 2Y (MOV3872A) (D-5) STO 0 2A RX CAVITY H2 DILUTION FAN DAMPER 02E22V0001B Aug B 10 GA MO A D-205019 C 0 Al PIT 2Y (MOV3782B) (E-5) STO 0 2B RX CAVITY H2 DILUTION FAN DAMPER

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 23 of 63 E23 - PostAccident Ctmt Vent and Sample PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02E23V0002 2 A 6 GL MO A D-205019 LC C Al STC a (MOV3740) (C-10) i_-C LJ CTMT POST-LOCA VENT (PEN 103) PIT 2Y Q2E23V0003 2 A 6 GL MO A D-205019 LC C Al PIT 2Y (MOV3530) (C-9) STC a CTMT POST-LOCA VENT (PEN 103) LI-C LI 02E23V0022A 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3528A) (B-8) STC Q CTMT POST-LOCA SAMPLE (PEN 67) LI-C I_

02E23V0022B 2 A 3/4 GL MO A D-205019 LC C Al STC 0 (MOV3528B) (C-9) LI-C I_

CTMT POST-LOCA SAMPLE (PEN 67) PIT 2Y Q2E23V0022C 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3528C) (D-8) STC a CTMT POST-LOCA SAMPLE (PEN 61A) LI-C LI 02E23V0022D 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3528D) (D-9) STC a CTMT POST-LOCA SAMPLE (PEN 61 A) LJ-C I_

02E23V0023A 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3739A) (C-10) STC 0 CTMT AIR SAMPLE (PEN 67) LI-C LI 02E23V0023B 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3739B) (D-10) STC a CTMT AIR SAMPLE (PEN 61 A) I_-C U Q2E23V0024A 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3745A) (G-10) STC Q CTMT AIR SAMPLE RETURN (PEN 66) U-C LI 02E23V0024B 2 A 3/4 GL MO A D-205019 LC C Al STC Q (MOV3745B) (F-10) LI-C LI CTMT AIR SAMPLE RETURN (PEN 61 B) PIT 2Y

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 24 of 63 E23 - Post Accident Ctmt Vent and Sample PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks 02E23V0025A 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV3835A) (G-9) STC a CTMT POST-LOCA SAMPLE RETURN (PEN 66) Li-C LJ Q2E23V0025B 2 A 3/4 GL MO A D-205019 LC C Al PIT 2Y (MOV38358) (F-9) STC Q CTMT POST-LOCA SAMPLE RETURN (PEN 61B) U-C Li

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 25 of 63 G21 - Liquid Waste Disposal PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks N2G21V0222 Aug C 3/4X1 SR S A D-205004/1 C O/C NA ETSP T (H-7)

CTMT SUMP PUMP RELIEF VALVE (PEN 78) 02G21HV3376 2 A 3 GL AO A D-205004/1 0 C C PIT 2Y (H-8) STC 0 CTMT SUMP PUMP DISCHARGE (PEN 78) Li-C Li 02G21HV33T7 2 A 3 GL AO A D-205004/1 0 C C STC 0 (H-8) Li-C Li CTMT SUMP PUMP DISCHARGE (PEN 78) PIT 2Y Q2G21HV3380 2 A 2 GL AO A D-205004/1 0 C C PIT 2Y (G-8) STC a CTMT SUMP RECIRCULATION (PEN 33) Li-C Li 02G21V0001 2 A 3/4 D AO A D-205042/1 C C C PIT 2Y (HV7150) (B-5) STC 0 RX COOLANT DRAIN TANK VENT TO WASTE GAS SYSTEM Li-C LJ (PEN 62) 02G21V0005 2 A 3 D M P D-205042/1 LC LC N/A Li-C LJ (V7135) (C-11)

RCDT PUMP DISCH CONTROL VALVE BYPASS (PEN 31) 02G21VO006 2 A 3 D AO A D-205042/1 0 C C PIT 2Y (HV7136) (C-10) STC a RCDT PUMP DISCH TO RECYCLE HOLDUP TANK (PEN 31) Li-C LJ 02G21V0064 2 A 3 GL AO A D-205042/1 0 C C PIT 2Y (LCV1003) (C-10) STC Q RCDT PUMP DISCH CONTROL VALVE (PEN 31) Li-C Li 02G21V0082 2 A 3/4 D AO A D-205042/1 0 C C PIT 2Y (HV7126) (C-4) STC a RCDT VENT TO WASTE GAS SYSTEM (PEN 62) Li-C Li 02G21V0204 2 AC 2 CK S A D-205004/1 O/C O/C N/A ETO RF ROJ-V-24 (G-9) ETC RF ROJ-V-24 CTMT SUMP RECIRC (PEN 33) Li-C Li

Joseph M. Farley NuclearPlant1ST Program Unit 2 Page 26 of 63 G21 - Liquid Waste Disposal PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2G21V0291 2 AC 3/4 CK S A D-205004/1 C 0/C N/A ETO RF ROJ-V-25 (H-8) ETC RF ROJ-V-25 CTMT SUMP PUMP DISCHARGE U-C U 02G21V0950 2 AC 3/4X1 SR S A D-205042 C O/C NA ETSP T (C-9) Li-C U WASTE PROCESSING SYSTEM (PEN 31) RELIEF VALVE

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 27 of 63 G24 - Steam GeneratorBlowdown PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02G24VO003A 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7614A) (E-3) STC Q SG BLOWDOWN ISOLATION VALVE Q2G24V0003B 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7614B) (G-3) STC Q SG BLOWDOWN ISOLATION VALVE 02G24V0003C 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7614C) (H-3) STC a SG BLOWDOWN ISOLATION VALVE 02G24V0005A 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7697A) (D-4) STC 0 SG BLOWDOWN BLOCK VALVE 02G24V0005B 2 B 2 GL AO A D-205071/1 O/C C STC a (HV7698A) (D-4) PIT 2Y SG BLOWDOWN BLOCK VALVE 02G24V0005C 2 B 2 GL AO A D-205071/1 O/C C PIT 2Y (HV7699A) (D-4) STC a SG BLOWDOWN BLOCK VALVE 02G24V0006A 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7697B) (D-4) STC Q SG BLOWDOWN ISOLATION VALVE 02G24V0006B 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7698B) (D-4) STC Q SG BLOWDOWN ISOLATION VALVE 02G24V0006C 2 B 2 GL AO A D-205071/1 O/C C C PIT 2Y (HV7699B) (D-4) STC a SG BLOWDOWN ISOLATION VALVE

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 28 of 63 G31 - Spent Fuel Pool Cooling Pin Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Tesst Freq RRICSJ/ROJ Remarks Q2G31V0012 2 A 2 D M P D-205043 LC C N/A L J-C LU (B-4)

SPENT FUEL POOL CLEAN-UP TO REACTOR CAVITY (PEN 95) 02G31V0013 2 AC 2 CK S P D-205043 C C N/A L J-C U (8-3)

SPENT FUEL POOL CLEAN-UP TO REACTOR CAVITY (PEN 95)

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 29 of 63 N1I - Main Steam PH)

Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02N11PV3371A 2 8 6 GL AO A D-205033 C O/C C STC CSD/RF (E-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE Q2N1IPV33718 2 B 6 GL AO A D-205033 C O/C C STC CSD/RF (D-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE Q2N11PV3371C 2 B 6 GL AO A D-205033 C O/C C STC CSD/RF (B-6) STO CSD/RF MAIN STEAM LINE ATMOSPHERIC VENT VALVE Q2N11V0001A 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3369A) (G-7) BDTO Normal Ops MAIN STEAM ISOLATION VALVE STC CSD/RF CSJ-V-12 Q2N11V0001B 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3369B) (E-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q2N11V0001C 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3369C) (B-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BOTO Normal Ops Q2NI1VO002A 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3370A) (G-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q2N11V0002B 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3370B) (E-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q2N11V0002C 2 BC 32 CK AO/S A D-205033/1 0 C C PIT 2Y (HV3370C) (B-8) STC CSD/RF CSJ-V-12 MAIN STEAM ISOLATION VALVE BDTO Normal Ops Q2N11V0003A 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3368A) (G-7) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS

JosephM. FarleyNuclear Plant IST Program Unit 2 Page 30 of 63 NIl - Main Steam pin Valve ID CC Cat. Size Type Act. AP (CoorMA NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2N11VO003B 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3368B) (E-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS 02N1IVO003C 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3368C) (C-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS Q2NI1VO003D 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3976A) (G-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS Q2NllVO003E 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3976B) (E-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS Q2N11VO003F 2 B 3 GA AO A D-205033/1 C C C PIT 2Y (HV3976C) (c-8) STC CSD/RF CSJ-V-13 MAIN STEAM ISOLATION BYPASS Q2N11V0010A 2 C 6X10 SR S A D-205033/1 C O/C NA ETSP T (G-3)

MAIN STEAM SAFETY Q2NI1VO010B 2 C 6X10 SR S A D-205033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY Q2N11V0010C 2 C 6X10 SR S A D-205033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY Q2N11V0010D 2 C 6X10 SR S A D-205033/1 C O/C N/A ETSP T (G-4)

MAIN STEAM SAFETY 02N11VO010E 2 C 6 X 10 SR S A D-205033/1 C O/C NA ETSP T (G-5)

MAIN STEAM SAFETY

Joseph M. Farley NuclearPlant IST Program Unit 2 Page 31 of 63 NI1 - Main Steam PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJIROJ Remarks Q2N11VO011A 2 C 6X 10 SR S A D-205033/1 C O/C NA ETSP T (D-3)

MAIN STEAM SAFETY Q2N11VO011B 2 C 6X 10 SR S A D-205033/1 C O/C NA ETSP T (D-4)

MAIN STEAM SAFETY Q2N11VOO11C 2 C 6X 10 SR S A D-205033/1 C O/C NA ETSP T (D-4)

MAIN STEAM SAFETY Q2N11VOO11D 2 6X 10 SR S A NA ETSP D-205033/1 O/C T (D-4)

MAIN STEAM SAFETY Q2N11VOO11E 2 6X10 SR S A NA T D-205033/1 O/C ETSP (D-5)

MAIN STEAM SAFETY Q2N11VO012A 2 6X 10 SR S A D-205033/1 NA O/C ETSP T (B-3)

MAIN STEAM SAFETY Q2N11VOO12B 2 6X10 SR S NA ETSP A D-205033/1 O/C T (B-4)

MAIN STEAM SAFETY Q2N11VOO12C 2 6X10 SR S A D-205033/1 NA ETSP T O/C (B-4)

MAIN STEAM SAFETY Q2N11VO012D 2 6X 10 SR S A NA ETSP D-205033/1 O/C T (B-4)

MAIN STEAM SAFETY Q2N11V0012E 2 C 6X10 SR S A D-205033/1 C O/C NA ETSP T (B-5)

MAIN STEAM SAFETY

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 32 of 63 N12 - Auxiliary Steam PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP 1rest Freq RR/CSJ/ROJ Remarks Q2N12HV3226 3 B 3 GL AO A D-205033/2 C 0 0 O ;TO Q (D-5) PIT 2Y MAIN STEAM TO TDAFW PUMP Q2N12HV3234A 2 B 1 GL AO A D-205033/2 0 C C PIT 2Y (G-8) ýTC a MAIN STM LINE TO TDAFW PUMP WARM-UP LIN E Q2N12HV3234B 2 B 1 GL AO A D-205033/2 0 C C iTC 0 (C-8) PIT 2Y MAIN STM LINE TO TDAFW PUMP WARM-UP LIN E Q2N12MOV3406 3 B 3 GL MO P D-205033/2 0 0 Al PIT 2Y (D-4)

TDAFW TRIP THROTTLE VLV Q2N12V0001A 2 BC 3 SC AO/S A D-205033/2 C O/C 0 PIT 2Y (HV3235A) (E-8) EETC 0 E E MAIN STEAM TO TDAFW PUMP SHUTOFF VALVE .TO 0 Q2N12V00011B 2 BC 3 SC AO/S A D-205033/2 C O/C 0 PIT 2Y (HV32358) (D-8) ETC 0 MAIN STEAM TO TDAFW PUMP SHUTOFF VALVE E.TO 0 Q2N12V0010A 3 C 4 CK S A D-205033/2 C O/C NA ETPO ARFD (E-6) E.TO a MAIN STEAM TO TDAFW PUMP TURBINE EETC RF ROJ-V-26 Q2N12V0010B 3 C 4 CK S A D-205033/2 C O/C NA ETPO ARFD (C-6) EETO 0 MAIN STEAM TO TDAFW PUMP TURBINE EETC RF ROJ-V-26

Joseph MK FarleyNuclearPlantIST Program Unit 2 Page 33 of 63 N21/C22 - Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02C22FCV478 Aug B 14 A AO A D-205073 0 C C PIT 2Y (G-5) STC CSD/RF MAIN FEEDWATER REGULATOR 02C22FCV479 Aug B 6 GA AO A D-205073 0 C C PIT 2Y (F-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS 02C22FCV488 Aug B 14 A AO A D-205073 0 C C PIT 2Y (D-5) STC CSD/RF MAIN FEEDWATER REGULATOR 02C22FCV489 Aug B 6 GA AO A D-205073 O C C PIT 2Y (D-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS 02C22FCV498 Aug B 14 A AO A D-205073 O C C PIT 2Y (B-5) STC CSD/RF MAIN FEEDWATER REGULATOR 02C22FCV499 Aug B 6 GA AO A D-205073 O C C PIT 2Y (A-5) STC CSD/RF MAIN FEEDWATER REGULATOR BYPASS Q2N21VO001A 2 BC 14 SC MO/S A D-205073 O C NA PIT 2Y (MOV3232A) (G-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops Q2N21VOOO1B 2 BC 14 SC MO/S A D-205073 O C NA PIT 2Y (MOV3232B) (E-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops O2N21VOOO1C 2 BC 14 SC MO/S A D-205073 O C NA PIT 2Y (MOV3232C) (B-7) STC CSD/RF CSJ-V-14 MAIN FEEDWATER SUPPLY BDTO Normal Ops

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 34 of 63 N23 - Auxiliary Feedwater PlO Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks N2N23V0001 Aug C 3 CK S A D-205007 C 0 NA ETO 0 (F-4)

TDAFW PUMP MINI FLOW CHECK VALVE N2N23V0005 Aug C 3 CK S A D-205007 C 0 NA ETO Q (C-6)

MDAFW PUMP MINI FLOW N2N23V0009 Aug C 3 CK S A D-205007 C 0 NA ETO 0 (D-6)

MDAFW PUMP MINI FLOW N2N23V0013 Aug C 6 CK S A D-205007 C 0 NA ETO 0 (F-2)

AFW PUMPS TO CONDENSATE STORAGE TANK Q2N23HV3227A 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (B-8) STO Q MDAFW PUMP TO SG 2A FCV Q2N23HV3227B 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (D-8) STO 0 MDAFW PUMP TO SG 2B DISCHARGE FCV Q2N23HV3227C 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (G-8) STO Q MDAFW PUMP TO SG 2C DISCHARGE FCV Q2N23HV3228A 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (C-8) STO 0 TDAFW PUMP TO 2A SG FCV Q2N23HV3228B 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (F-8) STO Q TDAFW PUMP TO SG 2B FCV 02N23HV3228C 3 B 3 GL AO A D-205007 0 0 0 PIT 2Y (H-8) STO 0 TDAFW PUMP TO SG 2C FCV

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 35 of 63 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02N23V0002A 3 C 4 CK S A D-205007 C O/C NA ETC Q (B-6) ETO CSD/RF CSJ-V-15 MDAFW 2A DISCHARGE TO SG 02N23V0002B 3 C 4 CK S A D-205007 C O/C NA ETC Q (E-6) ETO CSD/RF CSJ-V-15 MDAFW 2B DISCHARGE TO SG Q2N23V0002C 3 C 4 CK S A D-205007 C 0 NA ETO CSD/RF CSJ-V-15 (B-9) BDTC RF MDAFW DISCHARGE TO SG 2A 02N23V0002D 3 C 4 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-16 (C-9) ETO CSD/RF CSJ-V-15 TDAFW DISCHARGE TO SG 2A Q2N23V0002E 3 C 4 CK S A D-205007 C 0 NA ETO CSD/RF CSJ-V-15 (D-9) BDTC RF MDAFW DISCHARGE TO SG 2B 02N23V0002F 3 C 4 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-16 (F-9) ETO CSD/RF CSJ-V-15 TDAFW DISCHARGE TO SG 28 Q2N23V0002G 3 C 4 CK S A D-205007 C 0 NA ETO CSD/RF CSJ-V-15 (G-9) BDTC RF MDAFW DISCHARGE TO SG 2C 02N23V0002H 3 C 4 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-16 (H-9) ETO CSD/RF CSJ-V-15 TDAFW DISCHARGE TO SG 2C 02N23V0003 3 C 6 CK S A D-205007 C 0 NA ETO CSD/RF CSJ-V-15 (G-6) BDTC RF TDAFW DISCHARGE TO SG Q2N23V0006 3 C 8 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-17 (H-3) ETO CSD/RF CSJ-V-15 TDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 36 of 63 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (COord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02N23V0007A 3 C 6 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-17 (B-3) ETO CSD/RF CSJ-V-15 MDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK 02N23V0007B 3 C 6 CK S A D-205007 C O/C NA ETC CSD/RF CSJ-V-17 (E-3) ETO CSD/RF CSJ-V-15 MDAFW PUMP SUCTION FROM CONDENSATE STORAGE TANK Q2N23VO011A 2 C 4 CK MO/S A D-205007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350A) (B-10) STC a AUX FEEDWATER TO SG 2A PIT 2Y Q2N23V0011B 2 C 4 CK MO/S A D-205007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350B) (D-10) STC Q AUX FEEDWATER TO SG 2B PIT 2Y 02N23V0011C 2 C 4 CK MO/S A D-205007 C O/C NA ETO CSD/RF CSJ-V-15 (MOV3350C) (G-10) STC Q AUX FEEDWATER TO SG 2C PIT 2Y 02N23V0013A 3 B 6 GA MO A D-205007 C 0 Al PIT 2Y (MOV3210A) (A-3) STO RF ROJ-V-27 MDAFW PUMP SW INLET 02N23V0013B 3 B 6 GA MO A D-205007 C 0 Al PIT 2Y (MOV3210B) (D-3) STO RF ROJ-V-27 MDAFW PUMP SW INLET Q2N23V0014A 3 B 8 GA MO A D-205007 C 0 Al PIT 2Y (MOV3209A) (A-2) STO RF ROJ-V-27 MDAFW PUMP SW INLET Q2N23V0014B 3 B 8 GA MO A D-205007 C 0 Al PIT 2Y (MOV3209B) (D-2) STO RF ROJ-V-27 MDAFW PUMP SW INLET Q2N23V0014C 3 B 8 GA MO A D-205007 C 0 Al PIT 2Y (MOV3216) (G-3) STO RF ROJ-V-27 TDAFW PUMP SW INLET

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 37 of 63 N23 - Auxiliary Feedwater PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2N23V0025A 3 B 4 GA MO A D-205007 0 C Al PIT 2Y (MOV3764A) (B-7) STC Q MDAFW PUMP TO SG 2A 02N23V0025B 3 B 4 GA MO A D-205007 0 C Al PIT 2Y (MOV3764B) (D-7) STC a MDAFW PUMP TO SG 2B 02N23V0025C 3 B 4 GA MO A D-205007 0 C Al PIT 2Y (MOV3764C) (F-7) STC Q MDAFW PUMP TO SG 2C Q2N23V0025D 3 B 4 GA MO A D-205007 0 C Al PIT 2Y (MOV3764D) (D-7) STC 0 MDAFW PUMP TO SG 2B Q2N23V0025E 3 B 4 GA MO A D-205007 0 C Al PIT 2Y (MOV3764E) (B-7) STC 0 MDAFW PUMP TO SG 2A Q2N23V0025F 3 B 4 GA MO A D-205007 0 C Al- PIT 2Y (MOV3764F) (G-7) STC 0 MDAFW PUMP TO SG 2C 02N23V0081A 3 C 1.5X2 SR S A D-205007 C O/C NA ETSP T (PSV2922A) (B-4) 2A MDAFW PUMP SUCTION RELIEF VALVE Q2N23V0081 B 3 C 1.5X2 SR S A D-205007 C OC NA ETSP T (PSV2922B) (D-4) 2B MDAFW PUMP SUCTION RELIEF VALVE Q2N23VOOB1C 3 C 1.5X2 SR S A D-205007 C O/C NA ETSP (PSV2922C) (G-4)

TDAFW PUMP SUCTION RELIEF VALVE

Joseph M. Farley Nuclear PlantIST Progra Unit 2 Page 38 of 63 N25 - Chemical Injection PID Valve ID CC Cat. Size Type Act. AP (Cocrd) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02N25V0001A 2 B 1/2 GL AO A D-205000/1 O/C C C PIT 2Y (HV3772A) (B-i11) STO a CHEMICAL INJECTION INTO FEEDWATER Q2N25VO001B 2 B 1/2 GL AO A D-205000/1 O/C C C PIT 2Y (HV3772B) (D-11) STC a CHEMICAL INJECTION INTO FEEDWATER Q2N25VOOOIC 2 8 1/2 GL AO A D-205000/1 O/C C C PIT 2Y (HV3772C) (F-11) STC a CHEMICAL INJECTION INTO FEEDWATER

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 39 of 63 P11 - Demineralized Water PIt Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP rest Freq RRICSJ/ROJ Remarks Q2P11V0001 2 A 3 GL AO P D-205047 C C C PIT 2Y (HV3659) (H-10) STC Q DEMIN WATER TO RPV HEAD STORAGE STAND (PEN 82) I.j-C Li Q2P11V0002 2 AC 3 CK S P D-205047 C C NA -j-C Li (G-10)

DEMIN WATER TO RPV HEAD STORAGE STAND (PEN 82)

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 40 of 63 P13 - Containment Purge PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02P13V0281 2 A 48 B AO A D-205010/2 C C C PIT 2Y (HV3198D) (F-3) STC CSD/RF CSJ-V-18 PURGE SUPPLY DAMPER (PEN 12) Li-C Li Q2P13V0282 2 A 48 B AO A D-205010/1 C C C PIT 2Y (HV3197) (G-10) STC CSD/RF CSJ-V-18 PURGE SUPPLY DAMPER (PEN 12) Li-C Li Q2P13V0283 2 A 48 B AO A D-205010/1 C C C PIT 2Y (HV3196) (E-10) Li-C U CTMT PURGE EXHAUST (PEN 13) STC CSD/RF CSJ-V-1 8 Q2P13V0284 2 A 48 B AO A D-205010/2 C C C PIT 2Y (HV319SA) (D-3) STC CSD/RF CSJ-V-18 CTMT PURGE EXHAUST (PEN 13) Li-C Li 02P13V0301 2 A 8 B AO A D-205010/2 0 C C PIT 2Y (HV2866C) (F-3) STC Q CTMT MINI-PURGE SUPPLY (PEN 12) Li-C Li 02P13V0302 2 A 8 B AO A D-205010/1 0 C C PIT 2Y (HV2866D) (G-10) STC Q CTMT MINI-PURGE SUPPLY (PEN 12) Li-C Li Q2P13V0303 2 A 8 B AO A D-205010/2 0 C C STC Q (HV2867C) (D-3) Li-C Li CTMT MINI-PURGE EXHAUST (PEN 13) PIT 2Y Q2P13V0304 2 A 8 B AO A D-205010/1 0 C C PIT 2Y (HV2867D) (E-10) STC L CTMT MINI-PURGE EXHAUST (PEN 13) Li-C Li

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 41 of 63 P15 - Sampling PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJIROJ Remarks Q2P15HV3179A 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (A-3) STC a SG 2A BLOWDOWN LOWER ISOLATION VALVE Q2P15HV3179C 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (A-3) STC a SG 2A BLOWDOWN SAMPLE ISOLATION VALVE Q2P15HV3180A 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (C-3) STC Q SG 2B BLOWDOWN LOWER ISOLATION VALVE Q2P15HV3180C 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (C-3) STC Q SG 2B BLOWDOWN SAMPLE ISOLATION VALVE 02P15HV3181A 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (E-3) STC 0 SG 2C BLOWDOWN LOWER ISOLATION VALVE Q2P15HV3181C 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (E-3) STC Q SG 2C BLOWDOWN SAMPLE ISOLATION VALVE 02P15HV3328 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (A-3) STC a SG 2A BLOWDOWN SAMPLE ISOLATION VALVE 02P15HV3329 2 B 3/8 GL AO A D-205009/2 O/C C C PIT 2Y (C-4) STC a SG 2B BLOWDOWN SAMPLE ISOLATION VALVE 02P15HV3330 2 B 3/8 GL AO A C C D-205009/2 O/C PIT 2Y (E-3) STC 0 SG 2C BLOWDOWN SAMPLE ISOLATION VALVE 02P15HV3334 2 A 3/8 GL AO A C C D-205009/1 C PIT 2Y (G-5) STC Q ACCUMULATOR TANKS SAMPLE (PEN 50) LU-C U

Joseph M. FarleyNuclearPlant IST Program Unit 2 Page 42 of 63 P15 - Sampling PID Valve ID CC Cat. Size Type Act. AP (CoOrd) NP SP FP Irest Freq RR/CSJ/ROJ Remarks I

02P15HV3766 2 A 3/8 GL AO A D-205009/1 C C C PIT 2Y (G-4) *TC a ACCUMULATOR TANKS SAMPLE (PEN 50) 1J-C Li 02P15SV3103 2 A 3/8 GL SO A D-205009/1 0 C C PIT 2Y (A-3) *TC 0 RCS PRESSURIZER LIQUID SAMPLE (PEN 57) LJ-C Li 02P15SV3104 2 A 3/8 GL SO A D-205009/2 0 C C PIT 2Y (F-2) TC 0 PRESSURIZER STEAM SAMPLE TO GFFD (PEN 56) LJ-C Li 02P15SV3331 2 A 3/8 GL SO A D-205009/2 0 C C PIT 2Y (F-4) *TC Q PRESSURIZER STEAM SAMPLE LINE CTMT ISO (PEN 56) LJ-C Li Q2P15SV3332 2 A 3/8 GL SO A D-205009/1 0 C C PIT 2Y (A-5) iTC Q PRESSURIZER LIQUID SAMPLE TO GFFD (PEN 57) LJ-C Li 02P15SV3333 2 A 3/8 GL SO A D-205009/1 0 C C PIT 2Y (C-5) STC 0 RCS (HL) SAMPLE TO GFFD (PEN 58) LJ-C u 02P15SV3765 2 A 3/8 GL SO A D-205009/1 0 C C PIT 2Y (C-4) ;TC 0

.I-C u RCS (HL) SAMPLE TO GFFD (PEN 58) L

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 43 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJtROJ Remarks N2P16V0718A Aug C 2.5 VR S A D-200013/4 C O/C C ETO RF (B-10) ETC RF SW VACUUM BREAKERS - TURBINE BLDG HVAC N2P16V0718B Aug C 2.5 VR S A D-200013/4 C O/C C ETO RF (B-10) ETC RF SW VACUUM BREAKERS - TURBINE BLDG HVAC Q2P16V0003A 3 B 20 B MO P D-205003/1 0 0 Al PIT 2Y (MOV3130A) (E-2)

SW TO CCW HX INLET LINE ISO VALVE Q2P16V0003B 3 B 20 B MO P D-205003/1 0 0 Al PIT 2Y (MOV31308) (F-2)

SW TO CCW HX INLET LINE ISO VALVE Q2P16V0003C 3 B 20 B MO P D-205003/1 0 0 Al PIT 2Y (MOV3130C) (H-2)

SW TO CTMT AIR COOLER LINE ISO VALVE Q2P16V0010A 2 B 12 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3019A) (A-7) STO a SW TO CTMT AIR COOLER LINE ISO VALVE STC a Q2P16V0010B 2 B 12 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3019B) (C-7) STO 0 SW TO CTMT AIR COOLER LINE ISO VALVE STC 0 Q2P16V0010C 2 B 12 8 MO A D-205003/1 0 O/C Al PIT 2Y (MOV3019C) (E-7) STO Q SW TO CTMT AIR COOLER LINE ISO VALVE STC 0 02P16V0010D 2 B 12 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3019D) (F-7) STO 0 SW TO CTMT AIR COOLER LINE ISO VALVE STC Q Q2P16V0011A 3 C 1 1/2X2 SR S A D-275003/1 C O/C NA ETSP T (PSV3020A) (A-8)

SW SUPPLY TO CTMT COOLERS RELIEF

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 44 of 63 P16 - Service Water PID Valve lO CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P16V0011B 3 C 1 1/2X2 SR S A D-275003/1 C O/C NA ETSP T (PSV302OB) (C-8)

SW SUPPLY TO CTMT COOLERS RELIEF Q2P16V0011C 3 C 1 1/2X2 SR S A D-275003/1 C O/C NA ETSP T (PSV3o2oC) (E-8)

SW SUPPLY TO CTMT COOLERS RELIEF Q2P16V0011D 3 C 1 1/2X2 SR S A D-275003/1 C O/C NA ETSP T (PSV30200) (F-8)

SW SUPPLY TO CTMT COOLERS RELIEF Q2P16V0015A 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV31 42A) (B-3)

AFW PUMP ROOM COOLER RELIEF Q2P16V0015B 3 C 3/4 X I SR S A D-205003/2 C O/C NA ETSP T (PSV3142B) (D-3)

AFW PUMP ROOM COOLER RELIEF Q2P16V0020A 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3137A) (B-6)

RHR/LHSI PUMP ROOM COOLER RELIEF Q2P16V0020B 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3137B) (B-7)

RHR/LHSI PUMP ROOM COOLER RELIEF Q2P16V0025A 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3138A) (D-7)

CCW PUMP ROOM COOLER RELIEF 02P16V0025B 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3138B) (D-7)

CCW PUMP ROOM COOLER RELIEF Q2P16V0035A 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3139A) (E-7)

CTMT SPRAY PUMP ROOM COOLER RELIEF

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 45 of 63 P16 - Service Water pDI Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02P16V0035B 3 C 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3139B) (F-7)

CTMT SPRAY PUMP ROOM COOLER RELIEF G2P16V0043A 2 B 10 B MO A D-205003/1 C O/C Al PIT 2Y (MOV3024A) (A-10) STC Q SW EMERG FROM CTMT COOLER 2A STO Q Q2P16V0043B 2 B 10 B MO A D-205003/1 C O/C Al PIT 2Y (MOV3024B) (C-10) STO Q SW EMERG FROM CTMT COOLER 2B STC 0 02P16V0043C 2 B 10 B MO A D-205003/1 C O/C Al PIT 2Y (MOV3024C) (E-10) STC Q SW EMERG FROM CTMT COOLER 2C STO 0 Q2P16V0043D 2 B 10 B MO A D-205003/1 C O/C Al PIT 2Y (MOV3024D) (G-10) STO Q SW EMERG FROM CTMT COOLER 2D STC Q 02P16V0044A 2 8 6 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3023A) (B-10) STO Q SW FROM CTMT AIR COOLERS ST( Q Q2P16V0044B 2 B 6 B MO A D-205003/1 0 0/C Al PIT 2Y (MOV3023B) (D-10) STO 0 SW FROM CTMT AIR COOLERS STC Q Q2P16V0044C 2 B 6 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3023C) (E-10) STO 0 SW FROM CTMT AIR COOLERS STC 0 Q2P16V0044D 2 B 6 B MO A D-205003/1 0 O/C Al PIT 2Y (MOV3023D) (G-10) STO Q SW FROM CTMT AIR COOLERS STC Q 02P16V0052 3 B 10 B MO A D-205003/2 0 C Al PIT 2Y (MOV3149) (E-2) STC Q SW TO SG BLOWDOWN HX AND BTRS CHILLER UNITS

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 46 of 63 P16 - Service Water MID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02P16V0064 3 B 10 B MO A D-205003/2 0 Al PIT 2Y (MOV3150) (E-4) STC SW FROM SG BLOWDOWN HX AND BTRS CHILLER UNITS Q2P16V0069A 3 C 30 CK S A D-200013/8 NA BDTC RF (C-10) 0 ETO a AUX BLDG A TRAIN SW DISCHARGE LINE CHECK VALVE Q2P16V0069B 3 C 30 CK S A D-200013/8 NA BDTC RF (A-10) ETO a AUX BLDG B TRAIN SW DISCHARGE LINE CHECK VALVE Q2P16V0070A 3 C 16 CK S A 00 ETO D-205003/1 NA 0 (C-6) BDTC 0

A TRAIN SW TO CTMT COOLERS HEADER CHECK VALVE Q2P16V0070B 3 C 16 CK S A D-205003/1 0 ETO NA Q (E-6) BDTC a B TRAIN SW TO CTMT COOLERS HEADER CHECK VALVE Q2P16V0071 2 A 6 B MO A D-205003/2 0 AI PIT 2Y (MOV3135) (B-9) STC Q SW TO RCP MOTOR COOLERS LJ-C U Q2P16V0072 2 A 6 B MO A D-205003/2 Al PIT 2Y (MOV3134) (B-12) STC Q SW RETURN FROM RCP MOTOR COOLERS U-C U Q2P16V0075 2 AC 6 CK S A D-205003/2 0 C NA BDTO Normal Ops (B-9) ETC RF ROJ-V-28 SW TO RCP MOTOR COOLERS U-C U 02P16V0081 2 A 6 B MO A D-205003/2 0 C Al PIT 2Y (MOV3131) STC 0 (B-12)

SW RETURN FROM RC3P MOTOR COOLERS U-C U Q2P16V0203 2 AC 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3397) (B-12) U-C U CTMT PEN NO 32 THERMAL RELIEF VALVE

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 47 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks Q2P16V0204 2 AC 3/4 X 1 SR S A D-205003/2 C O/C NA ETSP T (PSV3401) (B-9) Li-C Li CTMT PEN NO 60 THERMAL RELIEF VALVE Q2P16V0206A 2 C 12 CK S D-205003/1 O/C NA ETPO ARFD (A-7) ETO a SW TO CTMT COOLER 2A CHECK VALVE ETC RF ROJ-V-30 02P16V0206B 2 C 12 CK S D-205003/1 O/C NA ETPO ARFD (C-7) ETO a SW TO CTMT COOLER 2B CHECK VALVE ETC RF ROJ-V-30 Q2P16V0206C 2 C 12 CK S D-205003/1 O/C NA ETPO ARFD (E-7) ETO 0 SW TO CTMT COOLER 2C CHECK VALVE ETC RF ROJ-V-30 02P16V0206D 2 C 12 CK S NA ARFD D-205003/1 O/C ETPO (F-7) ETO Q SW TO CTMT COOLER 2D CHECK VALVE ETC RF ROJ-V-30 Q2P16V0207A 2 B 10 B MO D-205003/1 Al STO 0 O/C (MOV3441A) (A-9) STC 0 SW FROM CTMT AIR COOLER LINE ISO VALVE PIT 2Y Q2P16V0207B 2 B 10 B MO D-205003/1 Al PIT 2Y O/C (MOV3441 B) (C-9) STC 0 STO 0 SW FROM CTMT AIR COOLER LINE ISO VALVE 02P16V0207C 2 B 10 8 MO D-205003/1 Al PIT 2Y O/C (MOV3441C) (E-9) STO Q SW FROM CTMT AIR COOLER LINE ISO VAVLE STC Q Q2P16V0207D 2 B 10 B MO D-205003/1 O/C Al PIT 2Y (MOV3441D) (F-9) STC SW FROM CTMT AIR COOLER LINE ISO VALVE STO Q2P16V0208A 2 C 1.5X2 SR S D-205003 O/C NA ETSP T (PSV3442A) (A-9)

CTMT COOLER SW RETURN RELIEF VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 48 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P16V0208B 2 C 1.5X2 SR S A D-205003 C O/C NA ETSP T (PSV3442B) (C-9)

CTMT COOLER SW RETURN RELIEF VALVE 02P16V0208C 2 C 1.5X2 SR S A D-205003 C O/C NA ETSP T (PSV3442C) (E-9)

CTMT COOLER SW RETURN RELIEF VALVE Q2P16V0208D 2 C 1.5X2 SR S A D-205003 C O/C NA ETSP T (PSV3442D) (F-9)

CTMT COOLER SW RETURN RELIEF VALVE Q2P16V0506 3 B 42 B MO P D-200013/2 Al Al Al PIT 2Y (E-7) 2C SW PUMP TO B HDR ISO VALVE Q2P16V0507 3 B 42 B MO P D-200013/2 Al Al Al PIT 2Y (E-4) 2C SW PUMP TO A HDR ISO VALVE Q2P16V0508 3 B 42 B MO P D-200013/2 0 0 Al PIT 2Y (D-1 1)

SW INLET TO STRAINER LINE ISO VALVE Q2P16V0511 3 B 42 B MO P D-200013/2 0 0 Al PIT 2Y (D-3)

SW INLET TO STRAINER LINE ISO VALVE 02P16V0514 3 B 24 B MO A D-200013/8 0 C Al PIT 2Y (E-5) STC CSD/RF CSJ-V-19 SW SUPPLY TO TURBINE BLDG-TRAIN B Q2P16V0515 3 B 24 B MO A D-200013/8 0 C Al PIT 2Y (E-4) STC CSD/RF CSJ-V-19 SW SUPPLY TO TURBINE BLDG-TRAIN A 02P16V0516 3 B 24 B MO A D-200013/8 0 C Al PIT 2Y (D-5) STC CSD/RF CSJ-V-19 SW TRAIN A TO TURBINE BLDG

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 49 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P16V0517 3 B 24 B MO A D-200013/8 0 C A[ PIT 2Y (D-3) STC CSD/RF CSJ-V-19 SW TRAIN B TO TURBINE BLDG Q2P16V0518 3 B 12 B MO A D-200013/3 0 O/C Al PIT 2Y (B-2) STC Q Note-1 SW TO DG HEADER-TRAIN B Q2P16V0519 3 B 12 B MO A D-200013/3 0 O/C Al PIT 2Y (B-2) STC 0 Note-I SW TO DG HEADER-TRAIN A Q2P16V0536 3 B 12 B MO A D-200013/3 0 O/C Al STC Q Note-1 (G-2) PIT 2Y SW FROM DG HEADER-TRAIN B Q2P16V0537 3 B 12 B MO A D-200013/3 0 O/C Al PIT 2Y (G-2) STC Q Note-1 SW FROM DG HEADER-TRAIN A 02P16V0538 3 B 42 B MO A D-200013/8 C 0 Al PIT 2Y (C- 10) STO Q SW HEADER B EMERG RECIRC TO STORAGE POND Q2P16V0539 3 B 42 B MO D-200013/8 C 0 Al PIT 2Y (E-9) STO 0 SW HEADER A EMERG RECIRC TO STORAGE POND Q2P16V0540 3 B 24 B MO D-200013/8 0 C Al PIT 2Y (D-9) STC CSD/RF CSJ-V-19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN A Q2P16V0541 3 B 24 B MO D-200013/8 0 A[ PIT CSJ-V-19 C 2Y CSJ-V-19 (B-9) STC CSD/RF CSJ-V-1 9 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN B Q2P16V0542 3 B 24 B MO D-200013/8 0 C Al PIT 2Y CSJ-V-19 (D-10) STC CSD/RF cSJ-v-19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN A

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 50 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks 02P16V0543 3 B 24 B MO A D-200013/8 0 C Al PIT 2Y (B-10) STC CSD/RF CSJ-V-19 SW RETURN FROM TURBINE BLDG ISOLATION - TRAIN B Q2P16V0545 3 B 30 B MO A D-200013/8 0 C Al PIT 2Y (A- 12) STC 0 SW HEADER B NORMAL DISC HDR ISO Q2P16V0546 3 B 30 B MO A D-200013/8 0 C Al STC a (C-12) PIT 2Y SW HEADER A NORMAL DISC HDR ISO 02P16V0549 3 B 30 B MO A D-200013/8 0 C Al PIT 2Y (E-12) STC 0 SW RETURN TO STANDPIPE LINE ISO VALVE Q2P16V0550 3 B 30 B MO A D-200013/8 0 C Al PIT STC 2Y (B-13)

SW RETURN TO CIRC WATER CANAL LINE ISO VALVE a Q2P16V0552 3 C 20 CK S A D-200013/2 O/C O/C NA ETO (H-2) ETC SW PUMP 2A DISCHARGE CHECK Q 02P16V0553 3 C 20 CK S A D-200013/2 O/C O/C NA ETO (H-4) ETC Q SW PUMP 2B DISCHARGE CHECK Q2P16V0554 3 C 20 CK S A D-200013/2 O/C NA O/C ETO (H-6) ETC SW PUMP 2C DISCHARGE CHECK Q Q2P16V0555 3 C 20 CK S A D-200013/2 O/C O/C NA ETO (H-8) ETC SW PUMP 2D DISCHARGE CHECK Q2P16V0556 3 C 20 CK S A D-200013/2 O/C O/C NA ETO (H-10) ETC Q SW PUMP 2E DISCHARGE CHECK

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 51 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (CoarCd NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P16V0557 3 B 24 B MO P D-200013/8 0 0 A[ PIT 2Y (F-7)

SW DILUTION BYPASS LINE ISO VALVE Q2P16V0558 3 B 24 B MO P D-200013/8 0 0 Al PIT 2Y (F-3)

SW DILUTION BYPASS ISO A TRAIN 02P16V0564 3 C 12 CK S A D-200013/3 0 0 NA BDTC RF (G-2) ETPO ARFD DIESEL GENERATORS 'TRAIN B' SERVICE WATER ETO RF ROJ-V-32 Q2P16V0565 3 C 12 CK S A D-200013/3 0 0 NA BDTC RF (G-2) ETPO ARFD DIESEL GENERATORS T'RAIN A'SERVICE WATER CHECK ETO RF ROJ-V-32 VALVE Q2P16V0592 3 B 8 B MO P D-200013/3 0 0 Al PIT 2Y (D-7)

SW TO DG LINE ISO VALVE Q2P16V0593 3 B 8 B MO P D-200013/3 0 0 Al PIT 2Y (F-7) 2B DG SW SUPPLY Q2P16V0659 3 C 6 CK S A D-200013/3 0 O/C NA ETPO ARFD (C-3) ETO 0 UNIT 2 SW SUPPLY TO DG 2C ETC RF ROJ-V-31 Q2P16V0660 3 C 6 CK S A D-200013/3 0 O/C NA ETPO ARFD (C-10) ETO a UNIT 2 SW SUPPLY TO DG 1C ETC RF ROJ-V-31 02P16V0661 3 C 8 CK S A D-200013/3 0 O/C NA ETPO ARFD (C-12) ETC RF RR-V-01 UNIT 2 SW SUPPLY TO DG 1-2A ETO a Q2P16V0679 3 C 8 VR S A D-200013/2 C O/C NA ETO RF (B-10) ETC RF SW HEADER VACUUM BREAKER

Joseph M. Farley Nuclear Plant IST Program Unit 2 Page 52 of 63 P16 - Service Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRPCSJ/ROJ Remarks Q2P16V0680 3 C 8 VR S A D-200013/2 C O/C NA ETO RF (B-) ETC RF SW HEADER VACUUM BREAKER Q2P16V0720A 3 B 2 GL MO P D-200014 0 0 Al PIT 2Y (E-5)

SW FROM CYCLONE SEPARATOR TRAIN A OUTLET Q2P16V0720B 3 B 2 GL MO P D-200014 0 0 Al PIT 2Y (E-9)

SW FROM CYCLONE SEPARATOR TRAIN B OUTLET Q2P16V0721A 3 B 2 GL MO A D-200014 0 C Al STC a (H-4) PIT 2Y SW FROM CYCLONE SEPARATOR TRAIN A INLET Q2P16V0721B 3 B 2 GL MO A D-200014 0 C Al PIT 2Y (H-9) STC 0 SW TO CYCLONE SEPARATOR TRAIN B INLET

Joseph A. Farley Nuclear Plant IST Program Unit 2 Page 53 of 63 P17 - Component Cooling Water P10 Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRICSJ/ROJ Remarks Q2P17HV2229 3 B 2 GL AO A D-205002/2 0 C C PIT 2Y (H-2) STC 0 CCW SUPPLY TO SAMPLE COOLERS Q2P17HV3045 2 A 3 GL AO A D-20500212 0 C C PIT 2Y (D-6) STC RF ROJ-V-33 CCW RETURN FROM RCP THERMAL BARRIER (PEN 43) LJ-C LJ Q2P17HV3067 2 A 6 GL AO A 0-205002/2 0 C C PIT 2Y (E-6) STC RF ROJ-V-36 CCW RETURN FROM EXCESS LETDOWN HX (PEN 46) Li-C Li Q2P17HV3095 2 A 6 GL AO A D-205002/2 0 C C PIT 2Y (E-1) STC RF ROJ-V-36 CCW SUPPLY TO EXCESS LETDOWN HX (PEN 45) Li-C Li Q2P17HV3096A 3 B 8 B AO A D-205002/2 0 C C PIT 2Y (G-12) STC Q CCW TO RECYCLE SYS, WASTE GAS SYS, HYDROGEN RECOMBINER 02P17HV3096B 3 B 8 B AO A D-20500212 0 C C PIT 2Y (F-7) STC Q CCW FROM RECYCLE SYS, WASTE GAS SYS, HYDROGEN RECOMBINER 02P17HV3184 2 A 3 GL AO A D-205002/2 0 C C PIT 2Y (D-6) STC RF ROJ-V-33 CCW RETURN FROM RCP THERMAL BARRIER (PEN 43) Li-C Li Q2P17HV3443 2 A 6 GL AO A D-205002/2 0 C C PIT 2Y (E-5) STC RF ROJ-V-36 CCW RETURN FROM EXCESS LETDOWN HX (PEN 46) L-C Li Q2P17RV3028 3 B 2 GL AO A D-205002/1 0 C C PIT 2Y (A-2) STC Q CCW SURGE TANK VENT

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 54 of 63 P17 - Component Cooling Water Plo Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P17V0001A 3 C 18 CK S A D-205002/1 O/C O/C NA ETO (C-3) ETC CCW PUMP DISCHARGE CHECK VALVES 0 02P17V0001B 3 C 18 CK S A D-205002/1 O/C O/C NA ETO a (E-3) ETC CCW PUMP DISCHARGE CHECK VALVES 0T Q2P17V0001C 3 C 18 CK S A D-205002/1 O/C O/C NA ETO I (G-3) ETC 0 CCW PUMP DISCHARGE CHECK VALVES Q2P17V0006A 3 C 3/4 X 1 SR S A D-205002/1 C O/C NA ETSP 0 (PSV3040A) (C-4)

CCW HX RELIEF VALVE Q2P17V0006B 3 C 3/4 X 1 SR S A D-205002/1 C O/C NA ETSP T (PSV3040B) (E-4)

CCW HX RELIEF VALVE 02P17V0006C 3 C 3/4 X1 SR S A D-205002/1 C O/C NA ETSP (PSV3040C) (G-4)

CCW HX RELIEF VALVE Q2P17V0011A 3 B 10 B MO P D-205002/1 0 0 Al PIT 2Y (MOV3094A) (D-8)

CCW INLET TO SFP CCW HX LINE ISO VAL EVE Q2P17V0011B 3 B 10 B MO P D-205002/1 0 0 Al PIT 2Y (MOV3094B) (G-8)

CCW INLET TO SFP CCW HX LINE ISO VAL VE Q2P17V0029A 3 B 14 B MO A D-205002/1 O/C 0 Al PIT 2Y (MOV3185A) (F-10) STO 0 CCW TO RHR HX Q2P17V0029B 3 B 14 B MO A D-205002/1 O/C 0 Al PIT 2Y (MOV3185B) (C-11) STO Q CCW TO RHR HX

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 55 of 63 r (- UruIICpIIIll i~t.Jnlliiy vvaltr PID Valve ID CC Cat. Size Type Act. AP (Coor") NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P17V0082 2 A 6 GA MO A D-205002/2 C Al PIT 2Y (MOV3052) (C-1) STC RF ROJ-V-33 CCW TO RCP (PEN 42) LJ-C Li Q2P17V0083 2 AC 6 CK S A D-205002/2 C NA ETC RF ROJ-V-34 (C-2) LJ-C Li CCW TO RCP (PEN 42) BDTO Normal Ops 02P17V0087A 3 C 2 CK S A D-205002/2 C NA ETC RF ROJ-V-35 (B-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE Q2P17V0087B 3 C 2 CK S A D-205002/2 C NA ETC RF ROJ-V-35 (C-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE Q2P17V0087C 3 C 2 CK S A D-205002/2 C NA ETC RF ROJ-V-35 (D-3) BDTO Normal Ops CCW INLET TO RCP THERMAL BARRIER CHECK VALVE 02P17V0097 2 A 6 GA MO A D-205002/2 Al PIT C 2Y (MOV3046) (B-6) STC RF ROJ-V-33 CCW RETURN FROM RCP BEARINGS (PEN 44) Li-C Li Q2P17V0099 2 A 6 GA MO A D-205002/2 C STC RF ROJ-V-33 (MOV3182) (C-7) LJ-C Li CCW RETURN FROM RCP BEARINGS (PEN 44) PIT 2Y 02P17V0111 3 C 14 CK S A D-205002/1 C NA ETC RF ROJ-V-37 (E-l) BDTO Normal Ops CCW PUMP SUCTION CHECK VALVE Q2P17V0115 3 C 4 X6 SR S A D-205002/1 O/C NA ETSP T (PSV3029) (A-2)

CCW SURGE TANK RELIEF VALVE 02P17V0117A 3 B 2 GL MO A D-205002/1 C O/C Al STO Q (MOV3031A) (A-5) STC Q RMW TO CCW SYSTEM PIT 2Y

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 56 of 63 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P17V0117B 3 B 2 GL MO A D-205002/1 C O/C Al PIT 2Y (MOV3031 B) (B-5) STO Q RMW TO CCW SYSTEM STC 0 Q2P17V0121A 3 B 2 GL MO A D-205002/1 O/C C Al PIT 2Y (MOV3030A) (A-5) STC 0 DEMIN WATER MAKEUP TO CCW SURGE TANK LINE ISO VALVE Q2P17V0121B 3 B 2 GL MO A D-205002/1 O/C C Al PIT 2Y (MOV30308) (B-5) STC Q DEMIN WATER MAKEUP TO CCW SURGE TANK LINE ISO VALVE 02P17V0126A 3 C 1 1/2X2 SR S A D-205002/1 C O/C NA ETSP T (PSV3354A) (E-1 1)

RHR HX RELIEF VALVE Q2P17V0126B 3 C 1 1/2X2 SR S A D-205002/1 C O/C NA ETSP T (PSV3354B) (B-11)

RHR HX RELIEF VALVE Q2P17V0149A 3 C I X 1-1/2 SR S A D-205002/1 C O/C NA ETSP T (PSV3381A) (F-11)

RHR PUMP SEAL COOLER RELIEF 02P17V0149B 3 C I X 1-1/' SR S A D-205002/1 C O/C NA ETSP T (PSV3381B) (B-9)

RHR PUMP SEAL COOLER RELIEF 02P17V0153 2 AC 3/4 X 1 SR S A D-205002/2 C O/C NA ETSP T (PSV3413) (E-2) U-C LJ THERMAL RELIEF VALVE ON CTMT PEN 45 Q2P17V0154 2 AC 3/4 X 1 SR S A D-205002/2 C O/C NA ETSP T (PSV3414) (F-6) U-C U THERMAL RELIEF VALVE ON CTMT PEN 46

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 57 of 63 P17 - Component Cooling Water PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Ilest Freq RR/CSJ/ROJ Remarks Q2P17V0155 2 AC 3/4 X 1 SR S A D-205002/2 C O/C NA ETSP T (PSV3415) (B-6) LJ-C U THERMAL RELIEF VALVE ON CTMT PEN 44 02P17V0158 2 AC 3/4 X 1 SR S A D-205002/2 C O/C NA ETSP T (PSV3444) (C-2) LJ-C U THERMAL RELIEF VALVE ON CTMT PEN 42 02P17V0159 2 AC 6 CK S A D-205002/2 0 C NA ETC RF ROJ-V-34 (E-2) LJ-C U CCW SUPPLY TO EXCESS LETDOWN HX (PEN 45) BIDTO Normal Ops 02P17V0263A 3 C 1 CK S A D-205002/1 C 0 NA ETSP T (A-2)

CCW SURGE TANK VACUUM RELIEF Q2P17V02638 3 C 1 CK S A D-205002/1 C 0 NA ETSP T (A-2)

CCW SURGE TANK VACUUM RELIEF 02P17V0288 3 C 2 CK S A D-20500212 0 C NA E)TC 0 (H-6) BIDTO Normal Ops CCW RETURN FROM GROSS FAILED FUEL DETE SAMPLE COOLERS

Joseph M. FarleyNuclear Plant IST Program Unit 2 Page 58 of 63 P18 - Service Air PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P18V0001 2 A 2 GL M P D-205035/1 LC C NA U-C U (G-7)

SERVICE AIR TO PENETRATION ROOMS AND CONTAINMENT (PEN 47)

Q2P18V0002 2 A 2 GL M P D-205035/1 LC C NA U-C U (G-7)

SERVICE AIR TO PENETRATION ROOMS AND CONTAINMENT (PEN 47) 02P18V0004 2 A 2 GL M P D-205035/1 LC C NA U-C U (B-12)

BREATHING AIR TO CTMT HDR ISO (PEN 79) 02P18V0005 2 A 2 GL M P D-20503511 LC C NA U-C U (B-12)

BREATHING AIR TO CTMT HDR ISO (PEN 79)

Joseph M. Farley NuclearPlant IST Program Unit 2 Page 59 of 63 P19 - Instrument Air PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks N2P19PSV2228 Aug C 3/4 SR S A D-205034/4 C O/C NA ETSP T (B-i)

BACKUP NITROGEN SUPPLY TO PRESS PORVs N2P19V0007A Aug C 1/2 CK S A 0-205033/2 O/C C NA ETC RF (E-9)

INST AIR SUPPLY TO AUX STEAM VALVE Q2N12VO01A AIR ACCUM N2P19V0007B Aug C 1/2 CK S A D-205033/2 O/C C NA ETC RF (D-9)

INST AIR SUPPLY TO AUX STEAM VALVE Q2N12V001B AIR ACCUM N2P19V0236A Aug C 3/4 CK S A D-205034/4 C C NA ETC RF (B-7)

INST AIR SUPPLY TO PORVS N2P19V0243 Aug C 3/4 CK S A D-205034/4 C C NA ETC RF (C-3)

INST AIR SUPPLY TO PORVS Q2P19HV2228 2 A 3/4 GL AO A D-205034/4 C O/C C PIT 2Y (V0006) (B-4) STO a BACKUP NITROGEN SUPPLY TO PRESSURIZER PORV'S (PEN STC Q 97B) U-C LT Q2P19HV3611 2 A 2 GL AO A D-205034/2 0 C C STC RF ROJ-V-40 (E-5) U-C U CTMT INSTRUMENT AIR SUPPLY (PEN 48) PIT 2Y 02P19V002 2 AC 2 CK S A D-205034/4 0 C NA ETC RF ROJ-V-38 (E-3) LI-C U CTMT INSTRUMENT AIR SUPPLY (PEN 48) BDTO Normal Ops Q2P19V0004 2 AC 1/2 CK S A D-205034/4 O/C O/C NA ETC RF ROJ-V-39 (B-6) ETO CSD/RF CSJ-V-20 BACKUP AIR SUPPLY TO PRESSURIZER PORV'S (PEN 97B) LJ-C U

Joseph M. FarleyNuclearPlant IST Program Unit 2 Page 60 of 63 P19 - Instrument Air PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RRPCSJ/ROJ Remarks 02P19V1099 2 A 3/4 GL M P D-205034/1 LC C NA U-C Li (B-4)

BACKUP NITROGEN SUPPLY BYPASS TO PORVS

Joseph M. Farley Nuclear PlantIST Program Unit 2 Page 61 of 63 P23 - Containment Cooling and Purge PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2P23V0002A 2 A 8 GL MO P D-205010/1 C C Al U-C Li (MOV3239) (G-2)

CTMT LEAK RATE TEST VALVE Q2P23V0002B 2 A 8 GL MO P D-205010/1 C C Al Li-C Li (MOV3239) (G-2)

CTMT LEAK RATE TEST VALVE

Joseph M. FarleyNuclear PlantIST Program Unit 2 Page 62 of 63 R43 - Diesel GeneratorAir Start PID Valve ID CC Cat. Size Type Act. AP (Coord) NP SP FP Test Freq RR/CSJ/ROJ Remarks Q2R43V0519 Aug B 3/8 TW SO A D-200212 C 0 Al E-TO 0 (C-8) 2B DG AIR START SOLENOID 02R43V0520 Aug B 3/8 TW SO A 0-200212 C 0 Al E-TO 0 (C-8) 2B DG AIR START SOLENOID 02R43V0532 Aug C 3/4 CK S A D-200212 O/C C NA E;TC N (F-4) BIDTO Normal Ops 2B DG AIR RECEIVER A AIR DRYER CHECK VAL' 02R43V0533 Aug C 3/4 CK S A D-200212 O/C C NA ETC 0 (F-8) BDTO Normal Ops 2B DG AIR RECEIVER B AIR DRYER CHECK VALVE Q2R43V0538 Aug C 1/2 SR S A D-200212 C O/C NA ETSP T (E-3) 2B DG AIR RECEIVER TANK A PRESSURE RELIEF VALVE 02R43V0539 Aug C 1/2 SR S A D-200121 C O/C NA ETSP T (E-7) 2B DG AIR RECEIVER TANK B PRESSURE RELIEF VALVE

Joseph M. Farley NuclearPlant IST Program Unit 2 Page 63 of 63 V48 - Spent Fuel Pool Vent & Filtration PID Valve ID CC Cat. Size Type Act. AP (CoOrc) NP SP FP Test Freq RRICSJ/ROJ Remarks 02V48V0001A Aug B 16 B AO A D-205022 0 O/C C PIT 2Y (HV3538A) (B- 11) STC Q SFP FILTRATION SYS TO PENETRATION RM FILTER UNIT STO Q Q2V48VO001B Aug B 16 B AO A D-205022 0 O/C C PIT 2Y (HV3538B) (D-11) STO Q SFP FILTRATION SYS TO PENETRATION RM FILTER UNIT STC Q

12.0 VALVE RELIEF REQUEST LOG Relief Request Component Status RR-V-1 Q1P16V0661 Submitted to NRC for review.

Q2P16V0661 Reference NRC letter to Mr. D. N. Morey dated October 29, 1998, titled "Relief Request for the Pump and Valve Inservice Testing Program - Joseph M. Farley Nuclear Plant, Units I and 2 (TAC Nos. M99186 and M99187)", NRC letter to Mr. D. N. Morey dated March 9, 2000, titled "Joseph M. Farley Nuclear Plant, Units 1 and 2, RE: Approval of Pump and Valve Inservice Testing Program Relief Requests (TAC Nos. MA5135 and MA5136)."

ISTPgmRRValves4thlnt.doc 12-1 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-V-1 PLANT/UNIT: Joseph M. Farley Nuclear Plant / Units I and 2 INTERVAL: 4th Interval beginning December 1, 2007 and ending November 30, 2017.

COMPONENT(S) QIP16V0661 AFFECTED: Q2P16V066 I CODE EDITION ASME OM Code-2001 Edition with Addenda through OMb-2003 AND ADDENDA:

REQUIREMENTS: Paragraph ISTC-5221(c)(3) of the OM Code requires; "At least one valve from each group shall be disassembled and examined at each refueling outage; all valves from each group shall be disassembled and examined at least once every 8 years."

REASON FOR There are no system design provisions to verify valve reverse flow REQUEST: closure quarterly, at cold shutdown or refueling outage. Therefore, per ISTC-5221(c)(3), this valve will be disassembled at refueling outages to verify operability. No relief is required for the above, per OM ISTC-5221(c)(3), if this valve is disassembled every refueling outage.

The inspection history of these valves suggests there is no need for disassembly/inspection each outage, thus any additional expense in doing so would be an unnecessary burden. The past inspections of these valves (for both units) dating back to 1984 have not detected any unsatisfactory conditions. On average, the disassembly/inspection of these valves requires 6 man-hours.

Additional costs associated with planning, scheduling, supervision, documentation, etc., are also required for this task.

Without a sampling disassembly and inspection plan, FNP will be required to remove each train of emergency diesel power from service each outage. This will cause the unavailability of the diesel train and hence the risk to the core to be twice that which would be required with grouping. In light of the good inspection history of these valves, FNP will be increasing risk to the core without a commensurate gain in the reliability of the valves.

This is counter to the philosophy of 10CFR50.65 of balancing reliability and availability which states that "Adjustments shall be made where necessary to ensure that the objective of preventing IST_Pgm.._RRValves4thlnt.doc 12-2 Version 1.0

SOUTHERN NUCLEAR OPERATING COMPANY IST PROGRAM RELIEF REQUEST PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(ii)

RR-V-1 failures of structures, systems and components through maintenance is appropriately balanced against the objective of minimizing unavailability of structures, systems and components due to monitoring or preventive maintenance."

PROPOSED As an alternative to the disassembly and inspection frequency ALTERNATIVE required by Paragraph ISTC-5221(c)(3) of the OM Code, SNC AND BASIS: proposes the following.

The valve will be disassembled and manually full stroke exercised every other refueling outage. The valve internals will be verified to be structurally sound (no loose or corroded parts) and the disk will be manually exercised to verify full stroke capability. The valve will be part stroked with flow after reassembly. The necessary valve obturator movement, verifying part stroke exercising, will be confirmed by changes in system pressure. flow rate, level, temperature, seat leakage testing or other positive means, or through the use of ultrasonic (or similar) flow measuring devices.

If a problem is determined while disassembling and inspecting the valve, an evaluation will be performed to determine if there is a generic issue involved. As part of this evaluation, the results of the disassembly and inspection from each valve will be reviewed. If a generic problem is determined to exist, then the valve on the other unit will be disassembled and inspected at the next refueling outage.

This proposed alternative of disassembling and inspecting the valve every other refueling provides reasonable assurance of adequate valve operation and readiness. On the basis that compliance with OM Code testing requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, this proposed alternative should be granted pursuant to 10 CFR 50.55a(a)(3)(ii).

DURATION: 4t IST Interval, December 1, 2007 through November 30, 2017.

PRECEDENTS: This Relief Request was approved as QIP16-RR-V-5 and Q2P16-RR-V-5 for the Third 10 Year IST Interval.

REFERENCES:

NRC Safety Evaluation dated March 9. 2000 - TAC Nos. MA5135 and MA5136.

STATUS: Submitted for NRC review.

ISTPgmRRValves4thlnt.doc 12-3 Version 1.0

VLVCSJ.Doc 13.0 COLD SHUTDOWN JUSTIFICATION (CSJ) LOG CSJ Components Status CSJ-V-1 Ql(2)BI3SV2213A & B QI(2)B 13SV2214A & B CSJ-V-2 Q1(2)EI1VOOO1A & B QI(2)EIIV0016A & B CSJ-V-3 Q1 (2)EI 1V0044 CSJ-V-4 Q I(2)E 1IV0009A & B CSJ-V-5 NOT USED CSJ-V-6 Q 1 (2)E21V0253A, B & C CSJ-V-7 Q I (2)E21V0210 CSJ-V-8 Q 1 (2)E21 V0254 QI(2)E21V0257 Q1(2)E21V0258 Q 1(2)E21V0565A & B CSJ-V-9 Q1(2)E21V0336A & B Q I(2)E21V0376A & B CSJ-V-10 Q 1(2)E21V0220A & B CSJ-V- 1I QI(2)E21V0265 CSJ-V-12 QI(2)N1 IV0001A, B & C QI(2)NII V0002A, B & C CSJ-V-13 QI(2)NI IV0003A thru F CSJ-V-14 QI(2)N21VO001A, B & C CSJ-V- 15 Q1(2)N23V0002 A thru H Qi (2)N23VO003, Q 1(2)N23V0006 Ql(2)N23V0007A & B QI(2)N23V001 IA, B & C CSJ-V-16 Q1(2)N23V0002D, F & H ISTPgmVLVCSJ_4thlnt.doc 13-1 Version 1.0

VLVCSJ.Doc CSJ Components Status CSJ-V-17 QI(2)N23V0006 QI(2)N23V0007A & B CSJ-V-18 QI(2)P13V0281 Ql(2)P13V0282 Ql(2)P13V0283 Q l(2)P13V0284 CSJ-V-19 Q1(2)P16V0514 QI(2)P16V0515 QI(2)Pl6V0516 Q1(2)P16V0517 Ql(2)P16V0540 QI (2)PI6V0541 QI(2)P 16V0542 Ql(2)P16V0543 CSJ-V-20 Q1(2)P19V0004 ISTPgmVLVCSJ_4thlnt.doc 13-2 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-1 System: Reactor Coolant (B 13)

Valve: QI(2)BI 3SV2213A, B, QI(2)B 13SV2214A, B Other Valve No: HV-1, HV-2, HV-3, HV-4 Drawing: D-175037-1 (E-7, E-7, E-8, E-8)

D-205037-1 (E-7, E-7, E-8, E-8)

Category: B Class: 2 Function: Reactor vessel head vent valve.

Quarterly Test Exercise, time, and fail (ISTC-3510, 5151 and 3560).

Requirements:

Cold Shutdown The head vent valves cannot be exercised during normal operation with Test adequate assurance that an uncontrolled release of reactor coolant and a rapid Justification: RCS de-pressurization would not occur. To exercise the valves open in any order could result in a potential pressure shock to the closed valve and a potential "BURP" reaction. The consequences of this reaction are too severe to warrant testing during normal operation.

Quarterly Part None, these are rapid acting valves. The operating controls were not Stroke designed for partial stroking.

Exercising:

Cold Shutdown Exercise, time and fail test per ISTC-3521(c).

Testing:

ISTPgnVLVCSJ_4thInt.doc 13-3 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-2 System: LHSI/RHR (E 1i)

Valve: QI(2)EI1VO001A, B, Q1(2)E11V0016A, B Other Valve No: 8701A, 8702A, 8701B, 8702B Drawing: D-175041 (G-3, E-3, G-2, E-2)

D-205041 (G-3, E-3, G-1, E-2)

Category: A Class: 1 Function: RHR Pump Suction from RCS (HL).

Quarterly Test Exercise and time (ISTC-3510 and 5121).

Requirements:

Cold Shutdown These are boundary valves between the high-pressure reactor coolant system Test and the low-pressure RHR system piping. The valves are interlocked to RCS Justification: pressure and cannot be opened with RCS pressure greater than 402.5 psig.

Defeating the interlocks to perform testing is not desirable since they are pressure isolation valves. If the inline valves were inadvertently opened during testing, an inter-system LOCA could occur.

Quarterly Part None, partial-valve exercising is precluded for the same reasons as full-Stroke stroke exercising.

Exercising:

Cold Shutdown Exercise and time per ISTC-3521(c).

Testing:

ISTPgmVLVCSJ_4thlnt.doc 13-4 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-3 System: LHSI/RHR (El 1)

Valve: QI(2)E11V0044 Other Valve No: 8889 Drawing: D-175038-2 (F-3)

D-205038-2 (F-3)

Category: B Class: 2 Function: RHR Hx Discharge to RCS (HL).

Quarterly Test Exercise and time (ISTC-3510 and 5121).

Requirements:

Cold Shutdown This valve is a normally closed motor-operated valve that is the boundary Test valve between the high pressure SI piping connected to the RCS and the low-justification: pressure piping of the RHR system. Exercising during normal operation could result in an over-pressurization of the R-R system piping and result in an inter-system LOCA condition.

Quarterly Part None, partial-valve exercising is precluded for the same reasons as full-Stroke stroke exercising.

Exercising:

Cold Shutdown Once per quarter the downstream pressure will be measured. If the pressure is Testing: < 550 psig, the valve will be full-stroke exercised. If the pressure is > 550 psig, the valve will not be exercised that quarter.

If the downstream pressure prohibits quarterly testing, the valve will be full-stroke exercised at cold shutdowns per ISTC-3521(c).

IST_PgnVLVCSJ_4thlnt.doc 13-5 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-4 System: LHSI/RHR (E 1i)

Valve: Q 1(2)E1IV0009A, B Other Valve No: 8706A, B Drawing: D-175041 (B-8, C-8)

D-205041 (B-8, C-8)

Category: B Class: 2 Function: Charging Pump Suction from RHR Hx.

Quarterly Test Exercise and time (ISTC-3510 and 5121).

Requirements:

Cold Shutdown These valves can only be exercised when the RCS boron concentration is Test > 200 ppm because opening these valves connects the RWST to the charging Justification: pumps suction. These valves cannot be exercised at the end of core life when RCS boron concentration is !5 200 ppm because exercising could produce an elevated boron concentration and cause a plant transient. In order to preclude a transient at end of core life, the RHR system must be removed from service and declared inoperable in order to support valve exercising.

Quarterly Part Valves will be full-stroke exercised quarterly whenever RCS boron Stroke concentration is > 200 ppm. Partial-valve exercising at end of core life is Exercising: precluded for the same reasons as described above.

Cold Shutdown Exercise and time quarterly whenever RCS boron concentration is > 200 ppm.

Testing:

Exercise and time at cold shutdown when quarterly testing cannot be perforned because RCS boron concentration is < 200 ppm per ISTC-3521(c).

ISTPgmVLVCSJ_4thlnt.doc 13-6 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-v-5 NOT USED ISTPgmVLVCSJ_4thlnt.doc 13-7 Version 1.0

VLVCSI.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-6 System: SI/CVCS (E21)

Valve: Q I (2)E21V0253A, B, C Other Valve No: 8149A, B, C Drawing: D-175039-1 (A-7, A-7, A-6)

D-205039-1 (A-7, A-7, A-6)

Category: A Class: 2 Function: Letdown Orifice Isolation.

Quarterly Test Exercise, time and fail (ISTC-3510, 5131 and 3560).

Requirements:

Cold Shutdown The number of times that these valves are exercised during normal operation is Test limited to as few as possible. Each time these valves are stroked, a Justification: downstream pressure surge occurs, which may lift the downstream relief valve QV0255. If the relief valve lifts and fails to re-seat, a loss of CVCS letdown will result in a forced plant shutdown. The only method to mitigate this surge is by manual operation of the automatic pressure control valve (PCV 145) which is at best, coarse control.

Quarterly Part None, valves full-stroke on initiation and cannot be partial-stroke exercised.

Stroke Exercising:

Cold Shutdown Exercise, time and fail per ISTC-3521(c).

Testing:

ISTPgm._VLVCSJ_4thlnt.doc 13-8 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-7 System: SI/CVCS (E21)

Valve: Q1(2)E21V0210 Other Valve No: 8442 Drawing: D-175039-6 (G-10)

D-205039-2 (H-8)

Category: C Class: 2 Function: CVCS Boric Acid Filter to Charging Pump Suction.

Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Cold Shutdown The only way to verify forward flow operational readiness is by passing Test concentrated boric acid solution through check valve QV0210 to the charging Justification: pump suction header. Transfer of concentrated boric acid at > 30 gpm with a concentration of 7000 to 7700 ppm to the charging pump suction during normal operation would subject the plant to an unnecessary safety challenge caused by a rapid temperature decrease in the RCS and ensuing power transient due to the boron addition.

Quarterly Part NA Stroke Exercising:

Cold Shutdown Full forward flow exercise per ISTC-3522(b). Bi-directional exercising in the Testing: non-safety related closed direction will be demonstrated by establishing a differential across the valve disc either with an outside pressure source, flow or other positive means.

ISTPgmVLVCSJ_4thlnt.doc 13-9 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-8 System: SI/CVCS (E21)

Valve: Qi(2)E21V0254, QI(2)E21V0257, QI(2)E21V0258, QI(2)E21V0565A, B Other Valve No: 8152, 8107, 8108, 8175A, B Drawing: D-175039-1 (A-11, A-10, A-10): Q 1V0254, Q 1 V0565A. B D-175039-6 (B-I, B-2): Q 1 V0257, Q1 V0258 D-205039-1 (A-11, A-10, A-10): Q2V0254, Q2V0565A, B D-205039-6 (E-l, E-2 ): Q2V0257, Q2V0258 Category: A (QV0254,. QV0257, QV0258)

B (QV0565A, B)

Class: 2 Function: QV0254 - Letdown line CIV.

QV0257 & QV0258 - CVCS Charging Pump Discharge to Regen. Hx.

QV0565A, B - CVCS Letdown Line Isolation.

Quarterly Test Exercise and time per ISTC-3510 and 5121 (QV0257, QV0258).

Requirements: Exercise, time and fail per ISTC-3510, 5131, and 3560 (QV0254, QV0565A, QV0565B).

Cold Shutdown These valves are in the normal letdown and charging lines to the RCS.

Test Exercising during normal operation would disrupt normal RCS charging flow Justification: which could decrease significantly the capability of the CVCS to provide the proper boration ratio. Failure of each valve in the closed position, coincident with normal charging flow, could result. in a high RCS water level trip.

Because of these reasons and a potential for thermal shock to the Regenerative Heat Exchanger, valve testing will be delayed to cold shutdown.

Quarterly Part None, valves are equipped with full-stroke-only operators and cannot be Stroke partial-stroke exercised.

Exercising:

Cold Shutdown Exercise and time (QV0257, QV0258).

Testing: Exercise, time and fail (QV0254, QV0565A,B).

Cold shutdown testing will be performed per ISTC-3521 (c).

ISTPgmVLVCSJ_4thlnt.doc 13-10 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-9 System: SI/CVCS (E21)

Valve: QI (2)E2 1V0336A, B, Q 1(2)E2 1V0376A, B Other Valve No: LCV115B, LCV115D, LCVI15C, LCV115E Drawing: D-175039-6 (B-9, F-9); D-175039-2 (H-8, H-8)

D-205039-6 (B-9, F-9); D-205039-2 (14-8, H-8)

Category: B Class: 2 Function: QV0336A, B - Charging Pump Suction from RWST.

QV0376A, B - VCT Outlet Isolation.

Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Cold Shutdown The RWST line block valves are interlocked to the VCT line block valves such Test that both sets cannot be opened at the same time. To exercise the VCT line Justification: block valves closed would require opening the RWST line block valves. If a RWST line block valve is opened during normal operation with a charging pump in operation, RWST water would be injected into the RCS. Injection of the highly borated RWST water into the RCS would adversely affect the boric acid concentration in the RCS and could cause a rapid decrease in RCS reactivity and temperature.

Quarterly Part None, valves full-stroke on initiation and cannot be partial-stroke exercised.

Stroke Exercising:

Cold Shutdown Exercise and time per ISTC-3521(c).

Testing:

ISTPgm_VLVCSJ_4thint.doc 13-11 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTMICATION CSJ-V-10 System: SI/CVCS (E21)

Valve: Q 1(2)E21V0220A, B Other Valve No: 8114A, B Drawing: D-175039-3 (F-5, H-5)

D-205039-3 (F-5, H-5)

Category: C Class: 3 Function: Boron Transfer Pump Discharge Line Check Valve.

Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Cold Shutdown The only way to verify full forward flow operability is by pumping Test concentrated boric acid from the boric acid tank through the inline flow Justification: element to the charging pump suction header. During normal operation, at least one charging pump is in operation such that concentrated boric acid would be injected directly into the reactor coolant system. The addition of concentrated boric acid to the reactor coolant system during normal operation would adversely affect RCS reactivity and temperature, and could cause a forced plant shutdown.

Quarterly Part NA Stroke Exercising:

Cold Shutdown Full-forward-flow operational readiness will be verified by measuring boric Testing: acid transfer flow rate at cold shutdown.

ISTPgmVLVCSJ_4thlnt.doc 13-12 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-1l System: SI/CVCS (E21)

Valve: Q 1(2)E21 V0265 Other Valve No: 8106 Drawing: D-175039-2 (H-4)

D-205039-2 (D-4)

Category: B Class: 2 Function: Charging Pump Minimum Flow Common Line Isolation Valve.

Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Cold Shutdown This valve ensures pump cooling for all three HHSI pumps. Should an Test automatic ECCS actuation occur with this valve closed, there may be Justification: insufficient pump flow for all pumps to remain cooled.

Quarterly Part None, partial-valve exercising is precluded for the same reason as full-stroke Stroke exercising.

Exercising:

Cold Shutdown Exercise and time per ISTC-3521 (c).

Testing:

ISTPgmVLVCSJ_4thlnt.doc 13-13 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-12 System: Main Steam (N 1l)

Valve: QI(2)NI IV0001A, B, C and QI(2)N11V0002A, B, C Other Valve No: HV3369A, B, C and HV3370A, B, C Drawing: D-175033-1 (G-7, E-8, B-8, G-8, E-8, B-8)

D-205033-1 (G-7, E-8, B-8, G-8, E-8, B-8)

Category: BC Class: 2 Function: Main Steam Isolation Valves.

Quarterly Test Exercise, time and fail per ISTC-3510, 5131 and 3560.

Requirements:

Cold Shutdown Exercising these valves during normal operation isolates one line of steam flow Test to the turbine and would cause a severe pressure transient in the main steam Justification: line which could result in a forced plant shutdown. Reducing power level to perform testing without causing a transient would significantly impact plant operations and power production.

Quarterly Part None. ISTC-3521(b) requires a partial exercise test quarterly if practical.

Stroke The MSIVs are equipped with a test circuit that allows the valves to be Exercising: partial exercised (approx. 10% closure) during operation at power. However, there have been numerous plant events reported in NPRDS associated with partial exercising the MSIVs during normal operation. These events involved instances where the test circuit did not function properly and the tested valve went full closed, resulting in a pressure transient and a subsequent plant trip. Therefore, no partial exercising will be performed during operation at power. (AIT 2002201825)

Cold Shutdown Exercise, time, and fail per ISTC-3521(c).

Testing:

ISTPgmVLVCSJ_4thlnt.doc 13-14 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-13 System: Main Steam (N 11)

Valve: QI(2)N11V0003A, B, C, D, E, and F Other Valve No: HV3368A, B, C, D, E and F Drawing: D-175033-1 (G-7, E-8, C-8, G-8, E-8, C-8)

D-205033-1 (G-7, E-8. C-8, G-8, E-8, C-8)

Category: B Class: 2 Function: Main Steam Isolation Bypass.

Quarterly Test Exercise, time and fail per ISTC 3510, 5131 and 3560.

Requirements:

Cold Shutdown These valves are interlocked with the main steam isolation valves and cannot Test be opened when the main steam isolation valves are open.

Justification:

Quarterly Part None, valves full-stroke on initiation and cannot be partial-stroke exercised.

Stroke Exercising:

Cold Shutdown Exercise, time, and fail per ISTC-3521(c).

Testing:

ISTPgm_VLVCSJ_4thlnt.doc 13-15 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-14 System: Feedwater (N21)

Valve: QI(2)N21VOOOA. B, C Other Valve No: MOV3232A, B, C Drawing: D-175073 (G-7, E-7, B-7)

D-205073 (G-7, E-7, B-7)

Category: BC Class: 2 Function: Main Feedwater Supply.

Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Cold Shutdown Exercising these valves closed during normal operation would result in a loss Test of feedwater to the associated steam generator. Isolation of feedwater flow Justification: during normal operation would cause a severe steam generator operating transient which could result in a forced plant shutdown and/or reactor trip.

Quarterly Part None, valves full-stroke on initiation and cannot be partial-stroke exercised.

Stroke Exercising:

Cold Shutdown Exercise and time per ISTC-3521(c).

Testing:

ISTPgmVLVCSJ_4thlnt.doc 13-16 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ.V-15 System: Auxiliary Feedwater (N23)

Valve: QI(2)N23V0002A, B, C, D, E, F, G, H Qi(2)N23V0003, Ql(2)N23V0006, Qi(2)N23V0007A, B.

Ql(2)N23V0011 A, B, C Other Valve No: NA Drawing: D-175007 (B-6, E-6, B-9, C-9, D-9, F-9, G-9, H-9, G-6, H-3, B-3, E-3, B-10, D-10, G-10)

D-205007 (B-6, E-6, B-9, C-9, D-9, F-9, G-9, H-9, G-6, H-3, B-3, E-3, B-10, D-10, G-10)

Category: C Class: 2 (QVOO1 1A, B, C) 3 (QV0002A, B, C, D, E, F, G, H, QV0003, QV0006, QV0007A, B)

Function: QV0002A, B - MDAFW Pump Discharge to SGs.

QV0002C, E, G - MDAFW Discharge Check Valve to SGs.

QV0002D*, F*, H* - TDAFW Discharge Check Valve to SGs.

QV0003* - TDAFW Pump Discharge Check Valve.

QV0006* - TDAFW Pump Suction Check Valve.

QV0007A, B - MDAFW Pump Suction Check Valve.

QVOO 11A, B, C - AFW Discharge to SGs.

Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Cold Shutdown The only way to full forward-flow exercise these valves is by operating the Test associated auxiliary feedwater pump and injecting relatively cold condensate Justification: water directly into the steam generators. The introduction of cold water into the hot steam generators during operation would result in large thermal shock to the feedwater nozzles and could cause cracking of the nozzles.

Quarterly Part NA Stroke Exercising:

Cold Shutdown Valves will be full-forward-flow exercised by injecting into the steam Testing: generators at cold shutdown per ISTC-3522(b).

To perform a full forward flow test for the TDAFW check valves, sufficient motive force is not achieved until the plant enters Mode 3 following cold shutdown. Therefore, the TDAFW check valves will be full-forward flow tested prior to leaving Mode 3, following cold shutdown.

ISTPgmVLVCSJ_4thlnt.doc 13-17 Version 1.0

VLVCSJ.Doc Those check valves that do not perform a safety function in the reverse direction will be bi-directionally exercised to their non-safety related, closed position during refueling outages by performing an individual pressure decay, flow type test or utilize other positive means for each valve.

ISTPgmVLVCSJ_4thlnt.doc 13-18 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-16 System: Auxiliary Feedwater (N23)

Valve: QI(2)N23V0002D, F, H Other Valve No: NA Drawing: D-175007 (C-91 F-9, H-9)

D-205007 (C-9, F-9, H-9)

Category: C Class: 3 Function: TDAFW Discharge to SGs.

Quarterly Test Verify reverse flow closure per ISTC-35 10 and 5221.

Requirements:

Cold Shutdown There are no system design provisions for verification of reverse flow Test closure. The only practical method to verify closure is by operating one of Justification: the MDAFW pumps and performing an individual flow test or pressure decay type test which confirms TDAFW discharge to SG check valve closure. Performing this type of test is impractical during normal operation since it renders the entire AFW system inoperable for an extended period of time.

Quarterly Part NA Stroke Exercising:

Cold Shutdown Reverse flow closure will be confirmed by performing an individual pressure Testing: decay or flow type test for each valve at cold shutdown and refueling. This test will confirm that the check valves are capable of reverse flow closure.

ISTPgm_VLVCSJ_4thlnt.doc 13-19 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-17 System: Auxiliary Feedwater (N23)

Valve: Q1(2)N23V0006, Q1(2)N23V0007A, B Other Valve No: NA Drawing: D-175007 (H-3, B-3, E-3)

D-205007 (H-3, B-3, E-3)

Category: C Class: 3 Function: QV0006 - TDAFW Pump Suction from CST.

QV0007A, B - MDAFW Pump Suction from CST.

Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Cold Shutdown There are no system design provisions suitable for verification of reverse Test flow closure. The only practical method to verify closure would involve Justification: isolating the condensate storage tank and performing a pressure decay type test which confirms that the check valve is closed. Performing this type test during normal operation would render the associated AFW pump inoperable for an extended period of time.

Quarterly Part NA Stroke Exercising:

Cold Shutdown Reverse flow closure will be confirmed by performing a pressure decay type Testing: test during cold shutdown and refueling. This pressure decay test will confirm that the check valve is capable of reverse flow closure.

ISTPgm-VLVCSJ_4thlnt.doc 13-20 Version 1.0

VLVCS).Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-18 System: Containment Purge (P13)

Valve: QI(2)PI3V0281, QI(2)PI3V0282, QI(2)P13V0283, Q1(2)Pl3V0284 Other Valve No: HV3198D, HV3197, HV3196, HV3198A Drawing: D-175010-1 (G-10, E-10): QV0282, & QV0283 D-175010-2 (F-3, D-3): QV0281 & QV0284 D-205010-1 (G-9, E-9): QV0282, & QV0283 D-205010-2 (F-3, D-3): QV0281 & QV0284 Category: A Class: 2 Function: QV0281, QV0282 - Purge Supply Damper.

QV0283, QV0284 - Purge Exhaust Damper.

Quarterly Test Exercise, time, and fail per ISTC-3510, 5131 and 3560.

Requirements:

Cold Shutdown Plant Technical Specifications require maintaining these valves closed during Test plant operating modes 1, 2, 3, and 4.

Justification:

Quarterly Part None, valves are administratively maintained closed during normal operation.

Stroke Exercising:

Cold Shutdown Exercise, time, and fail per ISTC-3521(c).

Testing:

ISTPgmVLVCSJ 4thlnt.doc 13-21 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V.19 System: Service Water (P16)

Valve: Q 1(2)P 16V0514, Q I (2)P16V0515, Q 1(2)P 16V0516, Q I (2)P16VO517 Q 1(2)P 16V0540, Q I (2)P 16V054 1, Q 1(2)P 16V0542, Q 1(2)PI 6V0543 Other Valve No: NA Drawing: D-170119-2 (E-6, E-4, D-5, D-4, D-9, B-9, D-10, B-10)

D-200013-2 (E-5, E-4, D-5, D-3, D-9, B-9, D-10, B-10)

Category: B Class: 3 Function: QV0514, QV0515, QV0516, QV0517 - SW Supply to Turbine Bldg.

QV0540, QV0541, QV0542, QV0543 - SW Return from Turbine Bldg.

Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Cold Shutdown The design of the turbine building service water supply and return system Test makes inadvertent service water isolation possible while exercising these Justification: valves. This is possible because train separation is not maintained downstream of the supply isolation valves and there are flow sensing devices in each train. These devices are designed to isolate the turbine building on a high flow condition resulting from a large line break. As the flow to one train is isolated during valve exercising, the flow through the other train will increase and possibly exceed the maximum flow limit, resulting in automatic service water isolation and a resultant turbine trip.

Quarterly Part None, valves full-stroke on initiation and cannot be partial-stroke exercised.

Stroke Exercising:

Cold Shutdown Exercise and time per ISTC-3521 (c).

Testing:

ISTPgmVLVCSJ_4thlnt.doc 13-22 Version 1.0

VLVCSJ.Doc COLD SHUTDOWN JUSTIFICATION CSJ-V-20 Valve: Q 1(2)P 19V0004 Other Valve No- NA Drawing: D-175034-1 (D-10)

D-205034-4 (B-6)

System: Instrument Air (P1 9)

Category: AC Class: 2 Function: Backup Air Supply to Pressurizer PORVs.

Quarterly Test Verify forward flow operational readiness per ISTC-35 10 and 5221.

Requirements:

Cold Shutdown The only practical way to forward flow exercise this valve would be to isolate Test the normal instrument air supply to the PORVs, utilize the backup nitrogen Justification: supply and exercise a PORV. Isolating the normal instrument air supply outside the containment (HV361 1) results in isolation of the normal air supply to all components located inside the containment that rely on normal instrument air for their supply. thus rendering them inoperable. Isolating the normal instrument air supply to the PORVs only (V0139) requires a containment entry which is not practical during normal operation.

Quarterly Part NA.

Stroke Exercising:

Cold Shutdown Valve will be forward-flow exercised by exercising a PORV at cold shutdown Testing: per ISTC-3522(b).

ISTPgnVLVCSJ_4thlnt.doc 13-23 Version 1.0

14.0 VALVE REFUELING OUTAGE JUSTIFICATION LOG ROJ Component ID Status ROJ-V-1 Q1(2)B13V0038 ROJ-V-2 QI(2)B13V0054 ROJ-V-3 QI(2)E1 1V0042A & B ROJ-V-4 QI(2)E1 1V0051A, B & C ROJ-V-5 QL(2)EIIV0021A, B & C ROJ-V-6 QI(2)E1 1V0028 ROJ-V-7 QI(2)E13VO002A & B ROJ-V-8 Ql(2)E13V00014 ROJ-V-9 Q 1(2)E 14VOOO1 ROJ-V- 10 Q I (2)E2 1V0026 ROJ-V- 1I QI(2)E21V0052 QI (2)E21 V0058 ROJ-V- 12 QI (2)E21V0119 ROJ-V-13 Ql(2)E21V0062A, B &C Q1(2)E21V0066A, B &C Q1(2)E21V0078A, B &C Q1(2)E21V0079A, B&C ROJ-V-14 Q1(2)E21VOOI6A & B Q I (2)E2 1V0063 Ql(2)E21V0068 QI (2)E21 V0072 ROJ-V-15 QI(2)E21VO1 15A, B & C ROJ-V-16 QI(2)E21V0122A, B & C ROJ-V-17 Ql(2)E21V0249A & B ROJ-V-18 Q1(2)E21V0077A, B & C 1STPgm_VLVROJ4thlnt.doc 14-1 Version 1.0

ROJ Component ID Status ROJ-V-19 QI(2)E21V0032A, B & C QI(2)E21V0037A, B & C ROJ-V-20 Q 1(2)E21V0213 ROJ-V-21 QI(2)E21V0076A & B ROJ-V-22 Q 1(2)E21V0326A & B QI(2)E21V0327A & B ROJ-V-23 QI(2)E21VO121A, B & C ROJ-V-24 QI (2)G2 I V0204 ROJ-V-25 Q 1(2)G21 V0291 ROJ-V-26 QI(2)N12VO010A & B ROJ-V-27 Q1(2)N23V0013A & B Ql(2)N23V0014A, B & C ROJ-V-28 Q1(2)P16V0075 ROJ-V-29 Q1P16V0635A & B Q1P16V0636A & B Q2P16V0635B Q2PI 6V0636B ROJ-V-30 QI(2)P16V0206A, B, C & D ROJ-V-31 Q 1(2)P 16V0659 QI (2)P16V0660 ROJ-V-32 Ql(2)PI6V0564 QI(2)P16V0565 ROJ-V-33 Qi (2)P 17V0082 Ql(2)P17V0097 QI (2)Pl 7V0099 QI (2)P17HV3045 Q1(2)P17HV3184 ROJ-V-34 Ql(2)P17V0083 Ql(2)P17V0159 ISTPgmVLVROJ4thlnt.doc 14-2 Version 1.0

ROJ Component ID Status ROJ-V-35 Ql(2)P17V0087A, B & C ROJ-V-36 Q1(2)P17HV3067 Qi (2)Pl 7HV3095 Q I(2)PI 7HV3443 ROJ-V-37 Q1(2)P17VO111 ROJ-V-38 QI(2)P19V0002 ROJ-V-39 Q 1(2)P19V0004 ROJ-V-40 Q1(2)P19HV3611 ISTPgmVLVROJ4thInt.doc 14-3 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-1 System: Reactor Coolant (1 13)

Valve: QI(2)B 13V0038 Other Valve No: 8046 Drawing/Coord: D-175037-2 (1-10)

D-205037-2 (B- 10)

Category: AC Class: 2 Function: Reactor Makeup Water to PRT Isolation Check Valve Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for This check valve is located inside the containment and any method to Justification: confirm closure would require a containment entry. The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. The Type C test requires isolating reactor makeup water to the PRT spray nozzles, and to the reactor coolant pump(s) seal #3.

The potential for relief valve discharge into the PRT exists during cold shutdown and the condensing effect of the RMW spray into the PRT may be required to condense any vaporization of the relief valve discharge.

Also, at least one of the reactor coolant pumps is required to be in service during cold shutdown for chemistry control purposes, thus requiring seal water. These factors make testing during cold shutdown impractical. In addition, NRC NUREG 1482, Rev. I Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test or, other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6. Bi-directional exercising in the non-safety related forward direction will be satisfied by normal system operation.

IST_Pgm_VLVROJ4thInt.doc 14-4 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-2 System: Reactor Coolant (B 13)

Valve: Qi (2)B 13V0054 Other Valve No: 8092 Drawing/Coord: D- 175037-2 (C-6)

D-205037-2 (C-6)

Category: AC Class: 2 Function: CVCS Charging Pump Relief Valve Discharge to PRT Quarterly Test Full forward-flow exercise and verify reverse flow closure per ISTC-3510 Requirements: and 5221.

Basis for This check valve is located in the CVCS charging and RHR pump relief Justification: valve discharge header. The header routes discharge from the relief valves to the PRT. Quarterly verification of reverse flow closure of this valve is not practicable because it is located inside containment and is not equipped with any instrumentation to allow confirmation of position. Verification of forward flow operability is not possible because there is no installed instrumentation or other positive means to make this determination at any plant condition.

The only practical way of verifying valve closure is by performing a seat leakage type test, such as the Appendix J, Type C test. The Type C test for this valve requires the removal of a spool piece from the common relief valve discharge line and the installation of a blind flange. This activity would be unsafe while the systems protected by the relief valves were in service. These relief valves include those protecting the RHR system, which is in service during cold shutdown conditions. These factors make testing during cold shutdown impractical. In addition, the NRC in NUREG 1482, Rev. 1, Section 4.1.6, has stated that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

ISTPgm_VLVROJ4thlnt.doc 14-5 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-2 (continued)

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J. Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

Forward flow operability will be determined during refueling outage by disassembly and manually full stroking the valve per ISTC-5221(c). The valve will be part-stroke exercised in the forward direction subsequent to reassembly, if practicable.

1ST_PgmVLVROJ4thlnt.doc 14-6 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-3 System: LHSI/RHR (Eli)

Valve: Q1(2)EI 1V0042A, B Other Valve No: 8974B, A Drawing/Coord: D-175038-2 (G-2, E-2)

D-205038-2 (G-2, E-2)

Category: AC Class: 2 Function: RI-R Pump Discharge to SIS Injection CL Quarterly Test Verify reverse flow closure and full forward-flow exercise per ISTC-3510 Requirements: and 5221.

Basis for Quarterly verification of reverse flow closure is not practicable because the Justification: valves are located inside the containment, they are not equipped with any instrumentation to allow closure verification, and any testing would require personnel entry into the containment. The only practical way of verifying valve closure is by performing a leakage type test. These are PIVs and are required to be leak tested per Tech Specs. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leak rate test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified in conjunction with the PIV leakage Outage testing in accordance with the Technical Specification surveillance Testing: requirement. This testing is consistent with the guidance found in NUREG-1482, Rev. 1, Section 4.1.6. Valves will be full-forward flow exercised each refueling outage.

ISTPgmSVLVROJ4thInt.doc 14-7 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V.4 System: LHSI!RHR (E 1i)

Valve: QI(2)El IV0051A, B, C Other Valve No: 8998A, B, C Drawing/Coord: D-175038-1 (C-2, D-2, D-2)

D-205038-1 (C-2, D-2, D-2)

Category: C Class: 1 Function: RCS Loop LHSI CL Quarterly Test Full forward-flow operational readiness per ISTC-3510 and 5221.

Requirements:

Basis for These 6 inch Velan swing check valves are located in the shared, high Justification: head/low head, safety injection lines to the RCS cold legs. The more conservative flow path testing for these valves is via the low head safety injection lines. Individual line flow rate cannot be utilized to verify individual valve full-flow exercising quarterly, or at cold shutdown because there is not installed flow instrumentation when testing via the low head safety injection lines. Confirmation of full-stroke exercise will be by non-intrusive check valve testing technology or valve disassembly. This test can only be performed at refueling with the RCS depressurized.

Refueling Valves will be full-forward flow exercised using nonintrusive testing each Outage refueling. Alternately, the check valve(s) may be disassembled and Testing: manually full stroked, on a sampling basis per ISTC-5221(c), during the refueling outage to verify operability. Partial stroking after reassembly is not practical for the reasons stated above.

IST_Pgm.VLVROJ4thlnt.doc 14-8 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-5 System: LHSI/RHR (El 1)

Valve: QI(2)E11V0021A, B, C Other Valve No: 8973A, B, C Drawing/Coord: D-175038-2 (E-1, F-I, G-1)

D-205038-2 (E-1, F-1, G-1)

Category: AC Class: 1 Function: RHR Pump Discharge to SI (CL)

Quarterly Test Verify forward-flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for These 6 inch Velan swing check valves are located in the LHSI paths to the Justification: RCS cold legs. The more conservative flow path testing for these valves is via the low head safety injection lines. Individual line flow rate cannot be utilized to verify individual valve full-flow exercising quarterly, or at cold shutdown because there is not installed flow instrumentation when testing via the low head safety injection lines. Confirmation of full-stroke exercise will be by nonintrusive check valve testing technology or valve disassembly. This test can only be performed at refueling with the RCS depressurized.

Quarterly verification of reverse flow closure is not practicable because the valves are located inside the containment, they are not equipped with any instrumentation to allow closure verification, and any testing would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test. These are PIVs and are required to be leak tested per Tech Specs. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leak rate test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

IST_Pgm VLVROJ4thlnt.doc 14-9 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-5 (continued)

Refueling Valves will be full-forward flow exercised using nonintrusive testing each Outage refueling outage. Alternately, the check valve(s) may be disassembled and Testing: manually full stroked, on a sampling basis per ISTC-5221(c), during the refueling outage to verify operability.

Reverse flow closure will be verified in conjunction with the PIV leakage testing in accordance with the Technical Specification surveillance requirement. This testing is consistent with the guidance found in NUREG-1482, Section, Rev. 1, Section 4.1.6. Partial stroking after reassembly is not practical for the reasons stated above.

ISTPgm_VLVROJ4thInt.doc 14-10 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-6 System: LHSI/RHR (El 1)

Valve: QI(2)EI 1V0028 Other Valve No: 8958 Drawing/Coord: D-175038-2 (F-11)

D-205038-2 (F- 11)

Category: C Class: 2 Function: LHSI/RHR Pump Suction from RWST Quarterly Test Verify reverse flow closure capability in accordance with ISTC-3510 and Requirements: 5221.

Basis for There are no system design provisions to allow closure verification for Justification: QV0028. The only practical method to verify valve closure is by performing an individual flow test or pressure decay type test utilizing leakrate type test equipment. Performing this type test is impractical during normal operation since it renders the entire RHR system inoperable for an extended period of time. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leakage type test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure of QV0028 will be verified by a pressure decay or flow Outage type test, or other positive means during refueling outages when the RHR Testing: system is not required to be operable.

ISTPgm VLVROJ4thlnt.doc 14-11 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-7 System: Containment Spray (El 3)

Valve: Q1(2)El3VO002A, B Other Valve No: 8822A, B Drawing/Coord: D-175038-3 (C-2)

D-205038-3 (C-2)

Category: C Class: 2 Function: Containment Spray Pump Discharge Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability in accordance with ISTC-3510 and 5221.

Basis for The only way to verify forward-flow operability during normal operation or Justification: cold shutdown would be by using the pumps and injecting a large quantity of water into the containment. Spraying the containment would result in extensive damage to safety-related equipment located inside the containment.

Quarterly verification of reverse flow closure for QV0002A, B is not practicable because the valves are located inside containment, they are not equipped with any instrumentation to allow closure verification, and any testing would require personnel entry into the containment.

Refueling Full forward-flow exercise will be proven with the CPT during each Outage refueling outage. Reverse flow closure will be verified by a leakage test Testing: similar to the Type C test, or other positive means, during each refueling outage.

ISThPgm._VLVROJ4thlnt.doc 14-12 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-8 System: Containment Spray (E 13)

Valve: Q1(2)E13V0014 Other Valve No: 8816 Drawing/Coord: D-175038-3 (E-10)

D-205038-3 (E-10)

Category: C Class: 2 Function: Containment Spray Pump Suction from RWST Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability in accordance with ISTC-3510 and 5221.

Basis for The only way to verify forward-flow operability during normal operation or Justification: cold shutdown would be by using the pumps and injecting a large quantity of water into the containment. Spraying the containment would result in extensive damage to safety-related equipment located inside the containment.

There are no system design provisions to allow closure verification for QV0014. Nonintrusive techniques cannot be successfully employed to test this valve. This valve is located in the 12" Containment Spray (CS) pump suction line from the Refueling Water Storage Tank (RWST). The only normal water flow through this valve is approximately 150 gpm during quarterly CS pump testing. SNC engineers experienced with nonintrusive check valve testing indicate that this application will not be successful because the 12" check valve will not fully open with 150 gpm flow.

The only practical method to verify valve closure is by performing an individual flow test or pressure decay type test utilizing leakrate type test equipment. Performing this type test is impractical during normal operation since it renders the entire CS system inoperable for an extended period of time. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leakage type test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

ISTPgmVLVROJ4thlnt.doc 14-13 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-8 (continued)

Refueling Both units have been modified such that spool pieces can be installed Outage downstream of check valves QV0002A and QV0002B. During refueling, Testing: these spool pieces will be installed and a full-forward-flow test performed by pumping water through these full-flow test lines to the containment refueling cavity. Because of the time involved in installing the spool pieces and the large quantity of water necessary, this test can only be performed at refueling.

Reverse flow closure of QV0014 will be verified by a pressure decay or flow type test, valve disassembly, or other positive means.

ISTPgm_VLVROJ4thlnt.doc 14-14 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-9 System: Containment Cooling & Purge (E14)

Valve: Q1(2)E14V0001 Other Valve No: NA Drawing/Coord: D-175010-2 (A-2)

D-205010-2 (A-2)

Category: AC Class: 2 Function: CTMT Air Sample Check Valve Quarterly Test Verify reverse-flow closure per ISTC-3510 and 5221.

Requirements:

Basis for Quarterly verification of reverse flow closure is not practicable because the Justification: valve is located inside containment, is not equipped with any instrumentation to allow closure verification, and any testing method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test such as the Appendix J, Type C test. Type C testing this valve requires removal of the containment air sampler from service and the installation of a blind flange downstream of the valve inside the containment. The air sampler is required to be in operation during cold shutdown conditions. Therefore, testing during cold shutdown is impractical. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

lST_PgmVLVROJ4thlnt.doc 14-15 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-10 System: SI/CVCS (E21)

Valve: QI(2)E21 V0026 Other Valve No: 8926 Drawing/Coord: D-175038-1 (E-12)

D-205038-1 (E-11)

Category: C Class: 2 Function: RWST to Charging Pump Suction Check Valve Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for The only practical method of full flow exercising this valve is by aligning the Justification: RWST to the charging pump suction and injecting full design flow into the RCS. Full flow exercising during normal operation is impossible because the charging pumps cannot develop full rated flow against RCS pressure.

Injecting the highly borated RWST water into the RCS during normal operation would adversely affect reactivity and RCS temperature.

The only practical way of verifying valve closure is by performing an individual flow test, or pressure decay type test, utilizing leakrate type test equipment. NRC NUREG- 1482, Rev. 1, Section 4.1.6, states that the need to set up leakrate type test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling The valve will be full exercised with flow during each refueling outage.

Outage Reverse flow closure will be verified by a pressure decay or flow type test, or Testing: other positive means.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-11 System: SI/CVCS (E21)

Valve: QI(2)E21V0052, Q1(2)E21V0058 Other Valve No: 8861, 8947 Drawing/Coord: D-175038-2 (D-9, A-10)

D-205038-2 (D-9, A-10)

Category: AC Class: 2 Function: QV0052 - SIS Accum. Fill QV0058 - Nitrogen Supply to Accumulator Tanks Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for Quarterly verification of reverse flow closure is not practicable because the Justification: valve is located inside containment, is not equipped with any instrumentation to allow closure verification, and any testing method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6. Bi-directional exercising in the non-safety related open direction will be satisfied by normal system operation.

IST_Pgm_VLVROJ4thlnt.doc 14-17 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-12 System: SICVCS (E21)

Valve: Qi(2)E21V0119 Other Valve No: 8381 Drawing/Coord: D-175039-I (B-11)

D-205039-1 (B-11)

Category: AC Class: 2 Function: CVCS Charging Pump Discharge to Regenerative Hx Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for Quarterly verification of reverse flow closure is not practicable because Justification: charging water flow is required during normal operation. Additionally, the valve is located inside containment, is not equipped with any instrumentation to allow closure verification, and any testing method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

ISTPgmVLVROJ4thlnt.doc 14-18 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-13 System: SI/CVCS (E21)

Valve: Qi (2)E21V0062A,B,C / Qi (2)E21V0066A,B,C / Qi (2)E21VO078A,BC /

Qi (2)E21V0079A,B,C Other Valve No: 8997A,B,C / 8995A,B,C / 8990AB,C / 8992A,B,C Drawing/Coord: D-175038-1 (E-3, E-3, F-3 / A-4, B-4, C-4 / G-3, G-3, G-3 / G-3, G-2, G-2)

D-205038-1 (E-3, E-3, F-3 / A-4, B-4, C-4 / G-3, G-3, G-3 / G-3, G-2, G-2)

Category: C Class: 1 Function: QV0062A,B,C - HHSI to RCS CL QV0066A,B,C - Charging (HHSI) Pump Discharge to RCS (CL)

QV0078A,B,C - HHSI Pumps Discharge to RCS Loops (HL)

QV0079A,B,C - HHSI Pumps Discharge to RCS Loops (HL)

Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Basis for It is impractical to full-stroke any of these check valves with flow during Justification: normal operation because all of the associated flow paths bypass the regenerative heat exchanger, and establishing flow through these valves would result in relatively cold water being injected into the RCS. The thermal stresses produced by injecting cold water could greatly reduce the service life of the injection nozzles. Additionally, pressurizer level would rise uncontrollably during the test possibly leading to an RCS pressurizer high level Rx trip.

These valves cannot be full-stroke exercised during cold shutdowns because the RCS may not contain sufficient expansion volume to accommodate the flow required, and a low temperature overpressure condition could occur.

In addition, initiating flow through valve QV0078A,B,C and QV0079A,B,C would also disturb RCS pressure isolation valves leading to further technical specification required testing.

ISTjPgmVLVROJ4thlnt.doc 14-19 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-13 (continued)

Refueling Valves will be full-stroke exercised with flow during each refueling outage.

Outage Either permanently installed or removable instrumentation will be utilized Testing: to confirm check valve exercising. Confirmation of full-stroke exercising will be either by flow measurement or by the use of nonintrusive check valve testing technology.

Bi-directional exercising in the non-safety related reverse direction will be demonstrated by the ability to establish differential pressure across the valve disc or other positive means.

IST_PgmVLVROJ4th~nt.doc 14-20 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-14 System: SI/CVCS (E21)

Valve: Q I(2)E21VO016A,B, QI (2)E21V0063, Q1(2)E21V0068, Ql(2)E21V0072 Other Valve No: 8803A,B / 8885 / 8886 / 8884 Drawing/Coord: D-175038-1 (B-6, H-7, J-6, G-7, G-7)

D-205038-1 (B-6, H-6, J-6, G-6, G-6)

Category: B Class: 2 Function: QV0016A,B - HHSI to RCS CL Isolation QV0063 - Charging (HHSI) Pumps Discharge to RCS (CL)

QV0068 - Charging (HHSI) Pumps Discharge to RCS (HL)

QV0072 - Charging (HHSI) Pumps Discharge to RCS (HL)

Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Basis for It is impractical to exercise these valves during normal operation because all Justification: of the associated flow paths bypass the regenerative heat exchanger, and establishing flow through these valves would result in relatively cold water being injected into the RCS. The thermal stresses produced by injecting cold water could greatly reduce the service life of the injection nozzles.

Additionally, pressurizer level would rise uncontrollably during the test possibly leading to an RCS pressurizer high level Rx trip.

These valves cannot be exercised during cold shutdowns because the RCS may not contain sufficient expansion volume to accommodate the flow required, and a low temperature overpressure condition could occur.

Q/CS Part These motor operated valves are not designed for partial stroke exercising.

Stroke Testing:

Refueling Exercise and time during refueling outage when the RCS is drained down to Outage the mid-plane level and all charging pumps are secured or placed in an Testing: alignment that allows testing.

ISTPgm_VLVROJ4thlnt.doc 14-21 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-15 System: SI/CVCS (E21)

Valve: Q1(2)E21 V0115A,B,C Other Valve No: 8368A,B,C Drawing/Coord: D-175039-1 (G-2 for all)

D-205039-1 (G-2 for all)

Category: C Class: 2 Function: CVCS Seal Injection to RCP Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for Reverse flow closure testing requires isolation of seal injection flow to the Justification: RCPs, therefore testing during normal operation is impractical.

Valves are located inside containment and testing requires personnel entry into the containment to position associated system valves and to set up testing equipment. Personnel entry into the containment and performance of this test has the potential to:

" increase personnel radiation exposure,

" increase the potential for RCP seal and bearing damage due to interruption of seal injection flow, and

" prolong the shutdown due to the stringent requirements on personnel entry into containment and the time required to perform the test.

Therefore, the only practical method available to verify reverse flow closure is by pressure decay or leak testing at each refueling outage.

Refueling Reverse flow closure will be confirmed by a pressure decay type test or leak Outage test (similar to Appendix J, Type C test) at each refueling outage. This type Testing: test will confirm that the check valve is capable of reverse flow closure. This is consistent with the guidance found in NRC NUREG-1482, Rev. 1, Section 4.1.6.

ISTPgmVLVROJ4thlnt.doc 14-22 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-16 System: SI/CVCS (E21)

Valve: Q 1(2)E21V0122A,B,C Other Valve No: 8481A,B,C Drawing/Coord: D-175039-6 (F-4, G-4, H-4)

D-205039-6 (C-6, E-6, G-5)

Category: C Class: 2 Function: Charging Pump Discharge Quarterly Test Verify forward-flow operational readiness per ISTC-3510 and 5221.

Requirements:

Basis for Charging flow during normal operation is automatically controlled by Justification: downstream flow control valve QV0347 in response to RCS operating conditions. To inject full flow into the RCS during normal operation would result in undesirable RCS boron concentrations and system pressure, temperature and level transients. Full-flow exercising these valves at cold shutdown would result in RCS pressure and level transients due to limitations on letdown capability.

Refueling Verification of full forward flow operational readiness will be performed Outage each refueling outage.

Testing:

ISTPgm_VLVROJ4thlnt.doc 14-23 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V.17 System: SI/CVCS (E21)

Valve: Qi(2)E21V0249A,B Other Valve No: 8112, 8100 Drawing/Coord: D-175039-1 (C- 11, C-11)

D-205039-1 (C- 11, C- 11)

Category: A Class: 2 Function: RCP Seal to Seal Water Hx Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Basis for Exercising these valves during normal operation or at cold shutdown results Justification: in a loss of normal seal water to the RCS pump seals. If seal water is terminated, reactor coolant is forced from the high pressure RCS into the seals. Reactor coolant normally contains a high particulate matter concentration which is carried with RCS in-leakage and contaminates the seals. Westinghouse has studied this problem (see FNP Manual U-214849, para. 6.1.1, Note 3) and recommends that seal flow be maintained at cold shutdown, as well as during normal operations.

Q/CS Part Partial exercising is precluded for the same reasons stated above.

Stroke Testing:

Refueling Exercise and time at refueling outages when the RCS is vented or open to the Outage atmosphere.

Testing:

1ST_PgmVLVROJ4thInt.doc 14-24 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-18 System: SIUCVCS (E21)

Valve: QI(2)E21V0077A,B,C Other Valve No: 8993A,B,C Drawing/Coord: D-175038-1 (F-2, G-2, G-1)

D-205038-1 (F-2, G-2, G-2)

Category: AC Class: 1 Function: HHSI/LHSI and RHR to RCS HL Quarterly Test Verify forward-flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for These 6 inch Velan swing check valves are located inside the containment Justification: on the safety injection lines to the RCS hot legs. The valves cannot be full-forward flow exercised quarterly or at cold shutdown because the individual injection lines are not equipped with flow measuring instrumentation.

Individual injection line flow rate can be measured for QV0077C in conjunction with the ECCS Branch Line flow conducted during each refueling outage. This test requires considerable test setup time and requires that the vessel head be removed to prevent possible overpressurization with a solid RCS. This test is only a partial flow test for valves QV0077A, B because these valves are also located in the LHSI flow path. Full-forward flow for QV0077A, B can only be verified using nonintrusive testing or valve sample disassembly each refueling. This test can only be performed at refueling with the RCS depressurized.

These valves are located inside the containment and are not equipped with any instrumentation that can be utilized to verify reverse flow closure. Any practical testing method would require personnel entry inside the containment. The only practical way of verifying valve closure is by performing a leakage type test. These are PIVs and are required to be leak tested per Tech Specs. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leak rate test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

ISTPgmVLVROJ4thlnt.doc 14-25 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-18 (continued)

Refueling Valve QV0077C will be full-forward flow exercised in conjunction with the Outage ECCS Branch Line flow test which is performed each refueling outage.

Testing: Valves QV0077A, B will be full forward flow exercised using nonintrusive testing each refueling. Alternately, the check valve(s) may be disassembled and manually full stroked on a sampling basis during the refueling outage to verify operability per ISTC-5221(c). Partial stroking after reassembly is not practical for the reasons stated above.

Reverse flow closure will be verified in conjunction with the PIV leakage testing in accordance with the Technical Specification surveillance requirement. This testing is consistent with the guidance found in NUREG-1482, Rev. 1, Section 4.1.6.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-19 System: SI/CVCS (E21)

Valve: Q I (2)E21 V0032A,B,C And Q I (2)E2 I V0037A,B,C Other Valve No: 8948A,BC And 8956A,B,C Drawing/Coord: D-175038-2 (D-2, D-2, E-1 And D-3, D-6, D-8)

D-205038-2 (D-2, D-2, E-2 And D-3, D-6, D-8)

Category: AC Class: 1 Function: Accumulator Tank Discharge to RCS (CL) Check Valves Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for The Safety Injection System (SIS) accumulator tanks are isolated from the Justification: Reactor Coolant System (RCS) by these normally closed check valves.

Each accumulator is charged with a nitrogen blanket from 601 to 649 psig.

This pressure is insufficient during normal operation to inject into the RCS.

If these valves were to be full exercised at cold shutdown, the contents of the tank would be dumped into the RCS at the charge pressure of 601 to 649 psig, which could result in overpressurization of the RHR suction lines, resulting in lifting the RHR suction relief valves.

The valves cannot be full-forward flow exercised quarterly or at cold shutdown because the individual lines are not equipped with flow measuring instrumentation. Full-forward flow can only be verified by observation of indirect evidence (such as changes in system pressure, flow, temperature, or level) or other positive means. This testing can only be performed at refueling with the RCS depressurized.

The only practical way of verifying valve closure is by performing a leakage type test. These are PIVs and are required to be leak tested per Tech Specs. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leak rate test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

ISTPgmVLVROJ4thlnt.doc 14-27 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-19 (continued)

Refueling Forward flow testing will be verified by the LUD value(s) for the check Outage valves and piping configurations are within acceptable limits, or verifying Testing: full open stroke by flow utilizing nonintrusive check valve diagnostic equipment. Alternately, the check valve(s) may be disassembled on a sampling basis per ISTC-5221(c) during refueling outage to verify operability. Partial stroking after reassembly is not practical for the same reasons stated above.

Reverse flow closure will be verified in conjunction with the PIV leakage testing in accordance with the Technical Specification surveillance requirement. This testing is consistent with the guidance found in NUREG-1482, Rev. 1, Section 4.1.6.

IST_PgmVLVROJ4thlnt.doc 14-28 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-20 System: SI/CVCS (E2 1)

Valve: Q I(2)E21 V0213 Other Valve No: 8103 Drawing/Coord: D-175039-1 (D-11)

D-205039-1 (D-11)

Category: AC Class: 2 Function: RCP Seal to Seal Water Hx Quarterly Test Verify forward-flow operational readiness and reverse flow closure capability Requirements: per ISTC-3510 and 5221.

Basis for This check valve provides for pressure equalization of the piping between Justification: CIVs QV0249A and QV0249B (Pen. 28) to provide over pressure protection should the RCP seal water return line be isolated during an accident. The valve, as part of the penetration, also provides a containment isolation function.

This valve is located inside containment and there is no instrumentation that could be utilized to verify forward flow exercising or reverse flow closure.

The only practical way of verifying valve closure is by performing a seat leakage type test such as the Appendix J, Type C test. The Type C test for these valves requires isolation of seal water to all three Reactor Coolant Pump seals. At least one of these pumps is in service during cold shutdown. This factor makes forward or reverse flow testing during cold shutdown impractical.

In addition, the NRC, in NUREG 1482, Rev. 1, Section 4.1.6, has stated that the need to set up Appendix 1, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

This valve does not have a design required forward flow rate since its only function is for containment isolation and pressure equalization due to thermal expansion of a water solid boundary. Therefore, any degree of opening of the check valve would be adequate to verify that it is capable of performing its thermal equalization function.

IST_Pgm_VLVROJ4thInt.doc 14-29 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-20 (continued)

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

Valve QV0213 will be verified to open each refueling outage by flowing air or water through the valve in the forward direction and observing flow out of an open test connection.

ISTPgmVLVROJ4thInt.doc 14-30 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-21 System: SI/CVCS (E21)

Valve: QI (2)E21V0076A,B Other Valve No: 8988A.B Drawing/Coord: D-175038-1 (F-4, G-4)

D-205038-1 (F-4, G-4)

Category: AC Class: I Function: Water from Residual Hx to SI to RCS Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for These valves are located inside the containment and are not equipped with Justification: any instrumentation that can be utilized to verify forward flow exercising or reverse flow closure. Any practical testing method would require personnel entry inside the containment. Confirmation of full-stroke exercise will be by nonintrusive check valve testing technology or valve sample disassembly. This test can only be performed at refueling with the RCS depressurized.

The only practical way of verifying valve closure is by performing a leakage type test. These are PIVs and are required to be leak tested per Tech Specs. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leak rate test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Valves will be full-forward flow exercised using nonintrusive testing each Outage refueling. Alternately, the check valve(s) may be disassembled and Testing: manually full stroked on a sampling basis per ISTC-05221(c) during the refueling outage to verify operability. Partial stroking after reassembly is not practical for the reasons stated above.

Reverse flow closure will be verified in conjunction with the PIV leakage testing in accordance with the Technical Specification surveillance requirement. This testing is consistent with the guidance found in NUREG-1482, Rev. 1, Section 4.1.6.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-22 System: SI/CVCS (E21)

Valve: QI(2)E21V0326A, B and QI(2)E21V0327A, B Other Valve No: 8132A, B and 8133A. B Drawing/Coord: D-175039-6 (D-5, E-5 and F-5)

D-205039-6 (D-5, E-5 and F-5)

Category: B Class: 2 Function: CVCS Charging Pump Discharge Header Block Valves Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Basis for These valves are normally open and remain open during safety injection.

Justification: During normal operation, only one charging pump is in operation supplying both charging water to the RCS and seal water to the RCS pump seals. To exercise these valves closed would require starting a second charging pump in order to continue to provide charging and seal water flow. Further, the closure of either of these valves places the high head safety injection system into an alignment different than that required for accident conditions.

Since these valves do not receive an automatic signal to open, re-alignment to their safety injection position would require operator action while responding to the accident situation. The low safety significance of these valves (Priority level 3), as established by the FNP MOV Program, does not warrant the risk of removing the system from the normal alignment.

None. The operating controls for these MOVs were not designed to allow Q/CS Part Stroke Testing: partial stroking.

Refueling Exercise and time at refueling outages.

Outage Testing:

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-23 System: SI/CVCS (E2 1)

Valve: QI(2)E21V0121A, B, C Other Valve No: 8480A,B,C Drawing/Coord: D-175039-6 (F-4, G-4, H-4)

D-205039-6 (F-4, G-4, H-4)

Category: C Class: 2 Function: Charging Pump Minimum Flow Line Check Valves Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Basis for The valves cannot be full-forward flow exercised quarterly, cold shutdown or Justification: during refueling outages because the charging pump minimum flow lines are not equipped with flow measuring instrumentation. Full-stroke exercising in the forward direction can only be verified by disassembly and inspection.

This activity can only be performed during refueling outages when the charging pumps can be removed from service.

Refueling The check valves shall be disassembled and inspected on a sampling basis Outage per ISTC-5221(c) during refueling outages to verify full opening capability.

Testing: The valves will be part-stroke exercised in the forward direction subsequent to reassembly.

ISTPgm_VLVROJ4thlnt.doc 14-33 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-24 System: Liquid Waste Disposal (G21)

Valve: Q 1(2)G2 IV0204 Other Valve No: NA Drawing/Coord: D-175004-1 (G-9)

D-205004-1 (G-9)

Category: AC Class: 2 Function: CTMT Sump Recirculation Quarterly Test Verify forward flow operational readiness and reverse flow closure Requirements: capability per ISTC-35 10 and 522 1.

Basis for This check valve provides for pressure equalization for containment Justification: penetration 33 in case of thermal expansion of trapped fluid in a post accident environment. It also provides a recirculation flow path to prevent pump runout, thus protecting the containment sump pumps. This valve is located inside containment and is not equipped with any instrumentation that can be utilized to verify forward flow exercising or reverse flow closure. Any practical testing method would require personnel entry inside the containment.

The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

This valve does not have a design required flow rate since its only function is for containment isolation and pressure equalization due to thermal expansion of a water solid boundary. Therefore, any degree of opening of the check valve would be adequate to verify that it is capable of performing its thermal equalization function.

ISTPgmnVLVROJ4thlnt.doc 14-34 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-24 (continued)

Refueling Reverse flow closure will be verified by an Appendix 1, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

Valve QV0204 will be verified to open each refueling outage by flowing air or water through the valve in the forward direction and observing flow out of an open test connection.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-25 System: Liquid Waste Disposal (G21)

Valve: Ql (2)G21 V0291 Other Valve No: NA Drawing/Coord: D-175004-1 (H-8)

D-205004-1 (H-8)

Category: AC Class: 2 Function: Containment Sump Pump Discharge Quarterly Test Verify forward-flow operational readiness and reverse flow closure Requirements: capability per ISTC-3510 and 5221.

Basis for This check valve provides for pressure equalization of the piping between Justification: CIVs HV3376 and HV3377 (Pen. 78) to provide over pressure protection should the containment sump pump discharge line be isolated during an accident. The valve, as part of the penetration, also provides a containment isolation function. This valve is located inside containment and there is no instrumentation that could be utilized to verify forward flow exercising or reverse flow closure.

The best and only practical way of verifying valve closure for this valve is by performing a seat leakage type test, such as the Appendix J, Type C test.

The NRC, in NUREG 1482, Rev. 1, Section 4.1.6, has stated that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

This valve does not have a design required flow rate since its only function is for containment isolation and pressure equalization due to thermal expansion of a water solid boundary. Therefore, any degree of opening of the check valve would be adequate to verify that it is capable of performing its thermal equalization function.

IST_PgmVLVROJ4thlnt.doc 14-36 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-25 (continued)

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

Valve QV0291 will be verified to open each refueling outage by flowing air or water through the valve in the forward direction and observing flow out of an open test connection.

ISTPgmVLVROJ4thlnt.doc 14-37 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-26 System: Auxiliary Steam (N12)

Valve: QI(2)N12V0010A, B Other Valve No: NA Drawing/Coord: D-175033-2 (E-6, C-6)

D-205033-2 (E-6, C-6)

Category: C Class: 2 Function: Main Steam to TDAFW Pump Turbine Check Valves Quarterly Test Verify reverse flow closure capability per ISTC-3510 and 5221.

Requirements:

Basis for The valves cannot be full-stroke exercised in the reverse direction quarterly, Justification: cold shutdown or during refueling due to the lack of upstream test connections or pressure instrumentation. Full-stroke exercising in the reverse direction can only be verified by disassembly and inspection. This activity can only be performed during refueling outages when the steam supply lines from the steam generators can be isolated and the TDAFW pump can be removed from service.

Refueling The check valves shall be disassembled and inspected on a sampling basis Outage per ISTC-5221(c) during refueling outages to verify full opening and Testing: closure capability. The valves will be part-stroke exercised in the forward direction subsequent to reassembly.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-27 System: Auxiliary Feedwater (N23)

Valve: Q1(2)N23V0013A, B, Q1(2)N23V0014A, B, C Other Valve No: MOV3210A, B, MOV3209A, B, MOV3216 Drawing/Coord: D-175007 (A-3, D-3, A-2, D-2, G-3)

D-205007 (A-3, D-3, A-2, D-2, G-3)

Category: B Class: 3 Function: QV0013A, B & QV0014A, B - MDAFW Pump Service Water Inlet Valve QV0014C - TDAFW Pump Service Water Inlet Valve Quarterly Test Exercise and time per ISTC-3510 and 5121.

Requirements:

Basis for Exercising these valves open during normal operation or at cold shutdown Justification: would introduce chlorides and fluorides into the auxiliary feedwater system and subsequently into the steam generators. The presence of chlorides and fluorides in the secondary water chemistry has been proven to contribute to steam generator degradation. Initiation of auxiliary feedwater during testing would inject a large quantity of service water directly into the steam generators. The only way to isolate the service water system from the auxiliary feedwater system to perform testing is by closing in line manual block valves QV0015E, QV0016A, and QV0016B. If an auxiliary feedwater initiation occurred during testing, one train of auxiliary feedwater would be disabled. In addition, there is no way to verify that subsequent flushing of the affected line has removed all of the service water contaminants.

Q/CS Part None. Partial valve exercising is precluded for the same reasons as stated Stroke Testing: above.

Refueling These valves will be exercised and timed each refueling outage when the Outage service water system can be isolated from the auxiliary feedwater system and Testing: extensive flushing of any residual service water can be performed.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-28 System: Service Water (P1 6)

Valve: Qi(2)P16V0075 Other Valve No: NA Drawing/Coord: D-175003-2 (B-9)

D-205003-2 (B-9)

Category: AC Class: 2 Function: Service Water to RCP Motor Coolers Quarterly Test Verify reverse-flow closure per ISTC-3510 and 5221.

Requirements:

Basis for This check valve is located inside containment and is not equipped with any Justification: instrumentation that can be utilized to verify reverse flow closure. Any practical test method would require personnel entry into the containment.

The best and only practical way of verifying valve closure for this valve is by performing a seat leakage type test, such as the Appendix J, Type C test. The Type C test for this valve requires the complete isolation of service water to all Reactor Coolant pump motor air coolers. At least one of the pumps is in service during cold shutdowns. The resulting additional heat input into containment, especially during the summer months, would cause habitability concerns during containment entry. This factor makes testing during cold shutdown impractical. In addition, the NRC, in NUREG 1482, Rev. 1, Section 4.1.6, has stated that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Outage Reverse flow closure will be verified by an Appendix J, Type C test, other seat Testing: leakage testing similar to the Type C test, or other positive means. The Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6. Bi-directional exercising in the non-safety related open direction is satisfied by normal system operation.

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REFUELING OUTAGE JUSTIFICATIONS ROJ.V-29 System: Service Water (P] 6)

Valve: Q1P16V0635A,B and Q1P16V0636A,B Q2P16V0635B and Q2P16V0636B Other Valve No: NA Drawing/Coord: D-175013 (E-2, E-11, E-2, E-11)

D-200014 (D-9 and D-9)

Category: C Class: 3 Function: Treated and Non-Treated SW to SW Pump Seals and Motor Coolers Quarterly Test Verify forward flow operational readiness and reverse-flow closure capability Requirements: per ISTC-3510 and 5221.

Basis for These check valves are located at the junction of cooling/lube water Justification: supplies from the cyclone separator (non-safety related) and the service water pumps. There are no system design provisions to facilitate monitoring any parameters that can be utilized to verify either full forward flow operational readiness or reverse-flow closure.

Refueling These valves will be disassembled and manually full stroke exercised on a Outage sampling basis per ISTC-5221(c) during refueling outages. The valve Testing: internals will be verified to be structurally sound (no loose or corroded parts), and the disk will be manually exercised to verify full stroke capability. The valves will be part stroked with flow after reassembly. The necessary valve obturator movement, verifying part stroke exercising, will be confirmed by changes in system pressure, temperature, proper sequencing of the cooling/lube water supplies from the cyclone separator and service water pumps, or other positive means, or through the use of ultrasonic (or similar) flow measuring devices. Part stroke exercising in the forward direction will be performed subsequent to reassembly.

ISTPgmVLVROJ4thlnt.doc 14-41 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-30 System: Service Water (P16)

Valve: Ql(2)P16V0206A, B, C, D Other Valve No: NA Drawing/Coord: D-175003-1 (E-2, E-11, E-2, E-1I)

D-205003-1 (A-7, C-7, E-7, F-7)

Category: C Class: 2 Function: SW to CTMT Coolers Check Valves Quarterly Test Verify reverse-flow closure per ISTC-3510 and 5221.

Requirements:

Basis for These check valves are located inside containment and are not equipped Justification: with any instrumentation that can be utilized to verify reverse flow closure quarterly, at cold shutdown or refueling outage. Nonintrusive techniques cannot be successfully employed to test this valve.

Refueling These valves will be disassembled and manually full stroke exercised on a Outage sampling basis per ISTC-5221(c) during refueling outages. The valve Testing: internal will be verified to be structurally sound (no loose or corroded parts), and the disk will be manually exercised to verify full stroke capability. The valves will be part stroked with flow after reassembly. The necessary valve obturator movement, verifying part stroke exercising, will be confirmed by changes in system pressure, temperature, or other positive means, or through the use of ultrasonic (or similar) flow measuring devices.

1ST Pgm_VLVROJ4thlnt.doc 14-42 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-31 System: Service Water (P16)

Valve: Ql(2)P16V0659, Ql(2)P16V0660 Other Valve No: NA Drawing/Coord: D-170119-3 (C-3, C-8)

D-200013-3 (C-3, C-10)

Category: C Class: 3 Function: Unit I Service Water Supply to Diesel Generator 2C and IC Check Valves Unit 2 Service Water Supply to Diesel Generator 2C and IC Check Valves Quarterly Test Verify reverse flow closure capability per ISTC-3510 and 5221.

Requirements:

Basis for The valves cannot be full-stroke exercised in the reverse direction quarterly, Justification: cold shutdown or during refueling due to the lack of upstream test connections or pressure instrumentation. Full-stroke exercising in the reverse direction can only be verified by disassembly and inspection. This activity can only be performed during refueling outages, when service water can be isolated, and the associated diesel generator is not required to be in standby.

Refueling The check valves shall be disassembled and inspected on a sampling basis Outage per ISTC-5221(c) during refueling outages to verify full opening and Testing: closure capability. The valves will be part-stroke exercised in the forward direction subsequent to reassembly.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-32 System: Service Water (P16)

Valve: Q1(2)P16V0564, Q(2)1P16V0565 Other Valve No: NA Drawing/Coord: D-170119-3 (G-2)

D-200013-3 (G-2)

Category: C Class: 3 Function: Unit 1 Diesel Generator Service Water Train Return Check Valves Unit 2 Diesel Generator Service Water Train Return Check Valves Quarterly Test Verify forward flow operational readiness per ISTC-3510 and 5221.

Requirements:

Basis for The valves cannot be full-stroke exercised with flow in the forward Justification: direction quarterly, cold shutdown or during refueling due to the lack of flow measuring instrumentation in the service water return headers. Full-stroke exercising in the forward direction can only be verified by disassembly and inspection. This activity can only be performed during refueling outages, when service water can be isolated, and the associated diesel generators are not required to be in standby.

Refueling The check valves shall be disassembled and inspected on a sampling basis Outage per ISTC-5221(c) during refueling outages to verify full opening and Testing: closure capability. The valves will be part-stroke exercised in the forward direction subsequent to reassembly.

ISTPgmVLVROJ4thlnt.doc 14-44 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-33 System: Component Cooling Water (P17)

Valve: Q 1(2)P17V0082, QI (2)P 17V0097, QI (2)P 17V0099, Q 1(2)P17HV3045, QIP17HV3184 Other Valve No: MOV3052, MOV3046, MOV3182, NA, NA Drawing/Coord: D-175002-2/C-1, B-5, C-6, D-6, D-5 D-205002-2/C- 1, B-6, C-7, D-6, D-6 Category: A Class: 2 Function: QV0082 - CCW to RCP QV0097/QV0099 - CCW Return from RCP Bearings HV3045/HV3184 - CCW Return from RCP Thermal Barrier Quarterly Test Exercise and time per ISTC-3510 and 5121 (QV0082, QV0097, QV0099).

Requirements: Exercise, time and fail per ISTC-3510, 5131 and 3560 (HV3045&HV3184).

Basis for These are the CIVs in the CCW supply and return lines to the RCP thermal Justification: barriers and bearing oil coolers. A loss of cooling water to these components for more than a few minutes could result in extensive damage to the reactor coolant pumps. Westinghouse recommends that cooling water be provided to these components at all times when RCS temperature is >_200' F. In addition, plant operating procedures require at least one RCP to be in operation when RCS temperatures are > 1600 F for hydrogen control of the reactor coolant. For short duration cold shutdowns, where the RCS temperature is maintained near 2000 F, stopping cooling water to these components could result in RCP degradation and unnecessary pump repairs.

Q/CS Part None. These valves full-stroke exercise on initiation and cannot be partial-Stroke Testing: stroke exercised.

Refueling Exercise, time, and fail (as appropriate) at each refueling outage when all Outage reactor coolant pumps are secured. This is consistent with NRC NUREG-Testing: 1482, Rev. 1, Section 3.1.1.4.

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REFUELING OUTAGE JUSTIFICATIONS ROJ.V-34 System: Component Cooling Water (P17)

Valve: QI(2)PI7V0083, QI(2)PI7V0159 Other Valve No: NA Drawing/Coord: D-175002-2 (C-2, E-2)

D-205002-2 (C-2, E-2)

Category: AC Class: 2 Function: QV0083 - CCW to RCP QV01 59 - CCW Supply to Excess Letdown HX Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for These valves are located inside the containment and are not equipped with any Justification: instrumentation that can be utilized to verify closure exercising. Any practical test method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a seat leakage type test such as the Appendix J, Type C test. Type C testing for these valves requires the complete isolation of component cooling water to the RCP thermal barriers and the Excess Letdown Hx and the RCDT Hx, which is not practical during normal plant operation. These components are required to remain inservice during cold shutdown, thus testing during cold shutdown is also impractical. In addition, NRC NUREG- 1482, Rev. I, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Outage Reverse flow closure will be verified by an Appendix J, Type C test, other seat Testing: leakage testing similar to the Type C test, or other positive means. The Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6. Bi-directional exercising in the non-safety open direction will be satisfied by normal system operation.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-35 System: Component Cooling Water (P17)

Valve: Q l(2)Pl 7V0087A,B,C Other Valve No: NA Drawing/Coord: D-175002-2 (B-3 C-3, D-3)

D-205002-2 (B-3 C-3, D-3)

Category: C Class: 3 Function: CCW Inlet to RCP Thermal Barrier Check Valve Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for The only way to verify reverse flow closure of these valves requires isolating Justification: CCW flow to the RCPs, at least one of which is required to be operated during cold shutdown. Personnel entry into the containment and the RCP cubicle is required to locally measure backflow leakage. Personnel entry into containment is strictly regulated by Plant procedures during normal operation and at cold shutdown.

Refueling During each refueling outage, CCW flow to the RCPs will be isolated and Outage reverse flow closure will be verified by measuring backflow leakage.

Testing: Alternately, the check valve(s) may be disassembled and manually full stroked on a sampling basis per ISTC-5221(c) during the refueling outage to verify operability. Bi-directional exercising in the non-safety open direction will be satisfied by normal system operation. If disassembled, the valves will be part-stroke exercised in the open direction subsequent to reassembly.

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-36 System: Component Cooling Water (P17)

Valve: Ql(2)P17HV3067, QI (2)P17HV3095, QI(2)P17HV3443 Other Valve No: NA Drawing/Coord: D-175002-2 (F-6, F-I, F-5)

D-205002-2 (E-6, E-1, E-5)

Category: A Class: 2 Function: CCW to the Excess Letdown and Reactor Coolant Drain Tank Heat Exchangers Quarterly Test Exercise, time and fail per ISTC-3510, 5131 and 3560.

Requirements:

Basis for Exercising these valves closed creates a pressure/flow transient in the RCS Justification: pump thermal barrier and oil cooler lines. Pressure and flow are monitored at the discharge of the thermal barrier cooling water lines and will automatically close valve HV3184 on an increase of pressure or flow rate.

Operating history indicates that the transient caused by closing these valves may be sufficient to cause HV3184 to close. Loss of cooling water to the pumps thermal barrier removes one of two cooling sources to the RCP seals. Closure of this cooling path is considered a threat to the seal package as part of the reactor coolant system boundary. Plant operating procedures require maintaining CCW flow to the thermal barriers or seal injection flow at all times when RCS temperature is greater than 150 0 F. The plant maintenance history and equipment failure trending program indicate that these valves are highly reliable. The increased risk of transients versus any gain in operational confidence level associated with quarterly testing is thus not warranted.

Q/CS Part None. The operating controls for these valves were not designed to allow Stroke Testing: partial stroking.

Refueling Exercise, time and fail at refueling outage when all reactor coolant pumps Outage are secured.

Testing:

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-37 System: Component Cooling Water (P17)

Valve: Q1(2)P17V0 11 Other Valve No: NA Drawing/Coord: D-175002-1/E-1 D-205002-2/E- I Category: C Class: 3 Function: CCW Pump Suction Check Valve Quarterly Test Verify reverse flow closure capability in accordance with ISTC-3510 and Requirements: 5221.

Basis for This check valve is located in the miscellaneous equipment return header to Justification: the CCW pump suction. There are no system design provisions to allow closure verification for QV0111 when CCW is in service. The only practical method to verify valve closure is by performing a reverse flow test or pressure decay type test utilizing leakrate type test equipment. Performing this type test is impractical during normal operation since it would require isolation of cooling water return flow from miscellaneous equipment or removal of the entire CCW system from service for an extended period of time. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up leakage type test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure of QV0 11I will be verified by pressure decay or a flow Outage type test, or other positive means during refueling outages when the CCW Testing: system is not required to be operable.

Bi-directional exercising in the non-safety related open direction is satisfied by normal system operation.

IST_Pgm_VLVROJ4thlnt.doc 14-49 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-38 System: Instrument Air (PI 9)

Valve: QI (2)PI 9V0002 Other Valve No: NA Drawing/Coord: D- 175034-3 (E-3)

D-205034-4 (E-3)

Category: AC Class: 2 Function: CTMT Instrument Air Supply Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for This valve is located inside the containment and is not equipped with any Justification: instrumentation that can be utilized to verify closure exercising. Any practical test method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. Type C testing for this valve requires the complete isolation of instrument air to the containment. Isolating instrument air to the containment affects the operation of all air operated instrument controls and valves while the instrument air header is isolated. The affected components are required to remain inservice during cold shutdown, thus testing during cold shutdown is also impractical. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Outage Reverse flow closure will be verified by an Appendix J, Type C test, other seat Testing: leakage testing similar to the Type C test, or other positive means. The Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. I, Section 4.1.6. Bi-directional exercising in the non-safety open direction will be satisfied by normal system operation.

ISTPgm_VLVROJ4thlnt.doc 14-50 Version 1.0

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REFUELING OUTAGE JUSTIFICATIONS ROJ-V-39 System: Instrument Air (P19)

Valve: Q I (2)P 19V0004 Other Valve No: NA Drawing/Coord: D-175034-1 (D-10)

D-205034-4 (B-6)

Category: AC Class: 2 Function: Backup Air Supply to Pressurizer PORVs Quarterly Test Verify reverse flow closure per ISTC-3510 and 5221.

Requirements:

Basis for This valve is located inside the containment and is not equipped with any Justification: instrumentation that can be utilized to verify closure exercising. Any practical test method would require personnel entry into the containment.

The only practical way of verifying valve closure is by performing a leakage type test, such as the Appendix J, Type C test. Type C testing for this valve requires the isolation of backup air to the PORVs which is not practical during normal operation or cold shutdown. In addition, NRC NUREG-1482, Rev. 1, Section 4.1.6, states that the need to set up Appendix J, Type C test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage.

Refueling Reverse flow closure will be verified by an Appendix J, Type C test, other Outage seat leakage testing similar to the Type C test, or other positive means. The Testing: Appendix J, Type C test will be performed during certain refueling outages, at frequencies per the requirements of Appendix J, Option B. Other seat leakage testing similar to the Type C test, or other positive means of confirming reverse flow closure, will be used during all other refueling outages. This testing is consistent with the guidance found in NUREG 1482, Rev. 1, Section 4.1.6.

ISTPg nVLVROJ4thlnt.doc 14-51 Version 1.0

REFUELING OUTAGE JUSTIFICATIONS ROJ-V-40 System: Instrument Air (P 19)

Valve: QI(2)P19HV3611 Other Valve No: NA Drawing/Coord: D- 175034-2 (E-11)

D-205034-2 (E-10)

Category: A Class: 2 Function: CTMT Instrument Air Supply Quarterly Test Exercise, time and fail test per ISTC-3510, 5131, and 3560.

Requirements:

Basis for Testing this valve requires the complete isolation of instrument air to the Justification: containment. Isolating instrument air to the containment affects the operation of all air operated instrument controls and valves while the instrument air header is isolated. The affected components are required to remain in service during normal operation and cold shutdown.

Q/CS Part Part stroke testing verification quarterly or during cold shutdown is also not Stroke Testing: practicable for the same reasons as stated above.

Refueling Valve will be exercised, stroke timed and fail position tested at refueling Outage outages.

Testing:

IST_PgmVLVROJ4thInt.doc 14-52 Version 1.0

Joseph M. Farley Nuclear Plant - Units 1 and 2 Enclosure 2 Detailed Phase-in Schedule for FNP Units I & 2 Affected Procedures

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed?

FNP-0-SOP-0.0 GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL 12/1/2007 FNP-0-AP-57 INSERVICE INSPECTION AND TESTING OF ASME CODE CLASS 1,2, AND 3 SYSTEMS 12/1/2007 FNP-2-STP-628.21 WASTE PROCESSING SYSTEM PENETRATION 31 SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 2/29/2008 FNP-2-STP-742 VERIFICATION OF RE-67 FLOW 2/29/2008 FNP-2-STP-628.10 VERIFICATIO OF RELIEF VALVE (N2P19SV2228) SETPOINT FOR PORV AIR SUPPLY 2/29/2008 FNP-2-STP-22.29 TURBINE DRIVEN AUXILIARY FEEDWATER CHECK VALVE REVERSE FLOW CLOSURE OPERABILITY 2/29/2008 FNP-2-STP-22.13 TURBINE DRIVEN AUX. FEEDWATER PUMP CHECK VALVES FLOW VERIFICATION 2/29/2008 yes FNP-2-STP-45.6 TURBINE BUILDING SERVICE WATER COLD SHUTDOWN VALVES INSERVICE TEST 2/2912008 FNP-1-STP-45.6 TURBINE BUILDING SERVICE WATER COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-22.20 TDAFW PUMP STEAM ADMISSION VALVES AIR ACCUMULATOR TEST 2/29/2008 yes FNP-2-STP-644.8 TDAFP STEAM SUPPLY CHECK VALVE (02N12VO10A, B) FULL STROKE TEST 2/29/2008 FNP-2-STP-45.13 SGBD COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-1-STP-45.13 SGBO COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-24.21B SERVICE WATER PUMPS B TRAIN REMOTE SHUTDOWN CAPABILITY TEST (PUMP BREAKERS IN TEST) 2/29/2008 yes FNP-2-STP-24.21A SERVICE WATER PUMPS A TRAIN REMOTE SHUTDOWN CAPABILITY TEST (PUMP BREAKERS IN TEST) 2/29/2008 yes FNP-1-STP-24.13 SERVICE WATER PUMP 2D AND 2E COLD SHUTDOWN/REFUELING INSERVICE TEST 2/29/2008 yes FNP-2-STP-24.12 SERVICE WATER PUMP 2A, 2B, AND 2C COLD SHUTDOWN/REFUELING INSERVICE TEST 2/29/2008 yes FNP-1-STP-24.12 SERVICE WATER PUMP 1A, 1B AND 1C COLD SHUTDOWN/REFUELING INSERVICE TEST 2/29/2008 yes FNP-2-STP-24.11 SERVICE WATER CYCLONE SEPARATOR VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-45.12 SEAL RETURN AND B TRAIN ECCS MOV'S COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-1-STP-45.12 SEAL RETURN AND B TRAIN ECCS MOV'S COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-40.0 SAFETY INJECTION WITH LOSS OF OFF-SITE POWER TEST 2/29/2008 FNP-2-STP-628.0 RHR PUMP SUCTION SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 2/29/2008 yes FNP-2-STP-628.14 RHR HEAT EXCHANGER TO CHARGING PUMP SUCTION SAFETY RELIEF VALVE SETPOINT AND SEAT TIGHTNESS TESTING 2/29/2008 yes FNP-2-STP-628.1 RHR HEAT EXCHANGER DISCHARGE SAFETY RELIEF VALVE SETPOINT & SEAT TIGHTNESS TEST 2/29/2008 FNP-2-STP-45.5 RHR COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-1-STP-45.5 RHR COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-11.4 RHR B TRAIN CHECK VALVE FLOW TEST 2/29/2008 FNP-2-STP-11.3 RHR A TRAIN CHECK VALVE FLOW TEST 2/29/2008 FNP-2-STP-4.10 REVERSE FLOW TEST OF RWST TO CHARGING PUMP CHECK VALVE 2/29/2008 yes FNP-2-STP-45.0 REFUELING VALVE INSERVICE TEST 2/29/2008 FNP-2-STP-24.15 REFUELING OUTAGE B-TRAIN SERVICE WATER VALVES REMOTE POSITION INDICATION INSERVICE TEST 2/2912008 FNP-2-STP-24.14 REFUELING OUTAGE A-TRAIN SERVICE WATER VALVES REMOTE POSITION INDICATION INSERVICE TEST 2/29/2008 FNP-2-STP-45.2 REACTOR VESSEL HEAD VENT VALVES OPERABILITY TEST 2/29/2008 FNP-2-STP-628.20 REACTOR MAKEUP WATER SYSTEM PENETRATION 30 SAFETY RELIEF VALVE SET PRESSURE & SEAT TIGHTNESS TESTING 2/29/2008 FNP-2-STP-158 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAK TEST 2/29/2008 FNP-2-STP-628.12 REACTOR COOLANT PUMP SEAL WATER RETURN SAFETY VALVE SETPOINT AND SEAT TIGHTNESS 2/29/2008 yes FNP-2-STP-628.19 REACTOR COOLANT PUMP MOTOR COOLER SERVICE WATER SAFETY RELIEF VALVE SETPOINT AND 2/29/2008 yes FNP-2-STP-8.1 RCS SEAL CONTROLLED LEAKAGE TEST (HCV-186 BYPASSED) 2/29/2008 FNP-2-STP-8.0 RCP SEAL CONTROLLED LEAKAGE TEST 2/29/2008 FNP-2-STP-604.1 PRESSURIZER SAFETY VALVE TESTING AT WYLE LABORATORIES 2/29/2008 FNP-2-STP-604 PRESSURIZER SAFETY VALVE TEST 2/29/2008 FNP-2-STP-168 NON-INTRUSIVE TESTING OF CHECK VALVES 2/29/2008:

1 of 6

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed?

FNP-2-STP-170 NON-INTRUSIVE FORWARD FLOW TESTING OF ACCUMULATOR DISCHARGE CHECK VALVES 2/29/2008 FNP-2-STP.45.7 MSIV AND BYPASS VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-22.12 MOTOR DRIVEN AUX. FEEDWATER CHECK VALVES FLOW VERIFICATION 2/29/2008 FNP-2-STP-47.1 MISCELLANEOUS SOLENOID VALVES REMOTE POSITION INDICATION INSERVICE TEST 2/29/2008 FNP-1-STP-45.11 MISCELLANEOUS COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-45.11 MISCELLANEOUS COLD SHUTDOWN INSERVICE TEST 2/29/2008 FNP-2-STP-608.1 MAIN STEAM SAFETY VALVE OPERATIONAL TEST BY FURMANITE 2/29/2008 FNP-2-STP-608.0 MAIN STEAM SAFETY VALVE OPERATIONAL TEST 2/29/2008 FNP-2-STP-46.0 MAIN FEEDWATER VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-45.10 MAIN FEEDWATER STOP VALVES COLD SHUTDOWN VALVES INSERVICE TEST 2129/2008 FNP-1-STP-45.10 MAIN FEEDWATER STOP VALVES COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-627.1 LOCAL LEAK RATE TESTING OF THE CONTAINMENT PURGE SYSTEM 2/29/2008 FNP-2-STP-627 LOCAL LEAK RATE TESTING OF CONTAINMENT PENETRATIONS 2/29/2008 FNP-2-STP-628.11 LETDOWN ORIFICE OUTLET SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 2129/2008 FNP-2-STP-627.2 LEAK TESTING OF THE CONTAINMENT PURGE SYSTEM 2/29/2008 FNP-2-STP-166 INSERVICE VALVE TESTING 2/29/2008 FNP-2-STP-644.7 HHSI/CVCS ACCUMULATOR TANK DISCHARGE CHECK VALVE FULL STROKE TEST 2/2912008 FNP-2-STP-628.17 EXCESS LETDOWN AND RCDT HX'S COMPONENT COOLING WATER SAFETY RELIEF VALVE SETPOINT 2/29/2008 FNP-2-STP-10.4 EMERGENCY BORATION VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-45.4 ECCS COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-1-STP-45.4 ECCS COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-40.8 ECCS BRANCH LINE FLOW VERIFICATION AND CHARGING PUMP LOW DISCHARGE HEAD FLOW TEST (SEAL INJECTION IN SERVICE) 2/29/2008 yes FNP-2-STP-40.7 ECCS BRANCH LINE FLOW VERIFICATION AND CHARGING PUMP LOW DISCHARGE HEAD FLOW TEST 2/29/2008 yes FNP-2-STP-644.2 DIESEL GENERATORS 12" SERVICE WATER CHECK VALVE FULL STROKE TEST AND INSPECTION 2/29/2008 FNP-2-STP-628.9 DIESEL GENERATOR AIR RECEIVER RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 2/29/2008 FNP-2-STP-644.11 DG SERVICE WATER SUPPLY CHECK VALVE FULL STROKE TEST &INSPECTION 2/29/2008 FNP-2-STP-644.3 CYCLONE SEPARATOR CHECK VALVE FULL STROKE TEST 2/29/2008 FNP-2-STP-45.1 CVCS COLD SHUTDOWN VALVES INSERVICE TEST 2/29/2008 FNP-1-STP-45.1 CVCS COLD SHUT DOWN VALVES INSERVICE TEST 2/29/2008 FNP-2-STP-628.16 CTMT SUMP DISCHARGE SAFETY RELIEF VALVE SETPOINT & SEAT TIGHTNESS TESTING 2/29/2008 FNP-2-STP-640.1 CTMT SPRAY PUMP SUCTION FROM RWST CHECK VALVE FULL STROKE TEST 5/31/2008 yes FNP-2-STP-640.0 CTMT SPRAY PUMP DISCHARGE CHECK VALVE Q2E13V002A &B FULL STROKE TEST 5/31/2008 yes FNP-2-STP-628.15 CONTAINMENT COOLERS SERVICE WATER RETURN SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 5/31/2008 FNP-2-STP-644.15 CONTAINMENT COOLER SERVICE WATER SUPPLY CHECK VALVE FULL STROKE TEST AND INSPECTION 5131/2008 FNP-2-STP-628.8 COMPONENT COOLING WATER SURGE TANK VACUUM RELIEF OPERATIONAL TEST Q2P17V263A, B) 5/31/2008 FNP-2-STP-628.6 COMPONENT COOLING WATER SURGE TANK RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 5/31/2008 FNP-2-STP-628.18 COMPONENT COOLING WATER SUPPLY & RETURN TO RCPS SAFETY RELIEF VALVE SETPOINT 5/31/2008 FNP-2-STP-628.7 COMPONENT COOLING WATER RHR HEAT EXCHANGER RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 5/31/2008 FNP-2-STP-644.14 CHARGING PUMP RELIEF VALVE DISCHARGE TO PRT CHECK VALVE FULL STROKE TEST 5/31/2008 yes FNP-2-STP-644.0 CHARGING PUMP MINIMUM FLOW LINE CHECK VALVE FULL FLOW STROKE TEST 5/31/2008 yes FN P-2-STP-23. 12 CCW TO RCP THERMAL BARRIER CHECK VALVES REVERSE FLOW TEST 5/3112008 FNP-2-STP-45.9 LCCW COLD SHUTDOWN 5131/2008 FNP-1-STP-45.9 LCCW COLD SHUTDOWN) 5/31/2008 5/31/2008 FNP-2-STP-2.5 BORIC ACID TRANSFER PUMP OPERABILITY TEST COLD SHUT DOWN 5/31/2008 yes FNP-1-STP-2.5 BORIC i ID TRANSFER PUMP OPERABILITY TEST COLD SHUT DOWN 5/31/2008 yes FNP-2-STP-628.5 AUXILIA f FEEDWATER PUMP SUCTION LINE RELIEF VALVE OPERATIONAL TEST 5/31/20081 yes FNP-2-STP-22.26 LAUXILIA f FEEDWATER PUMP 2A COLD SHUTDOWN INSERVICE TEST 1 5/31/2008 1 yes 2 of 6

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed'?

FNP-1-STP-22.27 AUXILIARY FEEDWATER PUMP 1B COLD SHUTDOWN INSERVICE TEST 5/31/2008 yes FNP-1-STP-22.26 AUXILIARY FEEDWATER PUMP 1A COLD SHUTDOWN INSERVICES TEST 5/3112008 yes FNP-2-STP-22.28 AUX FEEDWATER PUMP SUCTION CHECK VALVES REVERSE FLOW CLOSURE OPERABILITY TEST 5/31/2008 yes FNP-2-STP-22.27 AUX FEEDWATER PUMP 2B COLD SHUTDOWN INSERVICE TEST 5/31/2008 yes FNP-2-STP-32.1 ACCUMULATOR DISCHARGE CHECK VALVES LEAKAGE TEST 5/31/2008 FNP-1-STP-32.1 ACCUMULATOR DISCHARGE CHECK VALVES LEAKAGE TEST 5/31/2008 FNP-2-STP-24.13 IC, iD AND 1E SERVICE WATER PUMPS COLD SHUTDOWN/REFUELING INSERVICE TEST 5/31/2008 yes FNP-2-STP-644.12 1-2A DIESEL GENERATOR SERVICE WATER SUPPLY CHECK VALVE FULL STROKE TEST AND INSP 5/31/2008 FNP-0-GMP-27.2 (PM TASK) DISASSEMBLY, INSPECTION, REPAIR AND REASSEMBLY OF SAFETY RELATED AND NON-SAFETY RELATED CHECK VALVES 5/31/2008 FNP-0-STP-154.1 1-2A DIESEL GENERATOR AIR DRYER OPERABILITY VERIFICATION 5/31/2008 FNP-0-STP-154.2 IC DIESEL GENERATOR AIR DRYER OPERABILITY VERIFICATION 5/31/2008 FNP-0-STP-154.3 2C DIESEL GENERATOR AIR DRYER OPERABILITY VERIFICATION 5/31/2008 FNP-0-STP-24.17 DIESEL GENERATOR SERVICE WATER VALVES REMOTE POSITION INDICATION INSERVICE TEST 5/31/2008 FNP-0-STP-25.1 RIVER WATER PUMPS 1 2 3 4 AND 5 INSERVICE TEST 5/31/2008 yes FNP-0-STP-25.2 RIVER WATER PUMPS 6 7 8 9 AND 10 INSERVICE TEST 5/31/2008 yes FNP-0-STP-25.8 RIVER WATER DISCHARGE VALVE INSERVICE TEST 5/31/2008 FNP-0oSTP-26.1 CONTROL ROOM VENTILATION VALVE INSERVICE TEST 5/31/2008 FNP-0-STP-26.2 CONTROL ROOM PRESSURIZATION-FILTRATION OPERABILITY TEST 5/31/2008 1 FNP-0-STP-80.1 DG 1-2A OPERABILITY TEST 5/31/2008 FNP-1-STP-80.14 DIESEL GENERATOR 2C OPERABILITY TEST 5/31/2008 FNP-0-STP-80.17 DIESEL GENERATOR 2C OPERABILITY TEST 5/31/2008 FNP-0-STP-80.2 DG 1C OPERABILITY TEST 5/31/2008 FNP-0-STP-81.1 1-2A DIESEL GENERATOR FUEL OIL TRANSFER SYSTEM INSERVICE TEST 5/31/2008 FNP-0-STP-81.3 1C DIESEL GENERATOR FUEL OIL TRANSFER SYSTEM INSERVICE TEST 5/31/2008 FNP-0-STP-81.4 2C DIESEL GENERATOR FUEL OIL TRANSFER SYSTEM INSERVICE TEST 5/31/2008 FNP-2-STP-10.3 EMERGENCY CORE COOLING VALVES INSERVICE TEST 5/31/2008 FNP-2-STP-10.5 EMERGENCY BORATION VALVE QUARTERLY INSERVICE TEST 5/31/20081 FNP-2-STP°I1.1 RHR PUMP 2A INSERVlCE TEST 5/31/2008 yes FNP-2-STP-11.2 RHR PUMP 2B INSERVICE TEST 5/31/2008 yes FNP-2-STP-11.6 RESIDUAL HEAT REMOVAL VALVES INSERVlCE TEST 5/31/2008 FNP-2-STP-154.1 2B DIESEL GENERATOR AIR DRYER OPERABILITY VERIFICAT15N 5/31/2008 FNP-2-STP-16.1 CONTAINMENT SPRAY PUMP 2A INSERVICE TEST 5/31/2008 yes FNP-2-STP-16.10 2A CONTAINMENT SPRAY LOOP CHECK VALVE FLOW VERIFICATION 5/311/2008 FNP-2-STP-16.11 2B CONTAINMENT SPRAY LOOP CHECK VALVE FLOW VERIFICATION 5/31/2008 FNP-2-STP-16.2 CONTAINMENT SPRAY PUMP 2B INSERVICE TEST 5/31/2008 yes FNP-2-STP-16.7 CONTAINMENT SPRAY SYSTEM VALVE INSERVICE TEST 5/31/20081 FNP-2-STP-17.0 CONTAINMENT COOLING SYSTEM TRAIN A-B OPERABILITY TEST 5/31/2008 FNP-2-STP°18.3 CONTAINMENT PURGE AND EXHAUST VALVE INSERVICE TEST 5/31/2008 FNP-2-STP-18.5 CONTAINMENT MINIPURGE AND EXHAUST VALVE INSERVICE TEST 5/31/2008 FNP-2-STP-19.3 REACTOR CAVITY COOLING HYDROGEN MIXING AND POST-LOCA VENT AND SAMPLE VALVES INSERVICE TEST 5/31/2008 FNP-2-STP-2.6 2A BORIC ACID TRANSFER PUMP QUARTERLY INSERVICE TEST 5/31/2008 yes FNP-2-STP-2.7 2B BORIC ACID TRANSFER PUMP QUARTERLY INSERVICE TEST 5/31/2008 yes FNP-2-STP-20.0 PENETRATION ROOM FILTRATION SYS. TRAIN A-B OPERABILITY AND VALVE INSERVICE TEST 5/31/2008 FNP-2-STP-21.3 TDAFWP STEAM SUPPLY VALVES VALVE INSERVICE TEST 5/31/2008 FNP-2-STP-22.1 AUX. FEEDWATER PUMP 2A INSERVIC 5/31/2008 yes FNP-2-STP-22.16 TURBINE DRIVEN AUX. FEEDWATER F SERVICE TEST 5/31/2008 yes FNP-2-STP-22.2 JAUX. FEEDWATER PUMP 2B INSERVIC 5/31/2008 yes 3 of 6

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed?

FNP-2-STP-22.23 TURBINE DRIVEN AUX FEEDWATER PUMP TRIP AND THROTTLE VALVE INDICATION OPERABILITY 5/31/2008 yes FNP-2-STP-22.24 AUX FEEDWATER SYSTEM CHECK VALVE REVERSE CLOSURE OPERABILITY TEST 5/31/2008 FNP-2-STP-22.25 STEAM GENERATOR BLOWDOWN INSERVICE VALVE EXERCISE TEST INSERVICE TEST 5/31/2008 FNP-2-STP-22.8 AUX. FEEDWATER INSERVICE VALVE EXERCISE TEST 5/31/2008 FNP-2-STP-23.1 COMPONENT COOLING WATER PUMP 2A INSERVICE TEST 5/3112008 yes FNP-2-STP-23.2 COMPONENT COOLING WATER PUMP 2B INSERVICE TEST 5/31/2008 yes FNP-2-STP-23.3 COMPONENT COOLING WATER PUMP 2C INSERVICE TEST 5/31/2008 yes FNP-2-STP-23.8 COMPONENT COOLING WATER VALVE INSERVICE TEST 8/31/2008 FNP-2-STP-24.1 SERVICE WATER PUMP 2A 2B AND 2C INSERVICE TEST 8/31/2008 yes FNP-2-STP-24.16 CTMT CLR AND RCP MTR AIR CLR SERVICE WATER VALVE INSERVICE TEST 8/31/2008 FNP-2-STP-24.2 SERVICE WATER PUMP 2D 2E AND 2C INSERVICE TEST 8/31/2008 yes FNP-2-STP-24.7 SERVICE WATER VALVES INSERVICE TEST 8/31/2008 FNP-2-STP-4.1 CHARGING PUMP 2A INSERVICE TEST 8/31/2008 yes FNP-2-STP-4.2 CHARGING PUMP 2B INSERVICE TEST 8/31/2008 yes FNP-2-STP-4.3 CHARGING PUMP 2C INSERVICE TEST 8/31/2008 yes FNP-2-STP-44.0 LIQUID RAD WASTE VALVE INSERVICE TEST 8/31/2008 FNP-2-STP-47.0 MISCELLANEOUS VALVES INSERVICE TEST 8/31/2008 FNP-2-STP-80.1 DG 2B OPERABILITY TEST 8/31/2008 FNP-2-STP-81.5 2B DIESEL GENERATOR FUEL OIL TRANSFER SYSTEM INSERVICE TEST 8/31/2008 FNP-1-STP-10.3 EMERGENCY CORE COOLING VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-10.4 EMERGENCY BORATION VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-10.5 EMERGENCY BORATION VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-11.1 RHR PUMP 1A INSERVICE TEST 8/31/2008 yes FNP-1-STP-11.2 RHR PUMP 1B INSERVICE TEST 8/31/2008 yes FNP-1-STP-1 1.3 RHR A TRAIN CHECK VALVE FLOW TEST 8/31/2008 FNP-1-STP-11.4 RHR B TRAIN CHECK VALVE FLOW TEST 8/31/2008 FNP-1-STP-11.6 RESIDUAL HEAT REMOVAL VALVES INSERVICE TEST 8131/2008 FNP-1-STP-154.1 11BDIESEL GENERATOR AIR DRYER OPERABILITY VERIFICATION 8/31/2008 FNP-1-STP-158 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE LEAK TEST 8/3/12008 FNP-1-STP-16.1 CONTAINMENT SPRAY PUMP 1A INSERVICE TEST 8/31/2008 yes FNP-1-STP-16.10 CONTAINMENT SPRAY SYSTEM CHECK VALVES FLOW TEST-A TRAIN 8/31/2008 FNP-1-STP-16.11 CONTAINMENT SPRAY SYSTEM CHECK VALVES FLOW TEST-B TRAIN 8/31/2008 FNP-1-STP-16.13 CONTAINMENT SPRAY SYSTEM CHECK VALVES AND PUMP FLOW TEST-A TRAIN &B TRAIN 8/31/2008 yes FNP-1-STP-16.2 CONTAINMENT SPRAY PUMP 1B INSERVICE TEST 8/31/2008 yes FNP-1-STP-16.7 CONTAINMENT SPRAY SYSTEM VALVE INSERVICE TEST 8/31/2008 FNP-1-STP-166 INSERVICE VALVE TESTING 8/31/2008 FNP-1-STP-168 NON-INTRUSIVE FORWARD FLOW TESTING OF SAFETY INJECTION CHECK VALVES 8/31/2008 FNP-1-STP-169 CONTAINMENT SPRAY RWST SUCTION CHECK VALVE REVERSE CLOSURE TEST 8/31/2008 FNP-1-STP-17.0 CONTAINMENT COOLING SYSTEM TRAIN A-B OPERABILITY TEST 8/31/2008 FNP-1-STP-170 NON-INTRUSIVE FORWARD FLOW TESTING OF ACCUMULATOR DISCHARGE CHECK VALVES 8/3112008 FNP-1-STP-18.3 CONTAINMENT PURGE AND EXHAUST VALVE INSERVICE TEST 8/31/2008 FNP-1-STP-18.5 CONTAINMENT MINIPURGE AND EXHAUST VALVE INSERVICE TEST 8/31/2008 FNP-1-STP-19.3 REACTOR CAVITY COOLING HYDROGEN MIXING AND POST-LOCA VENT AND SAMPLE VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-2.6 1A BORIC ACID TRANSFER PUMP QUARTERLY INSERVICE TEST 8/31/2008 yes FNP-1-STP-2.7 1 B BORIC ACID TRANSFER PUMP QUARTERLY INSERVICE TEST 8/31/2008 yes FNP-1-STP-20.0 PENETRATION ROOM FILTRATION SYSTEM TRAIN A(B) QUARTERLY OPERABILITY AND VALVE INSERVICE TEST 8/31/2008 4 of 6

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed?

FNP-1-STP-21.3 T"DAFWP STEAM SUPPLY VALVES VALVE INSERVICE TEST 8/31/2008 FNP-1-STP-22.1 AUXILIARY FEEDWATER PUMP 1A INSERVICE TEST 8/31/2008 yes FNP-1-STP-22.12 MOTOR DRIVEN AUX. FEEDWATER CHECK VALVES FLOW VERIFICATION 8/31/2008 FNP-1-STP-22.13 TURBINE DRIVEN AUX. FEEDWATER PUMP CHECK VALVES FLOW VERIFICATION 8/31/2008 yes FNP-1-STP-22.16 TURBINE DRIVEN AUX. FEEDWATER PUMP INSERVICE TEST 8/31/2008 yes FNP-1-STP-22.2 AUXILIARY FEEDWATER PUMP 1B INSERVICE TEST 8/31/2008 yes FNP-1-STP-22.20 TDAFW PUMP STEAM ADMISSION VALVES AIR ACCUMULATOR TEST 8/31/2008 yes FNP-1-STP-22.23 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP TRIP AND THROTTLE VALVE INDICATOR OPERABILITY 8/31/2008 yes FNP-1-STP-22.24 AUX FEEDWATER SYSTEM CHECK VALVE REVERSE FLOW CLOSURE OPERABILITY TEST 813/12008 FNP-l-STP-22.25 STEAM GENERATOR BLOWDOWN INSERVICE VALVE EXERCISE TEST 88/31/2008 FNP-1-STP-22.28 AUX FEEDWATER PUMP SUCTION CHECK VALVES REVERSE FLOW CLOSURE OPERABILITY TEST 8/31/2008 yes FNP-1-STP-22.29 TURBINE DRIVEN AUXILIARY FEEDWATER CHECK VALVE REVERSE FLOW CLOSURE OPERABILITY 8/31/2008 FNP-1-STP-22.8 AUXILIARY FEEDWATER INSERVICE VALVE EXERCISE TEST 8/31/2008 FNP-1-STP-23.1 COMPONENT COOLING WATER PUMP 1A INSERVICE TEST 8/31/2008 yes FNP-1-STP-23.12 CCW TO RCP THERMAL BARRIER CHECK VALVE REVERSE FLOW TEST 8/31/2008 FNP-1-STP-23.2 COMPONENT COOLING WATER PUMP 1B INSERVICE TEST 8/31/2008 yes FNP-1-STP-23.3 COMPONENT COOLING WATER PUMP 1C INSERVICE TEST 8/31/2008 yes FNP-1-STP-23.8 COMPONENT COOLING WATER VALVE INSERVICE TEST 8/31/2008 FNP-1-STP-24.1 SERVICE WATER PUMP 1A 18 AND 1C INSERVICE TEST 8/31/2008 yes FNP-1-STP-24.11 SERVICE WATER CYCLONE SEPARATOR VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-24.14 REFUELING OUTAGE A-TRAIN SERVICE WATER VALVES REMOTE POSITION INDICATION INSERVICE TEST 8/31/2008 FNP-1-STP-24.15 REFUELING OUTAGE B-TRAIN SERVICE WATER VALVES REMOTE POSITION INDICATION INSERVICE TEST 8/31/2008 FNP-1-STP-24.16 CTMIT CLR AND RCP MTR AIR CLR SERVICE WATER VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-24.2 SERVICE WATER PUMP 1D 1E AND 1C INSERVICE TEST 8/31/2008 yes FNP-1-STP-24.21A SERVICE WATER PUMPS A TRAIN REMOTE SHUTDOWN CAPABILITY TEST (PUMP BREAKERS IN TEST) 8/31/2008 yes FNP-1-STP-24.21B SERVICE WATER PUMPS B TRAIN REMOTE SHUTDOWN CAPABILITY TEST (PUMP BREAKERS IN TEST) 8/31/2008 yes FNP-1-STP-24.7 SERVICE WATER VALVES INSERVICE TEST 8/31/2008 FNP-1-STP-4.1 CHARGING PUMP 1A INSERVICE TEST 8/31/2008 es FNP-1-STP-4.10 REVERSE FLOW TEST OF RWST TO CHARGING PUMP CHECK VALVE 11/30/2008 yes FNP-1-STP-4.2 CHARGING PUMP 1B INSERVICE TEST 11/30/2008 yes FNP-1-STP-4.3 CHARGING PUMP 1C INSERVICE TEST 11/30/2008 yes FNP-1-STP-40.0 SAFETY INJECTION WITH LOSS OF OFF-SITE POWER TEST 11/30/2008 FNP-1-STP-40.7 ECCS BRANCH LINE FLOW VERIFICATION AND CHARGING PUMP LOW DISCHARGE HEAD FLOW TEST 11/30/2008 yes FNP-1-STP-40.8 ECCS BRANCH LINE FLOW VERIFICATION AND CHARGING PUMP LOW DISCHARGE HEAD FLOW TEST (SEAL INJECTION IN SERVICE) 11/30/2008 yes FNP-1-STP-44.0 LIQUID RAD WASTE VALVE INSERVICE TEST 11/30/2008 FNP-1-STP-45.0 REFUELING VALVE INSERVICE TEST 11/30/2008 FNP-1-STP-45.2 REACTOR VESSEL HEAD VENT VALVES OPERABILITY TEST 11/30/2008 FNP-1-STP-45.7 MSIV AND BYPASS VALVES INSERVICE TEST 11130/2008 FNP-1-STP-46.0 MAIN FEEDWATER VALVE INSERVICE TEST 11/30/2008 FNP-1-STP-47.0 MISCELLANEOUS VALVES INSERVICE TEST 11/30/2008 FNP-1-STP-47.1 MISCELLANEOUS SOLENOID VALVES REMOTE POSITION INDICATION INSERVICE TEST 11/30/2008 FNP-1-STP-604 PRESSURIZER SAFETY VALVE TEST 11/30/2008 FNP-1-STP-604.1 PRESSURIZER SAFETY VALVE TESTING AT WYLE LABORATORIES 1113012008 FNP-1-STP-608 MAIN STEAM SAFETY VALVE OPERATIONAL TEST 11/30/2008 FNP-1-STP-608.1 MAIN STEAM SAFETY VALVE OPERATIONAL TEST BY FURMANITE 11/30/2008 FNP-1-STP-627 LOCAL LEAK RATE TESTING OF CONTAINMENT PENETRATIONS 111/30/2008 5 of 6

Comprehensive Update Pump Test and Procedure Number Procedure Title Completed Preservice By Procedures Needed?

FNP-1-STP-627.1 LOCAL LEAK RATE TESTING OF THE CONTAINMENT PURGE SYSTEM 11/30/2008 FNP-1-STP-627.2 LEAK TESTING OF THE CONTAINMENT PURGE SYSTEM 11/30/2008 FNP-1-STP-628.0 RHR PUMP SUCTION SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 yes FNP-1-STP-628.1 RHR HEAT EXCHANGER DISCHARGE SAFETY RELIEF VALVE SETPOINT & SEAT TIGHTNESS TEST 11/30/2008 FNP-1-STP-628.10 VERIFICATION OF RELIEF VALVE (N1P19PSV2228) SETPOINT FOR PORV BACKUP AIR SUPPLY 11/30/2008 FNP-1-STP-628.11 LETDOWN ORIFICE OUTLET SAFETY RELIEF VALVE SETPOINT AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.12 RCP PUMP SEAL WATER RETURN SAFETY RELIEF VALVE SETPOINT & SEAT TIGHTNESS TESTING 11/30/2008 yes FNP-1-STP-628.14 RHR HEAT EXCHANGER TO CHARGING PUMP SUCTION SAFETY RELIEF VALVE SETPOINT AND SEAT TIGHTNESS TESTING 11/30/2008 yes FNP-1-STP-628.15 CONTAINMENT COOLERS SERVICE WATER RETURN SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.16 CTMT SUMP DISCHARGE SAFETY RELIEF VALVE SETPOINT &SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.17 EXCESS LETDOWN AND RCDT HX'S COMPONENT COOLING WATER SAFETY RELIEF VALVE SETPOINT 11/30/2008 FNP-1-STP-628.18 COMPONENT COOLING WATER SUPPLY & RETURN TO RCP SAFETY RELIEF VALVE SETPOINT 11/30/2008 FNP-1-STP-628.19 RCP MOTOR COOLER SERVICE WATER SAFETY RELIEF VALVE SETPOINT & SEAT TIGHTNESS 11/30/2008 FNP-1-STP-628.20 REACTOR MAKEUP WATER SYSTEM PENETRATION 30 SAFETY RELIEF VALVE SET PRESSURE & SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.21 WASTE PROCESSING SYSTEM PENETRATION 31 SAFETY RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.5 AUXILIARY FEEDWATER PUMP SUCTION LINE RELIEF VALVE SETPOINT & SEAT TIGHTNESS 11/30/2008 yes FNP-1-STP-628.6 COMPONENT COOLING WATER SURGE TANK RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.7 COMPONENT COOLING WATER RHR HEAT EXCHANGER RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-628.8 COMPONENT COOLING WATER SURGE TANK VACUUM RELIEF OPERATIONAL TEST (Q1 P17V263A,B) 11/30/2008 FNP-1-STP-628.9 DIESEL GENERATOR AIR RECEIVER RELIEF VALVE SET PRESSURE AND SEAT TIGHTNESS TESTING 11/30/2008 FNP-1-STP-640.2 CTMT SPRAY PUMP SUCTION FROM RWST CHECK VALVE (01 El 3V014) FULL STROKE TEST 11/30/2008 yes FNP-1-STP-640.3 CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE (Q1E13VO02A AND B) FULL STROKE TEST 11/30/2008 yes FNP-1-STP-644.0 CHARGING PUMP MINIMUM FLOW LINE CHECK VALVE FULL FLOW STROKE TEST 11/30/2008 yes FNP-1-STP-644.11 DG SERVICE WATER SUPPLY CHECK VALVEB FULL STROKE TEST & INSPECTION 11/30/2008 FNP-1-STP-644.12 1-2A DG SW SUPPLY CHECK VALVE FULL STROKE TEST & INSPECTION 11/30/2008 FNP-1-STP-644.14 CHARGING PUMP RELIEF VALVE DISCHARGE TO PRT CHECK VALVE FULL STROKE TEST 11/30/2008 yes FNP-1-STP-644.15 CONTAINMENT COOLER SERVICE WATER SUPPLY CHECK VALVE FULL STROKE TEST AND INSEPCTION 11/30/2008 FNP-1-STP-644.2 DG 12" SERVICE WATER CHECK VALVE FULL STROKE TEST & INSPECTION 11/30/2008 FNP-1-STP-644.3 CYCLONE SEPARATOR CHECK VALVE FULL STROKE TEST 11/30/2008 FNP-1-STP-644.7 HHSI/CVCS ACCUMULATOR TANK DISCHARGE CHECK VALVE FULL STROKE TEST 11/30/2008 FNP-1-STP-644.8 TDAFP STEAM SUPPLY CHECK VALVE Q1N12V010A,B FULL STROKE TEST 11/30/2008 FNP-1-STP-742 VERIFICATION OF RE-67 FLOW 11/30/2008 FNP-1-STP-8.0 RCP SEAL CONTROLLED LEAKAGE TEST 11/30/2008 FNP-1-STP-8.1 RCS SEAL CONTROLLED LEAKAGE TEST (HCV-186 BYPASSED) 11/30/2008 FNP-1-STP-80.1 DG 1B OPERABILITY TEST 11/30/2008 FNP-1-STP-81.2 1B DIESEL GENERATOR FUEL OIL TRANSFER SYSTEM INSERVICE TEST 111/30/20081 6 of 6

NL-07-1418, Fourth Ten-Year Interval Inservice Testing Program Update

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NL-07-1418, Fourth Ten-Year Interval Inservice Testing Program Update

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