Text

Rev 2 to NPPD CNS Third Interval Inservice Testing Program
	ML20210H564
Person / Time
Site:	Cooper
Issue date:	08/07/1997
From:	; NEBRASKA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20210H559	List: ML20210H554; ML20210H564;
References
	PROC-970807, NUDOCS 9708140092
	Download: ML20210H564 (190)
	v • d • e

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NEllRASKA PUllLIC POWER DISTRICT COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM REVISION 2

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COOPlift NUCl.liAll STATION TillitD INTliitVAI.

INSlillVICl! TliSTING PitOGilAM 1213Lii 01: CONTliNIS

1. INTRO 11EC))QN PAGE A.- liasis for the Program I

11. The Third Ten Year Interval 2 C. Applicable ASMii Code 2 D. IST Program Scope 2 li IST liasis Document 3 F. Testing Frequency 3 G. Skid-Mounted Components and Component Subass:mblies 3

11. Program Description 4

11. IliS))NG_l'lWGIMhLliOldUMl'S A. Description i II, Allowable Itanges of Test Quantities 1 C. Instrumentation 1 D. Referense Values 2 111. L'UMI'_SUMh1AltY 1.lS11NG A. Notations I

11. Pump Summary Tables 2 C. Pump llelief llequests 11 D. Augmented Pump Relief Requests 19 IV. 111SIING_l!ROGlMhE01LYAllliS A. Description i

11. Cold Shutdown Testing i C. 1.imiting Values of 1:ull-Stroke Time I D. Reference Values 2

!!. Instrumentation Requirements 2 F. Active / Passive Valves 2 G. 1: ail-Safe Testing 3

11. Yalve Position Indication Verification 3

1. Water Scaled Valves 3 i J. Check Valve Testing 4 K. Relief Valve Testing 4 i.. Vacuum lireater Testing 5 llevision 2 Page i

COOL'l!R NUCl. liar STATION TillRD INTL!RVAl, INSliRVICli Tl! STING l'ROGRAM V. VAL \'lifiUMMAIO' LISllNG l' AGE A. Notations I

11. Valve Summary Tables 4 C. Cold Shutdown Justifications 80 D. Refueling Outage Justifications 04 li Valve Relief .sequests 117 17 Augmented Valve Cold Shutdown Justifications 136 G. Augniented Valve Refueling Outage Justifications 144 j 11. Augmented Valve Relief Requests 151 A

Revision 1.2 l' age ii i

COOPliR NUCl.I!AR STATION TillRD INTliRVAl.

INS!!!!VICl! TliSTING PROGRAM l 1

1. INE OHUCIl0E :

A. Ilasis for the Program The Cooper Nuclear Station (CNS), inservice Testing Program (IST) is required by 10CFR50.55a(f). Ilurns and Roe, the Architect lingineer for CNS during constmetion, was NPPD's agent in determining the ASMli Code classifications of plant components.

NRC Regulatory Guide 1.26 was not yet published; hence it was not used during construction. NPPD has since developed a piocedure for equipment safety classification. This procedure and the following guidance docun.ents were used in developing this revision to the IST Program:

e Regulatory Guide 1.26, Reve. ion 3. February 1976, " Quality Group Standards for Water , Steam , and Radioactive Waste-Containing Components of Nuclear Power Plants",

e Regulatory Guide 1.14', " Inservice inspection Code Case Acceptability, ASMii Svetion XI, Division I",

. ANSI /ANS-52.1-1983. American National Standard, " Nuclear Safety Criteria for the Design of Stationary lloiling Water Reactor Plants"

. Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves"

Updated Final Safety Analysis Report, Cooper Nuclear Station,

+ Technical Specifications. Cooper Nuclear Station.

Generic 1.etter 89-04, Supplement 1: " Guidance On Developing Acceptable Inservice Testing Programs", dated April 4,1995, a NURI!G-1482, Guidelines for Inservice Testing at Nuclear Power s Plants".

Revision 2 Section i Page 1 of 4

COOPlilt NUCLliAR STATION Tilll(D INTL!RVAl, INS!!!(VICli TliSTING PROGRAhi

11. The Third Ten Year Interval The commercial operation date for Cooper Nuclear Station is July 1,1974. The first and second intervals were extended as alli *ed by IWA 2400(c). CNS will begin the i third interval on h1 arch 1,1996.

C. Applicable AShil! Code Inservice Testing of AShil! Class 1,2 and 3 pumps and valves is performed in accordance with AShili Section XI 1989 lidition except as allowed by 10CFR50 or where specific written relief has been granted by the NRC pursuant to 10CFR50.55a(f)(6)(iii) for examinations and tests determined to be impiacticabic.

Provided the guidance of Generic lxtter 89-04 and NURiiG 1482 are followed, the proposed alternative examinations or tests may be implemented prior to receiving written NRC approval.

AShili Section XI, Subsections IWP and IWV invoke ANSI /AShili Operations and hiaintenance (Ohi) Standards Part 6, and Part 10,1987 lilition with the 1988 Addenda. The Oh! Standards are approved for use in 10CFR50.55a(bR2Rviii).

AShill Code Cases that have been approved by the NRC per Regulatory Guide 1.147 and are adopted for use at CNS, will t>e identified in the IST Program. No Code Cases are currently being used in the IST Program.

D. Program Scope AShili Class I,2, or 3 pumps which are provided with an emergency power source and perform a function to bring the plant to the sale sliutdown condition, maintain the plant in the safe shutdown condition, or mitigate the consequences of an accident are included in the IST Program. AShili Class 1,2, or 3 valves which perfonn these functions and safety or relief valves which provide over pressure protection for systems 4

or portions of systems which are required to perform these functions, are also included.

The safe shutdown condition at CNS is hot shutdown. The term " accident" refers not only to the design basis accidents analyicd in Section XIV of the USAR, but to a broad range of possible adyctse events which could affect plant safety. Additional accidents and operational transients, and the equipment required to mitigate the possible consequences thereof, are identified in the USAR, Appendix G. " Station Nuclear Safety Operational Analysis."

Revision 2 Section l Page 2 of 4

t COOPlilt NUCLliAlt STATlON TillitD INTlil(VAL INS!!!<VICli TIESTING pitOGitAM l

The scope of the IST regulations is limited to ASMi! Class 1,2, and 3 components.

Non Code Class components whor.e functium are essential to the safety or reliability of the plant are also included in the CNS IST Program as augmented components. These augmented components are tested to the same accepted standards for component testing to the extent practicable. Since Non-Code components are outside the scope of the l

regulations, requests for relief are not required if the OM Standards cannot be met.

llowever, deviations from the Standards are documented and justified in the program.

!!. IST liasis Document A .eparate IST liasis Document has been prepared for the third inspection interval. It documents the safety funMions and the basis for tiie tests specified for the components in the third interval program, ana provides the juuitication for certain components excluded from the testing program.

1. Tes.ing 1 tequency The required test frequency for pumps and valves is established in the OM Standards.

The actual test frequency is identified in the summary tables. A band of +25% of the test interval may be applied to the test schedule, as onc.aed by the Technical Specifications, to provide necessary operational llexibility.

G. Skid Mounted Components and Component Subassembli":s Skid mounted components are pumps and valses in skid systems of major equipment that are integral to the operation of the major equipment. These components are typically designed and installed without provisions for testing. Per the guidance of NUlti!G 1482, Section 3.4, skid nounted components and component subassemblies need not be individually tested to the Code requisements provided their operational readiness is adequately demonstrated by testing of the associated major equipment, lhamples of skid mounted ecmponents would be the diesel fuel oil booster pump and engine driven fuel oil pump, and the llPCI and itCIC turbine stop valves. Skid-mounted components are identified in the CNS IST Program liasis Document.

-lixamples of skid-mounted subassemblies would be the solenoid operated pilot valves ,

for air operated valves, llevision 2 Section 1 Page 3 of 4

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COOPl!R NUCl. liar STATION TillRD INTliRVAL INS!!RVICl! TliSTING PROGRAM

11. Program Description The IST Progrant is organited in five map r sections. The first section is the introduction, which provides the background for the development of the IST Program; the second section describes pump testing requirements; the third section provides the pump tables and associated relief requests; the fourth section describes valve testing requirements; and the fif th section provides the valve tables, cold shutdown test justificatium, and asweiated relief requests.

Revision 2 Section ! Page 4 of 4

l COOPlift NUCl.!!AR STATION TillRD INTL!!tVAL INSliRVICl! TliSTING PROGRAM

11. IES11NGEROGRAhtEOR 1'UA11'S A. Dcscription i r

The Pump Summary Listing, Section lil, identifies the pumps included in the CNS IST Program, the inservice test quantities to be measured, the test frequency, references to pump relief requests, and other pertinent information. 1

11. Allowable Ranges of Test Quantities The allowable ranges specified in OMa Part 6. Tables 3a, and 3h are used for pressure, flow, and vibration measurements except as provided in relief requests. In soine cews, the performance of a pump may be adequate to fulfill its safety function even though there may be a measurement that falls outside the allowable range. Should this 2

situation occus, an operability determination may be performed, in accordance with Generic lxtter 91-18. NURl!G 1482, and CNS administrative procedures.

I C. Instnunentation Instrumentation used in the IST Program will conform to the requirements of OMa Part 6 except where specific relief is requested. Two or more instruments or components working together to provide a single output are considered an instnunent loop. The allowable inaccuracy of an instrument loop is based on the squate root of the sum of the squares of the inaccuracies of each instnunent in the loop. The instrument accuracy requirements refer to the calibration of the instnunent. The Code does not require

! consideration of other factors which could contribute to measurement error such as orifice wear, instrument location, etc. Ilowever, excessive measurement error would be detected by erratic or unacceptable test results which would require corrective action. If test lesults are due to out of calibration instnaments, the instniments may be recalibrated and the test renm. If it is determined that unacceptable test results are due to other instnunent problems, corrective action shall be by repair or replacement of the instnanent system, The Code requires that flowrate be measured using a rate of quantity meter installed in the pump test circuit. Differential pressure may be measured using a dp gauge or transmitter, or may be determined by the difference between the pressure at the inlet and outlet of the pump., Per NURiiG-1482, Section 5.5.3. suction pressure may be calculated based on inlet tank or bay level.

Revision 2 Section 11 Page 1 of 2

COOPliR NUCl.l!AR STATION Ti!)RD INTERVAL.

INSliRVICl!TliSTING PROGRAM i Vibration instrumentation shall be calibrated o'er the required frequency response range of one third minimum pump speed to a, . cast 1(XX)IlZ. OMa Part 6 requires vibration velocity measurements to be reak. For a simple sinusoidal waveform, NURl!G 1482, Section 5.4 allows RMS values to be converted to peak values with a multiplier of 1.414.

D. Reference Values Reference values are determined from the results of the previous interval's inservice tests. Reference values will be reestablished followmg pump replacement. Reference values will only be established when the pump is known to be operating properly.

When any reference value may have been affected by repair or routine servicing of a pump, a reference value or set of reference values shall be determined, or the previous values (s) reconfirmed by an inservice test run prior to declaring the pump operable.

Pumps may be tested at more than one point of pump operation. Additional reference values must be established for these points in accordanec with Code requirements.

Whenever an additional set of reference values is established, the reasons for doing so shall be documented in the recon 1 of tests.

4 The Code requires that reference values be established at points of pump operation that can be readily duplicated during subsequent tests. It may not be possible, or it may be extremely difficult, to vary system resistance such that the reference conditions are duplicated exactly. NURl!G 1482, Section 5.3, allows variation in the setting of fixed

reference value of either differential pressure or flowrate provided the combination of this variation and the associated instrument error does not exceed i21 Revision 2 Section 11 Page 2 of 2

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COOPliR NUCLliAR STATION - -

TillRD INTliRVAL

INSliRVICl! TIISTING PROGRAM i

Ill, l'UhiP

SUMMARY

LISTING l A. Notations i The following notations ere used in the pump sununary tables:

. SYSTl!M: The plant systein in which the punip is located.

PUMP CIC: The pump component identification code.

ISI CLASS: The ASMi! inservice inspection (ISI) classification of the r component. Augmented components are classified "A".

l IWID: The associated piping and instromntation drawing number.

lWID COOR: The drawing coordinate locutien for the pump. >

PARAMl!TliRS: Refers to the test quantities to be measured or observed. The symbols used for designating which parameters will be measured or observed are as follows:

dP - Differential Pressure Pi - Inlet Pressure Pd . Discharge Pressure Q - Pump Flowrate ,

N - Rotative Speed -

V Vibration Amplitude FR11QUliNCY: The frequency of testing each pump. The letter "Q" denotes -

- quarterly testing; the letters "CS" denote cold shutdown testing; l and the letters "RF" denote refueling outage testing.

NOTliS: This column contains a brief component description, references any applicable relief request (s), and contains any other component related infonnation. Relief Requests are designated RP-XX. Augmented Relief Requests are designated ARP XX. .

Revision 2. Section 111 Page 1 of 21 ;

COOPER NUCLEAR STATION THIRD INTERVAL INSFRVICE TESTING PROGRA3I PL3tP SL3131ARY TABLES SYSTE31: CORE SPRAY (CS). P&ID No. 2645 Sheet 1 i PARAMETERS ,

PUMP P&lD ISI NOTES !

CIC COOR CLASS Q dP V N i CS-P-A F-3 2 Q Q Q (1) CS PUMP 1A, LOOP A i i RP-01. RP-02 -

CS-P-B l D-3 2 Q Q Q (1) CS PUMP 1B. LOOP B RP-01. RP-02 -

l NOTES:

(1) Pump is directly coupled to a constant speed synchronous or induction type driver.

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Revision 2 Section III Page 2 of 21 !

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i COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TFSTING PROGR,01 PDIP SD13tARV TABLES SYSTEM: DIESEL GENERATOR FUEL OIL TRANSFER. P&lD No. 2011 Sheet I I

PUMP P&lD ISI PARAMETERS CIC COOR CLASS NOTES Q dP V N DGDO-P-DOTA A-8 A Q Q Q (1) PUMPIA DGDO-P-DOTH A-10 A Q Q Q (1) PUMPIB NOTES:

(1) Pump is directly coupled to a constant speed synchronous or induction type driver.

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! i Revision 2 Section III Page 3 of 21 i

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 1

, POIP SU3 DIARY TABLES i

l i SYSTE31: IIIGII PRESSURE COOLANT INJECTION (IIPCI) P&ID No. 2%8 PARANIETERS PU31P P&ID ISI NOTES CIC COOR CLASS Q dP V N i

IIPCI-P-51P E4 2 Q Q i Q Q IIPCI Pi'AIP 1 A (51AIN) (1) j RP-01. RP-02 I

IIPCI-P-UP E-3 l '

2 Q Q Q Q IIPCI PGtP 1B (BOOSTER). (1) i RP-01. RP-02 NOTE:

(1) IIPCI main and txester pumps will be tested simultaneously.

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Revision 2 Section III Page 4 of 21 i

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COOPER NL' CLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGR,01 PL31P SL3tMARY TABLES SYSTEAt: RADIOACTIVE WASTE (RW). P&ID No. 2005 Sheet 2 PARANIFTERS PUS 1P - P&ID ISI NOTES t CIC COOR CLASS Q dP V N RW-P-Z1 G-10 A RF N/A N/A 41) ELEVATED REUiASE POINT SUNIP PUNIP 1 A. ARP-01 RW-P-Z2 G-10 A RF N/A N/A (1) ELEVATED RELEASE POINT SUNIP PUA1P IIL ARP-01 NOTES:

(1) Pump is directly coupled to a constant speed synchnmous or induction type driver. -

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Revision 2 Section III Page 5 of 21 r

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 PL31P SO31 MARY TABLES SYSTE31: RF

CTOR CORE ISOLATION COOLING (RCIC). P&lD No. 2S43 i

PARA 31ETERS PUMP P&ID ISI NOTES I

CIC COOR CLASS Q dP V N RCIC-P-MP G-3 2 Q Q Q Q RCIC PUMP 1 A RP-01. RP n2. RP-04 i

Revision 2 Section III Page 6 of 21 i

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 PU3tP SU3 DIARY TABLES SYSTE31: REACTOR EQUIP 31ENT COOLING (REC). P&lD No. 2031 Sheet 2 PARANIETERS PU31P P&lD ISI NOTES CIC COOR CLASS Q dP V N REC-P-A G-1 3 Q Q Q (1) REC PUNIP I A. LOOP A RP-03 REC-P- B G-2 3 Q Q Q (1) REC PUNIP IB. LOOP A ,

RP4)3 REC-P-C G-3 3 Q Q Q (1) REC PUNIP IC. LOOP B RP-03 i REC-P-D G-3 3 Q Q Q (1) REC PUNIP ID. LOOP B ,

RP-03 I

NOTES:

(1) Pun:p is directly coupled to a constant speed synchronous or induction type driver.

- Revision 2 Section III Page 7 of 21

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM PLSIP S031MARV TABLES SYSTE31: RESIDUAL IIEAT REA10 VAL (RIIR) P&lD No. 2040 4

PARAA1ETERS PUA1P P&ID ISI . NOTES CIC COOR CLASS Q dP V N 4

RIIR-P-A G4 2 Q Q Q (1) RIIR PUNIP 1 A. LOOP A RP-01. RP-02 4

RIIR-P-B G-9 2 Q Q Q (1) RIIR PUAIP IB. LOOP B RP-01. RP-02 l RIIR-P-C II4 2 Q Q Q (1) RIIR PUNIP IC. LOOP A l RP-01. RP-02 RIIR-P-D II-9 2 Q Q Q (1) RIIR PUNIP ID. LOOP B RP-01. RP-02 .

NOTES.

' I (1) Pump is directly coupled to a constant speed synchronous or induction type driver. >

Revision 2 Section III Page 8 of 21

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRA5i

- PL3tP SL3151ARY TABLES SYSTE31: SERVICE WATER (SW). P&lD No. 2006 Sheets I and .4 -

PARAA1ETERS !

PUSIP P&ID ISI _

NOTES 4

CIC COOR CLASS dP V N Q

i SW-P-A B-10 1 3 Q Q Q (1) SW PUNIP 1 A. RP-05 SW-P-B B-9 4 3 Q Q Q (1) SW PUNIP 18. RP-05 SW-P-C B-8 3 Q Q Q (1) SW PUNIP IC. RP-05 i SW-P-D B-7 3 Q Q Q (1) SW PUNIP ID. RP-05 SW-P-BPA F-7 3 Q Q Q (1) SW BOOSTER PU5fP I A. RP-02 SW-P-BPB C-7 3 Q Q Q (1) SW BOOSTER PUh1P 1B. RP-02 SW-P-BPC E-7 3 Q Q Q (1) SW BOOSTER PUS 1P IC. RP-02 i

SW-P-BPD A-7 3 Q Q Q (1) SW BOOSTER PU51P 1D. RP-02

, NOTES: i

{ (1) Pump is directly coupled to a constant speed synchronous or induction type driver.

J Revision 2 Section Ill Page 9 of 21 1

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 FU31P SU31MARV TABLES SYSTE31: STANDBY LIQUID CONTROL (SLC). P&lD No. 2045 Sheet 2 PARAMETERS PUMP P&lD ISI NOTES CIC COOR CLASS V N Q P SLC-P-A E-10 A Q Q Q (1) PUMP 1 A. ARP-02 SLC-P-Il F-10 A Q Q Q (1) PUMP 18. ARP-02 Notes: (1) Positive displacement pump 1

I Revision 2 Section III Page 10 of 21

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COOPliR NUCl. liar STATION TillRD INTI!RVAl.

. INSliRVICII TliSTING PROGRAM

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C. Pump Relief Requests ;

Rida Descrintion Notes

- RP CS, RilR, IIPCI, RCIC Pumps Suction Pressure 1 RP-02 CS, RilR, llPCI, RCIC, SW, and SWB Pumps Instrument 1 Accuracy l- ,

RP-03 RiiC Pumps Flowrate Gauge Range 1

- RP RCIC. Pump / Turbine Speed Measurement Range '

RP-05 SW Pumps Differential Pressure i Nets

1 Approved ny NRC letter dated February 19,1997 (TAC NO. M94530) i-1 e

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_ Revision 2 : Section til Page 11 of 21 e

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d COOPER NUCLEAR STATION - ;

TillRD INTERVAL- ,

INSERVICE TESTING PROGRAM -

i j-REllEF REQUEST RP-01 PUMP: Cote Spray CS-P-A, CS P-H

. Residual 'lleat Removal RilR P A. RilR-P-H, RilR-P-C RilR P-D liigh Pressure Coolant injection IIPCI-P MP/HP

_ Reactor Core Isolation Cooling RCIC-P-MP Cl; ASS: 2 ,

FUNCTION: Emergency core cooling.

REQUIRED The full scale range of each analog instrument shall be not greater than TEST: three times the reference value [OMa Part 6,4.6.1.2.(a)].

HASIS FOR The permanently installed suction pressure gauge of a pump is RlillEF: generally sized to accommodate the maximum pressure it 'would experience under normal or emergency conditions. In many cases, this results in an instrument range that exceeds the Code requirements since, under test conditions, normal or emergency condition suction pressures are typically not experienced.

Suction pressure measurements serve two primary functions. First, they provide assurance that the pump has an adequate suction pressure head i for proper operation.- For suction head detennina: ion, the accuracy and L range requirement is overly restrictive. Since, in most cases, plant-pumps are provided with a considerable margin of suction head, an accuracy of 1.0 percent or better is adequate.

J Secondly, the suction pressure is used to determine the pump differential

pressure. When used in determining differential pressure, the accuracy of the suction pressure measurement has little or no effect on the calculation since, generally, the pump discharge pressure is higher than .

the suction pressure by two or three ordets of magnitude.

< ALTERNATE When measuring pump suction pressure, the range requirement of OMa TEST: Part 6, para; 4.6.1- will not be followed, however, instruments used shall

- have an accuracy of 1.0 percent or better.

, i Revision 2- Section 111 Page 12 of 21

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COOPliR NUCLEAR STATION TillRD INTL!RVAL INSliRVICli TliSTING PROGRAM R111.1liF RliQUliST RP-02 PUMP: Core Spray CS-P-A, CS-P-H Residual lleat Removal RilR-P A, RilR-P-B, RilR-P-C, RIIR-P-D liigh Pressure Coolant injection llPCI-P-MP/HP Reactor Core isolation Cooling RCIC-P-MP Service Water llooster SW-P-BPA, SW-P-HPH, SW-P-BPC, SW-P-BPD Cl. ASS: 2 CS, RilR. IlPCI, and RCIC 3 - SW Hooster (SWB)

FUNCTION: CS, RilR, llPCI, RCIC - limergency core cooling.

SWH - Residual heat removal equipment cooling.

RI!QUIRiiD TliST: Instrument accuracy shall be within the limits of Table 1 (OMa Part 6, 4.6.1.1).

HASIS FOR Tl!ST: The percentages of total loop accuracy for the combination of instruments listed below does not meet the requirements of Table 1:

FUNCTION LOOP ACCURACY ( %)

CS Pump Discharge Pressure 2.06 CS Pump Flowrate 2.02 RilR Pump Flowrate 2.08 IIPCl Pump Flowrate 2.03 RCIC Pump Flowrate 2,03 SWB Pump Flowrate 2.03 The difference between the existing hiop accuracy for instrument combiaations and that required by the Code is a maximum of 0.08 percent as exhibited above. This difference is insignificant when compared to the cost of manpower required to obtain the 2 percent accuracy without providing a compensating increase in the level of quality or safety.

Revision 2 Section ill Page 13 of 21

COOPliR NUClJIAR STATION TillRD INTERVAL.

INSliRVICli TESTING PROGRAM Rlil.IliP Rl!QUliST RP-02 Continued Al.TliRNATl!

TliST: Inservice test measurements of pressure and flowrate, as described above, will be made using existing instruments with loop accuracies as indicated.

Revision 2 Section til Page 14 of 21

COOPER NUCLEAR STATION .

TillRD INTERVAL 4

INSERVICE TESTING PROGRAh!

REllEF REQUEST RP 03

PUh1P: Recctor Equipment Cooling REC-P-A, REC-P-B, REC-P-C, REC-P D i CLASS: 3 J

FUNCTION: Provide cooling to critical equipment.

4 REQUIRED TEST: The full scale range of each analog instrument shall be not greater than three times the reference value [Ohta Part 6,4.6.1.2.(a)).

BASIS FOR RELIEF: Permanent plant now gauges, REC-FI-450A and REC-F1-4508, for measurement of REC pump flowrate have ranges of 0-4000 gpm. This does not meet the range limitation imposed by Ohta Part 6,4.6.1.2(a) in that the instrument ranges exceeds the respective reference value (1000 ppm) by greater than a factor of three. Ilowever, the full scale accuracy

, of these gauges is 1.5% which is 60 ppm. '60 gpm accuracy on a range of 0-3000 ppm is 2% which is acceptable per Ohta Part 6,4.6.1.1.

Therefore, now gauges REC-FI-450A and REC-F1-450B are acceptable for nowrate measurement.

ALTERNATE TEST: Ri!C pump inservice test flowrates will be measured via How indicators i REC-F1-4501 and REC-F1-4508.

d i: Revision 2 Section til Page 15 of 21 t

~ - . . . - -. . - . . - . . . - -.-- - . . - - .-. .-.

- COOPER NUCl, EAR STATION TillRD INTERVAL, -

INSERVICE TESTING PROGRAh! '

4 RELIEF REQUEST RP-04 PUhiP: Reactor Core IsoMtion Cooling, RCIC-P-h1P CLASS: 2 FUNCTION: - Emergency core cooling.

REQUIRED _ _

- ~ TEST: The full scale range of cach analog instmment shall be not greater than ,

[ three times the reference value [Ohta Part 6,4.6.1.2.(a)].

1 BASIS FOR Based on previous work history, permanent plant tachometer, RCIC-SI-REl.lEF: 3067, for measurement of RCIC pump / turbine speed, may not provide the required consistency needed for inservice testing unless instrument -

calibration is performed immediately prior to each test. This " extra" calibration places an additional burden on limited Instrument & Control-personnel resources without a compensatmg increase in the level of '

quality and safety.

Iland-held tachometers have proven to be more reliable instruments as far as producing consistent readings. The tachometers available for IST, have ranges of 10-99,999 rpm or 6-30,000 rpm. The respective reference value is 4500 rpm. Therefore, the range limitation imposed by OMa Part 6,4.6.1.2(a) (3 times the reference value or less) is not met by these hand held tachometers.

t Ilowever, the accuracy of the 10-99,999 rpm tachometer is i9 rpm. An instrumental accuracy of i9 rpm on a full range of 0-13,500 rpm (3 x 4500 rpm) would be 10.07 percent of the full range which is better

. _ than the accuracy required by 4.6.1.1 (i.e. 2 percent of full scale).

For the 6-30,000 rpm tachometer, accuracy is i99 rpm. i99 rpm ,

accuracy on a range of 0-13,500 rpm is i0.73 percent which is also better than i2 percent.

Therefore, the proposed range and accuracy results in measurement with accuracy better than Code requirements and will provide reasonable

-assurance of component operational readiness.

-Revision 2 - Section ill Page 16 of 21 -

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COOPl!R NUCl.IIAR STATION TillRD INTERVAL, INSliRVICE TliSTING PROGRAM REl.IliF RiiQUliST RP-04 Continued Al TERIJATli TilST: RCIC pump / turbine speed will be measured via available tachometers identified in the liasis For Relief.

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l Revision 2 Section til Page 17 of 21 !

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1 COOPER NUCl. EAR STATION .

TillRD INTERVAL INSERVICE TESTING PROGRAM-- ,

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. RELIEF REQUEST RP.05 -

i PUMP; = Service Water, SW P-A, B, C, and D

] Cl. ASS: 3-P FUNCTION: Provide cooling for essential systems and components.

REQUIRED .

. TEST: The alert range for differential pressure for vertical line shaft pumps shall be 0.93 to <0.95AP, lOMa Part 6. Table 3b].

- BASIS FOR

. REl.lEF: . Previous experience has shown that the high silt content of Missouri River water decreases the life of the Service Water pump internals.

Under the rules of the 1981 ASME Code, pump differential pressure was allowed to degrade to 0.90AP, before corrective action was required.

When this condition was reached the pump lift was adjusted, the baseline was re-established, and the pump was returned to service. The OM Code requires corrective actior, when the differential pressure is

< 0.95 A P,.

The average differential pressure after a lift adjustment is 63 psid. The required action level would be <58.6 psid. Ilowevr the Service Water pumps can meet their design basis required Dows of 5500 gpm with a minimum differential pressure of 56.2 psid. The new limit in the OM Code results in more frequent pump maintenance. The difference in the acceptance criteria between the 1981 ASME Code and the 1988 OMa l Part 6 is only 39c' . This difference is insignificant when compared to the cost of manpower required to perform pump maintenance without providing a compensating increase in the level of quality or safety.

d.

ALTERNATli TEST:_ The low alert level for the Service Water pumps differential pressure will be 0.90 to <0.93AP,. The low' required action level shall be

<0.90AP,. A pump differential pressure <56.2 psid at 5500 gpm will not be acceptable for continued operation.

Revision 2 Section III Page 18 of 21 M

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COOPER NUCLliAR STATION

.- TillRD INTliRVAl.

INSERVICE TliSTING PROGRAM D. Augmented Pump Relief Requests ju d t Descrintion ARP 01 Elevated Release Point Sump Pump - Alternate Test ARP-02 SI.C Pump Vibration Measurement Revision 2 Section 111 Page 19 of 21

COOPER NUCLl!AR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM AUOMiiNTED RI!!.lliF REQUEST ARP-01 PUMP: RW-P-Z1 and RW-P-Z2 Cl. ASS: A FUNCTION: lilevated release point rump pumps (Z-Sumps) remove water from the sump supporting the Standby Gas Treatment system drains. Pump failure could cause SGT drains line to backup and interfere with SGT operatien.

REQUIRl!D TEST: An inservice test shall be run on each pump, nominally every 3 months, except as provided in OMa Part 6, paras. 5.3, S A, and 5.5. Perform operational readiness testing quarterly, llASIS FOR REl.IliF. These pumps operate intermittently depending on sump level. Testing requires manually providing sufficient sump inventory to facilitate pump operation. The pumps receive automatic actuation signals from sump level switches. Pump testing with insufficient inventory would result in damage to the pumps. Additionally, the pumps are submerged and water cooled. Suction pressure, differential pressure, flowrate, and vibration measurements are not feasible due to inaccessibility, the short time the pump runs, lack of available test instrumentation, and the change in suction pressure throughout the test. These sump pumps are not within the scope of ASME Section XI. NRC approval of this relief request is not required.

AI. TERNATE TEST: The time (TM) to pnmp a specified quantity of water from the sump will be measured and trended. The acceptance range will be between 0.90 to 1.10 TM,, there will not be an alert range, and the required action range will be < 0.00 or > 1,10 Tm,.

Revision 2 Section 111 Page 20 of 21

COOPliR NUCl. liar STATION TillRD INTL!RVAI, INSliRVICli TliSTING PROGRAM AUGMl!NTilD Rl!LiliF RiiQUliST ARP-02 PUMP: SLC.P-A and SLC-P-il Cl ASS: A FUNCTION: The SLC pumps function to pump a boron neutron absorber solution into the reactor if the reactor cannot be shut down or kept shut down with

, trol rods.

Rl!QUIRiiD Vibration meter accuracy shall be +/- Sc4 over the calibrated range TI!ST: [OMa-1988, Part 6. Table 1).

IIASIS FOR The Code requires vibration equipment to be calibcated at +/- Sc4 across Rlil.ll!F: the frequency response range, which includes the minimum frequency response of 1/3 pump shaft speed. For the SLC pumps this is 173.3 rpm or 2.8 liz. The vibration meters used at CNS can only be calibrated at

+/- 5% down to and including 6 liz. Below 6 liz. the accuracy is >

Sr4, however the calibration lab strives to maintain accuracy below 6 Ilz as low as reasonably achievable for the required frequency response range.

The average velocity for an IST test is a single, average energy readiag.

The effect of this change in accuracy, when averaged into the overall reading, is quite small, it would only be a concern if a single frequency in the spectrum were being evaluated between 2 - 6 Ilz. Furthermore, detection of pump degradation via vibration data is based on changes in vibration measurement from one test to another. Thus, if the calibration accuracy is consistent, then the change in vibration measurement from one test to another is appropriate information for trending purposes,-

Therefore, existing vibration equipment will provide adequate trending information and may be used for SLC pump vibration data collection.

ALTIIRNATli Vibration data for the SI.C pumps will be taken with equipment TliST: calibrated from 6 Ilz. to at least 1000 IIz at +/- Sck, and will not be calibrated to +/- 5% or lower below 6 Ilz.

Revision 2 Section til -

Page 21 of 21

w COOPER NUCLEAR STATION

- TillRD INTERVAL j

' INSERVICE TESTING PROGRAM IV. Il311t[G_ PROGRAM FOR VALYES' Ac - Description n The Valve Summary Listing,Section V, identilles the valves included in the CNS IST ,

L Program, the inservice test quantities to be measured, th- test requirements, the test frequencies, references to cold shutdown justifications, refueling outage justifications, valve relief requests, and other pertinent information.

1 11 Cold Shutdown Testing

- For those valves desig::ated to be tested at cold shutdown, testing will commence as n ~ soon as practicable after the plant reaches a stable cold shutdown condition as defined ;

in CNS Technical Specifications, but no later than;48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after reaching cold shutdown, If an outage is suffleiently long enough to allow testing of all valves ,

required to be tested during cold shutdown, then the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months requirement need not apply if all the ; valves are tested during the outage. Furtherraore, valve testing will not necessarily be performed more often than once every three months, Completion of all valve testing during a cold shutdown outage will not be required if plant conditions preclude testing of specific valves or if the cold shutdown duration is insufficient to complete all testing, Testing not completed before startup will be completed during subsequent cold shutdown outages in sequence such that scheduled testing does not omit or favor certain valves or groups of valves, Additional restrictions may be applied as e stated in specific cold shutdown justifications or relief requests. -!

l C. Limiting Values of Full Stroke Times l Where stroke time measurement of power-operated valves is required, the limiting F _ values of full stroke times are based on the valve's reference or average stroke time when it is known to be in good condition and operating properly. Technical L Specifications or safety analysis stroke time limits will be med in lieu of the calculated limiting values of full-stroke time if they are niore restrictive.

~

' in addition, stroke time acceptance criteria are assigned to each valve in accordance with OMa'Part 10 based on valve type and normal stroke times,

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f 4

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COOPER NUCl. EAR STATION

-TillRD INTERVAL,

< +-

LINSERVICE TESTING PWXiRAM 4 i

D. Reference Values

- Stroke time reference values are determined from the results of the previous interval's inservice tests. Refer ace values will be reestablished following valve replacement.

Reference values will only be established when the valve is known to be operating properly.

.When any reference value may have been affected by repair or routine servicing of a

-valve or its control system, a new reference value shall be determined, or the previous values (s) reconllrmed by an inservice test run prior to declaring the valve operable.

Valves may be tested at more than one mode of plant operation. Additional reference

. values must be established for these points in accordance with Code requirements.

?- . Whenever an additional. reference value is established, the reasons for doing so shall be Edocumented in the record of tests.

[ E. Instrumentation Requirements ,

.OMa Part 10 does not stipulate instmment accuracy or range requirements for instruments used in valve testing Any instmments used will be selected to ensure valid test results.

F. Active / Passive Valves For the purpose of IST, active valves are defined as those w.1ich may be required to change obturator position to accomplish their required safety function (s).

Passive vahes are defined as those which are not required to change obturator position

, to accomplish any required safety function (s). Valves that are locked, sealed, or deenergized in their required position are passive. Valves that are not periodically repositioned and whose normal position is the required safety position are considered 4 passive; Valves that are only occasionally repositioned from their safety position to -

support the performance of surveillance procedures or infrequent operations, and are administratively controlled while out of their safety position, are also considered passive.

. Revision 2 Section IV Page 2 of 5

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- COOPER NUCI. EAR STATION-

.TillRD INTERVAL "

l INSERVICE TESTING PROGRAM -

i n G. Fail safe Testing Required fail safe mechanisms are tested by observing the operation of the valve actuator upon loss of actuating power. A valve may fail open or closed by design on a L

loss of actuating power; however, fail-safe testing is performed only if the valve is required to fail to a safety position to mitigate the consequences of an accident, bring the plant to the safe shutdown condition, or maintain the plant in the safe shutdown condition. If a valve is repositioned by the fail-safe position actuator by operation of the control switch, as is the case with most air operated valves, quarterly exercise test satisfy fail-safe test requirements and no special tests need be performed. All CNS

motor operated valves fail "as is"; therefore no fail-safe tests are required for these valves. .

$ II. Valve Position Indication Verification The valve position indicators on active and passive valves are verified at least once every two years. Per NUREG-1482, Section 4.2.6, only the position indicators at the

remote location used for exercising and stroke timing a valve need be verified for those valves equipped with remote position indicators in multiple locations.

The valve position indicators on passive manual valves are also verified at least once every two years. Passive manual valves that are locked, sealed, or tagged are provided for system or component maintenance and testing. These valves are excluded by OMa

Part 10, para.1.2(a), and are not subject to position indication verification.

r I. Water Scaled Valves I

b Valves on piping systems that penetrate the torus and terminate below the minimum water level of the suppression pool are considered water scaled. This seal is a barrier i- against bypass leakage of the post accident gaseous primary reactor containment atmosphere to the environment. Loss of coolant accident analyses and the postulated -

containment response to these types of accidents are based on this minimum water level being maintained post-accident. Therefore these valves will remain water scaled.

These valves are considered Category H per OMa Part 10, and are not required to be tested in accordance with 10CFR50 Appendix J, Section Ill.C.2..

The discharge lines for several relief. valves are directed to the suppression pool and art.

also water scaled. These relief valves are located in systems which are normally in i

Section IV

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COOPliR NUCl. liar STATION TillRD INTERVAL, INSliRVICl! Tl! STING PROGRAM operation following an accident, such as the Core Spray and Residual lleat Removal systems. The seat tightness of these valves is verified during relief valve testing, Additionally, all flanges in the relief valve discharge lines are of testable design and are leak rate tested. Since these relief valves are water scaled, they do not present a credible leakage path from the primary containment to the environment and no additional leak rate testing is performed.

J. Check Valve Testing Only valves that have a specified maximum required accident flow are subject to position 1 of Generic letter 89-04. Either the How through the valve is measured or other quantitative parameters with acceptance criteria are monitored to demonstrate required now threugh the valve. Check valves that do not have a specified maximum required accident now are tested to the open position by either flow or other positive means. Per OMa Part 10 para. 4.3.2.4(c), check valves may be disassembled, manually exercised, and inspected in lieu of How (or now reversal) testing as described in the Code. Non-intrusive. methods, such as radiography, may be used to verify valve position.

K. Relief Valve Testing Only relief valves that have a specified safety function for over pressure protedion of systems, or portions of systems, which perform a specific function in mitigating the consequences of an accident, bring the plant to a safe shutdown condition, or maintaining the plant in a safe shutdown condition, are included in this program.

Relief valves that are provided for over pressure protection of individual components due to thermal expansion when they are isolated (thermal reliefs) are excluded from testing.

OMa Part 10 Section 4.3.1, requires safety and relief valves to be tested in accordance with OM Part 1. If the "as found" lift set point of a valve is out-of-tolerance, then two additional valves from the same sample group shall be tested. If any of these additional valves fail to meet the set point acceptance criteria, then all valves in that sample group shall be tested. Relief valve sample groups shall contain only valves of the same manufacturer, type, system application, and service media. All test failures shall be evaluated for generic concerns; however, additional testing of valves outside the sample group shall not be required unless the evaluation determines that the operability of other valves may be in question.

Revision 2 Section IV Page 4 of 5

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I l-COOPliR NUCl. EAR STATION TillRD INTliRVAl, INSERVICli TESTING PROGRAM:

Per NUREG 1482, Section 4.3.6, when the test of a safety or relief valve fails due to out-of tolerance set point, an adjustment of the set point is an acceptable corrective action in lieu of repair or replacement of the valve, provided the lift set point is within tolerance during the subsequent retest.

OMa Part 10, Section 4.4.2, requires rupture disks to be tested in accordance OM Part

1. Rupture discs will be replaced every five years after the implementation of the third interval program in accordance with OM Part 1, para.1.3.4.2. The replacement

- rapture discs will be receipt inspected in accordance with plant procedures, l.. Vacuum Ilreaker Testing Vacuum breakers that are simple check valves are required to be full-stroked exercised in accordance with OM 10, and set point tested in accordance with OM 1-1987. Since OM-1 is not clear as to the testing frequency for vacuum breakers, CNS has elected to follow the later guidance of the OM 1 committee and will test vacuum breakers to verify set point, opening, and closing functions, once per refueling cycle. Vacuum a breakers will not be full stroked exercised per OM 10. Seat leakage tests will only be performed on vacuum breakers that are part of the primary containment boundary or.

that have a specified leakage limit.

Revision'2 Section IV -.

Page 5 of 5

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COOPliR NUCl. EAR STATION TillRD INTliRVAL INSliRVICE Tl! STING PROGRAh!

V. VALVE

SUMMARY

LISTING A. Notations The following notations are used in the valve sununary tables:

SYSTliht: The plant system in which the component is located.

VAIN!! CIC: The component identification code.

P&lD: The associated piping and instrumentation drawing number.

P&lD COOR: The drawing coordinate location for the component.

ISI C1. ASS: The AShiliinservice inspection (ISI) classification of the component. Augmented components are classified "A" IST CAT: The category or categories assigned to the valve based on the defiintions in Ohta Part 10, Section 1.4.

VAINE SIZE. The nominal size of the component in inches.

VAINii TYPli The component body design as indicated by the following abbreviations:

ANG Angle IIAL llall IITF llutterfly CK-li llall Check CK-D Dual Disk Check CK-L Lift Check CK-P Piston Check CK-S Swing Check CK-T Tilting Disk Check DIA Diaphragm FOV Float Valve Gil Globe Revision 2 Section V Page 1 of 155

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COOPliR JUCl. liar STATION TillRD INTliRVAl.

INS!!RVICII TliSTING PROGRAh!

O'I Gate RD Rupture Disk RV Relief / Safety SOV Solenoid Valve S-CK Stop Check Si!R Squib ACT TYPli: The type of actuator as indicated by the following abbreviations:

AO Air Operated

!!X lixplosive Charge 11 0 liydraulle Operated h1A hianual MO hiotot Operated SA Self Actuated SO Solenoid Operated PA Pilot Actuat::d NORMAL POS: The normal position of the valve, specified as follows:

O Open C Closed T Throttled TliST RQMT: The test (s) that will be performed to fulfill the requirunents of OMa Part 10. The abbreviations are as follows:

1J-l 1.cakage test in accordance with the CNS Appendix J l'rogram IJ-2 lixcess flow check valve leakage test in accordance with the CNS Technical Specifications ill' l I.eakage test of air / nitrogen accumulator check valves 111'- 2 1.cakage tests othei than those already specified l'SO Full stroke exercise test to the open position (includes stroke time measurement except for Revision 2 Section V Page 2 of 155

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COOPER NUCLEAR STATION i TillRD INTERVAL INSERVICE TESTING PROGRAM -

check valvesand menual valvesi FSC Full stroke exercise test to the closed position ;

-(includes stroke time measurement except for check valves arvi cnanual valves)

-PSO Partial stroke exercise to the open position PSC Partial stroke exercise to the closed position FST Fail safe position test (includes stroke time 4' measurement unless otherwise noted) 4 PIT Position indication test

-RD Rupture Disc test per OM-1 RVT - Set point test of safety / relief valves per OM-1

. EX Explosive valve test VBT Vacuum breaker testing per OM-1 ,

, . FREQUENCY: The frequency of testing each valve, specified as follows:

t Q -Quarterly test CS Cold shutdown .

RF Refueling outage 2Y At least once every 2 years 5Y- At least once every live years per OM-1 10Y At least once every ten years per OM-1 1'

NOTES: This column contains a brief component description,

(

references any applicable cold shutdown test justifications (s), refueling outage justification (s), relief request (s), and contains any other component related

< - information. All valves are considered " active" unless

- otherwise noted in this column. Cold shutdown .

justifications are designated CSJ-XX; Refueling Outage p justifications are designated ROJ-XX; Relief Requests are designated RV-XX. Augmented Cold shutdown .

justifications are designated ACSJ XX; Augmented Refueling Outage Justifications are designated AROJ-XX; Augmented Relief Requests are designated ARV-XX.

Revision 2 - Section V Page 3 of 155 1

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: CONTROL ROD DRIVE (CRD) 4 VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NOR$1 TEST TEST NOTES /DESCRIPliON COOR CLASS CAT SIZE TYPE ~YPE POS RQ%IT FREQ CRD AOV-CV32A 2039 113 2 B I GB AO O FSt? Q SOUTil SDIV INBOARD VENT FST Q ISOLATION VALVE PIT 2Y CRD-AOV-CV32B 2039 I!4 2 B 1 GB AO O ESC Q NORTil SDIV INBOARD VENT FST Q ISOLATION VAL'/E PIT 2Y CR D- AOV-CV33 2039 112 2 11 2 GB AO O FSC Q SOUTil SDIV INBOARD DRAIN FST Q ISOLATION VALVE PIT 2Y CRD AOV-CV34 2039 !!4 2 B 2 GB AO O FSC Q NORTil SDIV INBOARD DRAIN FST Q ISOLATION VALVE PIT 2Y CRD-AOV CV35 2039 112 2 B 2 GB AO O FSC Q SOUTil SDIV OUTBOARD DRAIN FST Q ISOLATION VALVE ;

PIT 2Y CRD- AOV-CV36 2039 114 2 B 2 GB AO O FSC Q NORTil SDIV OUTDOARD DRAIN FST Q ISOLATION VALVE PIT 2Y CRD-AOV-CV38A 2039 113 2 B 1 GB AO O FSC Q SOUTil SDIV OUTBOARD VENT FST Q ISOLATION VALVE PIT 2Y CRD-AOV-CV38B 2039 H4 2 B 1 GB AO O FSC Q NORTil SDIV OUTBOARD VENT FST Q ISOLATION VALVE PIT 2Y Resision 2 Secthm V Page 4 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES l

SYSTDI: CONTROL ROD DRIVE (CRD)

VALVE CIC P&lD . P&ib ISI IST VALVE VALVE ACT NORN1 TEST TEST NOTES / DESCRIPTION l COOR CLASS CAT SIZE TYPE TYPE POS RQNIT FREQ CRD-AOV CV126 2039 C10 2 B I DIA AO C FSO RF SCRA%1 OUTLET.

GYP. OF 137) FST RF RV4)2 CRD-AOY CV!27 2039 B10 2 B 3/4 DIA AO C FSO RF SCRAM OUTLCT.

(TYP. OF 137) FST RF RV-02 CRD-CV-13CV 2039 A9 1 A!C 3 '4 CK-P SA O U-l RF CRD WATER TO REACTOR FSC RF RECIRCULATION PUMP A. ROJ411 CRD CV-14CV 2039 B9 1 A!C 3 /4 CK-l' SA O U-l RF CRD WATER TO REACTOR -

FSC RF RECIRCULATION PU?tP A.' ROJ4)I CR D-CV-15CV 2039 A8 i A!C 3/4 CK-P SA O U-l RF CRD WATER TO REACTOR ;

FSC RF RECIRCULATION PUMP B. RON11 5 CRD CV-16CV 2039 88 i A!C 3/4 CK-P SA O U-I RF CRD WATER TO REACTOR FSC RF RECIRCULATION PUMF B. ROJ411 CRD-CV-25CV 2039 IM A AiC I 1/2 CK-S SA O LT-2 RF CRD SYSTEM ISOLATION CI!ECK FSC CS VALVE. ACSJ4)I CRD-CV-26CV 2039 I;4 A A!C 1 !!2 CK-S SA O LT-2 RF CRD SYSTEM ISOLATION CllECK FSC CS VALVE. ACS14fl CRD-CV-2MCV 2039 12 A C 1/2 CK-P SA C FSO CS SOUTil SDIV DRAIN VALVE AIR SUPPLY BYPASS CV CRD-CV-29CV 2039 J4 A C 1/2 CK-P SA C FSO CS NORTil SDIV DRAIN VALVE AIR SUPPLY BVPASS CV CRD-CV-32CV 2039 J2 A C I/2 CK-P SA C FSO CS SOLTril SDIV DRAIN VALVE AIR SUPPLY BYPASS CV Revision 2 Section V Page 5 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIA1ARY TABLES l

SYSTEM: CONTROL ROD DRIVE (CRD)

VALVE CIC P&lD PAID ISI IST ' VALVE VALVE ACT NORht TEST TFST NOTES DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ CRD-CV-33CV 2039 14 A C 1/2 CK-P SA C FSO CS NORT11 SDIV DRAIN VALVE AIR SUPPL) BYPASS CV CRD-CV-CVil4 2039 Bil 2 C 3C CK-B SA O FSO RF SCRAM OUTLET CilECK VALVE.

frYP OF 137) RV412 CRD-CV-CVil 5 2039 D9 2 C I/2 CK-B SA O FSC RF SCRAM INLET CIIECK VALVE.

(TYP. OF 137) RV4)3 CRD CV-138 2039 C9 2 C II2 CK-B SA O FSC Q COOLING' SCRAM llEADER (TYP. OF 137) CllECK VALVE. RV-OS CRD-SOV-SO120 2039 BIO 2 B 1/4 SOY SO C FSC Q CRD WITilDRAWAL EX11AUST (TYP. OF 137) FST Q VALVE. RV-05 CRD-SOV-sol 2i 2039 B!O 2 B 1/4 SOV SO C FSC Q CRD INSERT EXilAUST frYP. OF 137) FST Q VALVE. RV-05 CRD SOV-SOI22 2039 BIO 2 B I/4 SOV SO C FSC Q CRD WITilDRAWAL VALVE.

(TYP. OF 137) FST Q RV45 CED-SOV-SO123 2039 HIO 2 B 1/4 SOV SO C FSC Q CRD INSERT VALVE, crvP or 1176 . rsT n ev sn ._

Revision 2 Section V Page 6 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUA131ARY TABLES I

SYSTDI: CORE SPRAY (CS)

PalD 151 IST VALVE VALVE ACT NORM TEST TEST A EGC ND COOR CLASS CAT SIZE TYPE TYPE POS RQNIT FREQ CS-CV-10CV 2(M5 F4 2 C 12 CK-5 SA C FSO Q CS PUMP A DISCIIARGE C!!ECK CS-CV-I ICV 2045 D4 2 C 12 CK-S SA C FSO Q CS PUMP B DISC 11 ARGE C11ECK _

CS-CV-12CV 2445 G5 A C 2 CK-P SA C FSC Q CS LOOP A OUTBOARD PRESSURE M AINTENANCE SUPPLY. RV4h CS-CV-13CV 2(MS G5 2 C 2 CK-P SA C FSC Q CS LOOP A INBOARD PRESSURE M AINTENANCE SUPPLY. RV4M CS CV-14CV 2M5 D5 A C 2 CK-P SA C FSC Q CS LOOP B OUTBOARD PRESSURE M AINTEN ANCE SUPPLY. RV4h CS-CV-15CV 2045 D5 2 C 2 CK-P SA C FSC Q CS LOOP B INBOARD PRESSURE MAINTENANCE SUPPLY. RV4%

CS f V-18CV 2045 C6 I A!C 10 CK-S SA C 13-1 RF CS SYSTEM A TESTABLE CllECK LT-2 RF CS!4)1 FSO CS FSC CS PIT 2Y CSCV-19CV 2045 B6 1 A/C 10 CK S SA C IJ-l RF CS SYSTE\1 B TESTABLE CilECK LT-2 RF CSI-01 FSO CS FSC CS PIT 2Y CS-MOV-MO5A 2n*5 E4 2 B 3 GT MO O FSO Q CS PUMP A MINIMUM FLOW FSC Q RECIRCULATION ISOLATION PIT 2Y Revision 2 Sectmn V Page 7 of 155 t

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTEM: CORE SPRAY (CS) f l VALVE CIC P&lD

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE 1 TYPE POS RQMT FREQ _

CS-MOV-MO5B 2tMS IM 2 B 3 GT MO O FSO Q CS PUMP B MINIMUM FLOW FSC Q RECIRCULATION ISOLATION PIT 2Y "l CS MOV4107A ' lim 5 F2 2 B i4 GT MO O FSO Q CS PUMP A SUCTION l FSC Q PIT 2Y CS410V4107B 2(45 D2 2 B 14 GT MO O FSO Q CS PUMP B SUCTION FSC Q PIT 2Y CS410V-Moll A 2fM5 F5 2 B 10 GT MO O FSO Q LOOP A INJECTION T11ROTTLE PIT 2Y CS-MOV-Moll B 2(45 D5 2 B 10 GT MO O FSO Q LOOP B INJECTION TIIROTTLE PIT 2Y CS410V41012A 2(45 F6 1 A 10 GT MO C LI-I RF LOOP A INJECTION BLOCK LT-2 RF FSO Q FSC Q PIT 2Y CS410V41012B 2(45 IM 1 A 10 GT MO C LI-I RF LOOP B INJECTION BLOCK LT-2 RF FSO Q j FSC Q PIT 2Y CS-MOV41026A 2(M5 F5 2 B 10 GB MO C PIT 2Y CS PUMP A TEST LINE PASSIVE ISOLATION Revision 2 Section V Page 8 of 155

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUAIAIARY TABLES SYSTDI: CORE SPRAY (CS)

P&lD 151 IST VALVE VALVE ACT NOR31 TEST TEST VALVE CIC P&ID '

CAT l COOR CLA3s SIZE TYPE TYPE POS RQN!T l FREO CS410V41026B 2N5 C5 2 B 10 GB 51 0 C PIT 2Y CS PU%1P B TEST LINE PASSIVE ISOLATION CS-R V-10RV 3MS F2 2 C 3/4 RV SA C RVT 10Y CS PUhfP A SUCTION RELIEF CS RV-11RV 2N5 F4 2 C 2 RV SA C RVT IOY CS PUNIP A DISCilARGE RELIEF CS-RV-12RV 2N5 C3 2 C 3/4 RV SA C R\T 10Y CS PUN 1P B SUCTION RElJEF C3-RV-11RV 2M5 C4 2 C 2 RV SA C RYT 10Y CS PUNIP B DISCIIARGE RELIEF t

Revision 2 Section V Page 9 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTDI: DDIINERALIZED WATER SYSTDI (DW)

P&lD IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION -

V ALVE CIC PAID 151 COOR CLASS CAT SIZE TYPE TYPE POS RO\1T FREQ DW-V-133 2029 G8 2 A 4 GT MA C U-l RF PASSIVE DRYWELL GUTBOARIi SUPPLY VALVE DW-V-219 2029 G8 2 A 4 GT MA C U-l RF PASSIVE DRYWELL NBOARD SUPPLY VALVE Revision 2 Section V Page to of 155

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COOPER NUCLEAR STATION TIIIRD INTERVAL .

INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES SYSTE31: DIESEI, GENERATOR (DG)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTFS11ESCRIPT10N COOR CLASS CAT SIZE TYPE TYPE POS RQNIT FREQ DG- AOV-M BI KSV- C2 A B 30 BFL AO C FSO Q DGI SIUFFLER BYPASS VALVE, 943 FST Q ARV4)3 DG-AOV- A182 KSV- C2 A B 30 BEL AO C FSO Q DG2 51UFFLER BYPASS VALVE.

96-3 FST Q ARV4)3 Revision 2 Section V Page 1I of 155 f

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3 DIARY TABLES SYSTEM: DIESEL GENERATOR DIESEL OIL GX;DO) 1 i

- I VALVE CIC P&ID P&ID 151 IST VALVE VALVE ACT NOR.\1 TTST TEST NOTES DESCRIPTION !

COOR CLASS CAT SIZE TYPE TYPE POS RQ\lT FREQ DGDO-CV-10CV 2011 AM A C 2 CK-P SA C FSO Q DGDO TRA%FLR PU%fP A 511 1 DISC 11 ARGE DGDO-CV-1 ICV 2011 A10 A C 2 CK-P SA C FSO Q DGDO TRANSFER Pt31P B Sil I DISrilARGE DGDO-CV-12CV 2011 A4 A C 2 CK-P SA C FSO Q DGDO DAY TANK I INLET Sil i FSC Q IXiDO CV-13CV 3)11 IM A C 2 CK-P SA C FSO Q DGDO DAY TANK 2 INLET 511 1 FSC Q

, DGDO-FOV-F LTV10 NT77 Ill A C 3. 4 FOV SA OC FSO Q DGDO DAY TANK I INLET FLOAT FSC Q VALVE. ARV all DGDO FOV-FLTVII 3177 116 A C 3/4 FOV SA OC FSO Q DGDO DAY TANK 2 INLET FLOAT FSC Q VALVE.ARV41 ;

i DGDO RV-10RV 3777 I!2 A C 3 '4 'V SA C RVT 10Y DGDO Pt StP 1 SUCT10N RELILF !

DGDO-RV-11 RV 2077 IIS A C 3/4 RV SA C RYT 10Y DGDO M31P 2 50CT10N RELIEF DGDO SOV- 3177 II: A d 3 'A SOY SO OC FSO Q DGCO DAY TANK I INLET F8 EL SSV5028 FSC Q SAFLTY YALVE. ARV41 FST Q DGDO SOV- 2077 , 116 A B 3'4 SOY SO OC FSO Q DGDO DAY YANK 2 INLET FUEL SSV5029 FSC Q SAFETY VALVE. ARV41 FST Q Revision 2 Sectxm V I%re 12 of 155

COOPER NUCLEAR STATION THIRD INTERVAL !

i INSERVICE TESTING PROGRA31 !

VALVE SU3131ARY TABLES SYSTDI: DIESEL GENERATOR STARTING AIR (DGSA)

VALVE CIC P&lD PAfD ISI IST VALVE VALVE ACT NORSt TEST TEST NOTES DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQ\lT FREQ DGSA-AOV-AV5 117.10 E3 A B 2 I/2 GB AO C FSO Q DG-1 LEFT BANK STARTING AIR i

-IC## FSC Q VALVE. ARV412 FST Q DGSA-AOV-AV6 117.10 E3 A B 2 IJ2 GB AO C FSO Q DG-2 LEFT BANK STARTING AIR [

j -lC4f) FSC Q VALVE.ARV412 FST Q >

I DGSA-AOV-AV7 117.10 El A B 2 1/2 GB AO C FSO Q DG-1 RIGIIT BANK STARTING AIR !

-IC## FSC Q VALVE. ARV-02 FST Q

DGSA-AOV AV8 117.10 El A B 2 1/2 GB AO C FSO Q DG-2 RIGIIT BANK STARTING AIR

-IC#7 FSC Q VALVE.ARV42 FST Q DGS A-CV-10CV 2077 DS A C 2 CK-L SA C FSO Q STARTING AIR CON 1 PRESSOR I A FSC Q DISCIIARGE DGSA CV-IICV N77 D8 A C 2 CK L SA C FSO Q STARTING AIR CON 1 PRESSOR IB 4 FSC Q DISCIIARGE

! i i

DGSA-CV-12CV 2077 DIO A C 2 CK-L SA C. FSO Q STARTING AIR COS1 PRESSOR 2B I '

FSC Q DIScliARGE i DGSA-CV-13CV 2077 DIO A C 2 CK-L SA C FSO Q STARTING AIR CO\1 PRESSOR 2A FSC Q DISCIIARGE DGSA-CV-14CV 2077 C8 A C 2 CK-S SA C FSO Q AIR RECEIVER 1 A INLET. ACS1412 i

! rSC CS DGSA-CV-15CV 2077 C8 A C 2 CK-5 SA C FSO Q AIR RECEIVI R IB INLET. ACSID2 FSC (3 l Revision 2 Section V IWe 13 (4155

COOPER NUCLEAR STATION THIRD INTERVAL '

l INSERVICE TESTING PROGRA31 VALVE

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR STARTING AIR (DGSA)

-~ -

j P&lD P11D ISI IST VALVE VALVE ACT NOR.\t TI.ST TEST NOTES T)ESCRIFI10N 1

lVA!XECir g

COOR CLASS CAT SIZE TYPE TYPE POS RQ\fT FREQ

] DGSA CV iv'Y ,

2077 CIO A C 2 CK-S SA C FSO Q AIR RECEIVER 2A INIE. ArSlac 1 l FSC CS i 4

OGSA CV-17CV 2077 CIO A C 2 CK-S >A C FSO Q AIR RECEIVER 2BINLET. ACSJ4C I FSC CS !

DGSA CV-IRCV 3m B7 A C 3 CK-5 SA C FSO y AIR RECEIVER 1 A Ot TLET FSC Q !

DGS A-CV-19CV 2077 Bx A C 3 CK-S SA C FSO Q AIR RECEIVER 18 OtMET f FSC Q t j DGSA CV-3CV 2077 B10 A C 3 CK-S SA C FSO Q AIR RECEIVER M 00 TLLT L FSC Q DGSA-CV-2 t CV 2077 BII A C 3 CK-S SA C FSO Q AIR RECEIVER 2B OUTLET FSC Q

. DGSACV-32CV 117.1 F5 A C 174 CK-S SA C FSO Q DGI LEFT BANK AIR START ,

j alC- FSC Q SilUTTLE VALVE I 4

m ;

i DGSA CV-33CV 117.1 FI A C I/4 CK-5 SA C FSO Q DGI RIGirr BANK AIR START ,

O IC- FSC Q SIIUTTLE VALVE I 09 !

I DGSA-CV-34CV 117.1 F5 A C 1/4 CK-S SA C FSO Q DG2 LEIT BANK AIR START !

O IC- FSC Q SIIUTTLE VALVE !

09 i DGSA-CV-35CV I17.1 FI A C 1/4 CK-5 SA C FSO Q DG2 RIGIIT BANK AIR START j 0-IC- FSC Q SlitTTTLE VALVE l l o9 Remnm 2 Sectum V Page 14 of 155 i

i COOPER NUCLEAR STATION I THIRD INTERVAL '

INSERVICE TESTING PROGRA31 l VALVE SU313tARY TABLES i

.i V

SYSTE31: DIESEL GENERATOR STARTING AIR (DGSA)

VALVE CIC P&lD PilD 151 IST VALVE VAL \E ACT NORM TEST TEST NOTES DESCRIPTION COOR CLASS CAT SIZE TYPE Em RQMT FREQ TYQ

, DGSA-SOV-SPVI 117,10 F5 A B 10 GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC4N FSC Q DGSA-AOV-AV5 tDGI LLFT BANK). t FST Q ARV412 ,

DGSA-SOV-SPV2 117.10 F5 A B 10 GB SO C FSO Q SOLENOID PILOT VALVE fOR ;

-IClN FSC Q DGS 4 AOV-AV6 tDG2 LFFT B ANK). ;

FST Q ARV4P l

DGS A-SOV SPV3 117.10 FI A B 12 GB SO C FSO Q SOLENOID PILOT VALVE FOR l 1 -ICAN FSC Q DGSA AOV-AV7 (DGI RIGitT BANK >.

FST Q ARV4C '

DGSA SOV-SPV4 117.10 F1 A B IO GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC#) FSC Q DGSA-AOV-AVE 4DG' RIGliT BANK).

FST Q ARVJ)2 DGS A-RV-14RV 2077 B7 A RV I RV SA C RVT 10Y DGSA AIR RECEIVER 1 A RE13EF j DGSA-RV-15RV 3P7 BR A RV I RV SA C RVT 10Y DGSA AIR RECEIVER IB RELIEF DGSA RV-16RV 2077 B10 A RV 1 RV SA C RVT 10Y DGSA AIR RECEIVER IC RELTEF I i

i DGSA-RV-17RV 2077 BI1 A RV I RV SA C RVT 10Y DGSA AIR RECEIVER ID RELIEF ,

I f

i i

4 i

Revism 2 Sectum V Page 15. ii 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SUA1MARV TABLES I

3Y$TDI: IIIGli PRESSURE C(XEAST INJECTION (IIPCI)

A EN PilD ISI IST VALVE VAL \E ACT NORSt TEST TEST P11D COOR CLASS CAT SIZE TYPE TYPE POS RQ\tT FREQ IIPCI-AOV-AG32 2021 G5 2 B i GB AO O FSC Q STEA%f UNE DRIPLEG DRAIN FST Q PIT 2Y IIPCI-AOV-A070 3 41 E9 2 A 1 BAL AO C U-l RF llPCI EXIIAUST BOOTLEG DRAIN FSC Q INBOARD

; FST Q 1

PIT 2Y t itPCI AOV-A071 3 41 E9 2 A 1 BAL AO C U-I RF IIPCI EXIIAUST BOOTLEG DRAIN FSC Q OUTBOARD FST Q 1

PTT 2Y

! IIPCI-AOV PCV50 2013 G4 2 B 2 GB AO O PSO Q IIPCI AUXIUARY COOUNG SUPPLY FSO CS PRESSURE CONTROL.

FST CS CSI 4)3 IIPCI CV-10CV 2444 13 2 C 16 CK-S SA C FSO Q ECST SUPPLY TO IIPCI PUNIP.

i i FSC CS CSI-Il liPCI CV-1 ICV 2324 1110 2 C 16 CK-S SA C FSO RF IIPCI PUStP SUCTION FRO %1 FSC RF SUPPRESSION POOI ROJ42 IIPCI CV-13CV 2324 115 2 C 4 CK-S SA C FSO Q IIPCI AUXIUARY COOUNG RETURN FSC Q IIPCI CV-14CV 2(44 11 5 2 C 2 CK-P SA C FSC Q 11PCI CONDENSATE PU5tP DL%CIIARGE TO AUXIUARY l C001 ING RETURN Revnion 2 Sectiam V Page 16 of 155 L

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SL3IMARY TABLES SYSTDI: IllGII ITFSSURE COOLANT INJECTION OIPCI)

VALVE CIC P&lD

' ^ ^ ^ '

NOTES DESCRIPTX)N COOR CLASS CAT SI7.E TYPE TYPE POS RO%fT FREQ ,

ifPCI-CV-15CV 3M4 D9 2 A--C 20 CK-5 SA C 13-1 RF IIPCI TURBINE EXilAUST. ROJ40

. FSO Q ,

FSC RF '

IIPCI-CV-16CV 3 44 F9 2 C 2 CK-P SA C FSC RF IIPCI TURBINE EX*lAUST DRAIN TO ;

SUPPRESSION POOL ROJ48 j IIPCI CV-17CV 344 D6 2 C 4 CK-S SA C PSO Q liPCI PD1P SilNI\ tat FLOW LINE.

FSO RF ROJiO. ROJ N l l 13C RF !

' l IIPCI-CV-1NCV 344 B8 2 C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO IIPC1 j I

SYSTTiSt. RV417 !

t I

11PCI-CV-19CV 3 44 B3 A C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO IIPCI

, SYSTE%t. RV4)7 I

IIPCI CV-24CV 2fM4 E10 2 C 3 CK-5 SA C VBT RF IIPCI VACIM1 BREAKER. RV-14 IIPCI CV-25CV 2044 Ell 2 C 3 CK-S SA C VBT RF IIPCI VACUU%1 BREAKER. RV-14 IIPCI-CV-26CV 2044 E10 2 C 3 CK-S SA C VBT RF IIPCI VACUUAf BREAKER. RV-14 IIPCI-CV-27CV 2nta El1 2 C 3 CK-S SA C VBT RF IIPCI VACUU%1 BREAKER. RV-14 IIPCI-CV-29CV 2n44 C9 I A/C 14 CK-S SA C LI-I RF INJECTION CIIECK VALVE. CSJ412 t FSO CS FSC CS ,

PfT 2Y l

IIPCI N10V-MOI 4 3Mt G3 2 B 10 GT AfD C FSO Q STEA%1 SUPPLY TO TURBINE PIT 2Y Rensm 2 Sectum V Page 17 of 155 t

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA3I '

VALVE SU3131ARY TABLES SYSTEM: IIIGII PRESSURE COOLANT INJECTION (IIPCO VALVE Cie P&ID

' ^ ^ ^ '

COOR CLASS CAT NOTES DESCRIPTION 4 SIZE TYPE TYPE POS RQ\tT FREQ

! IIPClatOV-MOIS 2tMi D5 I A 10 GT MO O U-I RF STFAM SUPPLY INBO ARD l FSC Q ISOIAllON l PTT 2Y ;

j t l IIPCI-MOV4f Ol6 3MI D4 I A 10 GT M0 , O U-I RF STEAM SUPPLY OUTBOARD ,

q FSC Q ISOLATION

PIT 2Y

{ IIPCI-MOV-Mol7 3M4 13 2 B 16 GT MO O FSO Q PUMPSUCTION FROM EMERGENCY FSC Q CONDENSATE STORAGE TANK f 1

PIT 2Y liPCI-MOV-MOl9 2044 C8 2 B I4 GT MO C FSO Q IIPCI INJECTION PIT 2Y

' i IIPC1410V-MO20 3 44 C8 2 B 14 GT MO O FSO -Q 11PCI PCMP DISCIIARGE '

PIT 2Y IIPClatOV-MO21 2iM4 D3 2 B 10 GB MO C PIT 2Y liPCI PUMP TEST BYPASS TO EMERGENCY CONDENSATE ;

STORAGE TANK I IIPCI-MOV-MO24 2tM4 E3 A B 10 GT MO O PTT 2Y IIPCI PUMP TEST BYPASS g

] REDUNDANT SIIUTOFF l l

! IIPCl410V-MO25 3M4 D7 2 B 4 GB MO C FSO Q IIPCI PUMP MINIMUM FLOW FSC Q BYPASS UNE ISOLATION ,

Prr 2Y i

i l Rensinn 2 Sectxm V Page 18 of 155 .

1- COOPER NUCLEAR STATION ,

i THIRD INTERVAL 4

INSERVICE TESTING PROGRA31 !

! VALVE SU3131ARY TABLES i j SYSTDI: IIIGli PRESSURE COOIANT INJECTION (HPCI) i i

VALVE CIC' PAID

^ ^ ^ NOTES. DESCRIPTION

COOR CLASS CAT SIZE TYPE TYPE POS RQ\tT FREQ I !

j. IIPCI-510V 51058 2044 G10 2 B 16 GT %10 C FSO Q llPCI PU%1P SUCT10N FRO %1 i FSC Q SUPPRESSION POOL PIT 2Y I

l IIPCI RD-S241 2M4 D5 2 D 16 RD SA C RD SY EXil AUST LINE RUPTCRE DISK IIPCI RV-!URV 5 44 J3 2 C i RV SA C RYT 10Y llPCI PU%tP SI'CTION REUEF IIPCI RV-12RV 2044 G5 2 C l RV SA C RVT 10Y IIIT1 AUXILIARY COOLING WATER StmY ;

i IIITI-SOV SSV64 2n14 F4 2 B 1 SOV SOY C FSC Q IIPCI EN!!AUST DRIP LEG DRAIN. i FST Q RVJM ;

! !!PCI SOV SSV87 2044 F4 2 B 1 SOV SOV C FSC Q IIPCI TURBINE DRIP LEG DRAIN.

l FST Q RV4R IIPCI-V-44 2044 D9 2 C N 5-CK SIA O U-I RF IIPCI TURBINE EXIIAUST TO ,

FSO Q SUPPRESSION POOL ISOLATION. !

FSC RF ROJ4M i i l IIPCI-V-50 2G44 F9 2 C 2 S-CK StA O FSC RF TURBINE DRAIN TO SUPPRESSION :

i POOL ISOIATION. ROJ 4M a !

I i

i Revishm 2 Sectkm V Page 19 of 155 l

4 COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUM 31ARY TABLES i

l SYSTDf: IIEATING AND VENTILATION (IIV)

VALVE C1C P&lD P&lD ISI IST VALVE VALVE ACT NORAt TEST TEST NOTES DESCRIPTION i COOR CLASS CAT SIZE TYPE TYPE POS RQ\fT FREQ 4

i !

! IIV-AOV-257AV 203) D2 A B 72 IN BTF AO O FSC Q REACTOR BUILDING VENELATION ;

I FST Q OUTBOARD SUPPLY PTT 2Y liv-AOV-159AV 3LM B12 A B 72 IN BTF AO O FSC Q REACTOR BUILDING VENillADON [

FST Q INBOARD EXil AUST !

PIT 2Y IIV-AOV-261 AV 3 05 B12 A B 72 IN BTF AO O FSC Q REACTe2 BUILDING VENRIATION

! FST Q INBOARD EX11AUST i P!T 2Y i r IIV-AOV-263AV 3LT E9 A B 72 IN BTF AO O FSC CS I EACTOR NtG SET 1A VENTILATION A

l. FST CS OUTBO \RD SUPPLY. ACSJ4)3 PTT 2Y IIV-AOV-265AV 203) E9 A B 72 IN BTF AO O FSC CS REACTOR AfG SET IB VENTILATION l FST CS OUTBOARD SUPPLY. ACSJ43 rri 2Y llV-AOV-267AV 3120 Dil A B 72 IN BTF AO O FSC CS REACTOR SIG SET I A VENRLAT1GN FST CS INBOARD EXIIAUST. ACSJ4)3 !

PIT 2Y IIV-AOV-269AV 203) E11 A B 72 IN BTF AO O FSC CS REACTOR AIG SET IB VENTILATION FST CS OLTBOARD EXilAUST. ACSJ43 PIT 2Y .

IIV-AOV-270AY 2019 B2 A B 20IN BIF AO O FSC Q CONTROL RSt IIVAC INLET VALVE Sli I FST Q i 11V-AOV-271 AV 3)19 Al A B 12 IN BTF AO C FSO Q CONTROL RAI IIVAC ESTERCENCY SII I a FST O BYPASS i l

[

Revskm 2 Sectum V Page 20 of 155 l

i COOPER NUCLEAR STATION !

TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES l SYSTEM: IIEATING AND * 'NTILATION OIV) i

!' I

( VALVE CIC PilD P&ID 151 IST VALVE VALVE ACT NORM TEST TEST' NOTES ~ DESCRIPTION 1 COOR CIA 55 CAT SIZE TYPE TYPE POS RQ\fT FREQ t

11V-AOV-272AV i

3 2019 B6 A B 8 IN BTF AO O FSC Q CONTROL RM PANTRY EXH SLCST I

SII 1 FST Q ISOIAT10N HV410V-258MV 20N B12 A B 18IN BTF MO O FSC Q REACTOR BUILDING VENi!LAT10N PIT 2Y OUTBO \RD EXII AUST I

IIV410V-2fCMV 20N . B12 A B 4R IN BTF MO O FSC Q REACTOR BUILDING VENTI 1ATION ;

FIT 2Y OUTBOARD LT11tt:ST ,

liv 410V-262MV 20N E9 A B 4x !N BTF MO O F5C C5 RR MG 5ET I A VENTILAT10N PIT 2Y INBOtRD SUPPI_Y. AC5141 IIVaf0V-264M\ 2rLM E9 A B 48IN BTF MO O FSC C5 RR MG SET IB VENTILATION P!T ZY INBO ARD SUPPLY. AC5143 I HV-MOV-266MV 20N D4 A B 4x IN LTF MO O FSC C5 RR MG SET I A VENTILATION !

PIT 2Y OUTBOARD EXII AUST. AC5J41 liv-MOV-268MV 20N E11 A B 48IN BTF MO O F5C C5 RR MG SET IB YENTILATION PTT 2Y OUTBOARD EXHAUST. AC5J43 HV-MOV-272MV 20N D4 A B 72 IN BTF MO O F5C Q REACTOR BUILDING YENTTIATION l PIT 2Y INBOARD 51TFLY l I

?

t 4

l

$ i I

i !

j Resiswn 2 Sctuon V Page 21 of 155

9 COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 i VALVE SU313tARY TABLES i

1-i SYSTEM: INSTRUMENT AIR (IA) i YALVE CIC P&ID PAID ISI IST VALVE VALVE ACT NORM TEST TEST NOTEST)ESCRIPTION

., COOR CLASS CAT STZE TYPE TYPE POS RfMfT FREQ

\ rw 1A-CV-17CV 2010 E3 A AC I/2 CK-L SA O LT-I 2Y MS-RV-71 A ACCT MCLATOR Sil 2 FSC RF SITPLY_AROJUI 1A{V-lMCV 3110 EB A AC l '2 CK-L SA O LT-1 2Y MS-RL71B ACCITIULATOR t l Sif 2 FSC RF SUPPLY.AFOJ41

IA-CLl9CV 2010 D8 A AC 10 CK-L SA O LT-1 2Y MS-RE71C ACC13tCLATOR Sif 2 FSC RF SLTPLY. AROI AI 14CE38CV 2010 D9 A AC 10 CK-L SA O LT-1 2Y MS RE7IF ACCUMCLATOR S11 2 FSC RF StTPLY.AROJ41 IAC%21CV 2010 E9 A AC IC CK L . SA O LT-1 2Y MS-RV-71G ACC13tULATOR Sif 2 FSC RF SITFLY. AROJ41 !

IA.CV-SCV 2010 E9 A AC 12 CK-L SA O LT-1 2Y MS-RV-7;il ACCU \lUIATOR. '

Sil 2 FSC RF SLTFLY. A8tOJ41 IA CV-2xCV 2010 F4 A A:C IC CK-L SA O LT-1 21 MSIEAOMOA SUPPLY SH 2 FSC RF AROJ42 -

l IA-CV _W 2010 F8 A AC IC CK-L SA O LT-1 2Y MSILAOSOB SUPPLY Sil 2 FSC RF AROJ42 IA-CO30CV 2010 FM A A-C l '2 CK L SA e O LT-1 2Y MSILAOSOC SUPPLY j S11 2 i FSC RF ARO!42

. IA-CV-31CV 2010 F9 A AC 1/2 CK-L SA O LT-1 2Y MSIWAOSOD SUPPLY Sil 2 FSC RF AROJ42

! IA C%32CV 2010 D12 A A:C IC CK-L SA O LT-1 2Y MSIEAOS6A. 5LTPLY j ! Sli 2 FSC RF AROIR2 Reshion 2 Sectum V Page 22 of 155 i

4 .

- 7 - 1+ ---

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAh!

VALVE SU31AIARY TABLES SYSTE31: IN$TRU3fENT AIR (IA)

VALVE CIC P&!D P&lD ISI IST VALVE VALVE ACT NOR\1 TEST TEST NOTES DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ\fT FREQ IA-CV-33CV 2010 D12 A A 'C 1/2 CK-L SA O LT-1 2Y %ISIV-AO%B SCPPLY Sil 2 FSC RF AROla?

I A CV-32CV 2010 DI2 A AC I/2 CK-L S,. O LT-1 2Y NtSIV-AO*< SrPPty 511 2 FSC RF AROJ o2 I A-CV-35CV 3 10 E12 A AC I /2 CK L SA O LT-I 2Y %1SIV-AO%D SUPPLY

$112 FSC RF AROI02 IA-CV-36CV 2010 ER A AC !!2 CK L SA O LT-1 2Y MS-RV 71D ACCOICLATOR Sif2 l FSC RF St'PPLY. AROJ al IA -CV-37CV '010 E10 A AC I/2 CK-L SA O LT-I 2Y STS-RV-71F ACCC\1CLATOR SH 2 FSC RF SUPPLY.AROJ41 1A-CV-50CV 2010 115 A AC !!4 CK-L SA O LT-I 2Y ACCDICLATOR AO-82 IA CIILCK SII 2 FSC Q VALVE I A-CV-51CV 2010 115 A A/C I!4 CK-L SA O LT-1 2Y ACCDICLATOR AO-831A CllECK Sil 2 FSC Q VALVE lA-CV-52CV 2010 116 A A.'C !!4 CK-L SA O LT-1 2Y ACCUMULATOR AOM 1A CIIECK Sli 2 FSC Q VALVE IA-CV-53CV 2010 116 A A ~C !!4 CK-L SA O LT-1 2Y ACCU %1CLATOR A0951A CilECK Sli 2 FSC Q VALVE l A-CV-54CV 2010 A7 A AcC 1/4 CK L SA O LT-1 2Y llV-AOV-257AV ACCD1ULATOR Sif 2 FSC CS CIIECK. ACSIOS IA-CV-55CV 2010 A6 A AIC I/4 CK-L SA O LT-1 2Y llV-AOV-259AV ACCDICLATOR Sil 2 FSC CS CllECK, ACSJ4u Revism 2 Section V Page 23 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES '

J SYSTE31: INSTRU31ENT AIR (IA) j!

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORN1 TEST TEST NOT5EDESCRL"IlON COOR CIi ASS CAT SIZE TYPE TYPE POS RQNfT FREQ j IA-CV-54CV 2010 A7 A AC I!4 CK-L SA O LT-1 2Y llV-AOV-26tAV ACCatCLATOR 511 2 FSC CS CliFCK. ACSJau I A-CV-57CV 2010 B9 A AC I f4 CK L SA O LT-1 2Y llV-AOV-263AV ACCU %trLATOR Sil 2 FSC CS CilECK. ACS14M AC IA CV-58CV 2010 E9 A I:4 CK-L SA O LT-1 2Y IIV-AOV-265 AV ACCD11 LATOR Sil 2 FSC CS CliECK. ACS1du IA CV-5?CV 2010 89 A AC I/4 CK L SA O LT-1 2Y llV-AOV-267AV ACCDICLATOR Sil 2 FSC CS CilECK. ACS14u a

IA-CV 60CV 2010 AM A AC 174 CK-L SA O I.T-1 .2Y IIV.AOV-264AV AC'OtELATOil SII 2 FSC CS CHECK. ACStau _

IA-CV-65CV 2010 F8 2 A'C 2 CK L SA O U-l RF X-22 INBOARD ISOLATION.

Sil 2 FSC RF ROIAM 1A-CV-78CV 2010 F8 2 A'C 2 CK L SA O U-l RF X-22 OUTBOARD ISOLATION.

Sil 2 FSC RF ROJ4M IA-CV-IIICV 2010 Eli A A'C I/4 CK-L SA O ._T-1 2Y 1A-271AV ACCDtULATOR CIIECK.

Sil 1 FSC CS ACSJ (M PC-V-559 2028 D3 2 A I GB A1 A C U -I RF PASSIVE 51 ANUAL ISOLATION PC V-560 2028 D8 2 A I GB NiA C U-I RF PASSIVE itANUAL ISOLATION PC V-561 2028 C8 2 A I GB 51 A C U-l RF PASSIVE NiANUAL ISOLATION PC-V-562 202R CH 2 A 1 l GT %1A C 13-1 RF PASSIVE NT ANUAL ISOLABON Reusion 2 Sectum V Page 24 of 155

\

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES r

SYSTEM: INSTRD1ENT AIR (I A)

VALVE CIC P&lD P&ID ISI IST VALVE %ALVE ACT NORSI TEST TEST NOTES: DESCRIPTION ;

COOR CLASS CAT SIZE TYPE TYPE __ POS RQ%1T , FREQ PC-V-563 3t28 C8 2 A I GT NTA C U-l RF PASSIVE \tANUAL ISOLATION PC-V-SM 3C8 C3 2 A I GT %IA C U-I RF PASSIVE 51 ANUAL ISO 1ATION PC-V-565 312M DM 2 A '

I GT NtA C U-l RF PASSIVE %I ANUAL ISOLATION '

PC-V-566 3)2M D8 2 A I GT StA C U-l RF PASSIVE St ANUAL ISOLATION PC-V-569 3)27 13 2 A I GT StA C U-l RF PASSIVF Nt ANUAL ISOLATION PC-V-570 2027 13 2 A 10 GB \tA C U-l RF PASSIVE St ANUAL ISO 1ATION PC-V-571 2027 33 2 A I GB \tA C U-l RF PASSIVE Nf ANUAL ISOLATION PC-V-572 2027 J3 2 A IC GB StA C U -l RF PASSIVE NtANUAL ISOLATION PC-V-573 3)27 J4 2 A I GT StA C U -l RF PASSIVE %1ANUAL ISOLATION PC-V-574 2027 J4 2 A 10 GB %1A C Ul RF PASSIVE ST ANUAL ISOIATION PC-V-575 3C7 14 2 A I GB StA C U-l RF PASSIVE 31 ANUAL ISOLAT10N j PC-V-576 2tC7 J4 2 A I/2 GB StA C U-l RF PASSIVE %1ANUAL ISOLATION PC-V-577 2027 J5 2 A I GB StA 0 U-I RF PASSIVE N1 ANUAL ISOLAllON !

PC-V-578 2027 15 2 A 1/2 GB StA C U-I RF PASSIVE St ANUAL ISOLATION PC-V-579 2027 15 2 A I GB AlA C U-l RF PASSIVE StANUAL ISOIATION i PC-V-5N) 2027 35 2 A 1/2 GB STA C U-l RF PASSIVE N1 ANUAL ISOIATION PC-% -SH I 2027 16 2 A I GB NfA C U-l RF PASSIVE S1 ANUAL ISOT ATION i

Revisum 2 Secthm V Page 25 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC PAID PAID ISI IST VALVE. VALVE ACT NORS1 TEST TEST NOTES DESCRit'T10N COOR CLASS , CAT SIZE TYPE TYPE POS RQ%1T FREQ PC-V-5 R2 2027 16 2 A IC GB P1A C IJ-1 RF PASSIVE %1 ANUAL ISOLATION PC-V-5R3 2027 16 2 A I GB \1 A C 13-1 RF PASSIVE %1 ANUAL ISOLATION PC "-5X4 2027 16 2 A 10 GB %1A C IJ-! RF PASS *VE sf ANUAL ISOIATION i

PC-V-585 2tC7 17 2 A 1 GB StA C IJ-I RF PASSIVE %1 ANUAL ISO!_ATION i

PC-V-586 2027 J7 2 A 1f2 GB N1 A C 1J-I RF PASSIVE %t %NUAL ISOLATION l

PC-V-587 2027 17 2 A I GB StA C 13-1 RF fjsSIVE %1 ANUAL ISOIAT10N PC-V-588 2027 17 2 A IC GB NTA C 13-1 RF PASSIVE %1 ANUAL ISOI.ATION PC-V-5W9 2027 18 2 A I GB 51A C 13-1 RF PASSIVE N1 ANUAL ISOIATION i

PC-V-5W 20_7 18 2 A 1C GB %1A C 13-1 RF PASSIVE STANUAL ISOLATION 6

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Reviskm 2 Sectum V Pace 26 of 155 i

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES SYSTEM: MAIN STEAM OfS) .

P&lD 151 IST VALVE VALVE ACT NORSt TEST TEST V VE CK PMD NOTES ~ DESCRIPTION i COOR CLASS CAT SIZE TYPE TYPE POS RQtfT FREO

^

S15-AOV-A O*)A 2(ut B5 i A 24 GB AO O Ul RF 5tSiv A INHO ARD ISOLATION.

FS: Q CSIAu FST Q PIT 2Y Nt S- AOV-AO%B 341 B5 I A 24 GB AO O U-l RF StSIV B INBOARD ISOLATION, FSC Q CSJau FST Q PIT 2Y !

MS AOV-AOW C 3 41 P", I A 24 GB AO O U1 RF MSIV C INBOARD ISOLATION. l FSC Q CSJ4u FST Q PIT 2r MS- AOV- AOSOD 2tMI B6 i A 24 GB AO O U-l RF MSIV D INBO ARD ISOLATION.

FSC Q CSJ4M FST Q Ptr 2Y MS-AOV-AOS6A yut B3 1 A 24 GB AO O U-I RF MSTV A OUTBO ARD ISOLATION l FSC Q CSJ 04 i FST Q

PIT 2Y MS-AOV-AOS6B 2tul A4 1 A 24 GB AO O U-I RF MS!V B OUTBOARD ISOLATION FSC Q CSJ,'u FST Q i l PTT 2Y .l i Revishm 2 Secthm V Page 27 of 155 l i

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU513fARY TABLES SYSTE31: 31AIN STEAM 01S) i l

VALVE CIC P&lD

' ^ ^

NOTESJDESCRIPT.'JN l COOR CIASS CAT SIZE TYPE TYPE POS RQ\lT FREQ l

MS- AOV- AOE 3 41 A8 I A 22 GB AO O 13-1 RF MSIV C OUTBO \RD ISOIATION '

FSC Q CSJ44 FS1' Q g rtT 2Y MS-AOV-AO%D 3u1 BX 1 -\ 24 GB AO O 13-1 RF MSIV D OUTIM)\RD ISOIAT10N FSC Q CSJ o* -

4 FST Q Pil 2Y

! MS-AOV-73 RAY 2023 B9 1 B l '2 GB AO C PTT 2Y RPV IIEAD VENT DRAIN TO SUMP.

P ASSIVE ISOLtTION j MS-AOV-739 AV 3C8 B9 1 B l '2 GB AO C PTT 2Y RPV IIEAD VENT DRAIN TO SUMP.

PASSIVE ISOLATION 1

MS-CV-3CV 3CR CII 3 C 10 CK-5 SA C VBT RF 71 A RV DISCIIARGE VACtXTM l BREAKER VB 71 A1 ,

)

' l MS-CV-21CV 3C8 ClI 3 C 10 CK-5 SA C VBT RF 7t A RV DISCIIARGE VACUUM BREAKER VB 71 A2 1

MS-CV-22CV 3C8 Cl1 3 C 10 CK-5 SA C VBT RF 71B RV DISC 11 ARGE V ACIXM ;

BREAKER VB 71 B1 MS-CV-23CV 3C8 C11 3 C 10 CK-S SA C VBT RF 718 RV DISCIIARGE VACUUM BRFAKER VB 71 B2 MS-CV-24CV 3C8 D11 3 C 10 CK-5 SA C VBT RF 71C RV DISCIIARGE VACUUM BREAKER VB 71 C1 l 1

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGR OI VAIXE SL3 DIARY TABLES SYSTE31: 31AIN STEA31 DIS)

i. i VALVE OC P&lD

^ ^ ' N' OTESDESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ\tT FREO i ,

MSCV-25CV 202M DII 3 C 10 CK-5 SA C VBT RF 71C RV DISCli tRGE VACIT%f

, BRfAKER VB 71 C2

.1 l M S-CV-2M'V 2tC8 D11 3 C 10 CK S SA C VBT RF 71D RV DISCHARGE VACUDI BREAKER VB 71 DI MS CV-27CV '028 DIi 2 C 10 CK 5 SA C VBT RF 71D RV DISC 11ARGE VACUni BREAKER VB 71 D2 i MS CV-2xCV . ' 2028 D9 3 C 10 CK-S SA C VBT RF 71E RV DISCIIARGE VACCD1 BREAKER VB 71 El MS-CV _*EV 3C8 D4 3 C 10 CK-5 SA C VBT RF 71E RV DLM'11 ARGE V ACUD1 BREAKER VB TI E' M S-CV-30CV 3I25

D9 3 C 10 CK S SA C VBT RF TiF RV DISCH tRGE VACLTV ,

BREAKER VB 71 FI MS-CV-31CV 2028 D9 3 C 10 CK-S SA C '1T RF 71F RV DISCIIARGE VACCD1 ,

BREAKER VB 71 F2 i MSCV-32CV 2028 E9 3 C 10 CK-5 SA C VBT RF 71G RV DISCliARGE VACUD1 EREAKER V3 71 GI {

uS-CvmCv 2028 E9 3 C 10 CK S SA C VBT RF viG av DtSCiiARGE ACUU%1 BREAKER VB 71 G2 MS-CV-MCV 21C8 E9 3 C 10 CK-5 SA C VBT RF 7111 RV DISCllARGE VACtJD1 l PREAKER Vil71 Ill l Remion 2 Sectum V Pare. %.f 155 t 4

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4 COOPER NUCLEAR STATION THIRD INTERVAL

, INSERVICE TESTING PROGRA31 l VALVE SU3131ARY TABLES 4

i i

SYSTE31: 31AIN STEA31 (3tS) i- PAID ISI IST VAISE VALVE ACT NORM TEST TEST -

VALVE CIC PAID NOTT3OESCRIPT10N CNR CWS CAT SEE n'M TM M RW Wl g i MSG-3D' N2N E9 5 3 C 10 CK-S SA C VBT RF !

l Till RV DISC 11 ARGE VACLTM BREAKER VB 71112 !

MS-MOV-MO74 2041 C6 i A 3 GT MO O U-1 RF MS UNE DRAIN INBOARD FSC Q ISOLATION l ;

iTT 2Y MS-MOV MO77 2041 CIO I A 3 GT MO O 111 RF MS LINE DRAIN OCTBO ARD (

FE Q ISOLATION PTT 2Y MS-RV-70ARV 2028 C!9 1 C 6 RV SA C RVT SY SAFETY VAISE MS IJNE A MS-RV 70BRV 2028 E9 I C 6 RV SA C RVT SY S AFETY VALVE MS LINE D MS-RV-70CR V 2023 E9 1 C 6 RV SA C RVT SY S AFETY VALVE MS UNE D MS-RV-71 ARY 2028 CIO 1 BC 6 RV AO C RYT SY S AFETY RELIEF VALVE MS UNE A. )

FSO RF RV#3

- i FSC RF i PIT RF MS-RV-71 BRV N28 ClI 1 B'C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS UNE A.

FSO RF kVe3 FT RF e PIT RF

.j i Resism 2 Sectum V Pne 30 of 135 ,

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j COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3 DIARY TABLES ,

4' SYSTE31: SIAIN STEAM 015) l V VE CIC P&lD

^ ^ ^ ~ NOTI 5:DESCRIPT10N -

COOR CIASS CAT SIZE TYPE TYPE POS RQ\fT FREQ f

%15 RV-71CRV 2028 D11 1 BC 6 RV AO C- RVT SY S ATTiTY REUIT VALVE 515 LINE B. ,

FSO RF RV4N FSC RF PIT RF

, s

- StS RV-71DRV 2028 D11 I BC 6 RV AO C RVT SY SAFETY REUEF VALVE %15 UNE B.

FSO RF RVAN FSC RF !

PIT RF 1

4 AtLRV-71ERV 2028 D9 i BC 6 RV AO C RVT SY SAFETY REUEF VALVE StS UNE C.

FSO RF RV#)

] FSC RF j PIT RF StS-RV-71FRV 202S D9 i B'C 6 RV AO C RVT SY SAFETY REUEF VALVE SIS UNE C.

i FSO RF RV4N

, FSC RF PIT RF AtS-RV-71GRV 202R E9 1 BC 6 RV AO C RVT SY SAFETY REUEF VALVE 515 UNE D. ,

FSO RF R V#)

.-K '= \

l NfS-RV-7111RV 2028 E9 1 BC 6 RV AO s SAFETY REUEF VALVE StS UNE D. !

FSO RF RVM7 FSC RF

PIT RF Reviuon 2 Sectam V Page 31 of 155 i

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SUMMARY

TABLES i

SYSTE31: NEUTRON MONITORING TRAVERSING INCORE PROBE (NMT)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NOR%t TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RONIT FREQ r

l NNICVCV2 3183 12 2 AC 38 CK-P SA C U-l 2Y N2 PURGE ISOLATION. C37-10 FSC CS NN1-CV-CV4 2083 J2 2 A 'C 373 CK-P SA C U -l 2Y N2 PURGE ISOL% TION. CSI-10 FSC CS ,

N%1T-NVA-!(MAX 2083 J2 2 D 38 SilR EX O EX 2Y VALVE ASSD1BLY Cil A N%1T-NVA-1(MBX 2m3 J2 2 D 3/8 SIIR. EX O EX 2Y VALVE ASSB!BLY Cil-B NSIT-NVA-1(MCX 2083 J2 2 D V8 SIIR EX 0 EX 2Y VALVE ASSD!BLY Cil-C NN1T-NVA-1(MDX 2083 J2 2 D 3J8 SIIR EX O EX 2Y VALVE ASSB1BLY CII-D NN1T-NVA-1(MA 2083 J2 2 A 3/8 BAL SO O U -1 RF VALVE ASSB1BLY CII-A FSC Q FST Q PIT 2Y j NN1T-NVA-104B 2083 J2 2 A 3/8 BAL SO O U-l RF VALVE ASSalBLY Cil-B l FSC Q FST Q j PIT 2Y Reviskm 2 Secthm V Page 32 of 155 i i

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SYSTE31: NEUTRON 310NITORING TRAVERSING INCORE PROBE (N3tT)

VALVE CIC PAID P&ID 151 IST VALVE VALVE ACT NOR31 TEST TEST NOTTi.S: DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQNIT FREQ -

NNfT-NVA-104C 2083 J2 2 A 33 BAL SO O Ul RF VALVE ASSEMBLY CH C t ESC Q FST Q PIT 2Y Y

d NMT-NVA-lO4D 20M3 J2 2 A 38 BAL SO O U-l RF VALVE ASSEMBLY CII D FSC Q FST Q g PIT 2Y 1

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Reviam 2 Section V Page 33 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA3I VALVE SU3131ARY TABLES l SYSTDI: NUCLEAR BOILER INSTRDIENTATION (NBI) AND VARIOUS OTilER ENCESS l' LOW CilECK VALVES l i VALVE CIC P&ID PAID 151 IST VALVE VALVE ACT NORN1 TEST TEST NOTES DESCRIPTION COOR CLASS CAT ) SIZE TYPE TYPE POS RQ\tT FREQ NBI-AOV-736AV 2028 C9 I B 1T2 GB AO O PIT 2Y RPV FLANGE LEAKOFF PASSIVE !

I 150LAT10N NBI AOV-737AV 2tC8 C9 i B IC GB AO C PIT 2Y RPV FLANGE LEAKOFF PASSIVE ISOLATION j NBI CV-10BCV 2026 C4 1 AC 1 CK B SA O U-2 RF IfPPLR C11ECK FOR 1 :i FSC RF U41. RV-10 f I f

? NBI (T-I:BCV 2026 D2 1 A. C I CK B SA O U-2 RF CONDENSING OI ANtBER 2A LTPER !

FSC RF TO 25-5 RACK. RV-10 NB! CV-12BCV N26 DJ I AC 1 CK-B SA O U-2 RF CONDENS NG OI A%1BER 2A LOWER FSC RF TO 25-5 RACK. RV-10

) i NBICV-13BCV 2026 E4 i AC 1 CK-B SA O U-2 RF CONDENSING OIA%1BER 3A TO j FSC RF UTS-7tA. RV-10 i

, NBI CV-14BCV '2006 E4 1 A-C 1 CK-B SA O U-2 RF CONDENSING OIA%IBER 3A TO 25 5 f j FSC RF

& 25-5-1 RACK. RV-10 [

i

! NBI-CV-15BCV 2026 E4 1 A!C 1 CK-B SA O U-2 RF LT-52A. US-83A & C; LT-61; DFT45; !

FSC RF US-101 A & B. RV-10 i

NBi CV-16BCV 2rC6 F4 1 A-C I CK-B SA O U-2 RF LOW STDF. FT-6*T. !

I FSC RF RV-10 :

NBICV-17BCV 2026 F4 1 AC I CK-B SA O U-2 RF LOW SIDE FT41R; ;

FSC RF FT-63D. RV-10 i

NBl CV-18BCV 2026 G4 I A:C 1 CK-B SA O U-2 RF IIIGil SIDE FT-63D. RV-10 ;

FSC RF l

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I SYSTEM: NUCLEAR BOILER INSTRDIENTAT !

VALVE CIC P&lD PAID ISI IST VALVE VALVE ACT NORSt TEST TEST NOTE 5 DESCRIPTION I

COOR CIASS CAT SIZE TYPE TTPE POS RQ\fT FREQ NBI CV-19BCV 3C6 G4 1 AC I CK-B SA O U-2 RF ABOVE CORE PLATE PRESS. RV-10 I F5C RF NBl=CV-3)BCV 2026 G4 AC I CK-B SA O U-2 RF BELOW CORE PI ATE TO 1 1 FSC RF INSTR 13 TENT R ACK 25-51. RV 10 '

NBI CV-21 BCV 21C6 DM i AC I CK B SA O U-2 RF t CONDENSING CIIA%1BER 2B 1.TPER FSC RF TO 254 RACK. RV-10 l 1

NBI CV-22BCV 2026 D8 I AC I CK-B SA O U-2 RF CONDENSING CIIA%fBER 2B l'PPER FSC RF TO 34 RACK. RV-10 NBICV-23BCV 2026 E8 i AC I CK B SA O U -2 RF CONDENSING CHAStBER 3B LT 70 i

_FSC RF UTS-738. RY-10 i

NBICV-22BCV 3C6 E8 I AC I CK-B SA O U2 RF CONDENSING CIIASIBER 3R TO 256 FSC RF A 2541 RACKS. RV-10 5 NBICV-2*BCV 3C6 EM ! A>C CK B SA O U -2 1 1 RF LOW SIDE US-538 FSC RF LT-52B. US-InlC & D. RV-10 4

5 NBifV-26BCV 2026 F8 i AC I CK-B SA O U-2 RF LOW SIDE FT-6*L.

FSC RF RV-10

NBICV-27BCV 3)26 F8 1' A!C 1 CK-B SA O U-2 RF LOW SIDE FT-63C.

FSC RF FT4tN. RV-10 i

l NBI CV-28BCV 2026 G8

AC 1 CK-B SA O U-2 RF HIGH SIDE FT-6E, RV-10 j j FSC RF

! NBI-CV-29BCV 2026 G8 I AC I CK-B SA O U-2 RF BELOW CCRE PLATE TO j FSC RF TNSTRIT1ENT R ACK 25-52. RV-la ,

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SYSTDI: NUCLEAR BOILER INSTRDIENTATION (NBI) AND VARIOUS OTIIER EXCESS FLOW CIIECK VALVES i i s

j VALVE CIC PAID PAID 151 IST VALVE VALVE ACT NORM TEST IT.ST NOTEXDt3CRIPT10N COOR CLASS CAT SIZE TYPE TYPE POS RQ%fT FREQ i

+

i NBICV-30BCV 3C6 F3 1 AC 1 CK-B SA O U-2 RF FT43B. FTM3 LOW SIDE. RY-10 FSC RF [

NBICV-31BCV 2026 F3 1 AC 1 CK-B SA O U-2 RF FT43B;ll!Gli SIDE. RV-10 k FSC RF NBI CV-32BCV 2026 F3 1 AC I CK-B SA O U -2 RF FTMD; LOW SIDE. RV-10 FSC RF e n

NBl CV-33BC\ 3C6 F3 1 AC 1 CK-B SA O U-2 RF FTMF. LOW SIDE. RV-10 FSC RF l NBICV-34BCV 3C6 F3 1 AC I CK-B SA O U-2 RF FTNK; LOW SIDE. RV-Its !

FSC RF I 2026 NBI CV-35BCV F3 1 AC I CK-B SA O U-2 RF FTMM; LOW SIDE. RV-10 FSC RF i

NBl CV-36BCV 2026 F3 1 A:C 1 CK-B SA O U-2 RF FT44V; LOW SIDE. RV-10

{

4 FSC RF NBICV-37BCV 2026 F3 1 A'C I CK-B SA O U-2 RF FTMX; LOW SIDE. RV-10 ;

, FSC RF f

NBI-CV-3xBCV 2026 F3 1 A:C I CK B SA O U2 RF FT4*Z; LOW SIDE. RV-10 [

FSC RF i NBICV-39BCV 2fC6 F3 1 AfC 1 CK-B SA O U-2 RF FT4*A; FT43A LOW SIDE. RV-10 ;

FSC RF i

NBl CV-40BCV 2026 F7 i AtC 1 CK-B SA O U-2 RF FT43A IllGli SIDE. RV-10 FSC RF j Reviske 2 Secthm V Page 36 of 155 !

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, INSERVICE TESTING PROGRAAI j VALVE SUAIAIARY TABLES i

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SYSTE31: NUCLEAR BOILER INSTRUMENTATION (N3I) AND VARIOUS OTIIER EXCESS FLOW C11ECK VALVES VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NOR31 TEST TEST NOTES T)ESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ}fT FREQ NBI-CV-11BCV 2026 F9 1 A'C 1 CK-B SA O U-2 RF FTMC LOW SIDE. RV-10 FSC RF NBI CV42BCV 3C6 F9 1 AC 1 CK-B SA O U-2 RF FT-64E LOW SIDE, RV-10 FSC RF

NBI CV43BCV 2tC6 F9 1 AC I CK-B SA O U-2 RF FTMJ LOW SIDE. RV-10 j FSC RF 1

NBI CV44BCV 2026 F9 I AC 1 CK-B SA O U-2 RF FTMS LOW SIDE. RV 10 FSC RF j NBI CV-45BCV 2tC6 I7 1 AC 1 CK-B SA O U-2 RF FTMU LOW SIDE. RV-10 ;

i FSC RF t i

NBICV-46BCV 2026 F9 i A 'C 1 CK-B SA O U-2 RF FTMW LOW SIDE. RV-10 !

FSC RF NBI CV47BCV 3C6 F9 1 AC 1 CK-B SA O U-2 RF FTMY LOW SIDE. RV-10 FSC RF l i

NBICV49BCV 2026 El 3 C 1T2 CK-5 SA C FSO RF REFERENCE LEG LOOP A INJECTION. ROJ4W NBI CV-50BCV 2026 El 3 C 1/2 CK-S SA C FSO RF REFERENCE LEG LOOP A INJECTION. ROJ4% i NBICV-51BCV 2(C6 E12 3 C 1f2 CK-S SA C FSO RF REFERENCE LEG LOOP B INJECTION. ROJ4E ;

i NBICV-52BCV 3C6 E12 3 C IT2 CK-5 SA C FSO RF REFERENCE LEG LOOP B INJECTION ROJ4%

Renskm 2 Sectkm V Page 37 of 155 1

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THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SODIARY TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE Cic P&lD PilD 151 IST VALVE VALVE ACT NORSt TEST TEST NOTES /DESCRIPIlON 4

COOR CLASS CAT SIZE TYPE TYPE POS FONIT FREQ NBI-CV-35CV 2026 A3 3 AC 38 CK-5 SA O LT2 RF REFERENCE UG LOOP 3A s FSC RF OUTBO ARD INJECT 10N. ROJ 417 NBICV-56CV 2026 A3 3 AC 3?d CK-S SA O LT2 RF REFERENCE LEG LOOP 3B !

FSC RF Ol;TBO ARD INJECTION. ROJ487

[

NBI SOV-SSV738 2026 El 2 B I/2 SOV SOV C FSO RF REFERENCE LEG LOOP A FST RF INIFCTION ROJ4W l PIT 2Y NBI-SOV SSV739 2(C6 E12 2 B 1r2 SOV SOV C FSO RF REFERENCE LEG LOOP B i FST RF INJECTION ROJ 06 PIT 2Y ,

t CS CV-16BCV 2ru5 A6 I AC I CK-B SA O U-2 RF DPIS-13A LOW SIDE ENCESS FLOW.

511 1 FSC RF RV-10 l CSCV-17BCV 2045 B6 1 A!C I CK-B SA O U-2 RF DPIS-43B LOW SIDE EXCESS FLOW.

SII I FSC RF RV-10 I l

11PCICV-10BCV 2041 D4 1 A/C I CK-B SA O U-2 RF llIGil SIDE 11PCI DPIS-76; DPIS-77; 1 FSC RF PS44A: PS4eC. RV-10 l i IIPCICV-IIBCV 2041 D4 I AC I CK-B SA O U-2 RF LOW SIDE IIPC1 DPIS-76; DPIS-77; PS-FSC RF 688. PS4dD. RV-10 i

, StSCV-10BCV 2041 C4 1 A:C 1 CK-B SA O U-2 RF FT-51 A; DPIS-116A. B. C. & D lilGli l FSC RF SIDE. RV-10 SISCV-IIBCV 2041 C4 1 A/C 1 CK-B SA O U -2 RF FT-SI A; DPIS-Il6A. B. C. & D LOW I

, FSC R. _ i SIDE, RV-10

Revidm 2 Section V Page 38 of 155

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRLSIENTATION (NBI) AND VARIOUS OTIIER EXCESS FLOW CIIECK VALVES !

VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT S?ZE TYPE TYPE POS ROMT FREQ _

MS-CV-12BCV 2041 C4 1 AC 1 CK-B SA O U-2 RF FT-51B. DPIL117A. B. C. & D LOW FSC RF SIDE. RV-10 MS-CV-13BCV 3MI C4 1 AC 1 CK-B SA O U-2 RF FT-S!B; DPISI17A. B. C. A D HIGH FSC RF SIDE. RV-10 ,

s MS-CV-14BCV 3MI C"T 1 A'C 1 CK B SA O U-2 RF FT-5IC; DPIS-IlM A. B. C. A D il!Gil FSC RF SIDE. RV-10 MS CV-15BCV 3u1 C7 I A'C 1 CK-B SA O U-2 RF FT-510. DPIsil9A. B. C. & D litGli FSC RF SIDE. RV-10 ,

MS-CV-16BCV 341 C7 1 AC 1 CK-B SA O U-2 RF FT-SIC. DP!S-118A. B. C. & D LOW I FSC RF SIDE. RV-10 i 1

, MS-CV-17BCV 341 C7 1 AC 1 CK B SA O U-2 RF FT-51D; DPISI19 4. B. C. & D LOW FSC RF SIDE. RV-10 i

RCIC-CV-10BCV 2tul E7 i A 'C I CK-B SA O U-2 RF RCIC-DPIS41 tilGil SIDE EXCESS l-SC RF FLOW CilECK VALVE. RV-10 t 1 RCIC-CV-IIBCV 2041 E7 i AC 1 CK-B SA O U-2 RF Rt iC-DP1584 LOW SIDE EXCESS I FSC RF FLOW CilECK VALVE. RV-10 i RCIC-CV-12BCV 3MI D7 I A/C 1 CK-B SA O U-2 RF RCIC-DPIS83 It!Gil SIDE EXCESS FSC RF FLOW CllECK VALVE' RV-10 j RCIC-CV-13BCV 2031 D7 i A!C 1 CK-B SA O U-2 RF RCIC-DPIS-83 LOW SIDE EXCESS FSC RF FLOW CIIECK VALVE. RV-10 RR.CV-lOCV 2027 C1 1 A!C 1 CK-B SA O U-2 RF PS-12RA SENSING UNE, RV-10 '

FSC RF Resision 2 Secten V Page 39 of 155 4

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SYSTEM: NUCLEAR HOILER INSTRUMENTATION (NBI) AND VARIOUS OTIIER EXCESS FLOW CIIECK VALYES I

VALVEC!C P&lD P&lD 15e IST VALVE VALVE I ACT NORNI TEST TEST NOTES / DESCRIPTION COF . CLASS CAT SIZE TYPE TYPE POS RO\lT FRFQ M4+

RR-CV-1 ICS 2027 I AC I CK B SA O U-2 RF PS-128A SENSING UNE. RV-10 FSC RF RP.-CV-12CV 2027 P.. 1 A'C 1 CK-B SA O U-2 RF DPT-IlI A LOW SIDE RV FSC RF RR-CV-13CV 2027 B2 1 AC 1 CK.B SA O U-2 RF DFT-1II A IIIGII SIDE. RV 19 FSC RF RR-CV-15CV 2027 E2 i A>C 1 CK-B SA O U -2 RF I T-25A SENSING LINE. RV-10 FSC RF R R-C V-16CV 2027 E2 1 A/C I CK- B SA O U-2 RF PT-24A SENSING LINE. RV-10 FSC RF RR-CV-17CV 2027 B2 1 A/C 1 CK-B SA O U-2 RF FT-110A AND B lilGli SIDE. RV-10 FSC RF RR-CV-IRCV 2027 B2 1 A/C 1 CK-B SA O U-2 RF FT-110A AND B LOW SIDE RV-10 FSC RF RR-CV-27CV 2027 C9 1 A/C I CK-B SA O U-2 RF DPT-11IB LOW SIDE. RV-10 -

F",C RF

! RR-CV-28CV 2027 B9 i A/C I CK-B SA O U -2 RF 7T-11IB IIIGli SIDE. RV-10 FSC RF RR-CV-30C V 2027 E9 i A/C 1 CK-B SA O U-2 RF iT-25B REACTOR RECIRCULATION FSC RF PUNf P IB SEAL CAVITY LINE, RV-10 RR-CV-31CV 2027 E9 1 A!C 1 CK-B SA O U-2 RF IT-24B SENSING LINE. RV-10 FSC RF Resision 2 Section V Page 40 of 155

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAAI V ALVE SUAIAIARY TABLES SYSTE31: NUCLEAR BOILER INSTRU31ENTATION (NBI) AND VARIOUS OTilER EXCESS FLOW CikECK VALVES VALVE CIC PilD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQMT FREQ RR-CV-32CV 2027 A9 1 AiC 1 CK-B SA O U-2 RF FT-110C AND D lilGil SIDE, RV-10 FSC RF R R -CV-33C V 2027 A9 I AC 1 CK B SA O U-2 RF FT-110C AND D U)W SIDE. RV-10 F%r RV Revision 2 Section V Page 41 of 155

t COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC) f VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORA1 TEST TEST NOTES /DESCRIFT10N COOR Ci ASS CAT Sf7F TYPF TYPF im ROA1T FRFO PC-AOV-237AV 2022 E4 2 A 24 BTF AO C U-l RF SUPPRESSION CIIAN1BER INLET 511 1 FSC Q OUTBOARD ISOLATION ;

FST Q '

PIT 2Y PC-AOV-238AV 2022 IM 2 A 24 BTF AO C U-l RF DRYWELL INLET OlJTBOARD Sil ! FSC Q ISOLATION y FST Q PIT 2Y ICAOV-243AV 2022 E5 2 A 20 BTF AO C U-l RF SUPPRESSION CilAN1BER VACUUSt SII 1 FSO Q REUEF FST Q PIT 2Y 10AOV-244AV 2022 F5 2 A 20 BTF AO C U-I RF SUPPRESSION CilAN1BER VACUU%1 Sil 1 FSO Q RELIEF '

I FST Q PIT 2Y PC-AOV-245AV 2022 El 2 A 24 BTF AO C U-l RF SUPPRESSION CIIA51BER EXilAUST Sil 1 FSC Q OUTBOARD ISOLATION FST Q PIT 2Y ICAOV-246AV 2022 C1 2 A 24 BTF AO C U-I RF DRYWELL EXIIAUST OUTBOARD Sil 1 FSC Q ISOLATION FST Q PIT 2Y Revision 2 Section V Page 42 of 155

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRA31 '

VALVE SUA131ARY TABLES i SYSTEM: PRDIARY CONTAINMENT (PC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST- TEST NOTESiDESCRIPTION COOR Cf A%% CAT ST7F TYPF TYPF POS RfWT FnFO PC-AOV-247AV 2022 Fil 2 A 24 BTF AO C U-l RF DRYWELL EXIIAUST OUTBOARD Sil ! FSC O ISOLATION FST Q PC-AOV-248AV 2022 Fil 2 A 24 BTF AO C U-l RF DRYWELL EXIIAUST OUTBOARD Sil i FSC Q ISOLATION ;

FST Q ICAOV-NRV20 2027 11 3 2 A.C 20 CK-S AO C LT-2 RF SUPPRESSION CllA51BER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PG AOV-NRV21 2027 113 2 A:C 20 CK-5 AO C LT-2 RF SUPPRESSION CIIAMBER TO >

PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV22 2027 114 2 A:C 20 CK-S AO C LT-2 RF SUPPRESSION CilAMBER TO VBT RF DRYWE11 VACUUM BREAKER PIT 2Y PC-AOV-NRV23 2027 114 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CilAMBER TO PIT 2Y DkYWELL VACUUM BREAKER VBT RF !

l' PC-AOV-NRV24 2027 115 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CII AMBER TO ,

VBT RF DRYWELL VACUUM BREAKER PIT 2Y PC-AOV-NRV25 2027 115 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CllAMBER TO I PIT 2Y DRYWELL VACUUM BREAKER VBT RF Revision 2 Section V Page 43 of 155 i

I

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUAIAIARY TABLES SYSTEM: PRI.TIARY CONTAIN.TIENT (PC)

VALVE CIC P&lD P&lD 151 IST VALVE VALVE ACT NORS1 TEST TEST NOTESIDESCRIPTION COOR Cf AS9 C AT Sf7F TYPF TYPF POS ROMT FPFO PC-AOV-NRV26 2027 116 2 AiC 20 CK-S AO C LT-2 RF SUPPRESSION Cil AA!BER TO PIT 2Y DRYVJELL VACUUA1 BREAKER VRT RF PC-AOV-NRV27 2027 116 2 A>C 20 CK-S AO C LT-2 RF SUPPRESSION CIIASIBER TO i PIT 2Y DRYWELL VACUUS1 BREAKER VBT RF PC- AOV-N RV28 2027 117 2 Arc 20 CK-S AO C LT-2 RF SUPPRESSION CIIA31BER TO PIT 2Y DRYWELL VACUUN1 BREAKER VBT RF PC-AOV-NRV29 2027 117 2 AtC 20 CK-S AO C LT-2 RF SUPPRESSION CilA%1BER TO PIT 2Y DRYWELL VACUUh1 BREAKER VBT RF PC-AOV-N RV30 2027 117 2 A!C 20 CK-S AO C LT-2 RF SUPPRESSION CIIAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV31 2027 118 2 AIC 20 CK-S AO C LT-2 RF SUPPRESSION CIIAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-CV-13CV 2022 E5 2 A/C 20 CK.D SA C 15 i RF SUPPRESSION CilAMBER VACUUM Sil i VBT RF RELIEF, ROJ-19 PC-CV-14CV 2022 F5 2 A/C 20 CK-D - SA C LJ-l RF SUPPRESSION CIIAMBER VACUUM Sil I VBT RF RELIEF, ROJ-19 i

Revision 2 Section V Page 44 of 155 i

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTEM: PRIMARY CONTAINME.VF (PC) i VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION CfYtR CI A%S CAT Sf7F TYPF TYPF POS PO\1T FRFO PC-CV-2] CV 2022 El 2 .AC 1/4 CK-S SA O 'C U-l RF' N2 SUPPLY TO II,0, MONITORS, Sil 2 FSC RF ROJ48 PC-CV-22CV 2022 D3 2 A/C II4 CK-S SA OC U-l RF N2 SUPPLY TO II,0, MONITORS.

Sil 2 FSC RF ROJ48 PC-CV-23CV 2022 C3 2 AC 1/4 CK-S SA OC U-l RF O2 SUPPLY TO II,0. MONITORS.

Sil 2 FSC RF ROJoS PC-C V-25C V 2022 E5 2 A/C I/4 CK-S SA OC U-l RF N2 SUPPLY TO II:0, MONITORS.

SII 2 FSC RF ROJ48 PC-CV-26CV 2022 D6 2 A 'C 1/4 CK 5 SA O 'C U-l RF N2 SUPPLY TO II;O, MONITORS.

Sil 2 FSC RF ROJ48 PC-CV-27CV 2022 C6 2 AfC 1/4 CK-S SA O 'C U-l RF O2 SUPPLY TO II,0, MONITORS.

Sil 2 FSC RF ROJ48 PC-CV-33CV 2027 A2 2 A/C 3/8 CK-S SA C U-l RF N2 SUPPLY TO RR-AOV-741 AV.

FSC Cs CSJ45 PC-CV-34CV 2027 A2 2 A/C 3/8 CK-S SA C U-l RF N2 SUPPLY TO RR-AOV-741 AV.

FSC CS CSJ45 PC CV-35CV 2028 D8 2 A/C 3/8 (K SA C U-l 2Y X-45D PASSIVE ISOLATION PC-CV-36CV 2028 D7 2 A/C 3/8 CK SA C U-l 2Y X-45D PASSIVE ISOLATION PC-MOV-230M V 2022 El 2 A 24 BTF MO C U-l RF SUPPRESSION CIIAMBER EXIIAUST Sil 1 FSC Q INBOARD ISOLATION PIT 2Y Revision 2 Section V Page 45 of 155 l

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRDIARY CONTAINMENT (PC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIt' TION COOR Cf A%S CAT %f7F TYPF TYPF POS RO\fT FRfD PC-MOV-231MV 2022 CI 2 A 24 BTF MO C U-1 RF DRYWELL EXII AUST INBOARD S11 i FSC Q ISOLATION PIT 2Y 10MOV-232MV 2022 D4 2 A 24 BTF MO C 13-1 RF DRYWELL INLET INBOARD Sil 1 FSC Q ISOLATION PIT $

2Y PC-MOV-233MV 2022 E4 2 A 24 BTF MO C U -l RF SUPPRESSION CilAMBER INLET Sil 1 FSC Q INBOARD ISOLATION PIT 2Y i

10MOV-305MV 2022 El 2 A 2 GT MO C U-l RF PC-MOV-230MV BYPASS Sil 1 FSC Q PIT 2Y PC-MOV-306M V 2022 C1 2 A 2 GT MO C U-I RF 10MOV-231MV BYPASS Sil 1 FSC Q PIT 2Y PC-MOV-130lM V 20S4 F8 2 A 1 GT MO O U-l RF SUPPRESSION CilAMBER ISOLATION FSC Q SYSTEM B PIT 2Y 10MOV-1302MV 2084 F7 2 A 1 GT MO O U-I RF SUPPRESSION CllAMBER ISOLATION FSC Q SYSTEM B PIT 2Y 10MOV-1303MV 2084 F4 2 A I GT MO C U-l RF SUPPRESSION CilAMBER ISOLATION FSC Q SYSTEM A i PIT 2Y Revision 2 Section V Page 46 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAINIARY TABLES SYSTEM: PftI3fARY CONTAIN31ENT (PC)

VALVE CIC P&ID P&ID' ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRll'FION COOR CT ASS CAT Sf7F TYPF TYPF POS R O\tT FRFO PC-MOV-1344MV 20 4 F4 2 A 1 GT MO C U-l RF SUPPRESSION CIIAMBER ISOLATION FSC Q SYSTLM A i PIT 2Y PC410V-1305M V 2084 E4 2 A 1 GT MO C U -l RF DRYWELL ISOLATION SYSTEM .A FSC Q.

PIT 2Y PC410V-1306%1V 2084 E4 2 A 1 GT MO C U-1 RF DRYWELLISOLATION SYSTEM A FSC Q PIT 2Y ,

PC-MOV-130SMV 20M 11 7 2 A 1 GT MO C U-l RF BLEED ISOLATION FOR FSC Q SUPPRESSION CIIAMBER PIT 2Y PCalOV-1310MV 2084 C7 2 A 1 GT MO C U-l RF BLEED ISOLATION FOR DRYWELL FSC Q PIT 2Y PC410V 1311MV 2084 E7 2 A 1 GT MO O U-l RF DRYWELL DILUTION SUPPLY FSC Q ISOLATION SYSTEM B PIT 2Y PC-MOV-1312MV 20M E7 2 A 1 GT MO O Ul RF DRYWELL DILUTION SUPPLY FSC Q ISOLATION SYSTEM B PIT 2Y I

i Revision 2 Section V Page 47 of 155

COOPER NUCLEAR STATION TIllRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUAIAIARY TABLES SYSTE31: RADIATION 310NITORING (R31V)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORS1 TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RONfT FREQ RMV-AOV-10AV 2022 E10 2 A 3/4 GB AO O U-l RF RSt-4 CONTAIN\ LENT ISOLATION, 5 11 i FSC Q INBOARD FST Q PIT 2Y RM V-AOV-II AV 2022 E10 2 A 3/4 GB AO O U-l RF RM-4 CONTAINMENT ISOIAT10N, Sil i FSC Q OUTBOARD FST Q PIT 2Y RMV-AOV-12AV 2022 F10 2 A 3/4 GB AO O U-l RF RM-4 CONTAINMENT ISOLATION, !,

511 1 FSC Q INBOARD FST Q PIT 2Y RM V- AOV-13AV 2022 FIO 2 A 3/4 GB AO O U-l RF RM-4 CONTAINMENT ISOLATION, Sil i FSC Q OUTBOARD FST Q PIT 2Y

i Revision 2 Section V Page 48 of 155 l

l

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SU31 MARY TABLES SYSTEM: RADIOACTIVE WASTE (RW)

VALVE CIC P&lD

^ ^ ^ NOTES!DESCRIP110N CAT COOR CLASS SIZE TYPE TYPE POS RQMT FREQ RW-AOV-AOR2 2038 G5 2 A 3 GT AO O U -I RF DRYWELL FLOOR DRAIN SUMP FSC Q DISCIIARGE FST Q PIT 2Y RW-AOV-A083 2038 G5 2 A 3 GT AO O U-l RF DRYWELL FLOOR DRAIN SUMP FSC Q DISCIIARGE FST Q !

PIT 2Y [

RW-AOV-AO94 2028 Gil 2 A 3 GT AO O U-l RF DRYWELL EQUIPMENT DRAIN FSC Q SUMP DISCIIARGE !

FST Q PIT 2Y I RW-AOV-AO95 2028 G12 2 A 3 GT AO O U-l RF DRYWELL EQblPMENT DRAIN FSC Q SUMP DISCIIARGE i FST Q PIT 2Y RW-CV-58CV 2005 G:3 A C 2 CK-S SA C FSO Q Z SUMP PUMP A DISCIIARGE Sil 2 FSC Q Cill!CK RW-CV-59CV 2005 GIO A C 2 CK-S SA C FSO Q Z SUMP PUMP B DISCIIARGE Sil 2 13C Q CIIECK l

Revision 2 Section V Page 49 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUA131ARY TABLES r SYSTD1: REACTOR CORE ISOLATION COOLING (RCIC)

P&lD 151 IST VALVE VALVE ACT TEST TEST

^ CIASS CAT SIZE

^

COOR ~1TPE TYPE RQN1T FREQ POS RCIC-AOV-AO34 3MI GIO 2 B I GB AO O FSC Q RCIC STEA%1 LINE DRIPLEG DRAIN FST Q PIT 2Y RCIC-CV-10CV 2043 13 2 C 6 CK-S SA C FSO Q ECST SUPPLY TO RCIC PU51P.

FSr CS CSJ-II RCIC-CV IICV 343 1110 2 C 6 CK-S SA C FSO RF RCIC SUPPLY FRON1 SUPPRESSION FSC RF CllAN1BER. ROJ 09 RCIC-CV 12CV 3M3 G9 2 C 2 CK-S SA C FSC RF VACUUN1 PUNIP DISCllARGE TO SUPPRESSION C11 A%1BER. ROJ-10 RCIC-CV-13CV 2043 DS 2 C 2 CK-P SA C FSO Q 511NIN1U%1 FLOW LINE. ROJ-10 FSC RF ,

RCIC-CV-15CV 3M3 D9 2 A/C 8 CK-S SA C U-l RF RCIC TURBINE ENilAUST TO FSC RF SUPPRESSION CII AN1BER. ROJ-10 I

FSO Q RCIC CV-18CV 3M3 B8 2 C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO RCIC PRESSURE h1AINTENANCE. RV-11 RCIC CV-19CV 2(M3 B8 A C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO RCIC PRESSURE A1AINTENANCE. RV-11 RCIC CV-20CV 3M3 117 A C 2 CK-P SA C PSO Q RCIC LUBE OIL COOLING WATER FSO RF RETURN. ROJ-17 Resision 2 Section V Page 50 of 155

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTE.\l: REACTOR CORE ISOLATION COOLING (RCIC)

P&lD ISI IST VALVE VALVE ACT TEST TEST VALVE CIC P&lD COOR CLASS CAT SIZE TYPE TYPE RQN!T FREQ POS I

RCIC-CV-21CV 2(43 117 2 C 2 CK-P SA C PSO Q RCIC CONDENSATE PUNIP FSO RF DIScilARGE, ROJ-17 FSC RF RCIC-CV-22CV 2043 E10 2 C i 1/2 CK-L SA C VBT RF RCIC VACCUNI BREAKER. RV-14 RCIC-CV-23CV 2(M3 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUUAf BREAKER. RV-14 RCIC-CV-24CV 2043 EIO 2 C 110 CK-L SA C VBT RF RCIC VACUUN1 BREAKER, RV-14 RCIC-CV-25CV 2143 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUU%1 BREAKER. RV-14 RCIC-CV-26CV 2043 C9 i A/C 4 CK-S SA O LI-I RF INJECTION CilECK VALVE. CSJ4)2 FSO CS FSC CS ;

PIT 2Y RCIC-510V-51015 2(M1 D6 i A 3 GT 51 O O U-l RF RCIC STEA%1 INBOARD ISOLATION FSC Q PIT 2Y RCIC-510V-51016 2041 D7 1 A 3 GT AIO O U-l RF RCIC STEAN1 OUTBOARD ;

, FSC Q ISOLATION PIT 2Y l

Revision 2 Section V Page 51 of 155 t

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUMAIARY TABLES l

SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

P&lD ISI IST VALVE VALVE ACT TEST TEST CAT COOR CLASS SIZE TYPE TYPE RQMT FREQ POS RCIC-MOV-MO!8 2(M3 J3 2 B 6 GT MO O FSO . Q RCIC SUPPLY FP.OM CONDENSATE FSC Q STORAGE PIT 27 RCIC MOV-MO20 2&43 C8 2 B 4 GT MO O FSO Q RCIC PUMP DISCIIARGE PIT 2Y RCIC-MOV41021 204) C8 2 B 4 GT MO C FSO Q RCIC INJECT'ON TO REACTOR PIT 2Y RCIC-MOV41027 2(M3 D7 2 B 2 GB MO C FSO Q RCIC PUMP MINIMUM FLOW FSC Q RECIRCULATION TO SUPPRESSION PIT 2Y CllAMBER RCIC-MOV41030 2043 El 2 B 4 GB MO C PIT 2Y RCIC TEST RETURN ROOT I RCIC-MOValO33 2G43 El A B 4 GT MO C PIT 2Y RCIC TEST RETURN SilUTOFF RCIC-MOV-MO41 2G43 GIO 2 B 6 GT MC C FSO Q RCIC SUPPLY FROM SUPPRESSION ,

FSC Q CIIAMBER PIT 2Y !

RCIC410V410131 2041 F8 2 B 3 GB MO C FSO Q RCIC STEAM SUPPLY TO RCIC PIT 2Y TURBINE RCIC-MOV4fOl32 2043 E3 2 B 2 GB MO C FSO Q AUXILIARY COOLING SUPPLY PIT 2Y RCIC-R D-S240 2n43 E4 ? D 8 RD SA C RD SY EXil AUST LINE RUPTURE DISC Revision 2 Section V Page 52 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEA1: REACTOR CORE ISOI.ATION COOLING (RCIC)

P11D ISI IST VALVE VALVF ACT TEST TEST

^ COOR CLASS CAT SIZE TYPE TYPE POS RQN1T FREQ RCIC-RV-10RV 2043 113 2 C 1 RV SA C RVT 10Y RCIC PUN 1P SUCTION RELIEF RCIC-RV-11RV 2M3 G5 2 C 1 RV SA C RVT 10Y RCIC AUXILIARY COOLING SYSTENT RCIC-V-37 2043 D9 2 A:C 8 S-CK N1A O LJ-l RF RCIC TURBINE EXilAUST TO FSO Q SUPPRESSION CllAN1BER FSC RF ! SOLATION. ROJ-Il RCIC-V-42 2M3 G9 2 C 2 S-CK NtA O FSC RF RCIC VACUUN1 PUNIP DISCilARGE TO SUPPRFSSION Cil AN1BER. ROJ-i l t

Kevision 2 Section V Page 53 of 155

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES .

SYSTE.\f: FEACTOR EQUIP 31ENT COOLING (REC)

I VALVE CIC P&lD P&lD 151 IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION Cone rtAss r u_ sr7F TYPF TYPF POS kn\1T FRFG REC-AOV-TCV861 2031 CIO 3 B I GB AO T FSO Q FC-R-E INLET SII 2 FST Q REC-AOV-TCV867 '031 C9 3 B l-l!4 GB AO T FSO Q FC-R-II INLET Sil 2 FST Q REC-AOV-TCV8M 2031 Eo 3 B GB AO T l'SO Q FC-R-F INLET Sil 2 FST Q R EC-AOV-TCV865 2031 E8 3 B l-1/4 GB AO T FSO Q F-R-J INLET S!I 2 FST Q REC CV-leCV 2031 F1 3 C 8 CK-T SA O FSO Q REC-P-A DISCIIARGE Sil 2 FSC Q REC-CV-1 ICV 2')31 F2 3 C P, CK-T SA O FSO Q REC-P-B DISCl!ARGE Sil 2 _

FSC Q REC CV-12CV 2031 F3 3 C 8 CK-T SA O FSO Q REC-P-C DISCilARGE Sil 2 FSC Q REC-CV-13CV 2031 F4 3 C 8 CK-T SA O FSO Q REC-P-D DISCilARGE Sil 2 FSC Q l REC-CV-mCV 2031 111 3 C 12 CK-S SA O FSC RF NON-CRITICAL IIEADER RETURN Sil 2 TO REC PUMPS, ROJ-12 REC-MOV-694MV 2031 J2 3 B 4 GT MO O PIT 2Y PASSIVE CRITICAL LOOP RETURN Sil 2 CROSSTIE REC-MOV-695M V 2031 D4 3 B 4 GT MO O PIT 2Y PASSIVE CRITICAL LOOP SUPPLY Sil 2 CROSSTIE Revision 2 Section V Page 54 of 155 i

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRtOI VALVE SU3151ARY TABLES 1

SYSTEM: REACTOR EQUIPMENT COOLING (REC) l l VALVE Cic P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES 'DESC RIPTION COOR F1 A%9 RAT Sf7F TYPF TYPF POS ROtfT FRFO R EC-M OV-697MV 2031 J2 3 B 6 GT MO O FSO Q NORTil CRITICAL LOOP RETURN Sil 2 FSC Q PIT 2Y REC 410V-698MV 2031 Jl 3 B 6 GT MO O FSO Q SOUTil CRITICAL LOOP RETURN

Sil 2 FSC Q PIT 2Y REC 410V-700N1V 2031 B1 3 B 10 GT MO O FSC Q NON CRITICAL LOOP SUPPLY Sil 2 PIT 2Y S11UTOFF REC-MOV-702M V 2031 A4 2 A 8 GT MO O U-l RF DRYWELL SUPPLY ISOLATION Sil 2 FSC Q VALVE PIT 2Y REC-MOV-709M V 2031 G3 2 A 8 GT MO O U-I RF DRYWELL RETURN ISOLAT10N Sil 1 FSC Q VALVE PIT 2Y REC 410V-711MV 2031 D4 3 B 6 GT MO O FSC Q NORTil CRITICAL LOOP SUPPLY i Sil 2 FSO Q PIT 2Y r i

REC 410V-712MV 2031 D2 3 B 12 BFL MO O FSC Q REC IIEAT EXCIIANGER A OUTLET Sil 2 PIT 2Y REC 410V-713MV 2031 C2 3 B 12 BFL MO O FSC Q REC llEAT EXCilANGER B OUTLEF ,

Sil 2 PIT 2Y :

Revision 2 Section V Page 55 of 155

COOPER NUCLEAR STATION '

TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUADIARY TABLES SYSTEM: REACTOR EQUIPMENT COOI.ING (REC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORNI TEST TEST NOTE 5 DESCRIPT10N rOOR ct tss FAT st7F TYPF TYPF POs RO\fT FRFO REC 410V-714N1V 203I C4 3 B 6 GT 51 0 0 FSC Q SOUTII CRITICAL LOOP SUPPLY Sil 2 FSO Q PIT 2Y REC 410V-132951V 2031 C2 3 B 8 GT N10 0 FSC Q AUXILIARY RADIOACTIVE WASTE Sil 2 PIT 2Y BUILDING SUPPLY t

Revision 2 Sectum V Page 56 of 155

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUA151ARY TAELES SYSTEM: REACTOR FEEDWATER (RF)

VALVE CIC P&lD

' ^ ^ ^ ' NOTES' DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ%fT FREQ RF CV-13CV 2(M4 B10 1 AC IN CK-T SA O Ul RF FEEDWATER LINE B TO REACTOR l FSC RF OUTBOARD. ROJ 13 RF-CV-14CV 2M4 Cil 1 A/C lx CK-T SA O U-I RF FEEDWATER UNE B TO REACTOR '

FSO RF INBOARD, ROJ-13. ROJ-14 FSC RF RF-CV-15CV 2(M3 BIO I A/C IN CK-T SA O U-1 RF FEEDWATER UNE A TO REACTOR FSC RF OtJTBOARD. ROJ-13 RF CV-16CV 2(43 Cil 1 A!C 18 CK-T SA O U-l RF FEEDWATER UNE A TO REACTOR FSO RF INBOARD. ROJ-13. ROJ-14 FSC RF

, Reusion 2 Section V Page 57 of 155

COOPER NUCLEAR STATION TilIRD INTERVAL

, INSERVICE TESTING PROGRA31 VALVE SU3151ARY TABLES SYSTDt: REACTOR RECIRCUIATION (RR)

VALVE CIC P&lD

' ' ^ ^ ^ ' . NOTES / DESCRIPTION I COOR CIASS CAT SIZE TYPE- TYPE POS RQNIT FREQ l RR-AOV-740AV 2027 Al 1 A 3/4 GB AO O U-l RF SP-1 OUTBOARD ISOIATION FSC Q FST Q !

PIT 2Y RR-AOV-741 AV 2027 A2 1 A 374 GB AO O Ul RF SP-I INBOARD ISOLATION -

FSC Q FST Q PIT 2Y RR410V41053A 2027 B4 1 B 2M GT N10 0 FSC CS RR PUMP A DISCIIARGE PIT 2Y CSJ4%

RR410V4tO53B 2027 B7 I B 28 GT MO O FSC CS RR PU51P B DISCII ARGE Prr 'y est(w Revision 2 Section V Fage 58 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTEM: REACTOR WATER CLEANUP (RWCU)

P&ID 151 IST VALVE VALVE ACT NOR51 TEST TEST V VE N P&lD NOTFS' DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RWCU-CV-15CV 2(M2 C4 1 A!C 4 CK-S SA O U-I RF RWCU RETURN TO REACTOR Sil 1 FSC RF VESSEL ROJ-15 RWCU410V-MO15 2fM2 E2 i A 6 GT MO O U-l RF RWCU SUPPLY INBOARD Sli i FSC Q ISOLATION PIT 2Y RWCU4 TOV 41018 2042 B4 1 A 6 GT 51 0 0 U-l RF RWCU SUPPLY OUTBOARD Sil i FSC Q ISOLATION PIT 2Y i

Resision 2 Section V Page 59 of 155

COOPER NUCLEAR STATION TIIIRD MTERVAL INSERVICE TESTING PROGRAAI VALVE SUAIAIARY TABLES SYSTE.\1: RESIDUAL IIEAT RE.\lOVAL (RIIR) l 1

V VE CIC P&lD

^ ^ ^ * ' NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ l l

Rl!RCV-10CV 2040 G3 2 C 3 CK-S SA C PSO Q Ri!R PUMP A MINIMUM FLOW. ROJ-Sif 1 FSO RF 18 FSC Q Ri!R-CV-1 ICV 2040 GIO 2 C 3 CK-S SA C PSO Q RIIR PUMP B MINIMUM FLOW. ROJ SII I FSO RF 18 FSC O RIIR-CV-12CV 2n40 114 2 C 3 CK-S SA C PSO Q RilR PUMP C MINIMUM FLOW. ROJ-Sil i FSO RF 18 FSC Q RiiR-CV-13CV 2NO Illo 2 C 3 CK-S SA C PSO Q RilR PUMP D MINIMUM FLOW. ROJ-Sil 1 FSO RF 18 FSC Q Ri!R-CV-14CV 2040 G3 2 C 16 CK-T SA C FSO Q RIIR PUMP A DISCIIARGE S!! I FSC Q _

RilR-CV-15CV 2040 GIO 2 C 16 CK-T SA C FSO Q RilR PUMP B DISCllARG*i Sil 1 1:SC Q RIIR-CV-16CV 2040 113 2 C 16 CK-T SA C FSO Q RIIR PUMP C DISCilARGE Sil 1 FSC Q RilR-CV-17CV 2040 1110 2 C 16 CK-T SA C FSO Q RIIR PUMP D DISCilARGE S11 1 FSC Q l RIIR-CV-18CV 2010 A9 A C 4 CK-S SA C FSC Q RI!R LOOP B OUTBOARD PRESSURE SIl i M AINTENANCE SUPPLY. RV-12 l

Resision 2 Section V Page 60 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAAI VALVE SUADIARY TABLES SYSTDI: RESIDUAL IIEAT RE.TIOVAL (RIIR) i VALVE CIC P&lD ^ ' ^ -

COOR CLASS CAT SIZE TYPE TYPE NOTES!DESCRIPT10N POS _ RQMT FREQ RilR-CV-19CV 2040 A9 2 C 4 CK-S SA C FSC Q RiiR LOOP B INBOARD PRESSURE

' SII I MAINTENANCE SUPPLY. RV-12 RilR-CV-24CV 2040 C4 A C 4 CK-S SA C FSC Q RIIR LOOP A OUTBOARD PRESSURE Sil 1 MAINTENANCE SUPPLY. RV-12 RilR-CV-25CV l'2040 C4 2 C 4 CK-S SA C FSC Q RIIR LOOP A INBOARD PRESSURE Sil 1 MAINTENANCE SUPPLY. RV-12 RilR-CV-26CV 2040 C6 i A!C 24 CK-S SA C U -I RI' UX)P A INJECTION LINE TESTABLE Sil I LT-2 RF CllECK PRESSURE ISOLATION FSO CS VALVE. CSJ 4)I FSC CS PIT 2Y RilR-CV-27CV 2NO C7 1 A/C 24 CK-S SA C U-l RF LOOP B INJECTION LINE TESTABLE Sil 1 LT-2 RF CIIECK. PRESSURE ISOLATION FSO CS VALVE. CSJ 41 FSC CS PIT 2Y RIIR-MOV-M012A 2040 E2 2 B 16 GT MO O FSO Q RilR IIEAT EXCilANGER A OUTLET Sil 1 PIT 2Y RilR-MOV-M012B 2MO Fil 2 B 16 GT MO O FSO Q RIIR IIEAT EXCllANGER B OUTLET SI! 1 PIT 2Y RilR-MOV-MOl3A 2040 G6 2 B 20 GT MO O FSO Q RilR PUMP A SUCTION FROM Sil i FSC Q SUPPRESSION CllAMBER PIT 2Y Revision 2 Section V Page 61 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU31AIARY TABLES SYSTD1: RESIDUAL IIEAT RDIOVAL (RIIR) yg,o vE CIC P&lo mo m IST VAWE VAWE AG NORSt M W N* OTES/ DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR410V-MOl3B 2440 G8 2 B 20 GT MO O FSO Q RIIR PUMP B SUCTION FROM S11 1 FSC Q SUPPRESSION CllAMBER FIT 2Y '

RIIR-MOV41013C 2G50 G6 2 B 20 GT MO O FSO Q RilR PUMP C SUCTION FROM Sil 1 FSC Q SUPPRESSION CilAMBER PIT 2Y RilR410V-Mol3D 2(M0 G7 2 B 20 GT MO O FSO Q REIR PUMP D SUCTION FROM 511 1 FSC Q SUPPRESSION CIIAMBER ;

PIT 2Y RilR MOV41015A 2040 G5 2 B 20 GT MO C FSC Q RilR PUMP A SDC SUCTION Sll i PIT 2Y RIIR410V41015B 2(M0 G8 2 B 20 GT MO C FSC Q RilR PUMP B SDC SUCTION Sil 1 PIT 2Y RIIR41OV41015C 2040 115 2 B 20 GT MO C FSC Q RilR PUMP C SDC SUCTION Sil 1 PIT 2Y RIIR410V41015D 2040 113 2 B 20 GT MO C FSC Q RilR l' UMP D SDC SUCTION SIl i PIT 2Y !

RilR-MOV41016A 2440 E3 2 B 4 GT MO O FSO Q PUMP A AND C MINIMUM FLOW SII I FSC Q PIT 2Y Resision 2 Section V Pap 62 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SUAIA1ARY TABLES SYSTE31: RESIDUAL IIEAT RE310 VAL (RIIR)

VALVE CIC P&lD

' ^ ^ ^

^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RilR-MOV-MOl6B 2040 E10 2 B 4 GT MO O FSO Q PUMP B AND D MIMINUM FLOW Sil 1 FSC Q PIT 2Y Ri!R-MOV-MOl7 2(W) D5 i A 20 GT MO C U-l RF RilR SDC SUPPLY OUTBOARD Sll I LT-2 RF PRESSURE 1501 ATION VALVE.

FSC CS CSJ4)7

PIT 2Y RilRalOV-MOl8 2040 D6 1 A 20 GT MO C U-l RF RilR SDC SUPPLY INBOARD Sil 1 LT-2 RF PRESSURE ISOLATION VALSTn FSC CS CSI-07 PIT 2Y RilR410V-MO20 2040 til 2 B 20 GT MO C PIT 2Y RilR PASSIVE CROSSilEADER Sil 1 SilUTOFi-RIIR410V-MO25A 2040 C5 1 A 24 GT MO C U-l RF RIIR LOOP A IN1ECTION INBOARD Sil I LT-2 RF ISOLATION FSO Q FSC Q PIT 2Y !

RIIR410V-T IO25B 2040 C8 I A 24 GT MO C U-l RF RilR LOOP B INJECTION INBOARD Sil 1 LT-2 RF ISOLATION FSO Q FSC Q Prr 2Y Roisson 2 Section V Page 63 of ISS

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SUM 31ARY TABLES SYSTE3f: RESIDUAL IIEAT RE310 VAL (RIIR)

__ ^m -

VALVE CIC P&ID

' ^ '

COOR CLASS CAT SIZE TYPE NOTES / DESCRIPTION TYPE POS RONIT FREQ RilR410V41026A 2(MO B4 2 A 10 GT MO C U -l RF DRYWELL SPRAY LOOP A Sil i FSC Q OUTBOARD ISOIATION PIT 2Y RilRaiOV41026B 2(MO 89 2 A 10 GT N10 C U -l RF DRYWELL SPRAY LOOP B Sil i FSC Q OUTBOARD ISOLATION PIT 2Y RilR410V41027A 2040 C4 1 B 24 ANG N1O O FSO Q LOOP A INJECTION OUT110ARD Sil 1 I PIT 2Y TilROTTLE RIIR4 TOV 41027B 2(M0 C9 1 B 24 ANG MO O FSO O LOOP B INJECTION OUTBOARD Sil 1 PIT 2Y TilROTTLE RilR410V41031 A 2(MO B5 ; A 10 GT MO C U-l RF DRYWELL SPRAY LOOP A INBOARD SII I FSC Q ISOLATION PIT 2Y RilR410V41031B 2(MO B8 2 A 10 GT MO C U-l RF DRYWELL SPRAY LOOP B INBOARD Sil 1 FSC Q ISOLATION PIT 2Y RilR410V41034A 2040 E4 2 A 18 GB MO C U-l RF SUPPRESSION CilAMPER COOLING ,

Sil i FSO Q LOOP A INBOARD TilRO^ITU' !

FSC Q ,

PIT 2Y Revision 2 Section V Page 65 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTE31: RESIDUAL IIEAT RE310 VAL (RIIR) i VAISE CIC P&lD

^ ' ^ ^ '

NOTES / DESCRIPTION COOR CLASS CAT- SIZE TYPE TYPE POS ROMT FREQ RilR410V41034B 2n*0 E9 2 A 18 GB MO C U-1 RF SUPPRESSION CIIAStBER COOLING -

Sil 1 FSO Q LOOP B INBOARD T11ROITLE FSC Q PIT 2Y RilR410V-MO3MA 2040 D5 2 A 6 GB MO C U-I RF SUPPRESSION CilAMBER SPRAY Sil 1 FSO Q LOOP A INBOARD TIIROTTLE FSC Q PIT 2Y nllR 410 V 4f038B' 24:0 D9 2 '

A 6 GB MO C U-l RF SUPPRESSION CllAMBEtt SPRAY Sil I FSO Q LOOP B INBOARD T11ROTTLE FSC Q PIT 2Y RllR410V41039A 2440 D4 2 A 18 GT MO C U-l RF SUDPRESSION CllAMBER COOLING Sil i FSO Q LOOP A OUTBOARD ISOLATION FSC Q PIT 2Y RilR410V41039B 2040 DIO 2 A 18 GT MO C U-l RF SUPPRESSION CllAMBER COOUNG Sil 1 FSO Q LOOP B OUTBOARD ISOIATION FSC Q PIT 2Y RilR-MOV-MO57 2040 112 2 B 4 GB MO C LT-2 RF RIIR DISCilARGE TO RADWASTE Sil 2 FSC Q INBOARD TilROTTLE PIT 2Y Revision 2 Section V Page 65 of 155

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SUAIAIARY TABLES i

SYSTD1: RESIDUAL IIEAT RDIOVAL (RIIR)

VALVE CIC P&lD

' ^ ^ ^

NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ Rilk-f.10V41065A 2(MO G2 2 B 16 GT MO O FSO Q RilR llEAT EXCIIANGER A INLET Sil i PIT 2Y RIIR-MOV-MO65B 2040 Gl! 2 B 16 GT MO O FSO Q RilR IIEAT EXCilANGER B INLET 511 1 PIT 2Y RIIR-MOV41066A 2MO F2 2 B 20 GB MO O FSO Q RilR IIEAT EXCilANGER A BYPASS Sli i FSC Q TilROTTLE PIT 2Y R11R419V4tO66B 2040 FII 2 B 20 GB MO O FSO Q RilR llEAT EXCll ANGER B BYPASS Sil 1 FSC Q T:IROTTLE PIT 2Y RIIR410V-MO67 2(M0 112 2 B 4 GT MO C LT-2 RF RilR DISCIIARGF TO RADWASTE Sil 2 FSC Q OUTBOARD SilUTOFF PIT 2Y RilR MOV-MOl66A 2(M1 112 2 A I GB MO C U-i RF RIIR llEAT EXCIIANGER A VENT RilR410V410166B 2(M t 112 2 A 1 GB MO C U-l RF RilR llEAT EXCIIANGER B VENT RilR-MOV410167A 2{MI til 2 A I GB MO C U-l RF RilR IIEAT EXCilANGER A VENT RIIR410V4101678 234I 112 2 A I GB MO C 13-1 RF RIIR ilEAT EXCIIANGER B VENT -

Revision 2 Section V Page 66 of 155

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SUMMARY

TABLES i

i SYSTE31: RESIDUAL IIEAT RE310 VAL (RIIR) 1 VALVE CIC P11D I A A A ORM M M NOTES /DI3CRIPTION l COOR CIASS CAT 517.E TYPE TYPE POS RCMT FREQ RllR-MOV-MO274A 2(141 C6 2 A 2 GB MO C U-l RF RIIR-CV-20CV PASSIVE BYPASS LT-2 RF PRESSURE ISOLATION VALVE PIT 2Y RilR-MOV-MO274B 2fMI C7 2 A 2 GB MO C U-l RF RIIR CV 27CV PASSIVE BYPASS LT-2 RF PRESSURE ISOLATION VALVE PTT 2Y RilR MOV-920MV 2(M1 El 2 B 3 GT MO C FSC CS STEAM SUPPLY TO AOG PIT 2Y UPSTREAM SIIUTOFF. CSI 08 RilR.MOV-921MV 2(M t El A B 3 GT MO C FSC CS STEAM SUPPLY TO AOG PIT 2Y DOWNSTREAM SIIUTOFF. CSI413 RIIR-RV-10RV 2fm G5 2 C 1 RV SA C RVT 10Y RIIR PUMP A SUCTION RELIEF Sif 1 i

s Resision 2 Section V Page 67 of 155

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 ,

VALVE SMI3tARY TABLES I

i SYSTDI: RESIDUAL HEAT RD10 VAL (RIIR)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORif TEST TEST NOTES ^ DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ\fT FREQ R11R-RV-IIRV Jun G3 2 C 1 RV SA C RVT 10Y RIIR PUSIF B SUCTION REUES SII I j RIIR-RV-12RV 3M0 115 2 C 1 RV SA C RVT 10Y RilR POIP C SUCTION REUEF Sif I RIIR RV-13RV 3MO 118 2 C I RV SA C RVT 10Y R11R POIP D SUCTION REUFF S 11 1 RIIR-RV-14RV 3un C3 2 C I RV SA ^ C RVT 10Y RIIR LOOP A SUPPLY REUEF l Sif I RIIR-RV-15RV NMO CIO 2 C 1 RV SA C RVT 10Y RIIR LOOP B SUPPLY RLUEF Sif I i '

IS RilR-RV-17RV 3u0 2 C 1 RV SA C RVT 10Y SIIUTDOWN COOLING Sil 1 SUPPLY REUEF

RilR-RV-18RV 2tMI GI 2 C 2% RV SA C RVT 10Y STEA%I SUPPLY TO RIIR U-l RF IIEAT EXCIIANGER A REllEF f

RhlR-RV-19RV 3MI G3 2 C 2% RV SA C RVT 10Y PANI SUPPLY TO R11R IIEAT 4 UI RF EACII ANGER B REUEF d

RIIR-HV-20RV 3MI G2 2 C 1 RV SA C RVT '

10Y RHR IIE,*.T EXCIIANGER A S11 ELL U-I RF SIDE REUEF RIIR-RV-2iRV 2(Mt G2 2 C 1 RV SA C RVT 10Y RIIR IIEAT EXC11ANGErt B SIIELL ,

13-1 RF SIDE RELIEF i

Resision 2 Seuxm V Pace 68 of 155 j I

i

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES SYSTDI: RESIDUAL HEAT RE310 VAL (RIIR) i VALVE CIC P&lD P&lD 151 IST VALVE VALVE ACT NORSI TEST TEST NOTES DESCRWT10N COOR CLASS CAT SIZE TYPE I TYPE POS RO\fT FRET)

RIIR-SOV-SSVfD 32) G2 2 B % SOV SO C FSC Q RilR llEAT EXC11 ANGER B PASS Sli i FST Q SA%1PLE VALVE PTT 2Y RilR SOV-SSV61 3M) F2 A B % SOV SO C FSC Q RilR liEAT EXC11 ANGER B PASS Sil 1 FST Q SANtPLE VALVE PTT 2Y RilR-SOV SSY95 3W) GI2 2 B % SOY SO C FSC Q RilR liEAT EXCIIANGER A PASS Sil ! FST O SAltPLE VALVE PIT 2Y RIIR-SOV-SSV96 NW) F12 A B % SOY SO C FSC Q RilR llEAT EXC11 ANGER A PASS Sil 1 FST Q S A%1PLE VALiE PIT 2Y _

1 Re,isitm 2 Sectx m V Page fW of 155 i

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COOPER NUCLEAR STATION TIIIRD INTERVAL 4 INSERVICE TESTING PROGRAM VALVE SUM 31ARY TABLES SYSTE.TI: SERVICE WATER (SM l .

4 VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NOR_M TEST .. TEST NOTES DESCRIPTION ,

j COOR CLASS CAT SIZE TYPE TYPE POS ROMT FREQ SW-AOV450AV 20 % G8 3 B 2 BAL AO O FSC Q REC ilEAT EXCli ANGER A OUTLET FST Q PROCESS RAD MONITOR SUPPLY ITT 2Y !

SW AOV451 AV 3)% G7 3 B 2 BAL AO O FSC Q REC IIEAT EXCIIANGER B OUTLET I FST Q PROCESS RAD MONITOR SLTPLY PIT 2Y SW. AOV452AV 20 % GR 3 B 2 BAL AO O FSC Q REC IIEAT EXCll ANGER A OLTLET

{ FST Q PROCESS RAD MJNITOR SUPPLY PTT 2Y SW-AOV-M53AV 3A% G4 ; B 2 BAL AO O FSC Q REC IIEAT EXCilANGER B OUTLET FST Q PROCESS RAD MONITOR SUPPLY PIT 2Y [

SW-AOV-854AV 20M G8 3 B 2 BAL AO C PIT 2Y SW PASSIVE RAD MONITOR !

SAMPLE RETURN t

SW-AOV455AV 20 % G4 3 B 2 BAL AO C PIT 2Y SW PASSIVE RAD MONTTOR SAMPLE RETURN SW-AOV-TCV451 A 20 % E7 3 B 12 GB AO OT FSO Q REC IIEAT EXCliANGER A OUTLET Sil I FST Q TEMPERATURE CONTROL VALVE.

PIT 2Y CSJJN SW-AOV-TCV451B 20 % F7 3 B 12 GB AO OT FSO Q REC IIEAT EXCllANGER B OLTIIT Sif 1 FST Q TEMPERATURE CONTROL VALVE. :

PIT 2Y CSJ4N i

! l SW-CV- A RA 31 % Es ~4 C 6 CK SC C FSC O SW AIR RELEASE l i j t

Reviuon 2 Secthm V Page 3) of 155

COOPER NUCLEAR STATION '

THI.RD INTERVAL l INSERVICE TESTING PROGRAM -

VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW) i i VALVE CIC PalD P&lD ISI I IST VALVE VALVE ACT NORM TEST TEST NOTES DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQ\fT FREQ SW CV- \RB 20 % C5 3 C 6 CK SC C FSC Q SW AIR RELEASE I

SW-CV-10CV 386 All 3 C 3) CK-D SA O FSO Q SW PDIP A DISCIIARGE r 511 1 FSC Q < l f

SWCV-11CV 384 A8 3 -

C 3) CK-D SA O FSO Q SW PD1P B DISCIIARG's t SII I FSC Q {

SW-CV-12CV 2fsM AIO 3 C 3) CK-D SA O FSO Q SW PDtP C DISCIIARGE I Sil-1 FSC Q SW-CV-13CY 3m% A7 3 C 20 CK D SA O FSO Q SW PD1P D DISCIIARGF Sil i FSC Q f l

SW-CV-l'<v 20 % G3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER PD1P A j FSC Q DLWilARGE :

SWCV-20CV 2036 F3 3 C 14 CK-T SA C FSO Q R.IIR SW IKX) STER PDIP B FSC Q DISCIIARGE I SW-CV-21CV 20 % G3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER FDIP C FSC Q DISCIIARGE SW{V-22CV 20 % F3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER PD1P D FSC Q DISC 11ARGE SW-CV-27CV 20 % C2 3 C la CK-D SA O FSO Q REC IIEAT EAC'I ANGER B SUPPLY

, SWCV-28CV 20 % C2 3 C 14 CK-D SA O FSO Q REC liEAT EXCIIANGER A SUPPLY l

SW-CV-35CV 2077 DI 3 C 10 CK-5 SA O FSO Q DGI SUPPLY I FSC O I 1

Reviskm 2 Sectxm V Page 71 of 155 l

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TEFFING PROGRA31 VALVE SU313tARY TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORN1 TEST TEST NOTES DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQ\tT FREQ SW-CV-36CV 2077 D2 3 C 10 CK-5 SA O FSO Q DGISUPPLY FSC Q SW CV-37CV 2077 D5 3 C 10 CK-S SA O FSO Q DG2 SUPPLY FSC Q SW-CV-3MCV ' 3177 D5 3 C 10 CK-5 SA O FSO Q DG2 SUPPLY FSC Q SW.CV-52CV 3)36 Gil 3 C 3 CK-S SA O FSC Q SW PROCESS RAD AtONTTOR PETURN SW<V-81CV 38% GII 3 C I NS SA O FSC Q RIVERWE11 SUPPLY TO SW PU%1PS SII 1 A AND C SW-CV-82CV JuW GIO 3 C I CK S SA O FSC Q RIVERWELL SUPPLY TO SW PU%tPS 511 1 A AND C SWCV-84CV 384 Gil 3 C I CK-5 SA O FSC Q RIVERWEll SUPPLY TO SW PUAIPS S!! I B AND D SW-CV-STV 3(6 GIO 3 C I CK-S SA O FSC Q RIVERWELL SUPPLY TO SW PU%1PS Sil 1 B AND D SW4f0V-36%1V Juva E10 3 B 24 BTF N10 0 FSC Q SW LOOP CRITICAL IIEADER Sil 1 PIT 2Y ISOLATION SW-MOV-37N1V 2006 E10 3 8 24 BTF NtO O FSC Q SW PUStPS CROSSTIE PTT 2Y l

SW-MOV41089A 2036 C7 3 B 18 GB MO C FSO Q RilR IIEAT EXCIIANGER A SW PIT 2Y 01TTLET, RV-13 Revism 2 Sectkm V Pare 72 of 155

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&lD P&ID 151 IST VALVE VALVE ACT NORN1 TEST TTST NOTES DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQ%fT FREO SW410V-31089B 2036 CIO 3 B 18 GB N10 C FSO Q RiiR IIEAT EXCilANGER B SW i PIT 2Y OtTLET. RV-13 SwatOV-650\tv 20 % D4 3 B 18 BTF S10 , O FSO Q REC llEAT EXCIIANGER A OUTLET j FSC Q

,j PIT 2Y SW410V-651N1V 20 % C4 3 8 1h BTF 'M

- - 0 FSO Q REC IIEAT EXCil ANGER B OUTilT.

FSC Q PIT 2Y SW410V-886%1V 20 % D2 3 B 4 GT %IO C FSO Q ENIERGENCY SLTPLY TO REC PTT 2Y NORT11 CRmCAL LOOP SW410V-887%1V 3)M D2 3 B 4 GT N10 C FSO Q ENTERGENCY SUPPLY TO REC PIT 2Y SOUTil CRmCAL LOOP i

SW410V-888%1V 20 % E4 3 B 4 GT %to C FSO Q E%tERGENCY RETURN FRONI REC PIT 2Y NORT11 CRACAL LOOP ,

SW-510V-889%IV 31 % C4 3 B 4 GT NIO C FSO Q ENTERGENCY RETURN FRO %1 REC PIT 2Y SOUT11 CRmCAL LOOP SWa!OV-2128N1V 3K6 G1 3 C I 1f2 GB S10 C FSO Q SW GLAND SEAL WAlliR BACKUP l Sil 4 PTT 2Y FRONI SW PU% FPS A AND C SW410V-212931V 2006 til 3 C 1 1f2 GB N10 C FSO Q SW GLAND SEAL WATER BACKUP l 511 4 PIT 2Y FRO \t SW Pt3f PS B ANT) D i

SW-RV-12RV 2iNM G8 3 C 3/4 RV SA C RVT 10Y SWBP I A SEAL WATER REUEF Sli 4 l

Revision 2 Sectam V Page 73 of 155 :

i

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SLSIAfARY TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&ID P&ID 151 IST VALVE VALVE ACT NOR%1 TEST TEST NOTES DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RO%1T FREQ SW-RV-13RV 21sM E8 3 C 3 '4 RV SA C RVT 10Y SWBP IC SEAL WATER REUEF Sli 4 SW-R V-14RV 2tre C8 3 C 3'4 RV SA C RVT 10Y SWEP IB SEAL WATER REULF S11 4 SW-RV-15RV 3m AM 3 C 34 RV SA C RVT iOY SWBP ID SEAL WATER REUEF Sif4 SW-V48) 35% F7 3 8 1 ba!. %1A O F5C Q SWBP C SEAL WATER RIVERWELL Sil 4 SiltrrotT SW-V N9 21 p, G7 3 B 1 BAL 4A O FSC Q SWEP A SEAL WATER RIVERWLU.

Sli 4 SliUTOFF SW-V-656 3MM B7 3 B 1 BAL %tA O F5C Q SWBP D SEAL WATER RIVERWELL Sil 4 SlitTTOFF SW-V-665 2t*M D7 3 B 1 BAL %1A O FSC Q SWBP B SEAL WATER RIVERWELL SII 4 SillTOFF SW-V-1422 AWM G8 3 C 3/4 GB NIA C FSO Q SWBP A GLAND WATER SCPPLY S 11 4 SW-V-1424 2(* 4 G8 3 C 3 74 GB StA C f50 Q SWEP A GLAND WATER f-LOW Sif 4 , CONTROL SW-V-1426 3X6 C8 2 C 3/4 GB N1A C FSO Q SV.T>P B GLAND WATER SLTPLY 581 4 ,

SW-V-1428 2(W4 CE 3 C 3/4 GB %' ' ,

- FSO Q SWBP B GLAND WATER FLOW Sif 4 _

COVTROL Revision 2 Sectsm V Page 74 of 155

i COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRA3I VALVE SU3 DIARY TABLES 4

SYSTDI: SERVICE WATER (SW)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NOR31 TEST TEST NOTES. DESCRIPTION i COOR CIASS CAT SIZE TYPE TYPE POS RQ\fT TREQ i l

SW-V-1430 2(s 6 E8 C GB 3 3 '4 31A C FSO Q SWBP C GLAND WATER StTPLY Sil 4 i SW-V-1432 2006 ES 3 C 34 GB NIA C FSO Q SWBP C GIAND WATER FLOW '

SII 4 CONTROL [

! i

SW-V 1434 386 B8 3 C 3'4 GB NfA C FSO Q SWBP D GLAND WATER SCPPLY '

1 511 4 [

, f

. SW-V-1436 35:n B8 3 C 3/4 GB NTA C FSO Q SWBP D GLAND WATER fl.OW !

j Sil 4 CONTROL

(

l i

i e

i t

Reviskm 2 Sectum V Pare 75 of 155 ,.

t

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGR OI VALVE

SUMMARY

TABLES SYSTEM: STANDBY GAS TREATMENT (SGT)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES DLSCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ\tT FREQ

, SGT-AOV-249AV 2037 C2 A B 12 BTF AO C FSO Q SGT UNIT A INLET

! FSC Q .

FST Q P!T 2Y SGT-AOV-250AV 2037 G2 A B 12 BTF AO C FSO Q SGT UNIT B INLET i FSC Q l FST Q '

PIT 2Y SGT- AOV-251 AV 2037 C6 A B 12 BTF AO C FSO Q SGT UNIT A DISCH ARGE MT Q PIT 2Y SGT-AOV-252AV 2037 G6 A B 12 BTF AO C FSO Q SGT UNIT B DISCIIARGE FST Q PIT 2Y SGT-AOV-255AV 2037 C6 A 51 10 BTF AO C PIT 2Y SGT UNIT A PASSIVE BYPASS SGT-AOV-256AY 2037 G6 A B 10 BTF AO C PIT 2Y SGT UNIT B PASSIVE BYPASS SGT-AOV-270AV 2037 Cl A B 10 BTF AO C FSO Q SGT UNIT A DILUTION AIR FST Q SIIUTOFF PIT 2Y SGT-AOV-271 AV 2037 Gl A B 10 BTF AO C FSO Q SGT UNIT B DILUTION AIR FST Q SIIUTOFF PIT 2Y Revishm 2 hxm V Page 76 of 155

COOPER NUCLEAR STATION TIIIR.D INTERVAL INSERVICE TESTING PROGRA31 VALVE SU313tARY TABLES SYSTEM: STANDHY GAS TREATMENT (SGT) a VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQ\fT FREQ SGT-AOV- 2037 C7 A B IG BTF no C FSO Q SGT UNTT A DISCll ARGE DPCV546A FST Q DIFFERENTI AL PRESSURE P!T 2Y CONTROL SGT-AOV- 2037 E' A B 10 BTF AO C FSO Q SGT UNIT B DISCH ARGE DPCV546B FST Q DIFFEREN11AL PRESSURE PIT 2Y CONTROL SGT-CV-14CV NG7 . C6 A C in CK-D 5A C PSO Q SGT UNTT A FAN EXH ALST.

FSO CS ACSJ 45 l FSC CS SGTEV-ITV 2037 G6 A C 13 CK-D 5A C PSO Q SGT UNIT B FAN EXH AUST.

FSO CS ACSJ45 FSC CS I

i 1

Rnism 2 Sectam V Page W of 155 i

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i COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES i f

SYSTEM: STANDBY LIQUID CONTROL (SLC) l V VE CIC P&ID

^ ^ ' NOTE 5 DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQitT FREQ SLC-CV-lOCV 2fuS E9 A C 1% CK L SA C FSO Q SLC PutP A DISCII ARGE CIIECK. !

Sil 2 FSC RF AROI45 SLCCV-1 ICV 2(45 F9 A C 1% CK-L SA C FSO Q SLC POIP B DISCIIARGE CIIECK.

Sil 2 FSC RF AROJ4)5 SLC CV-12CV 345 E8 I AC l'- CK. L SA C U -l RF SLC INJECTION UNE OUTBOARD SII 2 FSO RF CIIECK. ROJ-16. AROJ4M FSC RF SLC-CV-13CV 3M5 E7 i A~C 1% CK-L SA C U -1 RF SLC INJECTION UNE INBO ARD j Sil 2 FSO RF CIIECK. ROJ-16. AROJ Au

] FSC RF SLC- RV-10RV 3MS Dio A C 3/4 RV SA C R\T RF SLC POfP A DISCIIARGE RELILF 2 511 2 SLC-RV-11 RV 2(uS G9 A C 3'4 RV SA C RVT RF sir PatP B DISCIIARGE REUEF !

S11 2 i

i SLC-SQBV-14A 2045 ER A D Ib SilR Cil C EX 2Y SLC EXPLOSIVE VALVE A Sli 2 i SLC-SQBV-14B 3M5 EF A D 1% SIIR Cil C EX 2Y SLC EXPLOSIVE VALVE B Sil 2 i I f

l 1 Resnson 2 Sectiori V Page 75 of 155 I

COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRA31 VALVE SU3131ARY TABLES SYSTDI: STATION AIR (SA)

VALVE CIC PAfD P&ID ISI IST VALVE VALVE ACT NORSt TEST TEST NOTF5 DESCRIPTION COOR. CLASS CAT SIZE TYPE TYPE POS RQ\tT FREQ SA-V-647 2010 G4 2 A 1 GB SIA C U-I RF PASSIVE DRYWELL OUTBOARD SII 3 51'PPLY ISOLAT10N SA .'413 2010 G4 2 A 1 GB SIA C U-I RF PASSIVE DRYWELL INBO ARD SII 3 51TPLY ISOLAT10N Reviskm 2 Sectirm V Page M of 155

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1 COOL'liR NUCl.l!AR STATION I TillRD INTliRVAl.

INSliRVICl! TliSTING l'ROGRAh!

C Cold Shutdown Test Justifications CSJ No. DESCRIEDON CSJ-01 CS CV-18CV, CS CV-19CV, RilR CV 26CV, and RilR CV-27CV CSJ 02 lil'Cl CV 29CV and RCIC-CV 26CV Test I requency CSJ-03 lil'Cl-AOV l>CV50 Test lirequency CSJ 04 h1SIV Test lirequency CSJ-05 1*C-CV-33CV and l'C CV 34CV Test 1:requency j CSJ 06 RR h10V-h1053 A and RR h10V $311 Testing 1 requency CSJ-07 RilR-h10V h1017 and RilR h10V-h1018 Testing firequency CSJ 08 RilR-h10V-920h1V and RilR h10V-921h1V Testing 1 requency CSJ-09 SW-AOV-TCV451 A and SW AOV-TCV45lIl Testing Frequency CSJ 10 Nht CV CV2 and Nht CV CV4 Testing 1 requency CSJ l1 lil'Cl-CV-10CV and RCIC CV-10CV Testing 1 requency Revision 2 Section V l' age 80 of 15$

COOPliR NUCl.liAlt STATION TillitD INTL!RVAl.

INSliRVICl! Tl! STING PROGRAM Col.D SilOTDOWN TliST JUSTil lCATION CSJ-01 val.VliS: CS-CV 18CV. CS-CV-19CV, RilR-CV 26CV, and RilR-CV 27CV Cl. ASS: 1 CATl! GORY: A/C 1 UNCTION: These valves open for Core Spray or LPCI injection and close for primary containment isolation.

RiiQUIRl!D Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as previded by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS 1 OR Dlil liRRAl.: These valves are normally closed for primary containment isolation. They are also closed to isolate the related low pressure systems from the Reactor Recirculation system and the reactor vessel. Opening these valves during power operation is not possible due to the downstream side being exposed to reactor pressure.

Al.TliRNATl!

Tl!ST: These valves will be mechanically exercised, verifying open and closure capability, during cold shutdown periods, when the drywell is deinerted, in accordance with OMa Part 10, 4.3.2.2 and 4.3.2.4.

Revision 2 Section V Page 81 of 155

COOPliR NUCI.l!AR STATION TillRD INTL!RVAl, INSliRVICl! TliSTING l'ROGRAM COI.D SilUTDOWN Tl!ST JUSTIFICATION CSbO2 VAIN!!S: ilPCI-CV 29CV and RCIC-CV 26CV CLASS: 1 CATl! GORY: A/C ,

FUNCTION: IIPCI CV 29CV Opens to provide a flowpath from the llPCI pump to the reactor vessel via the feedwater system; closes for ptimary containment isolation.

RCIC-CV 26CV - Opens to provide a flowpath from the RCIC pump to the reactor vessel via the feedwater system; closes for primary containment isolation.

Rl!QUIRl!D Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4,3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR Dl!FliRRAl. These valves are normally closed to isolate the reactor coolant system and the llPCI and RCIC systems lixercising these check valves to the open position during normal plant operation would require llPCI or RCIC injection to the reactor vessel. This would result in a perturbation of normal feedwater flow and unnecessary thermal cycling of the feedwater nonles. It would also cause severe power Ductuations due to the relatively cold water from the limergency Condensate Storage Tanks. Furthermore, these valves are located in the Steam Tunnel.

During power operations, this area experiences temperatures of approximately 130

- 140"F, and whole body dose levels of approximately 3 Rem./IIR. In general, plant personnel are prohibited from entering this area during power operation due ,

to these conditions.

Al TliRNATli TliST: These valves will be mechanically exercised, verifying open and closure capability, durity cold shutdown periods in accordance with OMa Part 10, 4.3.2.2 and 4.3.2.4.

Revision 2 Section V Page 82 of 155

1 COOPlift NtJCI.l! Alt STATION l TillitD INTliRVAl, INSliRVICl! TliSTING PitOGRAM r

i Col.D SilllTDOWN Tl!ST JtJSTlFICATION CSJ-03 VAINii' ilPCI AOV PCY50 Cl. ASS: 2 CATl! GORY: 11 1 lJNCTION: Air operated, pressure legulating valve for the cooling water supply line to the llPCI lube oil cooler. The valve performs an active safety function in the open/ throttled position to allow cooling water flow to the lube oil cooler.

Rl!QlllRiiD 1) OMa Part 10, 4.2.1.1 requires Category A and il power operated valves to ,

Tl!ST: be individually full stroke exercised nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1,7.

2) OMa Past 10,4.2.1.6 requires valves with fall safe actuators to be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of paragraph 4.2.1.1.

This valve would normally be exempt from IST requirements as permitted by OMa Part 10,1.2(a)(2); however, the valve must be tested in accordance with the requirements of paragraph 4.2.1 because it performs a safety function in the fall-safe position.

IIASIS FOR This valve functions to control pressure in the cooling water supply line to the Rlil.ll!F- IIPCI turbine tube oil cooler. Cooling water is supplied from the llPCI booster pump discharge. The valve is normally maintained in the closed position as a result of the llPCI pump being idle and pressure maintenance, supplied by the auxiliary condensate system, maintaining the llPCI piping water solid.

The valve travels to a throttled position, when the llPCI pump starts, to automatically maintain pressure in the cooling water line at 50 psig. The valve's control circuitry prevents disk travel hom the full closed position to the full open ,

position. The valve is designed to fall to the open position on a loss of instrument -

air or electrical control power to ensure continuity of cooling water flow to the lube oil cooler, in the event the valve fails to the open position, the system design prevents over pressurization of the lube oil cooler by way of restricting orifices upstream and downstream of the valve in addition to a downstream relief valve.

Revision 2 Section V Page 83 of 155

COOPliR NtiCl.l!AR STATION TillRD INTL!RVAl.

INSliRVICl! Tl! STING PROGRAM i

Col.D SilllTDOWN TliST JUSTIFICATION CSJ 03 (Continued) j Stroke timing and f ail safe testing to the open position would require isolation of pressure maintenance and the imposition of a calibration signal to the pressure -

controller causing the valve to close. Upon completion of valve closure, the imposed signal would then be removed allowing valve travel to the open position at which point stroke timing can be performed. This process is impracticable during 7 power operation due to the necessity of placing the llPCI system in a condition which would compromise safe operation of the system upot utomatic actuation.

Additiotally, due to the intrusive method of imposing a calibration signal, the - ;

system would also be rendered incapable of initiation by operator action.

Al.TliRNATl!

TliST: This pressure control valve shall be stroke timed and fail safe tested during cold shutdowns by manipulating valve position with a calibration signal. A partial stroke mercise test will be performed quarterly.

I Revision 2 Section V Page 84 of 155

l COOPlift NUCl.l!All STA flON i TillitD INTliitVAl. !

INSliitVICl! Tl! STING PitOGilAh!

l COI.D SilUTDOWN Tl!ST JUSTil;1 CATION CSJ 04 VAINI!- hiS AOV A080A, hts. AOV. A080A, hts.AOV.A080ll, hts AOV A08611, hiS-AOV A080C, hts AOV A086C, h1S AOV.A080D. and hts.AOV.A086D Cl. ASS: 1 CATI!GoltY: A ,

I; UNCTION: The inboard and outboaid main steam isolation valves (htSIVs) must be capable of :

automatic closure to limit the release of radioactivity during a reactor transi:nt or accident condition.

Iti QUliti!D Tl!ST: 1) Ohta Pait 10, 4.2.1.1 requires Category A and 11 power operated valves to be individually full stroke exercised nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4 2,1,5 and 4.2,1,7.

2) Ohta Part 10,4.2.1.6 requires valves with fail safe actuators to be tested by observing the operation of the actuator upon loss of valve actuating power in J

accordance with the exe cising frequency of paragraph 4.2.1.1, ilASIS 1:Olt Diil;liititAl/ These valves are currently exercised in accordance with the surveillance requitements identified in the plant Technical Specification, Section 4.7.D.l.b.2 which states, "at least once per quarter, with the reactor power at less than 75% ,

trip main steam isolation valves individually and verify closure time " A l.icensing Change llequest (l. Cit) has been initiated to revise this Technical Specification surveillance requisement. The proposed revision will allow excreise testing to be performed in accordance with AShll!Section XI.

Quarterly full closure testing, as currently required, is a financial burden due to the cost of reducing reactor power levels to facilitate valve testing. Full closure testing of the htSIVs during 100% power operation is impracticable due to the potential for teactor transients and scrams. Also, full htSIV elosure could create the potential of lifting the main steam safety relief valves (SitVs) due to an increase in steam line pressure 1:ailure of an SitV to reclose could result in reactor vessel depressurization, llevision 2 Section Y Page 85 of 155

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COOPl!R NilCl.l!AR STATION TillRD INTliRVAl.

INSliRVICl! TliSTING PROGRAM i

COLD SillITDOWN TliST Jt1STil:lCATION CSJ-04 (Continued)

Al.Tl!RNATIVl!

Tl!ST: After the Technical Specification change is approved the MSIVs shall be partially 4

escressed approximately 10% closed, froni the full open position, at least once per quarter. Stroke timing to the closed position and fall safe testing shall be performed during cold shutdown periods in accordance with the requirements of OMa Part 10,4.2.1.2. (Intil then the MSIV's shall be stroke thned closed and fail !

safe ter,ted quarterly.

Revision 2 Section V Page 86 of 155 I

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COOPlill NtJCLliAlt STATION TillitD INTL!!(val, INS!!!(VICl! Tl! STING PROGRAM Col.D SiltlTDOWN Tl!ST Jt1STil lCATION CSJ 05 VAINii: l'C CV 33CV and PC CV 34CV CLASS: 2 CATliGoltY: A/C 1; UNCTION: These check valves perforni an active safety function in the closed position to provide containtnent iwlation and are located in the instrtunent air / nitrogen line at penetrations X 2911 and X 511;. The open function of these check valves is to provide actuating air to inboard recirculation Loop A sample line valve RR-AOV.

741 AV. Ilowever, this function is not safety related.

Rl!QtJilll!D Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 montht except as provided by paragraphs 4.3.2.2,4,3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I OR Dlil l!RRAl/ These check valves are not provided with position indication. Therefore, exercising these check valves to the closed position would require isolating the dowmtream piping and applying an outside pressure source while venting the upstream piping. This test method would allow establishing a differential pressure seross the valve seat to verify closure, l'erforming valve closure exercising during no.* mal plant operation is impracticable due to the necessity of installing scalhlding, temporary test equipment and a breach of system pressure boundary to f acilitate testing. This additional test activity during normal plant operation represents an unusual burden without a compensating increase in the level of quality and safety.

ALTl!RNATl!

TliST: The closure capability of these check valves will be verified during cold shutdown by demonstrating the ability to establish a differential pressure across the valve seat. The tests performed are pursuant to the requirements of OMa Part 10, 4.3.2.2.

Revision 2 Section V Page 87 of 155 1

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I COOPlill NUCl.liAlt STATION

'111111D INTL!!tVAl.

INSliitVICl! TliSTING PitOGitAh!

Col.D SilUTDOWN TliST JUSTil lCATION CSJ-06 VAIN!!S: Itit hiOV hiO53A and Itit h10V h105311 Cl. ASS: 1 CATl!GutY: 11 1 UNCTION: lleactor itecirculation Pump I A and til Discharge isolation ill!QUllt!!D TliST: Ohia Part 10, 4.2.1.1 requires Category A and 11 power operated valves to be individually full stroke exercised nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

IIASIS I:Olt Diil;liititAl.: Closure of either of the Itit pump discharge valves would reduce recirculation flow and result in reactor water temperature transients and reactivity transients. These transients would reduce control of power distribution and fuel usage, and increase the risk of other plant transients. This could lead to decreased fuel reliability and increase the possibility of a fuel element failure. In addition, failure of these valves during operation would require reactor shutdown due to inaccessibility.

A!!!'liitNATl!

TliST: Valve exercising to the closed position will be performed during cold shutdowns in accordance with Ohia l' art 10,4.2 i.2 Itevision 2 Section V Page 88 of 155 -

COOPl!R NUCl. liar STATION TillRD INTERVAL, INSl!RYlCli Tl! STING PROGRAM Col.D SilUTDOWN Tl!ST JUSTIFICATION CSJ-07 val,VliS: RilR MOV-Mol7 and RilR-MOV M018 ,

Cl. ASS: 1 CATliGORY: A FUNCTION: Reactor vessel return to the RilR pump suction and containment isolation during reactor operations. These valves are only opened for low pressure shutdown cooling.

RIIQUIRl!D

-Tl!ST: OMa Part 10, 4.2.1.1 requires Category A and il power operated valves to be individually full stroke exercised norninally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

HASIS FOR Dl!FliRRAl. Valves RilR MOV Mol7 and RilR-MOV-MOl8 are interhicked for pressure isolation during plant operation. Opening these valves during normal operation could possibly allow high pressure reactor coolant water into the low pressure suction lines of the RilR system. Therefore, it is essential that these valves remain closed during plant operations.

Al,Tl!RNATl!

TliST: Valve exercising to the closed poition will be performed during cold shutdowns in accordance with OMa Part 10, 4.2.1.2.

Revision 2 Section V Page 89 of 155

COOPlift NUCl.l! Alt STNI'lON TillitD INTL!!< val, INSliitVICl! Tl! STING l'ItOGilAh!

Col.D SilUTDOWN Tl!ST JUSTil lCATION CSJ 08 VAI,VliS: Illilt h10V 920h1V and Itllit-h10V-921h1V i l

Cl. ASS: 2, A (downstream) CATl! golly: 11 l 1: UNCTION: l'rovide isolation of main steam to the Augmented Of f Gas (AOG) system.

111!QU1111!!)

TliST: Ohta Part 10, 4.2.1.1 requires Category A and 11 power operated valves to be individually full stroke exercised nominally every 3 months, except as provided by paras. 4.2.1.2. 4.2.1.5, and 4.2.1.7.

IIASIS I;Olt Dlil lillitAl.: The steam supply cannot be isolated during normal plant operation without causing significant Augmented Of f Gas (AOG) system transients. Transients could include a fast or uncontrolled burn of hydrogen gas in the AOG piping buried underground and leading outside the plant. Also, routine quarterly testing of either of these valves could cause a release of radioactive material several orders of magnitude above normal release activities.

Al!!'liitNATl!

Tl!ST: Valve exercising to the closed position will be performed during cold shutdowns in accordance with Ohta Part 10, 4.2.1,2.

Revision 2 Section V Page 90 of 155

COOPlilt NUCl.I!All STATION TillitD INTliltVAl.

INSl!!(VICl! Tl! STING PitOGitAM .

Col.D SiltrIDOWN Tl!ST Jt1STilICATION CSJ 09 val.VliS: SW-AOV-TCV451 A and SW AOV+TCV45111 Cl. ASS: 3 CATl!GoltY: 11 1 UNCTION: Open to provide a llow path for cooling water to the IlliC heat exchangers, itI!Qllliti!D Tl!ST: OMa Part 10, 4.2.1.1 requires Category A and 11 power operated valves to be individually full stroke exercised nominally every 3 months, except as provided by paras. 4.2.1.2, 4.2.1.5, and 4.2.1.7. ;

OMa Part 10,4.2.1.6 tequires valves with fail safe actuators to be individually tested nominally every three months, except as provided by paras 4.2.1.2, 4.2.1.5, and 4.2.1.7.

IIASIS 1 0 11 Dlil liltitAl.: One temperature control valve is normally open to control flow to the associated IlliC heat exchanger. During the hot sununer months both heat exchangers are in service. Placing either valve in the closed position for an exercise test during this period would interupt the flow to the associated heat exchanger. The IllIC heat .

exchangers provide cooling water for a variety of essental and non-essential components. Therefore, it is essential that both of these valves remain open during plant operations. During cold shutdowns, when the heat load is reduced, one IlliC heat exchanger can be removed from service, The associated temperature control valve can then be closed and exercised to the full open position.

Al.TliitNATli TILT: Valve exercising to the open position will be performed quarterly except when both heat exchangers are in service When both heat exchangers are in service valve exercising to the open position will be performed during cold shutdowns in accordance with OMa Part 10, 4.2.1.2.

Itevision 2 Section V Page 91 of 155

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' COOPlift NUCl.l!All STATION TillitD INTliitVAl.

INSl!!<VICl! TilSTING PROGitAhi Col.D SilUTDOWN TliST JUSTIFICATION CSJ 10 VAINiiS: Nhi-CV-CV2 and Nhi-CV CV4 Cl ASS: 2 CATliGORO A/C FUNCTION: These valves close for primary containmt..t isolation.

Ill!QUIRiiD Tl!ST: Ohia Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4,3.2.3,4.3.2.4, and 5.2.5.

II A SIS F O lt DlifliRRAI.* These valves are normally closed for primary containment isolation. They are open intermitantly during power operation to support operation of the TIP system, which is not a safety function. These check valves are not provided with position indication. Therefore, exercising these check valves to the closed position would require isolating the downstream piping and applying an outside pressure source while venting the upstream piping. This test method would allow establishing a differential pressure across the valve seat to verify closure. Performing valve closure exercising during normal plant operation is impracticable due to the necessity of installing temporary test equipment and a breach of system pressure boundaiy to facilitate testing. This additional test activity during normal plant operation represents an unusual burden without a compensating increase in the level of quality and safety.

A!!!'l!RNATl!

Tl!ST: The closure capability of these check valves will be verified during cold shutdown by demonstrating the ability to establish a differential pressure across the valve seat. The tests performed are pursuant to the requirements of Ohta Part 10, 4,3.2.2.

Itevision 2 Section V Page 92 of 155

COOPlift NtJCI.l! Alt STATION TillRD INTL!!(val, '

INSliltVICl! TliSTING PROGRAM l

Col.D SiltJTDOWN TliST JtJSTil!! CATION CSJ ll VAINiiS: IIPCI-CV-10CV and RCIC CV-10CV ;

I Cl. ASS: 2 Call! GORY: C l Ft1NCTION: These valves close to prevent reverse flow when the suction supply is changed froin the !! CST's to the suppression pool.

Rl!QtilRl!D TliST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4,3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR Dl!FliRitAl; These valves are normally closed. When the llPCI or RCIC pumps are running, these valves open to provide suction supply from the !! CST's to the respective pumps. When the !! CST's scach the low level setpoint, the suppression pool suction supply valves open and the notor operated !! CST suction valves close, in the event of a failure of the motor operated valve, the associated check valve must close to prevent bypass leakage. These chect valves are not provided with position indication. The clore, exercising these check valves to the closed position would require isolating the !! CST's and checking for a differential pressure across the valve seats to verify closure. Performing valve closure exercising during normal plant operation is impracticable due to isolating the primary source of water for ilPCI and RCIC. This additional test activity during normal plant operation represents an unusual burden without a compensating increase in the level of quality and safety.

Al,TliRNATl!

TliST: The closure capability of these check valves will be verified during cold shutdown by demonstrating the ability to establish a dif ferential pressure across the valve seat. The tests performed are pursuant to the requirements of OMa Part 10, 4.3.2.2.

Revision 2 Section V Page 93 of 155

I COOL'liR NUCl.!!AR STATION TillRD INTliRVAI, IN.V.RVICl! TliSTING PROGRAM D. Relueling Outage Justifications ROl&1 Dexdption ROJ-01 CRD CV-13CV, CRD-CV-14CV, CRD CV-15CV, and CRD CV 16CV lixercise Testing Frequency ROJ-02 IIPCI.CV-llCV Testing Frequency ROJ-03 IIPCI-CV 15CV, IIPCI-CV 16CV, and llPCI-CV-17CV Testing to the Closed Position ROJ04 IIPCI V 44 and ilPCI-V-50 Testing to the Closed Position ROJ05 I A CV-65CV and IA-CV-78CV Closure Test Frequency ,

ROJ06 Nill CV-4911CV, Nill CV-50llCV Nill CV-5111CV. Nill-CV 52ilCV, Nill SOV SSV738, and Nill SOV SSV739 !!xercise Test Frequency <

ROJ07 Nill CV-55CV and Nill CV 56CV lixercise Test Frequency ROJ-08 PC-CV 21CV, PC-CV-22CV. PC-CV-23CV. PC CV-25CV, PC-CV-26CV, and PC CV-27CV Closure Test Frequency ROJ 09 RCIC CV-11CV Testing Relief ROJ10 RCIC-CV 12CV, RCIC-CV-13CV, and RCIC-CV 15CV Testing to the Closed Position ROJ il RCIC-V 37 and RCIC-V-42 Testing to the Closed Position ROJ 12 Ri!C-CV 16CV Closure Test Frequency ROJ-13 RF CV 13CV, RF CV-14CV, RF-CV 15CV, and RF-CV-16CV Reverse Flow Test ROJ14 RlLCV-14CV and RF-CV-16CV Open Test Frequency j ROJ-15 RWCU-CV-15CV Test Frequency Revision 2 Section V Page 94 of 155 I

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COOPliR NUCLIIAR STATION TillRD INTliRVAl.

INS!!RVICl! T11 STING PROGRAM ROJ16 SLC CV 12CV and St.C-CV 13CV Testing Frequency ROJ 17 . -

RCIC CV 20CV and RCIC CV 21CV Testing Frequency ROJ18 RilR CV-10CV, RilR CV llCV, RilR CV 12CV, and RilR CV-13CV Testing Frequency 4

ROJ-19 I$C CV 13CV and PC CV 14CV Testing Frequency ROJ 20 IIPCI CV 17CV Testing Frequency

' Revision 2 Section V- Page 95 of 155

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COOPliR NtJCI. liar STATION TillRD INTIIRVAl, INSliRVICli TIISTING PROGRAM Ri!FUlit. LNG OUTAGli JUSTIFICA*lON ROJ-01 VAINil: CRD-CV-13CV, CRD-CV-14CV, CRD-CV-15CV, and CRD-CV-16CV Cl.'u N 1 CATliGORY: A/C FUNCTION: Centainment isolation valves for Control Rod Drive (CRD) seal water injection for the Reacto! Ikcirculation (RR) pumps RI!QUIRiiD TliST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

DASIS l'OR DliFl!RRAl.: !!xercising these valves to the closed position during normal plant operation would require stopping or reversal of seal water flow which would impose a severe thermal transient on the reactor recirculation pump seals resulting in premature seal failure. Drywell entry during cold shutdown would be necessary to facilitate testing, thereby requiring deinerting which could potentially delay restart. Valve exercising during cold shutdown when the drywell is Jcinerted, could also delay plant restart due to the necessh,, of using portable test equipment inside the drywell. The additional test activity during cold shutdown represents an unusual burden without a compensating increase in the level of quality and safety.

AllfliRNATli TilST: The closure capability of these valves will be verified during refueling outages by performing a Type C local leak rate test per the requirements of OMa Part 10, 4.3,2.4 and the CNS Appendix J Program.

l Revision 2 1 Section V Page 96 of 155 i

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- COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM REFUEL.ING OUTAGE JUSTIFICATION ROJ-02 VAINE- IIPCI-CV-llCV CLASS: 2 CATEGORY: C FUNCTION: Normally closed ilPCI pump suction line check valve from the s em: nion pool, ilEQUIRiiD TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3 2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

HASIS FOR DEFERRAL: The llPCI pump normally takes suction from the Emergency Condensate Storage Tanks (ECST). When the ECSTs reach low level the pump suction is au;omatically realigned to the supprnion pool and ilPCI-CV-1 ICV opens. The valve is not equipped with position 'r.dication or a remote manual operator for exercising. The only method for exercising the valve during operation is to test it with flow. During performance testing the llPCI pump discharges to the ECSTs.

Testing this valve with flow would result in a reduction of suppression pool inventory and the mixing of relatively impure water in the suppression pool with the ECST water.

ALTERNATE TEST: The valve will be partially disassembled and manually exercised to the full open and closed positions during each refueling outage in accordance wim the requirements of OMa Part 10, 4.3.2.4.

Revision 2 Section V Page 97 of 155

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-i COOPER NUCLliAR STATION TillRD INTERVAL ;

INSliRVICli TliSTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ 03 E VALVE: i lil CI-CV 15CV, llPCI-CV-16CV and ilPCI CV-17CV - l

- CLASS: 2 CATEGORY: A/C and C -

i

' FUNCTION: IIPCI CV-15CV - Opens to provide an exhaust path for the llPCI Turbine; closes for primary containment isolation.

IIPCI-CV-16CV - Water scaled containment isolation valve.

ilPCI-CV 17CV - Opens to provide a flowpath for llPCI pump minimum flow

closes to prevent diversion of RilR suppression pool cooling.

4 REQUIRED E Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4,3.2,2,4.3,2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR -

DliFERRAla These valves are simple check valves, and thos, have no mechanism by which valve closure can be verified; Thus, the only practicable method of testing in the closed position is to impose a reverse differential pressure on the valve seat to verify closure capability or to measure the seat leakage.

t Performing such a test renders the llPCI system inoperable, thus it is impracticable 4

to perform during plant operation. Performing such a test at cold shutdowns could increase and complicate the outage work scope considerably and prove to be an undue burden on the plant staff without a compensating increase in the level of 4 quality and safety.

ALTERNATl!

TEST

The closure capability of these valves will be verified each refueling outage during the performance of leak rate testing (15CV) per the CNS Appendix J Program 'or by demonstrating the ability to maintain a differential pressure across the valve seat

. (16CV and.17CV),

Revision 2 .Section V Page 98 of 155 l

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l COOPliR NUCLliAR STATION TillRD INTERVAL.

INSliRVICE TESTING PROGRAM RiiFUlil ING OUTAGli JUSTIFICATION ROJ-04 VAINE: IIPCI V-44 and IIPti-V-50 CLASS: 2 CATliGORY: A/C FUNCTION: IIPCI V-44 is a containment isolation globe stop check from the IIPCI turbine exhaust to the suppression pool, ilPCI V-50 is a water scaled containment isolation globe stop check valve from the llPCI turbine drain to the suppression pool.

These valves are normally closed and the manual operators are locked in the open position to allow free disk movement. They open during IIPCI pump operation and are required to close for containment isolation.

REQUIRiiD TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR DliFl!RRAL: The operators on these valves are manual operators. Exercising these valves closed during plant operation or cold shutdown could result in undetected valve failure.

Since the valve disk is not connected to the valve stem, the disk cannot be moved to the open position by stem manipulation. The disk can, however, be forced shut by the manual operator. If the disk should stick shut, the failure would go undetected until the turbine was operated. This would result in llPCI being unavailable to perform its safety function. llaving IIPCI unavailable, should an accident occur, could lead to reactor damage and potential release of rrdioactive material.

Al.TliRNATli TliST: The closure capability of these valves will be verified each refueling outage during the performance of leak rate testing (V-44) per the CNS Appendix J Program or by -

demomtrating the ability to maintain a differential pressure across the valve seat (V-50).

Revision 2 Section V Page 99 of 155 n ~

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAh!

REFUELING OUTAGE JUSTIFICATION ROJ-05 VALVES: l A-CV-65CV and 1A-CV 78CV CLASS: 2 CATEGORY: A/C FUNCTION: These check valves have an active safety function in the closed position to provide containment isolation on the instrument air /mtrogen line which is the pneumatic supply to the htSIVs and SRVs located inside primary containment.

REQUIRED TEST: Ohia Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR DEFERRAL' These check valves are not provided with position indication. Therefore, exercising these check valves to the closed position would require isolating the downstream piping and applying an outside pressure source while venting the upstream piping. This test method would allow establishing a differential pressure across the valve seat to verify closure. This is not practicable during normal plant operation or cold shutdowns due to the location of the manual valve provided for downstream isolation, which is located inside the drywell. Entry into the drywell during power operation is not possible due to an inerted atmosphere and high levels of radiation. Valve exercising during cold shutdown, when the drywell is de-inerted, could potentially delay plant restart due to the installation of temporary test equipment.

ALTERNATE TEST: The closure capability of these valves will be verified during refueling outages by performing a Type C, hx;al leak rate test per the requirements of Ohta l' art 10, 4.3.2.4 and the CNS Appendix J Program.

Revision 2 Section V Page 100 of 155

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM REFUEL.ING OUTAGli JUSTIFICATION ROJ-06 val VE: Nill-CV-4911CV, NHI-CV-50HCV, NH1-CV-SlHCV, NHI-CV-52HCV, NHI-SOV SSV738, and NHI SOV-SSV739 CLASS: 3 CATEGORY: C and B FUNCTION: The reference leg injection check valves and solenoid operated valves have an active safety function in the open position to inject Core Spray water to the reactor vessel level instrumentation lines in case the reference leg water has flashed or boiled off due to accident conditions in the drywell.

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

OMa Part 10,4.2.1 requires Category A and H power operated valves to be individually full stroke exercised and stroked timed nominally every 3 months, except as provided by paragraphs 4.2.1.2,4.2.1.5, and 4.2.1.7.

OMa Part 10,4.2.1.6 requires valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercismg frequency of paragraph 4.2.1.1.

HASIS FOR DEFERRAL.: This system provides the capability for the Core Spray System to supply a backfill of water for maintaining inventory of the Nuclear Boiler Instrumentation System cold reference legs (condensing chambers 3A and 3H) during accident conditions in the drywell where the reference leg inventory could be compromised. Exercising these valves to the open position, full or partial, would require manually isolating 1 and venting the Cold Reference Ixg Backfill System. This is not practicable during power operation or cold shutdown, other than refueling, due to the possible introduction of air into the system. This could cause a spurious reactor vessel level indication which could cause a reactor trip during power operation. During cold shutdown spurious level indications could interrupt the operation of systems required for decay heat removal, thereby placing the reactor in an unsafe corvlition. During refueling outages, sufficient time exists for decay heat to be reduced to Revision 2 Section V Page 101 of 155 r# 4

1 COOPER NUCLEAR STATION TillRD INTERVAL INSliRVICE TESTING PROGRAM i REFUELING OUTAGli JUSTIFICATION ROJ-06 (Continued) a level which minimizes the impact of momentary interruption in the operation of systems required for decay heat removal such that testing can be performed.

ALTERNATE TEST: Exercising these check valves to the full open position, and full exercising with stroke timing to the open position of the solenoid operated valves, shall be performed during refueling outages.

Revision 2 Section V Page 102 of 155

COOPliR NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ 07 VALVE (s): Nill-CV-55CV and Nill-CV-56CV CLASS: 3 CATl! GORY: C FUNCTION: These Cold Reference leg Continuous llackfill System check valves have an active safety function in the closed position to isolate the Class 3 instrumentation piping from the Seismic ilS non-class CRD piping.

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5.

IIASIS FOR DEFERRAL This system provides for a continuous now of water from the CRD drive water pumps to prevent noncondensible gases from building up in the Nuclear Boiler Instrumentation System cold reference legs (condensing chambers 3A and 3B).

Exerci.ung these valves to the closed position would require manually isolating and venting of the Cold Reference leg Continuous Backfill System upstream of the check valves. This is not practicable during power operation or cold shutdown, other than refueling, due to the possibility of causing a spurious reactor vessel level indication from entrained air in the system. F.dse level indications resulting from entrained air in the system may either cause a reactor trip during power operation or interrupt the operation of systems required during cold shutdown for decay heat removal, thereby placing the reactor in an unsafe condition. During refueling outages, sufficient time exists for decay heat to be reduced to a level which minimizes the impact of momentary interruption in the operation of systems required for decay heat removal such that testing can be performed.

Al, TERNATE TEST: Exercising these check valves to the closed position shall be performed during refueling outages. Exercise testing shall be accomplished by performing a seat leakage test.

. Rev'ision 2 Section V Page 103 of 155

' COOPER NUCl EAR STATION LTillRD INTERVAL .

1 INSERVICE TESTING PROGRAM

.. REFUELING OUTAGE JUSTIFICATION ROJ-08 r

VALVE: .PC-CV-21CV, PC-CV-22CV, PC-CV-23CV, PC-CV-25CV, PC CV-26CV, and F PC-CV-27CV CLASS: 2 CATEGORY: A/C FUNCTION: The drywell 11/0 2 monitors 2 nitrogen purge supply check valves perform an active safety function in the closed position to maintain primary containment integrity.

These valves function in the open position only to supply nitrogen or oxygen to the 4

Il 2/Oimonitors for calibration and functional testing which is not a safety function.

- REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 momhs, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.-

F llASIS FOR i- DEFERRAL: Exercising these check valves to the closed position would require isolating the 11/0 2 2monitors from the drywell and suppression chamber atmosphere and applying an outside pressure source downstream of the check valves while venting f

the upstream piping. Performing this test activity during normal plant operation or cold shutdowns would require the removal of the 11:/O: Monitoring System from service during conditions when primary containment integrity is required. Plant Technical Specifications Tables 3.2.F and 3.2.11 identifies the 11/O: 2 monitors as surveillance instrumentation required for the assessment of the containment

. atmosphere by monitoring the hydrogen and oxygen concentrations. Testing these

, valves during conditions when 11/02 operability is required would result in a reduction in safety and would not provide a significant increase in assurance of continued operability.

, ALTERNATE 4 TEST: - The closure capability of these check valves will be verified by local leak rate testing them as a group at least once each refueling outage or whenever the system

, is opened. . If the system is opened, the 11/O: 2 monitoring system shall be local leak

, rate tested prior to resump't ion of service.

t +

i Revision 2 Section V Page 104 of 155

COOPER NUCl. EAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM REFUEL.ING OUTAGli JUSTIFICATION ROJ-09 val.VE RCIC-CV llCV CLASS: 2 CATEGORY: C 1: UNCTION: Normally closed RCIC pump suction line check valve from the suppression pool.

Rl! QUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exeicised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

BASIS FOR DEFERRAL: The RCIC pump normally takes suction from the Emergency Condensate Storage Tanks (ECST). When the ECSTs reach low level the pump suction is ,

automatically realigned tojhe suppression pool and RCIC-CV-1 ICV opens. The valve is not equipped with positien indication or remote manual operators for exercising. The only method for exercising the valve during operation is to test it with dow. During performance testing the RCIC pump discharges to the ECSTs.

Testing this valve with flow would result in a reduction of suppression pool inventory and the mixing of relatively impure water in the suppression pool with the ECST water.

ALTERNATE TEST: The valve will be partially disassembled and manually exercised to the full open and closed positions during each refueling outage in accordance with the requirements of OMa Part 10, 4.3.2.4.

- Revision 2 Sectien V Page 105 of 155

COOPliR NUCLl!AR STATION TillRD INTliRVAL INSliRVICli TliSTING PROGRAM Rl!FUllLING OUTAGli JUSTIFICATION ROJ 10 val,VliS: RCIC-CV-12CV, RCIC-CV-13CV, and RCIC-CV-15CV Cl. ASS: 2 CATl! GORY: C and A/C FUNCTION: RCIC-CV-12CV water scaled valve: closes for containment isolation.

RCIC-CV-13CV - Opens to provide a flowpath for RCIC pump minimum flow; closes to prevent diversion of RilR suppression pool cooling flow.

RCIC-CV-15CV - Opens to provide an exhaust path for the RCIC turbine; closes for primary containment isolation.

Rl!QUIRiiD TilST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR DliFl!RRAl.: These valves are simple check valves, and thus, have no mechanism by which valve closure can be verified, The only practicable method of testing in the closed position is to impose a reverse differential pressure on the valve seat to verify closure capability or to measure the seat leakage.

Performing such a test renders the RCIC system inoperable. It is impracticable to perform this test during plant operation. Performing such a test at cold shutdowns could increase and complicate the outage work scope considerably and prove to be an undue burden on the plant staf f without a compensating increase in the level of quality and safety.

ALTliRNATli TliST: The closure capability of these valves will be verified each refueling outage during the performance of leak rate testing (15CV) per the CNS Appendix J Program, or by demonstrating the ability to maintain a differential pressure across the valve seat (12CV and 13CV).

Revision 2 Section V Page 106 of 155

COOPER NUCl EAR STATION TillRD INTL?RVAl.

INSERVICE TESTING PROGRAM RiiFUlil.ING OUTAGli JUSTIFICATION ROJ l1 VAIN!!: RCIC-V 37 and RCIC-V-42 Cl. ASS: 2 CATl! GORY: C FUNCTION: RCIC-V-37 is a containment isolation globe stop check from the RCIC turbine exhaust to the suppression pool.

RCIC-V-42 is a water sealed containment isolation globe stop check valve from the RCIC vacuum pump to the suppression pool.

These valves are normally closed and the manual operators are locked in the open position to allow free disk movement. They open during RCIC pump operation and are reouired to close for containment isolation.

REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised TEST: nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3, 4.3.2.4, and 4.3.2.5.

HASIS FOR DEFliRRAl. The operators on these valves are manual operators. Exercising these valves closed during plant operation or cold shutdown could result in undetected valve failure.

Since the valve disk is not connected to the valve stem, the disk cannot be moved to the open position by stem manipulation. The disk can, however, be forced shut by the manual operator. If the disk should stick shut the failure would go undetected until the turbine was operated. For RCIC-V-37 this would result in RCIC being unavailable to perform its design function. Although RCIC does not have a safety function, it does provide cooling water when feedwater is unavailable. Failure of RCIC-V-42 to open would not prevent the RCIC system from operating, but would prevent the removal of noncondensible gases from the barometric condenser.

Al.TERNATli TEST: The closure capability of these valves will be verified each refueling outage during

'the performance of leak rate testing (V-37) per the CNS Appendix J Program or by demonstrating the ability to maintain a differential pressure across the valve seat (V-42).

Revision 2 Section V Page 107 of 155

l 4

, COOPER NUCLEAR STATION

, TillRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ 12 e ,

VALVii- R EC-CV-16CV CLASS: 3 CATEGORY: C l FUNCTION: This valve closes to prevent back flow into the non-critical Reactor Equipment

Cooling (REC) return header from the suction of the REC pumps.

l REQUIRED TEST: OMa Part 10,4,3.2.1 requires check valves to be individually exercised nomittally ;

4 every 3 months, except as provided isy paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

HASIS FOR DEFERRAL: Testing this valve in the closed direction requires depressurization of the non- ,

critical REC return header. This, in turn, would interrupt cooling to important equipment,-including the CRD pumps, RWCU pumps and heat exchangers, drywell ventilation coolers, reactor recirculation pumps, and the recirculation pump motor generator sets, This could not be donc during normal operation without subjecting major equipment to damage from overheating. Exercising this 1 check valve during cold shutdown would require the interruption of equipment operation which is normally maintained in service, e.g. RWCU, which is required to maintain water chemistry. Otherwise, testing during cold shutdown when component operability is not necessary would still require depressurization of the non critical header which could delay plant restart and represents an unusual burden without a compensating increase in the level of quality and safety.

ALTERNATE TEST: The closure capability of this valve will be verified at least once each reactor refueling outage.

-Revision 2. Section V Page 108 of 155

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COOPER NUCLEAR STATION TillRD INTERVAL

-INSERVICE TESTING PROGRAh!

REFUELING OUTAGE JUSTIFICATION ROJ 13 -

val,VE: RF CV-13CV, RF-CV-14CV, RF-CV-15CV, and RF-CV 16CV 6_

CLASS: 1 CATl! GORY: : A/C liU4CT10N: hiain Feedwater check valves open to allow normal feedwater flow.' Additionally, -

14CV and 16CV open to allow IIPCI and RCIC flow, respectively. These valves ,

! must be capable of closure to provide containment isolation Additionally,13CV ,

l and 15CV must be capable of closure to prevent diversion of IIPCI and RCIC i-flow, respectively.

REQUIRED TEST: Ohta Part 10, 4.3.2.1 requires check valves to be individually exercised nominally -

every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and j '4.3.2.5.

HASIS FOR j DEFERRAL: These valves are normally open and must remain open during reactor operations to ensure adequate feedwater flow. Feedwater provides normal reactor core cooling during operation. Exercising these valves during piant operation could cause a .

< transient in reactor water level resulting a reactor scram. T!.e observation of specified leakage during local leak-rate testing provides the only means for verification to the closed position.

ALTERNATE TEST: These valves will be exercised to the closed position during the Type C leak rate test performed each refueling outage in accordance with the requirements of Ohta l Part 10,4.3.2.2 and the CNS Appendix J Program.

l Revision 2 .Section V Page 109 of 155

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COOPER NUCLEAR STATION TillRD INTERVAL.

INS!!RVICE TESTING PROGRAM REFUEL.ING OUTAGE JUSTIFICATION ROJ-14 VAINE- RF-CV-14CV and RF-CV-16CV Cl. ASS: 1 CATl! GORY: 'A/C FUNC'llON: Open to provide a nowpath for ilPCI (RF-CV-14CV) or RCIC (RF CV-16CV) to the reactor vessel.

REQUIRED TEST: OMa Pan 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR DliFliRRAl.: The feedwater injection check valves are normally open during plant operation due to feedwater flow. Ilowever, individual now rate cannot be measured during normal operation due to system confieuration. These valves are located inside the drywell and are not accessible during normal operation or during cold shutdowns unless the drywell is de inerted.

ALTERNATl!

TEST: Although these valves are verified open by the normal operation of the feedwater system, these valves will be verified to open to pass the required HPCI and RCIC nows during refueling outages by either a now test or by valve disassembly and inspection.

Revision 2 Section V Page i10 of 155 1

l

COOPER NUCLEAR STATION TillRD INTL!RVAL INSERVICE TESTING PROGRAM REFUl! LING OUTAGE JUSTIFICATION ROJ 15 VAINES: RWCU-CV-15CV CLASS: 1 CATEGORY: A/C FUNCTION: Normally open Reactor Water Cleanup (RWCU) return line check valve and containment isolation valve.

REQUIRED Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IlASIS FOR DEFERRAL: This valve cannot be verified as being closed upon reversal or stopping of flow without opening and venting the line upstream of the check valve. Opening or venting the RWCU line during operations could cause a leak of high pressure reactor coolant and potentially lead to the release of radioactive material.

Stopping RWCU How during normal operations or cold shutdown for an extended period would lead to a degradation of reactor water purity. This would add to the radioactive contamination in the reactor coolant system and could lead to additional exposure of site personnel, it is essential that RWCU remain in operation as much as possible and RWCU-CV-15CV be exercised to the closed position only during refueling outages.

ALTERNATE TEST: The closure capability of RWCU-CV-15CV will be verified during refueling outages by performing a Type C hwal leak rate test per the requirements of OMa Part 10, 4.3.2.4 and the CNS Appendix J Program.

Revision 2 Section V Page 111 of 155

COOPER NUCl. liar STATION TillRD INTIIRVAL INSERVICI! TliSTING PROGRAM REFUlil.ING OUTAGli JUSTIFICATION ROJ-16 VAINE: SI.C-CV 12CV and St.C-CV-13CV

~

CLASS: 1 CATEGORY: A/C I; UNCTION: Inboard and outboard containment isolation valves which must open to allow injection of sodium pentaborate (neutron poison) for reactivity control. The injection of the neutron poison is not a safety function, but may be required in emergency situations. These valves must be capable of closure to provide containment isolation, RI!QUIRl!D TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

HASIS FOR DEFliRRAl. These valves are normally closed with reactar pressure on the downstream side.

Exercising these valves to the closed position during power operation would require drywell entry for the inboard valve and breach of reactor coolant pressure boundary when testing either valve. This is not practicable due to inaccessibility created by the inerted environment and the potential for a release of radioactivity as a result compromising the two-valve RCS isolation barrier, Valve exercising during cold shutdown, when the drywell is deinerted, could delay plant restart due to the necessity of using portable test equipment inside the drywell. The additional test activity during cold shutdown represents an unusual burden without a compensating increase in the level of quality and safety.

AllrERNATl!

TEST:- The closure capability of the St.C check valves will be verified during refueling outages by performing a Type C, local leak rate test per the requirements of OMa Part 10, 4.3.2.4 and the CNS Appendix J Program.

l l

Revision 2 Section V Page 112 of 155

COOPliR NUCl. liar STATION TillRD INTERVAL INSERVICE TliSTING PROGRAM REl UELING OUTAGE JUSTIFICATION ROJ 17 VALVE: RCIC-CV-20CV and RCIC-CV-21CV CLASS: A2 CATEGORY: C FUNCTION: Reactor Core Isolation Cooling (RCIC) condensate pump discharge check valves.

These valves open to provide a flow path for the RCIC condensat: pump discharge, and RCIC-CV 21CV closes to prevent diversion of RCIC pump suction flow.

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and

. 4.3.2.5.

IlASIS FOR DEFERRAL: These valves are normally closed check valves (in series). They open to provide a flow path for the RCIC condensate pump discharge. There is no practical means to verity sufficient flow to full-stroke exercise these valves open. System configuration and absence of appropriate instrumentation prohibits full stroke open verification.

Should the RCIC condensate pump fail to start, RCIC-CV-21CV closes to prevent diversion of RCIC pump suction flow. The current system design does not allow testing to ensure the valve has closed.

ALTERNATli TEST: The valves will be disassembled, inspected, and manually exercised during refueling outages, in addition, a partial stoke exercise test to the open position will be performed quarterly and after each disassembly and inspection.

Revision 2 Section V Page 113 of 155

COOPliR NUCl.IIAR STATION TillRD INTL!RVAL INSliRV'Cl! TESTING PROGRAM Ri!FUlil.ING OUTAGli JUSTIFICATION ROJ 18 VALVI!* RilR-CV-10CV, RilR-CV-11CV, RilR-CV-12CV, and RilR-CV-13CV CLASS: 2 CATliGOltY: C FUNCTION: Open to provide a flow path for RilR pump minimum llow.

RiiQUIRiiD TilST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally

. every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS FOR DliFliRRAl.: There is no practical means of verifying sufficient now to full-stroke exercise the valves open. System configuration and absence of appropriate instrumentation prohibits full stroke open verification.

ALTliRNATli TliST: A dilferent valve will be disassembled, inspected and manually exercised during each refueling outage until the entire group has been tested, if the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group will also be disassembled, inspected and manually exercised during the same outage, in addition, a partial stroke exercise test, with flow, will be performed quarterly, and after each disassembly / inspection.

Revision 2 Section V Page 114 of 155

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COOPliR NUCl.l!AR STA flON TillRD INTL!RVAl.

INSliRVICli TESTING PROGRAM Rl!FUlil.ING OUTAGE JUSTIFICATION ROJ-19 VAINii: PC-CV-13CV and PC-CV-14CV Cl. ASS: 2 CATliGORY: A/C 1: UNCTION: Open to provide vacuum relief for the suppression chamber.

REQlilRED TliST: OM Part 1,1.3.4.3 requires primary containment vacuum relief valves to have individual operability tests nominally every 6 months, ilASIS 1:OR DiiFliRRAL: These check valves open to provide assurance that the suppression chamber is not operated at a significantly lower pressure than the reactor building. They are not equipped with external operators for testing. These valves are located on top of the suppression chamber and are part of the primary containment boundary.

Access to these valves is hanrdous to personnel because there are no permanently installed walkways or handrails above the suppression chamber. These valve are not located in an environment that would degrade the valve seals. The valves are normally closed and are only opened for testing. A test frequency of every 6 months represents an unusual burden without a compensating increase in the level of quality and safety.

Al.TliRNATE TliST: The reactor building to suppression chamber vacuum relief valves will be operability tested each refueling outage in accordance with OM Part 1,3.3.2.3.

Revision 2 Section V Page 115 of 155

COOPER NUCLEAR STATION -!

1 TillRD INTERVAL.

INSERVICE TESTING PROGRAM :

REFUEL.ING OUTAGE JUSTIFICATION ROJ 20 ,

i

~

' val,VE: IIPCI CV-17CV !

CATEGORY: C '

C1. ASS: 2 FUNCTION: ilPCI-CV 17CV - Openc to provide a flowpath for itPCI pump minimum flow; closes to prevent diversion of RilR suppression pool cooling.

- REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

BASIS FOR l

DEFERRAL.: There is no practical means of verifying sufficient flow to full-stroke exercise this valve open. System configuration and absence of appropriate instrumentation prohibits full-stroke open verification.

l AllfERNATE TEST:. The valve w ill be disassembled, inspected and manually exercised during each refueling outage. In addition, a partial stroke exercise test, with flow, will be performed quarterly, and after each disassembly / inspection.

4 f

i-4 i

'r Revision 2 Section V Page 116 of 155

T$ TNm eNFmit7rT' "

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM E. Valve Relief Requests RR No. _Descrintion Notes RV-01 Ilot Shutdown Component Testing i RV-02 CRD-AOV-CV126, CRD-AOV-CV127, and CRD CV- 2 114CV (typical of 137) Exercising By Scram Testing RV-03 CRD-CV-115CV (typical of 137) Testing to the Closed 2 Position RV-04 CRD-CV-138CV (typical of 137) Test Method 2 RV-05 CRD-SOV-sol 20, S0121, S0122, and SO123 (Typical 2 of 137) Test Method RV-06 CS-CV-12CV, CS-CV-13CV, CS-CV-14CV, and CS-CV-15CV Testing to the Closed Position RV-07 IIPCI CV-18CV and 19CV Testing to the Closed Position RV-08 IIPCI-SOV-SSV64 and SSV87 Stroke Timing Alternative 3 RV-09 MS-RV-71 ARV to 7111RV Exercising Testing Frequency 3 RV-10 Excess Flow Check Valves Testing Per Technical 4 Specifications RV-I l RCIC-CV-18CV and 19CV Testing to the Closed Position RV-12 RilR-CV-18CV,19CV,24CV, and 25CV Testing to the Closed Posit ion RV-13 SW-MOV-MO89A and MO89B Testing Relief 3 RV-14 IIPCI-CV-24CV, 25CV, 26CV, 27CV, RCIC-CV-22CV, 23CV,24CV, and 25CV Testing Relief Notes:

I_ NRC Approval not required (TAC NO. M94530)

Revision 2 Section V Page 117 of 155

COOPliR NUCl.IIAR STATION TillRD INTliRVAL INSIIRVICE TI! STING PROGRAM 2 Approved by NRC letter dated February 19,1997 (TAC NO. M94530) 3 Revised to address NRC comments.

4 Acceptable per OM 10, NRC approval not required (TAC NO. M94530)

I Revision 2 Section V Page 118 of 155

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COOPER NUCLEAR STATION <

TillRD INTERVAL, INSERVICE TESTING PROGRAM RELIEF REQUEST RV 01 VALVEf Non component Specific .

. CLASS: 'All CATEGORY: All ;

FUNCTION: Various h REQUIRED TEST; OMa Part 10 provides the rules and requirements for inservice testing to verify operational readiness of certain valves (and their actuating and position indicating systems) in light water cooled nuclear plants, which are required to perform a

! specific function in shutting down a reactor to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an

. accident.

. HASIS FOR

RELIEF: Cooper Nuclear Stat. ion's accident analyses do not carry the response to an accident (e.g. Design Basis 1,0CA) to a point beyond the hot shutdown condition (i.e., to a 4 cold shutd ,wn condition). The licensing basis does not require the plant to r ; to -

s the cold shutdown condition in order to satisfy 10CFR100 radiological release -

guidelines.

Shice Safe Shutdown is defined in the CNS licensing basis as the hot shutdown 4

condition, inservice testing of components which are required to achieve cold shutdown is unwarranted, and does not provide any increase in the level of program quality or safety to the public.

ALTERNATE TEST: Cooper Nuclear Station's inservice Testing (IST) and Augmented Testing Programs will implement the rules and requirements for inservice testing to verify operational _ readiness of certain Class 1,2,3 and Non-Code Class valves (and their actuating and position indicating systems) which are required to perform a specific --

function in shutting down the reactor to the safe shutdown (hot ihutdown)

,- condition, in maintaining the hot shutdown condition, or in mitigating the consequences of an accident. Components which support achievement of cold shutdown only, are not required to be included in the lST or Augmented Test

Programs.

Revision 2 Section V- Page 119 of 155 l

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COOPER NUCLEAR STATION. !

-TillRD INTERVAL INSERVICl! TESTING PROGRAM i

}

RELIEF Rl! QUEST RV-02 VALVE: t.RD AOV CV126. CRD AOV-CV127, and CRD.CV-114CV (typical of 137)

CLASS: ' t ,- 2 CATEGORY: H, C FUNCTIONf CRD AOV-CV126 - Open with a scram signal to pressurize the lower side of the CRDM pistons from the accumulator or from the charging water header. l CRD-~AOV-CV127 - Open with scram signal to vent the top of the CRDM pistons !

to the scram discharge header.

CRD CV-114CV (typical of 137) Open to allow How from the top of the CRDM pistons to the scram discharge header.

l REQUIRED - 1) OMa Part 10, 4.2.1.1 requires Category A and H power operated valves to be TESTi individually full stroke exercised nominally every 3 months,1xcept as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7. l

2) OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3, 1 4.3.2.4, and 4.3.2.5.

HASIS FOR RELIEF: These valves are required to operate for rapid insertion (scram) of control rods.

Each valve is tested by scram-timing control rods in accordance with Technical Specification Sections 3.3 and 4.3. The Technical Specifications require testing 10 percent of the CRDs every 16 weeks and 100 percent of the drives each refueling.

The CRDs must fully insert within specified time limits. Should either the insert I or exhaust valves fail, the CRDs would not be able to meet Technical Specification requirements.

The air-operated valves fail-open on loss of air or power Normal opening removes power to the pilot solenoid valve, simulating a loss of power. On loss of power, the solenoid vents the air operator and CRD AOV-CV126 and CRD-AOV-CV127 are spring-driven openm Thus, each time a scram signal is

' Revision 2 Section V. Page 120 of 155

i COOPER NUCl. liar STATION TillRD INTERVAL.

INSERVICE TESTING PROGRAM RELIEF REQUEST RV-02 (Continued) given, the valves " experience" a loss of air / power to verify each valve's fail-safe open feature. In effect, scram testing meets or exceeds the functional testing requirements of Section XI to assess operational readiness. Individual stroke time measurements of CRD-AOV CV126 and CRD AOV CV127 are impracticable due to their rapid acting operation.

One hundred percent of the valves cannot be tested more often than each refueling outage. Testing 100 percent of the valves simultaneously would result in a full reactor scram. An excess number of scrams performed routinely could cause thermal and reactivity transients, which could lead to fuel, vessel, CRD, or piping damage. The CRDs cannot be tested during cold shutdown because the control rods are inserted and must remain inserted. This testing method for the valves is consistent with GL 89-04, position 7.

Alli'ERNATli Tl!ST: Scram testing per Technical Specifications will be substituted for all Section XI requirements. The test frequency will be 10% cach 16 weeks and 100% each refueling cycle. Valve stroke times will not be measured. This testing method is consistent with G1,89-04, position 7.

Revision 2 Section V Page 121 of 155

COOPliR NUCLEAR STATION TillRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-03 VALVE: CRD CV-115CV (typical of 137)

CLASS: 2 CATEGORY: C FUNCTION: Prevent bypassing scram water (from the accumulator) to the charging water header (if depressurized).

REQUIRED OMa Part 10, 4.3.2.1 requires check valves to be individually exercised TEST: nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3, 4.3.2.4, and 4.3.2.5.

IIASIS FOR Exercising these valves requires the depressurization of the charging water RELIEF header. The header is depressurized by either stopping the CRD pumps or by valving out and depressurizing the charging water header. Stopping the CRD pumps could result in seal damage to the control rod drive mechanisms (CRDM) from a loss of seal cooling water. Additionally, stopping the pumps would interrupt seal cooling water now to the reactor recirculation pumps resulting in shaft seal damage. This is impracticable during normal plant operation since valving out and depressurizing the charging water header would render the CRD accumulators inoperable and stopping the CRD pumps could cause pressure variations in the CRD System during the test evolution.

Exercising these valves during cold shutdown is not possible due to the interruption of shaft seal cooling water flow as previously discussed. If the recirculation pump became idle stopping the CRD pumps or manually isolating the charging water header for reverse exercise testing could delay plant startup due to the necessity of depressurizing upstream of each individual valve (137 each) in order to accomplish an adequate test. This additional test activity during cold shutdown represents an unusual burden without a compensating increase in the level of quality and safety.

This testing method for the charging water header check valves is consistent with GL 89-04, position 7.

ALTERNATE TEST: These valves will be tested during each reactor refueling outage. Proper closure I shall be verified by isolating each of the CRD scram accumulators and venting i pressure on the upstream side of the check valve. Accumulator pressure decay i would be observed should the respective valve fail to close properly.

Revision 2 Section V Page 122 of 155

COOPER NUCLEAR STATION TillRD INTERVAL INSERVICli TESTING PROGRAM REl.lEF Rl! QUEST RV-04 VALVES: CRD-CV-138CV (typical of 137)

CLASS: 2 CATEGORY: C FUNCTION: Close in the event of a scram to prevent diversion of pressurized ilCU accumulator water to the cooling water header.

REQUIRED TliST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5.

IIASIS FOR RlillEF* Normal control rod motion will verify that the associated cooling water check valve has moved to the safety function position. Industry experience has shown that rod motion may not occur if this check valve were to fail in the open position.

This testing method for the cooling water header check valves is consistent with GL 894M, position 7.

ALTERNATE TEST: During normal plant operation above 30 percent power, each partially or fully withdrawn operable control rod is exercised one notch at least once each week (Technical Specification 4.3. A.2). A cooling water header check valve is verified closed when the associated control md is successfully exercised.

Revision 2 Section V Page 123 of 155 l

COOPliR NtJCI. liar STATION TillRD INTliRVAl.

INSliRVICl! TliSTING PROGRAM i Rlil.Ilil' Rl!QUliST RV-05 VAINiiS: CRD.SOV liol20 S0121. 50122, and Sol 23 (Typical of 137) I Cl. ASS: 1 CATEGORY: 11 I;l)NCTION: Llose to provide Class 1 to No' -Code Class boundary isolation.

RiiQlllRl;D TliST: OMa l' art 10, 4.2.1.1 requires Category A and 11 power operated valves to be individually Dill strole exercised nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

IIASIS FOR Rlil.lliF: During normal operation these valves are used for riontros rod insertion and withdrawal. They are normally closed and must remali, ::losed to prevent diverting water during a sciam. They are exercised open and closed during normal operation of the assoelated CRD. They are not equipped with position indication.

This testing method for the CRD insert and withdrawl solenoid valves is consistent with GL 8944, position 7.

Al!!'l!RNATl!

TliST: 11oring normal plant operation above 30 percent power, each partially er fully drawn operable control rmi is exercised one notch at least once each week hnical Specificatbn 4.3. A 2). One pair of the:.e solenoids is exercised when th isw!ated CRD is withdrawn a noich, and the other pair is exercised when the CRD is inserted a notch. I' toper operation of the CRD verilles the operation of the associated solenoid valves.

, s Revision 2 Section Y Page 124 of 155

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COOPl!It NUCl.liAlt STATION Tilll(D INTill(VAL -

INSlil(VICl! Tl! STING PROGilAM ltlil.Il!F HliQUliSl' RV 06 VAINii: CS-CV 12CV, CS CV 13CV, CS CV 14CV, and r'S.CV-15CV i Cl. ASS: 2 A (outboard) CATI GORY: C FUNCTION: Coie Spray (CS) loop A and loop 11 pressure maintenance check valves from the condensate supply system. These valves open to maintain the Core Spray system solid and close to prevent diversion of core spray flow.

RI:QUIRl!D OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TliSTS: every 3 months, except as provided by paragraphs 4.3.2.2,4 s.2.3,4.3.2.4, and 4.3.2.5.

. IIASIS FOR These valves are normally closed check valves (with two in series). '11.e inboard Rl!Lil!F: valve is essential (safet) related). The redundant outboard valve is non-essential. ;

The valves are the same make and model number and met the same quality assurance requirements at the time they were installed. They open as necessary to keep the CS system in a solid uiandby condition, which is not a safety function.

When the CS pumps start, these valves close to ensure maximum flow to the reactor. These valves do not have perform a function which requires leakage to be limited to a sp:cifh:d amount.

Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classification requirements. Ilowever, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When a CS Pump is started, should both valves fail to close, a relief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.

ALTl!RNATl!

Tl!ST: The check valves in each loop will be tested closed simultaneously to assess the operational readiness of each pair of valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.

Revision 2 Section V Page 125 of 155

COOPlift NUCl.l.:.AIt STATION Tillitl) INTlil(VAI.

INSlil(VICl! TliSTING PI(OGl(AM l t

1(lil.ll!P 1(!!QUl!ST 1(V-07 VAIN!!. IIPCI CV-18CV and lil'Cl CV 19CV Cl. ASS: 2 A (outboard) CATl!Gol(Y: C FUN TION: liigh Pressure Coolant injection (llPCI) pressure maintenance check valves from the condensaie supply system. These valves open to maintain the llPCI system sol d and close to prevent diversion of IIPCI injection flow.

1(l!QUlit;il) OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TliSTS: every 3 months, except as provided by paragraphs J..i.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I:01< These valves are normally closed check valves (with two in series). The inboard 1(lil.ll!F: valve is essential (safety related). The redundant outboard valve is non-essential.

The valves are the same make and model number and met the same qualiry awurance requirements at the time they were installed. They open as necessary to keep the llPCI system in a solid standby condition, which is not a safety function.

When the llPCI stails, these valves close to ensure maximum flow to the reactor.

These valves do not have perform a function which requites leakage to be limited to a specified amount.

Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classificatien requirements. Ilowever, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When llPCI is staned, should both valves fail to close, a selief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.

ALTlil(NATL!

TliST: The check valves will be tested closed simultaneously to assess the operational ,

readiness of the pair of valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.

l(evision 2 Section V Page 126 of 155 u-.- _ . _ -.,..v. . - _ . _ , _ _ , . . . . , , . , _ . . ..mr..

t COOPliR NUCLliAR STATION TillRI) INTliRVAl, INSl!RVICl! Tl! STING PROGRAM l Rlil.lliF Rl!QUl!ST RV-Oh val,Vli: IIPCI SOV SSV 64 and llPCI-SOV SSV87 CLASS: 2 CATIIGolm 11 FUNCTION: The llPCi turbine and exhaust steam drip leg drain to gland condenser (llPCI-SOV SSV64) and ilPCI turbine and exhaust steam drip leg drain to equipment drain isolation valve (llPCI SOV SSV87) have an active safety function in the closed position to maintain pressure boundary integrity of the llPCI turbine exhaust line. These valves serve as a Class 2 to Non-code boundary barrier.

. Rl!QUIRiii) OMa Part 10,4.2.1 requires Category A and 11 power operated valves to be Tl!ST: Individually full stroke exercised and stroked timed nominally every 3 months, except as provided by paragraphs 4.2.1.2,4.2.1.5. and 4.2.1.7.

OMa Part 10,4.2.1.6 requires that vahes with fail safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accoru..nce with the exercising frequency of paragraph 4.2.1.1.

IIASIS FOR These valves are rapid acting, encapsulated, solenoid operated valves. Their ,

RiillliF: control circuitry is provided with a remote manual switch for valve actuation to the Open position and an Auto function which allows the valves to actuate from signals received from the associated level switches llPCI 1.S 98 and llPCI-LS-680. Iloth valves receive a signal to change dise position during operability testing of drain pot level switches. Ilowever, remote position indication is not provided for positive verification of dise position. Additionally, their encapsulated design i

prohibits the ability to visually verify the physical position of the operator, stem or internal components. Modification of the system to verify valve closure capability and stroke timing is not practicable nor cost beneficial since no commensurate increase in safety would be derived.

Al.Tl!RNATl!

TliST: Quarterly, each valve shall be exercised to the full closed position. Although valve stroke timing will not be performed, this test will verify that the valve moves to the safe position. linhanced maintenance shall be performed each refueling outage by disassembling and inspecting each solenoid valve to monitor for degradation.

i Revision 2- Section V Page 127 of 155

COOPlilt NUCl.l!All STATION Tilliti) INTliRVAl, INS!!!<VICli TliSTING PROGilAM Rlil.ll!F Hl!QUliST RV-09 VAINii: MS-RV 71 ARV, llRV, CRV, DRV, liRV,1 RV, GRV, and llRV Cl. ASS: 1 CATI GORY: ll/C ,

1 1: UNCTION: The main steam power operated safety valves have an active safety function in the open position to prevent over pressurization of the reactor vessel. These safety valves have an active safety function in the closed position to maintain reactor !

vessel integrity.

-Rl!QUIRiiD TliST: OMa Part 10,4.2.1 requires Category A and 11 power operated valves to be individually full stroke exercised and stroked timed nominally every 3 months, except as provided by paragraphs 4.2.1.2,4.2.1.5, and 4.2.1.7.

IIASIS 1:OR ltlil.IliF: These valves are power actuated safety relief valves for the main steam lines.

F.ach valve h exercised during startup following refueltag outages. lixerching these valves during power operations can cause pressure, temperature, and reactivity transients.

lixercising during cold ehutdown is impracticable since a minimum of $0 psig steam pressure is required to open the valves. The valve supplier does not recommend exercising these valves below 150 psig steam pressure because of the risk of valve seat damage and resultant leakage. Technical Specifications require testing once each refueling cycle at a reactor pressure > 100 psig, which is adequate to assess the operational readiness of these valves.

Relief valves are quick acting and their stroke-times cannot be measured by conventional means. They do not have position indication in the usual sense.

Pressure switches in the SRV discharge lines annunciate in the control room and indicate when the valve is open or closed Should a relief valve fail to function as designed, corrective action is required.

L Revision 2 Section V Page 128 of 155

C001'1114 NUCl.liAlt STATION l TillRD INTL!ItVAl. '

INS!!RVICl! TliSTING PitOGilAM Hlil.llil: Rl!QUliST ltV.09 (Continued)

All1lillNATl!

TliST: In addition to testing to the requirements of OM-1987, Part 1, I'mefraph 3.3.1.1, full stroke exercise tests of these valves open and closed will be istformed during l cach refueling outage. The opening stroke time will be measured from the tirne the switch is actuated until the pressure switeti in the discharge line annunciates.

This testing method is consistent with Gl. 89-04, position 6.

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Itevision 2 Sution Y Page 129 of 155

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COOPlilt NUCl.l!All STATION TillitD INTliRVAL INS!!RVICl! TliSTING PROGitAM ltlil.Ilil: RiiQUliST RV 10 VAIN!!S: lixcess 1 low Check Valves Cl. ASS: 1 CNfl! GORY: A/C I; UNCTION: The excess flow check valves are installed in instmment lines that provide signals for operation of safety related pumps and valves. They prevent excess flow of reactor water should an instrument line break outside containment.

IlliQUIRl!D TliST: OMu Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, ext.ept as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

Testing in accordance with OMa Part 10, 4.3.2.4 tequires demonstration that the valve disk travels to the seat on cessation of flow. Confirmation that the disk is on the seat may be by direct indication, such as position indicating devices, or by other indicators such as changes in system pressure, flowrate, level, temperature, seat leakage testing or other positive means. i IIASIS 1:OR \

lllit.Ilil: Uninterrupted function of these valves is essential for safety. Routine testing in accordance with Section XI would cause instrument line interruptions. This would disable instruments required for safe plant operations, safety-system actuation, reactor shutdown, or sensing accident conditions. In addition, these valves cannot be exercised during cold shutdown because removal of multiple instruments from

service could prevent or interrup; the operation of systems required for decay heat removal. ,

The excess flow check valves are tested using a modified leak rate test to assess operability. Testing is performed at least once er.ch operating cycle in accordance with Technical Specification 4.7.D.l.c. Testing more frequently could jeopardize the safety of the reactor.

Al.Tl!RNATl!

Tl!ST: In lieu of Section XI testing, a modified leak-rate test will be performed at least once each operating cycle.

Revision 2 Section V Page 130 of 155

1 COOFliR NUCLl!AR STATION TillRD INT!!RVAl, INMIRVICl! TliSTING PROGRAM j i

I Rlil.lliF RiiQUliST RY-11 l

VAINii: RCIC-CV-18CV and RCIC CV 19CV j J !

CIASS: 2. A (outboard) CATI! GORY: C i l

, FUNCTION: Reactor Core Isolation Cooling (RCIC) pressure maintenance check valves from the condensate supply system. These valves open to maintain the RCIC system solid and close to prevent diser a nn of RCIC injection flow. !

Hl!QUIRiiD OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally i TliSTS: every 3 months, cycept as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

, ilASIS FOR These valves are normally closed check valves (with two in series). The inboard Rill.lliF: valve is essential (safety related). The redundant outboard valve is non-essential, r The valves are the same make and model number and met the same quality

! assurance requirements at the time they were installed. They open as neecssary to i

- keep the RCIC system in a solid standby condition, which is not a safetygunction.

When the RCIC starts, thcx valves close to ensure maximum flow to the rhetor. .

These valves do not have perform a function which requires leakage to be limited

to a specified amount.

Only one valve is required to close to prevent diversion of flow as determined and documented in accordance with CNS safety classification requirements. Ilowever.

the current system design d u not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When RCIC is started, c should both valves fall to close, a relief valve would lift or a pressure sensor ivould

, alarm on the condensate supply side of the valves.

i Al.TliRNATli=

TliST: The check valves will be tested ' closed simultaneously to assess the operational ,

read! ness of the valves. Should the acceptance criteria be exceeded, both valves .

will be declared inoperable until they are repaired or replaced as necessary.

3 Revision 2 Secuon V Page 13_1 of 155 ;

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COOPlill NUCl.l!All STATION TillitD INTliitVAl, INSI!!(VICl! Tl! STING PitOGitAM Ill!LiliF liliQUliST ltV-12 VAIN!!: 1(llR CV-18CV, RilR CV 19CV, Itllit CV-24CV, and Rillt-CV 25CV Cl. ASS: 2 A (outboard) CATIIGOltY: C FUNCTION: Residual lleat Removal (Rif fs) loop A and loop 11 pressure maintenance check valves from the condensate supply system. These valves open to maintain the Illilt system solid and close to prevent diversion of LPCI injection now.

RI!QUIRl!D OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally TliSTS: every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS 1:OR These valves are normally closed check valves (with two in series). The inboard Rlil.IliF: valve is essential (safety related). The redundant outboard valve is non essential, liach pair of valves are the same design and met the same quality assurance requirements at the time they were installed. They open as necessary to keep the RilR system in a solid standby condition, which is not a safety funellon. When the RilR pumps start, these valves close to ensure maximum flow to the reactor.

These valves do not hase perform a function which requires leakage to be limited to a specified amount.

Only one valve is required to close to prevent diversion of now as determined and documented in accordance with CNS safety classification requirements, llowever, the current system design does not allow independent testing to ensure both valves have closed. Thus both valves will be tested together. When a RilR Pump is started, should both valves fail to close, a relief valve would lift or a pressure sensor would alarm on the condensate supply side of the valves.

Al.TliRNATli TliST: The check valves in each loop will be tested closed simultaneously to assess the operational readiness of each pair of valves. Should the acceptance criteria be exceeded, both valves will be declared inoperable until they are repaired or replaced as necessary.

Revision 2 Section V Page 132 of 155

COOPliR NUCl.liAlt STATION TillRD INTL!RVAl.

INS!!RVICl! TliSTING PROGRAh!

RiiLil!F RiiQUliST RV-13 val.VI!- SW.h10V.h1089A and SW h10V-h108911 CLASS: 3 CATliGORY: 11 FUNCTION: loop A and loop 11 outlet isolation for the Service Water booster pump cooling water to the RilR heat exchangers. These normally closed valves have an active safety function in the throttled position to provide a How path for cooling water How through the RilR heat exchangers during transient and accident conditions.

Rl!QUIRiiD Tl!ST: Ohta Part 10,4.2.1 requites Category A and il power operated valves to be individually full stroke exercised and stroked timed nominally every 3 months, except as provided by paragraphs 4.2.1.2,4.2.1.5, and 4.2.1.7.

IIASIS FOR Rlil.IliF: These valves are exercised during quarterly Service Water llooster Pump How testing to a throttled position required to satisfy Technical Specification How requirements. Valve stroke timing to the fully opened positian is impracticable.

Full opening will cause RilR Service Water llooster Pump run out. These valves cannot be accurately stroke timed because they are controlled with a thumb wheel type controller. After a pump associated with either valve has started, valve movement is subject to considerable variation. This type of controller provides an output signal that is dependant upon the speed with which the controller is operated. Stroke time measurements of these valves would be very difficult to repeat due to the absence of normal valve control switches and would not contribute meaningful data to utilire in monitoring valve degradation.

Al.TliRNATli TliST: These valves will be exercised to their safety-related throttled position quarterly, but stroke times will not be measured. At refueling outages, these valves will be tested under the CNS h10V Program in accordance with G1,8910. Stroke times will be one of the parameters measured.

i Revision 2 Section V Page 133 of 155

i COOPliR NUCLiiAR STATION TillRD INTliRVAI, INS!!RVICli TliSTING PROGRAM Rlil.IliF Rl!QUliST RV 14 VAINii: ilPCI CV 24CV. IIPCI CV 25CV, llPCI CV 26CV, llPCI CV-27CV, RCIC-CV 22CV, RCIC CV-23CV, RCIC-CV 24CV, and RCIC CV 2$CV Cl. ASS: 2 CATl! GORY: C PUNCTION: IIPCI and RCIC Turbine lixhaust I.ine Vacuum Hreakers open to prevent

<,iphoning suppression pool water into the exhaust line.

Rl!QUIRiiD OM Part 1,3.3.2.30U requires vacuum relief valves to be individually actuated to TliSTS: verify open and close capability, set pressure, and performance of any pressure and position sensing accessories. -,

OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I:OR These valves are normally closed check valves with two in series cross connected Rlilli!P: to two in parallel (11 pattern). The four RCIC valves are lift check valves, and the four llPCI valves are swing check valves. The valves are hicated in the suppression pool free space. In the closed position they prevent steam from the exhaust line entering the free space of the suppression chamber. liither two inboard valves or two outboard valves must be closed to perfonu this function.

Two valves in series provides added assurance that steam will not enter the suppression chamber.

The valves open to prevent siphoning suppression pool water into the exhaust line due to steam condensing when the associated llPCI or RCIC systems are isolated.

!!ach pair of valves is cross connected to the parallel pair of valves (11 pattern) so that a single failure will not prevent the vacuum relief function. These valves are not required to be leak tight and are not equipped with position indication or pressure sensing devices. During power operation the suppression chamber is inerted and inaccessible.

Due to the location and configuration of these valves (hicated on the open ended turbine exhaust lines) a closure test can not be performed and the inboard check valves are not accessible for a set pressure test. Also due to the configuration, a set pressure test of the two outboard RCIC lift check valves can not be performed.

Revision 2 Section V Page 134 of 155

COOPlilt NUCl.liAlt STATION TillitD INTliitVAl.

INSlil(VICl! Il! STING PI(OGl(AM ltlil.ll!! 1(l!QUl!ST ltV 14 (Continued)

Al.TliitNATl?

TliST: In lieu of the OM 1 and OM-10 requirements, each valve will be disassembled, inspected, and manually exercised open and closed during each refueling outape, in addition, the two outboard lipcl vacuum relief valves will be set point tested open in place each sel'ueling outage, llevision 2 Section V Page 135 of 155

C001'liR NUCl li AR STATION 1111RD INTL!RVAl.

INSl!!WICli T!!STINd l'ROGRAM 12 Augmented Vahe Cold Sheidown Test Justifications ACS).ML Denislun ACSJ 01 CnD CV-25CV and CRD.CV-26CV Closure Tc't I requency ,

ACSJ-02 DGSA CV !4CV, DGSA CV-15CV, DGSA CV 16CV, and DGSA CV.

17CV Closure Test 1 requency ACSJ-03 IIV-AOV 263AV, llV-AOV 265AV, llV-AOV-267AV, llV.AOV.269AV, llV.MOV-262hiV, llV MOV 264MV, llV-MOV 266MV, and ilV MOV 268'.1V Closure Test 1 requency ACS)-04 1 A-CV 54CV, IA-CV-55CV, IA CV 56CV, I A CV-57CV, IA-CV 58CV, IA CV-59CV, I A CV 60CV, and I A CV-IllCV Closure Test I requency ACSJ05 SGT-CV-14CV and SGT CV 15CV Open and Closure Test 1 requency 1

. Revision 2 Section V l' age 136 of 155

.. , ,e, , , .m, .~ -,.3 -_ _

COOPlift NUCl.l! Alt STATION -

Tilll(D INTlil(val.

INSl!!(VICli TliSTING PI(OGl(AM Al!GMl!NTliD COI.D SilUTDOWN JUSTil:lCATION ACS).01 :

VAINiiS: Cl(D CV 25CV and Cl(D CV 26CV Cl. ASS: A C NI!!GOltY: A/C l' UNCTION: Close to prevent pouible Cl(D bypass leakage from exiting secondary containment.

l(liQUll(lid TliST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5. ,

IIASIS Fult Dlil liRl(Al.: It is impracticable to perform a closure test or a partial closure test on these valves during power operations. These valves are located in the line from the CI(D pumps supplying drive water and charging water to the control rod's liydraulic .

Control Units (IICUs). During power operations these valves are open since drive water is constantly supplied to the llCUs, Closure or partial closure testing would require the CI(D pumps to be secured and the portion of the system containing these valves to be isolated. Isolating the valves or securing the Cl(D pumps terminates the constant drive water supply to the llCUs, which causes all the control tods to be inoperable. All control rods inoperable during power operations puts the plant into a Technical Specification I.CO requiring shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , which is operationally undesirable. Also, without a continuous charging water supply, ilCU accumulators would eventually depressurize, since the associated accumulator check valves are not designed to be leak tight.

Administrative controls require a scram initiation upon depressurization of two accumulators, which is a highly undesirable situation.

The interruption of the drive water flow wculd also interrupt Cl(D seal water cooling to the 1(cactor 1(eeirculation pumps. Stopping of flow would impose a severe thermal transient on the 1(R pump seals, which could possibly lead to premature seal failure.

l(evision 2 Section V Page 137 of 155

_ _ = - .-

COOPliR Nt1CLIIAR STATION TillRD INTliRVAl.

INSliRVICl! Tl! STING PROGRAM AUGMl!NTliD Col.D Sill 1TDOWN Jt)STIFICATION ACSJ-01 (Continued)

The increased potential for plant shutdown during testing at power operations outweighs the minor increase in confidence of component operational readiness when testing quarterly. These valves are not within the scope of ASMI!Section XI.

Al.TliRNATl!

TliST: Valve exercising, to the closed position, will be perfonned during cold shutdown by establishing a dif ferential pressure across the valve seat. This test requires the recirculation and reactor water cleanup pumps to be removed from service.

4 t

Revision 2 Section V Page 138 of 155

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COOFliR NUCl. liar STATION ;

TillRD INTL!RVAI, ;

INSl!RVICl! TESTING PROGRAM ;

AUGMiiNTl!D Col.D SilUTDOWN JUSTIFICATION ACSJ 02 ;

val.Vi!S: DGSA CV-14CV, DGSA CV-15CV, DGSA-CV 16CV, and DGSA CV 17CV Cl. ASS: A CATl! GORY: C FUNCTION: Opens to provide suf ficient tiarting air to start the diesel generators on loss of site electrical power and closes to provide system isolation and redundancy.

Rl!QUIRl!D

'I EST: UMa l' art 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3. 4.3.2.4, and 4.3.2.5.

IIASIS FOR Dl!FliRRAL: litercising these valves to the closed position requires isolating both emergency diesel generator starting air receivers causing the related emergency diesel generator to be considered inoperable dusing the test. Due to the importance of the diesel generator with sespect to plant safety, intentionally creating an inoperable condition during plant operation is not lustifiable. These valves are not within the scope of ASMi!Section XI.

ALTl!RNATl!

TliST: Valve exercising to the closed position will be performed during cold shutdown.

Revision 2 Section V Page 139 of 155

i CODPliR NUCl. EAR STATION TillRD INTL!RVAl, INSliRVICl! TliSTING PROGRAM 1

i AUGMiiNTl!D Col.D SittlTDOWN JUSTlFICATION ACSJ 03 val.VliS IIV AOV 263AV, llV AOV 265AV, llV AOV-267AV.

IIV AOV 269AV, ilV MOV 262MV. IIV MOV 264MV, ilV-MOV 266MV, and ilV MOV 268MV Cl. ASS: A CATl! GORY: 11 FUNCTION: Open to provide flow paths for ventilation to be supplied through the casing of both MG sets for cooling purposes, and close upon receipt of a PCIS Group IV or VI signal to provide secondary containment isolation.

RiiQUIRiiD '

TliST: 1) OMa Pari 10, 4,2.1.1 tequires Category A and 11 power operated valves to be individually full stroke exercised nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1,7.

2) OMa Part 10,4.2.1.6 requhes valves with fail safe actuators to be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of paragraph 4.2,1,1.

IIASIS FOR DFFl!RRAl/ These valves are required to remain in the open position during power operation to support reactor recirculation pump operation. Closure of these valves during reactor operation could result in oserheating the MG set which 'vould compromise reactor recirculation pump operation causing plant shutdown. Also, the valves' control circuitry does not provide for partial stroke capability. These valves are not within the scope of ASMl!Section XI. ;

Al Tl!RNATl!

TliST: These valves will be exercised to the closed position during cold shutdowns when the reactor recirculation pumps are in an idle state, in addition, the AOVs will he fail: safe tested during cold shutdowns when the reactor recirculation pumps ,uc in '

an idle state. During unscheduled cold shutdowns when the recirculation pumps are required to remain in operation, valve exercising and fail safe testing will be deferred until the next available opportunity when the recirculation pumps can be removed from service.

Revision 2 Section V Page 140 of 155

i COOPlilt N11Cl.l! Alt STATION TillitD INTliitVAL INSliRVICli TliSTING PitOGRAM ,

l Al)GMiiNTliD Col.D SilUTDOWN Jt!STillCATION ACSJ-04 .

val,Vli: lA CV-54CV, I A CV 55CV. I A-CV 56CV, IA-CV-57CV, IA CV 58CV, IA CV.

59CV, IA CV 60CV, and IA CV lllCV Cl. ASS: A CATl!Gol(Y: C PUNCTION: l A CV-54CV, IA CV 55CV, IA CV-56CV, IA CV 57CV, IA CV 58CV, IA CV-59CV, IA CV 60CV and IA CV lllCV Close to maintain pressure in the associated air operated valve's accumulator in the event of a loss of the Instrument Air (IA) supply. These I A supplies are for various safety related il&V system -

A0V's.

RiiQUIRiiD Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I;OR Dlil liRRAl.: The acceptance test for these check valves requires that the lA supply piping upstream of the c. heck valves to the associated accumulators be isolated and depressurized. The accumulator pressure is then monitored for one hour to verify that the check valve will hold. Isolation and depressurization of these lA lines will place these systems in an inoperable condition. The following sununarizes the specific system impacts:

I A CV-54CV, -55CV, and -56CV are in the IA supply lines to the Reactor fluilding supply and exhaust isolation dampers, Isolation and testing of these valves affects the operation of the Reactor lluilding Il&V system which controls area air nows and pressures.

IA-CV 57CV, -58CV, 59CV, AND 60CV are in the IA supply lines to the ll&V supply and exhaust for the MG Set I A and lit. Isolation and testing of these valves potentially affects the operation of the MG Sets.

i

, llevision 2 - Section V Page 141 of 155 l

i l

l

~

COOPl!R NUCl.l! Alt STATION TillRD INTliRVAL ,

INS!!RVICl! TliSTING PROGRAM l

AUGMl!NTliD Col.D SilUTDOWN JUSTil:lCATION ACSJ 04 CONTINUl!D i

IA CV-1IlCV is in the l A supply line for the Control Room limergency liypass I ilter inlet valve. Isolation and testing of this valve af fects the operation of this filter train. Therefore, it is impracticable to perform a reverse flow leakage test of these check valves during power operations. These d'es are not within the scope of ASMl!Section XI.

Al.Tl!RNATIVi! >

TliST: A reverse flow leakage test of these check valves will be performed during cold shutdown conditions, t

J Revision 2- Section V Page 142 of 155

i I

COOPlift Nt!Cl.l! Alt STATION Tilll(D INTlil(val. ,

INSlil(VICl! Tl! STING Pl(OGl(Ah!

AUGhiliNTl!D Col.D SilUTDOWN JUSTil:lCATION ACSJ-05 VAINiiS: SGT CV 14CY and SGT CV 15CV Cl ASS: A CATl!Gol(Y: C lti!QUll(lid TliST: Ohta Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

I UNCTION: Open to provide flow paths from their respective SGT litter trains. Close to prevent back flow from the operating SGT train discharge.

IIASIS 1:Olt Dlil liltl(Al/ The acceptance full flowrate for these valves is > 1602 cfm. During plant power operations, system conditions exist that prevent the SGT system from achieving a flowrate of > 1602 cim. l(eactor building differential pressure and back pressure '

from the Off Gas Dilution 1:ans act against SGT system pressure restricting SGT system 110wrate. Therefore, it is impracticable to perform a full flowrate test of these valves at power operations. These valves me not within the scope of ash 111 Section XI.

A!!!'lil(NATL!

TliST: A partial open stroke test will be performed on these valves during plant power operations on a quarterly frequency. A full flow open test will be performed on these valves during cold shutdown periods. The full flow test shall also satisfy the closure exercise requirements of the check valve in the idle train.

Revision 2 Section V Page 143 of 155 e ,

COOL'l!R NUCl.l!AR STATION TillRD INTL!RVAl -

INSliRVICl! Tl! STING PROGRAM 0, Augmented Valve Refueling Outage Justifications AROLNit Destintion AROJ 01 IA CV.17CV, IA CV-18CV, IA-CV-19CV, IA CV-20CV, ;

I A-CV-21CV, IA CV-22CV, IA CV.36CV, and IA CV 37CV Closure Test 1 requency AROJ 02 IA CV-28CV through I A CV CV35 Closure Test Method and 1 requency ;

AROJ 03 Withdrawn AROJ 04 St.C-CV-12CV and St.C-CV-13CV Opening Test lirequency .

AROJ 05 St.C CV 10CV and St.C-CV-1 ICV Opening and Closure Test 1 requency AROJ 06 Withdrawn !

s Revision 2 Section V Page 144 of 155

COOPliR NUCl liar STATION TillRD INTliRVAl, INSliRVIUi TliSTING PROGRAM AUGMiiNTliD Rlil Ulil.ING OUTAGli JUSTil:lCATION AROJ 01 VAIN!!- IA CV-17CV, IA-CV-18CV, IA-CV 19CV, IA CV 20CV. l A CV-21CV, IA CV 22CV, IA CV 36CV, and IA CV-37CV Cl. ASS: A CATl! GORY: A/C 1; UNCTION: Instrument Air / Nitrogen supply inlet check valves for Main Steam Relief Valve (SRV) accumulators. These check valves must be capable of closure to maintain accumulator integrity in the event of a loss of normal actuating air supply, IlliQUIRl!D TliST: OMa Part 10. 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I;OR Dlil;l!RRAl.: These valves are located inside the drywell and are inaccessible during normal operations or cold shutdowns. They cannot be exercised during each cold shutdown because the drywell is not routinely deiner!cd each cold shutdown.

Valve exercising duilng cold shutdown, when the drywell is deinerted, could dela' plant restart due to the necessity of using portable test equipment inside the drywell. The additional test activity during cold shutdown represents an unusual burden without a compensating increase in the level of quality and safety. These valves are not within the scope of ASMii Section XI.

Al.TliRNATl!

TliST: An extended time / pressure decay procedure will be used to verify each valve's closure. This will be done by venting the upstream side of the check valve and monitoring accumulator pressure to ensure each check valve functions properly.

The above valves will be tested each retueling outage to verily valve closure.

Revision 2 Section V Page 145 of 155

~ _

COOPlill NUCl.l!AR STATION TillRD INTliitVAl. '

INS!!RVICl! Tl! STING PROGRAh!

AtJGh11:.NTI!D Rlil lllil. LNG Ol1TAGli JtJSTil:lCATION AROJ 02 :

val.Vli: lA CV 28CV through IA CV-CV35 Cl. ASS: A CATl! GORY: A/C .

I (1NCTION: Close to isolate individual hiain Steam isolation Valve accumulators for emergency pas supply.

Rl!QUIRiiD TliST: Ohla Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

IIASIS I OR DI!! liRRAl.: These check valves do not have position indication devices. The only practicable method to verify valve closure is a pressure decay test. The valves are located in the steam tunnel and the drywell. They are inaccessible during operation and >

normal cold shutdowns. The complexity of the pressure decay test could delay plant startup alter a cold shutdown when the drywell is deinerted. Since these emergency air supply accumulators are a backup to the normal pneumatic supply, performing the test at refueling outages is adequate to assess valve operational readiness. These valves are not within the scope of AShili Section XI.

Al.TI!RNATl!

Tl!ST: A pressure decay test will be performed each refueling outage to verify valve closure.

J Revision 2 Section V Page 146 of 155

l COOL'l!R NUCl.l!AR STATION TillitD INTliRVAl, INS!!ItVICl! TliSTING l'HOGRAM AUGMt!NTl!!> Rlilittlil. LNG 01JTAGli JllSTillCATION AROJ 03 Withdrawn Revision 2 Section V l' age 147 of 155

COOPl!R NUCl.l!AR STATION TillRD INTliRVAI, INSliRVICliTliSTING PROGRAM AUGMiiNTl!D Rlil:Ulil.ING OUTAGliJUSTillCATION AROJ4)4 VAIN!!: St.C.CV 12CV and St.C-CV 13CV -

Cl. ASS: 1 CATl! GORY: A/C I; UNCTION: Inboard and outboard containment isolation valves must open to allow injection of sodium pentaborate (neutron poison) for reactivity control. The injection of the sodium pentaborate is not a safety function, but may be required in emergency situations.

Rl!QUIRl!D TliST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

ilASIS 1 OR Dlil liRRAl.: These valves are normally closed with reactor pressure on the downstream side. ;

lixereising these valves to the open position during power operation would require firing the upstream squib valve and injecting demineralized water from the test tank to (bc reactor vessel. This activity would not only require 11ushing the system of sodium pentaborate prior to testing, but would also subject the St.C injection nonle to thermal transients due to the relatively cold deminerallied water temperature. This additional test activity during cold shutdown represents an unusual burden without a compensating increase in the level of safety and could delay plant testart due to the measures required to prevent inadvertent admission of boron to the reactor coolant system resulting in the potential for an imbalance in teactor water chemistry. The open function of these valves is not within the scope of ASMll Section XI.

Al.TliRNATl! ;

TliST: The opening capability of the SI.C check valves will be verified during refueling l outages by performing a vessel injection from the SI.C system as required by Technical Specification 4.4. A.2.c.

i Revision 2 Section V Page 148 of 155 t'

)

COOPliR NllCl. liar STATION TillRD INTliRVAl.

INS!!RVICl! Tl! STING PROGRAM AUGMiiNTl!D 111!!:1JIil.ING Ol1TAGI! JUSTil:lCATION AROJ-05 VAINil: SI.C-CV 10CV and SI.C CV llCV j CLASS: A Call! GORY: C

FUNCTION: The St.C pump discharge check valves are required to open for sodium pentaborate injection (neutron poison) and close to isolate the inservice pump from the adjacent idle pump. The injection of the sodium pentaborate is not a safety function, but may be required in emergency situations.

Rl!QUIRI!D Tl!ST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 1.3.2.5.

IIASIS l'OR Dlil liRRAl.: These pump discharge check valves are located in a segment of piping which is not ;

provided with upstream vent / drain co,meetions or pressure connections to facilitate

. valve closure testing. Additionally, the pumps' positive displacement design does not allow for any appreciable back flow which otherwise may be detected in the pump suction piping. Modification to the system for verification of valve closure capability is not practicable nor cost beneficial since no commensurate increase in safety would be derived. The only practicable method of valve closure verification is by performing radiography (RT) of the seat area. Performing RT on a quarterly or cold shutdown frequency, as opposed to once each refueling, increases

. personnel radiation exposure due to the presence of a radioactive source. Although esposure is low, this is an undesirable AIARA practice. The burden of performing a quarterly RT is not justified based on the previous discussion. These .,

valves are not within the scope of ASMl!Section XI.

AlifliRNATl!

TliST: Valve closure capability shall be verified at or prior to each refueling outage by performing radiography on the valve seating area.

' Revision 2 Section V Page 149 of 155 yv, _. - . . - , ,p.- - ~ - . . - - - . . - - . ~ , , _ . . . - , , . . . , . . . .-

C001'liR NUCl.l!AR STATION TillRD INTliRVAI, INSliRVICl! Tl! STING l'ROGRAM AUGMiiNTliD Rlil:tilil.ING OllTAGli JlJSTillCATION AROJ-06 Withdrawn t

Revision 2 Section V l' age 150 of 155 e

. . . . , , , ~ + _. . . - _ _ _ .

i COOL' lilt NUCl.I!AR STATION TillRD INTL!RVAl, i INSliRVICII Tl! STING l'ROGRAh! i

11. Augmented Valve Relief Requests ARY No. Dnctiatled ARV-01 DGDO 1:OV 1 lli'V10. DGDO 1:OV 1 LTVil, DGDO SOV-SSV5028, and DGDO-SOV SSV5029 Test h1ethod ARV 02 DGSA SOV SI'VI, DGSA-SOV SI'V2, DGSA SOV-SI'V3, DGSA-SOV-SI'V4, DGSA AOV AV5, DGSA-AOV-AV6, DGSA AOV AV7, and DGSA-AOV-AV8 Test hiethod ARV.03 DG AOV h1111 and DG-AOV hill 2 Test hiethod Revision 2 Section V l' age 151 of 155

COOPER NUCl.l?AR STATION TillRD INTERVAL, INSERVICE TESTING PROGRAM AUGMENTED RELIEF REQUEST ARV-01 val,VE: DGDO FOV FLTV10 DGDO-FOV-Fl.TVil, DGDO-SOV-SSV5028, and DGDO SOV-SSV5029 CLASS: A CATEGORY: 11 and C (Fl TV 10/11)

FUNCTION:

The DG Day Tank Inlet valves ( DGDO-FOV-FLTV-10. FLTV-ll) have an active safety function in the closed position to prevent overfilling of the associated Day Tank during fuel oil transfer operations. These Goat operated inlet valves also have an active safety function in the open position to permit filling of the associated Diesel Fuel Tanks.

The DG Day Tank Fuel Safety Solenoid Valves (DGDO-SOV-SSV5028, SSV5029) have an active safety function in the closed position to provide redundant isolation capabilities in the event day tank inlet valve (DGDO-FOV-FilrV-10, Fl!!'V ll) fails to close, thereby preventing overfilling of the day tank.

These solenoid valves also have an active safety function in the open position to permit filling of the associated Diesel Fuel Tanks.

REQUIRED TEST: OMa Part 10,4.2.1 requires Category A and 11 power operated valves to be individually full stroke exercised and stroked timed nominally every 3 months, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7, i DGDO.SOV-SSV5028, and 5029 also require testing to the fail safe opea position on loss of actuation power per OMa Part 10, 4.2.1.6.

OMa Part 10, 4.3.2.1 requires check valves to be individually exereired nominally every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5.

~

Revision 2 Section V Page 152 of 155

COOPER NUCl. EAR STATION TillRD INTERVAL INSERVICE TliSTING PROGRAM AUGMENTED Rl! LIEF REQUEST ARV-01 (Continued)-

hASIS FOR RELIEl:- Float valves. DGDO-FOV FLTV.10/ll are encapsulated float operated valves and are not provided with remote position indication or remote manual switching capability. DGDO SOV.SSV 428,5029 are encapsulated solenoid valves and are not provided with remNe p n.iaon indication or remote manual switches. Other positive means such as now or pressure indication are not provided in the piping circuit. The design of these valves prohibits visual verification of the physical position of the valve operator, stem, or internal components. The float valve closes at 54 inches. Should the Goat valve fail to close, the solenoid vahe will close at 58.5 inches. Modification of the system to verify individual valve exercising capability is not practicable nor cost beneficial since no commensurate increase in safety would be derived. These valves are not within the scope of ASME Section XI. NRC approval of this relief request is not required.

ALTERNATE TEST:

Each diesel generator is started manually every month to demonstrate operational readiness. During this test the diesel fuel oil day tank level alarms and transfer pump control level switches are functionally tested. The operability of the float valves and solenoid valves shall be verified epen by observing restoration of day tank level. The Boat valves shall be serified closed by the lack of continuous rise in level once proper volume is echieved. The sound of solenoid mnvement shall be used to verify valve movement to the closed pasition.

Revision 2- Section V Page 153 of 155 Sum @ tussuims v *+e y

COOPER NUCLEAR STATION TillRD INTEP. VAL INSERVICE TESTING PROGRAM AUGMl!NTED RELIEF REQUEST ARV-02

- VALVE: DGSA-SOV-SPV1, DGSA-SOV-SPV2, DGSA-SOV-SPV3, DGSA-SOV-SPV4, DGSA AOV-AVS, DGSA AOV-AV6, DGSA AOV-AV7, and DGSA-AOV.AV8 CLASS: A CATEGORY: 11 FUNCTION: Diesel Generator Air Start Valves direct starting air to the emergency diesel generators.

REQUIRED TEST: OMa Part 10,4.2.1 cequires Category A and 11 power operated valves to be individually full stroke exercised and stroked timed nominally every 3 months, c:<c<.pt as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

IIASIS FOR REl.lEF. These valves are mounted on the diesel generator skid and are integral to the operation of the diesels. They are totally enclosed with no means to visually observe stem movement. Additionally, these valves are not provided with remote /

manual switches or position indicating lights. The control circuitry and design configuration of these valves is not conducive to performing valve stroke timing.

Modification to the system in order to facilitate valve stroke timing is not practicable nor cost beneficial since no commensurate increase in safety would be derived. These valves are not within the scope of ASME Section X1. NRC approval of this relief request is not rmuired.

ALTl!RNATE TEST: Starting the respective standby emergency diesel generator using the air start system with the opposing air start header valved out of service, will be adequate to demonstrate proper operation of the air start valves. Therefore, the air start val es will be tested when the diesel generators are tested. Satisfactory diesel testing wih satisfy valve exercising requirements. Each air start valve train will be exercised during this testing at least quarterly.

Revision 2 Section V Page 154 of 155

COOPliR NUCl. liar STATION TillRD INTL!RVAL INSliRVICE TliSTING PROGRAM AUGMiiNTI!D RI!!.Ilil: RiiQUEST ARV-03 val.Vli- DG-AOV-Mill and DG AOV Mll2 Cl. ASS: A CATliGORY: 11 FUNCTION: Diesel Generator Muf fler flypass Valves.

RI!QUIRl!D TI'ST: OMa Part 10,4.2.1 requires Category A and D power operated valves to be individually full stroke exercised and stroked timed nominally every 3 tuonths, except as provided by paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

IIASIS FOR REl.lEF. These valves are integral to the operation of the diesels. These valves are actuated by a pressure switch off the deisel exhaust. The are not provided with remote manual switches or position indicating lights. The control circuitry and design configuration of these valves is not conducive to performing valve stroke timing.

Modification to the system in order to facilitate valve stroke timing is not practicable nor cost beneficial since no commensurate increase in safety would be derived. These valves are not within the scope of ASME Section XI. NRC approval of this relief request is not required. .

Al.Tl!RNATli TliST: A pressure signal will be supplied to actuate the bypass valves. Each muf0er

bypass valve will be exercised open and fail safe tested at least quarterly. Stroke timing will not be performed.

- Revision 2 Section V Page 155 of 155 1

i i

ML20210H564

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