ML022610243

Submittal of Browns Ferry Nuclear Plant Units 1, 2, & 3, American Society of Mechanical Engineers (ASME)Section XI, Inservice Testing (IST) Program for Third Ten-Year Interval

ML022610243
Person / Time
Site:	Browns Ferry
Issue date:	09/06/2002
From:	Abney T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022610243 (63)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 September 6, 2002 10 CFR 50.55a(f)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket No. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE TESTING (IST) PROGRAM FOR THE THIRD TEN-YEAR INTERVAL This letter submits the Third Ten-Year Inservice Testing (IST) Program for Units 1, 2, and 3 of the Browns Ferry Nuclear Plant. The Code of record for the Third Ten-Year Interval IST Program is the 1995 Edition, of the ASME OM Code through the 1996 Addenda, subject to the limitations and modifications specified in 10 CFR 50.55a(b) (3). The IST Program is applicable to all three BFN units, which are on a concurrent Ten-Year IST Interval. The Third Ten-Year Interval commences on September 1, 2002, and ends on August 31, 2012.

The Code of Federal Regulations, 10 CFR 50.55a(f), requires that inservice testing of ASME Code Class 1, 2, and 3 pumps and valves of a water-cooled nuclear facility meet the requirements of ASME Section XI. In addition, 10 CFR 50.55a(f) (4) (ii) requires that the IST Program be updated every 10 years to the latest NRC approved Edition and Addenda of Section XI, which is in effect 12 months prior to the start of the next 120-month interval. The enclosed program updates satisfy that requirement.

Pnntedon recycod paer

U.S. Nuclear Regulatory Commission Page 2 September 6, 2002 The enclosure to this letter contains the updated BFN Units 1, 2, and 3 ASME Section XI IST Program for the Third Ten Year Interval. The Program update includes two requests for relief for NRC approval. Relief request PV-1 (Appendix B) seeks approval to use alternative testing for the Standby Liquid Control Pumps. Also, relief request PV-2 (Appendix C) asks approval to use alternative testing for the Control Rod Drive scram inlet valves (185 valves per unit) and scram outlet valves (185 valves per unit). These two requests for relief are updated versions of requests for relief which were previously approved during the Second Ten-Year IST Interval at BFN.

TVA requests approval of this ASME Section XI IST Program update for BFN Units 1, 2, and 3 by March 1, 2003, to support ongoing Inservice Testing activities.

There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.

S' cerely*

Manager of Li sing and Indus v Affairs cc: See

U.S. Nuclear Regulatory Commission Page 3 September 6, 2002 Enclosure cc (Enclosure):

(Via NRC Electronic Distribution)

Mr. Paul E. Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant P.O. Box 149 Athens, Alabama 35611 Mr. Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 1, 2, AND 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE TESTING (IST) PROGRAM THIRD TEN-YEAR INSPECTION INTERVAL INSERVICE TESTING (IST) PROGRAM (SEE ATTACHED)

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL OWNER TENNESSEE VALLEY AUTHORITY ADDRESS OF CORPORATE OFFICE: KNOXVILLE OFFICE COMPLEX 400 COMMERCE AVE KNOXVILLE, TN 37902 NAME AND ADDRESS OF NUCLEAR UNITS: BROWNS FERRY NUCLEAR PLANT P.O BOX 2000 DECATUR, AL 35609 APPLICABLE NUCLEAR UNITS: 1, 2, AND 3 COMMERCIAL OPERATION DATES: UNIT 1 -AUGUST 1, 1974 UNIT 2 - MARCH 1, 1975 UNIT 3 - MARCH 1, 1977 PAGE 1 OF 59

TABLE OF CONTENTS SECTION PAGE NUMBER Introduction -------------------------------- ------------------------------------------------3 Definitions ----------------------- ----------------------------------------------- 3 General Requirements ---------------

Appendix A - ASME Pump Matrix------ --------------------------------------------- -11 Appendix B - Requests for Relief (Pumps)--- ---------------------------------------------- .12 Appendix C - Requests for Relief (Valves) 13 Appendix D - Refueling and Cold Shutdown Justifications---- --------------------------------------------- 14 Appendix E - ASME Valve Matrix------ .18 Appendix F - Passive Valve List-------- ..............................- 4..

.t1 Appendix G - Condition Monitoring Program ---------------------------------------------.48 PAGE 2 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL INTRODUCTION PURPOSE 10 CFR 50.55a(f) requires the establishment and implementation of Inservice Testing (IST) to venfy the operational readiness of pumps and valves whose function is required for plant safety. This document describes the implementation of IST of pumps and valves at Browns Ferry Nuclear Plant (BFN).

SCOPE This document describes the IST Program for pumps and valves which are designated as ASME Code Class 1, 2, and 3 equivalent components that are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident. The Code of Record for IST of pumps and valves for the Third Ten-Year Interval is the 1995 Edition of the ASME OM Code through the 1996 Addenda, subject to the limitations and modifications specified in 10 CFR 50.55a(b)(3). This IST Program is applicable to all three BFN units, which are on a concurrent Ten-Year IST Interval. The 3rd Ten-Year IST Interval begins on September 1, 2002 and runs through August 31, 2012.

DEFINITIONS ACTIVE VALVE - A valve that must perform a mechanical motion during the course of accomplishing a system safety function.

AUTHORIZED NUCLEAR INSERVICE INSPECTOR (ANII) - Personnel qualified by written examination to meet the requirements of ANSI/ASME N626.1-1975 and who are employed by an Authorized Inspection Agency to perform inspections and verifications as required by Section XI of the ASME Boiler and Pressure Vessel Code.

GROUP A PUMPS - Pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations GROUP B PUMPS - Pumps in standby systems that are not operated routinely except for testing.

CATEGORY A VALVES - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.

CATEGORY B VALVES - Valves for which there is no defined maximum seat leakage amount for the fulfillment of their function.

CATEGORY C VALVES - Valves which are self-actuating in response to some system characteristic, such as pressure (safety and relief valves including vacuum relief valves) or flow direction (check valves).

CATEGORY D VALVES - Valves which are capable of only one operation, such as rupture disks or explosively actuated valves.

IST ENGINEER (REVIEWER) - An individual who is knowledgeable of lST requirements, is capable of identifying testing requirements for affected components, and competent to verify that surveillance instruction packages are complete and that results document proper component operation.

PAGE 3 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL DEFINITIONS (continued)

CONTAINMENT ISOLATION VALVE (CIV) - Any valve which is relied upon to perform a primary containment isolation function All CIVs are required to be included in the IST program as Category A valves.

EXERCISING - The demonstration based on direct visual or indirect positive indications that the moving parts of a valve function.

FULL STROKE TIME - The time interval from initiation of the actuating signal to the indication of the end of the operating stroke.

LIMITING VALUE OF STROKE TIME - The maximum allowable stroke time for a valve as determined by the owner. For BFN, the limiting values are generally established by Technical Specifications, the FSAR, or Design Criteria for individual systems If not established by these documents, the limiting value is assigned by the IST Engineer.

NONINTRUSIVE TESTING - Testing performed on a component without disassembly or disturbing the boundary of the component.

OBTURATOR - Valve closure member (disk, gate, plug, ball, etc.)

OPERATIONAL READINESS - The ability of a valve to perform its intended function.

PASSIVE VALVE - A valve which does not perform a mechanical motion during the course of accomplishing a system safety function PLANT OPERATION - The conditions of startup, operation at power, hot standby, and reactor cooldown, as defined by the plant technical specifications.

PRESSURE ISOLATION VALVE (PIVS) - Valves which are normally closed or capable of automatic closure which serve to isolate a higher operating pressure system from an attached lower operating pressure system REFERENCE VALUES - One or more values of test parameters measured or determined when the equipment is known to be operating acceptably.

SKID-MOUNTED COMPONENTS - Components integral to or that support operation of major components, even when these components may not be located directly on the primary equipment skid Generally, these components are supplied by the manufacturer of the major component. Examples include: diesel generator fuel oil pumps and valves, the steam admission and trip throttle valves for high-pressure coolant injection and auxiliary feedwater pump turbines, and solenoid-operated valves which provide control air to the air-operated valves.

TRENDING - A comparison of current data to previous data obtained under similar conditions for the same equipment.

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL IST PROGRAM ABBREVIATIONS FOR PUMP AND VALVE TESTING PARAMETER ABBREVIATION DESCRIPTION VALVE TYPE GA Gate valve GL Globe valve CK Check valve RV Relief valve SC Stop check BF Butterfly valve RD Rupture disc PL Plug valve BA Ball valve Actuator Type MO Motor Operated S Solenoid Operated X Explosive AO Air Operated SELF Self Actuated H Manual Safety Position 0 Open C Closed O/C Both Open and Closed LO Locked open LC Locked closed Tests Performed Q Quarterly test ST Full-stroke test FS Fail-safe test LT Leak-rate test RV Relief valve bench test CV Full-stroke check valve test VRPIL Verify position indicator lights VI Visual inspection CM Condition Monitoring PAGE 5 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL GENERAL REQUIREMENTS Title 10, Part 50 of the Code of Federal Regulations, paragraph 50.55a(f) requires the Inservice Testing (1ST) of certain nuclear power facility ASME Code Class 1, 2, and 3 pumps and valves whose functions are required for safety.

This testing is required to be conducted in 120-month intervals, beginning with initial power operation and continuing throughout the service life of the facility. The testing must comply with the latest edition and addenda of the American Society of Mechanical Engineers (ASME) OM Code, incorporated by reference in 10 CFR 50 55a(b), 12 months prior to the start of the 120-month interval. Specific exceptions to these requirements of ASME Section XI are included here as Relief Requests. BFNP Units 1, 2, and 3 are on a concurrent IST interval. The second 120-month interval for BFN expires on August 31, 2002. The third 120-month interval for BFN begins on September 1, 2002.

Portions of later editions and addenda of the ASME OM Code, which are incorporated by reference in 10 CFR 50.55a(b), may be used subject to limitations and modifications established by NRC, provided that all applicable requirements of the respective editions and addenda are met.

NRC Generic Letter 89-04 and NUREG-1482 provide alternatives to ASME Section XI IST requirements that are acceptable to NRC. In order to utilize the alternative methods, they must be complied with in their entirety and their use documented in the IST program.

The BFNP IST program was prepared using the following for guidance:

"* ASME OM Code, 1995 Edition through the 1996 Addenda

"* NRC Generic Letter 89-04

"* NRC Regulatory Guide 1.26

"* NUREG-0800

"* NRC Temporary Instructions 2515/110 and 2515/114

"* NRC Inspection Procedure (IP) 73756

"* NRC Generic Letter 91-18

"* NUREG-1482

"* BFN Updated Final Safety Analysis Report (UFSAR)

"* BFNP Technical Specifications (TS)

"* BFNP System Design Criteria All plant pressure retaining components were reviewed for IST applicability and those meeting the following criteria have been included in the BFNP IST program Components that meet the criteria of ISTB 1.2 and ISTC 1.2 are excluded from the IST program.

"* Components which are part of the reactor coolant pressure boundary and their supports must meet the requirements applicable to components which are classified as ASME Code Class 1.

" Other safety-related pumps and valves that are required to perform a specific function to shut down the reactor or maintain the reactor in a safe shutdown condition, mitigate the consequences of an accident, or provide overpressure protection for safety-related systems must meet the requirements applicable to components which are classified as ASME Code Class 2 or Class 3. Components must meet the test requirements applicable to components which are classified as ASME Code Class 2 and 3 to the extent practical. Classification is determined by TVA Site Engineering and designated on the controlled Inservice Inspection (ISI) series of drawings.

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL IST OF PUMPS The BFN Code of Record for IST of pumps is the 1995 edition of the ASME OM Code through the 1996 Addenda.

Actual requirements may be modified in accordance with NRC NUREG-1482, NRC Generic Letter 89-04, Relief Requests, Refueling Outage Justifications, and Cold Shutdown Justifications. See Appendix A for detailed test requirements for individual pumps. Evaluation of test deficiencies shall be performed and documented in accordance with the site corrective action program. Relief requests pertaining to IST of pumps are contained in Appendix B.

IST OF VALVES The BFN Code of Record for IST of valves is the 1995 edition of the ASME OM Code through the 1996 Addenda, subject to the limitations and modifications specified in 10 CFR 50.55a(b)(3). Actual requirements may be modified in accordance with NRC NUREG-1482, NRC Generic Letter 89-04, Relief Requests, Refueling Outage Justifications, and Cold Shutdown Justifications. See Appendix E for detailed test requirements for individual valves. Valves are tested in accordance with the requirements of their particular category. Valves which fall into more than one category are tested in accordance with the requirements of all applicable categories. Duplication or repetition of common testing requirements for valves that fall into more than one category is not performed.

The ASME Section XI valve operability requirements being satisfied by this instruction include the exercising (cycling) of the valves to the position required to perform their safety function and the stroke timing of power-operated valves. Valves having fail-safe actuators are tested by interrupting the electrical or pneumatic power to the actuator and observing the required valve operation. Exceptions to the IST requirements are documented in the Relief Request portion or in the Refueling Outage/Cold Shutdown Justification portion of the Browns Ferry Pump and Valve IST Program. Relief Requests are contained in Appendix C, and the Refueling Outage/Cold Shutdown Justifications are contained in Appendix D.

Evaluation of test deficiencies shall be performed and documented in accordance with the site surveillance testing and corrective action programs VALVE STROKE TIMES The maximum allowable stroke time for any valve can not exceed any Technical Specification, FSAR, or Design Criteria requirement for maximum allowable (limiting value) stroke time, where such value exists.

For valve stroke times not addressed by the Technical Specifications or the FSAR, the maximum allowable (limiting value) stroke time will be established by engineering evaluation. In most instances, the basis for the stroke times comes from the first inservice test performed on the valve, or from the first inservice test performed following valve maintenance or modification. Maximum stroke time for these valves is established at 1.5 x the stroke time recorded on the test for valves with stroke times greater than 10 seconds, or 2.0 x the stroke time recorded on first test for valves with stroke times less than or equal to 10 seconds In other instances, preoperational test data or valve trend data was used to establish maximum allowable stroke times (computed the same as for those based on test performances).

Maximum stroke times for valves with stroke times greater than 10 seconds may be rounded off to the nearest second PAGE 7 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL REMOTE POSITION INDICATORS Where possible, valves with remote position indicators will be observed at least once every two years to verify that valve operation is accurately indicated.

CHECK VALVES Check valves shall be exercised in both the open and closed directions The exercise tests are not required to be performed concurrently.

EXCESS FLOW CHECK VALVES (ECKVs)

Excess flow check valves are installed in instrument lines penetrating primary containment in accordance with Regulatory Guide 1.1. As such, the lines are sized and/or orificed such that offsite radiation doses will be substantially below 10 CFR 100 limits in the event of a rupture. Therefore, individual leak rate testing of these valves is not required for conformance with 10 CFR 50 Appendix J requirements. Functional testing of valves to verify closure can be accomplished by the process of venting the instrument side of the valve while the process side is under pressure.

Such testing is required by Technical Specifications at least once per operating cycle for a representative sample of the EFCVs. Testing on a more frequent basis is not feasible for several reasons Instruments serviced by these valves frequently have interlock or actuation functions that would be interfered with should testing be performed during plant operation. Also, process liquid will be contaminated to some degree, requiring special measures to collect flow from the vented instrument side. Functional testing with verification that excess flow is prevented will be performed for a representative sample of the EFCVs at least once per operating cycle per Technical Specifications FAIL-SAFE VALVES Fail-safe valves are tested in accordance with the OM Code for loss of electrical or pneumatic actuator power.

RELIEF VALVES Relief valves shall be tested in accordance with the OM Code Appendix I and NLJREG-1482 for verification of seat tightness and opening pressure (setpoint). Relief valves are required to be tested on a percentage basis with 100% of the Class 2 and 3 valves being tested by the end of each Ten Year Interval. 100% of Class 1 valves are required to be tested in any five year interval. The intent is that relief valves be tested on a regular basis throughout the Ten Year Intervals.

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOIR THE THIRD TEN-YEAR INTERVAL SEAT LEAKAGE REQUIREMENTS FOR CATEGORY A VALVES Valves for which seat leakage is important may be generally classified as pressure isolation valves (PIVs), containment isolation valves (CIVs), or both. CIVs are required to be included in the IST program as Category A valves. Testing is performed in accordance with OM Code requirements for Category A valves.

The testing of primary containment isolation valves is performed under the BFN 10 CFR 50 Appendix J Program.

For Category A PIVs the maximum allowable leak rate is established at 50% of the capacity of the upstream relief valve for the PIV. In order to ensure that any PIV does not exceed this ultimate leak rate, any PIV which has a leak rate greater than 50% of its upstream relief valve capacity shall be repaired to reduce its leak rate below the 50% figure. The maximum allowable leak rate for closed-loop water-sealed CIVs that are not PIVs is set at the capacity of the upstream relief valve. These limits may be reduced administratively to provide an additional safety margin against excessive leakage between tests.

COLD SHUTDOWN (CSD) TESTING Some of the components listed in the IST program cannot be tested at the quarterly frequencies required by the OM Code. These components are identified as Cold Shutdown components and are addressed by the Cold Shutdown Justifications listed in Appendix D. Testing of these components is required to begin as soon as possible (within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) after the applicable unit reaches the cold shutdown conditions except as follows:

"Testingis not required if the component is within the periodicity requirements of the OM code due to a recent cold shutdown (no need to test simply because of entry into a cold shutdown). This would be the case if a cold shutdown occurred and all tests within the cold shutdown test group had been performed within the last three months. Any decision to forego cold shutdown testing based on time since the last cold shutdown testing must ensure that the three month interval will not be exceeded before the unit is ready to return to power.

"* If the unit is entering a planned outage (refueling, major maintenance) where there will be sufficient time to test all of the required cold shutdown components before return to power operation, the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> requirement may be waived.

"* All cold shutdown tests are required to be performed during each refueling outage.

Once started, testing shall proceed in a normal manner until either all testing is completed or the unit is ready to return to power operation Completion of all cold shutdown testing is not a prerequisite to return to power operation, unless the unit is in a refueling outage Any testing not completed during a cold shutdown must be continued at the next cold shutdown, time and plant conditions permitting, beginning with the last valve tested during the previous cold shutdown. The valve with the longest interval since its last test and which can be tested in the current plant conditions should be tested first Then the valve with the next longest interval should be tested, and so on until all valves deferred to CSD are tested Any valve testing skipped due to plant conditions should be tested as soon as conditions allow.

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL PASSIVE VALVES Category A, B, C, and D passive valves are not required to be stroke-tested for IST purposes. Passive valves are required to be tested for position indication. Category A passive valves are tested to determine compliance with seat leakage criteria. Appendix F contains a listing of valves that have been determined to be passive valves.

BFN CONDITION MONITORING PROGRAM The 1995, 1996 Addenda, ASME OM Code contains an mandatory appendix (Appendix II) which details requirements for implementation of a Condition Monitoring Program for check valves. BFN has identified check valves which will be monitored using this appendix in lieu of the requirements of ISTC 4.5.1 through 4.5.4. The BFN Condition Monitoring Program is described in Appendix G of this program.

APPENDICES APPENDIX A ASME PUMP TEST PROGRAM APPENDIX B REQUESTS FOR RELIEF FOR THE ASME SECTION XI PUMP PROGRAM APPENDIX C RELIEF REQUESTS FOR THE ASME SECTION XI VALVE PROGRAM APPENDIX D REFUELING OUTAGE AND COLD SHUTDOWN JUSTIFICATIONS APPENDIX E ASME OM CODE VALVE MATRIX APPENDIX F PASSIVE VALVE LISTING APPENDIX G BFN CONDITION MONITORING PROGRAM PAGE 10 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX A - ASME PUMP TEST PROGRAM Page 1 of 1 ITEM' PUMP ID FUNCTION ASMIE PUMP DRAWIN'IG/D RAWYING RELIEF SPEED DISCHARG DIFFERENTIAL FLO VIBRATIO

1. CLAS CROU COORDINATES REQUES E PRESSURE W N S P T PRESSURE RAT E

6 0-PMP-023-0001 RHRSW PUMP AI 3 A 1.47E858-1/A-4 N/A NR. Q Q Q 2 I-PMP-023-0005 RHRSW PUMPA2 3 A 1.47W8581I/B-5 N/A NR Q Q Q 3 0-PMP-023-0008 RHRSW PUMP CI 3 A 1.47W85I.I/B.3 N/A NR Q Q Q Q 4 0-PMP-023-0012 RHRSW PUMP C2 3 A 1.47W858-1/B-4 N/A NR Q Q Q Q 1 0-PMP-023-0019 RHRSWPUMP BI 3 A 1.47W858.I/B.4 N/A NR Q Q Q Q 2 0-PMP-023-0039 RHRSWPUMPIB 3 A 1-47W858-I/B-3 N/A NR Q R Q Q Q Q

8 O-PMP-023-0027 RHRSW PUMP D2 3 A 1.47W858-1/B.3 N/A NR NKR Q Q Q Q 3 N/A 9 0.PMP-023-0085 RERSW PUMP A3 3 A 1-47ES59-1/A.4 1.47W85.1I/B. N/A NR 2Q Q Q _ Q 33 A 10 0-PMP-023-0088 REtRSW PUMP PUMP B3 BI A 1-47E8591I/A-4 N/A NR Q Q Q Q 11 0-PMP-023-0091 RRItRSW.HRSW PUMP C3 3 A 1-47E859-1/A-3 NIA NR Q Q Q Q 2 0-PMP-023-0015 12 0-PMP-023-0094 RHRSW PUMP D3 3 A 1-47ES59- I/A-3 N/A NR Q Q Q 12 I-PMP-063-0006A tA SLC PUMP 2 B 1-47E854-1/B-5 PV-1 NR 2 YR NR Q 22 Y YR.

R Q 2YR 12 I-PMP-063-0006B 2B SLC PUMP 2 B 1.47E854.I/-.4 PV-I NR 2 YR NR Q 2Y R. Q Q 2 YR 16 2-PMP-07I-0054 HPCI PUMP 2 B 1-47EBI2.1/F.4 N/A NQ2 YR F- N /A 17 I-PMP-074-0005 RHRPUMPIA 2 A .47 E8 1/ 4 I3-11,47E811-I/B-6 N/A NR Q Q Q Q 22 B 18 I-PMP-074-0016 RHRPUMPIC A 1.47E811.I/D-6 N/A NR Q Q Q Q RC IC PUM P 19 1-0 0 19 I-PMP-074-0028 RHR PUMP IB 2 A 1247E811.I/D.3 NIA NR Q Q Q Q 21 I -PM P-0 7 20 I-PMP-074-0039 RHR PUMP ID 2 A 1-47E811-I/B-3 N/A NR Q Q Q Q 21 I-PMP-075-0005 CORE SPRAY PUMP IA 2 B 1-47E814-1/C-6 N/A NR 2 YR. Q Q 2 YR 22 I.PMP-075-0014 CORE SPRAY PUMP IC 2 B 1-47EX14-1/D-6 N/A NR 2 YR Q Q 2 YR 23 I.PMP-075-0033 CORE SPRAY PUMP 1B 2 B 1-47E814.1/D-3 N/A NR 2 YR Q Q 2 YR 24 1.PMP-075-0042 CORE SPRAY PUMP ID 2 B 1.47E814.1IC.4 N/A NR 2 YR Q Q 2 YR 25 2-PMP-063-0006A 2A SLC PUMP 2 B 2.47E854.1/D.6 PV-I NR 2 YR NR Q 2 YP 26 2-PMP-063-0006B 2B SLC PUMP 2 B 2.47E854.1/D.4 PV.I NR_ 2 YR NR Q2 YR 27 2-PMP-071-0019 RCIC PUMP 2 B 2-47EI.1I./F-4 N/A Q2 YR. Q Q 2 YR 28 2-PMP-073-0054 HPCI PUMP 2 B 2-47E812-1/F.4 N/A Q 2 YR. Q Q 2 YR 29 2-PMP-074-0005 ,HRPUMP2A 2 A 2-47E8 1-I/B-6 N/A NR Q Q Q Q 30 2-PMP-074-0016 RHRPUMP2C 2 A 2-47E811I1/C-6 N/A NR Q Q Q Q 31 2-PMP-074-0028 RHRPUMP2B 2 A 2-47E811-I/B-3 N/A NR Q Q Q Q 32 2-PMP-074-0039 RNR PUMP 2D 2 A 2-47E811-I/D-3 N/A NR Q Q Q 0 33 2.PMP-075-0005 CORE SPRAY PUMP 2A 2 B 2-47E814-1/C-6 N/A NR 2 YR Q Q 2 YR 34 2.PMP-075-0014 CORE SPRAY PUMP 2C 2 B 2-47EE14.1/D-6 N/A NR 2 YR Q Q 2 YR 34 2-PMP-075-0033 CORE SPRAY PUMP 2B 2 B 2-47E814.1/D-3 N/A NR 2 YR Q Q 2 YR 36 2-PMP-075-0042 CORE SPRAY PUMP 2D 2 B 2.47E814.1/C-4 N/A NR 2 YR Q Q 2 YR 37 3-PMP-063-0006A 3A SLC PUMP 2 B A'47E854-.1/D.6 PV.I NR. 2 YR. NR. Q 2 YR.

38 3-PMP-063.000613 3B SLC PUMP 2 B 3-47ER54-1/D.4 PV.I NR 2 YR. NR. Q 2 YR.

39 3-PMP-071-0019 RCIC PUMP 2 B 34*7ESI-4.1/F.4 N/A Q 2 YR. Q Q 2 YR 40 3-PMP-073-0054 HPCI PUMP 2 B 3-47E812-1/F-4 N/A Q 2 YR. Q Q* 2 YR 41 3-P'MP-074-0005 RHR.PUMP 3A 2 A 3.47EX1I-.I/B-6 N/A NP. Q Q* Q Q 42 I-PMP-074-0016 -RHR PUMP 3C 2 A 3.47E811.1/C.6 N/A NR. Q Q Q Q 43 3-PMP-074-0028 RHR.PUMP 3B 2 A 3.47EX1I-.I/B-3 N/A NR. Q Q Q Q 44 1 3-PMP-074.0035 URHRPUMP 3D 2 1 A 347E11 -lI/D-3 N/A NR Q Q Q Q 45 3-PMP-075-0005 CORE SPRAY PUMP 3A 2 B 3-47EXl4-1/C-6 N/A NR 2 YR. Q Q 2 YR.

46 3-PMP-075.0014 CORE SPRAY PUMP 3C 2 B 3-47E8I4.1/D-6 N/A NR. 2YR. YR.

47 3-PM -075-0033 ORE SPRAY PUMP 3B 2 B 3-47E8I4-1/D-3 N/A NR 2 YR. 02 22YR.

48 3-PMP-075-0042 CORE SPRAY PUMP In 2 B 3.47ES14.1/C.4 N/A NR 2 YR. Q I Q 2 YR.

PAGE 11 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX B Page 1 of 1 REQUESTS FOR RELIEF FOR THE ASME SECTION XI PUMP PROGRAM Relief Request No PV-1 System: Standby Liquid Control (SLC) (63)

Drawing 1, 2, 3-47E854-1 Components SLC Pumps A and B (all three units)

Class: 2 Function: Emergency injection of sodium pentaborate into the reactor vessel to bring the reactor from full power to shutdown condition.

Impractical Test Requirement: ISTC 4.7.1(f) - Frequency response range of the readout system shall be from one third minimum pump shaft rotational speed to at least 1000 Hz.

Basis for Relief: ASME OM Code (1995, 1996 addenda) requires a frequency response range of from one-third minimum pump shaft rotational speed to at least 1000 Hertz (Hz) for vibration measuring instruments. The SLC pumps are not variable speed pumps.

The SLC pump shaft rotational speed is 520 RPM, which translates to a frequency response of 8.67 Hz. To comply with the OM Code, TVA would be required to monitor a frequency range of 2.89 Hz (one-third of 8.67 Hz) to 1000 Hz; however, TVA intends to monitor from 6 Hz to at least 1000 Hz.

NUREG-1482 states that the frequency response range of vibration monitoring instrumentation must meet the requirements of ASME/ANSI Standard OM-6 unless the information gained at the low frequency does not apply for the bearing design of the pump in question.

The information gained at a frequency lower than shaft rotational speed is used to detect oil swirl in sleeve type bearings. The bearings on the SLC pumps are roller type. Accordingly, there is no information gathered at a frequency lower than shaft rotational speed that would be applicable.

Therefore, TVA requests relief in accordance with 10 CFR 50.55a(a)(3)(ii) in that compliance with the test requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

This request for rehef was previously approved for use in the BFN Second Ten-Year IST interval. TVA submitted the request for relief (see PV-2) by letter dated May 2, 1994. TVA's request was approved by NRC letter dated May 16, 1995.

Alternative Testing: TVA will monitor the SLC pump vibration using a frequency response range of 6 Hz to at least 1000 Hz. This will encompass all frequencies from just below shaft rotational speed to the 1000 Hz minimum required by the ASME OM Code.

PAGE 12 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL "APPENDIX C Page 1 of 1 RELIEF REQUESTS FOR THE ASME SECTION XI VALVE PROGRAM Relief Request No. PV-2 System: Control Rod Drive (CRD) (85)

Drawing: 1, 2, 3-47E820-2; 2-47E820-5; 1, 3-47E820-6 Components: Scram inlet valve FCV-85-39A (185 valves per reactor)

Scram outlet valve FCV-85-39B (185 valves per reactor)

Category: B (FCV-85-39A and 39B)

Class: 1 (FCV-85-39A and 39B)

Function: Control Rod Scram Water Flow Path.

Impractical ASME OM Code 1995 through 1996 addenda, ISTC 4.2.1 and 4.5.1 Test Exercise valves every three months and measure stroke time.

Requirement:

Basis for These valves located on the hydraulic control units for the 185 control rod drives function Relief. on a reactor scram signal from the reactor protection system to insert the control rods rapidly into the reactor core. Cycling these valves requires scramming a control rod There are 185 control rods in the reactor. Scramming every rod once every three months is not practical for the following reasons*

a. A power reduction is required to test the scram function. Reducing power for the length of time required to scram 185 rods is not practical.

b. Fuel preconditioning must follow this power reduction to avoid possible fuel damage. The longer the reduction in power, the longer the preconditioning.

Their proper functioning is most practically verified by an actual scram test.

Therefore, TVA proposes to use alternate testing requirements provided for in Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs."

This request was previously approved (see PV-21) for use in the BFN Second Ten-Year IST interval by NRC letter dated October 22, 1993.

Alternative Scram testing and rod insertion timing will be performed in accordance with Technical Testing: Specifications Section 3.1.4 (at reactor coolant pressure 800 psig) for:

a. All control rods prior to THERMAL POWER exceeding 40 percent after each refueling outage.

b. A representative sample (at least 10%) on a rotating basis at least once every 120 days cumulative operation in Mode 1.

Note' This testing is in accordance with Position 7 of NRC Generic Letter 89-04 and NUREG 1482 PAGE 13 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX D REFUELING OUTAGE AND COLD SHUTDOWN JUSTIFICATIONS Page 1 of 4 Refueling Outage Justification RO-01 System: Main Steam (1)

Drawing. 47E801-1 Components: Valves FCV-1-14, 26, 37, 51 Class: 1 Function: Main Steam Isolation Valve Inboard of Primary Containment.

Impractical Test ASME OM Code, 1995 through 1996 Addenda, ISTC 4.2.1, Requirement: 4.2.2, and 4.2.6, stroke and fail-safe position testing of valves once each quarter or on a cold shutdown basis.

Basis for Relief: The MSIVs listed, along with their control air isolation valves, stroke adjustment needle valves, and accumulators are located inside primary containment. The fail safe testing of these main steam isolation valves requires the isolation of control air to the valve operator and the venting of the control air accumulator for the valve The full stroke testing of these valves requires access to the drywell in order to adjust stroke times (if needed). Entry is precluded during operation because the containment atmosphere is inerted with nitrogen gas for oxygen and hydrogen control, and radiation dose rates are prohibitive. The inert atmosphere is maintained during most cold shutdown periods.

Alternative Testing: The stroke timing, full-stroke exercising, and fail-safe testing of these valves will be performed during each refueling outage.

PAGE 14 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX D REFUELING OUTAGE AND COLD SHUTDOWN JUSTIFICATIONS Page 2 of 4 Cold Shutdown Justification Number I System: Reactor Recirculation Drawing: 47E817-1 Valves: FCV-68-3, 79 Category: B Class- 1 Function: Pump A&B discharge isolation.

Justification: The recirculation pump discharge isolation valves are in the main flow path of the reactor recirculation system, which is necessary to maintain proper cooling and reactivity control of the reactor. Cycling of these valves during power operations would interrupt the driving core flow, possibly resulting in severe changes in core power level. Cycling of these valves would also isolate that loop of the recirculation system. Failure of the valve to reopen could result in a plant shutdown, depending on plant conditions.

Cold Shutdown Justification Number 2 System: Reactor Building Closed Cooling Water Drawing: 47E822-1 Valves: FCV-70-47 Category: A Class: 2 Function: Primary Containment isolation.

Justification: This valve is in the cooling water return lines for the reactor recirculation pump bearing and seal coolers as well as the drywell atmospheric coolers. Cycling of this valve during power operation would interrupt this cooling water flow, possibly causing pump bearing damage and seal failure. Drywell temperatures could also exceed allowable values, requiring unit shutdown.

PAGE 15 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX D REFUELING OUTAGE AND COLD SHUTDOWN JUSTIFICATIONS Page 3 of 4 Cold Shutdown Justification Number 3 System: Residual Heat Removal Drawing: 47E811-1 Valves: FCV-74-47, 48 Category: A Class: 1 Function: Shutdown cooling isolation.

Justification: These normally closed containment isolation valves are only required to open when bringing the unit to a cold shutdown cooling mode of RHR. Valve 74-47 is normally closed with its breaker off for Appendix R reasons. Cycling these valves with reactor pressure greater than 100 psig is prevented by logic interlocks Cold Shutdown Justification Number 4 System: Main Steam Drawing: 47E801-1 Valves: FCV-1-15, 27, 38, 52 (Outboard MSIVs)

Category: A Class: I Function: Main Steam Isolation for primary containment.

Justification: Cycling of these valves during power operation requires a reduction in power to less than 70 percent of full power and involves the risk of a reactor scram.

PAGE 16 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX D REFUELING OUTAGE AND COLD SHUTDOWN JUSTIFICATIONS Page 4 of 4 Cold Shutdown Justification Number 5 System: Main Steam (01)

Drawing: 2, 3-47E807-2 (MS)

Components: Main Steam Steam Seal Supply Regulator valve 1-147 Category: B Class: 2 Function: Boundary valve for the MSIV Alternate Leakage Path Justification: This valve is normally closed when the unit is operating above 25% power.

Because it is a boundary valve for the MSIV Alternate Leakage Path and it will open between 0% to 25% power, it is necessary to verify that it will close when it is needed. Opening this valve in order to stroke time it closed during operation would be a radiological and safety hazard for personnel. This valve will be tested on a cold shutdown basis.

Cold Shutdown Justification Number 6 System: Main Steam (01)

Drawing: 2, 3-47E801-2 (MS)

Components: Steam Jet Air Ejector (SJAE) Pressure Regulator valves 1-151, -153, -166, -167 Category: B Class: 2 Function: Boundary valve for the MSIV Alternate Leakage Path.

Justification- These valves are normally open during operation to control operation of the SJAE stages 1, 2, and 3 (Trains A and B). Because of plant design there is no practical method of timing each valve closed without personnel being present at the valve This would present a radiological and safety hazard during power operation. These valves will be tested on a cold shutdown basis.

PAGE 17 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E ASME SECTION XI VALVE MATRIX NOTES A. This appendix provides a cross-reference of the valves in the BFN ASME Section XI Pump and Valve IST Program.

B. The test frequencies and their respective abbreviations are as follows:

1. O/OC: Once per Operating Cycle.

2. CSD: Cold Shutdown.

3. Q: Quarterly.

4. COND: Conditional.

5. 0/2 yr: Once per two years.

6. 0/16W: Once per 16 weeks.

7. O/RO: Once per Refueling Outage.

8. E/RO: Every other Refueling Outage.

9. CM: Frequency determined by the Condition Monitoring Program PAGE 18 OF 59

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BROWNS FERRY NUCLEAR PLANT INSERVICE, TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL 7vý.APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWVING CTEGOR SIZE VLV ACTUATOF N4ORMAL SAFETY TEST RELIEF TEST CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ NTERVA.

RO/CSDJ - L 235 1-SIIV.7I-0014 RCIC TRB LXIIVLV 2 I-47ES13-I/D-7 AC K SC 11/SELF 0 0/C /VVRP1 N/A CMI L

_______ ~~LT _______

236 1-FCV-71-00I7 FSC TO RCIC INBD ISOL 2 1-47ES13-1/B3-6 A 6 CA MIO C 0/C Q N/A Q LT N/A 0OlC

_____ ____VRPIL N/A 0/2YR 237 1-FCV-71-0019 PSC TO RCIC OUTBD) ISOL 2 1-47ES13-I/G-4 A 6 GA MlO C 0/C Q N/A Q LT N/A 0/OC

_____ ____VRPIL N/A 0/ZYR 23K I-RFV-71-0019 RCICPMPSUCTRLF 2 I-47E213-I/G-4 C I RV SELF C 0 RV N/A CONII 239 I-FCV-71-0025 RCIC LUBE OIL CLGVrR 2 1-47ES1341/B-4 B 2 GL MIO C 0/C Q N/A Q

____VRPIL N/A 0/2YR 240 "I-SV-7I-0032 RCIC COND VC PAMPDISCII 2 1-47ES13-I/D-,7 AC 2 SC 11/ELF C C C/VRPI N/A CMI L

LT 241 1-FCV-71-0034 RCIC FP AIIIN FLOWV 2 1-47EK13-I/E-5 A 2 GL M C 0/C Q N/A Q o LT N/A 0/OC 1"

___VRPIL N/A 0/2YR_

242 1-FCV-71-0037 RCICINJ OUTBD ISOL 2 147ES13-I/F-5 B 6 GA MIO 0 0 Q N/A Q

____VRPIL N/A O/2YR 243 1-FCV-71-003S RCIC PM? TEST RTN To ST 2 1-47ES13-1/G-5 B 4 GL MWO C C Q N/A Q

____VRPIL N/A 0/2YR 244 I-FCV-71-0039 RCIC INJ INBO ISOL 2 I-47E$13-1/F-6 B 6 GA MlO C 0/C Q N/A Q VRPIL N/A 0/2YR 2451 I.FCV-71-0040_ RCIC TESTABLE CLV 1 1-47ES13-1/F-6 AC 6 CL AO/SELF C 0/I VLT NA C 12461 I-CKCV-71-0499 CISTTO ECIC PIP INLT 2 1-47EKII-I/G-4 C 6 CL SELF C 0/C CV NA 6 247 1 -CKV-71-OSK FlSC TO RCIC PSIP INLT 2 I.47EK13-I/B6 C 6 CL SELF C 0 CV NA M 2481 I-RFV-71-0543 RCIC COND CLGWTVR 2 I-47EI3-I/B1-4 C 1 RV SELF C 0 V NA CD 1249 I-CKV-71-0-547 RCIC PMIP MIN FLOW 2 I-47ESI3-I/E5 AC 2 CK SELF- C 0/C C/T NA C 2510 1-CKV.71-0590 RCICTRB EXH CKV 2 I-47ES13-I/E-7 AC 10 CR SELF C 0/C CV/LT N/A Cml 251 I-CKV-71-0589 RCIC COND PM? CKV 2 1-47ES13-I/A-3 C 2 CK SELF C C CV N/A CMI 252 I-CKV-71-0592 RCICVCPMPD1SCII 2 1-47ES13-I/D-5 AC 2 CR SELF C C CV/LT N/A CMI 253 I-CKV-71-0597 RCICTRBEXHJVCRLF 2 I-47ES13-1/E7 C 2 CK SELF C 0 -CV- N/A CM%

2-54 I.CRV-7"-599 RCICTRBEXIUIVCRLF 2 1-47E813-1/E-7 C 2 CR SELF C 0 CV N/A CMl 255 I-CKV-71-0999 RCIC TREEIt VC ELF 2 1-471`13-M/D7 C 2 CK SELF C- 0- CV N/A CIN 256 I-CKV-71-0600 RCICTEBEXI1VCRLF 2 1-47EM131/D-7 c 2 CR SELF C 0 CV N/A CMI 257 1-FCV-73-0002 IIPCI STMILN LNBD ISOL I I-47]E$12-I/G-7 A 10 GA MO 0 0 /C Q N/A Q

___VIRPIL N/A O/2YR 250 1-FCV-73-1113 IIPCI STM LN OUTBD ISOL I I-47E812-1/G-6 A 10 GA MO 0 0/C Q N/A Q

___VRPIL N/A 0/2YR 259 1-FCV-73-0006A IIPCI STMILN TO COND DRIN 2 1-47ESI2-I/E-2 B I GA AO 0 0/C Q N/A Q

_________VRPIL N/A O/2YR 260 I-FCV-73-0016 HPCI TRB SAIMSPLY VLV 2 I-47ES12-I/G-3 B 10 GA MO C 0 Q N/A Q

___VIRPIL N/A 0/ZYR 261 I-FCV-73-0019 IIPCI TRB STOP VLV 2 I-47ESM12I/-3 B 10 GA E/H C 0 Q, FS N/A Q

____VRPIL N/A O/2YR 262 1-ISV-73-0023 1IPCI TRB EXII VLV 2 I-47EK12-I/D)-7 AC 16 SC H/ELF 0 0/C /~VRPI N/A CAI L

__________ _____ LT ___

263 I-ISV-73-0024 I!PCI LXIICOND POT DISCII 2 -47ES12-I/D6 AC 2 SC 11/SELF C C CV/LT N/A CM%

264 1-FCV-73-0026 PSC TO IIPCI INBD ISOL 2 1-47ES12-1/B-6 A 16 GA MOD C 0/C Q N/A Q LT N/A 0/OC

_____________VRPIL N/A 0/2YR 265 I-FCV-73-0027 PsC TO IIPCI OIJTBD ISOL 2 1-47ES12.1/G-S A 16 GA MO1 C 0/C Q N/A Q LT N/A 0/OC

_____________VRPIL N/A 0/2YR 266 I-FCV-73-0030 tipC ipM MIN FLOW 2 1-47EK12-/D-S A 4 GL MO1 C 0/C Q N/A Q LT N/A 0/OC

_____________VRPIL N/A 0/2YR 267 1-FCV.73-0034 IIPCI INJ OUTBD ISOL 2 1-47ES12-1/F-6 B 14 GA MO%1 0 0 Q N/A Q

_________ ____VRPIL N/A 0/OC 268 I-FCV-73-0035 IIPCI PMI TEST RTN TO CST 2 147ESM2I/F-6 B 10 GL MO0 C C Q N/A Q

_____________VRPIL N/A 0/2YR 269 1-FCV-73-0j040 11PCI PMI SUCTION ISOL 2 1-47ES12-I/II-5 B 14 GA MO1 0 C Q N/A Q

_____ ____VRPIL N/A 0/ZYR 270 1-FCV-73-0044 IIPCI IN.I INBD ISOL 2 1-47EK12-l/F-6 B 14 GA 1%10 C 0/C Q N/A Q

_____________VRPIL N/A 0/2YR 271 1-FCV-73-0045 I11'CI TESTABLE CKV I 1-47E82-1/E-6 AC 14 CR AO/SELF C 0/C /VPI N/A CMI L

_____ _____LT 272 I-FCV-73-0081 I-FCV-73-3 BYPASS I 1-47ES12-1/G-6 A I GL MlO 0 C Q N/A Q LT N/A 0/OC

______________VRPIL ,N/A O/2YR

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR-THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX VALVEID FUNCTION ASME DRAWiNG/DRAWLNG CATEGOR SIZE VLV ACTUATO NORMAI SAFETY TEST RELIEF TEST CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ INTERVA RO/CSDJ L 278 1.CK-V-73-0603 IIPCI TRB LXlI CHECK 2 1-47E8lT-I/D-7 AC 20 CK SELF C O/C CV/LT N/A CM 279 -CKV-73-0609 JIPCI TRB EXII DRN CHECK 2 1-47E812-I/D-6 AC 2 CK SELF C C CV/LT NIA CM 280 1-CKV-73-0625 IIPCIPMPGLNDSLRTN 2 1-47ESI2-1fB-4 C 2 CK SELF C C CV N/A CM 281 1-CKV-73-0633 HPCI TRB EXI VC RLF 2 I-47ESI2-1/D-7 C 2 CK SELF C 0 CV N/A CM 282 1-CKV-73-0634 IIPCI TRB EXII VC RLF 2 1-47E812-I/D-7 C 2 CK SELF C 0 CV N/A CM 283 I-CKV-73-0635 tIPCI TRE EXII VC RLF 2 1-47E812-I/E-7 C 2 CK SELF C o CV N/A CM 284 1-CK'V-73-0636 HIPCI TRB EXT! VC RLF 2 1-47ES12-I/E.7 C 2 CK SELF C 0 CV N/A CM 285 I-RPD-73-0729 IIPCI TRB EXtl RP DISC 2 1-47E812-1/D-4 D 16 RD SELF C 0 VI N/A 0/SYR 286 I-FCV-74-0001 REIIRPMIAPSCSUCT 2 1-47E811-l/B-S B 24 GA MO 0 0/C Q N/A Q VRPIL N/A O/2YR 287 1-FCV-74-0002 RIIRPMPASDCLGSUCT 2 1-47E811-1/C-6 B 20 GA MO C 0/C Q N/A Q VRPIL N/A O/2YR 288 I-FCV-74-0007 RIIR LPI1MIN FLOWV 2 1-47E811-1/D-6 B 4 GA MO 0 O/C Q N/A Q VRPIL N/A O/2YR 289 I-FCV-74-0012 RIlR PFMP C PSC SUCT 2 1-47ESI-I/D-5 B 24 GA MO 0 O/C Q N/A Q VRPIL N/A 0/2YR 290 1-FCV-74-0013 RIIRPhIPCSDCLGSUCT 2 1-47ES1I-I/D-6 B 20 GA MO C O/C Q N/A Q VRPIL N/A O/2YR 291 1-FCV-74-0024 RIIR PMP B PSC SUCT 2 1-47E11-I/C-4 B 24 GA MO 0 0/C Q N/A Q VRPIL N/A O/ZYR 292 1-FCV-74-0025 RIIR PMP B SD CLG SUCT 2 1-47ES11-I/D-4 B 20 GA MO C 0/C Q N/A Q VRPIL N/A O/2YR 293 1-FCV-74-0030 RIIR LP I1 MIN FLOW 2 1-47ES11-I/D-3 B 4 GA MO 0 O/C Q N/A Q

_ VRPIL N/A O/2YR 294 I-FCV-74-0035 RHR PMP D PSC SUCT 2 I-47ES11--l/B-4 B 24 GA MlO 0 0/C Q N/A Q VRPIL N/A O/2YR 295 I-FCV-74-0036 REIRPIMPDSDCLGSUCT 2 1-47ES11-1/C-4 B 20 GA MO C 0/C Q N/A Q VRPIL NIA O/2YR 296 I-FCV-74-0047 RiIRSDCLGOUTBDISOL 1 1-47ES11-I/E-5 A 20 GA MO C O/C Q CSDJ-03 CSD LT N/A O/OC VRPIL N/A O/2YR 297 1-FCV-74-0048 RIIR SD CLG LNBD ISOL 1 1-47E811I/E-5 A 20 GA MO C O/C Q CSDJ-03 CSD LT N/A O/OC VRPIL N/A 02tYR 298 I-FCV-74-0052 RIIR LPI TITROTTLE 2 1-47E811-I/F-7 B 24 AN 10 0 0 Q N/A Q VRPIL N/A 0/2YR 299 I-FCV-74-0053 RIIR LP I INJ I 1-47ESII-1/F-6 A 24 GA MO C O/C Q NIA Q LT NIA O/OC VRPIL NIA 0/2YR 300 I-FCV-74-0054 RIHR LP I TESTABLE CKV I 1-47ES11-I/F-6 AC 24 CK AO/SELF C O/C CV/LT N/A CM 301 1-FCV-74-0057 RIIR LP I PSC RTN 2 1-47EM11-IIG-8 A 18 GA MO C O/C Q N/A Q LT N/A 0/OC VRPIL NIA 0/2YR 302 I-FCV-74-0058 RIIR LP I PSC SPRAY 2 1-47ES11-1/F-, A 4 GL blO C O/C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 303 I-FCV-74-0059 RIIRLPIFIMPTESTRTN 2 1-47ES11-I/F-3 A 12 GL MO C O/C Q N/A Q LT N/A 0/OC VRPIL N/A 0/2YR 304 I-FCV-74-0060 RIIR LP I CNTMT SPRAY 2 1-47ES11-1/C-6 A 12 GA MO C O/C Q N/A Q OUTBD ISOL LT NIA 0/OC VRPIL NIA O/2YR 305 I-FCV-74-0061 RIIR LI I CNTMJr SPRAY MNIE 2 1-47E811-I/C-5 A 12 GA MO C 0/C Q N/A Q ISOL LT N/A O/OC VRPIL N/A 02YR 306 1-FCV-74-0066 RIIR LP II THROTTLE 2 1-47E811-I/F.-3 B 24 AN MO 0 0 Q N/A Q VRPIL N/A O/2YR 307 1-FCV-74-0067 RHR LP II LNJ 1 1-47ES11-I/F-4 A 24 GA NMO C O/C Q N/A Q LT N/A 0/OC VRPIL N/A 0/2YR 308 I-FCV-74-0068 RIIR LP 11TESTABLE CKV 1 1-47E01 -5/F-4 AC 24 CK AO/SELF C 0/C CV/LT NIA CM 309 I-FCV-74-0071 RIIR LP II PSC RTN 2 1-47E811.I/G-2 A i1 GA MlO C 0/C Q N/A Q LT N/A 0/OC VRPIL S N/A 0/2YR 310 I-FCV-74-0072 RIIRLPIIPSCSPRAY 2 1-47E81I-I/F-2 A 4 GL MO C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 311 I-FCV-74-0073 RIIRLPIIPFIPTESTRTN 2 1-47ES11-1/F-2 A 12 GL MIO C 0/C Q N/A Q LT N/A 0/OC VRPIL N/A O/2YR 312 I-FCV-74-0074 RIIR LPII CNTMT SPRAY 2 1-47E81I-I/G-4 A 12 GA MO C 0/C Q N/A Q OUTBDISOL LT N/A O/OC VRPIL N/A O/2YR 313 I-FCV-74-0075 EIIR LP 11ICNTMT SPRAY INBS 2 1-47E11-I/C-5 A 12 GA MO C 0/C Q N/A Q ISOL LT N/A 0/OC I I I VRPIL N/A 0/2YR 314 I-FCV-74-0098 RIIR PMP B SUCT XTIE 2 1-47E811-1/C-4 B 14 GA MO C 0 Q N/A Q VRPIL N/A O/2YR 315 1-FCV-74-0099 RIIR PMFDSUCTXTIE 2  !-47ES11-1/C-4 B 14 GA MO C 0 Q N/A Q VRPIL N/A 0/2YR PAGE 24 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWLNG/DRAWVING CATEGOR SIZE VLV ACTUATOF NORIMAL SAFETY TEST RELIEF TEST CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ ITERVA RO/CS1X. L 316 I-FCV-74-0101 RIIR IITX B-D DISCIIXTIE 2 1-47ESI1-I/D-1 B 10 GA MO C 0 Q N/A Q VRPIL NIA O/2YR 317 1-RFV-74-0509A RtIR MP A SUCT RLF 2 1-47ES11-I/B-6 C I RV SELF C 0 RV N/A COND 318 1-RFV-74-0509B RItR M? BISUCT RLF 2 1-47E11-1/D-4 C 1 RV SELF C 0 RV N/A COND 319 I-RFV-74-0509C RIIREFMPCSUCTRLF 2 1-47E111-l/D-6 C 1 RV SELF C 0 RV NIA COND 320 1-RFV-74-0509D RIlR FMEPDSUCT RLF 2 1-47E-11.1/B-3 C I RV SELF C 0 RV NIA COND 321 1 -CV-74-0559A RIIR MP A DISCl CRKV 2 1-47ES11-l/B-7 C 20 CK SELF C O/C CV N/A Q 322 I-CKV-74-0559B RITR PMP B DISCIE CKV 2 I-47ESl-1/D-3 C 20 CK SELF C O/C C'V N/A Q 323 1.CKV-74-0559C RItR PMPCDISCII CKV 2 1-47ES11-1/C-7 C 20 CK SELF C O/C CV N/A Q 324 1-CKV-74-0559D RJIT EMP D DISCII CKV 2 1-47ESll-1/B-3 C 20 CK SELF C O/C CV N/A Q 325 I-CKV-74-0560A RIR PMEPAAMIN FLOWV 2 1-47E11I-l/B-6 C 3 CK SELF C O/C CV N/A CM 326 I-CKV-74-0560B RI1R EMP A MIN FLOW 2 1-47E51 IIl/D-3 C 3 CK SELF C O/C CV N/A CAI 327 I-CKV-74-0560C RIR PMFAMINFLOW 2 1-47ES11IImD-6 C 3 CK SELF C O/C CV N/A Chi 321 I-CKV-74-0560D RIER PMPA AMIN FLOW 2 1-47E11I-I/B-3 C 3 CK SELF C O/C CV N/A CM 329 I-RFV-74-0579A RIIRIKTXARLF 2 1-47ES11-1/B-7 C 1 RV SELF C 0 RV N/A COND 330 1-RFV-74-0578B RUE IITX BRLF 2 I-47E811-1/C-2 C I RV SELF C 0 RV N/A COND 331 1-RFV-74-057RC RIEIIIT CRLF 2 1-47E811-1/C-S C I RV SELF C 0 RV N/A COND 332 1-RFV.74-0578D RIR HTX D RLF 2 1-47ES11-l/B2 C I RV SELF C 0 RV N/A COND 333 1-RFV-74-0587A RIIR LP IDISCI1 T1DRRLF 2 .-47E111-1/G-7 C I RV SELF C 0 RV N/A COND 334 I-RFV-74-0587B RIIR LP II DISCHHDR RLF 2 1-47ES11.1/G-3 C I RV SELF C 0 RV N/A COND 335 I-RFV-74-0659 RIIR SD CLG SPLY RLF 2 1-47ES11-1I/E-5 C I RV SELF C 0 RV N/A COND 336 1-CKV-74-0661 RIIR THERMAL RLF I 1-47E111I-/F-5 AC 3/4 CK SELF C O/C CV/LT N/A CM 337 1-CKV-74-0662 RIIRETIERMALRLF I 1-47E811I-/F-5 AC 3/4 CK SELF C O/C CVfLT NIA CM 331 I-HCV-74-0722 PSC DRN ISOL 2 1-47ES11-I/E-4 A 9 GA 1I C C LT N/A O/OC 339 1-CKV-74-0792 RIIRLPIKPFILL 2 1-47E811-1/H-6 AC 2 CK SELF O/C C CVILT N/A Cm 340 1-CKV-74-0802 RHR LP IRKP FILL 2 1.47E811-1/it-3 AC 2 CK SELF O/C C CV/LT N/A CM 341 1-CKV-74-0803 RUR LP II KP FILL 2 1-47ES11-I/H-3 AC 2 CK SELF O/C2 C CV/LT N/A CM 342 1-CK-V-74-0804 RIlR LP I KP FILL 2 1-47E811-1/tl-6 AC 2 CK SELF O/C C CV/LT N/A CM 343 I-FCV-75-0009 CS LP I MIN FLOWV 2 1-47ES14-1/F-5 B 3 GA MO 0 O/C Q N/A Q I VRPIL N/A 0/2YR 344 1-FCV-75-0022 CSLPIPNMPTEST 2 1-47ES14-1/F.5 B 10 GL IMO C C Q N/A Q VRPIL N/A 0/2YR 345 1-FCV-75-0023 CS LP I INJ 2 1-47E14--1/F-6 B 12 GA MO 0 0 Q N/A Q VRPIL NIA 0/2YR 346 I-FCV.7-5-0025 CS LP I INJ 1 1-47ES14-1/F-6 A 12 GA MIO C 0 Q N/A Q LT Nq/A O/OC VRPIL N/A O/2YR 347 I.FCV-75-0026 CS LP I TESTABLE CKV I 1-47E814-I/F-7 AC 12 CK AD/SELF C O/C CV/LT N/A CM 341 1.FCV-75-0037 CS LP II MIN FLOW 2 1-47E814-1/F-4 B 3 GA MO 0 O/C Q N/A Q VRPIL N/A 0/2YR 349 I.FCV-75-0050 CSLPII PMEPTEST 2 1-47ESI4-1/F-4 B 10 GL MO C C Q N/A Q VRPIL N/A 02YR 350 I-FCV-75-0051 CS LP II INJ 2 1.47E814-1/G-6 B 12 GA AI0 0 0 Q N/A Q VRPIL NIA 0/2YR 351 I-FCV-75-0053 CS LIP 11INJ 1 1-47ES14-1/G-6 A 12 GA MO C 0 Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 352 I.FCV.75-0054 CS LP 1I TESTABLE CKV 1 1-47ES14-1/C-7 AC 12 CK AO/SELF C O/C CV/LT N/A CMI 353 I-FCV-75-0057 CS DEN FME A LNBD ISOL 2 1-47ES14-1/B-4 A 3 GL AO 0 C Q N/A Q LT NIA OIOc VRPIL N/A O/2YR 354 I-FCV-75-0058 CS DEN PME A OUTBD ISOL 2 1-47ESI4-1/B-5 A 3 GL AO 0 C Q N/A Q LT N/A D/Oc VRPIL NIA O/2YR 355 I-RFV-75-0507A CS EME A SUCT RLF 2 1-47ES14.-1/C-4 C I RV SELF C 0 RV N/A COND 356 I-RFV-75-0507B CS PMP B SUCT RLF 2 1-47ES14-1/C-2 C I RV SELF C 0 RV N/A COND 357 1-RFV-75-0507C CS PMP C SUCT RLF 2 1-47ES14-1/C-6 C 1 RV SELF C 0 RV NIA COND 358 I-RFV-75-0507D CS PMP D SUCT RLF 2 I-47E814-1/C-4 C I RV SELF C 0 RV NIA COND 359 I-CKV-75-0537A CS FMP A DISCH CKV 2 1-47ES14-1/D-4 C 12 CK SELF C 0 CV NIA Q 360 I-CKV-75-0537B CSPMEPBDISCIICKV 2 1-47ES14-1/D-3 C 12 CK SELF C 0 CV N/A Q 361 I-CKV-75-0537C CSPNIPCDISCIICKV 2 1-47ES14-1fD-6 C 12 CK SELF C 0 CV NIA 0 362 I-CKV-75-0537D CSIPMEDDISCII CKV 2 1-47ES14-1/D-4 C 12 CK SELF C 0 CV N/A Q 363 1-RFV-75-0543A CSLPI DISCII RLF 2 1-47E814-1/F-4 C 1 RV SELF C 0 RV N/A COND 364 I-RFV-75-0543B CS LP If DISCII RLF 2 1-47ES14-1/E-4 C 1 RV SELF C 0 RV NIA COND 365 I-CKV-75-0570A CS PIMP A MIN FL*W 2 1-47E14,-1/D-5 C 3 CK SELF C O/C CV NIA CM 366 I-CKV-75-0570B CS PKEB MIN FLWV 2 1-47E14-1/D-2 C 3 CK SELF C O/C CV NIA CI 367 I-CKV-75-0570C CS PIP C MIN FLWV 2 1-47E814-1/D-6 C 3 CK SELF C O/C CV NIA C1M 368 I-CKV-75-0570D CS PIP D MIN FLIW 2 1-47ES14-1/D-4 C 3 CK SELF C O/C CV NIA CMT 369 I-CKV-75,-606 CSLPIKPFILLCKV 2 1-47ES14-I/F-5 AC 2 CK SELF O/C C CV/LT NIA CM 370 I-CKV-75-0607 CS LP I KP FILL CKV 2 1-47ESI4-1/F-5 AC 2 CK SELF O/C C CV/LT N/A CMl 371 1I-CKV-75-0609 CS LP 1i KP FILL CKV 2 1-47ES14-1/I-4 AC 2 CK SELF O/C C CV/LT N/A CM 372 I-CKV-75-0610 CSLPIIKPFILLCKV 2 I-47ES14-1/li-4 AC 2 CK SELF O/C C CVILT NIA CM 373 I-FCV-76-0017 DWN2 MKUP OUTBD ISOL 2 1-47E860-1/C-6 A 2 BF CYL O/C C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 374 I.FCV-76-001 DWN2 MKUP INBD ISOL 2 1-47E160-I/C-6 A 2 EF CYL O/C C Q NIA Q LT N/A O/OC VERPIL N/A 0/2YR PAGE 25 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVEID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ,CTUATOI NORMAl SAFETY TEST RELIEF TEST CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ ITERVA RO/CSDJ L 375 I-FCV-76-0019 PSCN2 NKUP INBD ISOL 2 1-47E860-S/B-5 A 2 BF CYL O/C C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 376 I-FCVo76-0024 DWN2 PURGE OUTBD ISOL 2 1-47E860-1/C-5 A 10 BF CYL C C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 377 I-FSV-76-0049 DW 112 ANLYZR A INED ISOL 2 1-47E1610-76-3/D-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 378 1-FSV-76-0050 DWI12 ANLYZRA OUTBD ISOL 2 1-47E1610-76-3/D-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 379 I-FSV.76-0051 DW 02 ANLYZR A LNBD ISOL 2 I-47E1610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q

_ LT N/A O/OC 380 1-FSV-76-0052 DWO2ANLYZRAOUTBD ISOI 2 I-47E1610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 381 I-FSV.76-0053 PSC 02 ANLYZR A INBD ISOL 2 1-47EI610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 382 I-FSV-76-0054 PSC 02 ANLYZR A OUTBD 2 1-47E1610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q ISOL LT N/A O/OC 383 1-FSV-76-0055 PSCH2IANLYZRAINBDISOL 2 1-47EI610-76-3/E-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 314 I-FSV-76-0056 PSCii2ANLYZRAOUTBD 2 1-47E1610-76-3/E-7 A 1/2 GA S O/C O/C Q N/A Q ISOL LT N/A O/OC 385 1-FSV-76-0057 PSC RTN INBD ISOL 2 1-47EI610-76-3/E-7 A 1/2 GA S 0 O/C Q N/A Q LT N/A O/OC 386 1-FSV-76-0058 PSC RTN OUTBD ISOL 2 1-47E1610-76-3/E-7 A 1/2 GA S 0 OC Q NIA Q LT N/A O/OC 387 1-FSV-76-0059 DWII2ANLYZRB INBD ISOL 2 1-47EI610-76-3/D-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 388 I-FSV-76-0060 DWIV2 ANLYZR B OUTBD ISOI 2 1-47E1610-76-3/D-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 389 1-FSV-76-0061 DW 02 ANLYZR B INBD ISOL 2 1-47E1610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 390 I-FSV-76-0062 DW 02 ANLYZR B OUTBD ISOI 2 1-47EI610-76-3/F-7 A 1/2 GA S O/C OC Q N/A Q LT N/A O/OC 391 I-FSV.76-0063 PSCO2ANLYZRBINBDISOL 2 1-47EI610-76-3/F-7 A 1/2 GA S O/C O/C Q NIA Q LT N/A O/OC 392 I-FSV-76-0064 PSC 02 ANLYZR B OUTBD 2 1-47E1610-76-3/F-7 A 1/2 GA S O/C O/C Q N/A Q ISOL LT N/A O/OC 393 I-FSV-76-0065 PSC H2 ANLYZR B INBD ISOL 2 1-47E1610-76-3/E-7 A 1/2 GA S O/C O/C Q N/A Q LT N/A O/OC 394 I-FSV-76-0066 PSCII2ANLYZRB OUTBD 2 1-47E1610-76-3/E-7 A 1/2 GA S O/C O/C Q N/A Q ISOL LT N/A O/OC 395 I-FSV-76-0067 PSCRTh INBD ISOL 2 1-47E1610-76-3/E-7 A 1/2 GA 5 0 O/C Q N/A Q LT N/A O/OC 396 I-FSV-76-0068 PSC RTN OUTBD ISOL 2 1-47EI610-76-3/E-7 A 1/2 GA S 0 O/C Q N/A Q LT N/A O/OC 397 1-CKV-760653 TIP INDEXER PURGE CKV 2 1-47E600-14/B-5 AC 1/4 CK SELF C C CV/LT N/A Chi 398 1-FCV-77-0002A DWFLRDRNSUMPINBD ISOL 2 1-47E852-I/C-4 A 3 GA AO 0 C Q N/A Q LT N/A O/OC VRPIL N/A 012YR 399 I-FCV-77-0002B DW FLR DRN SUIP OUTBD 2 1-47E852-1/C-4 A 3 GA AO 0 C Q N/A Q ISOL LT N/A O/OC VRPIL N/A 0/2YR 400 1-FCV-77-0015A DWEQDRNSUMPINBDISOL 2 1-47E852-2/D-3 A 3 GA AO 0 C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 401 1-FCV-77-0015B DWEQ DRN SUbP OUTBD 2 1-47E852-2/D-3 A 3 GA AO 0 C Q N/A Q ISOL LT N/A O/OC VRPIL N/A O/2YR 402 I-FCV-78-0061 RIlR TO FPC SPLY 2 147E855-1/!I-6 B 6 GL MIO C 0 Q N/A Q VRPIL N/A O/2YR 403 1-FCV-78-0062 RIIR TO FPC SPLY 3 1-47E8S55-1/11-5 B 6 GA mO C o Q N/A Q VRPIL N/A O/2YR 404 1-SIIV-78-0524 FUEL PL DIFF A ISOL 3 1-47E855-1/11-5 E 8 GL II LO C 0 N/A 0 405 1-CKV-78-0526 FUEL PL DIFF A SPLY 3 1-47E855-1/C-5 C 8 CK SELF O/C 0 CV N/A CM 406 1-FSV-.4-0008A DWN2 SPLY TIN A 2 1-47E862-1/E-7 A 2 GA S C O/C Q N/A Q LT N/A OOC VRPIL N/A 0/2YR 407 1-FSV-34-000SB PSCN2SPLYTRNA 2 1-47E862-1/E-5 A 2 GA S C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 408 I-FSV-84-0008C PSC N2 SPLY TRN B 2 1-47E862-1/E-5 A 2 GA S C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 409 I-FSV-84-0008D DWN2 SPLY TRN B 2 1-47E862-1/E-5 A 2 GA S C O/C Q NIA Q LT NIA 0/OC VRPIL NIA O/2YR 410 1-FCV-84-0019 DWVPSCDISCIITOSBGT 2 1-47ES62-I/E-2 A 2 GA AO C C Q N/A Q LT NIA O/OC VEPIL NIA 0/2YR PAGE 26 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVEMATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATOI NORMAL SAFETY TEST RELIEF TEST CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST) INTERVA RO/CSDJ L 411 I-FCV-94-0020 DAV/PSCDISCIITOSBGT 2 1-47ES62-1/G-2 A 2 GA AO C C Q N/A Q LT NIA O/OC VRPIL NIA 0/2YR 412 I-CKV-84-060D DWVSPLY CIIECKA 2 1-47E862-1/E-7 AC 2 C, SELF C O/C CV/LT N/A CNI 413 I-CKV-84-0601 PSC SPLY CIIECK A 2 1-47ES62-1/E-7 AC 2 CK SELF C O/C CV/LT N/A CM 414 I-CKV-.4-O602 D'W SPLYCIIECKB 2 1-47E862-1/E-5 AC 2 C- SELF C O/C CV/LT NIA CMI 415 1-CKV-94-0603 PSC SPLY CIECK B 2 1-47ES62-1/E-5 AC 2 CK SELF C O/C CV/LT N/A CM 416 1-FCV-.5-0037C SDIVDRNISOLWEST 2 1-47ES20-6/I7-6 B 2 GL AO 0 C Q/FS N/A Q VRPIL NIA O/2YR 417 1-FCV-SS-0037D SDIV DRN ISOLWEST N 1-47ES20-6/B-5 B 2 GL AO 0 C Q/FS N/A Q VRPIL NIA O/2YR 418 I-FCV-85-0037E SDIV DRN ISOL EAST 2 1-47ES20-6/B.3 B' 2 GL AO 0 C Q/FS NIA Q I VRPIL N/A 0/2YR 419 I-FCV-S5-0037F SDIV DRN ISOL EAST N 1-47E820-6/B-3 B 2 GL AO 0 C QIFS N/A Q VRPIL N/A O/2YR 420 1-FCV-95-0039A SCRM INLT(IS5 TOTAL) 1 1-47E820-2/F-3 B I GL AO C 0 Q/FS PV-2 0/16_

421 I-FCV-95-0039B SCRM OUTLT(15 TOTAL) I 1-47E820-2/F-4 B 3/4 GL AO C 0 Q/FS PV-2 O/16WV 422 1-FCV-85-0082 SCRM DISCIIIDR VT W N 1-47E820-61G-7 B 2 GL AO 0 C QIFS N/A Q I VRPIL NIA 0/2YR 423 1-FCV-35-0082A SCRM DISCH HDR VT W 2 1-47E820-6/C-7 B 2 GL AO 0 C QIFS N/A Q VRPIL NIA 012YR 424 1-FCV-SM-083 SCRM DISCH HDR VT E N 1-47E820-6/G-3 B 2 GL AO 0 C QIFS N/A Q VRPIL N/A 0/2YR 425 1-FCV-35-0093A SCRM DISCIIIIDR VIE 2 1-47ES20-6/G-3 B 2 GL AO 0 C Q/Fs N/A Q VRPIL N/A O/2YR 426 I-CKV-85-0589 CIIGING WrR(Q85 TOTAL) 2 1-47E820-2/F-3 C 1/2 CK SELF C O/C CV N/A CM 427 1-CKV-85.0S97 CLGIN-TR(ISS TOTAL) I 1-47ES20-2/G-3 C 1/2 CK SELF C C CV NIA CM 428 I-CKV-85-0616 SCRM OUTLT(! 5 TOTAL) 2 1-47E820-2/E-4 C 3/4 CR SELF C 0 CV N/A CM 429 I-FCV-90-0254A DNVLEAKDETISOL 2 1-47E610-90-1/G-2 A 1 PL MO 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 43D 1-FCV-90-0254B DNVLEAKDETISOL 2 1-47E610-90-1/G-1 A 1 PL MO 0 0/C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 431 I-FCV-90-0255 DIV LEAK DET ISOL 2 1-47E610-90-1/G-2 A I PL MO 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 432 I-FCV-90-0257A DWVLEAKDET ISOL 2 1-47E610-90-1/1I-2 A I FL MO 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 433 1-FCV-90-0257B DWLEAKDETISOL 2 1-47E610-90-1/II-2 A I PL MO 0 O/C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 434 I-FCV-94-0501 TIP INDEXER BALL VLV 2 1-47E600-14/B-8 A 3/S BA S C C Q N/A Q LT/VRPI NIA O/OC 435 I-FCV-94-0502 TIP INDEXER BALL VLV 2 1-47E600-14/A-8 A 3/S BA S C C Q N/A Q LT/VRPIL NIA O/OC 436 1-FCV-94-0503 TIP INDEXER BALL VLV 2 1-47E600-14/A-S A 3/S BA S C C Q N/A Q I I_ LT/VRPIL N/A O/OC 437 I-FCV-94-0504 TIP INDEXER BALL VLV 2 1-47E60&-14/A-8 A 3/S BA S C C Q N/A Q LT/VRPIJ NIA Q/OC 438 1-FCV-94-0505 TIP INDEXER BALL VLV 2 1-47E600-14/A-8 A 3/8 BA S C C Q N/A Q T_/VRPI! N/A O/OC PAGE 27 OF 59

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATO NORMAL SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ TERVA RO/CSDJ L 164 2-FCV-71-0017 PSC TO RCIC INBD CNTMT 2 2-47ES13-I/B-6 A 6 GA IO I C O/C Q N/A Q ISOL LT N/A O/OC VRPIL N/A O/2YR 165 2-FCV-71-001S PSC TO RCIC OUTBD CNTMT 2 2-47ES13-11G-4 A 6 GA MO C O/C Q N/A Q ISOL LT N/A O/OC VRPIL N/A O/2YR 166 2-RFV-71-0019 RCICPMPSUCrRLF 2 2-47E813-1/G-4 C I RV SELF C O RV N/A COND 167 2-FCV-71-0025 RCIC LUBE OIL CLGWTR 2 2-47ES13-1/B-4 B 2 GL MO C O/C Q N/A Q

_ SPLY VRPIL N/A O/2YR 168 2-SIIV-71-0032 RCIC COND VC PMP DISC1I 2 2-47E813-1/C-6 AC 2 SC 1/SELF C C CV/VRPI N/A CAI L

LT 169 2-FCV-71-0034 RCIC FMPMIL FL 2 2-47ES13-1/E-5 A 2 GL MO C O/C Q N/A Q LT NIA O/OC VRPIL N/A 0/2YR 170 2-FCV-71-0037 RCIC INJ OUTBD ISOL 2 2-47ES13-1/F-S B 6 GA MO 0 0 Q N/IA Q VRPIL N/A O/2YR 171 2-FCV-71-0038 RCIC PMPIST RTN TO CST 2 2-47E813-1/G-5 B 4 GL MO C C Q Ni/A Q VRP[L N/A 0/2YR 172 2-FCV-71-0039 RCIC INJ INBD ISOL 2 2-47ES13-1/F-6 B 6 GA MO C O/C Q NIA Q VRFIL N/A 0/2YR 173 2-FCV-71-0040 RCIC TSTABLE CK 1 2-47ES[3-I/F-6 AC 6 CK AO/SELF C O/C C'VVRPI N/A CM L LT 174 2-CKV-71-0499 CSTfRCIC PM? INLT 2 2-47E813-1/G-4 C 6 CK SELF C O/C CV N/A CM 175 2-CKV-71-05flg PSC/RCIC PMA INLT 2 2-47ES13-[/B-5 C 6 CK SELF C 0 CV N/A CM 176 2-RFV-71-0543 RCIC COND RLF 2 2-47ES13-./B-4 C I RV SELF C 0 RV N/A COND 177 2-CKV-71-0547 RCIC PM? MINFL CK 2 2-47ES13-1/N-5 AC 2 CK SELF C O/C CV/LT N/A CM 178 2-CKV-71-0580 RCICTRBEX]ICK 2 2-47ES13-1/D-6 AC 10 CK SELF C O/C CV/LT N/A CM 179 2-CKV-71-0589 RCICCONDPMPCK 2 2-47E113-1/B-3 C 2 CK SELF C C CV N/A CM 180 2-CKV-71-0592 RCICVCPMPDISCII 2 2-47E813-11/-5 AC 2 CK SELF C C CV/LT N/A CM 181 2-CKV-71-0597 RCICTRBEXIIVCRLF 2 2-47ES13-1/D-6 C 2 CK SELF C 0 CV N/A CM 182 2-CKV-71-0598 RCICTRBEXIIVCRLF 2 2-47ES13-M/D-7 C 2 CK SELF C 0 CV N/A CM 183 2-CKV-71-0599 RCICTRBEX]IIVCRLF 2 2-47ESI3-I/D-6 C 2 CK SELF C 0 CV N/A CM 184 2-CKV-71-0600 RCICTRBEXIVCRLF 2 2-47ES13.1/D-7 C 2 CK SELF C 0 CV N/A CM 115 2-FCV-73-0002 IIPCI STM LN INBD CTTMIT 1 2-47ES12-1/G-7 A 10 GA AMO O/C Q N/A Q ISOL LT N/A O/Oc VRPIL N/A O/2YR 186 2-FCV-73-0003 IIPCI STM LN OUTBD CNTRNT 2-47ES12-1/G-6 A I0 GA AMO 0 O/C Q LT N/A N/A Q

O/Oc ISOL VRPIL N/A O/2YR 187 2-FCV-71-0006A IIPCI STM LN TO COND DRN 2 2-47E812-1/E-2 B I GA AO 0 O/C Q N/A Q VRPIL N/A O/2YR 189 2-FCV-73-0006B IIPCI STR ,N TO COND DRN 2 2-47E812-1/-2 B 1 GA AO C O0e Q N/A Q VRPIL N/A O/2YR 190 2-FCV-73-0016 IHPCITRBSTOPSFLYVLV 2 2-47ES12-1/G-3 B 10 GA E/O C 0 Q N/A Q I _ IVRPIL N/A O2YR 190 2-FCV-73-0018 HPCI TRB STOP VLV 2 2-47ES17-11G-3 B 10 CA E/11 C 0 Q/S N/A Q VRPIL N/A 012YR 191 2-ISV.73-0023 IIPCI TRB EXHIAUST VLV 2 2-47ES12-I/D-7 AC 16 SC H/SELF 0 O/C CV/VRPI N/A CM L

LT 192 2-ISV.73-0024 HPCI EUI COND POT DISCII 2 2-47E812-1fD-6 AC 2 SC H/SELF C C CV/LT N/A CMi 193 2-FCV-73-0026 PSC TO IIPCI INBD ISOL 2 2-47E812-1/B-6 A 16 GA MIO C O/C Q NIA Q LT N/A O/OC VRPIL N/A O/2YR 194 2-FCV-73-0027 FSCTOIIPCI OUIBD ISOL 2 2-47ES12-I/G-5 A 16 CA MO C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 195 2-FCV-73-0030 IIPCI PMP AIN FL 2 2-47E812-1/D-5 A 4 GL MO C O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 196 2-FCV-73-0034 IIPCI INJ OUTBD ISOL 2 2-47ES12-1/F.6 B 14 CA MO 0 0 Q N/A Q VRPIL N/A O/2YR 197 2-FCV-73-0035 IIPCI PMP TST RTN TO CST 2 2-47ES12-1/F-6 B 10 GL MIO C C Q N/A Q VRPIL NIA O/2YR 198 2-FCV-73-0040 IlPCI FMP SUCTION ISOL 2 2-47ES12-1/H-S B 14 GA M1O 0 C Q N/A Q VRPIL N/A O/2YR 199 2-FCV-73-0044 IIPCI INJ INBD ISOL 2 2-47ESI2-I/F-6 B 14 GA M1O C O/C Q N/A Q I I I VRPIL N/A O/2YR 200 2-FCV-73-0045 IIPCI TSTABLE CK 1 2-47ESI2-I/E-6 AC 14 CK AOiSELF C O/C IV/VRPI N/A CAI L

LT 201 2-FCV-73-001I 2-FCV-73-3 BYPASS 1 2-47E812-1/G-6 A 1 GA I A1 C C Q N/A Q LT N/A O/OC VRPTI. NIA n/2"YR

.1. 4-4-0 .4. 4- - 4 102

_v_ 2-CKV-73-0505 STRI/PCI PMP INLT 2 2-47E812-1/tl-S C i 141CKI SELF C O/C I CV I N/A I CM 203 2-RFV-73-0506 2 2-47EI12-1/C-4 C 11 RVI SELF C 0 1 RV I N/A ICOND 204 2-CKV-73-0517 2 C 116 1CK SELF C 0 1 CV I NIA CM 205 1 2-CKV-73-0559 IlPCI MPIIN FL CIIECK 2 2-47E812-1 SELF C O/C I CVILT I N/A CM XV

-I- C 0 RV NIA COND 206 1 2-RFV-73-0574 TIPCI COND RLF 2 2-47E812-1 RV C jO/C CV/LT N/A CCM 207 1 2-CrV-73-0603 HPCI TRB EXII CIHECK 2-47ES12-1/D-7 AC 1 16 1 CI PAGE 31 OF59

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATO NORSLL I SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ INTERVA RO/CSDJ L 246 2-FCV-74-0099 I1IIRPAIPDSUCTXTIE 2 2-47ES11-IIC-4 B 14 GA AID C 0 Q NIA Q VRPIL N/A 0/2YR 247 2-FCV-74-0100 RIIRIrrX A-C XTIE TO UI B-D 2 2-47E811-1/C-8 B 10 GA MO C 0 Q N/A Q RIIR IrTX VRPIL N/A 0/2YR 248 2-FCV-74-0101 m 7RIR B-D DISCII xIE rIrX 2 2-47E811-1/C-1 B 10 GA MO C 0 Q N/A Q VRPIL N/A O/2YR 249 2-RFV-74-0509A RIIRPMPASUCTRLF 2 2-47E811..I/B-6 C I RV SELF C 0 RV N/A COND 250 2-RFV-74-0509B BIIR BSUCTRLF PMP 2 2-47E8111/C-3 C I RV SELF C 0 RV N/A COND 2-RFV.74-0509C RHR PMP C SUCT RLF 2 2-47E811-I/D-6 C 1 RV SELF C 0 RV N/A COND 251 252 2-RFV-74-0509D RIIR PMP D SUCT RLF 2 2-47E811-1/)-4 C I RV SELF C 0 RV N/A COND 253 2-CKV-74-0559A BIR PMP A DISCII CK 2 2-47E811-1/B-7 C 20 CK SELF C O/C CV NIA Q 254 2-CKV-74-0559B PMP B DISCII CK 17IR 2 2-47E811-1IB-3 C 20 CK SELF C O/C CV N/A 0 255 2-CKV-74-0559C 1R0R PMP C DISCH CK 2 2-47E8 1 -1/1-7 C 20 CK SELF C O/C CV N/A Q 256 2-CKV-74-0559D RHR PMPDDISCIICK 2 2-47ES 1.1/D-3 C 20 CK SELF C O/C CV N/A S 257 2-CKV-74-0560A RIB PMP A MN FLWV 2 2-47E811-1/B-6 C 3 CK SELF C O/C CV N/A CM 258 2-CKV-74-0560B RIIR PMP B MN FLIW 2 2-47E811-1/B-3 C 3 CK SELF C O/C CV N/A CM 259 2-CKV-74-0560C RHRIPMPCMN FLWV 2 2-47ES11-1/D-6 C 3 CK SELF C O/C CV N/A CM  !

260 2-CKV-74-0560 U RHR PMP D MN FLWV 2 2-47ES11I/D-3 C 3 CK SELF C O/C CV N/A CM 261 2-RFV-74-0572A RIIR AHTX RL F 2 2 .47E811-1/E-7 A C RV SELF C C RV N/A COND 262 2-RFV-74-0579B RHR Lrrx B RLL 2 2-47ES1 1-1/B-2 C 2 RV SELF /C C RV N/A COND 263 2-RFV-74-0578C RHRLr C RLF lX 2 2-47E81I-1/HC-7 C I RV SELF C C RV N/A COND IlT FLDRLF X 2 2-47E811-1/D-2 C 2 RV SELF C C RV N/A COND 264 266 2-RFV-74-0578D I2-RFV-74-0597B R11R LP PJR 11DISCII RL F 2 2- -4"/E9I-1/C-3 I DISCFI RLF 2 2-47ES11-/lI-7 CC2 I 1 RV SELF C (c C O RV N/A COND 265 267 2-RFV-74-0587A I2-RF'V 0659 RIRHR tR SDLPCLG SPLY RLF 2 2-47E9I 1-1/E-5 RV N/A CON qD C 1 RV SELF C 0 RV NIA COND 268 2-CKV-74-0661 RIR TRCV L 2-47E811-I/F-5 AC 34 CK SELF 0 O/C CVQLT N/A CA 269 2-CKV-74-0662 RITRMTRCV 2 2-47E811.1/F-5 AC 3/4 CK SELF C O/C CV0LT N/A C M 2- 0722 tICV PSC D SORNI L 2 2-47E 81 I-I/FE-4 A GA iM C c LT N/A 01 OC 270 271 2-CKV-74-0792 RIIRLPIKPFILLCK 2 2-47E811-1/ /-L7 AC 2 CK SELF O/C CVLT N/A CQ 273 2-C'KV-74-0903 FJ1RLP IIKP FILL CK 2 2-47ES11-1 /H-3 AC 2 CK RHR ITKPFILL CK 2 2-47E811-1/FI-3 AC 2 SELF O/C C CV/LT N/A CM 272 274 2-CKV-74-0902 2-CK 'V-74-0 804 RIFR LP LPI 1KPFILL CK 2 2 47E .. 811-111"-

C CVfLT N/A CNI AC_ 2 CK SELF O/C c C 'V/ LI N/A CNI 275 2-FCV-7o-0O09 CS LP I NIN FL 2 2-47E$14-1/F-5 B 3 GA MO 0 O/C Q N/A Q VRIL N/A 0/2YR 276 2-FCV-75-0022 CS LP I PMP TST 2 2-47ES14 *I/F-5 B 10 CL IMO C C Q N/A Q VRPIL N/A O/2YR 278 2-FCV-75-0025 CS LP I INJ 2 2-47E814-I/..6 B 12 GA MO 0 0 Q N/A O/2YR I VRPIL Q LT N/A O/OC VRPIL N/A O/2YR 279 2-FCV-75-0026 CS LP I TSTABLE CK I 2-47ES14-1/F-7 AC 12 CK SELF C O/C CV/LT N/A CM 285 2-FCV-75-0037 CSNLPPAIN MSFL 2 2-47ES14-1/F-4 B 3 GA MO 0 O/C Q N/A Q I 2-47ES14-I/G-6 A 12 GA MIO C 0 VRPIL Q N/A N/A O/2YR Q

273 2-FCV-75-0025 CS LP II WNI 281 2S2 2-FCV-75-0050 2-FCV-75-0051 CS CSLPM A I NJ P PTST 2 2-47E814-1/F-4 B 10 GL MO C C Q N/A Q LP]Ii 2 2-47ES14-1/"- VRPIL NIA O/2YR B 12 GA AIO 0 0 Q N/A Q VRPIL N/A O/2YR 217 2-FCV-75-0053 M LP 1 ICNJL CS 2-47ES14-1/G-6 A 12 GA SEO C 0 Q N/A Q L22 VRP1L N/A O/OC NIA O/2YR 294 2-FCV-75-0054 70 CS LPI TSTABLE CK 2 2-47ES14-1/D-7 AC 12 CK SELF C O/C CV/LT N/A CM 295 2-FCV-75-0057 CS DRNPI MNBD ISOL 2 2-47E814-1/D-4 A 3 GL AO C C Q N/A Q LT VRPIL N /A OIOC N/A Ot2YR 236 2-FCV-75-0058 CS P6P A OUTBD ISOL DRN 2 2-47E014-1/F-5 A 3 GL AO 0 C Q T LT N/A N/A Q O/OC VRPIL NIA 012YR SUCr RLF 2 2-47E81.9-11C-4 C 2 RV SELF C C RV N/A COND 2

289 872-RFV-75-0507C 2-RYV-75-0507A CS PLPA CS P PM~ CSUCT RLF 2 2- -,17E14-IIC-6 230 2-RFV-75-0507B CSLPIPBSUITrRLF 2 2-47E814-1/C-2 C I2 RV RV SELF C C 0C RV N/A COMN 290 2-RFV-75-0507D CS NPFD SUCT RLF RV N/A C 'OND

'2 2-47ES14-1/C-4 C I RV

'291 2-CKV-75.0537A SELF C 0 RV N/A CS P MkP A DISC liICK '2 2 -47F814-1/U-4 COND 292 2-C KT-75-0537B C 12 CK SELF C 0 C PAIP B DISC l] CK '2 . (V N/A Q 2-47 FS14-1/D.3 C 12 CK SELF 3'29 '2-C K V- 7 5-0 75,3 C CS P PM% C D IS CII C K 2 0 e 'V N/A Q

'2 2 -4 7ES 14- 1/ D-6 C 12 CK S EL F C 0 L'V N/ A Q DISCII CK 2 2-47ES14-1/D-4 C 12 CK SELF 0C CV N/A C 2-CKV-75-05371 294'296 2-RFV-7ý4054311 CS PLP CS LP 11DDISC'H RLF 2 2-47ES 295 2-RFV-75-0543A CS LP I DISCH RLF 2 2-47ES4-1/E-4 I4-1/E.4 C I2 RV SELF C C 0C RV N/A QCOND RV N/A COIND CS A N FL CK 2 2 47ES14 .- -1/D-5 C 3 CK SELF C O/C CV N/A Chi 297 299 CKV-75-0570A 2 CK .- "V-7 5-05 70C C S PIP P I%P (2N FL CK 2 7, ,47 E7-47814- 1-2D -6 C_ O cV N/A C5 299 300 2-C 'K'V-75-D570B 2-CKV-75-0570D CS PP MP CS N N F l, C K B MP D MN FL CK 2 E A14-1/D 9 3 CK

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2 2-47ES 14-1/D4 C 3 CK 301 2-CKV-75-0606 SELF C O/C c 'V N/A CS LP I KP FILL CK 2 2 -47ES14-I/F .5, F CM 302 AC 2 CK SELF O/C C 2-CK'V-75-0607 CS LPIKP FILL CK 2 C '%'LT N/A Cl M 2-47ES I,4-I/F-5 AC 2 C 'K SELF 303 2-CK 'V-7-5-0609 C -SLP It K P FILL CK _O IC C CVILT N/A CAI 2 2 -47ES14-1/11-4 AC 2 3 04 2- CK 7'V- 5, 0 6 10 K SELF O/C C C 'v/LT N /A CS L PI I K P F IL L C K 2 2- 7 -4 E81 4 -/I I- 4 c Mf AC 2 CK S E LF O /C c 305 2-FCV-76-0017 DNVN2b MKUP OUTBD ISOL C 'V/LT NIA CN I 2 7,.47ES60- 1/E - A 2 F AO O/C C Q N/A Q LT N/A O1OC VRP1L NIA O/2YR PAGE 33 OF 59

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATOF NORMAL SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ INTERVA RO/CSDJ L 343 2-BYV-84-0686 2-FSV-84-49 BYPASS 2 2-47ES62-1/F-4 A I BA HI C O/C Q NIA Q LT N/A O/OC 344 2-FCV-85-0037C SDIVDRNISOL WEST 2 2-47E2820*6/A-6 B 2 CL AO 0 C Q/FS N/A Q VRPIL NIA O/2YR 345 2-FCV-35-0037D SDIVDRN ISOLWEST N 2-47E2820-6/A-5 B 2 GL AO 0 C Q/FS N/A Q I I I VRPIL N/A O/2YR 346 2-FCV-8-0037E SDIV DRN ISOL EAST 2 2-47E2820O-6/A-3 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A O/2YR 347 2-FCV-85-0037F SDIV DRINISOL EAST N 2-47E2820-6/A-3 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A O/2YR 348 2-FCV-2-0039A SCRM INLT (185 TOTAL) 1 2-47E320-2/F-4 B I CL AO C 0 QIFS PV-2 O/16WV 349 2-FCV.S-'0039B SCRM OUTLT (125 TOTAL) 1 2-47ES20-2/F-4 B 3/4 GL AO C 0 Q/FS PV-2 O/166W 350 2-FCV-85-0082 SCRIM DISCII iODR VT WEST N 2-47E2S20-6/11-7 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A O/2YR 351 2-FCV-S5-0082A SCRM DISCIl IIDR VT WEST 2 2-47E2S20-6/t-7 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A O/2YR 352 2-FCV-85-0083 SCRM DISCH HDR VT EAST N z-47E2$2u-6/I-2 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A O/2YR 353 2-FCV-85-0083A SCPRMDISCIIIIDR VT EAST 2 2-47E2320-6/11-3 B 2 GL AO 0 C Q/FS N/A Q VRPIL N/A 0/2YR 354 2-CKV-85-0589 CHlRGWVTR (15 TOTAL) 2 2-47E320-2/F-3 C 1/2 CK SELF C O/C CV N/A CM 355 2-CKV-830597 CLGWTR (15 TOTAL) 1 2-47ES28-2/G-3 C 1/2 CK SELF C C CV N/A CM 356 2-CKV-85-0616 SCRM OUTLT (195 TOTAL) 2 2-47ES20-2T-4 C 3/4 CK SELF C 0 CV N/A CM 357 2-FSV-90-0254A DWLEAKDETISOL 2 2-47E610-90-1/C-2 A I GA S 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 359 2-FSV-90-0254B D*VLEAKDET ISOL 2 2-47E610-90-1/C-2 A I GA S 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 359 2-FSV-90-0255 DIV LEAK DET ISOL 2 2-47E610-90-IJG-2 A I GA S 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 360 2-FSV-90-0257A DW LEAK DET ISOL 2 2-47E610-90-1/11-2 A I GA S 0 /C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 361 2-FSV.90-0257B DWLEAKDETISOL 2 2-47E610-90-1/I1-2 A I GA S 0 0/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 362 2-FCV-94-0501 TIP INDEXER BALL VLV 2 2-47E600-14/B-8 A 3/S BA S C C Q N/A Q LT/VRPI[ N/A O/OC 363 2-FCV-94-0502 TIPINDEXERBALLVLV 2 2-47E600-14/B-3 A 3/8 BA S C C Q N/A Q LT/VRPII N/A O/OC 364 2-FCV-94-0503 TIP NDLEXER BALL VLV 2 2-47E600-14/A-3 A 3/8 BA S C C Q N/A Q I LT/VRPI[ N/A O/OC 365 2-FCV-94-0504 TIP INDEXER BALL VLV 2 2-47E600-14/A-8 A 3/9 BA S C C Q N/A Q I LT/VRPIq N/A O/OC 366 2-FCV-94-0505 TIP INDEXER BALL VLV 2 2-47E600-14/A-S A 3/S BA S C C Q N/A Q 1 LTVRPII N/A 0/OC PAGE 35 OF 59

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BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING .ATEGOR SIZE VLV ACrUAlOI '4ORNL. SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ [NTERVA RO/CSDJ L 218 3-ISV-73-0024 OIPCI EXT COND POT DISCIl 2 3-47E$12-1/D-6 AC 2 SC t1SELF C C CVfLT N/A CM 219 3-FCV-73-0026 PSCTOIIPCIINBDISOL 2 3-47ES12-1/B-6 A 16 GA MO C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 220 3-FCV-73-0027 PSC TO IIPCI OUTBD ISOL 2 3-47E812-C1/C-S A 16 GA MO C O/C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 221 3-FCV-73-0030 IIPCI PMP MIN FLOW 2 3-47ES12-1/D-5 A 4 GL 1MO C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 222 3-FCV-73-0034 IIPCI INJ OUTBD ISOL 2 3-47E812-1/F-5 B 14 GA MO 0 0 Q N/A Q VRPIL N/A 0/2YR 223 3-FCV-73-0035 IIPCI PMP TEST RTN TO CST 2 3-47ESI2-1/F-6 B 10 GL MO C C Q NIA Q VRPIL NIA 0/2YR 224 3-FCV-73-0040 HPCI PMP SUCTION ISOL 2 3-47ES12-1/IH-4 B 14 CA MO 0 C Q N/A Q VRPIL N/A 0/2YR 225 3-FCV-73-0044 IIPCI INJINBD ISOL 2 3-47ESI2-1/F-6 B 14 GA MO C O/C Q N/A Q VRPIL NIA 0/2YR 226 3-FCV-73-0045 ]IPCI TESTABLE CK 1 3-47E812-1/E-6 AC 14 CK AO/SELF C O/C CVfVRPI N/A CM L

LT 227 3-FCT-73-0081 3-FCV-73-3 BYPASS I 3-47E812-1/C-6 A I GL MO C C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 228 3-CKV-73-0505 CST TO ItPCI PMP INLT 2 3-47ES12-1/H.4 C 14 CK SELF C O/C CV N/A CM 229 3-RFV-73-0506 IIPCIPMPSUCTRLF 2 3.47E812-1/G-4 C 1 RV SELF C 0 RV N/A COND 230 3-CKV-73-0517 PSC TO IlPCI PMP INLT 2 3-47E812-1/B-6 C 16 CK SELF C 0 CV N/A CM 231 3-CKVo73-0559 TIPCI PMP MON FLOWV 2 3-47E812-1/D-5 AC 4 CK SELF C O/C CV/LT N/A CM 232 3-RFV-73-0574 HIPCI PMP GLD SEAL COND 2 3-47E812-1/C-4 C 1 RV SELF C 0 RV N/A COND 233 3-CKV-73-0603 IIPCI TRB EXM CIHECK 2 3-47ES12-1/E-7 AC 20 CK SELF C O/C CV/LT N/A CM 234 3-CKV-73-0609 1IPCI TRB EXH DRN CHECK 2 3-47ES12-1/D-6 AC 2 CK SELF C C CV/LT N/A CM 235 3-CKVR73-0625 IRPCI PMP GLD SEAL RTN 2 3-47E$12-1/B,4 C 2 CK SELF C C CV N/A CM 236 3-CKV-73-0633 IIPCI TRB EXII VAC RLF 2 3-47ES12-M/D-7 C 2 CK SELF C O/C CV N/A CM 237 3-CKV-73-0634 IIPCI TRB EXII VAC RLF 2 - 3-47E81l7-/D-7 C 2 CK SELF C O/C CV N/A CMl 238 3-CK%-73-0635 IIPCI TRB EX13VAC RLF 2 3-47FT12-1/F.7 C 2 CK SELF C O/C CV N/A CMI 239 3-CKV.73-0636 IIPCITRBEXIIVACRLF 2 3-47ES12-1/E-7 C 2 CK SELF C O/C CV N/A CM 240 3-RPD-73-0713 OIPCI TR 0EXI RP DISC 2 3-47E812-1/D-4 D 16 RD SELF C 0 VI N/A 0/5YR 241 3-FCV-74-0001 RIIR PMP A PSCSUCTION 2 3-47ES11-I/B-5 B 24 GA MO 0 0/C Q N/A Q IIVRPIL N/A 02YR 242 3-FCV-74-0002 RHR PMP A SD CLG SUCTION 2 3-47E$11-1/C-6 B 20 GA MO C O/C Q N/A Q VRPIL N/A O/2YR 243 3-FCV-74-0007 RIIR LOOPI MIN FLOW 2 3-47ES11-I/E-6 B 4 GA MO 0 O/C Q N/A Q VRPIL N/A 0/2YR 244 3-FCV-74-0012 RIIRPlIPMCPSCSUCTION 2 3-47E811-I/D-5 B 24 GA MO 0 0/C Q N/A Q

_/C VRPIL N/A O/2YR 245 3-FCV-74-0013 RIIR PMP C SD CLG SUCTION 2 3-47ES11-I/D-6 B 20 GA 1MO C O/C Q N/A Q VRPIL N/A O/2YR 246 3-FCV-74-0024 ROIRMP BPSCSUrCTIrON 2 3-47E811-1/B-4 B 24 GA MO 0 O/C Q N/A Q VRPIL N/A O/2YR 247 3-FCV-74-0025 RI!R PMP B SD CLG SUCTION 2 3-47ES I -I/C-4 B 20 GA MO C O/C Q N/A Q I VRPIL N/A O/2YR 248 3-FCV-74-0030 RIIR LOOP 11MIN FLOW 2 3-47E81I-1/E-3 B 4 GA MO 0 O/C Q N/A Q VRPIL N/A 0/2YR 249 3-FCV-74-0035 RIlR PMPDPSCSUCTION 2 3.47E811-I/C-4 B 24 GA MO 0 O/C Q N/A Q VRPIL N/A O/2YR 250 3-FCV-74-0036 RIIR PMP D SD CLG SUCTION 2 3-47E811-1/D-4 B 20 CA MO C O/C Q N/A Q VRPIL N/A O/2YR 251 3.-FCV-74-0047 RIIR SD CLG OUTBD ISOL 1 3-47E811-I/E-5 A 20 CA MO C O/C Q CSDJ-03 CSD LT N/A O/OC VRPIL N/A O/2YR 252 3-FCV-74-0048 RIBR SD CLG INBD ISOL 1 3-47ES01-1/F-S A 20 CA MO C O/C Q CSDJ-03 CSD LT N/A O/OC VRPIL N/A O/2YR 253 3-FCV-74-0052 RIIR LOOP I TIROTILE 2 3-47ES11-./F-7 B 24 AN MO 0 0 Q N/A Q VRPIL NIA 0/2YR 254 3-FCV-74-0053 RBORLOOP I INJ 1 3-47ES1-1.1/F-6 A 24 GA MO C O/C Q N/A Q LT N/A O/OC VRPIL NIA 02YR 255 3-FCV-74-0054 RIIR LP I TESTABLE CK I 3-47ES11-I/F-6 AC 24 CK AO/SELF C O/C CV/LT NIA CM 256 3-FCV-74-0057 RItRLOOPiPSCRTN 2 3-47E811-1/C-8 A 08 CA M*O C O/C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 257 3-FCV-74-0058 ROIR LOOP I PSC SPRAY 2 3-47E811I-1/F-8 A 4 CL MO C 0/C 0 N/A Q LT NIA O/OC 258 3-FCV-74-0059 VRPIL N/A O/2YR RIIRLOOPI PPTEST RTN 2 3-47E811-I/F-8 A 12 GL MO C O/C Q NIA Q LT NIA 0/OC VRPIL N/A 0/2YR PAGE 40 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL "APPENDIXE - VALVE MATRIX

1. VALVEID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATOF NORNAL SAFETY TEST RELIEF SIiSR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ [NTERVA 259 3-FCV-74-0060 RIR LPI CNTMT SPRAY 2 3-47ES11-IIC-6 A 12 GA MO C O/C Q NIA Q OUTBD ISOL LT N/A OOC

___VRPIL N/A 0/ZYR 260 3-FCV-74-0061 RIIR LP I CTN1%MT SPRAY INBD 2 3-47E811-1/G-5 A 12 GA MO C O/C Q N/A Q ISOL LT N/A O/OC I__I VEPIL N/A 0/2YR 261 3-FCV-74-0066 RIIR LOOP 11THROTILE 2 3-47E8lI-M/F-3 B 24 AN MO 0 0 Q N/A Q I F VRPIL N/A O/2YR 262 3-FCV-74-0067 RIIRLOOPIIINJ I 3-47E811-I/F-3 A- 24 GA MO C O/C Q 62PLT N/A N/A Q

O/C VRPIL N/A OR 263 3-FCMV74-0068 RIIR LP 1I TESTABLE CK I 3-47EtI1-1/F-4 AC 24 CK AOiSELF C O/C CV/LT N/A CM 264 3-FCV-74-0071 RHR LOOP I1 PSCRTN 2 3-47E811-I/G-2 A is GA 110 C O/C Q LT N/A N/A Q

O/OC 265 3-FCV-74-0072 LOOPRIIR II PSC SPRAY 2 3-47E811 -I/F-2 A 4 GL MO C O/C Q N/A Q LT N/A O/OC

____VRPIL N/A 0/2YR VRPIL NIA 266 3-FCV-74-0073 RIR LOOP It PMP TEST RTN 2 3-47ES11-1/F-2 A 12 GL MO C O/C Q N/A Q O/2YR OUTBD ISOL LT N/A O/OC VRPIL N/A O/2YR LT N/A 0/OC 268 3-FCV-74-0075 IR LP 11CNTMT SPRAY INBI 2 3-47ES11-I/G-5 A 12 GA MO C O/C Q N/A Q ISOL LT N/A O/OC IIIIVRPIL _N/A 0/2YR 269 3-FCV-74-0096 RIIR PMP A SUCTION XTIE 2 3-47E811-1/C-5 B 14 GA MO C 0 Q N/A Q IVRPIL 1 VRPIL N/A O/2YR N/A Oi2YR 270 3-FCV-74-0097 RIIR PM? CSUCTIONXTIE 2 3-47E811-o/C-5 B 14 GA MO C 0 Q N/A Q 271 3-FCV-74-0100 RIIRHITX A-C XTIE TO U2 B-D 2 3-47E811-I/C-3 B 10 GA MO C 0 Q N/A Q RHR lrrx VRPIL N/A 0_2YR 272 3-RFV-74-0509A RIIR PMP A SUCTION RLF 2 3-47E81I-IfB-6 C I RV SELF C 0 RV N/A COND 273 3-RFV-74-0509B RIIRPNIPBSUCT ION RLF 2 3-47E81I-I/B-4 C I RV SFLF C 0 RV N/A COND 277 274 3-C 3-RFV K V-74-0559B 0509C RIIRPMPCSUCTIO'RLF 2 3-4PESII-I/D-6 C 1 RV SELF C 0 RV NIA COND RTIR PFPN D ISC H CRLF 21 7

275 276 93-CKV-74-0559C 3-RFVM74-0509D 3-C5 V-74-0559A RIIR R PNIP ILE RIIR P MDP A DISCII CK SUCTION E 2 3-47ES1-/D-4 33-A S S11-1

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-7 C

C 20I RV CK SELF SE L F C C 00/C RV CV NIA N /A COND P M*PC DDISC IICK C 20 CK 277 3-CKV-74-0559B RIlR PMP B DISCH CK 2 33-47E811-1/1B-3

-47E811-I/D- C 20 CK S ELF SELF C O/C CV N/A Q C 20 O /C CV CK SELF N /A 0 C O/C CV 291 3- CKV-74-0560 C RIIR PNIP N/A Q 2 B MEN FLOW CKV 92 298 3-CKV-74-0559D 3-C K V-74-0560 C RRI IIR PPOPIP C MIN FLOCK 2 3-47E811-1/F-S 3- TES1 I-I/D- 7 B C

2 CK SELF C O/C QCV N/A Q 299 293 3-CKV-74-0560A R CIRLMPA DM1N F L OMIN FLOW .V CCKK 2 3-47E814-1/-

3-4 7E S 1 - I/ D -37 3 B 3

3 CK CK SELF C O/C O/C CV N/A CQ 3-CKV-74-0560D C 3 CK C 'V NIA RITR Pr D MI TX RLFA S E LF C CM f 294 3-RFV-74-0578A C C 2 3-47E O/C CV RIJR IITX A RLF $11-1fB-2 C N /A CM I 25 73 2 3 RV SELF

-RFV-7" -573 D RI 3 -47E I-I gl 7/ .- C Ol RI IR IX B RLF -C I RV RV NIA 286 3-RFV-7 4-587 A 2 3--47E 811 -1C-2 SELF C CM N R*I[R LP 1DIC IIHRLF C 2 I 0 RV N/A 2 3-47E RV SELF C COND 81I-1/1 - C 0 RV 29 0 3-RFV-7 I RV SELF NIA COND 4-f1659 1RIIR LPIDSDC LI SPLRLF C 0 RV 29 1 3 2 N/A COND

.CRKV-74-0597B R llR 3 -47ES11-11E-7 230 3-RFV-74-057D R IR THERMAL O LFIIND RLF RLF C 1 RV 290 3-RFVT-74-0659 2 3-47E81 SELF RI I t lRSD ALGSLRLF 3 .47E11

- l/ I-I/F-F-5 C AC 12 I / RV RV SELF C C 0 RV N/A N/A COND 2K 3-47ES1 SELF C COND l-I/F- 5 AC 0 / RV /L 200 3-RFV-74-0 1 / -R SELF N/A C MN 572 A cS C 0 / RV /L RlOOiTI RL 2 NIA CON 291 3 -CKV-74-06 04 3-47E81 I-I/F- 7 RIM R LP E IAL EPL CK B 12 I 3 -47ES11-1/11-5 RA M EL 0 290 AC O V N/A 3-FCV-75-0066 21 CK SELF OC OC Q ON 293 CS LOOPIIINFLOW CV /LT NIA 3-FCV-75-0722 CM cSLOOPSIIMPTEST 2 3-47ES14-1/F-5 305 3-FCV-75-0072 B 3 2 3-47ESI4-1/F-4 CA 293 3-1C SCDRNIS-74072 L MO 0 CS LOOP B O/C 306 FI INJ 3-7E~ l1/-_____A 10 Q 32 9 3-FCV 75-0-.

3-FCV-75-0035 2 GL N/A 792 C LOP H INJE CT 3-47E814-1/F-6 MO H Q CS LOOP II ION IK 3-47E81 I-1/ 1I-7 B C __C _ RPL INJ AC 12 12 CE GA Q T N/A N/A 1 3-47ES14-1/G-6 295 SELF MO O OC 0C CV/LT Q O/OYC 029 3-FCV- A IVRPIL 0 VRPIL N/A N/A CM O/2YR TS5-0022 CS LOOP IP NJEST IO 12 CA Q N/A N/A O/2YR 2 3-47ES I4-1/F- 7 MO Q 30 0 3-FCV-75-0 0 23 AB 10 C 7 CS LO OP I GL SELF 0 M]NJ F O 2 3 C OC Q Q~ L N/A E-47 S 1I4- / F- 4 B NIA Q 12 GA M 1% O 0 VRPIL 0 / VRPIL Q N/A N 0/2YR 301 3-FCV-75-0025 IA N/A Q 1 CS LOOP I VRPIL NIA O/2YR 11NJ I 3-47ES 012YR I4-1/G-6 A 12 CA 1% IO O 0 VQPLT N/A NIA O/2YR Q

LT N/A 307 3-FCV-75-0054 O/OC CS LOOP I INJECTION I 3-47ES14-I/G-7 AC 12 304~~~ CLOPI ~ %ITET ~ ~ 2~ ~34E1-F4~ PG 1 OF

.M7000 10G59C CK SELF C VRPIL I N/A O/C CV/LT O/2YR N/A CM

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWING/DRAWING CATEGOR SIZE VLV ACTUATOF NORMAL SAFETY TEST RELIEF 5I/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ NTERVA RO/CSDJ L 308 3-FCV-75-0057 CSDRN PMPAINBDISOL 2 3-47E814-1/B-4 A 3 GL AO 0 C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 309 3-FCV-75-0058 CSDRN PMPAOIITBDISOL 2 3-47ES14-1/B-5 A 3 GL AO 0 C Q N/A Q LT NIA O/OC VRPIL N/A O/2YR 310 3-RFV-75-0507A CSPMP ASUCTIONRLF 2 3-47E814-1/C-4 C I RV SELF C 0 RV N/A COND 311 3-RFV-75-0507B CS PMP B SUCTION RLF 2 3-47E$14-1/C-2 C 1 RV SELF C 0 RV N/A COND 312 3-RFV-75-0507C CSPMPCSUCTIONRLF 2 3-47ES14-1/C-6 C 1 RV SELF C 0 RV N/A COND 313 3-RFV-75-0507D CS PMP D SUCTION RLF 2 3-47E814-1/C-4 C 1 RV SELF C 0 RV N/A COND 314 3-CKV-75-0537A CSPMP ADISCIICK 2 3-47ES14-1/D-4 C 12 CK SELF C 0 CV N/A Q 315 3-CKV-7S-0537B CS PMP B DISCI CK 2 3-47ES14-1/D-3 C 12 CK SELF C 0 CV N/A Q 316 3-CKV-75-0537C CSPMPCDISCIICK 2 3-47ES14--/D-6 C 12 CK SELF C 0 CV N/A 0 317 3-CKV-7S-0537D CS PMP D DISCH CK 2 3.47ES14-1/D-4 C 12 CK SELF C 0 CV N/A 0 318 3-RFV-75-0543A CSLPIDISCH RLF 2 3-47E814-1/F-4 C I RV SELF C 0 RV NIA COND 319 3-RFV-7-0543B CS LP I1 DISCH RLF 2 3-47ES14-1/E-3 C I RV SELF C 0 RV N/A COND 320 3-CKV-75-0570A CSPMPABIILNFLONVCK 2 3-47ES14-I/D-5 C 3 CEK SELF C O/C CV N/A CM 321 3-CKV-75-0570B CS PMP B MIN FLOW CK 2 3-47E814-1/D-2 C 3 CK SELF C O/C CV N/A CM 322 3-CKV-75-0570C CS PMP C MIN FLOWV CK 2 3-47EMI4-1/D-6 C 3 CK SELF C O/C CV N/A CM 323 3-CKV-75-0570D UNPMP D MIN FLOV CK 2 3-47E"14-1/D-4 C 3 CK SELF C O/C CV N/A ChI 324 3-CKV-75-0606 CS LP I KEEP FILL CK 2 3-47F814-1/F-5 AC 2 CK SELF O/C C CV/LT N/A CM 325 3-CKV-75-0607 UNLP I KEEP FILL CE 2 3-47E814-1/F--5 AC 2 CE SELF 0/C C C'V/LT N/A CM 326 3-CKV-75-0609 CS LP II KEEP FILL CK 2 3-47E814-1/ti-4 AC 2 CK SELF OC C CVILT N/A CM 327 3-CKV-75-0610 CS LP II KEEP FILL CK 2 3-47E814-1/t-4 AC 2 CK SELF O/C C CV/LT N/A CM 328 3-FCV-76-0017 DWN2 IAKEUP OUTBD ISOL 2 3-47E860-1/E-S A 2 SF AO /OC C Q N/A Q LT N/A Q/OC VRPIL N/A O/2YR 329 3-FCV-76-0018 DWVN2 MAKEUP INBD ISOL 2 3-47E861-1/D-S A 2 BF AO O/C C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 330 3-FCV-76-0019 FSC N2 MAKEUP INBD ISOL 2 3-47E860-1/D-5 A 2 BF AO O/C C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 331 3-FCV-76-0024 DWN2 PURGE OUTBD ISOL 2 3-47E860-1)/D-4 A 10 BF AO C C Q N/A Q LT N/A O/OC VRPIL NIA 0/2YR 332 3-FSV-76-0049 DWNII2ANALYZER A INBD 2 3-47E3610-76.3/K-2 A 0D GA 5 0 O/C Q N/A Q ISOL LT N/A OOC 333 3-FSV-76-0050 DWI 2 ANALYZER A OUTBD 2 3-47E3610-76-3/K-3 A 00 GA 5 0 O/C Q N/A Q ISOL ____LT N/A 0/OC 334 3-1]V-76-00S1 DVO2ANALYZERAINBD 2 3-47E3610-76-3/T-2 A 00 GA 5 0 0/C Q N/A Q

_34 ISOL A ____ LT N/A Q/OC 335 3-FSV-76-0052 DWO2ANALYZERAOUTBD 2 3-47E3610-76-3/II-3 A 00 GA 5 0 0/C Q NIA 0 ISOL A LT N/A 0/OC 336 3]FSV-76-0053 PSCO2ANALYZERAINBD 2 3-47E3610-76-3/L-2 A 00 GA S C 0/C Q N/A Q 336 ISOL A 2T N/A Q/OC 337 3-FSV-76-0054 PsC O2ANALYZERAOIBD 2 3-47E3610-76-3/N-3 A 1/2 GA S C 0/C Q N/A Q 337 ISOL A LT N/A Q/OC 338 3-FSV-76-0055 ANALYZERAINBD 2 3-47E3610-76-3/J-2 A 1/2 GA S C 0/C Q NSCI2 INA Q 3313SOL A 2T N/A 0/DC 339 3-]SV-76-0056 PSCII2 ANALYZERAOUBD 2 3-47E3610-76-3/J-3 A 1/2 GA S C 0/C Q NIA Q 33931A SOL A 2T N/A Q/OC 340 3-FSV-76.0057 PSC RTN INBD ISOL 2 3-47E3610-76-3/I-2 A 1/2 GA s 0 O/C Q NIA Q LT N/A O/OC 341 3-FSV-76-0058 1SC RTN OUTBD ISOL 2 3-47E3610-76-3/1-3 A 1/2 GA S 0 O/c Q NIA Q

____LT N/A O/OC 342 3-FSV-76-0059 DWHI2 ANALYZER B INBD 2 3-47E3610-76-3/F-2 A 1/2 GA S 0 O/C Q N/A Q ISOL LT N/A O/OC 343 3-FSV-76-0060 DIVII2 ANALYZER B OUTBD 2 3-47E3610-76-3/F-3 A 1/2 GA S 0 O/C Q N/A Q

_______ISOL ____ T N/A O/OC 344 3-FSV-76-0061 DW 02 ANALYZER B INBD 2 3-47E3610-76-3/C-2 A 1/2 GA 5 0 0/C Q N/A Q 344 ISOL B LT N/A Q/OC 345 3-FSV76-0062 D'V 02 ANALYZER B OUTBD 2 3-47E3610-76-3/C-3 A 1/2 GA 5 0 0/C 0 N/A Q 345 ISOL B LT N/A Q/OC 346 3-FSV-76-0063 PSC 02 ANALYZER B INBD 2 3-47E3610-76-3/C-2 A 112 GA S C 0/C Q N/A Q 346 ISOL B LT N/A Q/OC 347 3-FSV-76-0064 PSC 02 ANALYZER B OUTBD 2 3-47E3610-76-3/C-3 A 1/2 GA S C 0/C Q N/A 0 347 ISOL B _____ LT N/A Q/OC 348 3-FSV-76-0065 PSC H2 ANALYZER B INBD 2 347E3610-76-3/E-2 A 1/2 GA S C O/C Q N/A Q ISOL I LT N/A O/OC 349 3-FSV-76-0066 PSC 112ANALYZER B OUTBD 2 3-47E3610-76-3/E-3 A 1/2 GA S C O/C Q N/A Q

_______ISOL ___________ LT N/A O/OC 350 3-FSV-76-0067 PSC R1' INBD ISOL 2 3-47E3610-76-3/D-2 A 1/2 GA 0 0/C 0 N/A N Q LT N/A Q/OC 351 3-FSV-76-0068 PSC RTN OUTIBD ISOL 2 3-47E3610-76-3/D-3 A 1/2 GA 5 0 0/C Q N/A Q LT N/A O/OC 352 3-CKV-76-0653 TIP INDEXER PURGE CK 2 3-47E600-14/B-5 AC 1/4 CK SELF C C CV/LT N/A CM 353 3-FCV-77-0002A DW FLOOR DRN SUMP INBD 2 3-47E852-1/C.4 A 3 GA AO 0 C Q N/A Q ISOL LT N/A 0/OC

____ VRPIL N/A O/2YR PAGE 42 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX VALVE ID FUNCTION ASME DRAWING/DRAWING -ATEGOR SIZE VLV ACTUATOP NORMAL SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ NTERVA RO/CSDJ L 354 3-FCV-77-0002B DW FLOOR DRN SUMP OUTBD 2 3-47E852-1/C-4 A 3 GA AD 0 C Q N/A Q ISOL LT N/A O/OC VRPIL N/A O/2YR 355 3-FCV-77-0015A DWVEQDIRNSUMPMNBDISOL 2 3-47E852-2/D-3 A 3 GA AD 0 C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 356 3-FCV-77-0015B DW EQ DEN SUMP OUTBD 2 3-47E852-2/D-3 A 3 GA AD 0 C Q N/A Q ISOL LT N/A O/OC VRPIL N/A Oi2YR 357 3-FCV-7S-0061 RHR TO FPC SPLY 2 3-47ES55-/1II-6 B 6 GL MO C 0 Q N/A Q VRPIL N/A O/2YR 358 3-FCV-7S-0062 RHR TO FPC SPLY 3 3-47ES55-I/I1-5 B 6 GA H1 C 0 Q N/A Q VRPIL NIA O/2YR 359 3-SITV-78-0524 FUEL POOL DIFF A SIV 3 3-47ES55-1/1"- B 8 GL H LO C Q N/A Q 360 3-CKV-78-0526 FUEL POOLDIFF A SPLY 3 3-47E855-1/G-5 C a CK SELF O/C 0 CV N/A CM 361 3-FSV-54-000SA DWN2 SPLY TEIN A 2 3-47E562-1/E-7 A 2 CA S C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 362 3-FSV-S4-0008B PSCN2SPLYTRNA 2 3-47E362-1/E-5 A 2 GA S C O/C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 363 3-FSV-84-O0OSC PSCN2SSPLYTRNB 2 3-47ES62-1/E-5 A 2 GA S C O/C Q N/A Q LT N/A O/OC VRPIL N/A 012YR 364 3-FSV-84-0008D DWNN2SPLY TRN B 2 3-47Es62-I/E-5 A 2 GA S C O/C Q NIA Q LT N/A O/OC VRPIL N/A O/2YR 365 3-FCV-S4-0019 DW/PSCDISClTODSBGT 2 3-47ES62-I/G-6 A 2 GA AD C C Q N/A Q LT N/A O/OC VRPIL N/A O/2YR 366 3-FCV-84-0020 DWV/PSCDISCIdTOSBGT 2 3-47E562-1/G-6 A 2 GA AD C C Q N/A Q LT N/A 0/DC VRPIL N/A O/2YR 367 3-FSV-94-0048 CADXTIETODW CONTAIR 2 3-47E862-I/E-7 A I GA S C O/C Q/FS N/A Q ISOL O/C VRPIL N/A O/OC C LT N/A 0/DC 368 3-FSV-84-0049 CADXTIETODW CONTAIR 2 3-47ES62-1/E-4 A 1 GA S C O/C Q/FS N/A Q ISOL O/C VRPIL N/A O/OC C LT N/A O/OC 369 3-CKV-"4-0600 DWSPLY CHECK A 2 3-47ES62-1/E-7 AC 2 CK SELF C O/C CV/LT N/A CM 370 3-CKV-84-0601 PSC SPLY CHECK A 2 3-47E862-1/E-6 AC 2 CK SELF C O/C CV/LT N/A CM 371 3-CKV-94-0602 DWVSPLY CHECK B 2 3-47E862-1/E5 AC 2 CK SELF C O/C CV/LT N/A CM 372 3-CKV-84-0603 PSC SPLY CHECK B 2 3-47E962-1/E-5 AC 2 CK SELF C O/C CV/LT N/A CM 373 3-BYV-54-0683 3-FSV-S4-48 BYPASS 2 3-47E862-1/E-7 A I GA H LC C Q N/A Q LT NIA O/OC 374 3-BYV-S4-06S6 3-FSV-94-49 BYPASS 2 3-47E862-1/E-4 A I GA H LC C Q N/A Q LT N/A O/OC 375 3-FCV-SS-0037C SDIVDRNISOL WEST 2 3-47ES20-6/B-6 B 2 GL AD 0 C Q/FS N/A Q VRPIL N/A 0/2YR 376 3-FCV-S5-0037D SDIV DRN ISOL WEST N 3-47E520-6/B-6 B 2 GL AD 0 C Q/FS N/A Q VRPIL N/A 0/2YR 377 3-FCV-S5-0037E SDIV DRN ISOL EAST 2 3*47ES20-6/B-3 B 2 CL AD 0 C Q/FS N/A Q VRPIL N/A 012YR 37S 3-FCV-SS-0037F SDIV DEN ISOL EAST N 3-47ES20-6/B-3 B 2 CL AD 0 C Q/FS N/A Q VRPIL N/A 0/2YR 379 3-FCV-35-0039A SC1RM INLET(195 TOTAL) I 3-47ES20-2/C-S B 1 CL AD C 0 Q/FS PV-2 0/16%V 310 3-FCV-S5-0039B SCRM OUTLET(185 TOTAL) I 3-47ES20-2/r-7 B 3/4 CL AD C 0 Q/FS PV-2 0/16%V 381 3-FCV-SM-082 SCRIE DISCIIIIDRV'W N 3-47ES20-6/G-7 B 2 GL AD 0 C Q/FS N/A Q VRPIL N/A 0/2YR 382 3-FCV-S5-0082A SCRM DISCIIHDRVTW 2 3-47E820-6/G-7 B 2 GL AD 0 C Q/FS N/A Q VRPIL N/A O/2YR 383 3-FCV-SS-D083 SCIM DISCG I1DR VT E N 3-47ES20-6/G-3 B 2 CL AD 0 C Q/FS N/A Q VRPIL N/A 0/2YR 384 3-FCV-85-0083A SCRIDISCIIIIDRVTE 2 3-47ES20-6/G-3 B 2 GL AD 0 C Q/FS N/A Q VRPIL N/A O/2YR 385 3-CKV-35-0599 CIIRGV'rR( 15 TOTAL) 2 3-47ES20-2/C-9 C 1/2 CK SELF C O/C CV N/A CM 386 3-CKV-85-0597 CLGWTR( 85 TOTAL) I 3-47ES20-2/C-9 C 1/2 CK SELF C C CV N/A CM 387 3-CKV-SS-0616 SCRM OUTLT(115 TOTAL) 2 3-47E 20-2/E-7 C 3/4 CK SELF C 0 CV N/A Chi 381 3-FSV-90-0254A DNVLEAK DET ISOL 2 3-47E610-90-1/G-3 A I GA S 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 389 3-FSV-90-0254B DWLEAKDET ISOL 2 3-47E610-90-1/G-3 A 1 GA S O O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 390 3-FSV-90-0255 DW LEAK DET ISOL 2 3-47E610-90-1/G-3 A 1 GA S 0 O/C Q N/A Q LT N/A O/OC VRPIL N/A 0/2YR 391 3-FSV-91-0257A DW LEAK DET ISOL 2 3-47ECI0-90-1/1--3 A 1 GA S 0 O/C Q N/A Q LT N/A 0/DC VRPIL NIA 02YR PAGE 43 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX E - VALVE MATRIX

1. VALVE ID FUNCTION ASME DRAWVINGIDRAWING CATEGOR SIZE VLV ACTUATOF NORMAl !SAFETY TEST RELIEF SI/SR CLASS COORDINATES Y TYPE STATUS STATUS REQD REQUEST/ INTERVA ROICSDJ L 392 3-1SV-90-0257B DWLEAKDETISOL 2 3-47E610-90-1/11-3 A I GA S 0 O/C Q NIA Q LT N/A O/OC VRPIL N/A O/2YR 393 3-FCV-94-0501 TIP INDEXER BALL VLV 2 3-47E600-14IA-S A 3/1 BA S C C Q N/A Q

_TfVRPI. N/A O/OC 394 3-FCV-94-0502 TIP INDEXER BALL VLV 2 3-47E600-14/A-9 A 3/S BA S C C Q N/A Q

_T/VRPIL NIA O/OC 395 3-FCV-94-0503 TIP INDEXER BALL VLV 2 3-47E600-14/A-S A 3/S BA S C C Q NIA Q

_ LTIVRPI N/A O/OC 396 3-FCV-94-0504 TIP INDEXER BALL VLV 2 3-47E600-14/A-3 A 3/1 BA S C C Q N/A Q

_TIVRPI N/A O/OC 397 3-FCV-94-0505 TIP INDEXER BALL VLV 2 3-47E600-14/A-S A 3/S BA S C C Q N/A Q

_TJVRPI1 N/A O/OC PAGE 44 OF 59

CN tn 0

W)

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX F - PASSIVE VALVE LIST

1. D ALE UNTINASME DRAWINCIDRA¶,VING CATEGORY SIZE VALVE NORIMA SAFETY CLASS COORDINATES TYPE L STATUS S~STATUS 76 2-BYV-12-0637 AUX BLR STM SUPPLY TO IIPCI ISV 2 2-47ES15-4/F-2 B 1 GL C C 77 2-BYV.12-0822 AUX BLR STM SUPPLY TO IIPCI ISV 2 0-I7ESI&Sl-l/- B I GL C C 73 2-STIV-24-0706 RCW TO LP IRIER RMCLRS 3 2-47E844-2/E-3 B3 CA C C 79 2-SIIV-24-0729 RCWVTO LP 11RIlM R7. CLRS 3 2-47ES44-2[F-2 B 3 CA C C so 2-FSV-43-0040 PASS CNTMIT ]SOL 2 2-47ES67-31E2 A 1/2 GL C C 31 2-FSV-4M-042 PASS CNTITU ISOL 2 2-47ES67-3/F-2 A 1)2 GL C C 32 2-FS V-43-0050I PASS CNTMT POOL 2 2-47ES67-3/G-2 A 1/2 GL C C 33 2-ES V43.0056 PASS CN~IMT ISOL 2 2-47E367-31C-2 A Ifl CL, C C 34 2-FSV-43-0070 PASS CNTM.T ISOL 1 2-47ES67-3/B-2 A 1/2 GL C C 35 2-ISV-43-0631_ IS SAM*PLE ISV 2 2-47E610-43-I/D-1 B 1/2 GL C C 36 2-ISV-43-0631A MiSSAM*PLE ISV 2 2-47E6I0-43-1/D-I B 1/2 GL C C 37 2-ISV-43-0632 MISSAMPLE ISV 2 2-47E610-43-I/D-1 11 1/2 CL, C C 33 2-SIIV-63-0500 -SLCT&NKISOLATION 2 2-47ES54-1/C-2 B 2-1)2 CA 0 0 39 2-sNiV.63-0502 SLC DEMIN SUPPLY ISOLATION 2 2-47ES54-1[F-2 B I CL C C 90 2-SIIV-63-01506 SLC PU7.IP 2A SUCTION ISOLATION 2 2-47ES54.1/D-5 B 2-1/2 GA 0 0 91 2-SIIV-63-0507 SLC PUMIP 2B SUCTION ISOLATION 2 2-47ES54-1/D-4 B 2-1/2 GA 0 0 92 2-SIIV-63-0509 SLC DEMIN SUPPLY ISOLATION__ 2 2-47ES54.1/D-4 B I CL C C 93 2-SHV-63-0511 SLC DEMIN SUPPLY ISOLATION 2 2-47E3S4-I/D-4 B I CL, C C 94 2-STIV.63-0515 SLC PUMP 2A DISCHIARCE ISOLATION 2 2-47ES54-I/E-5 B 2-112 CA 0 0 95 2-SIIV.63-0517 SL UP2 ICIREIOAIN 2 2-47E354-1/E-4 B 2-1/2 CA 0 0 96 2-S1IV-63-0513 SLC TEST LINE ISOLATION 2 2-47ES54-1/F-6 B 1-1/2 CL C C 97 2-DRV-63-0522 SLC TEST LINE ISOLATION 2 2-47ES54-1/D-6 B I CL C C 93 2-SIIV.63-0524 SLCINJECTION ISOLATION I 2-47ES54-11E-7 B 1-112 CA 0 0 99 2-FCV-"40017 DNVSPLY CTNTMTISOL 2 2-47E2965-12111-7 A 21) BF C C 100 2-FCV-64-0019 IIWSPLY CNTMITISOL 2 2-47E236'-12111.6 A 20 BE C C 101 2-FCV-64-0019 PSCSPLYCNTMITISOL 2 2-47E286&-12/11-6 A 20 BE C C 102 2-FCV6-"0029 D.V LXIICNTIT ISOL 2 2-47E2365-121E-1 A 1s BE C C 103 2-FCV6-"0030 PSC VAC RLY ISOL 2 2-47E2365-121E-4 A 13 BE C C 104 2-FCV-"40032 PSC E)(II OUTBD CNTMIT ISOL 2- 2-47E2805-12/13-3 A 1s BE C C 105 2-FCV-64-0033 PSC ENII INBD CNTMkT]SOL 2 2-47E2965-12/C-3 A 13 BE C C 106 2-SHV-71-0520 RCICPSCSUCTIONISOL 2 2-47ES13-1/C-6 B 2 GL 0 0 107 2-StIV-71-0601 RCIC PSC VACUUMIBKR ISOL 2 2-47ES13-1/C-6 B 3 CA 0 0 105 2-SIIV.73-0534 IIPCI PSC VACUUM HKR IOL 2 2-47FS12.-1/D-6 B 2 CL 0 0 109 2-SIIV-73-0642 IIPCI PSC VACUUM BKR ISOL 2 2.4TF912-1/O-6 B 3 CA 0 0 110 2-SIIV-S3"5-0I CRD BACKFILL SPLY TO R-1L1% ISOL 2 2-47E513-51E.9 Bt 1/2 C.L 0 0 ill 2-SIHV-35-0852 CR0 BACKFILL SPLY TO RVLIS ISOL 2 2-47ES034~-r-7 B 1/2 CL 0 0 112 2-SHIV-35-0854 CR0 BACKFILL SPLY TO RVLIS ISOL 2 2-47E303-5/II-2 B 1/2 CL 0 0 113 2-SHV-95-0956 CR0 BACKFILL SPLY TO RVLIS ISOL 2 2-47ES03-S5/II- B 1/2 CL 0 0 114 3-FCV-01-0057 MISDEN TO COND ISOL 2 3-47ES01-IID-9 B 3 GL 0 0 115 3-FCV-01-0145 STM SEAL BYPASS ISOL 2 3-47ES07-2/C-6 B 4 GL C C 116 3-FCV-01-0154 UXTTOT LIV2 3-47ES01-2/B-5 B 4 CA C C 117 3-FCV-06-0100 TSV6 DEN ISOL 2 3-47ES07-1/C- B I GL C C 113 3-FCV-06-0101 TSV#2DRNISOL 2 3-47ES07-1IF-3 B I CL C C 119 3-FCV.06-0102 TSV #3 DRN ISOL 2 3-47E807-I/E-9 B1 1 CL C C 120 3-FCV-06-0103 TSV#4 DENISOL 2 3-47ES07-1/0- B I CL C C 121 3-FCV-06-0122 REPT 3ASTOP VLVDORN 2 3-47E307-2/C-6 B 1-1/2 GL C C 122 3-FCV-06-0127 RFPT 3B STOP VLV DRN 2 3-47ES07-2/C-4 B 1-1/2 CL C C 123 3-FCV.06-0132 RFPT3CSTOPVLVDRN 2 3-47ES01-2/C-2 B 1-1/2 GL C C 124 3-FCV-06-0153 REPT 3A STOPVLV DEN 2 3-47ES07-2/G-6 B 1-1/2 CL C C 125 3-FCV-06-0155 REPT 3B1STOP VLV DR-N 2 3-47ES07-2/G-3 B 1-1/2 CL, C C 126 3-FCV.06-0157 REPT 3C STOP VLV DRN 2 3-47E307-2/r-I B1 1-1/2 CL, C C 127 3-SIW.IZ-0623 AUX BLR STM SUPPLY TO RCIC ISV 2 3-47E315-5/A-4 B I CL, C C 123 3-BYV-12-0625 AUX BLR STM SUPPLY TO RCIC ISV 2 3-47E315-S/A-4 B I CL, C C 129 3-SIIV-12-0635 AUX BLR SThlISUPPLY TOITIPCI ISV 2 3-47EM1-5/"- B I CL C C 130 3-BYVI-M0637 AUXBELR STMISUPPLYTO IPCIISV 2 3-47EM1-5/- B1 1 CL C C 131 3-FSV-43-0040 PASS CNTNIT ISOL 2 3-47ES67-3/E.2 A 1/2 CL, C C 132 3-ES V-4M-042 PASS CNT1%T [SOL 2 3-47ES67-W/-2 A 1/2 CL, C C 133 3-FSV-43-0050 PASS CNTMT ISOL 2 3-47E$67-3/F-2 A 1/2 CL C C 134 3-ES V43-0056 PASS CNTNIT ISOL 2 3-47ES67-3[F-2 AA 1/ CL C C 135 3-FSV-43-0070 PASS CNTMIT [SOL I 3-47ES67-3111-2 A 1/2 CL C C 136 1 3-ISV-43.0631 I MS SAMPLE ISV 2 3-47E610-43-6111-6 1/2 1 CL C C 137 3-ISV-43-0631A _____

____ 2 3-47E6]0-43-6tC-6 31__ -/ GI C__ _

138 j 3-ISV-43-0632 2_______610-43-6tC-6 B 1 CL, C___ C__

139 1 31-SHV6-63-0500 1 SLC TANK ISOLATION 2 3-47ES54-1/G-2 B1 12-1/2 I CA 1 0 0 140 Pi SUPPLY ISOLATION 2 3-47ES54-1/E-.2 B1 1 CL C___ C___

141 IA SUCTION ISOLATION 22 3-47ES354-1/D-5 B 21/2 CA 0__ 0___

142 1 3-SIIV.63-0S07 SLC PUMP IIB SUCTION ISOLATION 2 3-47ES54.1/D-4 B 1 2-1/2 1 CA 1 0 0 143 1 3-SMV-63-11509 1` SUPPLY ISOLATION 2 3-47ES54-1/D-4 B I I CL I C C 144 1 3-SIIV-6-3-0511 4SUPPLY ISOLATION 2 3-47E54-1/0-4 [ B1 GL C___ C___

145 1 3-%IIV-6M-'SI5 SLC PUMIP I DISCIIARGE ISOLATION I21 3-47ES54-1/E-5 B1 21/2 CA 0___ 0___

SLC PUMP IIB DISCHARGE ISOLATION 2 3.-47E554-1/E-4 E 2-1/2 1 CA 1 0 0

OTATIO)N 2 ýLAW7X54-1/E-g 149 1 3-SIIV-63-01524 150 1 3-FCV-64-0017 I -

PAGE 46 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX F - PASSIVE VALVE LIST FUNCTION ASME DRAIVINGIDRAWING CATEGORY SIZE VALVE NORMtA SAFETY 11 VALVE 1D CLASS COORDINATES TYPE L STATUS STATUS DIVSPLY CNTIT ISOL 2 3-47ES65-'12/B-6 A 20 BF C C 151 3-FCV-64-0013_

rSC SPLY NTNIT ISOL 2 3i-47E865-1211-6 A 20 BF C C 1-52 3-FCV-64-0019 DNVEMICNTMITISOL 2 3-47E865-'12/E-4 A is BF C C 153 3.FCV-"40029 PSCVACRLFISOL 2 3-47E865412D-4 A 18 BF C C 154 3-FCV-64-0030 PSC Dal OUTBD CNTIT ISOL 2 3-47E865-1ZIB3 A 1s BF C C 5155 3.ECV.6-"032 PS0 EM!I INBD CNTM~T ISOL 2 3-47ES65-1I2C-3 A is S-F -C C 156 3-FCV-64-0033 RCIC PSC SUCTION ISOL 2 3.47ES13-1/C-6 B 2 CL 0 0 157 3-SIIV-71-0520 10010 PSC VACUUM BKR ISOL 2 3-47ES13-1IC.6 B 3 CA 0 0 158 3-SHrV-71-0601 159 3-SIIV-73-0534 11PCI PSC VACUUM BKR ISOL 2 47ES12-1/D-6 B 2 GL 0 0 I1PCI PSO VACUUM BKRI]SOL 2 3-47ES12-1[M- B 3 CA 0 0 160 3-SHIV-73-0642 CR0B BCKFILL SPLY TO RYLISISOL 2 3-47E803.5/F-8 B 112 GL 0 0 161 3-S11V-S5-0950 CD BACKFILL SPLY TO RVLIS ISOL 2 3-47E83518;.F-,7 B 12 CL 0 0 162 3-SIIV.8-E+/-!2 ClOD BACKFILL SPLY TO RYLIS ISOL 2 34E8-512 _ 1/2 GL 0 0 163 3-SIFV-3505 CRD BACKFILL SPLY TO RVLIS ISOL1 2 3-47E803-5/11-1 B 1/12 GL 0 0 164 3-SIIV-5-,08S6 PAGE 47 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX G CONDITION MONITORING PROGRAM FOR CHECK VALVES INTRODUCTION The BFN check valve Condition Monitoring (CM) Program is a subsection of the BFN Inservice Test (IST) Program.

This Program is implemented as allowed by the BFN Code of Record for the Third Ten-Year IST Interval, ASME OM Code-1995 through OMa-1996 Addenda, Appendix II.

REQUIREMENTS The OM Code-1995 through OMa-1996 Addenda, Appendix II, establishes the method that is to be used to group, analyze, and monitor check valves under a CM Program. A CM Program is an alternative to the regular requirements for check valve IST specified in Subsection ISTC of the OM Code. In addition to the Appendix II requirements, three additional requirements specified by the NRC have been incorporated in the BFN Condition Monitoring Program.

First, each check valve in the Condition Monitoring Program is bi-directional tested to assess its condition and confirm acceptable valve performance. Second, the time between the initial test or examination and second test or examination, is limited to two fuel cycles or three years (whichever is longer), with additional extensions limited to one fuel cycle per extension The total interval is limited to a maximum of 10 years. An extension or reduction in the interval between tests or examinations would have to be supported by trending and evaluation of performance data.

Third, if the CM program is discontinued for any valve, the provisions of ISTC 4.5.1 through ISTC 4.5.4 must be implemented for the valve.

GROUPING Check valves tested under the CM Program are grouped based on the following:

(1) Intended purpose of CM (e g., to improve performance, or to optimize testing, examination, and preventive maintenance activities)

(2) Analysis of test results and maintenance history (3) Design characteristics, application, and service conditions.

(4) Grouping also considers the sample disassembly examination program grouping details of OM ISTC 4.5.4(c),

which states that valves are to be grouped by similar design, application, and service conditions The grouping also considers maintenance and modification history, potential flow instabilities, required degree of disassembly, the need for tolerance or critical dimension checks, valve manufacturer, design, service, size, materials of construction, and orientation.

ANALYSIS Check valves tested under the CM Program have their test and maintenance history analyzed to establish the basis for specifying inservice testing, examination, and preventive maintenance activities. The analysis includes the following:

(1) Identify any common failure or maintenance patterns (2) Analyze these patterns to determine their significance and to identify potential failure mechanisms (a) determine if certain preventive maintenance activities would mitigate the failure or maintenance patterns (b) determine if certain CM tests such as nonintrusive testing are feasible and effective in monitoring for these failure mechanisms (c) determine if periodic disassembly and examination activities would be effective in monitoring for these failure mechanisms (d) determine if changes in the valve groupings are required PAGE 48 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX G CONDITION MONITORING PROGRAM FOR CHECK VALVES MONITORING (a) Performance Improvement Activities (1) If sufficient information is not available to perform the analysis in the preceding section, or if the analysis is inconclusive, then the following activities will be performed at sufficient intervals over an interim period of the next 5 years or two refueling outages, whichever is less, to determine the cause of the failure or the maintenance patterns:

(a) Identify interim tests (e.g., nonintrusive tests) to assess the performance of the valve or group of valves (b) Identify interim examinations to evaluate potential degradation mechanisms (c) Identify other types of analysis that will be performed to assess check valve condition (d) Identify which of these activities will be performed on each valve in the group (e) Identify the interval of each activity.

(2) Complete or revise the CM Program test plans to document the Check Valve Program Improvement activities and their associated frequencies.

(3) Perform these activities at their associated intervals until:

(a) sufficient information is obtained to permit an adequate evaluation of the specific application, or (b) until the end of the interim period (4) After performance, review the results of each activity to determine if any changes to the program are required. If significant changes to the program are required, the program will be revised prior to the performance of the next activity, and the applicable requirements of the preceding sections must be repeated.

(b) Optimization of CM Activities (1) If sufficient information is available to assess the performance adequacy of the check valve or group of check valves, then the following activities will be performed.

(a) Identify the applicable preventive maintenance activities including their associated intervals that are required to maintain the continued acceptable performance of the check valve or group of check valves (b) Identify the applicable examination activities including their associated intervals that will be used to periodically assess the condition of each check valve or group of check valves (c) Identify the applicable test activities including their associated intervals that will be used to periodically verify the acceptable performance of each check valve or group of check valves (d) Identify which of these activities will be performed on each valve in the group (e) Identify the interval of each activity (2) Revise the test plans to document the optimized CM program activities, and the associated intervals of each activity (3) Perform these activities at their associated intervals (4) After performance, review the results of each activity to determine if any changes to the optimized CM program are required. If significant changes are required, the program will be revised prior to the performance of the next activity, and the applicable requirements of the preceding sections must be repeated.

PAGE 49 OF 59

BROWNS FERRY NUCLEAR PLANT INSERVICE TESTING PROGRAM FOR THE THIRD TEN-YEAR INTERVAL APPENDIX G CONDITION MONITORING PROGRAM FOR CHECK VALVES CORRECTIVE MAINTENANCE If corrective maintenance is performed on a check valve, the analysis used to formulate the basis of the CM activities for that valve and its associated valve group must be reviewed to determine if any changes are required. If significant changes are required, the program must be revised and the applicable requirements of the preceding sections repeated DOCUMENTATION The CM Program will be documented and will include the following information:

(a) list of valves in the program (b) list of the valves in each valve group (c) dates valves were added/deleted to the program and the reason for their inclusion/deletion (d) analysis forming the basis for the program (e) identified failure and maintenance history patterns for each valve (f) CM Program activities and their associated intervals for each valve or valve group.

PAGE 50 OF 59

CHECK VALVES IN THE BFN CONDITION MONITORING PROGRAM UNID CM DESCRIPTION SIZE MANIUFACTURER/MO GROU DEL P

0-CKV-23-601 I RHRSW Keep-Fill 1-1/2" Hancock 5580 0-CKV-23-603 I RHRSW Keep-Fill 1-1/2" Hancock 5580 0-CKV-23-605 I RHRSW Keep-Fill 1-1/2" Hancock 5580 0-CKV-23-607 I RBRSW Keep-Fill 1-1/2" Hancock 5580 0-CKV-50-1017 2 EECW HDR A Chemical Inject 1" Dow Coming 355 O-CKV-50-1018 2 EECW HDR A Chemical Inject 1" Dow Coming 355 0-CKV-50-1019 2 EECW HDR B Chenucal Inject 1" Dow Coming 355 0-CKV-50-1020 2 EECW HDR B Chemical Inject I" Dow Coming 355 0-CKV-50-1021 2 EECW HDR C Chemical Inject I" Dow Cormng 355 0-CKV-50-1022 2 EECW HDR C Chemical Inject 1" Dow Coming 355 0-CKV-50-1023 2 EECW HDR D Chemical Inject 1" Dow Cormng 355 0-CKV-50-1024 2 EECW HDR D Chemical Inject 1" Dow Coming 355 0-CKV-67-507 3 1D DG COr South Hdr Supply 4" Daniel 1601 0-CKV-67-508 3 1D DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-514 3 1C DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-515 3 IC DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-521 3 lB DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-522 3 1B DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-528 3 1A DG COr South Hdr Supply 4" Daniel 1601 0-CKV-67-529 3 1A DG Clr South Hdr Supply 4" Daniel 1601 0-CKV-67-538 3 UI CB Chiller South Hdr Supply 6" Daniel 1601 0-CKV-67-539 3 U1 CB Chiller South Hdr Supply 6" Daniel 1601 0-CKV-67-624 3 1C DG Clr North Hdr Supply 4" Daniel 1601 0-CKV-67-625 3 1C DG Cir North Hdr Supply 4" Daniel 1601 0-CKV-67-627 3 1D DG CIr North Hdr Supply 4" Daniel 1601 0-CKV-67-628 3 1D DG Clr North Hdr Supply 4" Daniel 1601 0-CKV-67-630 3 1B DG COr North Hdr Supply 4" Daniel 1601 0-CKV-67-631 3 1B DG COr North Hdr Supply 4" Daniel 1601 0-CKV-67-634 3 IA DG COr North Hdr Supply 4" Daniel 1601 0-CKV-67-635 3 1A DG COr North Hdr Supply 4" Daniel 1601 0-CKV-67-653 3 U1 CB Chiller North Hdr Supply 6" Daniel 1601 0-CKV-67-656 3 UI CB Chiller North Hdr Supply 6" Daniel 1601 I-CKV-01-742 4 Off Gas Preheater 1A Supply 2" Flowserve W99925484 I-CKV-01-744 4 Off Gas Preheater IB Supply 2" Flowserve W99925484 I-CKV-03-554 5 FDWTR Line A Outbd Isol 24" Atwood Morrill 10994 1-CKV-03-558 5 FDWTR Line A Inbd Isol 24" Atwood Morrill 10994 1-CKV-03-568 5 FDWTR Line B Outbd Isol 24" Atwood Morrill 10994 1-CKV-03-572 5 FDWTR Line B Inbd Isol 24" Atwood Morrill 10994 I-CKV-06-822 6 SJAE 1A Cond Drain Isol 1/2" Hancock 5580 1-CKV-06-826 6 SJAE 1B Cond Drain Isol 1/2" Hancock 5580 1-CKV-10-506 7 MSRV Tail Pipe A Vac Breaker 2-1/2" Powell 3061 1-CKV-10-507 7 MSRV Tail Pipe B Vac Breaker 2-1/2" Powell 3061 1-CKV-10-508 7 MSRV Tail Pipe C Vac Breaker 2-1/2" Powell 3061 I-CKV-10-509 7 MSRV Tail Pipe D Vac Breaker 2-1/2" Powell 3061 I-CKV-10-510 7 MSRV Tail Pipe E Vac Breaker 2-1/2" Powell 3061 1-CKV-10-511 7 MSRV Tail Pipe F Vac Breaker 2-1/2" Powell 3061 I-CKV-10-512 7 MSRV Tail Pipe G Vac Breaker 2-1/2" Powell 3061 I-CKV-10-513 7 MSRV Tail Pipe H Vac Breaker 2-1/2" Powell 3061 1-CKV-10-514 7 MSRV Tail Pipe J Vac Breaker 2-1/2" Powell 3061 1-CKV-10-515 7 MSRV Tail Pipe K Vac Breaker 2-1/2" Powell 3061 1-CKV-10-516 7 MSRV Tail Pipe L Vac Breaker 2-1/2" Powell 3061 1-CKV-10-519 8 MSRV Tail Pipe M Vac Breaker 2-1/2" Atwood Morrill 13894-41 1-CKV-10-520 8 MSRV Tad Pipe N Vac Breaker 2-1/2" Atwood Momll 13894-41 1-CKV-10-521 9 MSRV Tail Pipe A Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-522 9 MSRV Tail Pipe B Vac Breaker 10" GPE Controls LF240-435 PAGE 51 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

1-CKV-10-523 9 MSRV Tail Pipe C Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-524 9 MSRV Tail Pipe D Vac Breaker 10" GPE Controls LF240-435 I-CKV-10-525 9 MSRV Tail Pipe E Vac Breaker 10" GPE Controls LF240-435 I-CKV-1 0-526 9 MSRV Tail Pipe F Vac Breaker 10" GPE Controls LF240-435 I-CKV-10-527 9 MSRV Tail Pipe G Vac Breaker 10" GPE Controls LF240-435 I-CKV-10-528 9 MSRV Tail Pipe H Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-529 9 MSRV Tail Pipe J Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-530 9 MSRV Tail Pipe K Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-531 9 MSRV Tail Pipe L Vac Breaker 10" GPE Controls LF240-435 I-CKV-10-532 9 MSRV Tail Pipe M Vac Breaker 10" GPE Controls LF240-435 1-CKV-10-533 9 MSRV Tail Pipe N Vac Breaker 10" GPE Controls LF240-435 1-CKV-23-510 10 RHRSW Supply to RHR HTX IA 16" Atwood Momll 11601-02 1-CKV-23-530 10 RHRSW Supply to RHR HTX 1B 16" Atwood Momll 11601-02 1-CKV-23-550 10 RHRSW Supply to RHR HTX IC 16" Atwood Momll 11601-02 1-CKV-23-569 10 RHRSW Supply to RHR HTX 1D 16" Atwood Momll 11601-02 1-CKV-24-886 11 RCW Supply to Panel 25-340 1" Powel12341SWE 1-CKV-24-891 11 RCW Supply to Panel 25-340 1" Powel12341SWE 1-CKV-32-336 12 DCA Containment Isolation 1" Hancock 5580 1-CKV-32-915 12 DCA Containment Isolation 1" Hancock 5580 1-CKV-32-2516 13 DCA Containment Isolation 3/4" Kerotest MC-009 1-CKV-32-2521 13 DCA Containment Isolation 3/4" Kerotest MC-009 I-CKV-63-514 14 SLC Pump 2A Discharge 1-1/2" Velan W7234B13MS 1-CKV-63-516 14 SLC Pump 2B Discharge 1-1/2" Velan W7234B13MS I-CKV-63-525 14 SLC Inject Line Containment Isol 1-1/2" Velan W7234B1 3MS I-CKV-63-526 14 SLC Inject Line Containment Isol 1-1/2" Velan W7234B 13MS I-CKV-64-800 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 I-CKV-64-801 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 1-CKV-67-541 3 Loop I Core Spray Rm Clr Supply 2-1/2" Daniel 1601 I-CKV-67-542 3 Loop I Core Spray Rm Clr Supply 2-1/2" Daniel 1601 I-CKV-67-558 3 Loop I RHR Rm Clr South Hdr Sply 3" Daniel 1601 1-CKV-67-559 3 Loop I RHR Rm Clr South Hdr Sply 1 3" Daniel 1601 1-CKV-67-584 3 Loop II Core Spray PRm Clr Supply 2-1/2" Daniel 1601 1-CKV-67-585 3 Loop II Core Spray Rm Clr Supply 2-1/2" Daniel 1601 1-CKV-67-600 3 Loop II RHR Rm Clr South Hdr Sply 3" Daniel 1601 1-CKV-67-601 3 Loop 11 RHR Rm Clr South Hdr Sply 3" Daniel 1601 1-CKV-67-638 3 Loop I RHR Rm Clr North Hdr Sply 3" Darnel 1601 I-CKV-67-639 3 Loop I RHR Rm Clr North Hdr Sply 3" Daniel 1601 1-CKV-67-648 3 Loop I Core Spray Rm Cir Supply 2-1/2" Daniel 1601 1-CKV-67-649 3 Loop I Core Spray Rm Clr Supply 2-1/2" Daniel 1601 I-CKV-67-656 3 Loop II Core Spray Rm Clr Supply 2-1/2" Daniel 1601 I-CKV-67-657 3 Loop IHCore Spray Rm Clr Supply 2-1/2" Daniel 1601 I-CKV-67-659 3 Loop II RHR Rm Clr North Hdr Sply 3" Daniel 1601 1-CKV-67-660 3 Loop 11 RHR Rm Clr North Hdr Sply 3" Daniel 1601 I-CKV-67-787 16 UI Emergency Chiller Supply 4" Crane 123A-UX I-CKV-67-789 16 UI Emergency Chiller Supply 4" Crane 123A-UX I-CKV-67-838 3 Pnl 25-340 Supply I" Daniel 1601 1-CKV-67-839 3 Pnl 25-340 Supply 1" Daniel 1601 1-CKV-67-843 3 Pnl 25-341 Supply 1" Daniel 1601 1-CKV-67-844 3 Pnl 25-341 Supply 1i" Daniel 1601 I-CKV-68-508 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 1-CKV-68-523 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 1-CKV-68-550 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 I-CKV-68-555 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 I-CKV-69-630 18 RWCU to RPV Return 4" Anchor Darling W9624799B 1-CKV-70-506 19 RBCCW Supply Containment Isol 8" Velan B150114B2TS I-SHV-71-14 20 RCIC Turbine Exh Stop CKV 8" Walworth 5312WE I-SHV-71-32 21 RCIC Turbine Exh Drain Stop CKV 2" Velan W8-084B-2TY PAGE 52 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

1-FCV-71-40 22 RCIC Testable CKV 6" Rockwell 970 JMMNY 1-CKV-71-499 23 RCIC Suct Supply from CST 6" Velan B140116B2TS 1-CKV-71-508 24 RCIC Suct Supply from Torus 6" Powell 1561 1-CKV-71-547 25 RCIC Pump Mm Flow 2" Hancock 5580 1-CKV-71-580 26 RCIC Turbine Exh 10" Anchor Darling W9524568 1-CKV-71-589 25 RCIC Condensate Pump Discharge 2" Hancock 5580 1-CKV-71-592 25 RCIC Turbine Exh Drain 2" Hancock 5580 I-CKV-71-597 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-71-598 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-71-599 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-71-600 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 1-ISV-73-23 28 HPCI Turbine Exh Stop CKV 16" Walworth 5312WE 1-ISV-73-24 21 HPCI Turbine Exh Dram Stop CKV 2" Velan W8-084B-2TY 1-FCV-73-45 22 HPCI Testable CKV 14" Rockwell 970 JMMNY 1-CKV-73-505 29 HPCI Suct Supply from CST 14" Chapman 151AWE 1-CKV-73-517 30 HPCI Suct Supply from Torus 16" Powell 1561 1-CKV-73-559 31 HPCI Pump Min Flow 4" Powell 9061 1-CKV-73-603 26 HPCI Turbine Exh 16" Anchor Darling W9524569 1-CKV-73-609 32 HPCI Turbine Exh Drain 2" Rockwell 838Y 1-CKV-73-625 25 IPCI Gland Seal Return 2" Hancock 5580 1-CKV-73-633 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-73-634 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-73-635 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-73-636 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 1-CKV-74-54 33 RHR Loop I Testable CKV 24" Atwood Morrill 20800-H 1-CKV-74-68 33 RHR Loop II Testable CKV 24" Atwood Morrill 20800-H 1-CKV-74-560A 34 RHR Pump 2A Min Flow 3" Powell 3160A 1-CKV-74-560B 34 RHR Pump 2B Mmn Flow 3" Powell 3160A 1-CKV-74-560C 34 RHR Pump 2C Min Flow 3" Powell 3160A I-CKV-74-560D 34 RHR Pump 2D Min Flow 3" Powell 3160A I-CKV-74-661 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-13AA I-CKV-74-662 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-1 3AA 1-CKV-74-792 36 Loop I RHR Keep Fill 2" Hancock 5580 1-CKV-74-802 36 Loop II RHR Keep Fill 2" Hancock 5580 1-CKV-74-803 36 Loop 1IRHR Keep Fill 2" Hancock 5580 1-CKV-74-804 36 Loop I RHR Keep Fill 2" Hancock 5580 1-CKV-75-26 37 CS Loop I Injection CKV 12" Rockwell 770(CF8M) 1-CKV-75-54 37 CS Loop II Injection CKV 12" Rockwell 770(CF8M)

I-CKV-75-570A 38 CS Pump 2A Min Flow 3" Velan B101114B2T I-CKV-75-570B 38 CS Pump 2B Mm Flow 3" Velan B10 1114B2T 1-CKV-75-570C 38 CS Pump 2C Min Flow 3" Velan B10 11 14B2T I-CKV-75-570D 38 CS Pump 2D Mm Flow 3" Velan B101 114B2T 1-CKV-75-606 36 Loop I CS Keep Fill 2" Hancock 5580 1-CKV-75-607 36 Loop I CS Keep Fill 2" Hancock 5580 I-CKV-75-609 36 Loop 11 CS Keep Fill 2" Hancock 5580 1-CKV-75-610 36 Loop II CS Keep Fill 2" Hancock 5580 1-CKV-76-653 39 TIP Indexer Purge Supply 1/4" Teledyne 483-1 1-CKV-78-526 40 U1 Fuel Pool Cooling Supply 8" Daniel 1601 I-CKV-84-600 41 CAD Drywell Supply A 2" Kerotest TVD9911 S(2)

I-CKV-84-601 41 CAD Torus Supply A 2" Kerotest TVD9911 S(2)

I-CKV-84-602 41 CAD Dry~vell Supply B 2" Kerotest TVD991 S(2) 1-CKV-84-603 41 CAD Torus Supply B 2" Kerotest TVD9911S(2)

PAGE 53 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

1-CKV-85-589 42 CRD Charging Water (189 valves) 1/2" General Electric 117C3743P006 1-CKV-85-597 42 CRD Cooling Water (189 valves) 1/2" General Electric 117C3743P006 1-CKV-85-616 42 CRD Scram Outlet (189 valves) 1/2" General Electric 117C3743P006 2-CKV-01-742 4 Off Gas Preheater 2A Supply 2" Flowserve W99925484 2-CKV-01-744 4 Off Gas Preheater 2B Supply 2" Flowserve W99925484 2-CKV-03-554 5 FDWTR Line A Outbd Isol 24" Atwood Morrill 10994 2-CKV-03-558 5 FDWTR Line A Inbd Isol 24" Atwood Morrill 10994 2-CKV-03-568 5 FDWTR Line B Outbd Isol 24" Atwood Morrill 10994 2-CKV-03-572 5 FDWTR Line B Inbd Isol 24" Atwood Momll 10994 2-CKV-06-822 6 SJAE 2A Cond Drain Isol 1/2" Hancock 5580 2-CKV-06-826 6 SJAE 2B Cond Drain Isol 1/2" Hancock 5580 2-CKV-10-506 7 MSRV Tail Pipe A Vac Breaker 2-1/2" Powell 3061 2-CKV-10-507 7 MSRV Tail Pipe B Vac Breaker 2-1/2" Powell 3061 2-CKV-10-508 7 MSRV Tail Pipe C Vac Breaker 2-1/2" Powell 3061 2-CKV-10-509 7 MSRV Tail Pipe D Vac Breaker 2-1/2" Powell 3061 2-CKV-10-510 7 MSRV Tail Pipe E Vac Breaker 2-1/2" Powell 3061 2-CKV-10-511 7 MSRV Tail Pipe F Vac Breaker 2-1/2" Powell 3061 2-CKV-10-512 7 MSRV Tail Pipe G Vac Breaker 2-1/2" Powel13061 2-CKV-10-513 7 MSRV Tail Pipe H Vac Breaker 2-1/2" Powell 3061 2-CKV-10-514 7 MSRV Tail Pipe J Vac Breaker 2-1/2" Powell 3061 2-CKV-10-515 7 MSRV Tail Pipe K Vac Breaker 2-1/2" Powell 3061 2-CKV-10-516 7 MSRV Tail Pipe L Vac Breaker 2-1/2" Powell 3061 2-CKV-10-519 7 MSRV Tail Pipe M Vac Breaker 2-1/2" Powell 3061 2-CKV-10-520 7 MSRV Tail Pipe N Vac Breaker 2-1/2" Powell 3061 2-CKV-I 0-521 9 MSRV Tail Pipe A Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-522 9 MSRV Tail Pipe B Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-523 9 MSRV Tail Pipe C Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-524 9 MSRV Tail Pipe D Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-525 9 MSRV Tail Pipe E Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-526 9 MSRV Tail Pipe F Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-527 9 MSRV Tail Pipe G Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-528 9 MSRV Tail Pipe H Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-529 9 MSRV Tail Pipe J Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-530 9 MSRV Tail Pipe K Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-531 9 MSRV Tail Pipe L Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-532 9 MSRV Tail Pipe M Vac Breaker 10" GPE Controls LF240-435 2-CKV-10-533 9 MSRV Tail Pipe N Vac Breaker 10" GPE Controls LF240-435 2-CKV-23-579 10 RHRSW Supply to RHR HTX 2A 16" Atwood Morrill 11601-02 2-CKV-23-580 10 RHRSW Supply to RHR HTX 2B 16" Atwood Momll 11601-02 2-CKV-23-581 10 RHRSW Supply to RHR HTX 2C 16" Atwood Momll 11601-02 2-CKV-23-582 10 RHRSW Supply to RHR HTX 2D 16" Atwood Morrill 11601-02 2-CKV-24-886 11 RCW Supply to Panel 25-340 1" Powel12341SWE 2-CKV-24-891 II RCW Supply to Panel 25-340 1" Powell 2341SWE 2-CKV-32-336 12 DCA Containment Isolation 1" Hancock 5580 2-CKV-32-2163 12 DCA Containment Isolation 1" Hancock 5580 2-CKV-32-2516 13 DCA Containment Isolation 3/4" Kerotest MC-009 2-CKV-32-2521 13 DCA Containment Isolation 3/4" Kerotest MC-009 2-CKV-63-514 14 SLC Pump 2A Discharge 1-1/2" VelanW7234B13MS 2-CKV-63-516 14 SLC Pump 2B Discharge 1-1/2" Velan W7234B13MS 2-CKV-63-525 14 SLC Injection Line Containment Isol 1-1/2" Velan W7234BI 3MS 2-CKV-63-526 14 SLC Injection Line Containment Isol 1-1/2" Velan W7234B 13MS 2-CKV-64-800 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 2-CKV-64-801 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 2-CKV-67-541 3 Loop I Core Spray Pin Clr Supply 2-1/2" Daniel 1601 2-CKV-67-542 3 Loop I Core Spray Rm Clr Supply 2-1/2" Daniel 1601 PAGE 54 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

e 2-CKV-67-558 3 Loop I RHR Rm Clr Supply 3" Daniel 1601 2-CKV-67-559 3 Loop I RHR Rm Clr Supply 3" Darnel 1601 2-CKV-67-584 3 Loop II Core Spray Rm Clr Supply 2-1/2" Daniel 1601 2-CKV-67-585 3 Loop If Core Spray Rm Clr Supply 2-1/2" Daniel 1601 2-CKV-67-600 3 Loop H RHR Rm Clr Supply 3" Darnel 1601 2-CKV-67-601 3 Loop II RHR Rm Clr Supply 3" Daniel 1601 2-CKV-67-638 3 Loop I RHR Rm Cir Supply 3" Daniel 1601 2-CKV-67-639 3 Loop I RHR Rm Clr Supply 3" Daniel 1601 2-CKV-67-648 3 Loop I Core Spray Rm Cir Supply 2-1/2" Daniel 1601 2-CKV-67-649 3 Loop I Core Spray Rm Cir Supply 2-1/2" Daniel 1601 2-CKV-67-656 3 Loop II Core Spray Rm Clr Supply 2-1/2" Daniel 1601 2-CKV-67-657 3 Loop HICore Spray Rm Clr Supply 2-1/2" Daniel 1601 2-CKV-67-659 3 Loop II RHR Rm Clr Supply 3" Daniel 1601 2-CKV-67-660 3 Loop II RHR Rm Clr Supply 3" Daniel 1601 2-CKV-67-838 3 Pn 25-340 Supply 1" Daniel 1601 2-CKV-67-839 3 PnI25-340 Supply I" Daniel 1601 2-CKV-67-843 3 Prn 25-341 Supply 1" Daniel 1601 2-CKV-67-844 3 Pn 25-341 Supply V" Daniel 1601 2-CKV-68-508 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 2-CKV-68-523 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 2-CKV-68-550 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 2-CKV-68-555 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 2-CKV-69-630 18 RWCU to RPV Return 4" Anchor Darling W9624799B 2-CKV-70-506 19 RBCCW Supply Containment Isol 8" Velan B150114B2TS 2-SHV-71-14 20 RCIC Turbine Exh Stop CKV 8" Walworth 5312WE 2-SHV-71-32 21 RCIC Turbine Exh Drain Stop CKV 2" Velan W8-084B-2TY 2-FCV-71-40 43 RCIC Testable CKV 6" Atwood Morrill 15184-02 2-CKV-71-499 23 RCIC Suct Supply from CST 6" Velan B140116B2TS 2-CKV-71-508 24 RCIC Suct Supply from Torus 6" Powell 1561 2-CKV-71-547 25 RCIC Pump Mn Flow 2" Hancock 5580 2-CKV-71-580 26 RCIC Turbine Exh 10" Anchor Darling W9524568 2-CKV-71-589 25 RCIC Condensate Pump Discharge 2" Hancock 5580 2-CKV-71-592 25 RCIC Turbine Exh Drain 2" Hancock 5580 2-CKV-71-597 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-71-598 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-71-599 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-71-600 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 2-ISV-73-23 28 HPCI Turbine Exh Stop CKV 16" Walworth 5312WE 2-ISV-73-24 21 HPCI Turbine Exh Drain Stop CKV 2" Velan W8-084B-2TY 2-FCV-73-45 44 HPCI Testable CKV 14" Atwood Morrill 15184-01 2-CKV-73-505 29 HPCI Suct Supply from CST 14" Chapman 151AWE 2-CKV-73-517 30 HPCI Suct Supply from Torus 16" Powell 1561 2-CKV-73-559 31 HPCI Pump Min Flow 4" Powell 9061 2-CKV-73-603 26 HPCI Turbine Exh 16" Anchor Darling W9524569 2-CKV-73-609 32 HPCI Turbine Exh Drain 2" Rockwell 838Y 2-CKV-73-625 25 HPCI Gland Seal Return 2" Hancock 5580 2-CKV-73-633 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-73-634 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-73-635 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-73-636 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 2-CKV-74-54 33 RHR Loop I Testable CKV 24" Atwood Morrill 20800-H 2-CKV-74-68 33 RHR Loop II Testable CKV 24" Atwood Morrill 20800-H 2-CKV-74-560A 34 RHR Pump 2A Mn Flow 3" Powell 3160A PAGE 55 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

2-CKV-74-560B 34 RHR Pump 2B Min Flow 3" Powell 3160A 2-CKV-74-560C 34 RHR Pump 2C Mm Flow 3" Powell 3160A 2-CKV-74-560D 34 RHR Pump 2D Min Flow 3" Powell 3160A 2-CKV-74-661 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-13AA 2-CKV-74-662 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-13AA 2-CKV-74-792 36 Loop I RHR Keep Fill 2" Hancock 5580 2-CKV-74-802 36 Loop 11 RHR Keep Fill 2" Hancock 5580 2-CKV-74-803 36 Loop HRHR Keep Fill 2" Hancock 5580 2-CKV-74-804 36 Loop I RHR Keep Fill 2" Hancock 5580 2-CKV-75-26 37 CS Loop I Injection CKV 12" Rock-well 770(CF8M) 2-CKV-75-54 37 CS Loop II Injection CKV 12" Rockwell 770(CF8M) 2-CKV-75-570A 38 CS Pump 2A Min Flow 3" Velan B 101114B2T 2-CKV-75-570B 38 CS Pump 2B Min Flow 3" Velan B10 111 4B2T 2-CKV-75-570C 38 CS Pump 2C Min Flow 3" Velan B10 11 14B2T 2-CKV-75-570D 38 CS Pump 2D Mm Flow 3" Velan Bl 01114B2T 2-CKV-75-606 36 Loop I CS Keep Fill 2" Hancock 5580 2-CKV-75-607 36 Loop I CS Keep Fill 2" Hancock 5580 2-CKV-75-609 36 Loop II CS Keep Fill 2" Hancock 5580 2-CKV-75-610 36 Loop II CS Keep Fill 2" Hancock 5580 2-CKV-76-653 39 TIP Indexer Purge Supply 1/4" Teledyne 483-1 2-CKV-78-526 40 U2 Fuel Pool Cooling Supply 8" Daniel 1601 2-CKV-84-600 41 CAD Drywell Supply A 2" Kerotest TVD9911 S(2) 2-CKV-84-601 41 CAD Torus Supply A 2" Kerotest TVD9911S(2) 2-CKV-84-602 41 CAD Drywyell Supply B 2" Kerotest TVD9911S(2) 2-CKV-84-603 41 CAD Torus Supply B 2" Kerotest TVD991 IS(2) 2-CKV-85-589 42 CRD Charging Water (189 valves) 1/2" General Electric 117C3743P006 2-CKV-85-597 42 CRD Cooling Water (189 valves) 1/2" General Electric 117C3743P006 2-CKV-85-616 42 CRD Scram Outlet (189 valves) 1/2" General Electric 117C3743P006 3-CKV-01-742 4 Off Gas Preheater 3A Supply 2" Flowserve W99925484 3-CKV-01-744 4 Off Gas Preheater 3B Supply 2" Flowserve W99925484 3-CKV-03-554 5 FDWTR Line A Outbd Isol 24" Atwood Morrill 10994 3-CKV-03-558 5 FDWTR Line A Inbd Isol 24" Atwood Morrill 10994 3-CKV-03-568 5 FDWTR Line B Outbd Isol 24" Atwood Morrill 10994 3-CKV-03-572 5 FDWTR Line B Inbd Isol 24" Atwood Morrill 10994 3-CKV-06-822 6 SJAE 3A Cond Drain Isol 1/2" Hancock 5580 3-CKV-06-826 6 SJAE 3B Cond Dram Isol 1/2" Hancock 5580 3-CKV-10-506 7 MSRV Tail Pipe A Vac Breaker 2-1/2" Powell 3061 3-CKV-10-507 7 MSRV Tail Pipe B Vac Breaker 2-1/2" Powell 3061 3-CKV-10-508 7 MSRV Tail Pipe C Vac Breaker 2-1/2" Powell 3061 3-CKV-10-509 7 MSRV Tail Pipe D Vac Breaker 2-1/2" Powell 3061 3-CKV-10-510 7 MSRV Tail Pipe E Vac Breaker 2-1/2" Powell 3061 3-CKV-10-511 7 MSRV Tail Pipe F Vac Breaker 2-1/2" Powell 3061 3-CKV-10-512 7 MSRV Tail Pipe G Vac Breaker 2-1/2" Powell 3061 3-CKV-I 0-513 7 MSRV Tail Pipe H Vac Breaker 2-1/2" Powell 3061 3-CKV-10-514 7 MSRV Tail Pipe J Vac Breaker 2-1/2" Powell 3061 3-CKV-10-515 7 MSRV Tail Pipe K Vac Breaker 2-1/2" Powell 3061 3-CKV-10-516 7 MSRV Tail Pipe L Vac Breaker 2-1/2" Powell 3061 3-CKV-I 0-519 7 MSRV Tail Pipe M Vac Breaker 2-1/2" Powell 3061 3-CKV-I 0-520 7 MSRV Tail Pipe N Vac Breaker 2-1/2" Powell 3061 3-CKV-10-521 9 MSRV Tail Pipe A Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-522 9 MSRV Tail Pipe B Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-523 9 MSRV Tail Pipe C Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-524 9 MSRV Tail Pipe D Vac Breaker 10" GPE Controls LF240-435 PAGE 56 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

3-CKV-10-525 9 MSRV Tail Pipe E Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-526 9 MSRV Tail Pipe F Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-527 9 MSRV Tail Pipe G Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-528 9 MSRV Tail Pipe H Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-529 9 MSRV Tail Pipe J Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-530 9 MSRV Tail Pipe K Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-531 9 MSRV Tail Pipe L Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-532 9 MSRV Tail Pipe M Vac Breaker 10" GPE Controls LF240-435 3-CKV-10-533 9 MSRV Tail Pipe N Vac Breaker 10" GPE Controls LF240-435 3-CKV-23-579 10 RHRSW Supply to RHR HTX 2A 16" Atwood Momll 11601-02 3-CKV-23-580 10 RHRSW Supply to RHR HTX 2B 16" Atwood Morrill 11601-02 3-CKV-23-581 10 RHRSW Supply to RHR HTX 2C 16" Atwood Morrill 11601-02 3-CKV-23-582 10 RHRSW Supply to RHR HTX 2D 16" Atwood Morrill 11601-02 3-CKV-32-336 12 DCA Containment Isolation 1" Hancock 5580 3-CKV-32-2163 12 DCA Containment Isolation 1" Hancock 5580 3-CKV-32-2516 13 DCA Containment Isolation 3/4" Kerotest MC-009 3-CKV-32-2521 13 DCA Containment Isolation 3/4" Kerotest MC-009 3-CKV-63-514 14 SLC Pump 3A Discharge 1-1/2" VelanW7234B13MS 3-CKV-63-516 14 SLC Pump 3B Discharge 1-1/2" VelanW7234Bl3MS 3-CKV-63-525 14 SLC Inject Line Containment Isol 1-1/2" Velan W7234B 13MS 3-CKV-63-526 14 SLC Inject Line Containment Isol 1-1/2" Velan W7234B 13MS 3-CKV-64-800 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 3-CKV-64-801 15 PSC to Reactor Bldg Vac Breaker 20" GPE Controls LF240125 3-CKV-67-693 3 3A DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-694 3 3A DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-695 3 3A DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-696 3 3A DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-703 3 3B DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-704 3 3B DG Cir North Hdr Supply 4" Daniel 1601 3-CKV-67-705 3 3B DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-706 3 3B DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-713 3 3C DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-714 3 3C DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-715 3 3C DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-716 3 3C DG Clr South Hdr Supply 4" Darnel 1601 3-CKV-67-723 3 3D DG Clr North Hdr Supply 4" Daniel 1601 3-CKV-67-724 3 3D DG Cir North Hdr Supply 4" Daniel 1601 3-CKV-67-725 3 3D DG Cir South Hdr Supply 4" Daniel 1601 3-CKV-67-726 3 3D DG Clr South Hdr Supply 4" Daniel 1601 3-CKV-67-735 3 U3 SDBR Chiller North EECW Sply 2" Daniel 1601 3-CKV-67-736 3 U3 SDBR Chiller North EECW Sply 2" Daniel 1601 3-CKV-67-737 3 U3 SDBR Chiller South EECW Sply 2" Daniel 1601 3-CKV-67-738 3 U3 SDBR Chiller South EECW Sply 2" Daniel 1601 3-CKV-67-838 3 Pnl25-340 Supply 1" Daniel 1601 3-CKV-67-839 3 Pnl 25-340 Supply 1" Daniel 1601 3-CKV-67-841 45 U3 CB Chiller North EECW Supply 6" Anchor Darling EZ517-1-1 3-CKV-67-842 45 U3 CB Chiller North EECW Supply 6" Anchor Darling EZ517-1-1 3-CKV-67-843 3 Pnl 25-341 Supply 1" Daniel 1601 3-CKV-67-844 3 Pn1 25-341 Supply 1" Daniel 1601 3-CKV-67-845 45 U3 CB Chiller South EECW Supply 6" Anchor Darling EZ517-1-1 3-CKV-67-846 45 U3 CB Chiller South EECW Supply 6" Anchor Darling EZ517-1-1 3-CKV-67-5002 46 U3 EBR Chiller South EECW Supply 2" Anchor Darling 1878 3-CKV-67-5021 46 U3 EBR Chiller North EECW Supply 2" Anchor Darling 1878 3-CKV-67-5022 46 U3 EBR Chiller South EECW Supply 2" Anchor Darling 1878 3-CKV-67-5023 46 U3 EBR Chiller North EECW Supply 2" Anchor Darling 1878 3-CKV-68-508 17 Recire Pump Seal Isol 3/4" Anchor Darling W821722 3-CKV-68-523 17 Recire Pump Seal Isol 3/4" Anchor Darling W821722 3-CKV-68-550 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 PAGE 57 OF 59

UNID CM DESCRIPTION SIZE MANUFACTURER/MO GROU DEL P

3-CKV-68-555 17 Recirc Pump Seal Isol 3/4" Anchor Darling W821722 3-CKV-69-628 18 RWCU to RPV Return 4" Anchor Darling W9624799B 3-CKV-69-629 18 RWCU to RPV Return 4" Anchor Darling W9624799B 3-CKV-70-506 19 RBCCW Supply Containment Isol 8" Velan B150114B2TS 3-SHV-71-14 20 RCIC Turbine Exh Stop CKV 8" Walworth 5312WE 3-SHV-71-32 21 RCIC Turbine Exh Drain Stop CKV 2" Velan W8-084B-2TY 3-FCV-71-40 43 RCIC Testable CKV 6" Atwood Morrill 15184-02 3-CKV-71-499 23 RCIC Suct Supply from CST 6" Velan B140116B2TS 3-CKV-71-508 24 RCIC Suct Supply from Torus 6" Powell 1561 3-CKV-71-547 25 RCIC Pump Mmn Flow 2" Hancock 5580 3-CKV-71-580 26 RCIC Turbine Exh 10" Anchor Darling W9524568 3-CKV-71-589 25 RCIC Condensate Pump Discharge 2" Hancock 5580 3-CKV-71-592 25 RCIC Turbine Exh Dram 2" Hancock 5580 3-CKV-71-597 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-71-598 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-71-599 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-71-600 27 RCIC Turbine Exh Vac Bkr 2" Hancock 5580 3-ISV-73-23 28 HPCI Turbine Exh Stop CKV 16" Walworth 5312WE 3-ISV-73-24 21 HPCI Turbine Exh Drain Stop CKV 2" Velan W8-084B-2TY 3-FCV-73-45 44 HPCI Testable CKV 14" Atwood Morrill 15184-01 3-CKV-73-505 29 HPCI Suct Supply from CST 14" Chapman 151AWE 3-CKV-73-517 30 HPCI Suct Supply from Torus 16" Powell 1561 3-CKV-73-559 31 HPCI Pump Min Flow 4" Powell 9061 3-CKV-73-603 26 HPCI Turbine Exh 16" Anchor Darling W9524569 3-CKV-73-609 32 HPCI Turbine Exh Drain 2" Rockwell 838Y 3-CKV-73-625 25 HPCI Gland Seal Return 2" Hancock 5580 3-CKV-73-633 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-73-634 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-73-635 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-73-636 27 HPCI Turbine Exh Vac Bkr 2" Hancock 5580 3-CKV-74-54 33 RHR Loop I Testable CKV 24" Atwood Morrill 20800-H 3-CKV-74-68 33 RHR Loop II Testable CKV 24" Atwood Morrill 20800-H 3-CKV-74-560A 34 RHR Pump 3A Mm Flow 3" Powell 3160A 3-CKV-74-560B 34 RHR Pump 3B Min Flow 3" Powell 3160A 3-CKV-74-560C 34 RHR Pump 3C Min Flow 3" Powell 3160A 3-CKV-74-560D 34 RHR Pump 3D Main Flow 3" Powell 3160A 3-CKV-74-661 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-13AA 3-CKV-74-662 35 RHR Thermal Relief CKV 3/4" Velan W04-203B-13AA 3-CKV-74-792 36 Loop I RI-R Keep Fill 2" Hancock 5580 3-CKV-74-802 36 Loop II RHR Keep Fill 2" Hancock 5580 3-CKV-74-803 36 Loop II RER Keep Fill 2" Hancock 5580 3-CKV-74-804 36 Loop I RHR Keep Fill 2" Hancock 5580 3-CKV-75-26 37 CS Loop I Injection CKV 12" Rockwell 770(CF8M) 3-CKV-75-54 37 CS Loop 11 Injection CKV 12" Rockwell 770(CF8M) 3-CKV-75-570A 38 CS Pump 3A Mm Flow 3" VelanBI01114B2T 3-CKV-75-570B 38 CS Pump 3B Mmn Flow 3" Velan BI01114B2T 3-CKV-75-570C 38 CS Pump 3C Min Flow 3" Velan B101114B2T 3-CKV-75-570D 38 CS Pump 3D Mm Flow 3" Velan BI01114B2T 3-CKV-75-606 36 Loop I CS Keep Fill 2" Hancock 5580 3-CKV-75-607 36 Loop I CS Keep Fill 2" Hancock 5580 3-CKV-75-609 36 Loop IICS Keep Fill 2" Hancock 5580 PAGE 58 OF 59

UNID CM DESCRIPTION SIZE MANUFACTLRER/MO GROU DEL P

3-CKV-75-610 36 Loop It CS Keep Fill 2" Hancock 5580 3-CKV-76-653 39 TIP Indexer Purge Supply 1/4" Teledyne 483-1 3-CKV-78-526 40 U3 Fuel Pool Cooling Supply 8" Damel 1601 3-CKV-84-600 41 CAD Dryvell Supply A 2" Kerotest TVD9911 S(2) 3-CKV-84-601 41 CAD Torus Supply A 2" Kerotest TVD991 IS(2) 3-CKV-84-602 41 CAD Drywell Supply B 2" Kerotest TVD991IS(2) 3-CKV-84-603 41 CAD Torus Supply B 2" Kerotest TVD991IS(2) 3-CKV-85-589 42 CRD Charging Water (189 valves) 1/2" General Electric 117C3743P006 3-CKV-85-597 42 CRD Cooling Water (189 valves) 1/2" General Electric 117C3743P006 3-CKV-85-616 42 CRD Scram Outlet (189 valves) 1/2" General Electric I_ 117C3743P006 NOTES:

(1) Unit 1 check valves are listed in the Program listing, but are not monitored until required to be operational. As U1 components are returned to operation they will be phased into the normal monitoring activities.

(2) Monitoring activities include internal inspections (disassembly), radiographic inspections, flow/no flow testing, Appendix J leak rate testing, Maintenance Rule monitoring, SOER 86-03 Program inspections.

(3) Initial intervals are two operating cycles (maximum) with evaluations for increase or decrease in intervals after individual activities are completed.

PAGE 59 OF 59