Text

Revised Pump & Valve Inservice Testing Program
	ML20137E882
Person / Time
Site:	Sequoyah
Issue date:	08/16/1985
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20137E881	List: ML20137E875; ML20137E882;
References
	PROC-850816, NUDOCS 8508260092
	Download: ML20137E882 (147)
	v • d • e

4 DICLOSURE 1

-i -- em SEQUOYMI NUCLEAR PLANT UNITS 1 AND 2 PUMP MID VALVE INSERVICE TESTING PROGRR4 Submitted: b /d M IDate I

/

B508260092 850816 PDR P

ADOCK 05000327 PDR

pe r

SUMMARY

OF MAJOR REVISION TO IST PROCRAM FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 The major revisions to the Pumps and Valves Inservice Testing Program for ..

Sequoyah Nuclear Plant units 1 and 2 are outlined below:

1.0 Section 3.0/3.0* - Reworded to reflect addition of Appendix E, Catego'ry B-Passive valves. Comments regarding maximum allowable stroke time and

" cycled" valves were relocated to different sections (3.7 and 3.5, <

respectively) for clarity.

2.0 Section 3.1/3/1* - Additional information provided to describe application of paragraph IWV-3420 to containment isolation valves and pressure isolation valves (reference Enclosure 2, Section 3.1.4).

3.0 Section -/3.4* - Section from previous submittal titled Corrective Action delted as unnecessary (reference Enclosure 2, Section 3.2.2).

4.

Section 3.7/3.6* - Revised minimum limit on maxinum allowable stroke time and calculated maximum allowable stroke time to 22 seconds instead ofiti seconds as agreed to by NRC in working meeting held July 2, 1985 (reference Enclosure 2, Section 3.10.1).

5.0 Section 3.8/3.9* - Reworded to reflect addition of Appendix E, Category B-Passive valves.

Numbering in current submittal / numbering in 1982 submittal .

-J

6.0 Section 3.9/3.10* - Revised to reflect NRC position (wording) stated in SER.

7.0 Appendix A - Defined use of "Q" in Table A.

8.0 Table A - Numbering of notes was changed in some cases to reflect additions / deletions / revisions to Notes for Table A. Relief is no longer requested for~ measuring flowrates for AFWPs, CCPs, or BATPs (reference Enclosure 2, Section 2.3.2).

9.0 Notes for Table A Note 2/2* - Requested relief to measure flowrates to 3-percent accuracy when employing ultrasonics (reference Enclosure 2, Section 2.3.3).

Note -/7* - Deleted reference to AERCW; resulted in renumbering of subsequent notes. '

Note - /8* - Deleted relief request to measure vibration accuracy to ill-percent (reference Enclosure 2, Section 2.4.1).

Note 10/12* - Provided additional information to request relief for measuring inlet or differential pressure for diesel fuel oil transfer pumps (reference Enclosure 2, Section 2.2.2).

Numbering in current submittal / numbering in 1982 submittal.

d{

l l

10.0 Appendix C .

Reordered listing of valves as required to facilitate system and numerical sequencing.

Deleted AFW valves. PCV-3-122 and PCV-3-132 (reference Enclosure 2, Section 3.2.1).

Deleted pressurizer auxiliary spray valve, PCV-62-84 (reference Enclosure 2, Section 3.9.1).

Added diesel fuel oil transfer pump discharge CVs 18-578-1A/1B/2A/2B and 18-579-1A/1B/2A/2B (reference Enclosure 2, Section 3.9.2).

Added inlet CVs to diesel starting air tanks, 82-502-1A1/lB1, 2A1/2B1 and 85-529-1A2/1B2/2A2/2B2 (reference Enclosure 2 Section 3.9.3).

Added CVCS relief valves62-505, 62-518, and 62-688 (reference Cnclosure 2 Section 3.9.4.1).

Added RCS CV 68-599 (reference Enclosure 2, Section 3.9.5.1).

Added Reactor Head Vent System valves FSV-68-394, FSV-68-395, FSV-68-396, FSV-68-397 (reference Enclosure 2, Section 3.9.5.2).

di 10.0 Appendix C (continued)

Updated information in valve listing for PASF valves, FSV-43,250,.

FSV-43-251, -FSV-43-287, FSV-43-288, FSV-43-307, FSV-43-308, FSV-43-310, FSV-43-317, FSV-43-318, FSV-43-319, FSV-43-325, FSV-43-341, FSV-43-460, and FSV-43-461.

Relocated all-Category B-Passive valves _into Appendix E.

Reclassified various ERCW valves as B-Passive and relocated to Appendix E (reference Enclosure 2, Section 3.9.7.1).

Added indication of backsnating requirement for valve 63-510 to be performed at CSD.

PV references under Remarks were renunibered as required to reflect revirions/ additions to PVs.

11.0 PVs PV-7 and PV Separated CL Accumulator and Common RHR/ SIS / Accumulator i

CVs into separate relief requests; revised relief requests to address full flow exercising requirement through scheduled valve disassembly.

PV Revised relief request for CS and RilR Spray CVs to address full flow exercising requirement through scheduled' valve disassembly.

11.0 PVs (continued)

PV Revised relief request for UHI CVs to address full flow exercising requirement through schedule valve disassembly.

PV (new relief request) Requested relief from requirement of IWV-3300 for PASF valves (reference Enclosure 2, SEction 3.9.6).

PV-17 --(new relief requested) Requested relief from testing requirements for CV 68-559 (reference Enclosure 2, Section 3.9.5.1).

PV (new relief requested) Requested relief from requirements of IW7-3300 for Reactor Head Vent System valves (reference Enclosure 2, Section 3.9.5.2).

12.0 Appendix D Corrected typographical errors and clarified CSD testing basis for 63-570.

Added basis for backscating valve 63-510 at CSD.

Added basis for CSD testing of PASF valves.

Deleted FCV-67-478 from Appendix D due to reclassification as Category B-Passive.

f 12.0 Appendix D (continued)

Added basis for CSD testing of Reactor Head Vent-System valves.

13.0 Appendix E - All Category B-Passive valves are listed in this new Appendix.

Category E valves for unit 1 are indicated accordingly (reference Enclosure 2, Section 3.2.4 and Enclosure 1 Section 3.8).

vt,

f CONTENTS Page

1.0 INTRODUCTION

...... ............................................. 1

~

2.0 PUMP INSERVICE TESTING PR0 GRAM.................................. 1 2.1 Pump Testing Frequency.................................... 1 3.0 VALVE INSERVICE TESTING PR0 GRAM................................. 2 3.1 Category A Va1ves......................................... 2 3.2 Thermal Relief Valves..................................... 3 3.3 Thermal Relief Check Valves............................... 3 3.4 Systems Out of Service.................................... 4 3.5 Emergency Diesel Systems.................................. 4 3.6 Fail-Safe Actuators....................................... 4 3.7 Valve Timing and Remote Indication........................ 4 3.8 Passive Va1ves............................................ 5 3.9 Cold Shutdown Testing..................................... 5 Appendix A................................................ 6 Appendix B................................................ 10 Appendix C................................................ 17 Appendix D................................................ 98 Appendix E................................................ 104 e.

r INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE SEQUOYAH NUCLEAR POWER PLANT e- .

1.0 Introduction .

Under the provisions of 10CFR50.55a, inservice testing of safety related pumps and valves will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. As specified in 10CFR50.55a(b), the effective edition of Section XI with regard to this program is the 1974 Edition through the Summer 1975 Addenda (Unit 1) and the 1977 Edition through the Summer l 1978 Addenda (Unit 2). This program identifies the pump and valve inservice testing that will be performed at the Sequoyah Nuclear Power Plant to comply with the requirements of 10CFR50.55. Where this text refers to specific paragraphs in Section XI, the paragraphs in the 1977 Edition through Summer 1978 Addenda is referenced. Refer to the equivalent paragraph-in the 1974 Edition through Summer 1975 Addenda when required.

2.0 Pump Inservice Testing Program The pump test program shall be conducted in accordance with Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code (applicable Edition and Addenda) except for relief requested under the provisions of 10CRF50.55a (g) (5) (iii). Appendix A details the inservice testing program for all safety related pumps at Sequoyah Nuclear Plant. ' Table A in Appendix A lists each pump required to be tested in accordance with IWP-1100 of Section XI of the code. Each parameter to be measured as well as specific notes concerning nonccnformance are also listed.

2.1 Pump Testing Frequency Present regulatory policy requires that all safety related pumps installed in water-cooled nuclear power plants be tested in accordance with the ASME Code,Section XI, Subsection IWP. The purpose of these.

tests is to collect data to be used in assessing the operational readiness of pumps during their service life.

There are two reasons for conducting periodic pump testing. The first is to record data for assessing operational readiness and the second is to lubricate those bearings of the prime mover and pump which may

' lose their oil lubrication film due to lack of operation. In order to properly lubricate their bearings, these pumps should be " rolled" or

" jogged" for a very short time, in order to supply lubricant to wear surfaces.

Starting and running the pump for the purpose of recording data

. permits an assessment of operational readiness but also subjects the pump to wear. In determining the most effective and efficient pump test frequency, the benefits of running the pump to record this data 1

--,,--n ,m

2.1 pump Testing Frequency (continued) must be weighed against the cost in degraded pump integrity and reliability. Pump reliability can be adequately demonstrated (and degradation reduced) by con' ducting the Section XI pump test quarterly, ,

as is consistent with the operational readiness test for valves as presently endorsed by the ASME code. In addition, the latest NRC-accepted version of the ASME code calls for quarterly testing-of safety-related pumps.

Thus, Sequoyah will fully test each pump quarterly per Section XI.

3.0 Valve Inservice Testing Program The valve test program shall be conducted in accordance with Subsection IWV of Section XI cf the ASME Boiler and Pressure Vessel Code (applicable Edition and Addenda) except for where relief has been requested under the provisions of 10CFR50.55a (g) (5) (iii). The valve test program is included as Appendix C and Appendix E. The codes and symbols used to abbreviate the tables in Appendix C and Appendix E are explained in Appendix B. Appendix C provides the valve listing for all but B-passive valves; Appendix E lists all B-passive l

. valves in safety related systems for which there are no Code testing requirements.

3.1 Category A Valves Valves for which seat leakage is important may generally be classified as pressure isolation valves (PSIV), containment isolation valves (CIV), or both pressure and containment isolation valves. Containment isolation valves falling within the scope of ASME Section XI are tested in accordance with Section XI requirements for Category A valves with the exception of the seat leakage tests (IWV-3420). The seat leakage testing of these valves (IWV-3421 through IWV-3425) meets ,

the intent of Section XI, but the actual test procedures shall.be in accordance with the 10CFR50, Appendix J, Type C, CIV test program.

The pertinent leak rate criteria for CIVs is that the total leak rate :

for all penetrations and valves be less than 0.60 La. The Sequoyah I plant was designed to perform the Appendix J, Type C tests, not the individual Category A leak test (i.e., some penetration test connections test more than one valve at a time). Accordingly, all CIV seat leak testing shall be performed in accordance with the requirements of 10CFR50, Appendix J, Type C, in lieu of the Category A requirements of Section XI. The rec,uirements for analysis of leakage rates and corrective actions, paragraphs INV-3426 and INV-3427 respectively, are met as follows for CIVs. CIVs are assigned conservative reference leaktates based upon the valve size and the total allowable containment penetration leakage,.0.6 La. The total of all of the reference leakrates is set equal to approximately 40% of the total allowable containment leakage, i.e., 40% of (0.6 La); this provides a comfortable margin even if all valves are leaking their respective reference leakrates.

2

3.1 Category A Valves (Continued)

During refueling outages maintenance is performed, if required, in an attempt to restore all CIVs to below their refarence leakrates and as close to zero leakage as reasonably achievable; this ensures the ability,of the containment system to satisfy the Integrated Leakrate

~ Testing criteria,and to-provide adequate margin for valve degradation over tha next fueLcycle __While etvery attempt is.Jnade _to. maintain, CIVs at zero leakage or below their reference leakrates at all times, a valve leaking in excess of its reference value may remain operable and left "as is" in certain situations, provided that an evaluation by plant management (i.e. , supervisory personn'el or designated senio'r level engineer) finds it acceptable. While the maximum permissible leakrate at this time would, by plant technical specifications, be limited to the current margin between overall containment leakage and 0.6 La, maximum single penetration leakage is at all times administratively limited to 20% of 0.6 La. Any such valve, exceeding the reference leakrate.but not in excess.of 20%.of 0.6 La, would_be repaired or replaced no later than the next refueling outage oc.even during the next CSD of sufficient duration if practical.

PSIVs are leak tested in accordance with ASME Section XI requirements for Category A valves; acceptance criteria and test frequency are more conservatively defined by plant technical specifications. Corrective action requirements of INV-3427 for trending of leakrates are not performed due to the valve leak test system configuration and.

interaction with adjacent systems. (FCV-74-1 and FCV-74-2 will be trended per IWV-3427 until.an outstanding design change request which ties these valves into the valve leak test system is implemented.)

3.2 Thermal Relief Valves Many safety related systems, particularly those with heat exchangers, have been provided with relief valves. Somo of these relief valves are thermal relief valves (TRV) of small capacity intended to relieve pressure due to thermal expansion of fluid in a " bottled-up" condition. Experience has shown that failure of these valves will not result in failure of a system to fulfill its safety related function.

Thus, the thermal relief valve is not safety related and such valves have not been included in the program.

3.3 Thermal Relief Check Valves Several penetrations have been fitted with small check valves designed to relieve pressure due to thermal expansion of fluid in the penetration. These valves will be leak tested in the closed position per Appendix J (10CFR50); however, these valves do not have a safety related function to open. The reasoning is similar to that for the thermal relief valves, in that the only occasion -that would require the opening function of these valves is when both CIVs are absolutely tight with =ero leakage. On that occasion, the thermally-induced 3

1 1

l 3.3 Thermal Relief Check Valves (continued) pressure increase will be stabilized since only a minute amount of leakage past any barrier would stabilize the penetration pressure.

Sequoyah views these valves as safety related only in the closed ,

position to provide containment isolation function. These valves are identified in Appendix C with TRCV written in Remarks.

3.4 Systems Out of Service Relief is requested from the requirements for testing valves in systems which are out of service before returning those systems to operating status, per INV-3416 of Section XI. These testing requirements are adequately covered in the Sequoyah Technical Specifications and plant procedures.

3.5 Emergency Diesel Systems The inservice operability testing of pumps and valves associated with the Emergency Diesels are excluded from the enclosed test programs, with the exception of the fuel oil transfer pumps, air start valves and inlet check valves (CV's) to the starting air tanks. These components are an integral part of the Emergency Diesel System and are functionally tested by the Diesel tests. Thus, the functional operability testing of the pumps and valves is performed at a frequency equal to that required by Section XI for either pumps or valves. Additionally, the failure of a pump or valve to perform it's intended function will be identified by the failure of the associated Emergency Diesel to meet its functional requirements. The fuel oil transfer pumps, air start valves, and inlet CVs to the starting air tanks are tested quarterly per ASME Section XI and are included in this submittal. The stroke time of the air start valves cannot be measured as there is no visible valvo etem movement or indication.

They are identified in Appendix C, Remarks by the word " cycled"; they are only cycled and not timed. The stroke is verified as acceptable by verifying the Diesel comes up to speed in 510 seconds as required by Technical Specifications.

3.6 Fail-Safe Actuators All those valves which have a fail-safe actuator are exercised normally using that actuator. Thus, the fail safe actuator is regularly tested when the valve is tested per INV-3415.

3.7 Valve Timing and Remote Indication During each full stroke test of a power operated valve, the full stroke time shall be measured, in accordance with Section XI, Article INV-3413. The Calculated Maximum Allowable Stroke Times and the Maximum Allowable Stroke Times shall not be <2.0 seconds due to the eye and hand coordination involved in manually operating a stop watch. In addition, each valve with a remote operator shall be 4

3.7 Valve Timing and Remote Indication (continued) exercised using that operator and position indicator for verification of valve position during refueling outages, but not less than once every two years-in accordance with Section XI, Article IWV-3300.-

~

3.8 Passive Valves These valves, which have no Section XI testing requirement, are valves in-safety related systems which are not required to change position in order to accomplish their required safety function. Sequoyah has included in Appendix E as B-Passive all manually operated valves which are required by procedure to be maintained in their safety related position, any valves which are locked-open or locked-closed in their safety related position (indicated Category E for Unit 1 valves), any valves which are required to be maintained with power removed or control air isolated, the cold leg accumulator FCVs, and the alternate ERCW supply FCVs to the diesel coolers. The normal position for manually operated ERCW throttle valves used for balancing the ERCW system -is indicated as open; the normal position-for these valves may be full open or throttled depending upon the results of the latest balancing.

3.9 Cold Shutdown Testing (CSD)

CSD valve testing as identified by the licensee will be conducted pursuant to the following conditions:

Valve testing will commence as soon as possible, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching CSD conditions. Valve testing will proceed in a normal manner until all testing is complete or the plant is ready to return to power. A completion of all valve testing is NOT a prereq-uisite to return to power. Any testing not completed by the end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test performed at the previous cold shutdown.

Per planned cold shutdowns, where ample time is available and testing all the valves-identifed for the cold shutdown test frequency in the IST program will be completed, exceptions to the 48-hour requirement may be taken.

5

APPDIDIX A SEQUOYAII PUMP INSERVICE TESTING PROGRAM Summary of Information Provided The pump test table (Table A) provides the following information on testing requirements:

1. System

2. Drawing on which the pump is depicted

3. Speed

4. Inlet Pressure

5. Differential Pressure

6. Flow Rate

7. Vibration Amplitude

8. Bearing Temperature

9. Observation of Lube Oil Level / Pressure Quarterly testing in accordance with the requirements of Section XI, Subsection IWP is indicated by "Q"; non-conformance' is addressed in specific notes as indicated.

I I

l i

6 l

SEQUOYAH NUCLEAR POWER PLANT .

TABLE A-PUMP TEST PROGRAM Drawing Inlet Differential Flow Vibration Bearing Observe Lube Oil g, Nunber Speed Pressure Pressure Rate Applitude Tenperature Level / Pressure (Note.2) n Pj Ap Q V Tb Auxiliary Feed 47W803-2 Note 1 Q Q Q Q Note 7 Yes W ttr (Motor)

' Auxiliary Feed 47W803-2 Q Q Q .Q Q Note 7 Yes Watzr (Steam)

Centrifugal 47WD11-1 Note 1 Q Q Q Q Q Yes Charging 47W809-1 SafetyInjection 47W811-1 Note 1 Q Q Q Q Q Yes System EssIntial Raw 47WG45-5 Note 1 Q Note 4 Note 4 Note 5 Note 7 Note 3 Cooling h ter Note 9 Conponent 47W859-1 Note 1 Q Note 4 Note 4 Q Note 6 Yes Cooling Containment- 47W812-1 Note 1 Q Q Q Q Note 6 Yes Spray Residual Heat 47W10-1 Note 1 Q Q Q Q Note 8 Yes Removal Diss21 Fuel Oil 47W840-1 Note 1 Note 10 Note 10 Q Q Note 7 Note 10 Transfer Note 11 Boric Acid 47N809-5 Note 1 Q Q Q Q Note 6 Yes Trtnsfer

l s

i i

NOTES FOR TABLE A

1. Synchronous or induction motor driven pumps do not require speed check per IWP-4400.

2. When flow rate is measured with internally installed plant instrumentation accuracy will be within m 2% of full scale. When flow rate is measured with externally mounted ultrasonic transducers, accuracy will be z 3% of full scale.

. 3. This pump uses water lubricated bearings and thus, lubrication level measurements cannot be taken.

4. These pumps are not equipped with recirculation / test lines. The nature of the system they feed makes it impossible to specify a particular flowpath that can always be repeated. Various components which they feed _will sometimes require cooling water and sometimes not. Sequoyah j established an in situ pump curve which establishes the relationship

between flow and differential pressure in a band around the pump design 4

point. Subsequent inservice tests compare test data to this curve

using the allowable test ranges per IWP-3210.

! 5. The pump bearings are inaccessible as the pump is submerged in a pit.

6. These pumps have no installed instrumentation to measure bearing temperature. A bearing cap temperature measurement is not considered indicative of bearing temperature due to temperature gradient caused by operation of space coolers, pump location, etc.

) 7. Bearings are cooled by pumped fluid and bearing temperature measurements are not required per ASME XI.

8. This is a closed coupled pump and does not have a bearing in the pump and thererfore, does not require bearing temperature measurements per ASME XI.

l i

9. The inlet pressure is calculated for this pump by measurement of lake level.

! 10. No instrumentation exists to measure inlet or outlet pressure or to determine differential pressure. Differential pressure is not meaningful for detectir.g degradation on a positive displacement type

pump. The pumps are lubricated by the pumped fluid; therefore, lube oil level or pressure is not measured.

i i 8 i

4 I

,,--,,---.-,,--,,_,_y,--,-y ,, , - ,- - , , - - , - - - - , . -- , --

NOTES (continued)

11. The only means of measuring flow rate on these pumps is by measuring a level increase in the day tank while the' pumps are running. Accuracy

~

using this indirect method of measuring flow rate is poor. Even with poor accurancy, the 10 gpm -limit will provide adequate margin for -

allowing the pumps to fulfill their intended function. Therefore, the B10 gpm limit.is established in lieu of the ranges given in IWP-3100-2.

4 Y SM #O' eh P*M- M 4P w 4 WU<

e . me . e q, + m= '-+ - + .ym.- .e 9

APPENDIX B EXPLANATION OF CCDES AND SYMBOLS USED IN THE SEQUCYAH VALVE INSERVICE TESTING PROGRN4 -

This Appendix defines the meaning of all codes and symbols used in the valve test program presented in Appendix C and Appendix E.

4 l

t 10

TABLE B-1 SYMBOLS USED TO DESIGNATE VALVE TYPE VALVE TYPES SYMBOL MEANING BUT Butterfly BAL Ba11 CK Check DIA Diaphragm GA Gate GL Globe ND fleedle AN Angle PLG Plug RD Rupture Disk REL Relief SC Stop Check SK Spring Check 11

TABLE B-2 SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE VALVE ACTUATOR TYPES SYMBOL MEANING DIA Diaphragm Air Operator M Manual Operator MO Motor Operator SA Self Actuated SO Solenoid Operator CYL Cylinder /

Hydraulic Operator RD Rupture Disc 12

I TABLE B-3 SYMBOLS USED TO DESIGNATE VALVE POSITION VALVE POSITIONS _

1 SYMBOL MEANING O Open C Closed LO Locked Open LC Locked Closed TH Throttled Valve position determined by other system parameters as in the case of any check valve.

13

4 TABLE B-4 1 SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT

]

2 r

CATEGORY A OR B VALVES

QT-1 Exercise valve (full stroke) for operability every 3 months, in accordance with Section XI, Article IWV-3411.

QT-2 Exercise valve (part stroke) for operability every 3 months and full. stroke at cold shut-i down, in accordance with-Section XI, Article IWV-3412(a).

CS These valves.have been specifically identified 1

in Appendix D as valves which are not tested during power operation. These valves shall be full stroke tested during cold shutdowns in j accordance with Section XI, Article IWV-3412(a).

SLT Perform a Seat Leak Test during refueling, but

! not less than once every 2 years. Leak rate I

limits will be established by the licensee in accordance with 10CFR50 Appendix J. .

J I SLTP Perform a Scat Leak Test for pressure isolation f function as required by Technical Specifications.

< ER Exercise full stroke at refueling only.

i I

i i

f 14

TABLE B-4 (continued)

SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT CATECORY C VALVES-l CV-1 Exercise valve (full stroke) for operability every 3 months, in accordance with Section XI, Article IWV-3520.

CV-2 Exercise valve (part stroke) for operability every 3 months and full stroke at cold shutdown, in accordance with Section XI, Article IWV-3520.

CS- These valves have been specifically identified in Appendix D as valves which are not tested during power operation. These valves shall be full stroke tested during cold shutdown only, in accordance with Section XI, Article IWV-3520.

SLT Perform a Seat Leak Test during refueling, but not less than once every 2 years. Leak rate limits will be established by the licensee in accordance with 10CFR50 Appendix J.

SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications.

RF Test safety and relief valve setpoints in accordance with Section XI, Article INV-3510.

ER Exercise at refueling only.

TRCV Thermal Relief. Check Valves; tested only as CIVs (see 3.3).

DIS /IE Disassemble and inspect at least once every two years, in accordance with IE Bulletin 83-03.

15

TABLE B-4 (continued) s.kMBOLSUSEDTODESIGNATETESTINGREQUIREMENT S

CATEGCRY D RD Operational checks of rupture discs shall be performed in accordance with the manufacturers' recommendations. The frequency of tests shall be specified by the licensee in accordance with Section XI, Article IWV-3620.

16

APPENDIX C SEQUOYAH NUCLEAR PLANT VALVE PROGRAM Summary of Information Provided -

The following tables used the format referenced in the 1978 "NRC Staff Guidance for Preparing Pump and Valve Test Program Duscriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)" to give valve descriptions. The following information is provided:

1. System Name and Number

2. Drawing Number

3. Valve Number

4. ASME Section XI Classification or NNCC (Non Nuclear Code Class)

5. Drawing Coordinates of Valve

6. Valve Category Per Section XI, Article IRV-2110

7. Valve Si=e

8. Valve Type ,

9. Actuator Type

10. Normal Position

11. Testing Required Per Section XI

12. Relief Request Required

13. Alternate Testing

14. Remarks (including Relief Request Numbers, Specific Valve Data, etc.)

17

Sequsych Nuclocr Plznt insarvico Velvo Tacting Prcgram (1) MA STEAM ppAgygg pg 4N801-1 (R18) gyg g .

o6 > c4 H0 VALVE m 3$

- $$ w $a 8m jb TESTING D h5 NUMBER kO dO N d"

>b #$b i2 o "H REQUIRED U O id $ REMARKS

<o >b o ga NN ag 6 < =g g-FCV-1-4 2 C-4 B-ACT 32 GA CYL 0 QT-2 MSIV See Table 0-1 PCV-1-5 2 C-2 BC-ACT 6 GA DIA C CS FCV-1-11 2 E-4 B-ACT 32 GA CYL 0 QT-2 MSIV See Table D-1 PCV-1-12 2 D-2 BC-ACT 6 GA DIA C LS FCV-1-22 2 G-4 B-ACT 32 GA CYL 0 QT-2 MSIV See Table D-1 PCV-1-23 2 F-2 BC-ACT 6 GA DIA C CS FCV-1-29, . 2 A-4 B-ACT 32 GA CYL 0 QT-2 NSIV See Table 0-1 i PCV-1-30 2 A-2 BC-ACT 6 GA DIA C CS FCV-1-147 2 C-4 B-ACT 2 GL DIA C QT-1 FCV-1-148 2 E-4 B-ACT 2 GL DIA C QT-1 FCV-1-149 2 G-4 B-ACT 2 GL DIA C QT-1 FCV-1-150 2 A-4 B-ACT 2 GL DIA C QT-1 1-512 2 F-3 C 6 REL SA C RF 1-513 2 F-3 C 6 REL SA C RF 1-514 2 F-3 C 6 REL SA C RF 1-515 2 F-3 C 6 REL SA C RF 1-516 2 F-3 C 6 REL SA C RF 1-517 2 0-3 C 6 REL SA C RF 18

tl l F F F F S C C C C Y V V V V S 1 1 1 1 T

- - - - E 1

8 1

7 1

6 1

5 N M

, U V :

MA B L a

EV I RE I 3

dm S

2 2 2 2 o m e q

B B A B u

8 8

9 9

- *30 o y

U8 "$bU a

8 8

B B

>d$ h A A A A C

T C

T 6H8$M N u

4 4 4 4 mdp c

l e

G G G G >d$ a r

A A A A b"w P l

H M M H <

C a 0 0 O 0 4 GOC n b$a t I

=O2j n 0 O O 0 A8HNo s

1 9

e r

C C 0 Q S S 7 T

R ET v

i 1 1 QE c US I T RI e

EN DG V a

l v

gUD e MO b T e

WRyH$ s t

eW$dO i n

g P

r D

R o

g A

W r I

N a G

N m

R O E :

M

' A R 4 K N S 8 0

3 2

M1 4

_ 9

)

Scqurych Nuclocr Pl:nt incarvica Vciva Tcoting Pr: gram SYSTEM-(' $ ^" 4 N801 - 1 (R18)

DRAWING NO:

O > % n o VAINE M 3$" $o sa $ ga $ ca O TESTING Db h3 NUMBER u, NO

>b N

M d"

> #$b dOy5 REQUIRED U$U T2 $

WW REMARKS 4 0

=g ga ag 6 < g-1 518 2 D-3 C 6 REL SA C RF 1-519 2 D-3 C 6 REL SA C RF 1-520 2 D-3 C 6 REL SA C RF 1-521 2 D-3 C 6 REL SA C RF 1-522 2 C-3 C 6 REL SA C RF 1 523 2 C-3 C 6 REL SA C RF 1-524 , . 2 C-3 C 6 REL SA C RF 1-525 2 C-3 C 6 REL SA C RF I-526 2 C-3 C 6 REL SA C RF 1-527 2 A-3 C 6 REL SA C RF 1-528 2 A-3 C 6 REL SA C RF 1-529 2 A-3 C 6 REL SA C RF 1-530 2 A-3 C 6 REL SA C RF 1-531 2 A-3 C 6 REL SA C RF 20

F F F F F F F F C C C C C C C C V V V V V V V v 1 1 1 1 1 1 1 1 1 l 1 1 3 2 1 F 8 u 8 8 2 5 4 7 A 4 3 2 1 J V MA BL (

EV 1 RE )

S T

E A

M G

E N

E R

2 2 2 2 2 2 2 2 4m T A

S 0 m O

R e B q B F E C 6 F E C L

0 u 2

2 2

2 3

3 3

3 a 60 0

w o

y o

u $6O W N

a B

B B

B

- >N$ h A A A A A A A A C

T C

T O$> N u

2 2 2 2 2 2 2 2 mNm c

l e

G G G G A N

A N

A >N$ a r

L L L L N b$w P l

D D D D D D D D

OC C a I

A I

A n H$u t I

0 0 0 0 0 0 0 0 @dhi n

No s 2

1 Q Q Q Q Q Q Q A

e r

Q T

1 T

1 R

ET v i

QE c US I T RI e

EN DG V a

l v

@3D e

$mp T

e W2'hH$ s t

ym 5O i n

g P

r D o g

N r N a G

N m

R O E :

M A 4 R 7 W

K 8 S 0 1

2

(

R 1

4

)

Sequsych Nuclear Plant Inscrvico Vciva Tcating Prcgram gyg g ; (3) FEEDWATER DRAWING NO: 47wa03-1 (R12)

OH b >+ CC H 0 VAINE M 3$ $$ ga $ ga 8 ga hb TESTING DM h5 NUMBER dO N d* #$ (d REQUIRED U$ id $ REMARKS Eu a8 "O

!" E! ES

$5 FCV-3-33 2 C-3 B-ACT 18 GA MO O CS FCV-3-47 2 E-3 B-ACT 18 GA MO O CS FCV-3-87 2 G-3 B-ACT 18 GA MO O CS FCV-3-100 2 B-3 B-ACT 18 GA MO O CS 3-508 2 G-2 C 16 CK SA -

CS 3-509 2 E-2 C 16 CK SA -

CS 3-510 , . 2 C-2 C 16 CK SA -

CS ,

3-51I 2 B-2 C 16 CK SA -

CS 22

S quaych Nucbcr Plant Insarvico Valvo csting Prsgram (3) AUXILIARY FEEDWATER 47W803-2 (R19)

SYSTEM, DRAWI!3G IJO:

b > M H C OH ~ g o

VALVE m 3

"$ $o ga $ ga ga o TESTItJG Dy h3 NUMBER h k NO

>H N

m N$

>H

$H 2NO "

REQUIRED UDU id$

WW REMARKS 4 9 8 6 4

= 0 gM B" U 4 *C FCV-3-179A 3 G-5 B-ACT 10 GA HO C QT-1 FLV-3-liSB 3 G-5 B-ACT 10 GA HG C QT-1 3-8C5 3 F-5 C 8 CK SA -

CV-1 X YES See PV-9. Punp Test 3-806 3 F-6 C 8 CK SA -

CV-1 X YES See PV-9, Punp Test 3-810 3 G-4 C 10 CK SA -

CV-1 X 1ES See PV-9 Pump Test 3-814 3 F-5 C 1-1/2 CK SA -

CV-1 Punp Test 3-815 3 F-b C 1-1/2 CK SA -

CV-1 Puno Test 3-815 3 G-7 C l-1/2 CK SA -

CV-1 Punp Test 3-820 3 F-5 C 6 CK SA -

CV-1 X YES See PV-12 3-821 3 F-6 C 6 CK SA -

CV-1 X YES See PV-12 3-830 2 F-9 C 4 CK SA -

CV-1 X YES See PV-12 J-uji z L-9 C 4 UK bA -

CV-1 X iE5 See PV-12 3-632 2 C-9 C 4 CK SA -

CV-l X YES See PV-12 3-633 2 A-9 C 4 CA $A -

CV-1 X YES See PV-12 3-86) 2 F-10 C 4 CK SA -

CV-1 X YES See PV-12 3-862 2 E-10 C 4 CK SA -

CV-1 X YES See PV-12 3-864 3 G-6 C 6 CK SA -

CV-1 X YES See PV-12 3-871 2 F-9 C 4 CK SA -

CV-1 X YES See PV-12 23 t

Scquoyah Nuclacr Plant Inservico Valvo Tcsting Program (3) AUXILIARY FEEDWATER 47W803-2 (R19)

I n W HO DH > W ~ p VALVE M 6$ $o ga $ga d ca hO TESTING Dy hU NUMBER

k "k NO N N$ <$ i2 P h6 O"y REQUIRED 3g 72 $

WW REMARKS k" "8U

>P 6

M >H W g gM B" 4

3-872 2 D-9 C 4 C'K SA -

CV-1 X YES See PV-12 3-s13 2 C-9 C 4 CK SA -

CV-1 X YES See PV-12 3-874 2 A-9 C 4 CK SA - CV-1 X YES See PV-12 3-891 3 8-8 C 4 CK SA -

CV-1 X YES See PV-9, Pump Test 3-692 3 A-8 C 4 CK SA -

CV-1 X YES See PV-9. Pump Test 3-694 3 A-6 C-ACT 3 CK SA -

CV-1 Pump Test 3-695 3 A-b C-ACT 3 CK SA -

CV-I Pump Test 3-921 2 G-lo C 4 .CK SA -

CV-1 X YES See PV-12 3-922 2 E-10 C 4 CK SA -

CV-1 X YES See PV-12 24 e

Scqusych Nuclerr Plant Insarvico Vciva Tcsting Prsgram (3) AUXILIARY FEEDWATER D M ING NO, 47W803-2 (R19)

N oH > cc , wo VAINE m 3$

" $ o" m $ m. @m o TESTING h hM PRJMBER m 4 0 kk NO

>H U

m d

>$ "* 4$H d oH REQUIRED UNO R$

ww REMARKS 8 6 4 =8 gW "

O Da FCV-3-116A 3 F-6 B-ACT 8 GA H0 C QT-1 FCV-3-116B 3 F-6 B-ACT 8 GA M0 C QT-1 FCV-3-126A 3 F-7 B-ACT 8 GA HO C QT-1 FCV-3-1268 3 F-7 B-ACT 8 GA M0 C CT-1 FCV-3-l'6A 3 G-5 B-ACT 10 GA M0 C QT-1 FCV-3-136B 3 G-5 B-ACT 10 GA NO C QT-1 LCV-3-140 . 3 F-8 B-ACT 4 GA DIA C QT-1 :

LCV-3-148A 3 F-8 B-ACT 2 GA DIA C QT-1 LCV-3-156 3 E8 B-ACT 4 CA DIA C QT-1 LCV-3-156A 3 E8 B-ACT 2 GA DIA C QT-1 LCV-3-164 3 C8 B-ACT 4 CA DIA C QT-1 LCV-3-164A 3 C8 B-ACT 2 GA DIA C QT-1 LCV-3-171 3 A-8 B-ACT 4 GL DIA C QT-1 LCV-3-171A 3 B-8 B-ACT 2 GA DIA C QT-1 LCV-3-172 3 F-8 B-ACT 3 GL DIA C QT-1 LCV-3-173 3 D-8 B-ACT 3 GL DIA C QT-1 LCV-3-174 3 C-8 B-ACT 3 CL DIA C QT-1 LCV-3-175 3 A-8 B-ACT 3 GL DIA C QT-1 25 i

9 Scqusych Nuclacr Pinnt Insarvico Valvo Tcsting Program (18) FUEL CIL 47W840-1 (R17)

SYSTEM. DRAWItG tiO:

E $

0H > M ~ g H O VAINE y m 6$

$$ w $w $u hO TESTIf;G Dy hd liUMBER $ g N$ U d$

"" #$ Td N REQUIRED URg id N REMARKS

te a8U " E5 h" 05" E W $U

G In-5?u-IA r.NCC F-7 B-ACT 1-1/2 CK ,SA -

CV-1 Pump Test in-5io-15 tetaCC F-7 6-ACT l-1/2 CK SA -

CV-1 Pump lest to-576-2A feaCC F-7 8-ACT 1-1/2 CK SA -

CV-1 Ptsnp Test 15-576-26 f4NC C F-7 B-ACT l-1/2 CK SA -

CV-l Puno Test in-5/v-iA te r.tC F-7 6-ACT l-1/2 CA SA -

CV-1 Ptsup Test in-579-is rat 4CC F-7 6-ACT l-1/2 CA 5A -

CV-l Pump Test ia-5/9-sA l.l.CC F-7 6-ACT l-1/2 CK SA -

CV-1 Pinnp Test lo-5/9 .6 fi!.CC r-i 6-ACi 1-1/2 CK 5A -

CV-1 Pump Test 26 e

Sequsych Nuclecr Plant inacrvico Vciva Testing Pr: gram (26) FIRE PROTECTION 373 DRAWI!JG IJO: 4N850- 10 oe 0 - W x -o VALVE M

b hO M M OM o TESTItJG Dm y5 tensen !3 4 0 d a" >da e

m d

>s

<g aU ge oa nrouInto 3so gN a t; ww atnaaxs "8O 6 < =oA B" 4

FCV-26-240 2 A-9 A-ACT 4 GA MO O QT-1. SLT FCV-26-241 3 D-7 B-ACT 4 GA MO O QT-1 FCV-26-242 3 0-7 B-ACT 4 GA MO O QT-1 FCV-26-243 2 B-3 A-ACT 4 GA MO O QT-1. SLT FCV-26-244 3 G-2 B-ACT 4 GA MO O QT-1 FCV-26:245 3 G-1 B-ACT 4 GA MO O QT-1 9

26-IR60. 2 A-9 AC-PAS 4 CK SA -

SLT ,

26-1296 2 B-3 AC-PAS 4 CK SA -

SLT 27 e

Scquaych Nuclecr Plant Inscrvico Vcivo Tcctina Pragram (30) NEATING AhD VENTILATING AIR FLOW pgggggg 90: 4 N866-1 (R23)

E $

HO 0H H Ct g VAINE M hN hO E3 hW OW O TESTING Dm hU NUMf4ER NO N d" #$H d 5 REQUIRED U R$ REMARKS kg k* "k >H m >b O

= y O

Ly a WW ag e < e ge FCV-30-7 2 C-1 A-ACT 24 BUT CYL C QT-1, SLT FCV-10-8 2 C-2 A-ACT 24 BUT CYL C QT-1. SLT FCV-30-9 2 C-1 A-ACT 24 BUT CYL C QT-1. SLT FCV-30-10 2 C-2 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-14 2 E-1 A-ACT 24 BUT CYL C QT-1, SLT (CV-30-15 2 E-2 A-ACT 24 BUT CYL C QT-l. SLT FCV-30-10 - 2 F-1 A-ACT 24 BUT CYL C QT-1. SLT e FCV-30-17 2 F-2 A-ACT 24 BUT CYL C OT-1 SLT FCv-30-19 2 G-1 A-ACT 24 BUT CYL C QT-1. SLT FCV-30-20 2 G-2 A-ACT 24 BUT CVL C QT-1 SLT FCV-30-37 2 D-10 A-ACT 10 BUT CYL C QT-1 SLT FCV-30-40 2 D-9 A-ACT 10 BUT CYL C QT-1. SLT FCV-30-46 2 B-4 A-ACT 20 BUT CYL 0 QT-1. SLT FCV-30-47 2 B-5 A-ACT 20 BUT CYL 0 QT-1. SLT FCV-30-48 2 B-7 A-ACT 20 BUT CYL 0 QT-1. SLT FCV-30-50 2 C-10 A-ACT 24 BUT CYL C QT-1. SLT FCV-30-51 2 C-10 A-ACT 24 BUT CVL C QT-1. SLT FCV-30-52 2 C-10 A-ACT 24 BUT C)L C QT-1. SLT 28

Sequsych Nucle:r Plant incarvico Vcivo Tccting Prsgram (30) HEATING AND VENTILATING AIR FLOW D N ItJG 110, 47W866-1 (R23)

U Ct; h

HO 0b >e ,

VALVE m 3$

$ w $m @u o TESTI?JG D hd tJUMBER m NO gO N d"*

>$ #$ o 5 cd H REQUIRED U O R$

ww REMARKS

.< o 8

de 6

m he 4 =8 gN "

O D*

TCv-30-53 2 C-10 #-ACT 24 BUT CYL C QT-1, SLT FCV-30-56 2 E-9 A-ACT 24 RUT CYL C QT-1. SLT FCv-30-57 2 E-10 A-ACT 24 BUT CYL C QT-6, SLT FCV 30-58 2 G9 A-ACT 12 BUT CYL 0 QT-1. SLT FCV-30-59 2 G-10 A ACT 12 BUT CYL 0 QT-1. SLT FCv-30-134 2 F-9 A-ACT 3/8 GA SD 0 QT-1. SLT FCV-30-135 + 2 F-9 A-ACT 3/8 GA SO O QT-1. SLT ,30-571 2 B-4 AC-ACT 20 REL SA C RF SLT 30-572 2 B-5 AC-ACT 20 REL SA C RF SLT 30-573 2 B-7 AC-ACT 20 REL SA C RF SLT l

l l

29

Scqusych Nuclecr Plant Inscrvico Vcivo Torting Prsgrcm (31) AIR CONDITIONING CHILLED WATER 47W865-5 8 G oe >. m -o VALVE M

$w f. y jo TESTING Db h6 NUMBER w

3 $ $ o" w U d$ 4$ T2 N U$o g$

id REMARKS

<ho d "a >dd o m >e ge o- REQUIRED gM ww 8 6 4 =8A B" O 4 FCV-31C-222 2 A-7 A-ACT 2 GA DIA 0 QT-1. SLT FCV-31C-223 2 A-8 4-ACT 2 CA DIA 0 QT-1. SLT FCV-31C-224 2 B-7 A-ACT 2 GA DIA 0 QT-1. SLT FCV-31C-225 2 B-8 A-ACT 2 GA DIA 0 QT-1. SLT FCV-31C-229 2 0-7 A-ACT 2 GA DIA 0 QT-1. SLT FCV- 31C - 2 3 0 2 D-8 A-ACT 2 GA DIA 0 QT-1. SLT FCV-31C ,231 2 E-7 A-ACT 2 GA DIA 0 QT-1 SLT ,

FCV-31C-232 2 E-8 A-ACT 2 GA DIA 0 QT-1. SLT 31C-697 2 F-8 AC-PAS 1/2 SK SA C SLT TRCV 31C-715 2 E-8 AC-PAS 1/2 SK SA C SLT TRCV 31C-734 2 C-8 AC-PAS 1/2 SK SA C SLT TRCV 31C-752 2 B-8 AC-PAS 1/2 SK SA C SLT TRCV l

30

Scqusych Nuclecr Plant inacrvico Vciva Tccting Program gyg g (32) COMPEESSED AIR DRAWING NO- 47W848-1 (R13) 06 >+ 0; , p HO VALVE M U$ $$ w $w 8m hO TESTING [3 y hU NUMBER U

dO N d" #$ kN REQUIRED 3D T4 $ REMARKS Qg O N N O A l-FCV-32-80 2 C-9 A-ACT 2 GA DIA 0 CS, SLT 2-FCV-32-81 2 F-9 A-ACT 2 GA DIA 0 CS. SLT 1-FCV-32-102 2 D-9 A-ACT 2 GA DIA 0 CS, SLT 2-FCV-32-103 2 E-9 A-ACT 2 GA DIA 0 CS, SLT l-FCV-32-110 2 A-9 A-ACT 2 GA DIA D CS, SLT 2-FCV-32-111 2 G-9 A-ACT 2 GA DIA 0 CS, SLT l-32.285 2 C-9 A-PAS 2 GA M C SLT 1-32-2M7 2 A-lO AC-ACT 2 CK SA - CS, SLT 1-32-295 2 E-9 A-PAS 2 GA M C SLT 1-32-297 2 C-10 AC-ACT 2 CK SA - CS, SLT 2-32-34I 2 E-9 A-PAS 2 GA M C SLT 2-32-348 2 E-10 AC-ACT 2 CK SA - CS, SLT 2-32-353 2 F-9 A-PAS 2 GA M C SLT 2-32-358 2 F-10 AC-ACT 2 CK SA - CS, SLT 1-32-375 2 B-9 A-PAS 2 GA M C SLT 1-32-377 2 0-10 AC-ACT 2 CK SA - CS, SLT 2-32-385 2 G-9 A-PAS 2 CA M C SLT 2-32-387 2 G-10 AC-ACT 2 CK SA - CS, SLT 31 e

Sequrych Nucle r Plant inacrvico Vcivo Testina Program (33) CONTROL & SERVICE AIR DMWING NO. 47W846-2 (R18) gyg 08 b > M H O

~ p VALVE M U$ $o" w $w $w O TESTING hy h3 f.tMBER m NO s" d$ $$ d N REQUIRED 3Dg 2$ REMARKS U

og O b

NM N U

33-704 2 F-7 A-PAS 2 CIA M C SLT 33-722 2 F-4 A-PAS 2 DIA M C SLT 33-739 2 F-4 A-PAS 2 GA M C SLT 33-740 2 F-6 4-PAS 2 GA M C SLT

, a f 32

I F F F F F F C C C C C C V V w V V V 4 4 4 4 4 4 3 3 3 3 3 3 2

2 1 i

3 2

n

. 3 2 2 l uY nA aI *

(

tE a 3 4

)

S A

M P

L I

h G

<mg S 2 2 2 2 2 2 o5m" e q

D F C C C C u 5

5 5

4 5

4 "2= o y

o O8 ~ e0 A A A A A a

A

\

A A

A

>g h C C C C C C T T T T T T aO >. N u

/

3 8

3

/

d 3

/

8

/

3 s

3

/

d 3

/

8 c

l m :: W e

G G G G G G >e a r

A A A A A A maw P l

D D D D D D a I

A I

A

< <hx n ecM t i

0 0 C C 0 0 =o n A8 CO s 3

3 e

r Q Q Q Q Q Q T

T T

T nT v i

1 1

,1 1 1

,1

, . . eE uS c S

L T

5 L

T S

L T

S L

T S

L T

S L

T rT nI e

eN oG V a

l v

3D e Mos= T e

4Baah W .

s t

"w;t5o i n

g P

r o

g r

a m

a c

?

a u 4 x

s 7

W 6

2 5

1

(

R I

5

)

F F F F F F C C C C C C V V V V V V 4 4 4 4 4 4 3 3 1 3 3 3 6

6 5

5 3

3 N

4 1 8 5 5 4 uV nA sL tV (

aE 3 4

)

S A

M P

L I

N G

<m S 3 3 3 3 2 2 o3M e q

0 C C C C C u 8

8 8

8 3

2

- "n2bo y

o o8a~ zed a- a B B A a

A A A

A A

>dh h C C C C C C T T T T T T 6eao >. N u

3

/

3

/

3

/

3 i

3

/

3

/ c 8 8 8 a 8 8 w "W l e

G C G G G G >d$

a r

A A A A A A E"w P l

D D D D D D a I

A I

A

< g 4p .:

n eRw t i

C C

=o n 0 0 0 0 A8~CO s 3 e r

4 Q Q Q Q Q Q T

T T

T 1

a rT v i

1 1 1 1 1 gE uS c S

L T

S L

T rT aI e

tN oG V a

l v

g:Ds e Mos T e

<Uwah U s t

"w;t3o i n

g P

r o

g r

a m

a n

s

' x a 4 x 7 W

s o 2

5 2

(

R 1

i 3

)

? -

G.

'?

O ke b

z E a~

Ow 2 o

w a

O C

OflIIS31

() 3AIlv!M317Y O

b IS3n53u O J3I13H U

> 90 mM 2 %

O e- a w u ne : :

} "U i i e O n t10IIISOd g TYWOtt w 3dA1 , ,

C HO1VfUDV E E

.0, 1 3dA1 6 3A7va 5 0

()

$ 3ZIS = =

u = =

3 2, Auocalva 3 3 g 3A7vA ; ;

U h S31Vt1IcHOOD M OtIIMvua $ a 3

7 SSV70 g ~ ~

m awSv 9

0 m

m 5 W5 am .

si ~

e :: -

@ s 6 e b b

S:qusych Nuclocr Pl:nt inscrvico Vciva Tcctina Prcgram I"3I S # 'I"C DRAWING NO:

4 25-11 M9) sys m .

0H b >< M H O VAINE M $$ , $ w $w f. w O TESTING D h5 NUMBER mh kO N d$ #$ d N REQUIRED U $! $ REMARKS U $ N N Og D*

U FCV-43-201 2 F-8 t-ACT 3/8 GA DIA 0 QT-1. SLT FCV-43-202 2 C-9 s-ACT 3/8 GA DIA 0 QT-1. SLT FCV-43-207 2 C-10 A-ACT 3/8 GA DIA 0 QT-1. SLT FCV-43-208 2 B-11 A-ACT 3/8 GA DIA 0 QT-1. SLT

. I I

36

?

Scquoyah Nuclacr Plant Inservico Valvo Tcsting Program (43) SAMPLING 47w625-15 SYSTm. DR7 MING NO:

$ > h 06 M ~ g H C VAEVE M bh hO M hw Ou 6 TESTING UM h3 NUMBER "o NO N d$

2N REQUIRED "3 g M$ REMARKS l

a8O "O h"$05"A EN 5.C 0 FSV-43-250 2 0-1 A-ACT 3/8 GA SO C CS, SLT. X .Ves PV-15 i

esv-43-251 2 C-1 4-ACT 3/a LA su C ts, dLT x ves PV-15 i

FSV-43-287 2 8-9 A-ACT 3/8 GA 50 C CS, SLT X Yes PV-15 FSV-43-255 2 B-9 A-ACT 3/8 GA 50 C CS, SLT X 'fes PV-15 FSv-43-307 2 8-10 A-ACT 3/8 GA SO C CS, SLT X Yes PV-15 FSV-43-3G9 2 0-2 A-ACT 3/8 GA S0 C CS, SLT X Yes PV-15 FSV-43-310 2 C-2 A-ACT 3/8 GA SO C CS, SLT X Yes PV-15 FSV-43-317 2 G-b A-ACT 3/8 GA S0 C CS, SLT X .Yes PV-15 FSV-43-318 2 8-9 A-ACT 3/8 GA S0 C CS, SLT X Yes PV-15 j FSV-43-319 2 B-9 A-ACT 3/8 GA SO C CS, SLT X Yes PV-15 FSV-43-325 2 6-10 A-ACT 3/8 GA SO C CS, SLT X Yes PV-15 ryw-43-341 n-o 2 A-ALI 3/a GA 50 C CS, SLT A tes PV-15 43-460 2 A-10 C-ACT 3/8 CK SA C SLT 43-401 2 G-5 C-ACT 3/8 CK SA C SLT 37 e

' llI l ll ll 1 3

3 3

3 S

K

R A e M _

E _

O R N

m G ar I

N W

g A R

D r

P a

n d

i t

O5$y c gHhi d o

T b$

o [3U@

i v

c V GD NE T T T T T T T T I R o TI SU L

S L

S i

c EQ TE v

r R

8 a n O5 3

s C L

C L

i n 4@

g t w$b n MO#

l a M H M M M M M M P w$b r $dD L

G L

G c

l o uNM 4 4 4 4 4 4 4 4 c /

3

/

3

/

3

/

3

/

3

/

3

/

3

/

3 u

N >$O S A

P S

A P

S A

P S

A P

S A

P S

A P

S A

P S

A P

h $N> A A

A A

c y Y mNI s T I

Od a u L I

q C A

a F M U T 2 2 2 2 2 2 2 2 S S E

T m4 H

E T

S Y

S

)

2 5 ER

(

VE .

LB AM 0 1 2 3 4 5 6 p

7 VU 0 5

0 5

0 5 5 0

5 N - - - - - - - -

2 2 2 2 2 2 2 2 5 5 5 5 5 5 5 5 lll l

Scqusych Nuclacr Pl nt insarvico Vcivo Tocting Prcgram (59) DEHINERALIZED WATER & CASK DECONTAMINATION W 856-1 (R19)

DRAWING NO:

O > M n o VALVE M d$ $ m $m @m jo TESTING $ hh NUMBER m

"" <0 N d"

&N REQUIRED U$ i"d $ REMARKS 8

U "O h EUA ES U 59-522 2 F-3 A-PAS 2 GA H LC SLT 59-529 2 F-3 .A-PAS 3/4 BUT H C SLT 59-633 2 F-3 AC-PAS 2 CK SA -

SLT 39 e

l ~

Saqusych Nuclocr Pinnt Insarvico Valva Tcsting Pr gram

( 1) CE CONDENSER DRAWING NO: 47W814-2 (R13)

SYSTEM:

ON N N O VALVE m dI $$ w $ ga O ga hbN TESTING D hM NUMBER

N "O NO

>H N

m d"

$ o(dH REQUIRED U$O R$

WW REMARKS 4o =84 bg M "

"8U 6 4 FCV-61-96 2 G-10 A-ACT 2 DIA DIA 0 QT-1. SLT FCV-61-97 2 G-10 A-ACT 2 DIA DIA 0 QT-1. SLT FCV-61-110 2 H-10 A-ACT 2 DIA DIA 0 QT-1. SLT FCV-61-122 2 H-10 A-ACT 2 DIA DIA 0 OT-1. SLT FCV-61-191 2 A-5 A-ACT 4 DIA DIA 0 QT-1, SLT FCV 61-192 2 A-5 A-ACT 4 DIA DIA 0 QT-1, SLT ,

FCV-61-193 e 2 A-5 A-ACT 4 DIA DIA 0 QT-1 SLT e FCV-61-194 2 A-5 A-ACT 4 DIA DIA 0 OT-1, SLT 61-533 2 A-5 AC-PAS 3/8 SK SA C SLT TRCV 61-680 2 A-5 AC-PAS 3/8 SK SA C SLT TRCV 61 692 2 G-10 AC-PAS 3/8 SK SA C SLT TRCV 61-745 2 H-10 AC-PAS 3/8 SK SA C SLT TRCV 40 i

Scqusych Nuclacr Plant Insarvico Vcivo Tcsting Prcgrcm (62) CHEMICAL & VOLUME CONTROL SYSTEM 47W809-1 (R19)

DMWING NO:

0 >< ct: p o VALVE M $$ $$ w $w Ow O TESTING hM hU NUMBER h NO N d" N REQUIRED U id $ REMARKS U Q O N N FCV-62-61 2 B-7 A-ACT 4 GA MO O CS, SLT FCV-62-63 2 B-8 A-ACT 4 GL MO O CS, SLT FCV-62-72 2 A-5 A-ACT 2 GL DIA C QT-1. SLT FCV-62-73 2 A-4 A-ACT 2 GL DIA 0 QT-1. SLT FCV-62-74 2 A-4 A-ACT 2 GL DIA C QT-l', SLT FCV-62-77 2 A-7 A-ACT 2 GL DIA 0 QT-1, SLT FCV-62-90 . 2 D-7 B-ACT 3 GA M0 O QT-1 i FCV-62-91 2 D-8 B-ACT 3 GA M0 O OT-1 FCV-62-98 3 0-9 8-ACT 2 GA M0 O CS FCV-62-99 3 D-9 B-ACT 2 GA MO O CS FCV-62-132 2 E-10 B-ACT 4 GA MO O CS FCV-62-133 2 E-10 B-ACT 4 GA M0 O CS LCV-62-135 2 H-10 B-ACT 8 GA M0 C CS LCV-62-136 2 H-10 B-ACT 8 GA M0 C CS62-504 2 H-10 C 8 CK SA -

CV-1 X ER See PV-2 62-505 2 F-10 C 3/4 REL SA C 62-518 2 F-9 C 3/4 REL SA C 62-519 2 F-9 C-ACT 3 CK SA C CV-1 41

Scqusych Nuclacr Pirnt inservico Valvo Tosting Program (62) CHEMICAL & VOLUME CONTROL SYSTEM DRAWING NO:

b h 0H N D: H0 VALVE M U$ $$ ga $m @ ga b TESTING Db hd NUMBER 4 0 *2 "2 >HNO N w

d*

>C #$ gg N ge o"8s REQUIRED U o is! $

ww REMARKS "8O 6 <

gW D" A 4 62-523 2 H-9 C 2 CK SA -

CV-l Pump Test 62-525 2 H-9 C 4 CK SA C CV-1 X Yes See PV-1, Pump Test 62-530 2 G-9 C 2 CK SA -

CV-1 Pump Test 62-532 2 G-9 C 4 CK SA C CV-1 X Yes See PV-1, Pump Test 62-636 2 B-6 C 2 REL SA C RF 62-639 2 C-7 AC-PAS 3/4 SK SA -

SLT TRCV 62-6,49.. 2 C-9 C 2 REL SA C RF ,62-662 2 A-3 AC-ACT 2 REL SA C RF, SLT 62-675 2 A-10 C 2 REL SA C RF 62-688 NNCC C-10 C 3 REL SA C ti2-69 7 2 E-10 C-ACT 4 CK SA -

CV-1 Pump Test 42

\,

's' i A $

f tn 0 "

~

e< 9

. 5 E$

sM 2

~

9 9

M

, ME * @

CLASS 5 DRAWING

- e

n Q COORDINATES @ M A N VALVE O C CATEGORY y Z w

M z

C SIZE n

=

g VALVE m 5

TYPE g 2

ACTUATOR 3

3 TYPE *

NORMAL 3

POSITION fn w c ,O 7

~ se $.

@U O

-e U

o-

@n o <

m RELIEF g

REQUEST

-4 ALTERNATIVE m

(/)

TESTING 7.

3 Q

,M e O E C, e

5 N 2

3

f g .O.

a "o

~

Scqusych Nuciscr Plant insarvico Valvo Tasting Prsgram (63) SAFETY INJECTION SYSTEM 811-1 @ 20)

DRAWING NO:

OH > % n 9 HO VALVE M U$ $$ ga $ga O ga hU TESTING hM hM NUMBER U

NO N d" k$ &N REQUIRED U id $ REMARKS og O A

N N O

FCV-63-1 2 F-10 8-ACT 12 GA H0 0 CS FCV-63-3 2 D-8 B-ACT 2 CL H0 0 CS FCV-63-4 2 0-8 B-ACT 2 GL HQ O QT-1 FCV-63-5 2 0-10 B-ACT 8 GA H0 O CS i

FCV-63-6 2 F-10 B-ACT 4 GA H0 C QT-1 FCV-63-7 2 F-10 B-ACT 4 GA H0 C OT-1 FCV-63-8, . 2 H-9 B-ACT 8 GA HO C CS 4

FCV-63-11 2 F-9 B-ACT 8 GA H0 C CS FCV-63-22 2 0-6 B-ACT 4 GA H0 0 CS FCV-63-23 2 D-6 A-ACT 3/4 GA DIA 0 QT-1.SLT FCV 63-25 2 A-7 B-ACT 4 GA HO C QT-1 FCV-63-26 2 B-7 B-ACT 4 GA H0 C QT-1 FCV-62 38 2 B-8 B-ACT 1 GL DIA 0 QT-1 FCV-63-39 2 B-9 B-ACT 4 GA MO C QT-1 FCV-63-40 2 C-9 B-ACT 4 GA H0 C QT-1 FCV-63-41 2 A-9 B-ACT 1 GL DIA 0 QT-1 FCV-63-42 2 A-9 B-ACT I GL DIA 0 QT-1 j FCV-63-47 2 E-10 B-ACT 6 GA N0 0 'QT-1 44 i

4 Saquoyah Nuclocr Plant Insarvico Valva Tcsting Program (63) SAFETY INJECTION SYSTEM 47W811-1 (R20) 0H >< C4 g H 0 VAINE NUMBER y

j U$

" $o NO u

N

$ga N$

O ga f

$H $y TESTING REQUIRED

$y hU UDg R$ REMARKS 4o kk >b U2 >H O "mo ggd WW "8U 6 < 4 B" 4

tLV-63-4d 2 0-10 d-ACT 6 GA M0 O QT-1 ety uJ /l 4 L-6 4-AL6 LL 3/4 UIA C QT-1,SLT FCV-63-72 2 N-O B-ACT 18 GA M0 C CS FCV-63-73 2 N-6 6-ACT Id GA MO C CS tui-u3-os 2 C-o A-ACT 3/4 GL DIA C Qi-1,$LI FCV-03-93 2 G-7 6-ACT b GA MO O CS FCV-63-94 2 G-7 B-ACT 8 GA M0 O CS FCV-63-lL2 2 D-7 B-ACT 4 GA M0 O QT-1 FCV-63-153 2 E-7 B-ACT 4 CA MO O QT-1 FCV-63-156 2 E-6 B-ACT 4 GA M0 C QT-1 FCV-03-157 2 0-0 B-ACT 4 GA M0 C QT-1 tLV-us-i/4 4 t-b d-ALI IZ UA MO C CS FCV-o3-175 2 D-d B-ACI 2 GL MO O QT-1 o3-502 2 F-lu C 12 CK SA CV-1 X ER See PV-3 63-510 2 D-10 C a CK SA -

CV-1, CS X ER See PV-4 63-511 2 0-10 C 3/4 REL SA C RF 63-524 2 E-8 C 4 CK SA -

CV-1 X ER See PV-13 Pump test verifies closure 63-526 2 0-8 C 4 CK SA -

CV-1 X ER See PV-13 Pump test verifies closure 45 6

Soquoych Nuciscr Pl:nt Insarvico Valvo Tcsting Pragram (63) SAFETY INJECTION SYSTEM 1- ( 0)

DRAWING NO:

N $

09 > N g HC VAINE M dI" $$ w $w 8m hb TESTING $m h3 NUMBER d8 d d" #$ 2 N REQUIRED. "a D R$ REMARKS U o O N $

U 4 63-528 2 E-8 C 3/4 CK SA -

CV-1 Pump Test 63-530 2 D-8 C 3/4 CK SA -

CV-1 Pump Test 63-534 2 E-7 C 3/4 REL SA C RF 63-535 2 D-7 C 3/4 REL SA C RF 63-536 2 D-7 C 3/4 REL SA C RF 63-543 1 F-4 AC-ACT 2 CK SA - CV-1, SLTP X ER See PV-5 63 535 . 1 E-4 AC-ACT 2 CK SA -

CV-1, SLTP X ER See PV-5 ,63-547 1 D-4 AC-ACT 2 CK SA - CV-1, SLTP X ER See PV-5 63-549 1 E-4 AC-ACT 2 CK SA -

CV-1. SLTP X ER See PV-5 63-551 1 G-1 AC-ACT 2 CK SA -

CV-1 SLTP X ER See PV-5 63-553 1 H-3 AC-ACT 2 CK SA - CV-1, SLTP X ER See PV-5 63-555 1 G-3 AC-ACT 2 CK SA -

CV-1. SLTP X ER See PV-5 63-557 1 G-2 AC-ACT 2 CK SA -

CV-1. SLTP X ER See PV-5 63-558 1 E-3 AC-ACT 6 CK SA - CV-1, SLTP X ER See PV-5 63-559 1 D-1 AC-ACT 6 CK SA -

CV-1. SLTP X ER See PV-5 63-560 1 E-1 AC-ACT 10 CK SA - CS, SLTP X YES See PV-16 63-561 1 D-2 AC-ACT 10 CK SA - CS, SLTP X YES See PV-16 63-562 1 D-3 AC-ACT 10 CK SA -

CS, SLTP X YES See PV-16 46

?

Scquaych Nucirr Picnt Insarvico Vcivo Tcsting Prsgram (63) SAFETY INJECTION SYSTEN N WING NO, 47W811-1 (R20) o >e a; m g o VAINE W d$

" $$ w $w 8m N6 TESTING $1 M h3 NUMf4ER dO N d" kN REQUIRED U$ k$ REMARKS O a M

@ Q Wy U A 63-563 1 F-2 AC-ACT 10 CK SA - CS, SLTP YES See PV-16 63-570 2 B-8 C 1 CK SA -

CS63-581 1 8-7 C 3 CK SA -

CV-1 X ER See PV-6 63-586 1 E-1 C 1-1/2 CK SA -

CV-1 X ER See PV-6 63-587 1 D-2 C 1-1/2 CK SA -

CV-1 X ER See PV-6 63-588 1 0-3 C 1-1/2 CK SA -

CV-1 X ER See PV-6 63-5$9 . 1 E-2 C 1-1/2 CK SA -

CV-1 X ER See PV-6 63-602 3 A-1 C 1 REL SA C RF 63-603 3 A-3 C 1 REL SA C RF 63-604 3 A-4 C 1 REL SA C RF 63-605 3 A-6 C 1 REL SA C RF 63-622 1 C-1 AC-ACT 10 CK SA -

CV-1. SLTP X YES See PV-7 63-623 1 C-2 AC-ACT 10 CK SA -

CV-1. SLTP X YES See PV-7 63-624 I C-3 AC-ACT 10 CK SA -

CV-1 SLTP X YES See PV-7 63-625 1 C-3 AC-ACT 10 CK SA -

CV-1. SLTP X YES See PV-7 63-626 2 G-7 C 2 REL SA C RF 63-627 2 G-7 C 2 REL SA C RF 63-632 I G-3 AC-ACl 6 CK SA - CS, SLTP X YES See PV-8 47 e

i

Scqusych Nuclocr Pirnt Insarvico Valvo Tocting Prcgram (63) SAFETY INJECTION SYSTEH 47W811-1 (R20)

WING NO, O N C4 g O VAIXE NUMBER m dI $$

dO m

'N

$m d"

8m fb Id N TESTING REQUIRED

$y hU Ug Td $ REMARKS U

Ag O Ny N U S

'63-633 1 G-2 AC-ACT 6 CK SA - CS, SLTP X YES See PV-8 63-634 1 G-3 AC-ACT 6 CK '4

- - CS, SLTP X YES See PV-8 63-635 1 G-2 AC-ACT 6 CK SA - CS, SLTP X YES See PV-8 63-637 2 F-6 C 3/4 REL SA C RF 63-640 1 F-4 AC-ACT 8 CK SA - CS, SLTP X YES See PV-8 63-641 1 F-2 AC-ACT 6 CK SA - CS, SLTP X YES See PV-8 63-643.. 1 F-4 AC-ACT 8 CK SA -

CS, SLTP X YES See PV-8 i 63-644 1 D-2 AC-ACT 6 CK SA -

CS, SLTP X YES See PV-8 48

E T

= m

- N e

5 z

E e

~

G h 3 G W Q Q 6

4 m

C

DNIIS31 M 3AI1YinI317V O

b IS3n53H O .I3I73H (O

> 90 42 -

a gg g

.9

> soW i 6 O

U; <

NOIIISOd M u g 7vWHON w 3dIl C HOlvru.DV $

2 1 3dA1 5 3A7VA d t).

g

- 3ZIS O -

l 3 Z AHoo31vD y g 3A7va g f5 5

> G S31vNIGHOOD

%) E ONIMvHQ T 3 =

g h SSrID g g SuSv ~

O a

E W5 .

oc

<E l

>Q~ $

, A

\

f 2 i m ;

I $ M l

S qusych Nuclacr Plant insarvico Vcivo Tcsting Prsgram (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 845-1 (R16) 0H b >e C4 n 9 HO VAINE M d$ $$ w $w Ow jo TESTING $M hM NUMBER doh k* k" dy

>H U

m d$ #$H

>H

$! H O H REQUIRED U$O id$

WW REMARKS 8

U 6 < =8A Ld N "

FCV-67-66 3 C-11 B-ACT 6 BUT M0 C QT-1 FCV-67-67 3 C-7 B-ACT 6 BUT H0 C OT-1 67-508A 3 C-11 C-ACT 6 CK SA -

CV-1, DIS /IE DIESEL TEST IE BULLENTIN 83-03 67-5088 3 C-8 C-ACT 6 CK SA -

CV-1 DIS /IE DIESEL TEST. IE BULLENTIN 83-03 67-512A 3 C-10 C-ACT 8 CK SA -

CV-1 DIS /IE DIESEL TEST. IE BULLENTIN 83-03 67-5128 3 C-9 C-ACT 8 CK SA -

CV-1,' DIS /IE DIESEL TEST, IE BULLENTIN 83-03 67-5]3A. 3 C-11 C-PAS 6 CK SA -

DIS /IE IE BULLENTIN 83-03 i 67-5138 3 C-8 C-PAS 6 CK SA -

DIS /IE IE BULLENTIN 83-03 67-517A 3 C-8 C-ACT 8 CK SA CV-1, DIS /IE DIESEL TEST IE BULLENTIN 83-03 67-5178 3 C-10 C-ACT 8 CK SA -

CV-1, DIS /IE DIESEL TEST, IE BULLENTIN 83-03 "O

i

Scquoyah Nucicar Plant insarvice Valva Tcsting Program (67) ESSENTIAL RAW COOLING WATER 47W845-2 (RIS)

SYSTm. DRAWItJG 140:

0H N

N CC H0

~ g VALVE ca y $ $o ga $ra $ ga jO[ TESTIt1G Dy hM 13UtiBER kj 4 9 "g

4

<0

>H N

m d$

>B

$ O(4 fj bb REQUIRED UDg id $

WW RD4 ARKS "g "mg gW 6 W g" FCV-67-123 3 C-9 B-ACT 24 BUT H0 C QT-1 FCv-67-124 3 E-8 8-ACT 18 BUT H0 C QT-1 FCV-67-125 3 C-8 B-ACT 18 BUT H0 C QT-1 FCV-67-126 3 0-7 8-ACT 18 BUT H0 C QT-1 FCV-67-146 3 C-7 B-ACT 24 BUT H0 O CS FCV 67-152 3 C-7 B-ACT 24 BUT H0 C QT-1 51 e

Scqueyah Nuclocr Plant insarvico Valva Tcsting Prcgrcm (67) ESSENTIAL RAW COOLING WATER 47W845-3 (R14) 08 0 > m Ho VMNE m 3$ $$ w $w 0m

~

o TESTING $gm y6 NUMBER m MO N d" 4$b N REQUIRED U$ $! $ REf1 ARKS du a W > @ Q yy u m <

FCV-67-83 ? G-4 T-ACT 6 BUT HQ O CS, SLT FCV-67-87 2 G-4 4-ACT 6 BUT tO O CS, SLT FCV-67-88 2 G-4 4-ACT 6 BUT MO O CS, SLT FCV-67-91 2 F-4 4-ACT 6 BUT H0 0 CS, SLT FCV-67-95 2 F-4 A-ACT 6 BUT N0 0 CS, SLT FCV-67-96 2 F-4 A-ACT 6 BUT M0 O CS, SLT FCV-67-9? . 2 E-4 T-ACT 6 BUT H0 0 CS, SLT ,

FCV-67-103 2 E-4 4-ACT 6 BUT N0 0 CS, SLT

- FCV 104 2 E-4 A-ACT 6 BUT H0 0 CS, SLT FCV-67-107 2 0-4 A-ACT 6 BUT M0 O CS, SLT FCV-67-111 2 D-4 A-ACT 6 BUT H0 O CS, SLT FCV-67-112 2 D-4 A-ACT 6 BUT H0 O CS, SLT FCV-67-130 2 C-4 A-ACT 2 GA MO O OT-1. SLT FCV-67-131 2 C-4 A-ACT 2 GA MO O QT-1. SLT FCV-67-133 2 B-4 A-ACT 2 GA MO O QT-1, SLT FCV-67-134 2 C-4 A-ACT 2 GA MO O QT-1, SLT FCV-67-138 2 B-4 A-ACT 2 GA MO O QT-1. SLT FCV-67-139 2 B-4 A-ACT 2 GA H0 0 QT-1 SLT 52

Scqusych Nuclacr P!cnt insarvico Valvo Tocting Prcgram (67) ESSENTIAL RAW COOLING WATER 47W845-3 (R14)

DRAWING NO:

0H N >< 0; H0 VALVE M U$ $$ w $w* 8m b TESTING $M hdN NUMBER m MO N 4$ d REQUIRED U Td to REliARKS do og "@

" 5

!" 8j Wy gn FCV-67-141 2 A-4 A-ACT 2 GA M0 O QT-1 SLT FCV 67-142 2 A-4 A-ACT 2 GA M0 O OT-1. SLT FCV-67-295 2 C-4 A-ACT 2 GA MO O QT-1, SLT FCV-67-296 2 C-4 A-ACT 2 GA M0 O OT-1, SLT FCV-67-297 2 B-4 A-ACT 2 GA MO O QT-1. SLT FCV-67-298 2 A-4 A-ACT 2 GA MO O OT-1. SLT 67-552A, 2 G-4 AC-ACT 6 CK SA - CS, SLT ,

67-5628 2 E-4 AC-ACT 6 CK SA - CS, SLT 67-562C 2 F-4 AC-ACT 6 CK SA - CS,'SLT 67-562D 2 D-4 AC-ACT 6 CK SA - CS, SLT 67-575A 2 G-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-575B 2 E-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-575C 2 F-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-5750 2 D-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-580A 2 C-3 AC-ACT 2 CK SA -

CV-1. SLT 67-5800 2 0-3 AC-ACT 2 CK SA -

CV-1. SLT 67-580C 2 B-3 AC-ACT 2 CK SA -

CV-1. SLT 67 5800 2 A-3 AC-ACT 2 CK SA -

CV-1 SLT 53

Scquaych Nuclocr Plant Insarvico Valvo Testing Prcgram (67) ESSENTIAL RAW COOLING WATER 47W845-3 (R14) 0H N

> M H0 VALVE to d$ $ w $w 8m b TESTING $ h$

NUMBER h

U O N d*. 4$ N REQUIRED U id$ REMARKS Qg O N O A st; 67-Se5A 2 C-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-5858 2 B-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-585C 2 C-4 AC-PAS 1/2 CK SA -

SLT TRCV 67-5850 2 A-4 AC-PAS 1/2 CK SA -

SLT TRCV

. i 54 e

Sc:quaych Nuclocr Pl:nt insarvico Valva Tcsting Prcgram (67) ESSENTIAL RAW COOLING WATER DMWING NO- 47W845-5 (R6)

OH lH C4 HO VALVE m U$ $$ w $w f. w hb TESTING hb hd NUMBER dO N d"

$b fd 5 REQUIRED U Td $ REMARKS 4 0 -a M 9, @ y U A 2 FCV-67-205 3 G-9 B-ACT 6 BUT M0 O OT-1 FCV-67-208 3 G-10 B-ACT 6 BUT N0 0 QT-1 67-723A 3 B-3 C 24 CK SA -

CV-1 Pump Test 67-7238 3 0-3 C 24 CK SA -

CV-1 Pump Test 67-724A 3 B-3 C 24 CK SA -

CV-1 Pump Test 67-724B 3 0-3 C 24 CK SA -

CV-1 Pump Test 67-743A.. 3 G-3 C 24 CK SA -

CV-1 Pump Test i 67-7438 3 E-3 C 24 CK SA -

CV-1 Pump Test 67-744A 3 G-3 C 24 CK SA -

CV-1 Pump Test 67-7448 3 E-3 C 24 CK SA -

CV-1 Pump Test 55 0

Scqucych Nuclocr PI:nt Insarvico Vcivo Tcating Prsgram (67) ESSENTIAL RAW COOLING WATER 47W845-4 (RIS)

D N ING &

o > N o VALVE m dI

$$ w $w O na hb TESTING $m hM NUMBER k dO

>H N

M d*

>b 4$ (d "

H O REQUIRED U U id M WW REMARKS 8

O 6 < "U A by M "

FCV-67-162 3 B-7 B-ACT 2 GA DIA 0 QT-1 FCV-67-164 3 B-9 B-ACT 2 GA DIA C QT-1 FCV-67-176 3 0-7 B-ACT 1-1/2 GA DIA C QT-1 FCV-67-182 3 D-9 B-ACT 1-1/2 GA DIA C QT-1 FCV-67-184 3 0-7 B-ACT l-1/2 GA DIA C QT-1 FCV-67-186 3 D-9 B-ACT 1-1/2 GA DIA C QT-1 FCV-67-213 . 3 B-7 B-ACT l-1/2 GA DIA 0 QT-1 FCV-67-215 3 8-9 B-ACT 1-1/2 GA DIA C QT-1 FCV-67-217 3 B-2 B-ACT 2 GA DIA 0 QT-1 FCV 67-219 3 B-4 B-ACT 2 GA DIA 0 QT-1 FCV-67-336 3 A-2 B-ACT 1 GA DIA 0 QT-1 FCV-67-338 3 A-4 B-ACT 1 CA DIA 0 QT-1 FCV-67-342 3 G-7 B-ACT 2 GA DIA 0 QT-1 FCV-67-344 3 G-9 B-ACT 2 GA DIA C QT-1 FCV-67-346 3 E-8 B-ACT 1-1/2 GA DIA 0 QT-1 FCV-67-348 3 E-9 B-ACT 1-1/2 GA DIA C QT-1 FCV-67-350 No remote ind 3 E-7 B-ACT I-1/2 GA DIA 0 QT-1 FCV-67-352 3 E-9 B-ACT 1-1/; GA DIA C QT-1 l

56 i

{

1Il1 1ll i

e F F C C S V V Y 6 6 S 7 7 T E

3 3

" M

. 5 6

5 4 "v :

"A t N

o r

"u

'E

(

e )

m o

t e

i N

n d

3 3 Ng S

!m A

W q

e 0

F F 0 u o

L 9

7

- $50 I N

U8Eg G y B B W

A a A

A

- $g H h R

C C T T 6$gN N

1 1 u

/

1 1

/

Sm c

l 2 2 e

G A

G A $g a r

P l

D I

< j g;0 a A A

$, t n

i C 0 =@g n A8U8 s 5

7 Q Q e

r T T 1

1

- R Er v i

Qe c Us e

Mrni Dc V a

l v

WU3g e

W g T

es e

s t

_ e 3e i n

g P

r D

R o

g A

W r I

f 3

a G

1 1

m R 0 E :

M

. A 4

- R 7 K W S 8 4

5

- 4

- (

R I

, S

)

F C

V 6

8 3 N

, 0 UV

_ 5 MA

.- B L EV (

RE 6 8

)

R E

A C

T O

R C

2 O

O S Uho t L

A N

e q

T G S u 6

Og Q di ' Y S

T o

y

$H13 E 4

M a

A M$ h C

T O$.we N l

u 3

/

4 Nca c

l e

G d$ a L r "w P l

D

Oa:

a I

A n

$w t i

0 Od n 5o ,, s 5

8 Q A

e r

T 1

R ET v i

QE c

.S US L

T I T RI e

EN DG V a

l v

N3$ e T

e NhHW s t

N$do i n

g P

r D

R o

A g W r I

N a G

N m

R O E :

M e

A R 4 7

K W S 8 3

0 6

(

R 2

i 1

)

f Scquoyah Nucher Plant Insarvico Valvo Tcsting Program (68) REACTOR COOLANT SYSTEM 47W813-1 (R16)

SYSTEM. DRAWItJG 110:

D W oe >. a: g -o VALVE M d$

~

$ ga $ga O ga TESTI!JG f-e arguInEn El y hd tw.sen ,ca N <0 oa~h 3g at; 230 22 >e m

2

>e Be gN ww annAnxS "8U 6 W "oN B" FCV-68-332 1 B-3 8-ACT 3 CA MO O QT-1 FCV-o8-333 1 B-3 B-ACT 3 GA MO O OT-1 PCV-6d-334 1 B-3 B-ACT 3 GL DIA C CS X YES PORV; see PV 14 PCV-68-340A I B-3 B-ACT 3 GL DIA C CS X YES PORV; see PV 14 FSV-68-394 1 C-7 B-ACT I GL S0 -

QT-1 X Yes See PV 18 FSV-68-395 1 C-7 B-ACT 1 GL S0 C QT-1 X tYes See PV 18 FSV-68-396 1 C-7 B-ACT 1 GL S0 C QT-1 X Yes See PV 18 FSV-68-397 1 C-7 B-ACT 1 GL SO C QT-1 X Yes See PV 18 68-f~9 1 C-9 C 4 CK SA -

CV-1 X Yes See PV 17 68-563 1 A-3 C 6 REL SA C RF 68-564 1 A-4 C 6 REL SA C RF 68-565 I A-4 C b kEL SA C RF 59 I

F F C C V V

- - g 6 6 8 8 3 3 N

. 0 0 U V 8 7 MA B L EV (

RE 6 8

)

R E

A C

T O

R C

2 2 <

O O S o M L

A e N

T q F G S u 1

2 o dO Y S o T

g $bb E y M

a A

A

- >N$ h A A C

T C

T goo > N 3 3 u

/

8

/

8 c

Na l e

G G >d$

a r

A A c"w P l

D D .

c a I

A I

A l#84 n

$m t i

0 0 skQ n gH O ~ s 6

0 Q Q e

r T

1 T

1 R

ET v i

, . QE c US S

L T

S L

T I .-

R I' e

EN DG V a

l v

uUD e gDyg T

e gThH d s t

e$hO i n

g P

r D o M g W r I

N a G

N m

R E O.

M A 4 R 7 K W S 6 2

5 8

a i

Scqusych Nuclocr Plant inacrvico Velvo Tacting Program (70) COMPONENT COOLING SYSTEM 47W859-1 (R12) gg N $

0H > % n HO VALVE M U$

" $$ w $w Ow jo TESTING $ M NUMI4ER m 4 9 kk NO

>H N

M d"

>b #$H &N O H REQUIRED "$O i

gg

$ REMARKS 8 6 4 = 8A W U" O 4 FCV-70-1 3 H-6 B-ACT 12 BUT M0 O OT-1 FCV-70-11 3 H-5 B-ACT 12 BUT M0 O OT-1 FCV 70-66 3 E-3 B-ACT 2 AN DIA 0 OT-1 FCV-70-193 3 B-4 B-ACT 20 BUT MO O OT-1 FCV-70-194 3 B-4 B-ACT 20 BUT M0 0 OT-1 FCV-70-197 3 B-6 B-ACT 20 BUT MO O OT-1 FCV-70-Ic/d . 3 B-6 B-ACT 20 BUT MO O OT-1 i FCV-70-206 3 G-10 B-ACT 10 BUT M0 O OT-1 FCV-70-207 3 A-2 B-ACT 10 BUT M0 O OT-1 FCV-70-208 3 B-1 B-ACT 10 BUT M0 O OT-1 70-504 3 E-8 C 16 CK SA -

CV-1 Pump Test 70-504A 3 C-8 C 16 CK SA -

CV-1 Pump Test 70-504B 3 D-8 C 16 CK SA -

CV-1 Pump Test 70-538 3 E-3 C 4 REL SA C RF 70-753 3 F-9 C 8 CK SA -

CV-1 61 e

Scqucych Nuclocr PI:nt Insarvico Vcivo Tcsting Pragram (70) COMPONENT COOLING SYSTEM 47W859-2 (R14)

D M NG NO, N $

0H > t% n HO VALVE M U$ $$ m $w $w hO TESTING $ hM NUMilER Au f$N dO

>H N

M d$

>b

$b $5 O H REQUIRED U O id gg

$ REMARKS "8O 6 < =8A W B" FCV-70-85 2 0-10 A-ACT 6 BUT M0 O QT-1 SLT FCV-70-87 2 H-9 A-ACT 3 GA MO O CS, SLT FCV-70-89 2 E-9 A-ACT 6 BUT M0 O CS, SLT FCV-70-90 2 E-10 A-ACT 6 BUT M0 O CS, SLT FCV-70-92 2 E-10 A-ACT 6 BUT MO O CS, SLT FCV 70-134 2 H-3 A-ACT 3 GA M0 O CS, SLT FCV-70-140 , 2 G-3 A-ACT 6 BUT M0 O CS, SLT ,

FCV-70-143 2 E-3 A-ACT 6 BUT M0 O QT-1,SLT 70-679 2 H-4 AC-ACT 3 CK SA -

CS, SLT 70-687 2 H-9 AC-PAS 1/2 CK SA -

SLT 70 692 2 C-4 AC-ACT 6 CK SA - CS, SLT 70-698 2 E-9 AC-PAS 1/2 CK SA -

SLT 70-703 3 0-4 AC-ACT 3 REL SA C RF, SLT 62 i

) ,

7 R

(

4 9

5 8 S W

7 K 4 R 1 A

M E

R m g a

r g

g g

s r

P g

i n

t o5$N s $H 4 c

T ' D a

v UUN l

a V GD NE o I R TI SU i

c EQ 1 1 TE v

r R T Q

T Q

a bN A 3

6 s

I n h&O C C t w$

n c$4 0 O i

c c M M P :

g$.

T T r U U rc $d B B i

wN 8 8 u

1 1 N >$O T C

T C

h M

$N A A

B B c

y E

T S

Y 0H$ gO n S od a 3

4 u G N

F F q I L

O M U C

C S T N

3 3 E

4 r

C P

M O

C

)

0 7 ER

(

VE -

Lf 4 AM 3 6 VU 5 5 ,

N 1 1

0 0

_ 7 7

_ V V C C F F

Saqusych Nuclocr Plant Insarvico Vcivo Tccting Prcgram (72) CONTAINMENT SPRAY SYSTEM 47W812-1 (R11)

$ p: $

0P > ~ Ho VALVE y 3$ $$ m $m Om jU TESTING $] hh NUMBER g$

u3 Nd N d$ #" y-5 REQUIRED U N$ REMARKS U

ag > M >b A

Q My U

FCV-72-2 2 B-4 A-ACT 12 GA MO C QT-1, SLT FCV-72-13 2 B-7 B-ACT 2 GA M0 C OT-1 FCV-72-20 2 B-9 B-ACT 12 GA M0 C QT-1 FCV-72-21 2 B-10 B-ACT 12 GA M0 O OT-1 FCV-72-22 2 0-10 B-ACT 12 GA MO O 07-1 FCV-72-23 2 D-9 B-ACT 12 GA M0 C OT-1 FCV-72-34A . 2 C-7 B-ACT 2 GA M0 C QT-1 ,

FCV-72-39 2 0-4 A-ACT 12 GA M0 C OT-1. SLT FCV-72-40 2 E-4 B-ACT 8 GA PC C CS FCV-72-41 2 F-4 B-ACT 8 GA M0 C CS 72-506 2 0-9 C 12 CK SA -

CV-1 Pump test 72-507 2 B-9 C 12 CK SA -

CV-1 Pump test 72-528 2 0-7 C 12 CK SA -

CV-1 Pump test 72-529 2 B-7 C 12 CK SA -

CV-1 Pump test 72-547 2 D-3 C .12 CK SA -

CV-1 X Yes See PV-10 72-548 2 B-3 C 12 CK SA -

CV-1 X Yes See PV-10 72-555 2 F-3 C 8 CK SA -

CV-1 X Yes See PV-10 72-556 2 E-3 C 8 CK SA -

CV-1 X Yes See PV-10 64 e

Scqua.ych Nuclocr P!:nt Insarvico Vciva Tceting Prcgram (74) RESIDUAL HEAT REMOVAL SYSTEM DRAWING NO: 4N810-1 (R11)

U N oH u a: -o VALVE m d$" $$ g3 $w @ gi j-o TESTING hM hd NuMnER m3 4o ie mW aS

>b Ei V3 dD

>H "s &N O H REQUIRED U$

b O R b$ REMARKS "8O 6 bH =8 d'd h3 W

< A B" FCV-74-1 1 G-3 A-ACT 14 GA M0 C CS, SLTP FCV-74-2 1 lG-3 A-ACT 14 GA M0 C CS, SLTP FCV-74-3 3 E-9 B-ACT 14 GA MO O QT-1 FCV-74-12 2 F-6 8-ACT 2 GA MO O QT-1 FCV-74-16 2 F-4 B-ACT 8 BUT DIA 0 QT-1 FCV-74-21 2 C-9 8-ACT 14 GA MO O QT-1 FCV-74-24 . 2 B-6 8-ACT 2 GA MO O QT-1 ,

FCV-74-28 2 C-4 G-ACT 8 BUT DIA 0 QT-1 FCV-74-33 2 E-4 6-ACT 8 GA M0 O CS FCV-74-35 2 C-4 B-ACT 8 GA M0 0 CS74-505 2 G-3 C 3 REL SA C RF 74-514 F-7 2 C 8 CK SA - -

CV-2 Pump test: See Table D-1 74-515 2. C-7 C 8 CK SA -

CV-2 Pump test: See Table 0-1 l

65 i

lllllll F F F F F F F C C C C C C C V V V V V V V 7 7 7 7 7 7 7 7 7 7 7 7 7 7 2 1 1 1 1 1 9 N 0 9 8 7 6 0 UV MA 1

4 L E V (

RE 7 7

)

W A

S T

E D

I S

2 2 2 2 2 2 2 4 P O S 0 M S

A e L q C B B B B E 0 S

Y u 6

6 5

5 5

1 1

"k*d0 S T

E y

o O8k"$90 M A A A A A A A a

A A

A h h -

C C C C C C C T T T T T T T 6bho"> N u

1 I 1 3

/

4 3

/

4 3 3 mNw c

l e

D I

D D >d$ r a

I I A A A A A A A H$w P -

l D D D D D D D

< 4$4( a I

A I

A n

$"w t i

C D 0 C 0 0 0 =O n A8HNb s _

6 6

Q Q Q Q Q Q Q e

r T

1 T

1 R

ET v i

, , . . , , , QE c US S

L T

S L

T S

L T

S L

T S

L T

S L

T S

L T

I T RI e P P P P P P P EN DG V a

l v

Uh e NU T

WihHW e

d s t

"WNhO i n

g P

r o

g r

a m

R E

M i

A R 4 7

K W S 8 3

0 1

(

R 1

4

)

lll l1l llllllll l l l l l l

Sequoyah Nuciaer Plant inservice Valvo Tcsting Program (77) WASTE DISPOSAL SYSTEM 47W830-6 (R21)

!JG IJO, b

0B > CC ~ g H0 VALVE m U$

o a w 0m j$ TESTI!1G Dy hU IJUMBER j gO N $ #$ &H REQUIRED ~ Ug id $ RE!iARKS 4g >H M > H h6 O H

= 8 gg "8O 6 e D' W B" 4

77-849 2 G-6 AC-ACT 3/4 CK SA - CS, SLT 77-868 2 B-6 AC-ACT 1 CK SA -

CS, SLT 67

Scqusyah Nuclocr PI:nt insarvico Vciva Tcsting Prsgram (77) WASTE DISPOSAL - FLOOR AND EQUIPMENT DRAIt{S ' '

/ DRAWING NO:

0H >< M HO VALVE m 5$" $$ w w

$w b TESTING $M hh NUMBER U

dO N

M > #$H N REQUIRED U$ id $ REMARKS g3 @ @ %

U * *t FCV-77-127 2 F-7 A-ACT 2 DIA DIA 0 QT-1, SLT FCV-77-128 2 F-7 A-ACT 2 DIA DIA 0 QT-1. SLT 68 e

Scqunyah Nuclacr Plant Insarvice Valva Tcsting Prsgram (78) FUEL POOL COOLING 855-1 (0 2)

DRAWING NO:

N $

0H >4 C4 ,

g H0 VALVE to 3$ $ m $m O m 8 TESTING $1 m hU NUM14ER mh U 4O N d" 4$ d N REQUIRED U R$ REMARKS Qg O N N O A 78-557 2 G-8 A-PAS 4 CA H C SLT 78-558 2' G-8 A-PAS 4 GA H C SLT 78-560 2 G-8 A-PAS 6 GA H C SLT 78-561 2 G8 1-PAS 6 CA M C SLT 69 e

Scqusyah Nuclacr Plant Insorvico Valvo Testing Prcgram (81) PRIMARY WATER -

0)

DRAWING NO:

0H ft: H0 VALVE M d$

$$ w $w Nw hb TESTING $M hh IRJMBER 4 0 da >e N {;$ N m

d$

>e 4$

ge $! H o

REQUIRED U o id $

ww REMARKS 8 6 < =8A gW U" O 4 FCV-81-12 2 G-4. A-ACT 3 GA DIA 0 QT-1. SLT 81-502 2 G-4 AC-ACT 3 CK SA - CS, SLT i

70 s

Scqueych Nuclocr PI:nt Insarvico Velvo Tcsting Prsgram

( ) ESEL STARTING A M SYSTEM SYSTEM: DRAWING NO: 47W839-I 0H H M n HO VAINE y U$

$$ m $m Oa h6 TESTING ${ yy hd NUMBER kuj k k" N8

>H N

m d b"

> 4$ O2N h6 H REQUIRED UD g O T4 gy

$ REMARKS "8 6 e "E W g" FCV-82-160 3 C-5 B-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-161 3 C-6 B-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-170 3 C-2 B-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-171 3 C-10 B-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-190 3 C-5 8-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-191 3 C-6 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-2q0 .

3 C-2 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-201 3 C-10 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-220 3 C-5 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-221 3 C-6 8-ACT l-1/2 DIA DIA C QT-1 C)CLED FCV-82-230 3 C-2 B-ACT I-1/2 DIA DIA C QT-1 CYCLED FCV-82-231 3 C-10 B-ACT l-1/2 DIA DIA C QT-1 CYCLED FCV-82-250 3 C-S 8-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-251 3 C-6 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-260 3 C-2 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED FCV-82-261 3 C-10 B-ACT 1-1/2 DIA DIA C QT-1 CYCLED 82-502-1A1 f4NCC G-4 B-ACT 1 1/4 CK SA -

CV-1 82-502-181 NNCC G-4 B-ACT I 1/4 CK SA -

CV-1 71.

t

Scqucych Nuclocr Pl:nt insarvico Velvo Tcsting Prcgram (82) DIESEL STARTING AIR SYSTEM 47W839-1 0 > N ~ 0

, VALVE m U$ o w $u Om O TESTING Dm U IRJM14ER *"

NO <w N d$ 4" 5 REQUIRED U y$

Td REMARKS 4o >H m >H b oH O WW "8o 6 4 " 8a gM S" 4

82-502-2A1 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 82-502-2B1 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 82-529-1A2 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 52-529-182 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 82-5;9-2A2 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 d2-529-282 NNCC G-4 B-ACT 1 1/4 CK SA -

CV-1 I

72

en

< 1 M

E<

2>

~ w t~

$N E e

8v 3

m ASME N CLASS

, a e

DRAWING g Q COORDINATES M W

k VALVE E CATEGORY Z c

O SIZE =

m p VALVE m

m TYPE q ACTUATOR m

3 TYPE _

NORMAL 3 5 ft)

POSITION g 3

m Me <

Y

?$

-s O

e 5"

05 <

m RELIEF REQUEST q ALTERNATIVE m

ft)

TESTING 2.

3 Q

T m

o O 5 C, c

d m

=

3

~ - .

k m

y i

~

23 w

Scqusych Nucirr Plant insarvico Vcivo Tcsting Prsgram (87) UPPER HEAD INJECTION SYSTEN 47W811-2 (R9) s OH > M n 9 HO VALVE M d

"$ $$ w $a $m j6 TESTING bM hM NUMI4ER 4oh NO

> E4 N

to d$

>b 6$

U Ed (d

O H REQUIRED U b O $! $

MW REMARKS "8O 6 W- =8A yW u" 4

FCV-87-7 1 E-3 A-ACT 2 GL DIA C QT-1, SLT SLTP FCV-87-8 1 E-3 A-ACT 2 GL DIA C QT-1. SLT SLTP FCV-u?-9 2 E-4 A-ACT 2 GL DIA C QT-1. SLTP FCV-87-10 2 F-5 B-ACT 3/t c GL DIA C QT-1 FCV-87-11 2 F-5 B-ACT 2 GL DIA C QT-1 FCV-87-21 2 E-6 B-ACT 12 GA CYL 0 QT-1 fCV-87-22 , 2 E-7 B-ACT 12 GA CYL 0 QT-1 ,

FCV-87-23 2 F-6 B-ACT 12 Gt CYL 0 QT-1 FCV-87-24 2 F-7 B-ACT 12 CA CYL 0 QT-1 87-556 2 C-7 C 1-1/2 REL SA C RF 87-557 2 C-10 C 1-1/2 REL SA C RF 87-558 1 E-1 AC-ACT 8 CK SA -

CS, SLTP See PV-11 87-559 1 F-1 AC-ACT 8 CK SA - CS, SLTP See PV-11 87-500 1 F-2 AC-ACT 8 CK SA -

CS, SLTP See PV-11 87-561 1 G-2 AC-ACT 8 CK SA -

CS, SLTP See PV-11 87-562 1 E-4 AC-ACT 12 CK SA -

CS, SLTP See PV-11 87-563 1 F-4 AC-ACT 12 CK SA -

CS, FLTP See PV-11 Rup*ure Disk 2 8-7 0 12 RD SA C RD 74 s

Saqusych Nuclocr PI:nt insarvico Vcivo Tcsting Prcgram (90) RADIATION MONITORING SYSTEM DMWING NO. 47W610-90-3 0 F4 > D: . H0 VALVE m d$ $o ga $a @ ga jo TESTING h h NUMf4ER U

NO U d$ #$ NN REQUIRED U$ $ REMARKS Qg O N N O A <

FCV-90-107 2 A-9 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-108 2 C-9 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-109 2 C-9 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-110 2 C-9 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-111 2 D-9 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-113 2 A-6 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-lj4.. 2 C-5 A-ACT 1-1/2 GA DIA 0 QT-1. SLT :

FCV-90-115 2 C-5 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-116 2 C-5 A-ACT 1-1/2 GA DIA 0 QT-1. SLT FCV-90-117 2 D-6 A-ACT 1-1/: CA DIA 0 QT-1. SLT 75 i

1 PV-1 I

System: -Chemical and Volume Control System i

Valve: 62-525, 62-532 Class: 2 Category: C Function: Opens to admit charging pump flow to the boron injection tank during safety injection.

Impractical Requirement: Exercise valve at full flow on a quarterly basis.

Basis for Relief: The centrifugal charging pumps cannot be run at full flow during operation for charging or through the cold leg injection lines due to undesirable temperature and/or boron concentration transients. CCP cannot be run at full flow during CSD with Rx vessel head in place due to.

the inability to letdown that full flow. This would result in a low temperature overpressurization of the RCS.

Alt.

Testing: Test valve at normal charging flow quarterly and verify that it will open to pass at least the minimum design required flow during each refueling outage.

Frequency for Alt.

Testing: Part stroke quarterly and full stroke at refueling outage.

N 4

t 76 i

,_,-.----,,-...,,,-,-m.-.r--- - - - - - - + - - - - ' -

r w'----w - --- - ---~--wv+-*-r- ' - - - ~ + -- -- w-'

PV-2 System: Chemical and Volume Control System Valve: 62-504 Class: 2 Category: C Function: Opens to admit flow from refueling water storage tank to the centrifugal charging pumps and closes to prevent backflow to RWST during recirculation mode of ECCS.

Impractical Requirement: Exercise quarterly at full flow.

Basis for Relief: Charging pumps cannot be run at full flow taking suction from the RWST without causing undesirable RCS temperature and/or boron concentration changes resulting in boration and power changes and could result in a plant trip. Full flow cannot be obtained during CSD with Rx vessel head in place. (See PV-1).

Alt.

Testing: Exercise at full flow each refueling outage during system performance tests and part stroke at reduced flow during cold shutdown. Verify valve will backseat quarterly.

Frequency for Alt.

Testing: Full stroke once per refueling outage and part stroke during cold shutdowns (but not more often than once every three months). Verify valve will backseat quarterly.

77

.- - - _ . - _ _ . _.. - __.m.

2 a

4 PV-3 System: Safety Injection System Valve: 63-502 Class: 2 Category: C.

Function: Opens to admit flow from RWST to the'RHR pumps during safety injection. Closes to prevent flow to RWST during recirculation mode of ECCS.

Impractical Requirement: Exercise valve quarterly at full flow.

Basis for Relief: The RHR pumps do not develop sufficient head to pump to the reactor at normal operating pressures. The pumps recirculat.on flow path does not include this check valve. The refueling cavity dewatering line cannot he used because the valve alignment required to use it results in degrading both trains of RHR. Capabilities of the CVCS letdown system preclude use during cold

shutdowns. Backseating of 63-502 during power operations would require closure of FCV-63-1 and inoperability of i both trains of low head SIS.

Alt.

Testing: Exercise at full flow each refueling outage during system performance tests. Verify check valve will backseat during cold shutdowns.

Frequency for Alt.

Testing: Full stroke once per refueling outage. Backseat during 1.

cold shutdown (but not more often than once every three months).

1

~78

,. , - - . - - . -%-.-,-------.---.m-- - - - - - - -a- - , . ,---, - - - - -

, , , - - . - - - - - - . . - . . -,,..-_vs.

. - - - -.- .-. . - - . = - - . . - - - . ~ _ _ _ _ - .

i I

1 -

PV-4 System: Safety Injection System Valve: 63-510 Class: B Category: C Function: Opens to admit flow from RWST to the SIS pumps during safety injection.

Impractical ~

Requirement: Exercise valve quarterly at-full flow.

Basis for.

Relief: SIS pumps do not develop sufficient head to pump to the a

RCS at normal operating pressures and the pump recirculation line will not pass full flow. RCS letdown

, capability will not allow pumps to be run at full flow '

4 during cold shutdown.

Alt.

Testing: Exercise valve at reduced flow quarterly during SIS pump test and at full flow each refueling outage during system performance tests.

Frequency for Alt.

Testing: Part stroke quarterly,. full stroke each refueling outage.

f.

i l

I i

79

PV-5 System: Safety Injection System Valve: 63-547, 63-559,63-549, 63-558,63-545, 63-543,63-557, 63-551,63-555, 63-553.

Class: 1 Category: AC Function: Cpens to admit flow from SIS pumps to RCS during LOCA and closes to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow.

Basis for Relief: SIS pumps do not develop sufficient head to overcome normal RCS pressure. Use of another pump would result in an undesirable temperature transient in the RCS. Letdown capability will not allow full flow testing with reactor head on.

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to allow partial stroking of these valves during cold shutdown not to exceed once per nine months and full 1troke exercising during refueling outages.

Valve closure will be verified during cold shutdown, not to exceed once per nine months when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.

Alt.

Testing: Part stroke exercise during cold shutdown and full stroke exercise during refueling outages. Leak test as required by Technical Specification 4.4.6.2.2.

Frequency for Alt.

Testing: Part stroke every cold shutdown not to exceed once per nine months and full otroke each refueling outage. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.

80

PV-6 System: Safety Injection System Valve: 63-581, 63-587,63-588, 63-589,63-586 Class: 1 Category: C Function: Open to admit flow from boron injection tank to the RCS during safety injection.

Impractical Requirement: Exercise' valve on a quarterly basis at full flow.

Basis for Relief: RCS letdown capacity will not allow full flow injection with the reactor vessel head on. Valve cannot be part stroked without discharging heavily borated water from the boron injection tank to the reactor. This would cause undesirable temperature and boron concentration transients which could result in a safety injection or unit trip. If the BIT and injection lines are not flushed completely to the vessel, boron plateout will occur in the non heat-traced portion of the injection lines. The last 4 valves are in parallel and individual branch line flows are only measured during refueling testing since instrumentation is not available to measure the individual branch. flows.

Alt.

Testing: Part stroke valve (63-581) during cold shutdown and exercise valve at full flow each refueling outage during system performance tests. Part stroke the combination of parallel valves (63-586, 587, 588, 589) during CSD and full stroke each refueling outage during system performance tests.

Frequency for Alt.

Testing: Part stroke valve during cold shutdown (but not more often than every three months), full stroke each refueling outage.

81

E t

1 -

l PV-7 l

4 System: Safety Injection System 4

Valve: 63-622, 63-623,63-624, 63-625 i Class: 1

) category: AC

Function: Opens to admit flow from cold leg accumulators to the RCS 4

' during safety injection and closes to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow

, Basis for Relief:

These VLives cannot be exercised at full flow without removing the fuel from the core, removing the internals package and causing a rapid depressurization of the RCS

) from above 650 psig to atmospheric pressure. This is an unreasonable burden and could cause damage to the reactor vessel.

I Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to i

^

allow partial stroking of these valves during cold shutdown not to exceed once per nine months, so as not to impose additional leak testing requirements.

Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure j isolation boundary leak test required by 4.4.6.2.2 is performed.

I 1

l l

1 82

Alt.

Disassemble and inspect one (1) valve each refueling

~

Testing:

outage on a rotating basis. If any valve is'found to be inoperable and the cause determined to be potentially generic, then the remaining three valves will also be disassembled and inspected prior to declaring the valves operable.

Part stroke exercise using sis or RHR pump and CV test system during CSDs.

Verify valve closure when the pressure isolation boundary leak test required by SR 4.4.6.2.2 is performed.

Frequency for Alt.

Testing: Disassemble and inspect one valve each refueling outage.

Part stroke during CSD not to exceed once per nine months. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.

83

. = - . - _ - - . .. -. _- - .

i i

I

.e

~

] PV-8 System: Safety Injection System Valve: 63-632, 63-633,63-634, 63-635,63-640, 63-641,63-643, j 63-644 Class: 1 Category: AC Function: Opens to admit flow from RHR pumps to RCS during LOCA and closes to prevent intersystem LOCA.

Impractical i - Requirement: Exercise quarterly at full flow.

Basis for Relief: RHR pumps do not develop sufficient head to overcome normal RCS pressure. Use of another pump would result in an undesirable temperature transient in the RCS and possible reactor trip.

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to i

allow full stroking these valves during cold shutdown not to exceed once per nine months.

Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.

Alt.

Testing: Full stroke exercise during cold shutdown. Leak test as required by Technical Specification 4.4.6.2.2.

Frequency for Alt 4

Testing: Full stroke exercise during cold shutdown not to exceed once per nine months. Leak test at frequencies required by Technical Specification 4.4.6.2.2.

84

~ ~ . , - - --m- g-.m,, .m.,- mm.--,,,,,.,..e, , , , - , - - - _n,,,,_,,,,,.,p. - , - , _, m e n y_,- -,--_w,e- ,- c- . - .., --- - ,- - - , -

PV-9 System: Auxiliary Feedwater Valve: 3-805, 3-806, 3-810, 3-891, 3-892 Class: 3 Category: C Function: 3-805, 3-806, and 3-810 open to admit auxiliary feedwater flow the auxiliary feedwater pumps: they also close when

'the ERCW is aligned to the auxiliary feedwater pump suction. 3-891 and 3-892 open to admit steam flow to the turbine driven auxiliary feedwater pump.

Impractical Requirement: Exercise valve quarterly at full flow.

Basis for Relief: Exercising these valves cturing power operation could result in severe thermal shock to the auxiliary feedwater nozzles and cause SG 1evel transients and a unit trip.

Alt.

Testing: These valves will be part stroked during the associated pump test and full stroked during hot standby not to exceed once per three months. 3-805, 3-806, and 3-810 will be backseated quarterly.

Frequency for Alt.

Testing: Part stroke quarterly and full stroke during HSB not to exceed once per three months. Backseat 3-805, 3-806 and 3-810 quarterly.

85

I L

1 l

PV-10 System: Containment Spray Valve: 72-547, 72-548, 72-555, 72-556 i

i Class: 2 Category: C Function: . Opens to admit flow from the containment spray and RHR pumps to the spray headers.

Impractical Requirement: Exercise quarterly at full flow.

Basis for Relief: Testing these valves with water would deluge the containment. Testing with air could cause an SI, unit trip and containment isolation signal from high containment pressure.

j Alt.

Testing: Disassemble and inspect one (1) valve each refueling outage, on a rotating basis. If any valve is found to be inoperable and the cause determined to be potentially a generic, then the remaining three valves will also be j

disassembled and inspected prior to declaring the valves operable.

Frequency for Alt.

Testing: Disassemble and inspect one valve each refueling outage.

i i

l 1

4 86 I

4

PV-ll System: Upper Head Injection System Valve: 87-558, 87-559,87-560, 87-561,87-562, 87-563 Class: 1 Category: AC Function: Opens to admit upper head injection fluid to reactor vessel during rapid depressurization (LOCA).

Impractical Requirement: Exercise quarterly at full flow.

Basis for ~

Relief: Plant was not designed to allow full flow inservice testing. To test at full flow it would be necessary at minimum to remove all fuel, remove reactor internals, install a temporary impingement plate and drain the reactor coolant system. The resultant extended down time due to additional fuel movement, storage problems, water chemistry cleanup and refill operations presents an unbearable operational burden.

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. Therefore, relief is requested to allow partial stroking of these valves during cold shutdown not to exceed once per nine months so as not to impose additional leak testing requirements.

l l

87

1 i

~

Alt.

Testing: Manually stroke all 8" CVs each refueling outage.

Disassemble and inspect one 12" CV each refueling outage, on a rotating basis. If any 12" valve is found to be inoperable and the cause is determined to be potentially generic, then the remaining 12" CV will also be disassembled and inspected prior to declaring the valves operable.

Part stroke exercise during CSD.

Verify valve closure when the pressure isolation boundary leak test required by SR 4.4.6.2.2 is performed.

Frequency for Alt.

Testing: Manually stroke all 8" CVs each refueling outage.

Disassemble and inspect one 12" CV-each refueling outage. Part stroke during CSD, not to exeed once per nine months. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.

i i

t 88

PV-12 System: Auxiliary Feedwater Valve: 3-820, 3-821, 3-830, 3-831, 3-832, 3-833, 3-861, 3-862, 3-864, 3-871, 3-872, 3-873, 3-874, 3-921, 3-922 Class: 3 Category: C Function: Opens to admit flow to steam generators.

Impractical Requirement: Exercise quarterly at full flow.

Basis for Relief: Exercising these valves during power operation could result in severe thermal shock to the auxiliary feedwater nozzles and cause SG level transients and a unit trip.

These valves are routinely operated during operation of the auxiliary feedwater system during hot standby.

Alt.

Testing: Full flow will be verified through these checks during HSB not to exceed once per three months.

Frequency for Alt.

Testing: HSB not to exceed once per three months.

89

PV-13 System: Safety Injection System Valve: 63-524, 53-526 Class: 2 Category: C Function: Opens to admit flow from SIS pumps to RCS during LOCA.

Impractical Requirement: Exercise quarterly at full flow.

Basis for Relief: SIS pumps do not develop sufficient head to pump to the RCS during normal operation.

Alt.

Testing: Part stroke valves during cold shutdown and full stroke exercise velves during refueling outage. Verify valve closure quarterly during pump test.

Frequency for Alt.

Testing: Verify closed quarterly, part stroke during cold shutdown not to exceed once per nine months and full stroke during refueling outages.

f 90

PV-14 System: Reactor Coolant System .

Valvo: PCV-68-340A, PCV-68-334 Class: 1 Category: B - Active Function: Provide pressurizer pressure relief capability in addition to safety relief valves. Provide cold overpressurization protection.

Impractical Requirement: Observe visually every two years to verify remote valve indications accurately reflect valve operation.

Basis for Relief: The previous globe type, diaphragm actuated PORVs have been replced by new, faster acting globe type, solenoid actuated valves; the new valves are totally enclosed, preventing visual determination of valve position.

Alternate Testing: Observe PORV discharge line temperature before and after remote stroking of valve during cold shutdown (at sufficient temperature and pressure to effect a blowdown). Verify remote valve position indications with appropriate increase and decrease of temperature.

Frequency for Alternate Testing: At same frequency as sJheduled refueling outages, but not less than once every two years.

91

PV-15 System: Post Accident Sampling Valve: FSV-43-250, FSV-43-251, FSV-43-287, FSV-43-288, FSV-43-307, FSV-43-309, PSV-43-310, FSV-43-317, FSV-43-318, FSV-43-319, FSV-43-325, FSV-43-341 Class: 2 Category: A - Active Eunction: To permit reactor coolant system sampling in a post accident condition.

Impracti:a1 Requirement: Observe valve movement every two years to verify remote valve indicators accurately reflect valve operation.

Basis for Relief: These solenoid actuated valves are totally enclosed and valve position cannot be determined visually.

Alternate Testing: Pressure indicators will be used to independently verify valve operation.

Frequency for Alt.

Testing: Every 2 years.

92

PV-16 System: Safety Injection System Valve: 63-560, 63-561,63-562, 63-563 Class: 1 Category: AC Function: Opens to admit flow from cold leg accumulators, safety injection pumps, and RHR pumps to the RCS cold legs during safety injection and close to prevent intersystem LOCA. - - -

Impractical Requirement: Exercise quarterly at full flow Basis for Relief: These valves cannot be exercised at full flow without removing the fuel from the core, removing the internals package and causing a rapid depressurization of the RCS.

This is an unreasonable burden and coald cause damage to the reactor vessel.

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during CSD if they have not been leak tested in the last nine months. Therefore, relief is raquested to allow partial stroking of these valves during CSD not to exceed once per nine months so as not to impose additional leak testing requirements.

93

1 i

Alt.

Testing: Disassemble and inspect one valve each refueling outage on a rotating basis. If any valve is found to be inoperable and the cause is determined to be potentially generic, then the remaining three valves will also be disassembled and inspected prior to declaring the valves operable.

Part stroke exercise using Fuut pump during CSDs.

Verify valve closure when the pressure isolation l boundary leak test required by SR 4.4.6.2.2 is performed.

Frequency for Alt.

Testing: Disassemble and inspect one valve each refueling outage.

Part stroke during CSD not to exceed once per nine months. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.

l l

94

,4-

- -- -- +a-- e- -_ _-_i*+_e-=.--M4--1---2 4l.AhmA2d= -ae 42-4-.u b-*hha MheA--+. -- - *" ---_ - -,-->-

i I

s .

PV-17 l

System: Reactor Ceolant System Valve: 68-559 Class: 2 Category: C i Function: Opens to admit SIS and CS relief valve discharge to the PRT.

Impractical Requirement: Exercise quarterly at full flow, a

Basis for Relief: Full flow exercising, by definition, is not possible due i

to the nature of the system. Partial stroke exercising would present unacceptable personnel hazards unless all j interacting systems were removed from service; these

.; systems include RCS,' CVCS charging / seal flow / letdown, RHR, SIS and CS systems. Removal from service of.the affected systems would required entry into LCO's and an overall degraded plant condition, regardless of operating mode. Plant operating experience has shown that this CV does function to provide release to the PRT as indicated by PRT temperature, pressure and level increases.

Alt.

Testing: None ,

L Frequency

, for Alt.

Testing: N/A i

95

1 l

l f

t PV-18 i System: Reactor Coolant System Valve: FSV-68-394, FSV-68-395, FSV-68-396, FSV-68-397 4

Class: 2 Category: B 5

Function: Opens to provide reactor vessel head vent path; to vent

, non-condensibles from head during an accident to promote natural circulation and prevent gases from impeding reactor coolant circulation flow through the core, Impractical Requirement: Exercise valve quarterly. Observe visually every two years to verify remote valve indications accurately reflect valve operation.

i Basis for i Relief: These valves are Target Rock valves (similar to the pressurizer PORVs) and have shown a high probability of sticking open. Inappropriate or inadvertent operation of this system (resulting from valves sticking open) could 1

create an unanalyzed condition or worsen the severity of

! an analyzed faulted condition. Due to the risk of stroking these valves, the licensee requests relief to ,

exercise these valves at refueling outages only, the same frequency as proposed for future technical specification i surveillance testing.

These valves are totally enclosed, preventing visual .

I confirmation of valve position.

2 96

Alt..

Testing: Exercise at refueling outages.

Observe downstream temperature following actuation of FSV-68-394 and FSV-68-3956 Observe changes in PRT temperature / pressure / level following actuation of FSV-68-396 and FSV-68-397; or use accoustic emissions equipment to verify indicated position of FSV-68-396 and FSV-68-397.

Frequency for Alt.

Testing: Every refueling outage 97

a l

4 APPENDIX D I

VALVES TESTED ONLY DURING COLD SHUTDOWN CONDITIONS I Valves listed in Table D-1 are therein specifically identified by the j Licensee as valves which cannot be exercised during power operation, per Section XI, Article IWV-3412(a). The table lists the System, Valve Number, and the basis for cold shutdown. testing for each valve listed in appendix C l.

which is being tested on a cold shutdown frequency.

! Table D-1 System Valve Basis for Cold Shutdown Testing Main Steam FCV-1-4 Full stroke exercising of these valves FCV-1-ll during operation could cause SG 1evel FCV-1-22 transients which could result in a plant trip.

FCV-1-29 These valves will be part stroke exercised quarterly and full stroke exercised during cold shutdown.

Main Steam FCV-1-17 Closing these valves during power operation a FCV-1-18 causes a loss of steam to the steam driven auxiliary feedwater pump. Failure in the j closed position will result in no heat sink for the loss of all AC power accident.

i i Main Steam PCV-1-5 Opening valve during power operation will cause PCV-1-12 a steam generator level transient which could i

PCV-1-23 result in an inadvertent safety injection signal PCV-1-30 and/or plant trip.

Feedwater FCV-3-33 Exercising these valves during power operation FCV-3-47 causes a loss of feedwater to the loop they 4 FCV-3-87 supply. When feedwater flow is restored, the FCV-3-100 resulting SG level shrink could cause a reactor FCV-3-508 trip.

FCV-3-509 FCV-3-510 l FCV-3-511 i

I i

4 98 l

Table D-1 (continued) ,

Sys' tem Valve 'I ~ ' Basis for' Cold Shutdown Testing Compressed Air FCV-32-80 Exercising these valves during operations FCV-32-81 results in a loss of control air to control FCV-32-102 valves inside containment and could result FCV-32-103 in valves going to their failed position and FCV-32-110 resulting in a unit trip.

FCV-32-lll FCV-32-287 FCV-32-297 FCV-32-377 FCV-32-348 FCV-32-358 FCV-32-387 Post FSV-43-250 Testing at power would require entry into LCO Accident -FSV-43-251 3.6.1.1 and a degraded plant condition since Sampling ~FSV-43-287 these FSVs do not receive a containment FSV-43-288 isolation signal.

FSV-43-307 FSV-43-309 FSV-43-310 FSV-43-317 FSV-43-318 FSV-43-319 FSV-43-325 FSV-43-341 Chemical and FCV-62-61 Exercising valves during operation would cause Volume Control FCV-62-63 loss of seal water return and probable damage System to the reactor coolant pump seals.

Chemical and FCV-62-98 Exercising valves during operation results in Volume Control FCV-62-99 isolation of the miniflow path of the centri-System fugal charging pumps and could result in pump damage.

Chemical and FCV-62-132 Stroking these valves during power operation Volume Control FCV-62-133 would cause unacceptable boron transients System LCV-62-135 causing RCS boration and power transients LCV-62-136 which could result in a unit trip.

Safety Injection FCV-63-1 Exercising valve during operation results in System losing suction from RWST to both trains of residual heat removal.

99

.. . _ . . _ _ . . . . . = - . - . _ ~ _ _ - _ _ _ - - - __

Trable D-1 (continued) ..

j System Valve Basis for Cold Shutdown Testing Safety FCV-63-3 Exercising valve during operation results in Injection isolating the recirculation line to both System trains of. pumps. If the pumps started without recirculation,' severe damage to both pumps could occur.

Safety Injection FCV-63-5 Exercising the. valve during operation isolates System both SIS pump suction lines from the refueling water storage tank.

I Safety FCV-63-22 Exercising valve quarterly isolates both trains Injection of safety injection from their normal flow path 4- System to the cold legs.

1 Safety FCV-63-72 These valves are asscciated with the containment Injection FCV-63-73 sump and their operation during power operation System FCV-63-8 could cause flooding of lower containment or FCV-63-ll would result in inoperability of both trains of low head safety injection. FCV-63-8 and -11 are interlocked with FCV-63-72 and -73.

Safety FCV-63-93 Closing these valves during operation results Injection FCV-63-94 'in less than the required number of RHR cold System leg injection flow. paths operable.

Safety 63-510 Exercising (backseating) this valve during Injection- operation isolates both SIS pump suction lines

. System from the refueling water storage tank.

Safety 63-570 Exercising (backseating) this. valve during Injection power operation could cause unacceptable boron System concentration changes in the boron injection tank as the continuous recirculation of the tank would have to be stopped and stratification would. occur.

1 4

100

Table D-1 (continued) -

System Valve Basis for Cold Shutdown Testing Safety 63-563 These valves are in the residual heat removal Injection 63-560 pump injection lines.and the RHR pumps do not System 63-561 develop sufficient head to open the valves63-562 during operation. Injection through these 63-635 lines using another pump would result ~in 63-633 overpressurization of the RHR lines behind the 63-632 check valves and cause an undesirable 63-634 temperature transient in the RCS which would 63-640 cause a safety injection.63-641 63-643 63-644 Safety FCV-63-172 Closing or opening these valves during Injection and FCV-74-33 operations results in the inoperability of the Residual Heat FCV-74-35 cold leg injection path to provide its required Removal System flow rate (common mode failure).

Essential Raw FCV-67-83 Exercising valve quarterly causes a loss of Cooling Water FCV-67-87 flow to control rod drive coolers and reactor System FCV-67-88 coolant pump motor coolers.

FCV-67-91 FCV-67-95 FCV-67-96 FCV-67-99 FCV-67-103 FCV-67-104 FCV-67-lll FCV-67-107 FCV-67-112 Essential Raw FCV-67-146 Failure of this valve in the closed position Cooling Water would result in loss of cooling to the RCP oil System cooler, thermal barriers and seal HTXs.

Essential Raw FCV-67-562A These valves normally pass water to the Cooling Water FCV-67-562B control rod drive coolers and the reactor System FCV-67-562C coolant pump motor coolers. Exercising the FCV-67-562D valve causes a loss of flow to this equipment.

. Reactor PCV-68-340A NRC has requested that the pressurizer PORVs Coolant PCV-68-334 be tested during cold shutdown rather than System during power operation.

101

Table D-1 (continued) ..

System Valve Basis for Cold Shutdown Testing Reactor FCV-68-394 Stroking these valves at power could result Head Vent FCV-68-395 in depressurization of the RCS and resulting System FCV-68-396 unit trip and safety injection. Failure of FCV-68-397 these valves open could result in a LOCA.

Component- FCV-70-134 Exercising valves during operation results in Cooling FCV-70-87 loss of cooling water flow to all four reactor System FCV-70-90 coolant pump thermal barrier coolers introducing the possibility of seal failure, loss of a RCP and a LOCA or a unit trip.

Component FCV-70-140 Exercising valve during operation results Cooling FCV-70-92 in loss of cooling water flow to all eight System FCV-70-89 _ reactor coolant pump oil coolers.

Component 70-679 This valve normally passes water to the Cooling thermal barrier coolers. Removal from System service for testing will cause a loss of flow to all four thermal barrier coolers; thus, introducing the possibility of seal failure on the reactor coolant pumps upon loss of normal seal flow causing a LOCA or unit trip.

Component 70-692 This valve normally passes flow to the reaccor Cooling coolant pump oil cooler. Removal from service System for testing while reactor coolant pumps are running will result in overheating and subsequent loss of all four reactor coolant pumps and a unit trip.

Containment FCV-72-40 These valves are interlocked with the Spray System FCV-72-41 containment sump valves. Exercising these valves during operations could result in flooding of lower containment or would result in inoperability of both trains of low head safety injection.

Residual Heat FCV-74-1 Valves have interlocks to prevent opening Removal FCV-74-2 them when RCS is above the RHR design temperature and prescure. Exercising valve during operation results in overpressurizing RHR.

102

d Table D-1 (continued) ..

System Valve Basis for Cold Shutdown Testing Residual Heat 74-514 These valves cannot be full stroked quarterly Removal 74-515 since the RHR pumps do not develop enough pressure to overcome normal RCS pressure. The refueling dewatering lineocannot be used because opening HCV-74-34 would cause degradation of both trains of RHR. These valves will be part stroked quarterly during the pump test and full stroked during cold shutdown, but not to exceed once per three months.

Reactor 77-868 Cycling these valves during power operation Coolant System 77-849 shuts down nitrogen supply inside containment to a number of components and systems.,

Personnel radiation exposure and valve

, inaccessibility also prohibits quarterly exercising of these valves.

Primary Water 81-502 Exercising this valve results in loss of System primary water to the RCP stand pipes and PRT.

Personnel radiation exposures and valve inaccessibility also prohibits exercising these valves quarterly.

Upper Head 87-358/559 Exercising these valves during power operation Injection 87-560/561 would necessitate removal of both trains of 87-562/563 Upper Head Injection from service to prevent overpressurization of UHI during the test. The test flow path would require charging flow to be distributed to the UHI check valve test line which would present severe thermal shock problems. Injection of this cold charging flow into the reactor vessel head results in a positive reactivity addition and a power transient will probably result in a unit trip.

103 l

i APPENDIX E SEQUOYAH NUCLEAR PUWT VALVE PROGRAM CATEGORY B-PASSIVE VALVES Summary of Information Provided The following tables list all safety related B-passive valves; there are no Section XI testing requirements for B-passive valves. Category E valves for unit 1 are also included and identified accordingly. The format referenced in the 1978 "NRC Staff Guidance for Preparing Pump and Valve Test Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)" was used to give valve descriptions. The following information is provided:

1. System Name and Number

2. Drawing Number

3. Valve Number

4. ASME Section XI Classification or NNCC (Non Nuclear Code Class)

5. Drawing Coordinates of Valve

6. Valve Category Per Section XI, Article IWV-2110

7. Valve Size.

8. Valve Type

9. Actuator Type

10. Normal Position

11. Testing Required Per Section XI

12. Relief Request Required

13. Alternate Testing

14. Remarks (including Relief Request Numbers, Specific Valve Data, etc.)~

104

Scqusych Nuclocr Plznt Insarvico Valvo Tcsting Prsgrcm

( " " ^" 4 80 N SYSTEM: DRAWING NO:

oe 13

>. m 9

-o VALVE M

$$ $ga O ga TESTING $

3so hU

U $ L2 h

Nunnes !3 #"2 4 0 W la

>e N

w 2s

>e 4m oeM ge s neguinto a t; ww annAnxS "8U 6 < "8A gM U" .

l-1-532 2 G-4 E 2 GL M LC None 2-1-532 2 G-4 B-PAS 2 GL M LC None '

1-1-534 2 E-4 E 2 GL M LC None 2-1-534 2 E-4 B-PAS 2 GL M LC None 1-1-536 2 C -4 E 2 GL M LC None 2-1 536 2 C-4 B-PAS 2 GL M LC None 1-1-538 , , 2 A-4 E 2 GL M LC None ,

2-1-538 2 A-4 B-PAS 2 GL M LC None 105 8

a N

O S

K R

A 0 M

E O R N

m G a

r N

I W

g A R

e r

D P

g i

n odgs t

c Wy u4 o

T b ,W o

v DUM l

a V GD NE o I R TI SU i

c EQ e u TE r

v R N

n o

N c

o a _6 8N 6

0 s 1 i

n o= 0 0 t a g

n :Q<!

a i

c M H P y r y A A c G G l

o a g

2" c 2 1 1 u S S N uo 6 A P

A P

B B h

c y Ns@ 8U s od "

2 G

3 G

u q ) C C e U C rJ C

N S N N ER VE

LB A M VU .

M N E

T 4 5 S 0 0 Y 5 5 S 2 2

S;qusych Nuclocr Plcnt Insarvico Valva Tcsting Prsgrcm SYSTEM:

(' "^ "

DRAWING NO:

47wa03-1 O N OP W 0: H O VALVE M d$ $$ w $a Ow %o~ TESTING $M hU NUMBER m 4 0 na dO

>H N

m N$

>e 4$ 's ge oMH "8A REQUIIED U o gW ix! $

ww REMARKS "8O 6 < U" 4

1-3-513 2 G-3 'E 1 1/; GL H LC None 1-3-517 2 E-3 E 1 1/; GL H LC None 1 3 521 2 D-3 E 1 1/. GL H LC None 1-3-609 2 C-3 E 2 GL H LC None 2-3-609 2 C-3 8-PAS 2 GL H LC None 1-3-610 2 E-3 E 2 GL M LC None 2-3-610 , .. 2 E-3 B-PAS 2 GL H LC None ,

1-3-611 2 G-3 E 2 GL M LC None 2-3-611 2 G-3 B-PAS 2 GL H LC None 1 3-612 2 B-3 E 2 GL M LC None 2-3-612 2 B-3 B-PAS 2 GL H LC None

107

i

Saqusych Nuclacr Picnt inscrvico Valva Tcsting Prsgram g (3) AUXILIARY FEEDWATER 47W803-2 DRAWING NO:

N OP >e N H0 VAINE m d$

" $$ w $w Ow hb TESTING $1 h3 NUMBER m "OP N d*

>b 4$b 74 H5 REQUIRED U id $ REMARKS 4 9 8 6 W O

" 8A y9L b MM U

4 B" 4

3-800 NNCC B-4 8-PAS 16" GA H 0 None 1-3-803 NNCC E-S B-PAS 8" GA H 0 None 2-3-803 NNCC D-5 8-PAS 8" CA H 0 None 1-3-804 NNCC F-6 8-PAS 8" GA H 0 None 2-3-804 NNCC D-6 B-PAS 8" GA H 0 None 1-3-809 NNCC F-4 B-PAS 10" GA H 0 None 2-3-809 , .

NNCC B-4 B-PAS 10" GA H 0 None i 1-3-816 NNCC F-5 E 1 1/: CL M LO None 2-3-816 NNCC F-5 B-PAS 1 1/: GL M LO None

/

1-3-817 NNCC F-6 E 1 1/; GL M LO None 2-3-817 NNCC F-6 B-PAS 1 1/: GL M LO None 1-3-819 NNCC B-7 E 1 1/: GL M LO None 2-3-819 NNCC B-7 B-PAS 1 1/: GL M LO None 1-3-826 3 F-3 E 4 GA H LO None 2-3-826 3 F-3 B-PAS 4 GA H LO None 1-3-827 3 E-3 E 4 GA H LO Hone 2-3-827 3 E-3 B-PAS 4 GA H LO None 109 e

, Saqusych Nuclocr PI:nt Insarvico Valvo Tcsting Prcgram gg (3) AUXILIARY FEE 0 WATER 47W803-2 DRAWING NO.

N $

08 > N ~ HO VALVE M U$

" $o m $m On3 hO TESTING $gy hU NUMBER

<o k NO

>H N

m d$ #$B O$N

>B H REQUIRED UDO TdN REMARKS ag ga WM 6 < =s ge 1-3-828 3 C-3 E 4 GA H LO None 2-3-828 3 C-3 B-PAS 4 GA H LO None 1 3-629 3 B-3 E 4 GA H LO None 2-3-829 3 B-3 B-PAS 4 GA H LO None 1-3-834 2 F-3 E 4 GA H LO None 2-3-834 2 F-3 b-PAS 4 GA H LO None 1 3 H35 , . 2 E -- 3 E 4 GA H LO None i 2 3 835 2 E-3 B-PAS 4 CA H LO None 1-3-336 2 C-3 E 4 GA H LO None 2-3-836 2 C-3 B-PAS 4 GA H LO None 1-3-637 2 B-3 E 4 GA H LO None 2-3-837 2 B-3 B-PAS 4 GA H LO None 1-3 d67 3 F-3 E 4 GA H LO N3ne 2-3-867 3 F-3 B-PAS 4 GA H LO None 1-3-868 3 0-3 E 4 GA H LO None 2-3-868 3 0-3 B-PAS 4 GA H LO None 1-3-869 3 C-3 E 4 GA H LO None 2-3-869 3 C-3 B-PAS 4 GA H LO None 109

?

Scqusych Nuclacr PI:nt Insarvico Velvo Tcsting Program (3) AUXILIARY FEEDWATER 03-2 DRAWIt4G 140:

N $

0H N (C g H0 VALVE M d$ $$

" w $w Ow hb TESTI!JG $y hU IJUMBER NO

>H

,N d" m >$ #$H O2H REQUIRED "a g R$ REMARKS 4 9 ag 6 < =g ga geWW 1-3-870 3 A-3 E 4 GA H LO None 2-3-870 3 A-3 B-PAS 4 GA H LO None 1-3-875 2 F-3 E 4 GA H LO None 2-3-875 2 F-3 8-PAS 4 GA H LO None 1-3-876 2 D-3 E 4 GA H LO None 2-3-876 2 D-3 B-PAS 4 GA H LO teone 1-3 877 , .. 2 C-3 E 4 GA H LO None ,

2-3-877 2 C-3 8-PAS 4 GA H LO None 1-3-878 2 A-3 E 4 GA H LO None 2-3-878 2 A-3 B-PAS 4 GA H LO None 3-923 NNCC B-7 E 3" GA H LO None 3-927 NNCC B-C E 3" GA H LO None 110 e

Scqusych Nuclacr PI:nt insarvico Volvo Tcsting Pragram (62) CHEMICAL AND VOLUME CONTROL SYSTEM' 47W809-1 D MWING NO: _

o de- p: o VALVE M d$ $$ ga $ ga O ra b TESTING $m hM NUMBER U

O N d$ 4$ g4 5 REQUIRED U T:! $ REMARKS og O Ny $

0 A 62-509 2 G-10 B-PAS 6" GA H 0 None 62-510 2 G-10 B-PAS 6" GA H 0 None 62-527 2 G-8 B-PAS 4" GA H 0 None 62-533 2 G-8 B-PAS 4" GA H 0 None 62-535 2 F-8 B-PAS 3" GL M 0 None 62-536 2 F-d B-Pn3 3" GL M 0 None 62-537 , . 2 D-8 B-PAS 3" GL M 0 None i 62 539 NNCC D-8 B-PAS 3" GL H 0 None 62-696 NNCC E-10 B-PAS 2" GA H 0 None ill e

S;quayah Nuclocr Picnt Insarvico Valvo Tcsting Prsgram g (62) CHEMICAL AND VOLUME CONTROL SYSTEM 47W809-2 Dr4 WING NO, 0H

$ h H M HO VALVE y 6$ $$

w $w 0m jO TESTING $ $d NUMBER Au j

k k" >H NO' N m

d$

>H 4

h a$ O2HH REQUIRED U O id $

gg REMARKS "8O 6 W = 8A W u" 4

62-927 2 A-3' B-PAS 1" GA H 0 None 62-929 2 A-3 B-PAS 1" GA H C None 62-936 NNCC C-2 B-PAS 2" GA H C None l

112 e

S:qusych Nucirr PI:nt Insarvico Vcivo Tcsting Pr:2 gram SYSTEM- (62) CHEHICAL AND VOLUME CONTROL SYSTEM 47W809-5 DMWING NO.

oe n N u a: -o VAI,Ve y d$

" $$ w $ga @ ra h TESTING hU nunnen ms 22 ea n m,d"D de aM neournto $so n at; nen m S

<o >e > ge o- gW wm "8O 6 < =8A D" 1-62-1047 2 H-6 B-PAS 2" GA H C None 2 52-1047 2 H-5 B-PAS 2" GA H C N o.'a 1-62-1048A 2 H-7 B-PAS 3" GA H C None 2 62-1048A 2 H-4 B-PAS 3" GA H C .Nono 1-62-10 deb 2 H-6 B-PAS 3" GA H 0 None 2-62-1048B 2 H5 B PAS 3" GA H 0 Nonc l-62-1049

2 H-8 B-PAS 3" GA M D None i 2-62-1049 2 H-3 B-PAS 3" GA H O None H

0-62-1049 2 H-5 B-PAS 3" GA N O None 1-62-1050A 2 H-7 B-PAS 3" GA H 0 None 2-62-1050A 2 H-4 B-PAS 3" GA H 0 None 1-62-1050B 2 G-6 B-?AS 3" GA H 0 None 2 62-10508 2 G-4 B-PAS 3" GA H 0 None 1-62-1051A 2 G-7 B-PAS 2" GA H C None 2-62-1051A 2 G-4 B-PAS 2" GA H C None 1-62-1051B 2 G-6 B-PAL 2" GA H C None 2-62-1051B 2 G-4 B-PAS 2" GA H C None

/

113 i

Scquoych Nuclocr Plant Insarvico Vciva Tcsting Pragram gyg (62) CHEMICAL AND VOLUHE CONTROL SYSTEM 47W809-5 DMWING NO.

a W oe u m _ y so VALVE M $ $$ m $m 'Om hO TESTING $! y hh Nunnen m3 M "a da

,nw d 4m &s M nrouInto 3oo k0; nenAnxs 4 0 >e >e ge =8 o

gW ww 8

U 6 < 4 U" 4

1-62-1053A 2 F-7 B-PAS 2" GA H 0 None 2-62-1053A 2 F-4 B-PAS 2" GA H 0 None 1-62-1053B 2 F-6 B-PAS 2" GA H C None 2-62-1053B 2 F-4 B-PAS 2" GA H C None 1-62-1054A 2 F-7 B-PAS 2" GA H 0 None 2-62-1054A 2 F-4 B-PAS 2" GA H 0 None 1-62-10598 . 2 F-6 B-PAS 2" GA H 0 None i 2-62-1054B 2 F-5 B-PAS 2" GA H 0 None 1-c2-1055A 2 E-7 B-PAS 2" GA H 0 None 2-62-1055A 2 E-4 B-PAS 2" GA N O None 1-62-10558 2 E-7 B-PAS 2" GA H C None 2 62-1055B 2 E-4 B-PAS 2" GA H C None 1-62-1057 2 D-6 B-PAS 3/4* GA H 0 None 2-62-1057 2 D-3 B-PAS 3/4* GA H 0 None 0-62-1057 2 D-5 B-PAS 3/4' GA H 0 None 1-62-1059 2 E-10 B-PAS 1" GA H 0 None 2-62-1059 2 E-1 B-PAS 1" GA H 0 None 114 s

Scqucych Nucbar Plant insarvico Vcivo Tcsting Prsgram (62) CHEMICAL AND VOLUME CONTROL SYSTEM 47W809-5 g

/

0 f* >+ C4 , H0 VALVE m 3$ $ o" ga ygg @ ga jo TESTING $ hU NUMBER mhU NO N d_

4$ 2N REQUIRED U R$ REMARKS Qg O N E O A 1-62-1060 2 F-9 B-PAS 2" GA H 0 None 2-62-1060 2 F-2 B-PAS 2" GA M 0 None 1-62-1061 2 F-9 B-PAS 2" GA H 0 None 2-62-1061 2 F-2 B-PAS 2" GA H 0 None 115 e

Saqusych Nuclocr Plant insarvico Vcivo Tcsting Prcgram (63) SAFETY INJECTION SYSTEM 811-1 DRAWING NO:

0H >< tG n HO VALVE m $$ o a $m @m 4"

o TESTING $b hd NUMBER 4 9 *". >gH5 N m

d*

>b b d O H REQUIRED UO g id $

gg REMARKS "8U 6 < " 8A W U" I

4 FCV-63-67 2 B-6 B-PAS 10 GA M0 O None FCV-63-80 2 B-4 B-PAS 10 GA MO O None FCV-63-98 2 B-3 B-PAS 10 GA HO O None FCV-63-118 2 B-1 B-PAS 10 GA H0 0 None 1-o3-525 2 E-8 E 4 GA H LO None 1-63-527 2 D-8 E 4 GA H LO None 1-63-531, . 2 E-10 E 4 GA H L0 None ,

1-63-564 2 B-9 E 1 GA H LO None 1-63-697 2 B-9 E 1 GA H LC None 2-63-525 2 E-8 B-PAS 4 GA H LO None 2-63-527 2 D-8 B-PAS 4 GA H LO None 2-63-531 2 E-10 B-PAS 4 GA H LO None 2-63-564 2 B-9 B-PAS I GA H Lo None 2-63-697 2 B-9 B-PAS 1 GA H LC None 116 i

Scquaych Nuclocr Plznt Insarvico Vciva Tcsting Prsgram (67) ESSENTIAL RAW COOLING WATER 47W845-1 (R16) g ,gygg g I

0H >< CG H0 VALVE to U$

" $ m $u @m kb TESTING d h$

NUMBER gO N d" #"

kH REQUIRED D to 4 9 kk H tes >b hb O H g O U, k Td yy

$ REMARKS 8

U

>6 W "8" U" 4

FCV-67-12 3 E-1 B-PAS 36 BUT M0 O None AERCW Deleted - Appendix R Deleted FCV-67-14 3 D-1 B-PAS 36 BUT to 0 None AERCW Deleted - Appendix R Deleted FCV-67-65 3 C-7 B-PAS 6 BUT N0 C None FCV-67-68 3 C-11 8-PAS 6 BUT MO C None FCV-67-360 3 E-2 B-PAS 24 BUT M0 O None AERCW Deleted FCV-67-361 3 E-2 B-PAS 30 BUT MO O None AERCW Deleted FCV-67-362 . 3 E-3 B-PAS 30 BUT ' MO O None AERCW Deleted ,

FCV-67-363 3 E-4 B-PAS 24 BUT MO O None AERCW Deleted FCV-67-364 3 E-1 B-PAS 36 BUT MO O None AERCW Deleted - Appendix R Deleted FCV-67-365 3 D-1 8-PAS 36 BuT MO O None FCV-67-366 NNCC E-3 B-PAS 24 BUT M0 O None AERCW Deleted - Appendix R Deleted FCV-67-367 NNCC E-3 B-PAS 24 buT M0 O None AERCW Deleted 1-67-504A NNCC F-9 E 20" BUT H LC None AERCW Deleted 2-67-504% NNCC F-8 B-PAS 20" BUT H LC None 1-67-5048 NNCC F-9 E 20" BUT H LC None

/

2-67-5048 NNCC F-8 B-PAS 20" BUT H LC None 1-67-504C NNCC E-9 E 20" BUT H LC 'None 117 8

Scquaych Nuclocr PI nt Insarvico VcIvo Tcsting Prsgram SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 47W845-1 0 F4 u c4 H0 VAI.VE y 6$ $o n2 $ ga O ga TESTING $1 hM NUMBER j U

O N N" #$ (4 N REQUIRED U$ id $ REMARKS Qg U 4 4

2-67-504C tmCC E-8 B-PAS 20" BUT H LC None 1-67-504D NNCC E-9 E 20" BUT H LC None 2-67-5040 kNCC E-8 B-PAS 20" BUT H None 1-67-505A 3 F-10 E 30" BUT H LC None 2-67-505A 3 F-7 B-PAS 30" BUT H LC None 1-67-5058 3 E-10 E 30 BUT H LC None 2-67-5058 e 3 E-7 B-PAS 30" BUT H LC None. t 1-67-506A 3 F-10 E 24" BUT H LC None 2-67-506A 3 F-6 B-PAS 24" BUT H LC None 1-67-5068 3 E-10 E 24" BUT H LC None 2-67-506B 3 E-6 B-PAS 24" BUT H LC None 1-67-510A 3 C-11 B-PAS 6 BUT H 0 None 2-67-510A 3 C-9 B-PAS 6 BUT H 0 None 1-67-510B 3 C-8 B-PAS 6 BUT H 0 None 2-67-5108 3 C-6 B-PAS 6 BUT H 0 None 1-67-515A 3 C-11 8-PAS 6 BUT H 0 None 2-67-515A 3 C-11 G-PAT 6 BUT H 0 None 1-67-515B 3 C-8 B-PAS 6 BUT H 0 None 118 e

, S;qusych Nuclocr PI:nt insarvico Velva Tocting Prdgram

< (67) ESSENTIAL RAW C00LIf4G WATER 47W845-1 DRAWING NO:

D N oe >. m ~o VAINE y 6$" $o w $a Om o TESTING $ gh h

nunnen ms ao *d a dS >e N

w >s <0 d" ge aM o- nrouInto 3s ya a t; ww annanxs "8o 6 4 "8 A N B" 4

2-67-515B 3 C_ B-PAS 6 BUT H 0 None 1-67-518A 3 F-12 E 36" BUT H LO None 2-67-518A 3 F-b B-PAS 30" BUT H LO None 1-67-5168 3 E-12 E 30" BUT H LO None 2-67-516B 3 E-6 B-PAS 30" BUT H LO None 0-67-656A 3 E-2 C-PAS 30 CK SA -

None AERCW Deleted 0-67-656p , 3 E-3 C-PAS 30 CK SA -

t4one AERCW Deleted i 0-67-669A NNCC H-3 C-PAS 24 CK SA -

None AERCW Deleted 0-67-6698 f4NCC H-3 C-PAS 24 CK SA -

None AERCW Deletco 119 s

Saqusych Nuclocr Pl nt Insarvica Vcivo Tcsting Prcgram gg (67) ESSENTIAL RAW COOLING WATER pgygg pg 47W845-2 (RIS)

E $

0H >e (4 g H 0 VALVE M $ $$ m $m Om h5 TESTING by hh NUMBER m

<o N-m$ NO

>H N

m N$

>b h6 74O H H REQUIRED UD b O L! m WW REMARKS l "8U 6 W " 8A yM U" l 4 i I

FCV-67-81 3 H-10 B-PAS 24 BUT HQ O None Appendix R Deleted FCV-o7-82 3 H-9 B-PAS 24 BUT' H0 O None Appendix R Deleted FCV-67-177 3 B-10 B-PAS 8 BUT H0 0 None Appendix R Deleted FCV-67-128 3 B-10 B-PAS 8 BUT H0 0 None Appendix R Deleted FCV-67-147 3 A-6 B-PAS 24 BUT H0 C None Appendix R Deleted FCV-67-151 3 L-6 B-PAS 24 BUT H0 C None Appendix R Deleted FCV-67 2q3 . 3 Ao B-PAS 24 - DUT M0 C None Appendis R DelcLed ,

FCV-67-424 3 A-9 B-PAS 24 BUT N0 0 None Appendix R Deleted FCV-67-478 3 B-7 B-F%S 24 BUT H0 0 None Appendix R Deleted 1-07-520A 3 G-9 E 6" BUT H LO 2-67-520A NNCC G-2 B-PAS 6" BUT H LO l-67-520B 3 H-9 E 6" BUT H LO 2 67-520B NNCC H-2 B-PAS 6" BUT H LO 1 67-527A 3 F8 B PAS 1 1/2 CL M 0 None 2-67-527A 3 F-4 B-PAS 1 1/2 GL H 0 None 1-67-5278 3 F-8 B-PAS 1 1/2 GL M 0 None 2-67-5278 3 F-4 B-PAS I 1/2 GL M 0 None 120

i S;qusych Nuciccr Plant inscrvico Valvo Tcsting Program 1

(67) ESSENTIAL RAW COOLING WATER 47W845-2 gg OH > % HO VALVE NUMBER M d$ $$

NO w

N

$w d"

$w

$H

]n QN O TESTING REQUIRED

$1 y UD 9

hU Td $ REMARKS 4U > M >

p @ M N$

U A*

1-67-537A 3 0-7 B-PAS 18 BUT H 0 None 2-67-537A 3 0-4 B-PAS 18 BUT H 0 None 1-67-5378 3 B-8 B-PAS 18 BUT H 0 None 2-67-537B 3 D-3 B-PAS 18 BUT H 0 None 1-67-540A 3 B-9 E 1" BUT H LC 2 67-540A 3 B-2 B-PAS 4" BUT H LC j 1-u7-5408 , 3 A8 E 4" BUT H LC ,

2-07-540B 3 B-2 B-PAS 4" BUT H LC 0-67-551A 3 C-7 B-PAS 24 BUT H 0 tone 0-n7-5518 3 C-5 B-PAS 24 BUT H 0 None 0-67-552 3 C-6 B-PAS 24 BUT H 0 None 0-67-553 3 C-6 8-PAS 24 BUT H 0 None 0-67-555A 3 G-6 8-PAS 6 BUT H 0 None 0-67-5558 3 H-5 B-PAS 6 BUT H 0 None 1-67-718A 3 G-6 B-PAS 6" BUT H 0 None 2-67-718A 3 G-5 B-PAS 6" BUT H 0 None 1-67-718B 3 H-6 B-PAS 6" BUT H 0 None 2-67-7188 3 H-5 B-PAS 6" BUT H 0 None 121

?

Scqu:Sych Nuclocr Pl:nt incorvico Valvo Tcsting Przgram (67) ESS M UAL RAW C00 WATR 47W845-3 SYSTEM: DRAWItJG FJO:

OH b lH ct; h

H O VALVE m 6$ $$ p $g Om o TESTI!JG $1 hd FJUMBER m NO ,0 4$ d REQUIRED U$ id $ REMARKS AQO N 4 4 1-67-564A NNCC H-4 B-PAS ~ 4 BUT H 0 None 2-67-564A NNCC G-9 B-PAS 4 BUT H 0 None 1-67-5640 NNCC E-4 B-PAS 4 BUT H 0 None 2-67-5648 NNCC E-9 B-PAS 4 BUT H 0 None 1-67-564C NNCC F-4 B-PAS 4 BUT H 0 None 2-67-564C NNCC F-9 B-PAS 4 BUT H 0 None 1-67-5640 .

NNCC D-4 B-PAS 4 BUT H 0 None ,

7-67-564D NNCC D-9 B-PAS 4 BUT H 0 None 1-67-567A NNCC H-2 B-PAS 3 GA H 0 None 2-67-567A NNCC G-8 B-PAS 3 GA H 0 Nonc 1-67-5678 NNCC F-2 B-PAS 3 GA H 0 None 2-67-5678 NNCC F-8 B-PAS 3 GA H 0 None 1-67-567C NNCC G-2 B-PAS 3 GA H 0 None 2-67-567C NNCC J-8 B-PAS 3 GA H 0 None 1-67-567D NNCC E-2 B-PAS 3 GA H 0 None 2-67-5670 NNCC E-8 B-PAS 3 GA H 0 None l 122 e

Scquoych Nucirr PI:nt Insarvico Vcivo Tcsting Prcgram

,g ,

(67) ESSENTIAL RAW COOLING WATER W 845-3 DnAWING NO:

El Wo oe >. m varuc = gg y, am g5 bM 3so 25

5 g m TesTINc nunnen g3 d"a n d0 <m oaMs nrourneo aa arnanxs 2 0 >de a m >s ge "8A gM ww "8U 6 < De g

1-67-572A NNCC G-2 B-PAS 3 GA H 0 None 2-67-572A NNCC G-8 B-PAS 3 GA H 0 None 1-67-572B NNCC E-2 B-PAS 3 GA H 0 None 2-67-572B NNCC E-8 B-PAS 3 GA H 0 None 1-67-572C NHCC F-2 B-PAS 3 GA H 0 None 2-67-572C NNCC F-8 B-PAS 3 GA H 0 None 1-o7-572Q . NNCC D-2 B-PAS 3 GA H 0 None ,

2-67-572D NNCC D-8 B-PAS 3 GA H 0 None 1-67-583A NNCC C-1 B-PAS 2 GL H 0 None 2-67-583A NNCC C-7 B-PAS 2 GL H 0 None 1-67-5838 NNCC B-1 8-PAS 2 GL M 0 None 2-67-5838 NHCC B-7 B-PAS 2 GL H 0 None 1-67-583C NkCC B-1 B-PAS 2 GL M 0 None 2-67-583C NNCC B-7 B-PAS 2 GL H 0 None 1-67-583D NNCC A-1 B-PAS 2 GL H 0 None 2-67-583D NNCC A-7 B-PAS 2 GL H 0 None 123 1

Scquaych Nuclocr Picnt Insarvico Valvo Tcsting Prsgrcm (67) ESSENTIAL RAW COOLING WATER D W ING NO, 47W845-4 0H lH tt: ~ HO VALVE M d$

" $$ w $w Ow

- fO TESTING $gy hd UUMBER 4 9 h"OH N

m d"

>b b 28 O H REQUIRED UD U M$

WW REMARKS "8U 6 4 "84 yb W u"

4 FCV-67-168 3 C-7 B-PAS 1 1/2 GA DIA 0 None Appendix R Deleted FCV-67-170 3 C-9 B-PAS 1 1/2 GA DIA 0 None Appendix R Deleted FCV-67 188 3 E-7 B-PAS 1 GA DIA 0 None Appendix R Deleted FCV-67-190 3 E-9 B-PAS 1 GA DIA 0 None Appendix R Deleted 1-67-601A 3 C-1 B-PAS 2 GL H 0 None 2-67-601A 3 C-6 B-PAS 2 GL M 0 None 1-67-6015 . 3 C-5 B-PAS 2 GL M 0 None ,

2-67-601B 3 C-10 B-PAS 2 GL M 0 None 1-67-604A 3 D-6 8-PAS 2 GL M 0 None 2-67-604A 3 D-1 B-PAS 2 GL M 0 None 1-67-6048 3 D-10 B-PAS 2 GL H 0 None 2-67-604B 3 D-5 B-PAS 2 GL M 0 None 1-67-605A 3 E-6 B-PAS 2 GL M 0 None 2-67-605A 3 E-1 B-PAS 2 GL M 0 None 1-67-605B 3 E-10 B-PAS 2 GL M 0 None 2-67-6058 3 E-5 B-PAS 2 GL M 0 None 124 e

Scquoyah Nuciocr Plant Insarvico Valvo Tcsting Program (67) ESSENTIAL RAW COOLING WATER 47W845-4 SYSTEM: DPAWING NO:

N $

0H N cr ,

g H o VALVE m U$ $o -a $m Om jO TESTING hm yU NUMBER 4 9 * "k >H NO N m

d$

>b

$b ~

d 5 Oy REQUIRED ' U O id M WW REMARKS "8U 6 < "o% gM !3"

C 1-67-606A 3 E-6 B-PAS 1 1/2 GL U 0 None 2-67-o0cA 3 E-1 B-PAS 1 1/2 GL H 0 Nonc l-67-606B 3 E-10 B-PAS 1 1/2 GL M 0 None 2-67-606B 3 E-5 B-PAS 1 1/2 GL H 0 None 1-07-608A 3 E-6 B-PAS 2 GL M 0 None 2-67-608A 3 F-1 B-PAS 2 GL M 0 None 1-67-608B 3 E-10 B-PAS 2 GL M 0 None 2-67-6088 3 F-5 B-PAS 2 GL H 0 None 1-67-609A 3 F-6 8-PAS 2 GL M 0 None 2-67-609A 3 F-! B-PAS 2 GL M 0 None I - b 7 - b u'JB 3 F-lu D-PAS 2 GL M 0 None i-bi-6U9b 4 t-b U-FA5 Z LL M U None 1 -6 7-b l 0 A 3 F-6 B-PAS 2 GL M 0 None 2-b7-bl0A 3 G-1 B-FAS 2 GL M 0 None 1-67-610B 3 F-10 6-PAS 2 GL M 0 None 2-67-610B 3 G-5 B-PAS 2 GL H 0 None

~

125 6

Scquoyah Nuciscr Plant Insarvico Valva Tcsting ~ Program (67) ESSENTIAL RAW COOLING WATER 47W845-4 SYSTEM. DRAWIf1G 110:

0P N 84 ~ p H O VALVE M d$ $$ m $m $ ga kO TESTI?iG DM yd 11UMEiER

<o * "2 NO 2 >e N

m d$

>e Re o2

'U REQUIPED ~ U o N$

ww REMARKS "8U 6 W "8% gM B"

G l-67-611A 3 G-6 B-PAS 2 GL M 0 None 2-u/-olla 3 G-1 b-PAS 2 GL M 0 None 1-67-6118 3 G-10 B-PAS 2 GL M 0 None 2-67-6118 3 G-5 B-PAS 2 GL M 0 None U-b/-bibA 3 H-o S-PAS u BUT H 0 None 0-07-oloB 3 H-10 B-PAS o BUT H 0 None 0-07-023A 3 H-o 0-PAS 5 BUI M 0 None 0-07-0236 3 H-10 6-PAS S BUT H 0 None 1-67-640 3 0-10 B-PAS 1 1/2 GL M 0 None 2-o/-o40 3 D-5 B-PA5 1 1/2 GL M 0 None U-6/-o43A 3 L-6 6-FAS 3 GL M U None v c. / - u s a a a L,-au u rha a u n u Hone U-b/-04uh J b-6 b-FA5 Z LL M U None u-u/-usuu a b-6u u-VAs 4 ut r1 U rione u-u/-u/as J L. - i u-Vnd 4 uL (1 U idone 0-6/-6/36 3 C-5 B-PAS 2 GL M 0 None 126 e

._ . _ - . . . . . . _- _. _= _.

Sequsych Nuclocr Pl5nt Insarvico Vcivo Tceting Prsgram g (67) ESSENTIAL RAW COOLING WATER m 84 -4 (R16)

DRAWING NO:

e m

O M N H VALVE m d$ $$ w $m Ow b TESTING $b N NUMBER $ $ - REQUIRED ~ U $ REMARKS asO e g

=As ur e 1-67-683 3 B-6 B-PAS 1 GA M 0 None

?-67-683 3 8-5 B-PAS 1 GA H 0 None 0-67-685A 3 A-1 B-PAS 1 GL M 0 None 0-67-6858 3 A-5 B-PAS 1 GL H 0 None 1-67-7648 3 C-10 B-PAS 2 GL M 0 None 2-67-764B 3 C-5 B-PAS 2 GL M 0 None sl-b7-766A 3 C-6 8-PAS 2 GL H 0 None F

?-67-7n6A 3 C-1 B-PAS 2 GL M 0 None O

127 i

Sequsych Nuclocr PI:nt incorvico Vcivo Tonting Prsgrcm

. :,7 ) ESSENTIAL RAW COOLING WATER + " -

DRAWING NO:

m ON y N m Ho VAINE g m 5$ $$ m $m Om b TESTING bm Nd BER E@IED ~ U REAES a8U 6 .c "8A EN "

-e f3 0-4 B-PAS 24 BUT MO O- '4one ippendix R Deleted S - -1 8-PAS 24 BUT M0 O 'ione ippendix R Deleted nr4CC 'F-8 B-PAS 2 GL M 0 tone NNCC E-6 B-PAS 2 GL M 0 Jone N4CC E-8 B-PAS 2 GL M 0 ' lone NNCC D-6 B-PAS 2 GL M 0 '4one NNCC F-10 B-PAS 2 GL M 0 fione vacc E-10 B-PAS 2 GL M 0 tione f .:aCC E-10 B-PAS 2 GL M 0 fione

-T l!2-10 B-PAS 2 GL M 0 rione

!^ B-7 E 3" BUT H LC rione G-7 B-PAS 3" BUT M LC rione 2 D-7 E 3" BUT M LC rJone 3 L 7 B-PAS 3" BUT M LC None h .

128 e

Sequoyah Nucl:Cr Plant inservico Valvo Testing Program (68) REACTOR CCOLai SYSTEM 47W813-1 SYSTEM. DRAWING NO:

$ > h O t< CG HO VALVE y 3$ $$ w $w Om jb TESTING $ hd NUMBER 4o j

b "k NO

> E4 N

to d$

> Ed

$ E4 Q5 O H REQUIRED UDO Td yy

$ REMARKS "8U 6 < = 8D* M B" 4

1-68-579 1 F-8 E 1" ,GL M .LO None 2-06-579 i F-d B-PAS 1" GL M LO None 1-68-580 1 F-9 E 3" GL M LO None 2 L8 SHO 1 I-9 B PAS 3" GL M LO None I

LO 129 e

- +=

l o _ i j

- c ~ - o o - > - o c o N o J m

~

o L

o e-

~

o

~

o L

o ;

~

~- L ~ 4 L L L' <

c o o o o o en u, u, v_ a a i, o

6 o

s > ,

u ., 6 6 6 6

= c o o .o o O o o o C +J M i w sJ W =a W m m 2, > > m m > > < -

2>

= t<

m<

f =M n

?

v o

z

-__ C m

{

ur s u s -s w s w w w w bbM M r

o CLASS P a a o r ri o m r, - i= o

. m. o, m. 7 AWING m ,J

c. v & a . :r m a a e m = =

CO OINATr 5 M

~

13 2

a m r m m -

!m m 1

i m c) m a m 7

, e m 4 b m Z

,u ,e. m --

" Cl> ~-

(7 .S to W t S v. La O

~ ~ ~ ~ - . _

o

=

o 3

o a

r e 2

s a

e o

a m

a c.

es a _o m m m e m m o m -

4

~, VALVE 'Sm L

C C : C C C C C C

- - - - - - - - - TYPE ,. g

} -

1 , .- 1 1 = = ACL, Ln ID

g l'

TYPE **

i _ . , . ..

O o o o js o e l0 o o o c. lo o o o NORMAL 3 l

i' J POSITION (A z z .- z z .- z z z fz z z z o o o e o c c c o o o o a = : 2 z -: 2 : -

2 2 s o e c o e -

c. e o o o 4 ==.

OE O I

-e e Md c ii 4 l t

. m t ,

C RELIEF g REQUEST

-4 ALTERNATIVE e

(A TESTING T.

3 C

,U e O E @

c m

= 3

.O.

l l

l

Jlb ln

%D L

1 1

l

Sequoyah '; clear Plant incervica Vciva Tceting Prsgram g (70) COMPONENT C00LI*.C Sr$ TEM 47W859-1 DnWIM NO, 5

m g-oN de cc w He VALVE m 3

dO w , y @m jo

$ oH TESTING $m Ub Nd kgh NUMBER U l@ &E N"O H m

H he REQUIRED NW

$ REMARKS 8

U

>6 <

8A gGW3 "

2-70-5108 D-4 20" M 0 3

BP{ BUT None 0-70-529A '3 H-5 B-PAS 12" EUT M 0 None 0-70-529B 3 H-6 B PAS 12" BUT H 0 None 1-70-531 3 D-9 B-PAS lo" BUT h 0 None 2 70-531 3 E-9 B-PAS In" h.T H 0 None s

i i

e 131 i

Scqusych Nuclocr Plcnt inservico Velva Tcating Prsgram gyg (70) COMPONENT COOLING SYSTEM 47W859-4 DRAWING NO:

13 oe u .: No VALVE to 3$ $$ m $m 8m b TESTING Db Nd NMER 3, g REQtJIRED ' RmMS "8O 6 < =8A MN "

1-70-545A 3 0-6 B-PAS 18" BUT H 0 None 2-70-545A 3 0-12 B-PAS 18" GUT H 0 None 1-70-545B 3 E-1 B-PAS 18" BUT H 0 None 2-70-545B 3 E-7 B-PAS 18" BUT H 0 None 1-70-546A 3 D-5 B-PAS 18" BUT H 0 None 2-70-546A 3 D-11 B-PAS 18" BUT H 0 None 61 70-546B 3 F-2 B-PAS 18" BUT H 0 None F

?-70-516B 3 F-7 B-PAS 18" BUT H 0 None 1-70-552A 3 B-6 B-PAS 3" GA H 0 None 2-70-552A 3 B-12 B-PAS 3" GA H 0 None I-70-552B 3 B-1 B-PAS 3" GA M 0 None 2-70-552B 3 B-7 B-PAS 3" GA H 0 None 1-70-553A 3 B-5 B-PAS 1" GL H 0 None 2-70-553A 3 B-11 B-PAS 1" GL H 0 None 1-70-5538 3 B-2 B-PAS 1" GL H 0 None 2-70-553B 3 B-8 B-PAS 1" GL M 0 None 1-70-557A 3 8-4 B-PAS 3" GA H 0 None B-10 2-70-557A 3 B-PAS 3" GA H 0l None 132 e

Scqusych Nuclocr Pirnt incorvico Vcivo Totting Prsgram gyg ( 70) COMPONENT COOLING SYSTEM DRAWING NO: 47W859-4 e

o M M O VALVE to dI

" $$ ga ga

@ ga jb TESTING D Nd NUMBER ko kk dO N b 4$H RN REQUIRED ' U $ REMARKS a8O

>H 6

m O H "8A g%N W Ed 1-70-557B 3 B-3 B-PAS 3" GA ff 0 None 2-70-557B 3 B-9 B-PAS 3" GA M 0 kone 1-70-558A 1 C-6 B-PAS 1" GA M 0 None 2-70-55sA 3 C-12 B-PAS 1" GA M 0 None 1-70-55bB 3 B-1 B-PAS I 1/2 CA M 0 None 2 70-5558 3 B-7 B-PAS 1 1/2 GA M 0 None

. I 70 Sc0A 3 C-5 B-PAS 1 1/2 GL M 0 None F

2-70-560A 3 C-11 B-PAS 1 1/2 GL M 0 None 1-70-560B 3 C-2 B-PAS I 1/2 GL M 0 None 2-70-5608 3 C-8 B-PAS 1 1/2 GL M 0 None 1-70-562A 3 B-4 B-PAS 1 1/2 GA M 0 None 70-562A 3 B-10 B-PAS 1 1/2 GA N O None 1-70-562B 3 C-3 B-PAS 1 1/2 GA M 0 None 2-70-562B 3 C-8 B-PAS 1 1/2 GA M 0 None 1-70-564A 3 0-6 B-PAS 1" GA M 0 None 2-70-564A 3 0-12 B-PAS 1" GA M 0 None 1-70-564B 3 D-1 B-PAS 1" GA M 0 None 2-70-5b48 3 0-7 B-PAS 1" GA M 0 None 133 i

Sequrych Nucirr Pl nt insarvico Vciva Tcating Pragram gyg (70) COMPONENT COOLING SYSTEM D MWING NO: 47W859-4 e

o > M o VALVE to M$ $$ m $m Om b TESTING

$h bd k o u,m asO B < =sA -

1-70-566A 3 D-4 B-PAS 1" GL M' O None 2-70-566A 3 D-10 B-PAS 1" GL M 0 None-1-70-566B 3 D-3 B-PAS la GL M 0 None 2-70-5668 3 D-8 B-PAS 1" GL M 0 None 1-70-567A 3 D-4 B-PAS 1" GA M 0 None 2-70-567A 3 D-10 B-PAS 1" GA M 0 None

$1-70-567B 3 0-3 B-PAS 1" GA H 0 None F

2-70-567B 3 D-9 B-PAS 1" GA M 0 None 1-70-569A 3 D-o B-PAS 1" GA M 0 None 2-70-569A 3 D-12 B-PAS la GA M 0 None 1-70-5698 3 D-1 B-PAS 1" GA M 0 None 2-70-5698 3 D-7 B-PAS 1" GA M 0 None 1-70-571A 3 D-4 B-PAS 1" GL M 0 None 2-70-571A 3 0-10 B-PAS 1" GL M 0 None 1-70-571B 3 D-3 B-PAS la GL M 0 None 2-70-571B 3 D-8 B-PAS 1" GL M 0 None 1-70-572A 3 D-4 B-PAS 1" GA M 0 None 2-70-572A 3 0-10 B-PAS 1" GA M 0 None 134 6

S qusych Nucl:Cr Pir.nt incarvica Vcivo Tcating Prsgram g (70) COMPONENT COOLING SYSTEM 47W859-4 y

5 o > M n o VALVE m dI $$ m $m 8m o TESTING $ "d o

a8U 6 < *8A M N, "

1-70-5728 3 D-3 B-PAS 1" GA tt 0 None 2-70-5728 3 D-9 B-PAS 1" GA H 0 None 1 70-707A 3 B-6 B-PAS 1" GA H 0 None 1

2 70-707A 3 B-11 B-PAS 1" GA H 0 None 1-70-7078 3 B-1 B-PAS 1" GA H 0 None 2-70-7078 3 8-7 B-PAS I" GA H 0 None sI-70-709A 3 B-5 B-PAS 1" GA H 0 None 2-70-709A 3 B-11 B-PAS 1" GA H 0 None 1-70-709B 3 B-2 B-PAS 1" GA H 0 None 2-70-7098 3 B-7 B-PAS 1" GA H 0 None 1-70-712A 3 C-5 B-PAS 3/4" GA H 0 None 70-712A 3 C-11 B-PAS 3/4" GA H 0 None 1-70-7128 3 B-2 B-PAS 3/4" GA H 0 None

. 2-70-7128 3 B-7 B-PAF 3/4" GA H 0 None 1

l 1-70-713A 3 C-5 B-PAS 1" GA H 0 None j 2-70-713A 3 C-11 B-PAS 1" GA H 0 None 1-70-7138 3 B-2 B-PAS 1" GA H 0 None 2-70-713B 3 B-8 B-PAS 1" GA H 0 None l

135 1

t 4

Scqusych Nuciccr Pl:nt incorvico Vcivo Tcating Prcgram I

gygg _(70) COMPCNENT COOLING SYSTEM DMWIE NO: 47W859-4 Oe >* a:

VAINE u)

@$ g3 $ ga $ TESTING Db b s

""* " !yga l W! l$$E $$

8 O

6 0 $ l0 yh" o

p.

"0"' " ~ 35, W W e!E s

=^ns l-70-725A 3 B-4 B-PAS 3" GA H 0 None 2-70-725A 3 B-9 B-PAS 3" GA H 0 None 1-70-725B 3 B-3 8 PAS 3" GA H 0 None 2-70-725B 3 B-9 B-PAS 3* GA H 0 None

?

i i

136 e

Scqusych Nuciccr Picnt incorvico Vcivo Tcsting Prsgram SYSTEM: (72) CGNTAD. MENT SPRAY DRAWING NO: 4 N812-1 B

m ON N M o VALVE m dI $$ ra $ga O sa TESTING DL bd 4" 5 UD% WdN ko a8 dOH%" d*

NUMBER N 40 m >b $ oH REQUIRED REMARKS

, O

>6 < " 8 A

N M a" "

4 1-72-502 2 C-8 E 8" GA M' LC None 1-72-503 2 C-5 E 8"' GA :t LC None 1-72-504 2 B-5 E 8" GA H LC None 1-72-533 2 D-8 E 12" GA H LO None I-72-534 2 B-6 E 12" GA H LO None 1-72-545 2 C-4 E 2" GA H LC None 1 72-546 2 B-4 E 2" GA H LC None F

1-72-553 2 F-4 E 2" GA M LC None 1-72-554 2 E-4 E 2" GA H LC None 2-72-502 2 C-8 B-PAS 8" GA H LC None 2-72-503 2 C-5 B-PAS 8" GA H LC None 2-72-504 2 B-5 B-PAS 8" GA H LC None 2-72-533 2 D-6 B-PAS 12" GA H LO None 2-72-534 2 B-6 B-PAS 12" GA H LO None 2-72-545 2 C-4 B-PAS 2" GA H LC None 2-72-546 2 B-4 B-PAS 2" GA H LC None 2-72-553 2 F-4 B-PAS 2" GA H LC None 2-72-554 2 E-4 B-PAS 2" GA H LC None 137 i

I e

Scqusych Nuciccr PI:nt insarvico Vcivo Tocting Prsgram (74) RESIDUAL HEAT REMOVAL DMWIM NO: 47We10-1 3

0 > M n O VALVE m 6$ $$ ra $ga @ ra O TESTING Db bd

!RIMBER h

U dO N d* 4$ d N REQUIRED U$ ' $ REMARKS Qg O Nh

, U l 1-74-34 2 D-4 E 3/4 GL H' LC None

\

74-36 2 E-6 B-PAS 8" GA H C None

, 74-37 2 D-6 B-PAS d" GA H C None 1-74-512 2 E-8 E 3/4 GL M LC None 1-74-513 2 C-8 E 3/4 GL M LC None 1-74-516 2 F-7 E 3/4 GL H LC None 3 1-74-517 2 B-7 E 3/4 GL H LC None F

1-74-520 2 F-7 E 8 GA H LO None 1-74-521 2 C-7 E 8 GA H LO None 1-74-524 2 F-5 E 8 GA H LO None 1-74-525 2 C-5 E 8 GA H LO None

_r 74-530 2 E-5 B-PAS 2" GL M C None 74-53) 2 C-4 B-PAS 2" GL M C None 1-74-542 2 C-5 E 3/4 GL M LC None 1-74-544 2 C-5 E 3/4 GL H LC None 1-74-546 2 F-5 E 3/4 GL H LC None 1-74-547 2 F-5 E 3/4 GL M LC None l 1-74-550 NNCC G-3 E 3/4 GA H LO None 138 e

Scqusych Nuciccr Plant Insarvico Vcivo Tecting Prsgram (74) RESIOUAL HEAT REMOVAL 47W810-1 to O N N HO VAI,VE m

$o a P w 8m b TESTING Db Nd d ld$ l sg U

a la ja a j gl. !g -

2-74-34 2 D-4 B-PAS 3/4 GL M' LC None 2-74-512 2 E-8 B-PAS 3/4 CL M LC None 2-74-513 2 C-8 B-PAS 3/4 GL H LC None 2-74-516 2 F-7 B-PAS 3/4 GL M LC None 2 71-517 2 B-7 B-PAS 3/4 GL H LC None 2-74-520 2 F-7 B-PAS 8 GA H LO None 2-74 521 2 C-7 B - PX 8 GA H LO None 2-74-524 2 F-5 B-PAS 8 GA H LO None 2-74-525 2 C-5 B-PAS 8 GA H LO None 2-74-542 2 C-5 B-PAS 3/4 GL M LC None 2-74-544 2 C-5 B-PAS 3/4 GL M LC None 2-74-546 2 F-5 B-PAS 3/4 GL M LC None 2-74-547 2 F-5 B-PAS 3/4 GL M LC None 2-74-550 NNCC G-3 B-PAS 3/4 GA H LO None 139 i

ML20137E882

Text

SUMMARY

1.0 INTRODUCTION

Navigation menu

Search