Text

NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1
	ML20134E109
Person / Time
Site:	Cooper
Issue date:	10/25/1996
From:	; NEBRASKA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20134E095	List: ML20134E093; ML20134E109;
References
	PROC-961025, NUDOCS 9610310282
	Download: ML20134E109 (187)
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l NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM REVISION 1 l l

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9610310282 DR 961025 ADOCK 05000298 PDR

I COOPER NUCLEAR STATION l THIRD INTERVAL

! INSERVICE TESTING PROGRAM TABLE OF CONTENTS

1. INTRODUCTION PAGE A. Basis for the Program 1 B. The Third Ten Year Interval 2 C. Applicable ASME Code 2 l

D. IST Program Scope 2 E. IST Basis Document 3 F. Testing Frequency 3 l G. Skid-Mounted Components and Component Subassemblies 3 l H. Program Description 4 l

II. TESTING PROGRAM FOR PUMPS A. Description 1 B. Allowable Ranges of Test Quantities 1 C. Instrumentation 1 D. Reference Values 2 III. PUMP

SUMMARY

LISTING

! A. Notations 1 l

B. Pump Summary Tables 2 C. Pump Relief Requests 11 D. Augmented Pump Relief Requests 19 IV. TESTING PROGRAM FOR VALVES A. Description 1

! B. Cold Shutdown Testing 1 l

C. Limiting Values of Full-Stroke Time 1 D. Reference Values 2 :

E. Instrumentation Requirements 2 F. Active / Passive Valves 2 G. Fail-Safe Testing 3 H. Valve Position Indication Verification 3 I. Water Sealed Valves 3 J. Check Valve Testing 4 K. Relief Valve Testing 4 L. Vacuum Breaker Testing 5 ,

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COOPER NUCLEAR STATION TIIIRD INTERVAL i

INSERVICE TESTING PROGRAM i

l V. VALVE

SUMMARY

LISTING PAGE A. Notations 1 B. Valve Summary Tables 4 C. Cold Shutdown Justifications 80 ,

D. Refueling Outage Justifications 94 E. Valve Relief Requests 117 F. Augmented Valve Cold Shutdown Justifications 134 l G. Augmented Valve Refueling Outage Justifications 142 II. Augmented Valve Relief Requests 149 l r :

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l COOPER NUCLEAR STATION )

THIRD INTERVAL l INSERVICE TESTING PROGRAM '

I. INTRODUCTION ;

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

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

Regulatory Guide 1.26, Revision 3, Febmary 1976, " Quality Group Standards for Water , Steam , and Radioactive-Waste-Containing Components of Nuclear Power Plants",

i Regulatory Guide 1.147, " Inservice Inspection Code Case Acceptability, ASME Section XI, Division I", >

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ANSI /ANS-52.1-1983, American National Standard, " Nuclear Safety Criteria for the Design of Stationary Boiling 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 letter 89-04, Supplement 1: " Guidance On Developing Acceptable Inservice Testing Programs", dated April 4,1995,

NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants" l

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l

B. 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 allowed by IWA-2400(c). CNS will begin the third interval on March 1,1996.

C. Applicable ASME Code 1

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

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

ASME Section XI, Subsections IWP and IWV invoke ANSI /ASME Operations and Maintenance (OM) Standards Part 6, and Part 10,1987 Edition with the 1988 l Addenda. The OM Standards are approved for use in 10CFR50.55a(b)(2)(viii).

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

D. Program Scope ASME Class 1,2, or 3 pumps which are provided with an emergency power source and perform a function to bring the plant to the safe shutdown condition, maintain the plant in the safe shutdown condition, or mitigate the consequences of an accident are included in the IST Program. ASME Class 1, 2, or 3 valves which perform these functions and safety or relief valves which provide over pressure protection for systems 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 analyzed in Section XIV of the USAR, but to a broad range of possible adverse events which could affect plant safety. Additional accidents I

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."

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM

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

l Non-Code Class components whose functions are essential to the safety or reliability of the plant are also included in the CNS IST Program as augmented components. These l 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 regulations, requests for relief are not required if the OM Standards cannot be met.

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

E. IST Basis Document A separate IST Basis Document has been prepared for the third inspection interval. It documents the safety functions and the basis for the tests specified for the components in the third interval program, and provides the justification for certain components excluded from the testing program.

F. Testing Frequency 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 allowed by the Technical Specifications, to provide necessary operational flexibility.

G. Skid-Mounted Components and Component Subassemblies ;

Skid-mounted components are pumps and valves in skid systems of major equipment l 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 NUREG 1482, Section 3.4, skid-mounted components and component subassemblies !

need not be individually tested to the Code requirements provided their operational readiness is adequately demonstrated by testing ef the associated major equipment.

l Examples of skid-mounted components would he the diesel fuel oil booster pump and l engine driven fuel oil pump, and the HPCI and RCIC turbine stop valves. Skid-mounted components are identified in the CNS IST Program Basis Document.

Examples of skid-mounted subassemblies would be the solenoid operated pilot valves l

for air operated valves.

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T COOPER NUCLEAR STATION l THIRD INTERVAL INSERVICE TESTING PROGRAM i H. Program Description The IST Program is organized in five major sections. The first section is the !

introduction, which provides the background for the development of the IST Program; I

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 fifth section provides the valve tables, cold shutdown test ,

justifications, and associated relief requests.

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INSERVICE TESTING PROGRAM i

II. TESTIMG PROGRAM FOR PUMPS A .' Description The Pump Summary Listing,Section III, identifies the pumps included in the CNS IST I

Program, the inservice test quantities to be measured, the test frequency, references to pump relief requests, and other pertinent information.

B. Allowable Ranges of Test Quantities I

The allowable ranges specified in OMa Part 6, Tables 3a, and 3b are used for pressure, flow, and vibration measurements except as provided in relief requests. In some cases, 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 situation occur, an operability determination may be performed, in accordance with Generic I2tter 91-18, NUREG 1482, and CNS administrative procedures.

l C. Instrumentation

! 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 instrument loop. The allowable inaccuracy of an instrument loop is based on the square root of the sum of the squares of the inaccuracies of each instmment in the loop. The instmment accuracy requirements refer to the calibration of the instrument. The Code does not require consideration of other factors which could contribute to measurement error such as

! orifice wear, instrument location, etc. However, excessive measurement error would be detected by erratic or unacceptable test results which would require corrective action. If test results are due to out of calibration instruments, the instruments may be recalibrated and the test rerun. If it is determined that unacceptable test results are due to other instrument problems, corrective action shall be by repair or replacement of the instrument system, l

The Code requires that flowrate be measured using a rate of quantity meter installed in I 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 4

and outlet of the pump.. Per NUREG-1482, Section 5.5.3, suction pressure may be calculated based on inlet tank or bay level.

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l COOPER NUCLEAR STATION '

THIRD INTERVAL INSERVICE TESTING PROGRAM Vibration instrumentation shall be calibrated over the required frequency response ,

range of one third minimum pump speed to at least 1000 HZ. OMa Part 6 requires i vibration velocity measurements to be peak. For a simpit, sinusoidal waveform, l NUREG 1482, Section 5.4 allows RMS values to be converted to peak values with a multiplier of 1.414.

l l D. Reference Values Reference values are determined from the results of the previous interval's inservice l tests. Reference values will be reestablished following pump replacement. Reference i

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

I 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 i values (s) reconfirmed by an inservice test run prior to declaring the pump operable.

j Pumps may be tested at more than one point of pump operation. Additional reference :

j values must be established for these points in accordance with Code requirements. j Whenever an additional set of reference values is established, the reasons for doing so ;

shall be documented in the record of tests. ;

The Code requires that reference values be established at points of pump operation that l

can be readily duplicated during subsequent tests. It may not be possible, or it may be i l extremely difficult, to vary system resistance such that the reference conditions are .

l duplicated exactly. NUREG 1482, Section 5.3, allows variation in the setting of fixed !

l reference value of either differential pressure or flowrate provided the combination of this variation and the associated instrument error does not exceed 2%.

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TIIIRD INTERVAL i INSERVICE TESTING PROGRAM III. PUMP

SUMMARY

LISTING 1

A. Notations '

l The following notations are used in the pump summary tables: ,

SYSTEM: The plant system in which the pump is located.

l PUMP CIC: The pump component identification code.

ISI CLASS: The ASME Inservice Inspection (ISI) classification of the l component. Augmented components are classified "A".

P&ID: The associated piping and instrumentation drawing number. ;

P&ID COOR: The drawing coordinate location for the pump.

PARAMETERS: Refers to the test quantities to be measured or observed. The symbols used for designating which parameters will be measured or obsen'ed are as follows:

dP - Differential Pressure I

Pi - Inlet Pressure Pd - Discharge Pressure )

Q - Pump Flowrate N - Rotative Speed V -Vibration Amplitude FREQUENCY: The frequency of testing each pump. The letter "Q" denotes quarterly testing; the letters "CS" denote cold shutdown testing; and the letters "RF" denote refueling outage testing.

t NOTES: This column contains a brief component description, references

! any applicable relief request (s), and contains any other component-related information. Relief Requests are designated RP-XX. Augmented Relief Requests are designated ARP-XX.

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SUMMARY

TABLES SYSTEM: CORE SPRAY (CS), P&lD No. 2045 Sheet 1 PARAMETERS PUMP P&ID ISI NOTES CIC COOR CLASS Q dP V N CS-P-A F-3 2 Q Q Q (1) CS PUMP 1A, LOOP A RP-01, RP-02 CS-P-B D-3 2 Q Q Q (1) CS PUMP IB, LOOP B RP-01, RP-02 NOTES:

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

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR FUEL OIL TRANSFER, P&ID No. 2011 Sheet 1 PUMP P&ID ISI PARAMETERS CIC COOR CLASS NOTES ,

Q dP V N DGDO-P-DOTA A-8 A Q Q Q (1) PUMP 1A '

DGDO-P-DOTB A-10 A Q Q Q (1) PUMP 1B NOTES:

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

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI), P&ID No.' 2044 PARAMETERS PUMP P&ID ISI NOTES CIC COOR CLASS Q dP V N HPCI-P-MP E-4 2 Q Q Q Q HPCI PUMP 1 A (MAIN), (1)

RP-01, RP-02 HPCI-P-BP E-3 2 Q Q Q Q HPCI PUMP IB (BOOSTER), (1)

RP-01, RP-02 NOTE:

(1) HPCI main and booster pumps will be tested simultaneously.

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SUMMARY

TABLES SYSTEM: RADIOACTIVE WASTE (RW), P&lD No. 2005 Sheet 2 PARAMETERS 1 PUMP P&ID ISI NOTES CIC COOR CLASS Q dP V N RW-P-Z1 G-10 A RF N/A N/A (1) ELEVATED RELEASE POINT ;

SUMP PUMP 1A, ARP-01 l RW-P-Z2 G-10 A RF N/A N/A (1) ELEVATED RELEASE POINT t SUMP PUMP IB, ARP-01 !

NOTES:

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

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COOPER NUCLEAR STATION THIRD INTERVAL ,

INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC), P&ID No. 2043 PARAMETERS PUMP P&ID ISI -

NOTES CIC COOR CLASS Q dP V N ,

RCIC-P-MP G-3 2 Q Q Q Q RCIC PUMP 1 A

, RP-01, RP-02, RP-04 i I

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THIRD INTERVAL INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES SYSTEM: REACTOR EQUIPMENT COOLING (REC), P&lD No. 2031 Sheet 2 I

PARAMETERS PUMP P&ID ISI NOTES CIC COOR CLASS Q dP V N REC-P-A G-1 3 Q Q Q (1) REC PUMP 1A, LOOP A RP-03 REC-P-B G-2 3 Q Q Q (1) REC PUMP IB, LOOP A RP-03 REC-P-C G-3 3 Q Q Q (1) REC PUMP IC, LOOP B ,

RP-03 REC-P-D G-3 3 Q Q Q (1) REC PUMP ID, LOOP B RP-03 NOTES:

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

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR), P&ID No. 2040 PARAMETERS PUMP P&lD ISI NOTES CIC COOR CLASS Q dP V N RIIR-P-A G-4 2 Q Q Q (1) RIIR PUMP 1A, LOOP A RP-01, RP-02 RHR-P-B G-9 2 Q Q Q (1) RHR PUMP IB, LOOP B RP-01, RP-02 RHR-P-C H-4 2 Q Q Q (1) RHR PUMP IC, LOOP A RP-01, RP-02 RHR-P-D H-9 2 Q Q Q (1) RHR PUMP ID, LOOP B RP-01, RP-02 NOTES:

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

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I COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l PUMP

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW), P&ID No. 2006 Sheets 1 and 4 l PARAMETERS PUMP P&ID ISI NOTES CIC COOR CLASS dP V N Q

t SW-P-A B-10 3 Q Q Q (1) SW PUMP 1 A, RP-05 SW-P-B B-9 3 Q Q Q (1) SW PUMP 1B, RP-05 SW-P-C B-8 3 Q Q Q (1) SW PUMP IC, RP-05 SW-P-D B-7 3 Q Q Q (1) SW PUMP ID, RP-05 SW-P-BPA F-7 3 Q Q Q (1) SW BOOSTER PUMP 1 A, RP-02 SW-P-BPB C-7 3 Q Q Q (1) SW BOOSTER PUMP IB, RP-02 ;

SW-P-BPC E-7 3 Q Q Q (1) SW BOOSTER PUMP IC, RP-02 i

SW-P-BPD A-7 3 Q Q Q (1) SW BOOSTER PUMP ID, RP-02 r

NOTES:

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

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM PUMP

SUMMARY

TABLES :

SYSTEM: STANI;BY LIQUID CONTROL (SLC), P&ID No. 2045 Sheet 2 PARAMETERS PUMP P&ID ISI NOTES CIC COOR CLASS Q P V N SLC-P-A E-10 A Q Q Q (1) PUMP 1A SLC-P-B F-10 A Q Q Q (1) PUMPIB y

Notes: (1) Positive displacement pump t

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM C. Pump Relief Requests RR No. Description '

RP-01 CS, RHR, HPCI, RCIC Pumps Suction Pressure RP-02 CS, RHR, HPCI, RCIC, SW, and SWB Pumps Instrument Accuracy l RP-03 REC Pumps Flowrate Gauge Range l

l RP-04 RCIC Pump / Turbine Speed Measurement Range ;

i l RP-05 SW Pumps Differential Pressure i

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THIRD INTERVAL 4

INSERVICE TESTING PROGRA.M t RELIEF REQUEST RP-01 PUMP: Core Spray CS-P-A, CS-P-B i Residual Heat Removal RHR-P-A, RHR-P-B, RHR-P-C, RHR-P-D High Pressure Coolant Injection HPCI-P-MP/BP Reactor Core Isolation Cooling RCIC-P-MP CLASS: 2 L

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)].

BASIS FOR The permanently installed suction pressure gauge of a pump is RELIEF: ge .:: rally 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 for proper operation. For suction head determination, the accuracy and 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.

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 orders 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.

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~ THIRD INTERVAL INSERVICE TESTING PROGRAM l

i RELIEF REQUEST RP-02 l PUMP: Core Spray CS-P-A, CS-P-B l Residual Heat Removal RHR-P-A, RHR-P-B, RHR-P-C, RHR-P-D High Pressure Coolant Injection HPCI-P-MP/BP ;

Reactor Core Isolation Cooling RCIC-P-MP l

Service Water Booster SW-P-BPA, SW-P-BPB, SW-P-BPC, SW-P-BPD j CLASS: 2 - CS, RHR, HPCI, and RCIC !

3 - SW Booster (SWB) l FUNCTION: CS, RHR, HPCI, RCIC - Emergency core cooling. l SWB - Residual heat removal equipment cooling.

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REQUIRED ;

TEST: Instrument accuracy shall be within the limits of Table 1 (OMa Part 6, 4.6.1.1).

BASIS FOR TEST: The percentages of total loop accuracy for the combination of instruments listed below does not meet the requirements of Table 1:

FUNCTION LOOP ACCURACY ( 0 l CS Pump Discharge Pressure 2.%

CS Pump Flowrate 2.02 RHR Pump Flowrate 2.08 HPCI Pump Flowrate 2.03 RCIC Pump Flowrate 2.03 SWB Pump Flowrate 2.03 The difference between the existing loop accuracy for instrument combinations 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.

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e COOPER NUCLEAR STATION THIRD INTERVAL j INSERVICE TESTING PROGRAM RELIEF REQUEST RP-02 Continued

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

indicated. :

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RELIEF REQUEST RP-03 r

l PUMP: Reactor Equipment Cooling REC-P-A, REC-P-B, REC-P-C, REC-P-D CLASS: 3 FUNCTION: Provide cooling to critical equipment.

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

BASIS FOR ,

RELIEF: Permanent plant flow gauges, REC-FI-450A and REC-FI-450B, for i measurement of REC pump flowrate have ranges of 0-4000 gpm. This does not meet the range limitation imposed by OMa Part 6,4.6.1.2(a) in that the instrument ranges exceeds the respective reference value (1000 gpm) by greater than a factor of three. However, the full scale accuracy of these gauges is 1.5% which is 60 gpm. 60 gpm accuracy on a range of 0-3000 gpm is 2% which is acceptable per OMa Part 6,4.6.1.1.

Therefore, flow gauges REC-FI-450A and REC-FI-450B are acceptable l

for flowrate measurement.

l ALTERNATE TEST: REC pump inservice test flowrates will be measured via flow indicators REC-FI-4501 and REC-FI-450B.

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! i l RELIEF REQUEST RP-04 j PUMP: Reactor Core Isolation Cooling, RCIC-P-MP CLASS: 2 1

FUNCTION: Emergency core cooling.

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

BASIS FOR Based on previous work history, permanent plant tachometer, RCIC-SI-RELIEF: 3067, for measurement of RCIC pump / turbine speed, may not provide ;

the required consistency needed for inservice testing unless instrument I calibration is performed immediately prior to each test. This " extra" calibration places an additional burden on limited Instrument & Control personnel resources without a compensating increase in the level of quality and safety.

Hand-held tachometers have proven to be more reliable instruments as j far as producing consistent readings. The tachometers available for IST, l have ranges of 10-99,999 rpm or 6-30,000 rpm. The respective l reference value is 4500 rpm. Therefore, the range limitation imposed by i

OMa Part 6,4.6.1.2(a) (3 times the reference value or less) is not met by these hand held tachometers.

However, 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 i0.07 percent of the full range which is better than the accuracy required by 4.6.1.1 (i.e. i2 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 2 percent.

Therefore, the proposed range and accuracy results in measurement with

, accuracy better than Code requirements and will provide reasonable I assurance of component operational readiness.

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INSERVICE TESTING PROGRAM !

I l RELIEF REQUEST RP-04 Continued -

ALTERNATE TEST: RCIC pump / turbine speed will be measured via available tachometers l l identified in the Basis For Relief.

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l COOPER NUCLEAR STATION l THIRD INTERVAL INSERVICE TESTING PROGRAM l

! i RELIEF REQUEST RP-05

. PUMP: Service Water, SW-P-A, B, C, and D CLASS: 3 FUNCTION: Provide cooling for essential systems and components.

i J REQUIRED l l TEST: The alert range for differential pressure for vertical line shaft pumps j shall be 0.93 to <0.95AP, [OMa Part 6, Table 3b].

l BASIS FOR l RELIEF: 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 ,

l allowed to degrade to 0.90AP, before corrective action was required. l l When this condition was reached the pump lift was adjusted, the baseline .

l was re-established, and the pump was returned to service. The OM Code requires corrective action when the differential pressure is

< 0.95 AP,. ;

l The average differential pressure after a lift adjustment is 63 psid. The required action level would be < 58.6 psid. Howevr the Service Water pumps can meet their design basis required flows 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 3%. This difference is insignificant when compared to the cost of manpower required to perform pump maintenance without i

providing a compensating increase in the level of quality or safety. )

ALTERNATE TEST: The low alert level for the Service Water pumps differential pressure 1 l will be 0.90 to <0.93AP,. The low required action level shall be l l

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

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l D. Augmented Pump Relief Requests RR No. Description i

ARP-01 Elevated Release Point Sump Pump - Alternate Test i

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AUGMENTED RELIEF REQUEST ARP-01 PUMP: RW-P-Z1 and RW-P-Z2 l

l CLASS: A l

FUNCTION: Elevated release point sump 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 l operation.

REQUIRED l TEST: An inservice test shall be run on each pump, nominally every 3 months, l except as provided in OMa Part 6, paras. 5.3,5.4, and 5.5. Perform

! operational readiness testing quarterly.

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l BASIS FOR l RELIEF: 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 i 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.

ALTERNATE TEST: The time (TM) to pump 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 i

range will be <0.90 or > 1.10 TM,. .

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i l COOPER NUCLEAR STATION j THIRD INTERVAL l INSERVICE TESTING PROGRAM IV. TESTING PROGRAM FOR VALVES :

i A. Description The Valve Summary Listing,Section V, identifies the valves included in the CNS IST Program, the inservice test quantities to be measured, the test requirements, the test frequencies, references to cold shutdown justifiestions, refueling outage justifications, valve relief requests, and other pertinent information.

B. Cold Shutdown Testing For those valves designated to be tested at cold shutdown, testing will commence as 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 sufficiently 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. Furthermore, 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 l l 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 stated in specific cold shutdown justifications or relief requests.

C. Limiting Values of Full-Stroke Times Where stroke time measurement of power-operated valves is required, the limiting 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 Specifications or safety analysis stroke time limits will be used in lieu of the calculated limiting values of full-stroke time if they are more 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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INSERVICE TESTING PROGRAM l !

D. Reference Values Stroke time reference values are determined from the results of the previous interval's inservice tests. Reference 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 i' valve or its contral system, a new reference value shall be determined, or the previous l values (s) recon 6rmed by an inservice test run prior to declaring the valve operable. l

. 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 documented in the record of tests.

E. Instrumentation Requirements OMa Part 10 does not stipulate instrument accuracy or range requirements for ;

instmments used in valve testing. Any instruments used will be selected to ensure valid l test results.

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

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l Passive valves are denned 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 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.

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l 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 !

. 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 i 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 l 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.

H. 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.

l I. Water Sealed Valves Valves on piping systems that penetrate the torus and terminate below the minimum water level of the suppression pool are considered water sealed. This seal is a barrier 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 sealed.

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

l The discharge lines for several relief valves are directed to the suppression pool and are l also water sealed. These relief valves are located in systems which are normally in j Revision 1 Section IV Page 3 of 5 l

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8 operation following an accident, such as the Core Spray and Residual Heat 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 sealed, they do not present a ;

credible leakage path from the primary containment to the environment and no :

additional leak rate testing is performed. j J. Check Valve Testing !

Only valves that have a specified maximum required accident flow are su'oject to i position 1 of Generic Letter 89-04. Either the flow through the valve is measured or other quantitative parameters with acceptance criteria are monitored to demonstrate '

required flow through the valve. Check valves that do not have a specified maximum !

required accident flow 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, -l manually exercised, and inspected in lieu of flow (or flow 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 protection 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.

l 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 j

evaluated for generic concerns; however, additional testing of valves outside the sample !

i- group shall not be required unless the evaluation determines that the operability of other valves may be m question.

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1 Per NUREG-1482, Section 4.3.6, when the test of a safety or relief valve fails due to I out-of-tolerance set point, an adjustment of the set point is an ecceptable 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 l

third interval program in accordance with OM Part 1, para.1.3.4.2. The replacement rupture discs will be receipt inspected in accordance with plant procedures.

l L. Vacuum Breaker Testing l

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 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.

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V. VALVE

SUMMARY

LISTING l A. Notations -

The following notations are used in the valve summary tables:

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

VALVE CIC: The component identification code.

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

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

ISI CLASS: The ASME Inservice Inspection (ISI) classification of the component. Augmented components are classified "A".

IST CAT: The category or categories assigned to the valve based on the defm' itions in OMa Part 10, Section 1.4. 4

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VALVE SIZE: The nominal size of the component in inches. 1 VALVE TYPE: The component body design as indicated by the following abbreviations:

l ANG Angle BAL Ball BTF Butterfly CK-B Ball 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 GB Globe Revision 1 Section V Page 1 of 153

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GT Gate RD Rupture Disk '

RV Relief / Safety SOV Solenoid Valve S-CK Stop Check '

SHR Squib ACT TYPE: The type of actuator as indicated by the following abbreviations:

j AO Air Operated l EX Explosive Charge ,

HO Hydraulic Operated l MA Manual MO Motor Operated SA Self Actuated SO Solenoid Operated PA Pilot Actuated NORMAL POS: The normal position of the valve, specified as follows:

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

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l U-1 Leakage test in accordance with the CNS Appendix J Program U-2 Excess flow check valve leakage test in accordance with the CNS Technical Specifications LT-1 Leakage test of air / nitrogen accumulator check valves LT-2 Leakage tests other than those already specified

. FSO Full stroke exercise test to the open position ;

l (includes stroke time measurement except for

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FSC Full stroke exercise test to the closed position -

(includes stroke time measurement except for check valves and manual 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 measurement unless otherwise noted) :

PIT Position indication test l RD Rupture Disc test per OM .

RVT Set point test of safety / relief valves per OM-1 EX Explosive valve test VBT Vacuum breaker testing per OM-1 i i

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

Q Quarterly test CS Cold shutdown RF Refueling outage l 2Y At least once every 2 years 5Y At least once every five years per OM-1 10Y At least once every ten years per OM-1 l

I 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 Justifications are designated ROJ-XX: Relief Requests are ,

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

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SUMMARY

TABLES SYSTEM: CONTROL ROD DRIVE (CRD)

VALVE CIC P&lD P&ID 151 IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ CRD-AOV-CV32A 2039 113 2 B 1 GB AO O FSC Q SCRAM DISCilARGE VOLUME FST Q ISOLATION VALVE PIT 2Y CRD-AOV-CV32B 2039 114 2 B 1 GB AO O FSC Q SCRAM DISCHARGE VOLUME FST Q ISOLATION VALVE PIT 2Y CRD-AOV-CV33 2039 112 2 B 2 GB AO O FSC Q SOUTil SCRAM DISCIIARGE FST Q VOLUME ISOLATION VALVE PIT 2Y CRD-AOV-CV34 2039 114 2 B 2 GB AO O FSC Q NORTil SCRAM DISCIIARGE FST Q VOLUME ISOLATION VALVE PIT 2Y CRD-AOV-CV126 2039 C10 2 B 1 DIA AO C FSO RF SCRAM OUTLET, (TYP. OF 137) FST RF RV-02 CRD-AOV-CV127 2039 BIO 2 B 3/4 DIA AO C FSO RF SCRAM OUTLET, (TYP. OF 137) FST RF RV-02 CRD-CV-13CV 2039 A9 I A/C 3/4 CK-P SA O U-l RF CRD WATER TO REACTOR FSC RF RECIRCULATION PUMP A. ROJ-01 CRD-CV-14CV 2039 B9 1 A/C 3/4 CK-P SA O U-l RF CRD WATER TO REACTOR '

FSC RF RECIRCULATION PUMP A. ROJ-01 CRD-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, ROJ-01 CRD-CV-16CV 2039 B8 1 A/C 3/4 CK-P SA O U-l RF CRD WATER TO REACTOR FSC RF RECIRCULATION PUMP B. ROJ4)I Revision 1 Section V Page 4 of 153

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SUMMARY

TABLES SYSTEM: CONTROL ROD DRIVE (CRD)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ CRD-CV-25CV 2039 B4 A A/C 1 1/2 CK-S SA O LT-2 RF CRD SYSTEM ISOLATION CIIECK FSC CS VALVE, ACSJ-01 CRD-CV-26CV 2039 B4 A A/C 1 1/2 CK-S SA O LT-2 RF CRD SYSTEM ISOLATION CilECK FSC CS VALVE, ACSJ-01 CRD-CV-CVI14 2039 Bl1 2 C 3/4 CK-B SA O FSO RF SCRAM OUTLET CllECK VALVE, (TYP. OF 137) RV-02 CRD-CV-CVI15 2039 D9 2 C 1/2 CK-B SA O FSC RF SCRAM INLET CIIECK VALVE, (TYP. OF 137) RV-03 CRD-CV-138 2039 C9 2 C 1/2 CK-B SA O FSC Q COOLING / SCRAM IIEADER (TYP. OF 137) CIIECK VALVE, RV-Of CRD-SOV-SO120 2039 BIO 2 B 1/4 SOV SO C FSC Q CRD WITIIDRAWAL EXIIAUST (TYP. OF 137) FST Q VALVE, RV-05 CRD-SOV-SO121 2039 BIO 2 B 1/4 SOV SO C FSC Q CRD INSERT EXIIAUST (TYP. OF 137) FST Q VALVE, RV-05 CRD-SOV-SO122 2039 BIO 2 B 1/4 SOV SO C FSC Q CRD WITilDRAWAL VALVE, EP. OF 137) FST Q RV4)5 CRD-SOV-sol 23 7339 B10 2 B 1/4 SOV SO C FSC Q CRD INSERT VALVE, AVP OF 117) _

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES

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l SYSTEM: CORE SPRAY (CS)

VALVE CIC P&lD

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ CS-CV-10CV 2015 F4 2 C 12 CK-S SA C FSO Q CS PUMP A DISCHARGE CHECK CS-CV-1 ICV 2015 D4 2 C 12 CK-S SA C FSO Q CS PUMP B DISCIIARGE CIIECK CS-CV-12CV 2045 G5 A C 2 CK-P SA C FSC Q CS LOOP A OUTBOARD PRESSURE MAINTENANCE SUPPLY, RV-06 CS-CV-13CV 2045 G5 2 C 2 CK-P SA C FSC Q CS LOOP A INBOARD PRESSURE MAINTENANCE SUPPLY, RV-06 CS-CV-14CV 2045 D5 A C 2 CK-P SA C FSC Q CS LOOP B OUTBOARD PRESSURE MAINTENANCE SUPPLY, RV-06 CS-CV-15CV 2445 DS 2 C 2 CK-P SA C FSC Q CS LOOP B INBOARD PRESSURE ,

MAINTENANCE SUPPLY, RV-06 CS-CV-18CV 2045 C6 i A/C 10 CK-S SA C U-l RF CS SYSTEM A TESTABLE CHECK LT-2 RF CSJ-01 FSO CS FSC CS PIT 2Y CS-CV-19CV 2045 B6 1 A/C 10 CK-S SA C U-l RF CS SYSTEM B TESTABLE CHECK I

LT-2 RF CSJ-01 FSO CS FSC CS PIT 2Y CS-MOV-M05A 2015 E4 2 B 3 GT MO O FSO Q CS PUMP A MINIMUM FLOW FSC Q RECIRCULATION ISOLATION PIT 2Y Revision i Section V Page 6 of 153

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SUMMARY

TABLES j SYSTEM: CORE SPRAY (CS)

P&ID I ' ^ ^ ^ NOTES /DESCRIM10N VALVE CIC CLASS CAT SIZE TYPE TYPE COOR POS RQMT FREQ CS-MOV-M05B 2M5 IM 2 B 3 GT MO O FSO Q CS PUMP B MINIMUM FLOW FSC Q RECIRCULATION ISOLATION PIT 2Y CS-MOV-MO7A 2M5 F2 2 B 14 GT MO O FSO Q CS PUMP A SUCTION FSC Q PIT 2Y CS-MOV-MO7B 2M5 D2 2 B 14 GT MO O FSO Q CS PUMP B SUCTION FSC Q PIT 2Y CS-MOV-MOI 1 A 2045 F5 2 B 10 GT MO O FSO Q LOOP A INJECTION TilROTTLE PIT 2Y CS-MOV-MOIIB 2045 DS 2 B 10 GT MO O FSO Q IDOP B INJECTION TIIROTTLE PIT 2Y CS-MOV-MO12A 2045 F6 i A 10 GT MO C 13-1 RF LOOP A INJECTION BLOCK LT-2 RF FSO Q FSC Q PIT 2Y CS-MOV-MO12B 2M5 D6 i A 10 GT MO C 13-1 RF LOOP B INJECTION BLOCK LT-2 RF FSO Q FSC Q PIT 2Y CS-MOV-MO26A 2M5 F5 2 B 10 GB MO C PIT 2Y CS PUMP A TEST LINE PASSIVE l ISOLATION Revision 1 Section V Page 7 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: CORE SPRAY (CS)

VALVE CIC P&lD

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ CS-MOV-MO26B 2M5 C5 2 B 10 GB MO C PIT 2Y CS PUMP B TEST LINE PASSIVE ISOLATION CS-RV-10RV 2M5 F2 2 C 3/4 RV SA C RVT 10Y CS PUMP A SUCTION RELIEF CS-RV-11RV 2045 F4 2 C 2 RV SA C RVT 10Y CS PUMP A DISCIIARGE RELIEF CS-RV-12RV 2NS C3 2 C 3/4 RV SA C RVT 10Y CS PUMP B SUCTION RELIEF CS-RV-13RV 2045 C4 2 C 2 RV SA C RVT 10Y CS PUMP B DISCIIARGE RELIEF Revision 1 Section V Page 8 of 153

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SUMMARY

TABLES SYSTEM: DEMINERALIZED WATER SYSTEM (DW)

VALVE CIC P&lD PalD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ DW-V-133 2029 G8 2 A 4 GT MA C U-1 RF PASSIVE DRYWELL OUTBOARD SUPPLY VALVE DW-V-219 2029 G8 2 A 4 GT MA C U-l RF PASSIVE DRYWELL INBOARD SUPPLY VALVE Revision 1 Section V Page 9 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR (DG)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ DG-AOV-MBI KSV- C2 A B 30 BFL AO C FSO Q DGl MUFFLER BYPASS VALVE, 96-3 FST Q ARV-03 DG-AOV-MB2 KSV- C2 A B 30 BFL AO C FSO Q DG2 MUFFLER BYPASS VALVE, 96-3 FST Q ARV-03 Revision 1 Section V Page 10 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR DIESEL OIL (DGDO)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CIASS CAT SIZE TYPE TYPE POS RQMT FREQ DGDO-CV-10CV 2011 A8 A C 2 CK-P SA C FSO Q DGDO TRANSFER PUMP A S11 1 DISCIIARGE DGDO-CV-IICV 2011 A10 A C 2 CK-P SA C FSO Q DGDO TRANSFER PUMP B SH I DISCIIARGE DGDO-CV-12CV 2011 A4 A C 2 CK-P SA C FSO Q DGDO DAY TANK 1 INLET Sil 1 FSC Q DGDO-CV-13CV 2011 B4 A C 2 CK-P SA C FSO Q DGDO DAY TANK 2 INLET SII I FSC Q DGDO-FOV-FLTV10 2077 til A C 3/4 FOV SA O/C FSO Q DGDO DAY TANK 1 INLET FLOAT FSC Q VALVE, ARV-01 DGDO-FOV-FLTVII 2077 116 A C 3/4 FOV SA O/C FSO Q DGDO DAY TANK 2 INLET FLOAT FSC Q VALVE, ARV-01 DGDO-RV-10RV 2077 112 A C 3/4 RV SA C RVT 10Y DGDO PUMP 1 SUCTION RELIEF DGDO-RV-IIRV 2077 115 A C 3/4 RV SA C RVT 10Y DGDO PUMP 2 SUCTION RELIEF DGDO-SOV- 2077 111 A B 3/4 SOV SO O/C FSO Q DGDO DAY TANK 1 INLET FUEL SSV5028 FSC Q SAFETY VALVE, ARV-01 FST Q DGDO-SOV- 2077 11 6 A B 3/4 SOV SO O/C FSO Q DGDO DAY TANK 2 INLET FUEL SSV5029 FSC Q SAFETY VALVE, ARV-01 FST Q Revision 1 Section V Page !I of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR STARTING AIR (DGSA)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIM10N COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ DGSA-AOV-AV5 117.10 E3 A B 2 1/2 GB AO C FSO Q DG-1 LEFT BANK STARTING AIR

-IC-09 FSC Q VALVE, ARV-02 FST Q DGSA-AOV-AV6 117.10 E3 A B 2 1/2 GB AO C FSO Q DG-2 LEFT BANK STARTING AIR

-IC-09 FSC Q VALNE, ARV-02 FST Q DGSA-AOV-AV7 117.10 El A B 2 1/2 GB AO C l' FSO Q DG-1 RIGIIT BANK STARTING AIR

-IC-09 ' 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 RIGilT BANK STARTING AIR

-IC-09 FSC Q VALVE, ARV-02 FST Q DGSA-CV-10CV 2077 D8 A C 2 CK-L SA C FSO Q STARTING AIR COMPRESSOR 1A FSC Q DISCIIARGE DGSA-CV-llCV 2077 D8 A C 2 CK-L SA C FSO Q STARTING AIR COMPRESSOR IB ,

FSC Q DISCHARGE DGSA-CV-12CV 2077 DIO A C 2 CK-L SA C FSO Q STARTING AIR COMPRESSOR 2B FSC Q DISCHARGE DGSA-CV-13CV 2077 DIO A C 2 CK-L SA C FSO Q STARTING AIR COMPRESSOR 2A FSC Q DISCHARGE DGSA-CV-14CV 2077 C8 A C 2 CK-S SA C FSO Q AIR RECEIVER I A INLET, ACSJ-02 FSC CS DGSA-CV-15CV 2077 C8 A C 2 CK-S SA C FSO Q AIR RECEIVER IB INLET. ACSI-02 FSC CS Revision 1 Section V Page 12 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: DIESEL GENERATOR STARTING AIR (DGSA)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ DGSA-CV-16CV 2077 C10 A C 2 CK-S SA C FSO Q AIR RECEIVER 2A INLET, ACSJ-02 FSC CS DGSA-CV-17CV 2077 C10 A C 2 CK-S SA C FSO Q AIR RECEIVER 2B INLET ACSJ-02 FSC CS DGSA-CV-18CV 2077 B7 A C 3 CK-S SA C FSO Q AIR RECEIVER 1 A OUTLET FSC Q DGSA-CV-19CV 2077 B8 A C 3 CK-S SA C FSO Q AIR RECEIVER IB OUTLET FSC Q DGSA-CV-20CV 2077 B10 A C 3 CK-S SA C FSO Q AIR RECEIVER 2A OUTET FSC Q DGSA-CV-21CV 2077 Bil A C 3 CK-S SA C FSO Q AIR PECEIVER 2B OUTLET FSC Q DGSA-CV-32CV 117.1 F5 A C I/4 CK-S SA C FSO Q DG1 EFT BANK AIR START 0-IC- FSC Q SHUTTLE VALVE 09 DGSA-CV-33CV i17.1 F1 A C 1/4 CK-S SA C FSO Q DGl RIGHT BANK AIR START 0-IC- FSC Q SHUTTE VALVE 09 DGSA-CV-34CV 117.1 F5 A C 1/4 CK-S SA C FSO Q DG2 EFT BANK AIR START 0-IC- FSC Q SHUTTE VALVE 09 DGSA-CV-35CV 117.1 F1 A C 1/4 CK-S SA C FSO Q DG2 RIGHT BANK AIR START 0-IC- FSC Q SHUTTLE VALVE 09 Revision 1 Section V Page 13 of 153

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SUMMARY

TABLES SYSTEM: DIESEL GENERATOR STARTING AIR (DGSA)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ DGSA-SOV-SPV1 117.10 F5 A B 1/2 GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC-09 FSC Q DGSA-AOV-AVS (DG1 LEFT BANK).

FST Q ARV-02 DGSA-SOV-SPV2 117.10 F5 A B 1/2 GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC-09 FSC Q DGSA-AOV-AV6 (DG2 LEIT BANK),

FST Q ARV-02 DGSA-SOV-SPV3 117.10 F1 A B 1/2 GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC-09 FSC Q DGSA-AOV-AV7 (DG1 RIGIIT BANK),

FST Q ARV-02 DGSA-SOV-SPV4 117.10 F1 A B 1/2 GB SO C FSO Q SOLENOID PILOT VALVE FOR

-IC-09 FSC Q DGSA-AOV-AV8 (DG2 RIGIIT BANK),

FST Q ARV-02 DGSA-RV-10RV 2077 F8 A RV 1 RV SA C RVT 10Y DGSA AIR COMPRESSOR I A RELIEF DGSA-RV-IIRV 2077 F9 A RV 1 RV SA C RVT 10Y DGSA AIR COMPRESSOR IB RELIEF DGSA-RV-12RV 2077 F10 A RV 1 RV SA C RVT 10Y DGSA AIR COMPRESSOR IC REUEF DGSA-RV-13RV 2077 F11 A RV 1 RV SA C RVT 10Y DGSA AIR COMPRESSOR ID REUEF DGSA-RV-14RV 2077 B7 A RV 1 RV SA C RVT 10Y DGSA AIR RECEIVER 1A REUEF DGSA-RV-15RV 2077 B8 A RV I RV SA C RVT 10Y DGSA AIR RECEIVER IB RELIEF DGSA-RV-16RV 2077 BIO A RV 1 RV SA C RVT 10Y DGSA AIR RECEIVER IC REUEF DGSA-RV-17RV 2077 Bil A RV 1 RV SA C RVT 10Y DGSA AIR RECEIVER ID REUEF Revision 1 Section V Page 14 of 153

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SUMMARY

TABLES SYSTEM: IIIGH PRESSURE COOLANT INJECTION (HPCI)

VALVE CIC P&ID I ^ ^ ^ NOTES /DESCRIlrTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IIPCI-AOV-AO42 20$1 G5 2 B 1 GB AO O FSC Q STEAM LINE DRIPLEG DRAIN FST Q '

PIT 2Y HPCI-AOV-A070 2044 E9 2 A 1 BAL AO C U-l RF HPCI EXIIAUST BOOTLEG DRAIN FSC Q INBOARD FST Q PIT 2Y llPCI-AOV-AO71 2014 E9 2 A 1 BAL AO C U-l RF HPCI EXIIAUST BOOTLEG DRAIN FSC Q OUTBOARD FST Q PIT 2Y llPCI-AOV-PCV50 2044 G4 2 B 2 GB AO O PSO Q IIPCI AUXIUARY COOUNG SUPPLY FSO CS PRESSURE CONTROL, FST CS CSJ-03 IIPCI-CV-10CV 2044 J3 2 C 16 CK-S SA C FSO Q ECST SUPPLY TO HPCI PUMP, FSC CS CSJ-Il IIPCI-CV-1 ICV 2044 1110 2 C 16 CK-S SA C FSO RF IIPCI PUMP SUCTION FROM FSC RF SUPPRESSION POOL, ROJ-02 HPCI-CV-13CV 2044 HS 2 C 4 CK-S SA C FSO Q HPCI AUXILIARY COOUNG RETURN FSC Q llPCI-CV-14CV 2044 115 2 C 2 CK-P SA C FSC Q HPCI CONDENSATE PUMP DISCHARGE TO AUXILIARY COOLING RETURN t

Revision 1 Section V Page 15 of 153

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SUMMARY

TABLES SYSTEM: IIIGH PRESSURE COOLANT INJECTION (HPCI)

VALVE CIC P&ID

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IIPCI-CV-15CV 2M4 D9 2 A/C 20 CK-S SA C U-l RF llPCI TURBINE EXIIAUST, ROJ-03 FSO Q FSC RF flPCI-CV-16CV 2M4 F9 2 C 2 CK-P SA C FSC RF IIPCI TURBINE EXIIAUST DRAIN TO SUPPRESSION POOL, ROJ-03 IIPCI-CV-17CV 2044 D6 2 C 4 CK-S SA C PSO Q IIPCI PUMP MINIMUM FLOW LINE, FSO RF ROJ-03, ROJ-20 FSC RF IIPCI-CV-18CV 2044 B8 2 C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO IIPCI SYSTEM, RV-07 IIPCI-CV-19CV 2044 B8 A C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO IIPCI SYSTEM, RV-07 IIPCI-CV-24CV 2M4 E10 2 C 3 CK-S SA C VBT RF HPCI VACUUM BREAKER, RV-14 HPCI-CV-25CV 2044 El1 2 C 3 CK-S SA C VBT RF HPCI VACUUM BREAKER, RV-14 IIPCI-CV-26CV 2044 E10 2 C 3 CK-S SA C VBT RF HPCI VACUUM BREAKER, RV-14 IIPCI-CV-27CV 2M4 El1 2 C 3 CK-S SA C VBT RF HPCI VACUUM BREAKER, RV-14 HPCI-CV-29CV 2M4 C9 1 A/C 14 CK-S SA C U-l RF INJECTION CHECK VALVE, CSJ-02 FSO CS FSC CS PIT 2Y IIPCI-MOV-M014 2041 G3 2 B 10 GT MO C FSO Q STEAM SUPPLY TO TURBINE PIT 2Y Revision 1 Section V Page 16 of 153

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SUMMARY

TABLES SYSTEM: IIIGH PRESSURE COOLANT INJECTION (IIPCI)

VALVE CIC P&ID

' ^ ^ ^ NOTES /DESCRII* TION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IIPCI-MOV-MOI 5 2041 D5 1 A 10 GT MO O U-l RF STEAM SUPPLY INBOARD FSO Q ISOLATION FSC Q PIT 2Y llPCI-MOV-MOl6 2041 D4 1 A 10 GT MO O U-l RF STEAM SUPPLY OUTBOARD FSO Q ISOLATION FSC Q PIT 2Y llPCI-MOV-MOl7 2044 J3 2 B 16 GT MO O FSO Q PUMP SUCTION FROM EMERGENCY FSC Q CONDENSATE STORAGE TANK PIT 2Y IIPCI-MOV-MOl9 2044 C8 2 B 14 .GT MO C FSO Q llPCIINJECTION PIT 2Y llPCI-MOV-MO20 20t4 C8 2 B 14 GT MO O FSO Q IIPCI PUMP DISCIIARGE PIT 2Y IIPCI-MOV-MO21 2044 D3 2 B 10 GB MO C PIT 2Y llPCI PUMP TEST BYPASS TO EMERGENCY CONDENSATE STORAGE TANK llPCI-MOV-MO24 2044 E3 A B 10 GT MO O PIT 2Y llPCI PUMP TEST BYPASS REDUNDANT SIIUTOFF IIPCI-MOV-MO25 2044 D7 2 B 4 GB MO C FSO Q IIPCI PUMP MINIMUM FLOW FSC Q BYPASS LINE ISOLATION PIT 2Y l Revision 1 Section V Page 17 of 153

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SUMMARY

TABLES SYSTEM: IIIGH PRESSURE COOLANT INJECTION (HPCI)

VALVE CIC P&lD

^ ^ NOTES /DESCRilrTION !

COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IIPCI-MOV-MO58 2054 GIO 2 B 16 GT MO C FSO Q IIPCI PUMP SUCTION FROM FSC Q SUPPRESSION POOL PIT 2Y IIPCI-RD-S241 2Gt4 DS 2 D 16 RD SA C RD SY EXIIAUST LINE RUPTURE DISK IIPCI-RV-10RV 2014 J3 2 C 1 RV SA C RVT 10Y llPCI PUMP SUCTION RELIEF llPCI-RV-12RV 2014 G5 2 C 1 RV SA C RVT 10Y IIPCI AUXILIARY COOLING WATER ,

SUPPLY IIPCI-SOV-SSV64 2G14 F4 2 B 1 SOV SOV C FSC RF IIPCI EXIIAUST DRIP LEG DRAIN, FST RF RV-08 IIPCI-SOV-SSV87 2044 F4 2 B 1 SOV SOV C FSC RF IIPCI TURBINE DRIP LEG DRAIN, FST RF RV-08 IIPCI-V-44 2044 D9 2 C 20 S-CK MA O LI-l RF llPCI TURBINE EXIIAUST TO FSO Q SUPPRESSION POOL ISOLATION, FSC RF ROJ-Gi MPCI-V-50 2044 F9 2 C 2 S-CK MA O FSC RF TURBINE DRAIN TO SUPPRESSION POOL ISOLATION, ROJ-OS Revision 1 Section V Page 18 of 153

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SUMMARY

TABLES SYSTEM: IIEATING AND VENTILATION (HV)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ ilV-AOV-257AV 2020 D4 A B 72 IN BTF AO O FSC Q REACTOR BUILDING VENTILATION FST Q OUTBOARD SUPPLY PIT 2Y IIV-AOV-259AV 2020 B12 A B 72 IN BTF AO O FSC Q REACTOR BUILDING VENTILATION FST Q INBOARD EXIIAUST PIT 2Y 0

llV-AOV-261 AV 2020 B12 A B 72 IN BTF AO O FSC Q REACTOR BUILDING VENTILATION FST Q INBOARD EXIIAUST PIT 2Y llV-AOV-263AV 2020 E9 A B 72 IN BTF AO O FSC CS REACTOR MG SET l A VENTILATION FST CS OUTBOARD SUPPLY. ACSI-03 PIT 2Y IIV-AOV-265AV 2020 E9 A B 72 IN BTF AO O FSC CS REACTOR MG SET IB VENTILATION FST CS OUTBOARD SUPPLY, ACSJ-03 FIT 2Y llV-AOV-267AV 2020 DII A B 72 IN BTF AO O FSC CS REACTOR MG SET l A VENTILATION FST CS INBOARD EXIIAUST, ACSJ-03 PIT 2Y llV-AOV-269AV 2020 El1 A B 72 IN BTF AO O FSC CS REACTOR MG SET IB VENTILATION FST CS OUTBOARD EXilAUST, ACSJ-03 PIT 2Y llV-AOV-270AV 2019 B2 A B 20 IN BTF AO O FSC Q CONTROL RM IIVAC INLET VALVE Sil 1 FST Q IIV-AOV-27I AV 2019 Al A B 12 IN BTF AO C FSO Q CONTROL RM llVAC EMERGENCY Sil 1 FST O BYPASS Revision 1 Section V Page 19 of 153

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SUMMARY

TABLES SYSTEM: IIEATING AND VENTILATION (IIV)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IIV-AOV-272AV 2019 B6 A B 8 IN BTF AO O FSC Q CONTROL RM PANTRY EXIIAUST Sli I FST Q ISOLATION llV-MOV-258MV 2020 B12 A B 48 IN BTF MO O FSC Q REACTOR BUILDING VENTILATION PIT 2Y OUTBOARD EXIIAUST IIV-MOV-260MV 2020 B12 A B 48 IN BTF MO O FSC Q REACTOR BUILDING VENTILATION PIT 2Y OUTBOARD EXIIAUST llV-MOV-262MV 20'0 2 E9 A B 48IN BTF MO O FSC CS RR MG SET 1 A VENTILATION PIT 2Y INBOARD SUPPLY, ACSJ-03 IIV-MOV-264MV 2020 E9 A B 48 IN BTF MO O FSC CS RR MG SET IB VENTILATION PIT 2Y INBOARD SUPPLY, ACSJ43 IIV-MOV-266MV 2020 D9 A B 48 IN BTF MO O FSC CS RR MG SET I A VENTIIATION PIT 2Y OUTBOARD EXHAUST. ACSJ-03 IIV-MOV-268MV 2020 ElI A B 48 IN BTF MO O FSC CS RR MG SET IB VENTILATION PIT 2Y OUTBOARD EXIIAUST, ACSJ43 IIV-MOV-272MV 2020 D4 A B 72 IN BTF MO O FSC Q REACTOR BUILDING VENTILATION PIT 2Y INBOARD SUPPLY Revision 1 Section V Page 20 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IA-CV-17CV 2010 E8 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-71A ACCUMULATOR Sil 2 FSC RF SUPPLY, AROJ-01 IA-CV-18CV 2010 E8 A A/C I/2 CK-L SA O LT-1 2Y MS-RV-71B ACCUMULATOR Sil 2 FSC RF SUPPLY. AROJ-01 i IA-CV-19CV 2010 D8 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-71C ACCUMULATOR Sil 2 FSC RF SUPPLY. AROJ-01 IA-CV-20CV 2010 D9 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-71E ACCUMULATOR Sil 2 FSC RF SUPPLY, AROJ-01 IA-CV-21CV 2010 E9 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-71G ACCUMULATOR Sil 2 FSC RF SUPPLY, AROJ-01 IA-CV-22CV 2010 E9 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-7111 ACCUMULATOR Sli 2 FSC RF SUPPLY, AROJ-01 IA-CV-28CV 2010 F9 A AIC If2 CK-L SA O LT-1 2Y MSIV-A080A SUPPLY Sil 2 FSC RF AROJ-02 IA-CV-29CV 2010 F8 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-AO80B SUPPLY Sil 2 FSC RF AROJ-02 IA-CV-30CV 2010 F8 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-AO80C SUPPLY Sil 2 FSC RF AROJ-02 ,

IA-CV-31CV 2010 F9 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-AO80D SUPPLY SH 2 FSC RF AROJ-02 IA-CV-32CV 2010 D12 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-AO86A SUPPLY l SH 2 FSr RF AROJ-02 Revision i Section V Page 21 of 153

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SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IA-CV-33CV 2010 D12 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-AO86B SUPPLY Sil 2 FSC RF AROJ-02 IA-CV-34CV 2010 D12 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-A086C SUPPLY Sli 2 FSC RF AROJ-02 IA-CV-35CV 2010 E12 A A/C 1/2 CK-L SA O LT-1 2Y MSIV-A086D SUPPLY Sil 2 FSC RF AROJ-02 IA-CV-36CV 2010 E8 A A/C 1/2 CK-L SA O LT-1 2Y MS-RV-71D ACCUMULATOR Sil 2 FSC RF SUPPLY, AROJ-01 IA-CV-37CV 2010 E10 A A/C I/2 CK-L SA O LT-1 2Y MS-RV-71F ACCUMULATOR Sil 2 FSC RF SUPPLY, AROJ-01 IA-CV-50CV 2010 115 A A/C 1/4 CK-L SA O LT-1 2Y ACCUMULATOR AO-82 IA CIIECK Sil 2 FSC Q VALVE IA-CV-51CV 2010 115 A A/C 1/4 CK-L SA O LT-1 2Y ACCUMULATOR AO-83 IA CilECK Sil 2 FSC Q VALVE IA-CV-52CV 2010 116 A A/C I/4 CK-L SA O LT-1 2Y ACCUMULATOR AO94 IA CIIECK Sil 2 FSC Q VALVE IA-CV-53CV 2010 116 A A/C 1/4 CK-L SA O LT-1 2Y ACCUMULATOR AO95 IA CHECK Sil 2 FSC Q VALVE lA-CV-54CV 2010 A7 A A/C I/4 CK-L SA O LT-1 2Y llV-AOV-257AV ACCUMULATOR Sli 2 FSC CS CllECK. ACSJ-OS 1A-CV-55CV 2010 A6 A A/C I/4 CK-L SA O LT-1 2Y IIV-AOV-259AV ACCUMULATOR Sil 2 FSC- CS CilECK. ACSI-G1 Revision 1 Section V Page 22 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM 1 VALVE

SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIFTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ IA-CV-56CV 2010 A7 A A/C 1/4 CK-L SA O LT-1 2Y llV-AOV-261AV ACCUMULATOR Sil 2 FSC CS CIIECK, ACSI-G4 IA-CV-57CV 2010 B9 A A/C l/4 CK-L SA O LT-1 2Y llV-AOV-263AV ACCUMUIATOR Sil 2 FSC CS CIIECK. ACSI-G4 IA-CV-58CV 2010 B9 A A/C 1/4 CK-L SA O LT-1 2Y llV-AOV-265AV ACCUMULATOR Sil 2 FSC CS CIIECK. ACSJ-04 IA-CV-59CV 2010 B9 A A/C 1/4 CK-L SA O LT-1 2Y llV-AOV-267AV ACCUMULATOR Sil 2 FSC CS CIIECK. ACSJ-Of IA-CV-60CV 2010 A8 A A/C 1/4 CK-L SA O LT-1 2Y llV-AOV-269AV ACCUMULATOR Sil 2 FSC CS CIIECK. ACSJ-G4 IA-CV-65CV 2010 F8 2 A/C 2 CK-L SA O U-l RF X-22 INBOARD ISOLATION, Sil 2 FSC RF ROJ-05 IA-CV-78CV 2010 F8 2 A/C 2 CK-L SA O U-l RF X-22 OUTBOARD ISOLATION, SII 2 FSC RF ROJ-05 IA-CV-IllCV 2010 Ell A A/C I/4 CK-L SA O LT-1 2Y IA-271 AV ACCUMULATOR CIIECK, Sil 1 FSC CS ACSJ-Of PC-V-559 2028 D8 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-560 2028 D8 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-561 2028 C8 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOIATION PC-V-562 2028 C8 2 A 1 GT MA C U-l RF PASSIVE M ANUAL ISOLATION Revision 1 Section V Page 23 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC P&ID l-Aii) ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIP110N COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ PC-V-563 2028 C8 2 A 1 GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-564 2028 C8 2 A 1 GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-565 2028 D8 2 A I GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-566 2028 D8 2 A I GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-569 2027 J3 2 A 1 GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-570 2027 J3 2 A I/2 GB MA C U-l RF PASSIVE M ANUAL ISOLATION PC-V-571 2027 J3 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-572 2027 13 2 A I/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-573 2027 J4 2 A 1 GT MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-574 2027 J4 2 A 1/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-575 2027 14 2 A I GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-576 2027 J4 2 A I/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-577 2027 J5 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-578 2027 15 2 A 1/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-579 2027 15 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-580 2027 15 2 A 1/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-581 2027 16 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION Revision i Section V Page 24 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: INSTRUMENT AIR (IA)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ PC-V-582 2027 16 2 A 1/2 GB MA C U-l RF PASSIVE MANUAL ISOIATION PC-V-583 2027 16 2 A 1 GB MA C U-1 RF PASSIVE MANUAL ISOLATION PC-V-584 2027 16 2 A I/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-585 2027 17 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-586 2027 J7 2 A I/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-587 2027 17 2 A 1 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-588 2027 J7 2 A I/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION PC-V-589 2027 18 2 A 1 GB MA C U-1 RF PASSIVE MANUAL ISOLATION PC-V-590 2027 38 2 A 1/2 GB MA C U-l RF PASSIVE MANUAL ISOLATION Revision 1 Section V Page 25 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

' TABLES SYSTEM: MAIN STEAM (MS)

VALVE CIC P&ID

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ MS-AOV-AO80A 2011 B5 1 A 24 GB AO O U-l RF MSIV A INBOARD ISOLATION, FSC Q CSJ 04 FST Q PIT 2Y MS-AOV-ADEt 2441 B5 i A 24 GB AO O U-l RF MSIV B INBOARD ISOLATION, FSC Q CSJ-04 FST Q PIT 2Y MS-AOV-AOSOC 2011 B6 1 A 24 GB AO O U-l RF MSIV C INBOARD ISOLATION, FSC Q CSJ44 FST Q PIT 2Y MS-AOV-AOS0D 2041 B6 i A 24 GB AO O U-l RF MSIV D INBOARD ISOLATION, FSC Q CSJ44 FST Q PIT 2Y MS-AOV-A086A 2041 B3 1 A 24 GB AO O U-l RF MSIV A OUTBOARD ISOLATION FSC Q CSJ44 FST Q PIT 2Y MS-AOV-A086B 2041 A4 1 A 24 GB AO O U-l RF MSIV B OUTBOARD ISOLATION FSC Q CSJet FST Q PIT 2Y i

Revision 1 Section V Page 26 of 153

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SUMMARY

TABLES SYSTEM: MAIN STEAM (MS)

VALVE CIC P&ID

^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ MS-AOV-AO86C 2041 A8 1 A 24 GE AO O 13-1 RF MSIV C OUTBOARD ISOLATION FSC Q CSJ-04 FST Q PIT 2Y MS-AOV-AO86D 2041 B8 1 A 24 GB AO O 13-1 RF MSIV D OUTBOARD ISOLATION FSC Q CSJ-04 FST Q PIT 2Y MS-AOV-738AV 2028 B9 1 B 1/2 GB AO C PIT 2Y RPV IIEAD VENT DRAIN TO SUMP.

PASSIVE ISOLATION MS-AOV-739AV 2028 B9 i B 1/2 GB AO C PIT 2Y RPV IIEAD VENT DRAIN TO SUMP.

PASSIVE ISOLATION MS-CV-20CV 2028 Cl1 3 C 10 CK-S SA C VBT RF 71 A RV DISCIIARGE VACUUM BREAKER VB 71 Al MS-CV-21CV 2028 Cll 3 C 10 CK-S SA C VBT RF 71A RV DISCHARGE VACUUM BREAKER VB 71 A2 MS-CV-22CV 2028 Cl1 3 C 10 CK-S SA C VBT RF 71B RV DISCIIARGE VACUUM BREAKER VB 71 B1 MS-CV-23CV 2028 Cl1 3 C 10 CK-S SA C VBT RF 71B RV DISCIIARGE VACUUM BREAKER VB 71 B2 MS-CV-24CV 2028 Dil 3 C 10 CK-S SA C VBT RF 71C RV DISCIIARGE VACUUM BREAKER VB 71 Cl Revision 1 Section V Page 27 of 153

_ _ _ - --___ _-_____ _____ - - ~ _ _ _ _ _ _ - _ . _ _ _ - -- _ ..

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: MAIN STEAM (MS)

VALVE CIC P&lD

^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ MS-CV-25CV 2028 DIi 3 C 10 CK-S LA C VBT RF 71C RV DISCilARGE VACUUM BREAKER VB 71 C2 MS-CV-26CV 2028 D11 3 C 10 CK-S SA C VBT RF 71D RV DISCIIARGE VACUUM BREAKER VB 71 DI MS-CV-27CV 2028 D11 3 C 10 CK-S SA C VBT RF 71D RV DISCHARGE VACUUM BREAKER VB 71 D2 MS-CV-28CV 2028 D9 3 C 10 CK-S SA C VBT RF 71E RV DISCllARGE VACUUM BREAKER VB 71 El MS-CV-29CV 2028 D9 3 C 10 CK-S SA C VBT RF 71E RV DISCIIARGE VACUUM BREAKER VB 71 E2 MS-CV-30CV 2028 D9 3 C 10 CK-S SA C VBT RF 71F RV DISCHARGE VACUUM BREAKER VB 71 F1 MS-CV-31CV 2028 D9 3 C 10 CK-S SA C VBT RF 71F RV DISCHARGE VACUUM BREAKER VB 71 F2 MS-CV-32CV 2028 E9 3 C 10 CK-S SA C VBT RF 71G RV DISCilARGE VACUUM BREAKER VB 71 G1 MS-CV-33CV 2028 E9 3 C 10 CK-S SA C VBT RF 71G RV DISCHARGE VACUUM BREAKER VB 71 G2 MS-CV-34CV 2028 E9 3 C 10 CK-S SA C VBT RF 71H RV DISCHARGE VACUUM BREAKER VB 71 H1 Revision i Section V Page 28 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: MAIN STEAM (MS)

VALVE CIC P&lD

' ^ ^ ^ NOTES /DESCRilrTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ _

MS-CV-35CV 2028 E9 3 C 10 CK-S SA C VBT RF 7111 RV DISCHARGE VACUUM BREAKER VB 71112 MS-MOV-MO74 2041 C6 1 A 3 GT MO O U-l RF MS LINE DRAIN INBOARD FSC Q ISOLATION PIT 2Y MS-MOV-MO77 2041 C10 1 A 3 GT MO O U-l RF MS LINE DRAIN OUTBOARD FSC Q ISOIATION PIT 2Y MS-RV-70ARV 2028 CIO 1 C 6 RV SA C RVT SY SAFETY VALVE MS LI:s-- . ,

MS-RV-70BRV 2028 E9 1 C 6 RV SA C RVT SY SAFETY VALVE MS LINE D MS-RV-70CRV 2028 E9 i C 6 RV SA C RVT SY SAFETY VALVE MS LINE D MS-RV-71ARV 2028 CIO 1 B/C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS LINE A, FSO RF RV-09 FSC RF MS-RV-71BRV 2028 Cl1 1 B/C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS LINE A.

FSO RF RV-09 FSC RF MS-RV-71CRV 2028 D11 1 B/C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS LINE B, FSO RF RV-09 FSC RF Revision i Section V Page 29 of 153

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SUMMARY

TABLES SYSTEM: MAIN STEAM (MS)

VALVE CIC P&lD

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ MS-RV-71DRV 2028 D11 1 B/C 6 RV AO C RVT SY SAFETY REUEF VALVE MS LINE B.

FSO RF RV-09 FSC RF MS-RV-71ERV 2028 D9 1 B/C 6 RV AO , C RVT SY SAFETY RELIEF VALVE MS LINE C, l FSO RF RV-09 FSC RF MS-RV-71FRV 2028 D9 i B/C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS LINE C, FSO RF RV-09 FSC RF i MS-RV-71GRV 2028 E9 1 B/C 6 RV AO C RVT SY SAFETY REUEF VALVE MS LINE D, FSO RF RV-09 FSC RF MS-RV-7111RV 2028 E9 i B/C 6 RV AO C RVT SY SAFETY RELIEF VALVE MS LINE D.

FSO RF RV-09 FSC RF Revision i Section V Page 30 of 153

__ ._ - . . _ _ _ _._ ..______________.______._____mm____ _ _ _ _ _ . . _ _ _ _

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NEUTRON MONITORING TRAVERSING INCORE PROBE (NMT)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ NM-CV-CV2 2083 J2 2 A/C 3/8 CK-P SA C U-l 2Y N2 PURGE ISOLATION, CSJ-10 FSC CS NM-CV CV4 2083 J2 2 A /C 3/8 Cir-P SA C U-l 2Y N2 PURGE ISOLATION, CSJ-10 FSC CS NMT-NVA-104AX 2083 J2 2 D 3/8 SIIR EX O EX 2Y VALVE ASSEMBLY CII-A NMT-NVA-104BX 2083 J2 2 D 3/8 SIIR EX O EX 2Y VALVE ASSEMBLY CII-B NMT-NVA-101CX 2083 J2 2 D 3/8 SIIR EX O EX 2Y VALVE ASSEMBLY Cll-C NMT-NVA-104DX 2083 J2 2 D 3/8 SilR EX 0 EX 2Y VALVE ASSEMBLY CII-D NMT-NVA-104A 2083 J2 2 A 3/8 BAL SO O U-l RF VALVE ASSEMBLY Cil-A FSC Q FST Q PIT 2Y NMT-NVA-104B 2083 J2 2 A 3/8 BAL SO O U-l RF VALVE ASSEMBLY Cll-B FSC Q FST Q i PIT 2Y Revision 1 Section V Page 31 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NEUTRON MONITORING TRAVERSING INCORE PROBE (NMT)

VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ NMT-NVA-101C 2083 J2 2 A 3/8 BAL SO O U-l RF VALVE ASSEMBLY Cil-C FSC Q FST Q PIT 2Y NMT-NVA-104D 2083 J2 2 A 3/8 BAL SO O U-l RF VALVE ASSEMBLY CII-D FSC Q FST Q PIT 2Y 1

Revision 1 Section V Page 32 of 153

l COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ NBI-AOV-736AV 2028 C9 1 B 1/2 GB AO O PIT 2Y RPV FLANGE LEAKOFF PASSIVE ISOLATION NBI-AOV-737AV 2028 C9 1 B 1/2 GB AO C PIT 2Y RPV FLANGE LEAKOFF PASSIVE ISOLATION NBI-CV-10BCV 2026 C4 1 A/C 1 CK-B SA O U-2 RF UPPER CIIECK FOR FSC RF LI41, RV-10 NBI-CV-IIBCV 2026 D4 1 AiC 1 CK-B SA O LI-2 RF CONDENSING CIIAMBER 2A UPPER FSC RF TO 25-5 RACK, RV-10 NBI-CV-12BCV 2026 D4 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 2A LOWER FSC RF TO 25-5 RACK, RV-10 NBI-CV-13BCV 2026 E4 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 3A TO FSC RF LITS-73A, RV-10 NBI-CV-14BCV 2026 E4 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 3A TO 25-5 FSC RF & 25-5-1 RACK, RV-10 NBI-CV-15BCV 2026 E4 1 A/C : CK-B SA O U-2 RF LT-52A; LIS-83A & C; LT-61; DPT-65; FSC RF LIS-101 A & B, RV-10 NBI-CV-16BCV 2026 F4 1 A/C 1 CK B SA O U-2 RF LOW SIDE, FT-64T, FSC RF RV-10 NBI-CV-17BCV 2026 F4 1 A/C 1 CK-B SA O U-2 RF LOW SIDE FT-64R; FSC RF FT-63D, RV-10 NBI-CV-18BCV 2026 G4 1 A/C 1 CK-B SA O U-2 RF lilGli SIDE FT-63D, RV-10 FSC RF Revision 1 Section V Page 33 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES l

SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS R_Q" f FREQ NBI-CV-19BCV 2026 G4 1 A/C 1 CK-B SA O U-2 RF ABOVE CORE PLATE PRESS, RV-10 FSC RF i NBI-CV-20BCV 2026 G4 1 A/C 1 CK-B SA O U-2 RF BELOW CORE PLATE TO FSC RF INSTRUMENT RACK 25-51. RV-10 NBI-CV-21BCV 2026 D8 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 2B UPPER FSC RF TO 25-6 RACK. RV-10 NBI-CV-22BCV 2026 D8 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 2B UPPER FSC RF TO 254 RACK, RV-10 '

l NBI-CV-23BCV 2026 E8 1 A/C 1 CK-B SA O U-2 RF CONDENSING CIIAMBER 3B LT-70; F';C RF LITS-73B, RV-10 NBI-CV-24BCV 2026 E8 1 A/C 1 CK-B SA O U-2 RF CONDENSING CHAMBER 3B TO 25-6 FSC RF & 25-6-1 RACKS, RV-10 NBI-CV-25BCV 2026 E8 1 A/C I CK-B SA O U-2 RF LOW SIDE LIS-83B; FSC RF LT-52B: US-101C & D, RV-10 NBI-CV-26BCV 2026 F8 1 A/C 1 CK-B SA O U-2 RF LOW SIDE FT44L, FSC RF RV-10 NBI-CV-27BCV 2026 F8 1 A/C 1 CK-B SA O U-2 RF LOW SIDE FT43C; FSC RF FT-64N, RV-10 NBI-CV-28BCV 2026 G8 1 A/C 1 CK-B SA O U-2 RF llIGH SIDE FT43C, RV-10 FSC RF NBI-CV-29BCV 2026 G8 1 A/C 1 CK-E SA O U-2 RF BELOW CORE PLATE TO FSC RF INSTRUMENT R.ACK 25-52. RV-10 Revision 1 Section V Page 34 of 153

COOPER NUCLEAR STATION THIRD INTERVAL ,

INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND YARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ NBI-CV-30BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF Fr43B; FT-64B LOW SIDE, RV-10 FSC RF NBI-CV-31BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT43B; IllGli SIDE, RV-10 FSC RF NBI-CV-32BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64D; LOW SIDE, RV-10 FSC RF NBI-CV-33BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64F; LOW SIDE, RV-10 FSC RF NBI-CV-34BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FF-64K; LOW SIDE, RV-10 ,

FSC RF NBI-CV-35BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64M; LOW SIDE, RV-10 FSC RF NBI-CV-36BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64V; LOW SIDE, RV-10 FSC RF NBI-CV-37BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64X; LOW SIDE, RV-10 FSC RF NBI-CV-38BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64Z: LOW SIDE, RV-10 FSC RF NBI-CV-39BCV 2026 F3 1 A/C 1 CK-B SA O U-2 RF FT-64A; FT-63A LOW SIDE, RV-10 ,

FSC RF NBI-CV-40BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-63A filGli SIDE, RV-10 FSC RF Revision 1 Section V Page 35 of 153 t

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRil* TION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ <

. NBI-CV-41BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-64C LOW SIDE, RV-10 ll FSC RF NBI-CV-42BCV 2026 F9 i A/C 1 CK-B SA O U-2 RF FT-64E LOW SIDE, RV-10 FSC RF NBI-CV-43BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-64J LOW SIDE, RV-10 FSC RF NBI-CV-44BCV 2026 F9 i A/C 1 CK-B SA O U-2 RF FT-64S LOW SIDE, RV-10 FSC RF NBI-CV-45BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-64U LOW SIDE, RV-10 FSC RF NBI-CV-46BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-64W LOW SIDE, RV-10 FSC RF NBI-CV-47BCV 2026 F9 1 A/C 1 CK-B SA O U-2 RF FT-64Y LOW SIDE, RV-10 FSC RF NBI-CV-49BCV 2026 El 3 C 1/2 CK-S SA C FSO RF REFERENCE LEG LOOP A INJECTION, ROJ-06 NBI-CV-50BCV 2026 El 3 C 1/2 CK-S SA C FSO RF REFERENCE LEG LOOP A INJECTION, ROJ-06 NBI-CV-51BCV 2026 E12 3 C 1/2 CK-S SA C FSO RF REFERENCE LEG LOOP B INJECTION, ROJ-06 NBI-CV-52BCV 2026 E12 3 C 1/2 CK-S SA C FSO RF REFERENCE LEG LOOP B INJECTION. ROJ-06 Revision 1 Section V Page 36 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMEP'TATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIFFION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ NBI-CV-55CV 2026 A3 3 A/C 3/8 CK-S SA O LT2 RF REFERENCE LEG LOOP 3A FSC RF OUTEOARD INJECTION, ROJ-07 NBI-CV-56CV 2026 A3 3 A/C 3/8 CK-S SA O LT2 RF REFERENCE LEG LOOP 3B FSC RF OUTBOARD INJECTION, ROJ-07 NBI-SOV-SSV738 2026 El 2 B 1/2 SOV SOV C FSO RF REFERENCE LEG LOOP A FST RF INJECTION, ROJ-06 PIT 2Y NBI-SOV-SSV739 2026 E12 2 B 1/2 SOV SOV C FSO RF REFERENCE LEG LOOP B FST RF INJECTION, ROJ-06 PIT 2Y CS-CV-16BCV 2M5 A6 1 A/C 1 CK-B SA O U-2 RF DPIS-43A LOW SIDE EXCESS FLOW, SII 1 FSC RF RV-10 CS-CV-17BCV 2045 B6 1 A/C 1 CK-B SA O U-2 RF DPIS-43B LOW SIDE EXCESS FLOW, SH I FSC RF RV-10 HPCI-CV-10BCV 2M1 D4 1 A/C 1 CK-B SA O U-2 RF HIGH SIDE HPCI-DPIS-76; DPIS-77; FSC RF PS-68A: PS-68C, RV-10 HPCI-CV-IIBCV 2M1 D4 1 A/C 1 CK-B SA O U-2 RF LOW SIDE HPCI-DPIS-76; DPIS-77; PS-FSC RF 68B: PS-68D, RV-10 MS-CV-10BCV 2NI C4 1 A/C 1 CK-B SA O U-2 RF FT-51A; DPIS-Il6A, B, C, & D HIGli FSC RF SIDE, RV-10 MS-CV-1IBCV 2041 C4 1 A/C 1 CK-B SA O U-2 RF FT-51A; DPIS-Il6A, B, C. & D LOW FSC RF SIDE. RV-10 Revision 1 Section V Page 37 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM .

VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ MS-CV-12BCV 2041 C4 1 A/C 1 CK-B SA O U-2 RF IT-51B; DPIS-Il7A, B, C, & D LOW FSC RF SIDE, RV-10 MS-CV-13BCV 2N1 C4 1 A/C 1 CK-B SA O U-2 RF FT-51B; DPIS-Il7A, B, C. & D HIGH FSC RF SIDE, RV-10 MS-CV-14BCV 2041 C7 1 A/C 1 CK-B SA O U-2 RF FT-51C; DPIS-Il8A, B, C, & D IIIGli FSC RF SIDE, RV-10 MS-CV-ISBCV 2(M1 C7 I A/C 1 CK-B SA O U-2 RF FT-51D; DPIS-119A, B, C & D HIGH FSC RF SIDE, RV-10 MS-CV-16BCV 2041 C7 1 A/C 1 CK-B SA O U-2 RF FT-51C; DPIS-118A, B, C & D LOW FSC RF SIDE, RV-10 MS-CV-17BCV 2041 C7 1 A/C 1 CK-B SA O U-2 RF FT-51D; DPIS-119A, B, C, & D LOW FSC RF SIDE, RV-10 RCIC-CV-10BCV 2041 E7 1 A/C 1 CK-B SA O U-2 RF RCIC-DPIS-84 Il!GH SIDE EXCESS FSC RF FLOW CHECK VALVE, RV-10 RCIC-CV-11BCV 2041 E7 1 A/C 1 CK-B SA O U-2 RF RCIC-DPIS-84 LOW SIDE EXCESS FSC RF FLOW CHECK VALVE, RV-10 RCIC-CV-12BCV 2041 D7 1 A/C 1 CK-B SA O U-2 RF RCIC-DPIS-83 HIGH SIDE EXCESS FSC RF FLOW CHECK VALVE, RV-10 RCIC-CV-13BCV 2041 D7 1 A/C 1 CK-B SA O U-2 RF RCIC-DPIS-83 LOW SIDE EXCESS FSC RF FLOW CHECK VALVE, RV-10 RR-CV-10CV 2027 C1 1 A/C 1 CK-B SA O U-2 RF PS-128A SENSING LINE, RV-10 FSC RF Revision i Section V Page 38 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CHECK VALVES VALVE CIC PalD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RR-CV-IICV 2027 Cl 1 A/C 1 CK-B SA O U-2 RF PS-128A SENSING LINE, RV-10 FSC RF RR-CV-12CV 2027 B2 1 A/C 1 CK-B SA O U-2 RF DFF-Ill A LOW SIDE, RV-10 FSC RF RR-CV-13CV 2027 B2 1 A/C 1 CK-B SA O U-2 RF DPT-111 A IllGH SIDE, RV-10 FSC RF RR-CV-15CV 2027 E2 1 A/C 1 CK-B SA O U-2 RF PT-25A SENSING LINE, RV-10 FSC RF RR-CV-16CV 2027 E2 1 A/C 1 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 HIGII SIDE, RV-10 FSC RF RR-CV-18CV 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 1 CK-B SA O U-2 RF DFT-111B LOW SIDE, RV-10 FSC RF RR-CV-28CV 2027 B9 1 A/C 1 CK-B SA O U-2 RF DFT-111B HIGH SIDE, RV-10 FSC RF RR-CV-30CV 2027 E9 1 A/C 1 CK-B SA O U -2 RF FT-25B REACTOR RECIRCULATION FSC RF PUMP IB SEAL CAVITY UNE. RV-10 RR-CV-31CV 2027 E9 1 A/C 1 CK-B SA O U-2 RF PT-24B SENSING LINE, RV-10 FSC RF Revision i Section V Page 39 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: NUCLEAR BOILER INSTRUMENTATION (NBI) AND VARIOUS OTHER EXCESS FLOW CIIECK VALVES VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RR-CV-32CV 2027 A9 1 A/C 1 CK-B SA O U-2 RF FT-110C AND D lilGH SIDE, RV-10 FSC RF RR-CV-33CV 2027 A9 1 A/C 1 CK-B SA O U-2 RF FT-110C AND D LOW SIDE, RV-10 FSC RF Revision 1 Section V Page 40 of 153

- =. . _ = . .

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR Cf .A RS CAT K17F TYPE TYPF POR ROMT FRFO PC-AOV-237AV 2022 E4 2 A 24 BTF AO C U-l RF SUPPRESSION CilAMBER INLET Sil 1 FSC Q OUTBOARD ISOLATION FST Q PIT 2Y PC-AOV-238AV 2022 D4 2 A 24 BTF AO C U-l RF DRYWELL INLET OUTBOARD Sil 1 FSC Q ISOLATION FST Q PIT 2Y PC-AOV-243AV 2022 E5 2 A 20 BTF AO C U-l RF SUPPRESSION CilAMBER VACUUM Sil 1 FSO Q RELIEF FST Q PIT 2Y PC-AOV-244AV 2022 F5 2 A 20 BTF AO C U-l RF SUPPRESSION CIIAMBER VACUUM Sil 1 FSO Q RELIEF FST Q PIT 2Y PC-AOV-245AV 2022 El 2 A 24 BTF AO C U-l RF SUPPRESSION CliAMBER EXilAUST Sil 1 FSC Q OUTBOARD ISOLATION FST Q PIT 2Y PC-AOV-246AV 2022 C1 2 A 24 BTF AO C U-l RF DRYWELL EXIIAUST OUTBOARD SIl 1 FSC Q ISOIATION FST Q PIT 2Y Revision 1 Section V Page 41 of 153

u_. __ -, ._ . __. .

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC)

VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION POOR FI ARR PAT R17F TYPF TYPF POR ROMT FRFD PC-AOV-247AV 2022 Fil 2 A 24 BTF AO C U-l RF DRYWELL EXHAUST OUTBOARD Sil 1 FSC Q ISOLATION FST Q PC-AOV-248AV 2022 Fil 2 A 24 BTF AO C U-l RF DRYWELL EXilAUST OUTBOARD ,

SII I FSC Q ISOLATION FST Q PC-AOV-NRV20 2027 H3 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CIIAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV21 2027 113 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER 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 CHAMBER TO VBT RF DRYWELL VACUUM BREAKER PIT 2Y PC-AOV-NRV23 2027 114 2 A/C 20 CK-5 AO C LT-2 RF SUPPRESSION CIIAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV24 2027 HS 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CriAMBER TO VBT RF DRYWELL VACUUM BREAKER FIT 2Y PC-AOV-NRV25 2027 H5 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF Revision i Section V Page 42 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR FI .AS9 CAT RI7F TYPF TYPF POR ROMT FRFO PC-AOV-NRV26 2027 116 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV27 2027 116 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV28 2027 117 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV29 2027 H7 2 AiC 20 CK-S AO C LT-2 RF SUPPRESSION CllAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV30 2027 117 2 A/C 20 CK-S AO C LT-2 RF- SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-AOV-NRV31 2027 H8 2 A/C 20 CK-S AO C LT-2 RF SUPPRESSION CHAMBER TO PIT 2Y DRYWELL VACUUM BREAKER VBT RF PC-CV-13CV 2022 E5 2 A/C 20 CK-D SA C U-l RF SUPPRESSION CHAMBER VACUUM Sil 1 VBT RF RELIEF, ROJ-19 PC-CV-14CV 2022 F5 2 A/C 20 CK-D SA C 13-1 RF SUPPRESSION CHAMBER VACUUM SH I VBT RF RELIEF. ROJ-19 Revision i Section V Page 43 of 153

I COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIlrTION COOR Cf ARR CAT Rf7F TYPF TYPF POS ROMT FDFO PC-CV-21CV 2022 El 2 A/C 1/4 CK-S SA O/C U-l RF N2 SUPPLY TO 110 2 2 MONITORS.

SH 2 FSC RF ROJ-08 PC-CV-22CV 2022 D3 2 A/C 1/4 CK-S SA O/C U-l RF N2 SUPPLY TO II,0, MONITORS.

Sil 2 FSC RF ROJ-08 PC-CV-23CV 2022 C3 2 A/C 1/4 CK-S SA O/C U-l RF O2 SUPPLY TO H2 0, MONITORS, Sil 2 FSC RF ROJ-08 PC-CV-25CV 2022 E5 2 A/C 1/4 CK-S SA O/C U-l RF N2 SUPPLY TO 110 2 2 MONITORS, Sil 2 FSC RF ROJ-08 PC-CV-26CV 2022 D6 2 A/C I/4 CK-S SA O!C U-l RF N2 SUPPLY TO 110, 2 MONITORS, SII 2 FSC RF ROJ-08 PC-CV-27CV 2022 C6 2 A/C 1/4 CK-S SA O/C U-l RF O2 SUPPLY TO 110 2 2 MONITORS.

Sil 2 FSC RF ROJ-08 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 CSJ-05 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 CSJ-05 PC-CV-35CV 2028 D8 2 A/C 3/8 CK 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-230MV 2022 El 2 A 24 BTF MO C U-l RF SUPPRESSION CIIAMBER EXIIAUST Sil 1 FSC Q INBOARD ISOLATION PIT 2Y Revision 1 Section V Page 44 of 153

l COOPER NUCLEAR STATION l

THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CI _ ARK PAT Sf7F TYPF TYPF POR ROMT FRFO PC-MOV-231MV 2022 C1 2 A 24 BTF MO C U-l RF DRYWELL EXII AUST INBOARD Sil 1 FSC Q ISOLATION PIT 2Y PC-MOV-232MV 2022 D4 2 A 24 BTF MO C U-l 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 CliAMBER INLET Sil 1 FSC Q INBOARD ISOLATION PIT 2Y PC-MOV-305MV 2022 El 2 A 2 GT MO C U-l RF PC-MOV-23OMV BYPASS Sil 1 FSC Q PIT 2Y PC-MOV-3%MV 2022 C1 2 A 2 GT MO C U-l RF PC-MOV-231MV BYPASS SH I FSC Q PIT 2Y PC-MOV-130lMV 2084 F8 2 A 1 GT MO O U-I RF SUPPRESSION CIIAMBER ISOLATION FSC Q SYSTEM B PIT 2Y PC-MOV-1302MV 2084 F7 2 A 1 GT MO O U-l RF SUPPRESSION CIIAMBER ISOLATION FSC Q SYSTEM B PIT 2Y PC-MOV-1303MV 2084 F4 2 A 1 GT MO C U-1 RF SUPPRESSION CIIAMBER ISOLATION FSC Q SYSTEM A PIT 2Y Revision i Section V Page 45 of 153

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SUMMARY

TABLES SYSTEM: PRIMARY CONTAINMENT (PC) '

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CI AR9 CAT Rf7F TYPF TYPF POR D O\fT FRFO PC-MOV-1304MV 2084 F4 2 A 1 GT MO C U-l RF SUPPRESSION CIIAMBER ISOLATION FSC Q SYSTEM A PIT 2Y PC-MOV-1305MV 2084 E4 2 A I GT MO C U-l RF DRYWELL ISOLATION SYSTB1 A FSC Q PIT 2Y PC-MOV-13%MV 2084 E4 2 A I GT MO C U-l RF DRYWELLISOLATION SYSTEM A FSC Q PIT 2Y PC-MOV-1308MV 2084 117 2 A 1 GT MO C U-l RF BLEED ISOLATION FOR FSC Q SUPPRESSION CilAMBER PIT 2Y PC-MOV-1310MV 2084 C7 2 A 1 GT MO C U-l RF BLEED ISOLATION FOR DRYWELL FSC Q PIT 2Y PC-MOV-1311MV 2084 E7 2 A 1 GT MO O U-l RF DRYWELL DILUTION SUPPLY FSC Q ISOIATION SYSTEM B PIT 2Y PC-MOV-1312MV 2084 E7 2 A 1 GT MO O U-l RF DRYWELL DILUTION SUPPLY FSC Q ISOLATION SYSTEM B PIT 2Y Revision i Section V Page 46 of 153

l COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RADIATION MONITORING (RMV)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RMV-AOV-10AV 2022 E10 2 A 3/4 GB AO O U-l RF RM4 CONTAINMENT ISOLATION, Sil 1 FSC Q INBOARD FST Q PIT 2Y RMV-AOV-11 AV 2022 E10 2 A 3/4 GB AO O U-l RF RM-4 CONTAINMENT ISOLATION, '

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, Sif 1 FSC Q INBOARD FST Q PIT 2Y RMV-AOV-13AV 2022 F10 2 A 3/4 GB AO O U-l RF RM-4 CONTAINMENT ISOLATION, Sil i FSC Q OUTBOARD FST Q PIT 2Y i

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SUMMARY

TABLES SYSTEM: RADIOACTIVE WASTE (RW)

VALVE CIC P&ID

^ ^ ^ NOTES /DESCRil'rION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RW-AOV-AO82 2028 G5 2 A 3 GT AO O U-1 RF DRYWELL FLOOR DRAIN SUMP FSC Q DISCIIARGE FST Q PIT 2Y RW-AOV-A083 2028 G5 2 A 3 GT AO O U-l RF DRYWELL FLOOR DRAIN SUMP FSC Q DISCIIARGE l

FST Q PIT 2Y RW-AOV-AO94 2028 G11 2 A 3 GT AO O U-l RF DRYWELL EQUIPMENT DRAIN FSC Q SUMP DISCIIARGE FST Q PIT 2Y RW-AOV-AO95 2028 G12 2 A 3 GT AO O U-l RF DRYWELL EQUIPMENT DRAIN FSC Q SUMP DISCHARGE FST Q PIT 2Y RW-CV-58CV 2005 GIO A C 2 CK-S SA C FSO Q Z SUMP PUMP A DISCIIARGE SII 2 FSC Q CIIECK RW-CV-59CV 2005 GIO A C 2 CK-S SA C FSO Q Z SUMP PUMP B DISCIIARGE Sil 2 FSC Q CHECK Revision 1 Section V Page 48 of 153

i COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

P&lD ISI IST VALVE VALVE ACT TEST TEST VALVE CIC P&lD COOR CLASS CAT SIZE TYPE TYPE RQMT FREQ POS RCIC-AOV-A034 2011 GIO 2 B 1 GB AO O FSC Q RCIC STEAM LINE DRIPLEG DRAIN FST Q PIT 2Y RCIC-CV-10CV 2043 J3 2 C 6 CK-S SA C FSO Q ECST SUPPLY TO RCIC PUMP, FSC CS CSJ-il RCIC-CV-IICV 2043 , 1110 2 C 6 CK-S SA C FSO RF RCIC SUPPLY FROM SUPPRESSION i FSC RF CIIAMBER, ROJ-09 RCIC-CV-12CV 2043 G9 2 C 2 CK-S SA C FSC RF VACUUM PUMP DISCIIARGE TO SUPPRESSION CllAMBER, ROJ-10 RCIC-CV-13CV 2043 DS 2 C 2 CK-P SA C FSO Q MINIMUM FLOW LINE, ROJ-10 FSC RF RCIC-CV-15CV 2043 D9 2 A/C 8 CK-S SA C 13-1 RF RCIC TURBINE EXHAUST TO FSC RF SUPPRESSION CIIAMBER, ROJ-10 FSO Q RCIC-CV-18CV 2043 B8 2 C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO RCIC PRESSURE MAINTENANCE, RV-Il RCIC-CV-19CV 2043 B8 A C 2 CK-P SA C FSC Q CONDENSATE SUPPLY TO RCIC PRESSURE MAINTENANCE, RV-11 RCIC-CV-20CV 2043 H7 A C 2 CK-P SA C PSO Q RCIC LUBE OIL COOLING WATER FSO RF RETURN. ROJ-17 Revision 1 Section V Page 49 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE SUABIARY TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

P&ID ISI IST VALVE VALVE ACT TEST TEST

^ COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RCIC-CV-21CV 2043 117 2 C 2 CK-P SA C PSO Q RCIC CONDENSATE PUMP FSO RF DISCIIARGE, ROJ-17 FSC RF RCIC-CV-22CV 2G43 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUUM BREAKER. RV-14 RCIC-CV-23CV 2043 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUUM BREAKER, RV-14 RCIC-CV-24CV 2043 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUUM BREAKER. RV-14 PCIC-CV-25CV 2043 E10 2 C 1 1/2 CK-L SA C VBT RF RCIC VACUUM BREAKER, RV-14 RCIC-CV-26CV 2043 C9 1 A/C 4 CK-S SA O 13-1 RF INJECTION CllECK VALVE, CSJ42 FSO CS FSC CS PIT 2Y RCIC-MOV-MOIS 2041 D6 1 A 3 GT MO O 13-1 RF RCIC STEAM INBOARD ISOLATION i FSO Q FSC Q PIT 2Y RCIC-MOV-MOl6 2041 D7 1 A 3 GT MO O 13-1 RF RCIC STEAM OUTBOARD FSO Q ISOLATION FSC Q PIT 2Y Revision i Section V Page 50 of 153

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SUMMARY

TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

P&ID ISI IST VALVE VALVE ACT TEST TEST VALVE CIC P&lD COOR CLASS CAT SIZE TYPE TYPE RQMT FREQ POS RCIC-MOV-M018 2M3 J3 2 B 6 GT MO O FSO Q RCIC SUPPLY FROM CONDENSATE FSC Q STORAGE PIT 2Y RCIC-MOV-MO20 2M3 C8 2 B 4 GT MO O FSO Q RCIC PUMP DISCIIARGE PIT 2Y RCIC-MOV-MO21 2043 C8 2 B 4 GT MP C FSO Q RCIC INJECTION TO REACTOR PIT 2Y RCIC-MOV-MO27 2M3 D7 2 B 2 GB MO C FSO Q RCIC PUMP MINIMUM FLOW FSC Q RECIRCULATION TO SUPPRESSION PIT 2Y CIIAMBER RCIC-MOV-MO30 2M3 El 2 B 4 GB MO C PIT 2Y RCIC TEST RETURN ROOT RCIC-MOV-MO33 2M3 El A B 4 GT MO C PIT 2Y RCIC TEST RETURN SilUTOFF RCIC-MOV-MO41 2M3 GIO 2 B 6 GT MO C FSO Q RCIC SUPPLY FROM SUPPRESSION FSC Q CIIAMBER PIT 2Y RCIC-MOV-MOl31 2041 F8 2 B 3 GB MO C FSO Q RCIC STEAM SUPPLY TO RCIC PIT 2Y TURBINE RCIC-MOV-MOl32 2M3 E3 2 B 2 GB MO C FSO Q AUXILIARY COOLING SUPPLY PIT 2Y RCIC-RD-S240 2043 E4 2 D 8 RD SA C RD SY EXIIAUST LINE RUPTURE DISC Revision 1 Section V Page 51 of 153

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SUMMARY

TABLES SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

P&lD ISI IST VALVE VALVE ACT TEST TEST VALVE CIC P&lD COOR CLASS CAT SIZE TYPE TYPE RQMT FREQ POS RCIC-RV-10RV 2043 113 2 C 1 RV SA C RVT 10Y RCIC PUMP SUCTION RELIEF RCIC-RV-11RV 2Gt3 G5 2 C 1 RV SA C RVT 10Y RCIC AUXILIARY COOLING SYSTEM RCIC-V-37 2043 D9 2 A/C 8 S-CK MA O 13-1 RF RCIC TURBINE EXIIAUST TO FSO Q SUPPRESSION CIIAMBER FSC RF ISOLATION, ROJ-Il RCIC-V-42 2043 G9 2 C 2 S-CK MA O FSC RF RCIC VACUUM PUMP DISCIIARGE TO SUPPRESSION CIIAMBER, ROJ-l1 l

l Revision 1 Section V Page 52 of 153

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SUMMARY

TABLES SYSTEM: REACTOR EQUIPMENT COOLING (REC)

VALVE CIC P&lD P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIIYTION COOR CI ARS FAT SI7F TYPF TYPF POR ROMT FRFO REC-AOV-TCV861 2031 CIO 3 B 1 GB AO T FSO Q FC-R-E INLET Sil 2 FST Q L REC-AOV-TCV862 2031 C9 3 B l-1/4 GB AO T FSO Q FC-R-li INLET Sil 2 FST Q REC-AOV-TCV861 2031 E9 3 B 1 GB AO T FSO Q FC-R-F INLET Sil 2 FST Q REC-AOV-TCV865 2031 E8 3 B l-1/4 GB AO T FSO Q F-R-J INLET Sil 2 FST Q REC-CV-10CV 2031 F1 3 C 8 CK-T SA O FSO Q REC-P-A DISCIIARGE Sil 2 FSC Q REC-CV-IICV 2031 F2 3 C 8 CK-T SA O FSO Q REC-P-B DISCIIARGE Sil 2 FSC Q REC-CV-12CV 2031 F3 3 C 8 CK-T SA O FSO Q REC-P-C DISCIIARGE Sil 2 FSC Q REC-CV-13CV 2031 F4 3 C 8 CK-T SA O FSO Q REC-P-D DISCIIARGE Sil 2 FSC Q REC-CV-16CV 2031 HI 3 C 12 CK-S SA O FSC RF NON-CRITICAL IIEADER RETURN SII 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-695MV 2031 D4 3 B 4 GT MO O PIT 2Y PASSIVE CRITICAL LOOP SUPPLY Sil 2 CROSSTIE Revision 1 Section V Page 53 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: REACTOR EQUIPMENT COOLING (REC)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR Cl . A 99 CAT SY7F TVPF TYPF PO9 ROUT FRFO REC-MOV-697MV 2031 J2 3 B 6 GT MO O FSO Q NORTil CRITICAL LOOP RETURN Sil 2 FSC Q PIT 2Y REC-MOV-698MV 2031 Ji 3 B 6 GT MO O FSO Q SOUTil CRITICAL LOOP RETURN SH 2 FSC Q PIT 2Y REC-MOV-700MV 2331 BI 3 B 10 GT MO O FSC Q NON-CRITICAL LOOP SUPPLY Sil 2 PIT 2Y SIIUTOFF REC-MOV-702MV 2031 A4 2 A 8 GT MO O U-l RF DRYWELL SUPPLY ISOLATION Sil 2 FSC Q VALVE PIT 2Y REC-MOV-709MV 2031 G3 2 A 8 GT MO O U-l RF DRYWELL RETURN ISOLATION Sil 1 FSC Q VALVE PIT 2Y REC-MOV-711MV 2031 D4 3 B 6 GT MO O FSC Q NORTii CRITICAL LOOP SUPPLY SII 2 FSO Q PIT 2Y REC-MOV-712MV 2031 D2 3 B 12 BFL MO O FSC Q REC IIEAT EXCIIANGER A OUTLET '

Sil 2 PIT 2Y REC-MOV-713MV 2031 C2 3 B 12 RFL MO O FSC Q REC IIEAT EXCHANGER B OUTLET SII 2 PIT 2Y Revision 1 Section V Page 54 of 153

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SUMMARY

TABLES SYSTEM: REACTOR EQUIPMENT COOLING (REC)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CI _ARS CAT Rf7F TYPF TYPF POS RO\fT FRFO REC-MOV-714MV 2031 C4 3 B 6 GT MO O FSC Q SOUTII CRITICAL LOOP SUPPLY Sil 2 FSO Q PIT 2Y REC-MOV-1329MV 2031 C2 3 B 8 GT MO O FSC Q AUXILIARY RADIOACTIVE WASTE Sil 2 PIT 2Y BUILDING SUPPLY l

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SUMMARY

TABLES SYSTEM: REACTOR FEEDWATER (RF)

VALVE CIC P&ID

' ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RF-CV-13CV 2044 BIO I A/C 18 CK-T SA O U-l RF FEEDWATER UNE B TO REACTOR FSC RF OUTBOARD. ROJ-13 RF-CV-14CV 2044 Cll 1 A/C 18 CK-T SA O U-l RF FEEDWATER LINE B TO ?EACTOR ,

FSO RF INBOARD, ROJ-13. ROJ-14 j FSC RF ,

RF-CV-15CV 2043 B10 1 A/C 18 CK-T SA O U-l RF FEEDWATER UNE A TO REACTOR FSC RF OUTBOARD. ROJ-13 RF-CV-16CV 2043 C11 1 A/C 18 CK-T SA O U-l RF FEEDWATER LINE A TO REACTOR FSO RF INBOARD, ROJ-13, ROJ-14 FSC RF Revision 1 Section V Page 56 of 153

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SUMMARY

TABLES SYSTEM: REACTOR RECIRCULATION (RR)

P&ID ISI IST VALVE VALVE ACT NORM TEST TEST

^ ' COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RR-AOV-740AV 2027 Al 1 A 3/4 GB AO O U-l RF SP-1 OUTBOARD ISOLATION FSC Q FST Q PIT 2Y RR-AOV-741 AV 2027 A2 1 A 3/4 GB AO O U-1 RF SP-1 INBOARD ISOLATION FSC Q FST Q PIT 2Y RR-MOV-MO53A 2027 114 I B 28 GT MO O FSC CS RR PUMP A DISCIIARGE FIT 2Y CSM)6 RR-MOV-MO53B 2027 B7 i B 28 GT MO O FSC CS RR PUMP B DISCIIARGE PIT ?Y CRIM f

Revision 1 Section V Page 57 of 153

l l

l COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: REACTOR WATER CLEANUP (RWCU)

I VALVE CIC P&lD

^ ^ ^ ' NOTES /DESCRII* TION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RWCU-CV-15CV 2042 C4 1 A/C 4 CK-S SA O U-l RF RWCU RETURN TO REACTOR Sil 1 FSC RF VESSEL, ROJ-15 RWCU-MOV-MOIS 2042 E2 1 A 6 GT MO O U-l RF RWCU SUPPLY INBOARD '

Sil 1 FSC Q ISOLATION PIT 2Y RWCU-MOV-MOI 8 2042 B4 1 A 6 GT MO O U-l RF RWCU SUPPLY OUTBOARD Sil 1 FSC Q ISOLATION I PIT 2Y l l

L i

Revision 1 Section V Page 58 of 153

l l

l COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING FROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

P&lD

^ ^

VALVE CIC CAT SIZE TYPE TYPE NOTES / DESCRIPTION COOR CLASS POS RQMT FREQ RilR-AOV-PCV69A 2041 F1 2 B 4 GB AO C FSC Q RHR IIEAT EXCIIANGER A STEAM FST Q SUPPLY PIT 2Y RilR-AOV-PCV69B 2041 F3 2 B 4 GB AO C FSC Q RilR IIEAT EXCHANGER B STEAM FST Q SUPDLY PIT 2Y RilR-AOV-PCV70A 2041 F1 2 B 4 GB AO C FSC Q RiiR 11 EAT EXCIIANGER A STEAM FST Q SUPPLY PIT 2Y RIIR-AOV-PCV70B 2041 F3 2 B 4 GB AO C FSC Q RHR llEAT EXCIIANGER B STEAM !

FST Q SUPPLY PIT 2Y RilR-AOV-LCV71A 2043 E2 2 B 3 GB AO C FSC Q RIIR IIEAT EXCHANGER A LEVEL FST Q CONTROL PIT 2Y RIIR-AOV-LCV71B 2043 E3 2 B 4 GB AO C FSC Q RIIR IIEAT EXCHANGER B LEVEL FST Q CONTROL PIT 2Y RIIR-CV-10CV 2040 G3 2 C 3 CK-S SA C PSO Q RHR PUMP A MINIMUM FLOW, ROJ-Sil 1 FSO RF 18 FSC O ,

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SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

' ^ ^ ^ NOTES / DESCRIPTION VALVE CIC P&lD TYPE COOR CLASS CAT SIZE TYPE POS RQMT FREQ RIIR-CV-1 ICV 2040 GIO 2 C 3 CK-S SA C PSO Q RHR PUMP B MINIMUM FLOW, ROJ-Sil 1 FSO RF 18 FSC O RIIR-CV-12CV 2010 114 2 C 3 CK-S SA C PSO Q RHR PUMP C MINIMUM FLOW, ROJ-S11 1 FSO RF 18 FSC Q RIIR-CV-13CV 2010 1110 2 C 3 CK-S SA C PSO Q RHR PUMP D MINIMUM FLOW, ROJ-Sil 1 FSO RF 18 FSC Q RilR-CV-14CV 2040 G3 2 C 16 CK-T SA C FSO Q RHR PUMP A DISCilARGE SH I FSC Q RilR-CV-15CV 2040 GIO 2 C 16 CK-T SA C FSO Q RIIR PUMP B DISCHARGE SH 1 FSC Q RHR-CV-16CV 2040 H3 2 C 16 CK-T SA C FSO Q RHR PUMP C DISCHARGE SH 1 FSC Q RIIR-CV-17CV 2040 1110 2 C 16 CK-T SA C FSO Q RHR PUMP D DISCIIARGE Sil 1 FSC Q RIIR-CV-18CV 2040 A9 A C 4 CK-S SA C FSC Q RHR LOOP B OUTBOARD PRESSURE SH I M AINTENANCE SUPPLY, RV-12 RIIR-CV-19CV 2010 A9 2 C 4 CK-S SA C FSC Q RHR LOOP B INBOARD PRESSURE SH I MAINTENANCE SUPPLY. RV-12 Revision 1 Section V Page 60 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&ID

^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR-CV-24CV 2040 C4 A C 4 CK-S SA C FSC Q RIIR LOOP A OUTBOARD PRESSURE SII I MAINTENANCE SUPPLY RV-12 RIIR-CV-25CV 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 LJ-l RF LOOP A INJECTION LINE TESTABLE Sil 1 LT-2 RF CllECK, PRESSURE ISOLATION FSO CS VALVE, CSJ-01 FSC CS PIT 2Y RHR-CV 27CV 2040 C7 1 A/C 24 CK-S SA C IJ-l RF LOOP B INJECTION LINE TESTABLE SII 1 LT-2 RF CliECK, PRESSURE ISOLATION ,

FSO CS VALVE, CSJ-01 FSC CS PIT 2Y RIIR-MOV-MOl2A 2040 E2 2 B 16 GT MO O FSO Q RHR IIEAT EXCllANGER A OUTLET Sil 1 PIT 2Y RIIR-MC v-MOl2B 2040 F11 2 B 16 GT MO O FSO Q RHR HEAT EXCilANGER B OUTLET SH I PIT 2Y RHR-MOV-MOl3A 2040 G6 2 B 20 GT MO O FSO Q RHR PUMP A SUCTION FROM Sil 1 FSC Q SUPPRESSION CHAMBER PIT 2Y Revision 1 Section V Page 61 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&ID

' ^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RilR-MOV-MOl3B 2010 G8 2 B 20 GT MO O FSO Q RilR PUMP B SUCT10N FROM Sil 1 FSC Q SUPPRESSION CllAMBER PIT 2Y RilR-MOV-MOl3C 2010 G6 2 B 20 GT MO O FSO Q RIIR PUMP C SUCTION FROM Sil 1 FSC Q SUPPRESSION CIIAMBER PIT 2Y RilR-MOV-MOl3D 2010 G7 2 B 20 GT MO O FSO Q RIIR PUMP D SUCTION FROM Sil 1 FSC Q SUPPRESSION CilAMBER PIT 2Y RIIR MuV-MOl5A 2010 G5 2 B 20 GT MO C FSC Q RIIR PUMP A SDC SUCTION Sil 1 PIT 2Y RIIR-MOV-MOISB 2040 G8 2 B 20 GT MO C FSC Q RIIR PUMP B SDC SUCTION Sil 1 PIT 2Y RIIR-MOV-M015C 2040 115 2 B 20 GT MO C FSC Q RIIR PUMP C SDC SUCTION Sil 1 PIT 2Y RilR-MOV-MOI 5D 2040 118 2 B 20 GT MO C FSC Q RIIR PUMP D SDC SUCTION Sil 1 PIT 2Y '

RIIR-MOV-MOl6A 2040 E3 2 B 4 GT MO O FSO Q PUMP A AND C MINIMUM FLOW Sil 1 FSC Q PIT 2Y Revision 1 Section V Page 62 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&ID

^ ^ NOTES /DESCRIFTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR-MOV-MOl6B 2040 E10 2 B 4 GT MO O FSO Q PUMP B AND D MIMINUM FLOW Sil i FSC Q PIT 2Y RIIR-MOV-MOl7 2040 D5 l A 20 GT MO C U-l RF RIIR SDC SUPPLY OUTBOARD SII I LT-2 RF PRESSURE ISOLATION VALVE, FSC CS CSJ47 PIT 2Y RiiR-MOV-MOl8 2010 D6 1 A 20 GT MO C U-l RF RilR SDC SUPPLY INBOARD Sil i LT-2 RF PRESSURE ISOLATION VALVE, FSC CS CSJ47 PIT 2Y RIIR-MOV-MO20 2040 til 2 B 20 GT MO C PIT 2Y RIIR PASSIVE CROSSIIEADER Sil 1 SHUTOFF RIIR-MOV-MO21A 2040 112 2 B 4 GT MO C FSC Q RifR llEAT EXCIIANGER A DRAIN Sil 1 PIT 2Y TO SUPPRESSION CHAMBER RIIR-MOV-MO21B 2040 Illi 2 B 4 GT MO C FSC Q RIIR HEAT EXCIIANGER B DRAIN Sil 1 PIT 2Y TO SUPPRESSION CHAMBER RIIR-MOV-MO25A 2010 C5 1 A 24 GT MO C U-l RF RilR LOOP A INJECTION INBOARD Sil 1 LT-2 RF ISOLATION FSO Q FSC Q PIT 2Y Revision 1 Section V Page 63 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES ll SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&lD

^ NOTES /DESCRINION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RHR-MOV-MO25B 2040 C8 1 A 24 GT MO C U-1 RF RiiR LOOP B INJECTION INBOARD SII 1 LT-2 RF ISOLATION FSO Q FSC Q PIT 2Y RilR-MOV-MO26A 2040 B4 2 A 10 GT MO C U-l RF DRYWELL SPRAY LOOP A Sil 1 FSC Q OUTBOARD ISOLATION PIT 2Y RIIR-MOV-MO26B 2040 B9 2 A 10 GT MC C U-l RF DRYWELL SPRAY LOOP B Sil 1 FSC Q OUTBOARD ISOLATION PIT 2Y RIIR-MOV-MO27A 2010 C4 1 B 24 ANG MO O i'SO Q LOOP A INJECTION OUTBOARD Sil 1 PIT 2Y TilROTTLE RilR-MOV-MO27B 2040 C9 i B 24 ANG MO O FSO Q LOOP B INJECTION OUTBOARD SH I PIT 2Y TIIROTTLE RIIR-MOV-MO31 A 2040 B5 2 A 10 GT MO C U-l RF DRYWELL SPRAY LOOP A INBOARD Sil 1 FSC Q ISOLATION PIT 2Y RIIR-MOV-MO31B 2040 B8 2 A 10 GT MO C U-l RF DRYWELL SPRAY LOOP B INBOARD Sil 1 FSC Q ISOLATION PIT 2Y Revision 1 Section V Page 64 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

P&lD

^ ^ ^ NOTES / DESCRIPTION VALVE CIC CAT SIZE TYPE TYPE COOR CLASS POS RQMT FREQ RHR-MOV-MO34A 204C E4 2 A 18 GB MO C U-l RF SUPPRESSION CilAMBER COOLING SH I FSO Q LOOP A INBOARD THROTTLE FSC Q PIT 2Y RilR-MOV-MO34B 2040 E9 2 A 18 GB MO C U-l RF SUPPRESSION CHAMBER COOLING Sil 1 FSO Q LOOP B INBOARD THROTTLE FSC Q PIT 2Y RilR-MOV-MO36A 2043 F2 2 B 4 GT MO C FSC Q RIIR IIEAT EXCHANGER A DRAIN PIT 2Y TO RCIC RIIR-MOV-MO36B 2043 F2 2 B 4 GT MO C FSC Q RHR IIEAT EXCHANGER B DRAIN PIT 2Y TO RCIC RIIR-MOV-MO38A 2040 DS 2 A 6 GB MO C U-l RF SUPPRESSION CHAMBER SPRAY Sil 1 FSO Q LOOP A INBOARD THROTTLE FSC Q PIT 2Y RHR-MOV-MO38B 2040 D9 2 A 6 GB MO C U-l RF SUPPRESSION CHAMBER SPRAY SH I FSO Q LOOP B INBOARD THROTTLE FSC Q PIT 2Y RHR-MOV-MO39A 2040 D4 2 A 18 GT MO C U-l RF SUPPRESSIGN CHAMBER COOLING SH I FSO Q LOOP A OUTBOARD ISOLATION FSC Q PIT 2Y Revision 1 Section V Page 65 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL IIEAT REMOVAL (RIIR)

P&ID

^ ^ NOTES /DESCRII910N VALVE CIC CLASS CAT SIZE TYPE TYPE COOR POS RQMT FREQ RHR-MOV-MO39B 2MO DIO 2 A 18 GT MO C U-l RF SUPPRESSION CIIAMBER COOLING SH I FSO Q LOOP B OUTBOARD ISOLATION FSC Q PIT 2Y RHR-MOV-MO57 2MO 117 2 B 4 GB MO C LT-2 RF RIIR DISCliARGE TO RADWASTE Sil 1 FSC Q INBOARD TIIROTTLE PIT 2Y RIIR-MOV-MO65A 2040 G2 2 B 16 GT MO O FSO Q RHR HEAT EXCllANGER A INLET Sil 1 PIT 2Y RIIR-MOV-MO65B 2NO G11 2 B 16 GT MO O FSO Q RHR IIEAT EXCIIANGER B INLET SH I PIT 2Y RIIR-MOV-MO66A 2MO F2 2 B 20 GB MO O FSO Q RHR IIEAT EXCIIANGER A BYPASS Sit I FSC Q TIIRO1TLE PIT 2Y RHR-MOV-MO66B 2MO F11 2 B 20 GB MO O FSO Q RHR IIEAT EXCIIANGER B BYPASS SH I FSC Q TIIROITLE PIT 2Y RHR-MOV-MO67 2MO 117 2 B 4 GT MO C LT-2 RF RHR DISCIIARGE TO RADWASTE SH I FSC Q OUTBOARD SIIUTOFF PIT 2Y RHR-MOV-MOl66A 2M1 112 2 A 1 GB MO C U-l RF RHR HEAT EXCIIANGER A VENT FSC Q PIT 2Y Revision 1 Section V Page 66 of 153

y

(

COOPER NUCLEAR STATION <

THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&ID

' ^ ^ ^ NOTES /DESCRll' TION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR-MOV-MOl66B 2M1 H2 2 A 1 GB MO C U-l RF RiiR HEAT EXCliANGER B VENT FSC Q PIT 2Y RIIR-MOV-MOl67A 2M1 HI 2 A 1 GB MO C U-l RF RiiR llEAT EXCHANGER A VENT FSC Q l PIT 2Y RilR-MOV-MOl67B 2041 112 2 A I GB MO C U-l RF RiiR HEAT EXCIIANGER B VENT FSC Q l PIT 2Y RHR-MOV-MO274A 2M1 C6 2 A 2 GB MO C U-l RF RHR-CV-26CV PASSIVE BYPASS LT-2 RF PRESSURE ISOLATION VALVE PIT 2Y ,

RHR-MOV-MO274B 2M1 C7 2 A 2 GB MO C U-l RF RHR-CV-27CV PASSIVE BYPASS LT-2 RF PRESSURE ISOLATION VALVE PIT 2Y RHR-MOV-920MV 2041 El 2 B 3 GT MO C FSC CS STEAM SUPPLY TO AOG PIT 2Y UPSTREAM SHUTOFF, CSI-08 RHR-MOV-921MV 2M1 El A B 3 GT MO C FSC CS STEAM SUPPLY TO AOG PIT 2Y DOWNSTREAM SIIUTOFF CSJ-08 RHR-RV-10RV 2MO G5 2 C 1 RV SA C RVT 10Y RHR PUMP A SUCTION RELIEF Rif f Revision 1 Section V Page 67 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR-RV-11RV 2040 G8 2 C 1 RV SA C RVT 10Y RIIR PUMP B SUCTION RELIEF SII I RilR-RV-12RV 2040 115 2 C 1 RV SA C RVT 10Y RilR PUMP C SUCTION REUEF SII I RilR-RV-13RV 2040 11 8 2 C 1 RV SA C RVT 10Y RIIR PUMP D SUCTION REUEF Sil I RI!R-RV-14RV 2040 C3 2 C 1 RV SA C RVT 10Y RIIR LOOP A SUPPLY RELIEF Sil 1 RHR-RV-15RV 2040 CIO 2 C 1 RV SA C RVT 10Y RIIR LOOP B SUPPLY RELIEF Sil I RIIR-RV-17RV 2040 F5 2 C 1 RV SA C RVT 10Y SIIUTDOWN COOLING Sil 1 SUPPLY REUEF RIIR-RV-18RV 2041 G1 2 C 2% RV SA C RVT 10Y STEAM SUPPLY TO RIIR U-l RF IIEAT EXCHANGER A REUEF RHR-RV-19RV 2041 G3 2 C 2% RV SA C RVT 10Y STEAM SUPPLY TO RHR HEAT U-l RF EXCHANGER B RELIEF RHR-RV-20RV 2041 G2 2 C 1 RV SA C RVT 10Y RHR HEAT EXCHANGER A SHELL U-l RF SIDE REUEF RIIR-RV-21RV 2041 G2 2 C 1 RV SA C RVT 10Y RHR HEAT EXCIIANGER B SilELL U-l RF SIDE REUEF Revision i Section V Page 68 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: RESIDUAL HEAT REMOVAL (RHR)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ RIIR-SOV-SSV60 2040 G2 2 B % SOV SO C FSC Q RIIR IIEAT EXCIIANGER B PASS SII I FST Q SAMPE VALVE PIT 2Y RIIR-SOV-SSV61 2040 F2 A B % SOV SO C FSC Q RiiR llEAT EXCIIANGER B PASS SII 1 FST Q SAMPW VALVE PIT 2Y RilR-SOV-SSV95 20$0 G12 2 B % SOV SO C FSC Q RilR llEAT EXCIIANGER A PASS Sil i FST Q SAMPE VALVE P!T 2Y RilR-SOV-SSV% 20$0 F12 A B M SOV SO C FSC Q RilR IIEAT EXCIIANGER A PASS Sil 1 FST Q SAMPG VALVE PIT 2Y Revision i Section V Page 69 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIIrrION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SW-AOV-850AV 2036 G8 3 B 2 BAL AO O FSC Q REC IIEAT EXCIIANGER A OUTLET FST Q PROCESS RAD MONITOR SUPPLY PIT 2Y SW-AOV-851 AV 2036 G7 3 B 2 BAL AO O FSC Q REC IIEAT EXCHANGER B OUTLET FST Q PROCESS RAD MONITOR SUPPLY PIT 2Y SW-AOV-852AV 2036 G8 3 B 2 BAL AO O FSC Q REC IIEAT EXCilANGER A OUTLET FST Q PROCESS RAD MONITOR SUPPLY PIT 2Y SW-AOV-853AV 2036 G9 3 B 2 BAL AO O FSC Q REC IIEAT EXCIIANGER B OUTLET FST Q PROCESS RAD MONITOR SUPPLY PIT 2Y SW-AOV-854AV 2036 G8 3 B 2 BAL AO C PIT 2Y SW PASSIVE RAD MONITOR SAMPLE RETURN SW-AOV-855AV 2036 G9 3 B 2 BAL AO C PIT 2Y SW PASSIVE RAD MONITOR SAMPLE RETURN SW-AOV-TCV451 A 2036 E7 3 B 12 GB AO Orr FSO Q REC IIEAT EXCIIANGER A OUTLET Sil I FST Q TEMPERATURE CONTROL VALVE, PIT 2Y CSJ-09 SW-AOV-TCV451B 2036 F7 3 B 12 GB AO Off FSO Q REC IIEAT EXCilANGER B OUTLET SIl 1 FST Q TEMPERATURE CONTROL VALVE, PIT 2Y CSJ-09 SW-CV-ARA 2036 ES 3 C 6 CK SC C FSC O SW AIR RELEASE Revision 1 Section V Page 70 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIFTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SW-CV-ARB 2036 C5 3 C 6 CK SC C FSC Q SW AIR RELEASE SW-CV-10CV 2006 Al1 3 C 20 CK-D SA O FSO Q SW PUMP A DISCIIARGE Sil 1 FSC Q SW-CV-IICV 2006 A8 3 C 20 CK-D SA O FSO Q SW PUMP E DISCIIARGE Sil i FSC Q SW-CV-12CV 2006 A10 3 C 20 CK-D SA O FSO Q SW PUMP C DISCIIARGE Sil-1 FSC Q SW-CV-13CV 2006 A7 3 C 20 CK-D SA O FSO Q SW PUMP D DISCIIARGE Sil i FSC Q SW-CV-19CV 2036 G3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER PUMP A FSC Q DISCHARGE SW-CV-20CV 2036 F3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER PUMP B FSC Q DISCIIARGE SW-CV-21CV 2036 G3 3 C 14 CK-T SA C FSO Q RIIR SW BOOSTER PUMP C FSC Q DISCIIARGE SW-CV-22CV 2036 F3 3 C 14 CK-T SA C FSO Q RHR SW BOOSTER PUMP D FSC Q DISCIIARGE SW-CV-27CV 2036 C2 3 C 14 CK-D SA O FSO Q REC IIEAT EXCIIANGER B SUPPLY SW-CV-28CV 2036 C2 3 C 14 CK-D SA O FSO Q REC llEAT EXCIIANGER A SUPPLY SW-CV-35CV 2077 D1 3 C 10 CK-S SA O FSO Q DG1 SUPPLY FSC O Revision 1 .Section V Page 71 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&ID P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIIq' ION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SW-CV-36CV 2077 D2 3 C 10 CK-S SA O FSO Q DG1 SUPPLY FSC Q SW-CV-37CV 2077 D5 3 C 10 CK-S SA O FSO Q DG2 SUPPLY FSC Q SW-CV-38CV 2077 D5 3 C 10 CK-S SA O FSO Q DG2 SUPPLY FSC Q SW-CV-54CV 2036 G11 3 C 3 CK-S SA O FSC Q SW PROCESS RAD MONITOR RETURN SW-CV-81CV 2006 G11 3 C 1 CK-S SA O FSC Q RIVERWELL SUPPLY TO SW PUMPS SII I A AND C SW-CV-d2CV 2006 GIO 3 C 1 CK-S SA O FSC Q RIVERWELL SUPPLY TO SW PUMPS SII I A AND C SW-CV-84CV 2006 Gil 3 C 1 CK-S SA O FSC Q RIVERWELL SUPPLY TO SW PUMPS SH 1 B AND D SW-CV-85CV 2006 G10 3 C 1 CK-S SA O FSC Q RIVERWELL SUPPLY TO SW PUMPS Sil 1 B AND D SW-MOV 36MV 2006 E10 3 B 24 BTF MO O FSC Q SW LOOP CRITICAL HEADER SH I PIT 2Y ISOLATION SW-MOV-37MV 2006 E10 3 B 24 BTF MO O FSC Q SW PUMPS CROSSTIE PIT 2Y SW-MOV-MO89A 2036 C7 3 B 18 GB MO C FSO Q RHR HEAT EXCHANGER A SW PIT 2Y OUTLET. RV-13 Revision 1 Section V Page 72 of 153

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COOPER NUCLEAR STATION i THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SW-MOV-MO89B 2036 CIO 3 B 18 GB MO C FSO Q RIIR IIEAT EXCilANGER B SW PIT 2Y OUTLET. RV-13 SW-MOV-650MV 2036 D4 3 B 18 BTF MO O FSO Q REC HEAT EXCllANGER A OUTLET FSC Q PIT 2Y SW-MOV-651MV 2036 C4 3 B 18 BTF MO O FSO Q REC IIEAT EXCliANGER B OUTLET FSC Q PIT 2Y SW-MOV-886MV 2036 D2 3 B 4 GT MO C FSO Q EMERGENCY SUPPLY TO REC PIT 2Y NORTil CRmCAL LOOP SW-MOV-887MV 2036 D2 3 B 4 GT MO C FSO Q EMERGENCY SUPPLY TO REC PIT 2Y SOUTli CRmCAL LOOP SW-MOV-888MV 2036 E4 3 B 4 GT MO C FSO Q EMERGENCY RETURN FROM REC PIT 2Y NORTli CRmCAL LOOP SW-MOV-889MV 2036 C4 3 B 4 GT MO C FSO Q EMERGENCY RETURN FROM REC PIT 2Y SOUTII CRmCAL LOOP SW-MOV-2128MV 2006 G1 3 C 1 1/2 GB M0 C FSO Q SW GLAND SEAL WATER BACKUP Sli 4 PIT 2Y FROM SW PUMPS A AND C SW-MOV-2129MV 2006 Ill 3 C 1 1/2 GB MO C FSO Q SW GLAND SEAL WATER BACKUP Sli 4 PIT 2Y FROM SW PUMPS B AND D SW-RV-12RV 2006 G8 3 C 3/4 RV SA C RVT 10Y SWBP 1A SEAL WATER RELIEF S 11 4 Revision 1 Section V Page 73 of 153

COOPER NUCLEAR STATIO3 THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ ,

SW-RV-13RV 2006 E8 3 C 3/4 RV SA C RVT 10Y SWBP IC SEAL WATER RELIEF Sil 4 SW-RV-14RV 2006 C8 3 C 3/4 RV SA C RVT 10Y SWBP IB SEAL WATER RELIEF Sil 4 SW-RV-15RV 2006 A8 3 C 3/4 RV SA C RVT 10Y SWBP ID SEAL WATER RELIEF Sil 4 SW-V-640 2006 F7 3 B 1 BAL MA O FSC Q SWBP C SEAL WATER RIVERWELL Sil 4 SIIUTOFF SW-V-649 2006 G7 3 B 1 BAL MA O FSC Q SWBP A SEAL WATER RIVERWTLL SII 4 SIIUTOFF SW-V-656 2006 B7 3 B 1 BAL MA O FSC Q SWBP D SEE WATER RIVERWELL ,

SH 4 SHUTOFF SW-V-665 2006 D7 3 B 1 BAL MA O FSC Q SWBP B SEAL WATER RIVERWELL Sil 4 SIIUTOFF SW-V-1422 2006 G8 3 C 3/4 GB MA C FSO Q SWBP A GLAND WATER SUPPLY SH 4 SW-V-1424 2006 G8 3 C 3/4 GB MA C FSO Q SWBP A GLAND WATER FLOW Sil 4 CONTROL ;

SW-V-1426 2006 C8 3 C 3/4 GB MA C FSO Q SWBP B GIAND WATER SUPPLY Sil 4 SW-V-1428 2006 C8 3 C 3/4 GB MA C FSO Q SWBP B GLAND WATER FLOW Sil 4 CONTROL Revision i Section V Page 74 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: SERVICE WATER (SW)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SW-V-1430 2006 E8 3 C 3/4 GB MA C FSO Q SWBP C GLAND WATER SUPPLY Sil 4 SW-V-1432 2006 E8 3 C 3/4 GB MA C FSO Q SWBP C GLAND WATER FLOW S11 4 CONTROL SW-V-1434 2006 B8 3 C 3/4 GB MA C FSO Q SWBP D GLAND WATER SUPPLY SII 4 SW-V-1436 2006 B8 3 C 3/4 GB MA C FSO Q SWBP D GLAND WATER FLOW Sil 4 CONTROL Revision 1 Section V Page 75 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: STANDBY GAS TREATMENT (SGT)

VALVE CIC P&ID P&lli ISI IST VALVE VALVE ACT NORM TEST TEST NOTES /DESCRIirTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SGT-ADV-249AV 22t37 C2 A B 12 BTF AO C FSO Q SGT UNIT A INLET FSC Q FST Q PIT 2Y SGT-AOV-250AV 2037 G2 A B 12 BTF AO C FSO Q SGT UNIT B INLET FSC Q FST Q PIT 2Y SGT-AOV-251 AV 2037 C6 A B 12 BTF AO C FSO Q SGT UNIT A DISCHARGE FST Q PIT 2Y SGT-AOV-252AV 2037 G6 A B 12 BTF AO C FSO Q SGT UNIT B DISCilARGE FST Q PIT 2Y SGT-AOV-255AV 2037 C6 A B 10 BTF AO C PIT 2Y SGT UNIT A PASSIVE BYPASS SGT-AOV-256AV 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-271AV 2037 Gl A B 10 BTF AO C FSO Q SGT UNIT B DILUTION AIR FST Q SIIUTOFF PIT l 2Y r

Revision i Section V Page 76 of 153

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COOPER NUCLEAR STATION THIRD INTERVAL !

INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: STANDBY GAS TREATMENT (SGT)

VALVE CIC P&ID P&ID ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SGT-AOV- 2037 C7 A B 10 BTF AO C FSO Q SGT UNIT A DISCilARGE ,

DPCV546A FST Q DIFFERENTIAL PRESSURE PIT 2Y CONTROL SGT-AOV- 2037 E7 A B 10 BTF AO C FSO Q SGT UNIT B DISCIIARGE DPCV546B FST Q DIFFERENTIAL PRESSURE PIT 2Y CONTROL SGT-CV-14CV 2037 C6 A C 10 CK-D SA C PSO Q SGT UNIT A FAN EXIIAUST, PSC Q ACSJ-05 FSO CS FSC CS SGT-CV-15CV 2037 G6 A C 10 CK-D SA C M Q SGT UNIT B FAN EXHAUST, PSC Q ACSJ-05 FSO CS FSC CS Revision 1 Section V Page 77 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: STANDBY LIQUID CONTROL (SLC)

VALVE CIC P&lD

^ ^ ^ NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SLC-CV-10CV 2045 E9 A C 1% CK-L SA C FSO Q SLC PUMP A DISCHARGE CHECK.

SH 2 FSC RF AROJ-05 ,

SLC-CV-IICV 2M5 F9 A C 1% CK-L SA C FSO Q SLC PUMP B DISCIIARGE CHECK, SH 2 FSC RF AROJ-05 SLC-CV-12CV 2M5 E8 i A/C 1% CK-L SA C 13-1 RF SLC INJECTION LINE OUTBOARD Sil 2 FSO RF CHECK, ROJ-16, AROJ4%

FSC RF SLC-CV-13CV 2045 E7 i A/C 1% CK-L SA C 13-1 RF SLC INJECTION LINE INBOARD Sil 2 FSO RF CIIECK, ROJ-16, AROJ44 FSC RF SLC-RV-10RV 2M5 DIO A C 3/4 RV SA C RVT 10Y SLC PUMP A DISCHARGE RELIEF Sil 2 SLC-RV-11RV 2045 G9 A C 3/4 RV SA C RVT 10Y SLC PUMP B DISCHARGE RELIEF SH 2 SLC-SQBV-14A 2045 E8 A D 1% SHR CH C EX 2Y SLC EXPLOSIVE VALVE A SH 2 SLC-SQBV-14B 2045 E8 A D 1% SHR CH C EX 2Y SLC EXPLOSIVE VALVE B SH 2 Revision i Section V Page 78 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM VALVE

SUMMARY

TABLES SYSTEM: STATION AIR (SA)

VALVE CIC P&lD P&lD ISI IST VALVE VALVE ACT NORM TEST TEST NOTES / DESCRIPTION COOR CLASS CAT SIZE TYPE TYPE POS RQMT FREQ SA-V-647 2010 G4 2 A I GB MA C 13-1 RF PASSIVE DRYWELL OUTBOARD SH 3 SUPPLY ISOLATION SA-V-M8 2010 G4 2 A 1 GB MA C 1J-1 RF PASSIVE DRYWELL INBOARD Sil 3 SUPPLY ISO 1ATION Revision 1 Section V Page 79 of 153

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l l COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l

i C. Cold Shutdown Test Justifications CSJ No. DESCRIPTION t '

l CSJ-01 CS-CV-18CV, CS-CV-19CV, RHR-CV-26CV, and RHR-CV-27CV i CSJ-02 HPCI-CV-29CV and RCIC-CV-26CV Test Frequency CSJ-03 HPCI-AOV-PCV50 Test Frequency I CSJ-04 MSIV Test Frequency CSJ-05 PC-CV-33CV and PC-CV-34CV Test Frequency CSJ-06 RR-MOV-MO53A and RR-MOV-53B Testing Frequency CSJ-07 RHR-MOV-M017 and RHR-MOV-M018 Testing Frequency CSJ-08 RHR-MOV-920MV and RHR-MOV-921MV Testing Frequency CSJ-09 SW-AOV-TCV451 A and SW-AOV-TCV451b Testing Frequency -

CSJ-10 NM-CV-CV2 and NM-CV-CV4 Testing Frequency CSJ-11 HPCI-CV-10CV and RCIC-CV-10CV Testing Frequency I

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! Revision 1 Section V Page 80 of 153 l

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1 COOPER NUCLEAR STATION l

THIRD INTERVAL '

INSERVICE TESTING PROGRAM l <

l COLD SHUTDOWN TEST JUSTIFICATION CSJ-01 VAL.VES: CS-CV-18CV, CS-CV-19CV, RHR-CV-26CV, and RHR-CV-27CV l j CLASS: 1 CATEGORY: A/C l l FUNCTION: These valves open for Core Spray or LPCI injection and close for primary i l containment isolation. ;

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 l 4.3.2.5. !

! BASIS FOR I DEFERRAL: These valves are normally closed for primary containment isolation. They are also l 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 j possible due to the downstream side being exposed to reactor pressure. ;

l

. ALTERNATE !

TEST: 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. i I

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! Revision 1 Section V Page 81 of 153 l

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i l COOPER NUCLEAR STATION I THIRD INTERVAL l INSERVICE TESTING PROGRAM l COLD SHUTDOWN TEST JUSTIFICATION CSJ-02 VALVES: HPCI-CV-29CV and RCIC-CV-26CV {

t

CLASS: 1 CATEGORY: A/C l FUNCTION: HPCI-CV-29CV - Opens to provide a flowpath from the HPCI pump to the reactor vessel via the feedwater system; closes for primary 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. ,

l REQUIRED l 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 l 4.3.2.5.

1 BASIS FOR -

DEFERRAL: These valves are normally closed to isolate the reactor coolant system and the !

HPCI and RCIC systems. Exercising these check valves to the open position l l

during normal plant operation would require HPCI or RCIC injection to the reactor I l

vessel. This would result in a perturbation of normal feedwater flow and 1 unnecessary thermal cycling of the feedwater nozzles. It would also cause severe i power fluctuations due to the relatively cold water from the Emergency 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./HR. In general, plant personnel are prohibited from entering this area during power operation due to these conditions.

l

! ALTERNATE l TEST: These valves will be mechanically exercised, verifying open and closure capability, l during cold shutdown periods in accordance with OMa Part 10, 4.3.2.2 and j l 4.3.2.4. !

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Revision 1 Section V Page 82 of 153 I

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COOPER NUCLEAR STATION '

THIRD INTERVAL INSERVICE TESTING PROGRAM i

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COLD SHUTDOWN TEST JUSTIFICATION CSJ-03 i VALVE: IIPCI-AOV-PCV50 i CLASS: 2 CATEGORY: B

! 1 l

l FUNCTION: Air operated, pressure regulating valve for the cooling water supply line to the ,

I HPCI lube oil cooler. The valve performs an active safety function in the l open/ throttled position to allow cooling water flow to the lube oil cooler.

REQUIRED- 1) OMa Part 10, 4.2.1.1 requires Category A and B power operated valves to TEST: 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.

l

2) OMa 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 accordance with the exercising frequency of paragraph 4.2.1.1.

This valve would normally be exempt from IST requirements as permitted by OMa l 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 fail-l safe position. i BASIS FOR This valve functions to control pressure in the cooling water supnly line to the RELIEF: HPCI turbine lube oil cooler. Cooling water is supplied from the HPCI booster pump discharge. The valve is normally maintained in the closed position as a result of the HPCI pump being idle and pressure maintenance, supplied by the l auxiliary condensate system, maintaining the HPCI piping water solid.

The valve travels to a throttled position, when the HPCI pump starts, to automatically maintain pressure in the cooling water line at 50 psig. The valve's l control circuitry prevents disk travel from the full-closed position to the full-open position. The valve is designed to fail to the open position on a loss of instrument air or electrical control power to ensure continuity of cooling water flow to the j 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.

4 Revision 1 Section V Page 83 of 153

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l COOPER NUCLEAR STATION l THIRD INTERVAL :

l INSERVICE TESTING PROGRAM COLD SHUTDOWN TEST JUSTIFICATION CSJ-03 (Continued)

Stroke timing and fail-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 ,

l imposed signal would then be removed allowing valve travel to the open position at I l which point stroke timing can be performed. This process is impracticable during power operation due to the necessity of placing the HPCI system in a condition which would compromise safe operation of the system upon automatic actuation.

Additionally, due to the intrusive method of imposing a calibration signal, the .i system would also be rendered incapable of initiation by operator action.

ALTERNATE ,

TEST: 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 exercise test will be performed quarterly.

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Revision 1 Section V Page 84 of 153 f

i l_ COOPER NUCLEAR STATION ,

l THIRD INTERVAL INSERVICE TESTING PROGRAM '

t L COLD SIIUTDOWN TEST JUSTIFICATION CSJ-04

VALVE: MS-AOV-AO80A, MS-AOV-A086A, l MS-AOV-AO80B, MS-AOV-AO86B, j MS-AOV-AO80C, MS-AOV-A086C, ;

l MS-AOV-A080D, and MS-AOV-A086D 1

CLASS: 1 CATEGORY: A FUNCTION: The inboard and outboard main steam isolation valves (MSIVs) must be capable of automatic closure to limit the release of radioactivity during a reactor transient or accident condition, i

i l REQUIRED ,

! TEST: 1) OMa Part 10, 4.2.1.1 requires Category A and B power operated valves to be l 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 requires valves with fail-safe actuators to be tested by l observing the operation of the actuator upon loss of valve actuating power in j accordance with the exercising frequency of paragraph 4.2.1.1. ,

BASIS FOR '

DEFERRAL: These valves are currently exercised in accordance with the mrveillance requirements identified in the plant Technical Specification, Section 4.7.D.1.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 Licensing Change Request (LCR) has been initiated to revise this Technical Specification surveillance requirement. The proposed revision will allow exercise testing to be performed in accordance with ASME 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 MSIVs during 100% power operation is impracticable due to the potential for reactor transients and scrams. Also, full MSIV closure could create the !

potential of lifting the main steam safety relief valves (SRVs) due to an increase in ]

i steam line pressure. Failure of an SRV to reclose could result in reactor vessel 4 depressurization.

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, INSERVICE TESTING PROGRAM .

l COLD SHUTDOWN TEST JUSTIFICATION CSJ-04 (Continued)

ALTERNATIVE TEST: After the Technical Specification change is approved the MSIVs shall be partially exercised approximately 10% closed, from the full open position, at least once per quarter. Stroke timing to the closed position and fail-safe testing shall be '

performed during cold shutdown periods in accordance with the requirements of '

OMa Part 10, 4.2.1.2. Until then the MSIV's shall be stroke timed closed and fail l safe tested quarterly.

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COLD SHUTDOWN TEST JUSTIFICATION CSJ-05 l

l VALVE: PC-CV-33CV and PC-CV-34CV '

CLASS: 2 CATEGORY: A/C l FUNCTION: These check valves perform an active safety function in the closed position to provide containment isolation and are located in the instrument air / nitrogen line at penetrations X-29E and X-51F. The open function of these check valves is to provide actuating air to inboard recirculation Loop A sample line valve RR-AOV-741 AV. However, this function is not safety related. j l

l REQUIRED !

f 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 j 4.3.2.5. !

BASIS FOR DEFERRAL: These check valves are not provided with position indication. Therefore, exercising these check valves to the closed position would require isolating the l downstream piping and app ying 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 scaffolding, temporary test equipment and a breach of system pressure boundary to !

facilitate testing. This additional test activity during normal plant operation l l represents an unusual burden without a compensating increase in the level of I

' quality and safety. .

1 ALTERNATE TEST: 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.

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l COOPER NUCLEAR STATION i THIRD INTERVAL '

INSERVICE TESTING PROGRAM :

l COLD SHUTDOWN TEST JUSTIFICATION CSJ-06 ,

VALVES: RR-MOV-MO53A and RR-MOV-MO53B '

CLASS: 1 CATEGORY: B i

FUNCTION: Reactor Recirculation Pump 1 A and IB Discharge Isolation j l

l REQUIRED TEST: OMa Part 10, 4.2.1.1 requires Category A and B 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.

BASIS FOR ,

l DEFERRAL: Closure of either of the RR pump discharge valves would reduce recirculation flow l 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 ;

j increase the possibility of a fuel element failure. In addition, failure of these i l valves during operation would require reactor shutdown due to inaccessibility. )

ALTERNATE TEST: Valve exercising to the closed position will be performed during ( old shutdowns in l l

accordance with OMa Part 10, 4.2.1.2.

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j COOPER NUCLEAR STATION THIRD INTERVAL i INSERVICE TESTING PROGRAM 1

f l COLD SHUTDOWN TEST JUSTIFICATION CSJ-07 l . VALVES: RHR-MOV-M017 and PHR-MOV-M018 l

l ~ CLASS: 1 CATEGORY: A l

l FUNCTION: Reactor vessel return to the RHR pump suction and containment isolation during i reactor operations. These valves are only opened for low pressure shutdown

! cooling.

REQUIRED TEST: OMa Part 10, 4.2.1.1 requires Category A and B power operated valves to be l l 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.

l BASIS FOR DEFERRAL: Valves RHR-MOV-M017 and RHR-MOV-M018 are interlocked for pressure l isolation during plant operation. Opening these valves during normal operation l could possibly allow high pressure reactor coolant water into the low pressure l suction lines of the RHR system. Therefore, it is essential that these valves remain closed during plant operations.

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

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THIRD INTERVAL INSERVICE TESTING PROGRAM ,

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COLD SHUTDOWN TEST JUSTIFICATION CSJ-08 !

VALVES: RHR-MOV-920MV and RHR-MOV-921MV l CLASS: 2, A (downstream) CATEGORY: B FUNCTION: Provide isolation of main steam to the Augmented Off Gas (AOG) system.

REQUIRED !

TEST: OMa Part 10, 4.2.1.1 requires Category A and B 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.

l BASIS FOR DEFERRAL: The steam supply cannot be isolated during normal plant operation without causing >

significant Augmented Off Gas (AOG) system transients. Transients could include a fast or uncontrolled burn of hydrogen gas in the AOG piping buried underground i' and leading outside the plant. Also, routine quarterly testing of either of these i valves could cause a release of radioactive material several orders of magnitude j above normal release activities.

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

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1 COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM COLD SHUTDOWN TEST JUSTIFICATION CSJ VALVES: SW-AOV-TCV451 A and SW-AOV-TCV451B CLASS: 3 ' CATEGORY: B FUNCTION: Open to provide a flow path for cooling water to the REC heat exchangers.

REQUIRED TEST: OMa Part 10, 4.2.1.1 requires Category A and B 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 requires 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.

BASIS FOR DEFERRAL: One temperature control valve is normally open to control flow to the associated REC heat exchanger. During the hot summer 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 REC 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 REC heat exchanger can be removed from service. The associated temperature control valve can then be closed and exercised to the full open position.

l ALTERNATE TEST: 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.

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THIRD INTERVAL l INSERVICE TESTING PROGRAM l COLD SHUTDOWN TEST JUSTIFICATION CSH0 VALVES: NM-CV-CV2 and NM-CV-CV4 CLASS: 2 CATEGORY: A/C l

FUNCTION: These valves close for primary containment isolation.

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l REQUIRED l 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 DEFERRAL: These valves are normally closed for primary containment isolation. They are open intermitantly during power operation to support operation of the TIP system, l 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 I 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 boundary 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.

ALTERNATE TEST: 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.

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! INSERVICE TESTING PROGRAM COLD SHUTDOWN TEST JUSTIFICATION CSJ-11

! VALVES: HPCI-CV-10CV and RCIC-CV-10CV i CLASS: 2 CATEGORY: C ,

l l FUNCTION: These valves close to prevent reverse flow when the suction supply is changed from the ECST's to the suppression pool.

l REQUIRED l 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 l 4.3.2.5.

BASIS FOR DEFERRAL: These valves are normally closed. When the HPCI or RCIC pumps are running, these valves open to provide suction supply from the ECST's to the respective ;

pumps. When the ECST's reach the low level setpoint, the suppression pool !

suction supply valves open and the motor operated ECST 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 check valves are not provided with position -

indication. Therefore, exercising these check valves to the closed position would

require isolating the ECST'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 HPCI 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.

l ALTERNATE TEST: 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, j 4.3.2.2.

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! THIRD INTERVAL l INSERVICE TESTING PROGRAM l

l D. Refueling Outage Justifications ROJ No. Description ROJ-01 CRD-CV-13CV, CRD-CV-14CV, CRD-CV-15CV, and CRD-CV-16CV Exercise Testing Frequency ROJ-02 HPCI-CV-11CV Testing Frequency

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l l I ROJ-03 HPCI-CV-15CV, HPCI-CV-16CV, and HPCI-CV-17CV Testing to the f l Closed Position ROJ-04 HPCI-V-44 and HPCI-V-50 Testing to the Closed Position l l l ROJ-05 1A-CV-65CV and IA-CV-78CV Closure Test Frequency ROJ-Oo NBI-CV-49BCV, NBI-CV-50BCV, NBI-CV-51BCV, NBI-CV-52BCV, NBI-SOV-SSV738, and NBI-SOV-SSV739 Exercise Test Frequency I

ROJ-07 NBI-CV-55CV and NBI-CV-56CV Exercise Test Frequency l

ROJ-08 PC-CV-21CV, PC-CV-22CV, PC-CV-23CV, PC-CV-25CV, l PC-CV-26CV, and PC-CV-27CV Closure Test Frequency -

i ROJ-09 RCIC-CV-11CV Testing Relief ROJ-10 RCIC-CV-12CV, RCIC-CV-13CV, and RCIC-CV-15CV Testing to the Closed Position ROJ-11 RCIC-V-37 and RCIC-V-42 Testing to the Closed Position ROJ-12 REC-CV-16CV Closure Test Frequency I

ROJ-13 RF-CV-13CV, RF-CV-14CV, RF-CV-15CV, and RF-CV-16CV Reverse Flow Test ROJ-14 RF-CV-14CV and RF-CV-16CV Open Test Frequency i

! ROJ-15 RWCU-CV-15CV Test Frequency i

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM i ROJ-16 SLC-CV-12CV and SLC-CV-13CV Testing Frequency ROJ-17 RCIC-CV-20CV and RCIC-CV-21CV Testing Frequency ROJ-18 . RHR-CV-10CV, RHR-CV-11CV, RHR-CV-12CV, and RHR-CV-13CV Testing Frequency ROJ-19 PC-CV-13CV and PC-CV-14CV Testing Frequency ROJ-20 HPCI-CV-17CV Testing Frequency l

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l COOPER NUCLEAR STATION l THIRD INTERVAL l INSERVICE TESTING PROGRAM I

REFUELING OUTAGE JUSTIFICATION ROJ-01 l VALVE: CRD-CV-13CV, CRD-CV-14CV, CRD-CV-15CV, and CRD-CV-16CV i

CLASS: 1 CATEGORY: A/C

FUNCTION: Containment isolation valves for Control Rod Drive (CRD) seal water injection for j the Reactor Recirculation (RR) pumps. '

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally I 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: Exercising these valves to the closed position during normal plant operation would require stopping or reversal of seal water flow which would impose a severe l thermal transient on the reactor recirculation pump seals resulting in premature seal failure. Drywell entry during cold shutdown would be necessary to facilitate I l testing, thereby requiring deinerting which could potentially delay restart. Valve j i

exercising during cold shutdown when the drywell is deinerted, could also delay l plant restart due to the necessity of using portable test equipment inside the drywell. The additional test activity during cold shutdown represents an unusual l burden without a compensating increase in the level of quality and safety.

l ALTERNATE TEST: 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.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-02 VALVE: HPCI-CV-11CV CLASS: 2 CATEGORY: C FUNCTION: Normally closed HPCI pump suction line check valve from the suppression pool.

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 DEFERRAL: The HPCI pump normally takes suction from the Emergency Condensate Storage Tanks (ECST). When the ECSTs reach low level the pump suction is automatically realigned to the suppression pool and HPCI-CV-11CV opens. - The valve is not equipped with position indication 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 HPCI pump discharges to the ECSTs.

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

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

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-03 VALVE: HPCI-CV-15CV, HPCI-CV-16CV and HPCI-CV-17CV CLASS: 2 CATEGORY: A/C and C j FUNCTION: HPCI-CV-15CV - Opens to provide an exhaust path for the HPCI Turbine; closes l for primary containment isolation.

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HPCI-CV-16CV - Water sealed containment isolation valve.

, HPCI-CV-17CV - Opens to provide a flowpath for HPCI pump minimum Gow; l closes to prevent diver::ica of RHR suppression pool cooling.

l REQUIRED i TEST: OMa Part 10,4.3.2.1 requires check valves to be individually exercised nominally !

l every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and l

4.3.2.5.

! BASIS FOR ,

l DEFERRAL: These valves are simple check valves, and thus, have no mechanism by which l

{ valve closure can be verified. Thus, the only practicable method of testing in the !

l closed position is to impose a reverse differential pressure on the valve seat to j verify closure capability or to measure the seat leakage. '

1 Performing such a test renders the HPCI system inoperable, thus it is impracticable 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 l undue burden on the plant staff without a compensating increase in the level of l quality and safety. !

ALTERNATE l TEST: The closure capability of these valves will be veriGed each refueling outage during L the performance of leak rate testing (15CV) per the CNS Appendix J Program or !

L by demonstrating the ability to maintain a differential pressure across the valve seat ,

(16CV and 17CV). !

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t REFUELING OUTAGE JUSTIFICATION ROJ-04 ;

VALVE: HPCI-V-44 and HPCI-V-50 l I

CLASS: 2 CATEGORY: A/C

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FUNCTION: HPCI-V-44 is a containment isolation globe stop check from the HPCI turbine exhaust to the suppression pool.

HPCI-V-50 is a water sealed containment isolation globe stop check valve from the HPCI 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 HPCI pump operation and are required to close for containment isolation.

I 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 DEFERRAL: 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 1 by the manual operator. If the disk should stick shut, the failure would go )

undetected until the turbine was operated. This would result in HPCI being l unavailable to perform its safety function. ~ Having HPCI unavailable, should an accident occur, could lead to reactor damage and potential release of radioactive material.

ALTERNATE TEST: 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 demonstrating the ability to maintain a differential pressure across the valve seat (V-50).

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. COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-05 I

VALVES: IA-CV-65CV and IA-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 / nitrogen line which is the pneumatic supply to the MSIVs and SRVs located inside primary containment.

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 DEFERRAL: These check valves are not provided with position indication. Therefore, i 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

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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 l TEST: 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.

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COOPER NUCLEAR STATION l THIRD INTERVAL l/ INSERVICE TESTING PROGRAM l REFUELING OUTAGE JUSTIFICATION ROJ-06 :

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i . VALVE: NBI-CV-49BCV, NBI-CV-50BCV, NBI-CV-51BCV, NBI-CV-52BCV, ,

NBI-SOV-SSV738, and NBI-SOV-SSV739 CLASS: 3 CATEGORY: C and B i FUNCTION: The reference leg injection check valves and solenoid operated valves have an l

! 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.

l- REQUIRED ;

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

OMa Part 10,4.2.1 requires Category A and B 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 !

l accordance with the exercising frequency of paragraph 4.2.1.1.

BASIS 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 3B) 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 i l and venting the Cold Reference Leg Backfill System. This is not practicable L during power operation or cold shutdown, other than refueling, due to the possible 1 introduction of air into the system. This could cause a spurious reactor vase! 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 condition. During refueling outages, sufficient time exists for decay heat to be reduced to I

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COOPER NUCLEAR STATION THIRD INTERVAL l INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-06 (Continued) l 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.

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

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COOPER NUCLEAR STATION THIRD INTERVAL l INSERVICE TESTING PROGRAM I REFUELING OUTAGE JUSTIFICATION ROJ-07 VALVE (s): NBI-CV-55CV and NBI-CV-56CV CLASS: 3 CATEGORY: C FUNCTION: These Cold Reference leg Continuous Backfill System check valves have an active safety function in the closed position to isolate the Class 3 instrumentation piping i from the Seismic IIS 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.

BASIS FOR DEFERRAL: This system provides for a continuous flow of water frorn 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).

Exercising these valves to the closed position would require reanually isolating and venting of the Cold Reference leg Continuous Backfill System tipstream 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. False 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 l 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 I 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 closed position shall be performed during refueling outages. Exercise testing shall be accomplished by performing a seat leakage test.

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i COOPER NUCLEAR STATION l THIRD INTERVAL l l INSERVICE TESTING PROGRAM l

REFUELING OUTAGE JUSTIFICATION ROJ-08 l

l VALVE: PC-CV-21CV, PC-CV-22CV, PC-CV-23CV, PC-CV-25CV, PC-CV-26CV, and ,

PC-CV-27CV l CLASS: 2 CATEGORY: A/C FUNCTION: The drywell H /0 2 monitors 2 nitrogen purge supply check valves perform an active

safety function in the closed position to maintain primary containment integrity.

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. These valves function in the open position only to supply nitrogen or oxygen to the H 2/02monitors 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 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: Exercising these check valves to the closed position would require isolating the l H 2/02monitors from the drywell and suppression chamber atmosphere and applying an outside pressure source downstream of the check valves while venting the upstream piping. Performing this test activity during normal plant operation or cold shutdowns would require the removal of the H 2 /02 Monitoring System from

. service during conditions when primary containment integrity is required. Plant Technical Specifications Tables 3.2.F and 3.2.H identifies the H2 /02 monitors as surveillance instmmentation required for the assessment of the containment atmosphere by monitoring the hydrogen and oxygen concentrations. Testing these valves during conditions when H2 /02 operability is required would result in a reduction in safety and would not provide a significant increase in assurance of continued operability.

ALTERNATE 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 H2/02 monitoring system shall be local leak

rate tested prior to resumption of service.

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THIRD INTERVAL '

INSERVICE TESTING PROGRAM ;

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REFUELING OUTAGE JUSTIFICATION ROJ-09 VALVE: RCIC-CV-11CV CLASS: 2 CATEGORY: C l !

FUNCTION: Normally closed RCIC pump suction line check valve from the suppression pool.

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 DEFERRAL: The RCIC pump normally takes suction from the Emergency Condensate Storage i Tanks (ECST). When the ECSTs reach low level the pump suction is automatically realigned to the suppression pool and RCIC-CV-11CV opens. The - -

valve is not equipped with position indication or remote manual operators for exercising. The only method for exercising the valve during operation is to test it i

with flow. 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 disassembled, inspected and manually exercised to the full open and closed positions during each refueling outage in accordance with the j requirements of OMa Part 10, 4.3.2.4.

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l REFUELING OUTAGE JUSTIFICATION ROJ-10

, VALVES: RCIC-CV-12CV, RCIC-CV-13CV, and RCIC-CV-15CV 1 l

CLASS: 2 CATEGORY: C and A/C j 1

FUNCTION: RCIC-CV-12CV - water sealed valve; closes for containment isolation. !

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

RCIC-CV-15CV - Opens to provide an exhaust path for the RCIC turbine; closes for primary containment isolation. I i 1 REQUIRED l 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.

l BASIS FOR DEFERRAL: 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 j closure capability or to measure the seat leakage. 1 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 staff without a compensating increase in the level of quality and safety.

- ALTERNATE TEST: The closure capability of these valves will be verified each refueling outage during the performance ofleak rate testing (15CV) per the CNS Appendix J Program, or !

by demonstrating the ability to maintain a differential pressure across the valve seat ]

l (12CV and 13CV).

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COOPER NUCLEAR STATION l THIRD INTERVAL L INSERVICE TESTING PROGRAM l

L l REFUELING OUTAGE JUSTIFICATION ROJ-11 !

VALVE: RCIC-V-37 and RCIC-V-42 CLASS: 2 CATEGORY: 'C FUNCTION: RCIC-V-37 is a containment isolation globe stop check from the RCIC turbine $

l exhaust to the suppression pool.

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

l 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 required to close for containment isolation. -

r 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, l 4.3.2.4, and 4.3.2.5.

! BASIS FOR 1 l DEFERRAL: The operators on these valves are manual operators. Exercising these valves closed l during plant operation or cold shutdown could result in undetected valve failure.

l Since the valve disk is not connected to the valve stem, the disk cannot be moved i j 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 l RCIC being unavailable to perform its design function. Although RCIC does not ,

l- have a safety function, it does provide cooling water when feedwater is l 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.

ALTERNATE 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 l (V-42).

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l COOPER NUCLEAR STATION I TIIIRD INTERVAL INSERVICE TESTING PROGRAM i

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REFUELING OUTAGE JUSTIFICATION ROJ-12 VALVE: REC-CV-16CV l CLASS: 3 CATEGORY: C t

FUNCTION: This valve closes to prevent back flow into the non-critical Reactor Equipment i Cooling (REC) return header from the suction of the REC pumps.

! 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

DEFERRAL: Testing this valve in the closed direction requires depressurization of the non- !

I 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 i j pump motor generator sets. This could not be done during normal operation I without subjecting major equipment to damage from overheating. Exercising this check valve during cold shutdown would require the intermption 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. I l

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

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L THIRD INTERVAL !

l' INSERVICE TESTING PROGRAM l l

i REFUELING OUTAGE JUSTIFICATION ROJ-13 .

l l I j VALVE: RF-CV-13CV, RF-CV-14CV, RF-CV-15CV, and RF-CV-16CV !

l CLASS: 1 CATEGORY: A/C l l

l FUNCTION: Main Feedwater check valves open to allow normal feedwater flow. Additionally, -

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

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

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

i REQUIRED l TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally [

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

BASIS FOR :

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 plant operation could cause a

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

l ALTERNATE l TEST: These valves will be exercised to the closed position during the Type C leak rate l test performed each refueling outage in accordance with the requirements of OMa

Part 10,4.3.2.2 and the CNS Appendix J Program.

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COOPER NUCLEAR STATION ,

THIRD INTERVAL INSERVICE TESTING PROGRAM i l l i REFUELING OUTAGE JUSTIFICATION ROJ-14 i VALVE: RF-CV-14CV and RF-CV-16CV CLASS: 1 CATEGORY: A/C l l I

FUNCTION: Open to provide a flowpath for HPCI (RF-CV-14CV) or RCIC (RF-CV-16CV) to l ~t he reactor vessel.

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

BASIS FOR DEFERRAL: The feedwater injection check valves are normally open during plant operation due l to feedwater flow. However, individual flow rate cannot be measured during j normal operation due to system configuration. These valves are located inside the

' drywell and are not accessible during normal operation or during cold shutdowns unless the drywell is de-inerted.

ALTERNATE TEST: Although'these valves are verified open by the normal operation of the feedwater l system, these valves will be verified to open to pass the required HPCI and RCIC i

flows during refueling outages by either a flow test or by valve disassembly and inspection.

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l COOPER NUCLEAR STATION THIRD INTERVAL L

INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-15 VALVES: RWCU-CV-15CV j CLASS: 1 CATEGORY: A/C l

l FUNCTION: Normally open Reactor Water Cleanup (RWCU) return line check valve and I

containment isolation valve.

I l 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 l 4.3.2.5.

I-BASIS FOR DEFERRAL: This valve cannot be verified as being closed upon reversal or stoppir.g 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 flow 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 l

l 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 l outages by performing a Type C local leak rate test per the requirements of OMa i

Part 10,4.3.2.4 and the CNS Appendix J Program. !

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i REFUELING OUTAGE JUSTIFICATION ROJ-16 -

VALVE: SLC-CV-12CV and SLC-CV-13CV i

. CLASS: 1 CATEGORY: A/C l FUNCTION: Inboard and outboard containment isolation valves which must open to allow i injection of sodium pentaborate (neutron poison) for reactivity control. The j t

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. ;

REQUIRED .

TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally !

l 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.

F

- BASIS FOR !

DEFERRAL: These valves are normally closed with reactor pressure on the downstream side. l Exercising these valves to the closed position during power operation would i i

require drywell entry for the inboard valve and breach of reactor coolant pressure l 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 i as a result compromising the two-valve RCS isolation barrier. Valve exercising during cold shutdown, when the drywell is deinened, 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.

. ALTERNATE TEST: The closure capability of the SLC check valves will be verified during refueling l

l outages by performing a Type C, local leak rate test per the requirements of OMa t Part 10,4.3.2.4 and the CNS Appendix J Program.

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, COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-17 VALVE: RCIC-CV-20CV and RCIC-CV-21CV CLASS: A,2 CATEGORY: C l

FUNCTION: Reactor Core Isolation Cooling (RCIC) condensate pump discharge check valves.

These valves open to provide a flow path fo: the RCIC condensate pump

!- discharge, and RCIC-CV-21CV closes to prevent diversion of RCIC pump suction

! How.

REQUIRED l TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally i

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.

l BASIS 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 verify sufficient flow to full-stroke exercise these valves open. System configuration and absence of appropriate instrumentation prohibits full stroke open l verification.

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l 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.

ALTERNATE TEST: The valves will be disassembled, inspected, and manually exercised during l refueling outages. In addition, a partial stoke exercise test to the open position will be performed quarterly and after each disassembly and inspection.

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i COOPER NUCLEAR STATION ;

THIRD INTERVAL ;

INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-18 I VALVE: RHR-CV-10CV, RHR-CV-11CV, RHR-CV-12CV, and RHR-CV-13CV j CLASS: 2 CATEGORY: C FUNCTION: Open to provide a flow path for RHR pump minimum flow.

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally l 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: There is no practical means of verifying sufficient flow to full-stroke exercise the valves open. System configuration and absence of appropriate instrumentation prohibits full-stroke open verification.

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ALTERNATE TEST: A different 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.

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COOPER NUCLEAR STATION TIIIRD INTERVAL INSERVICE TESTING PROGRAM REFUELING OUTAGE JUSTIFICATION ROJ-19 l I

l VALVE: PC-CV-13CV and PC-CV-14CV l CLASS: 2 CATEGORY: A/C FUNCTION: Open to provide vacuum relief for the suppression chamber.

REQUIRED TEST: OM Part 1,1.3.4.3 requires primary containment vacuum relief valves to have

individual operability tests nominally every 6 months.

BASIS FOR DEFERRAL: 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 !

l the suppression chamber and are part of the primary containment boundary.

Access to these valves is hazardous 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 l of quality and safety.

l ALTERNATE l

TEST: 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.

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COOPER NUCLEAR STATION :

THIRD INTERVAL l

INSERVICE TESTING PROGRAM t I ;

REFUELING OUTAGE JUSTIFICATION ROJ-20 j VALVE: HPCI-CV-17CV CLASS: 2 CATEGORY: C '

l FUNCTION: HPCI-CV-17CV - Opens to provide a flowpath for HPCI pump minimum flow; closes to prevent diversion of RHR suppression pool cooling.

3

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 l 4.3.2.5.

BASIS FOR DEFERRAL: There is no practical means of verifying sufficient flow to full-stroke exercise this valve open. System configuration and absence of appropriate instrumentation j prohibits full-stroke open verification.

i ALTERNATE TEST: The valve will be disassembled, inspected and manually exercised during each l refueling outage. In addition, a partial stroke exercise test, with flow, will be performed quarterly, and after each disassembly / inspection.

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COOPER NUCLEAR STATION l THIRD INTERVAL i INSERVICE TESTING PROGRAM !

1 E. Valve Relief Requests l

RR No. Description

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RV-01 Hot Shutdown Component Testing i RV-02 CRD-AOV-CV126, CRD-AOV-CV127, and CRD-CV-114CV (typical of i 137) Exercising By Scram Testing l RV-03 CRD-CV-115CV (typical of 137) Testing to the Closed Position RV-04 CRD-CV-138CV (typical of 137) Test Method RV-05 CRD-SOV-SO120, SO121, SO122, and SO123 (Typical of 137) Test Method I

RV-06 CS-CV-12CV, CS-CV-13CV, CS-CV-14CV, and CS-CV-15CV Testing to the Closed Position RV-07 HPCI-CV-18CV and 19CV Testing to the Closed Position RV-08 HPCI-SOV-SSV64 and SSV87 Disassembly Testing Frequency i

RV-09 MS-RV-71 ARV to 71HRV Exercising Testing Frequency RV-10 Excess Flow Check Valves Testing Per Technical Specifications RV-11 RCIC-CV-18CV and 19CV Testing to the Closed Position l RV-12 RHR-CV-18CV,19CV,24CV, and 25CV Testing to the Closed Position RV-13 SW-MOV-MO89A and MO89B Testing Relief RV-14 HPCI-CV-24CV, 25CV, 26CV, 27CV, RCIC-CV-22CV, 23CV, 24CV, and 25CV Testing Relief i

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-01 VALVE: Non-component Specific CLASS: All CATEGORY: All FUNCTION: Various ,

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.

BASIS FOR l RELIEF: Cooper Nuclear Station's accident analyses do not carry the response to an accident I (e.g. Design Basis LOCA) to a point beyond the hot shutdown condition (i.e., to a !

cold shutdown condition). The licensing basis does not require the plant to go to l the cold shutdown condition in order to satisfy 10CFR100 radiological release l guidelines.

I 4 Since Safe Shutdown is defined in the CNS licensing basis as the hot shutdown I 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 shutdown)

I 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 IST or Augmented Test l Programs.

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INSERVICE TESTING PROGRAM RELIEF REQUEST RV-02 VALVE: CRD-AOV-CV126, CRD-AOV-CV127, and CRD-CV-114CV (typical of 137) l CLASS: 1, 2 CATEGORY: B, C i FUNCTION: CRD-AOV-CV126 - Open with a scram signal to pressurize the lower side of the l CRDM pistons from the accumulator or from the charging water header. i i

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 flow from the top of the CRDM pistons to the scram discharge header.

REQUIRED 1) OMa Part 10, 4.2.1.1 requires Category A and B power operated valves to be l TEST: individually full stroke exercised nominally every 3 months, except as provided by i

paragraphs 4.2.1.2, 4.2.1.5, and 4.2.1.7.

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, i 4.3.2.4, and 4.3.2.5.

BASIS 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 I 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 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 open. Thus, each time a scram signal is L

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l COOPER NUCLEAR STATION !

THIRD INTERVAL INSERVICE TESTING PROGRAM i l

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 i 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.

ALTERNATE TEST: Scram testing per Technical Specifications will be substituted for all Section XI requirements. The test frequency will be 10% each 16 weeks and 100% each refueling cycle. Valve stroke times will not be measured. This testing method is consistent with GL 89-04, position 7.

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COOPER NUCLEAR STATION

( THIRD INTERVAL INSERVICE TESTING PROGRAM I 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.

BASIS 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 flow 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.

l 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 l 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

! shall be verified by isolating each of the CRD scram accumulators and venting l pressure on the upstream side of the check valve. Accumulator pressure decay l would be observed should the respective valve fail to close properly.

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) THIRD INTERVAL INSERVICE TESTING PROGRAM 3

RELIEF REQUEST RV-04 4

VALVES: CRD-CV-138CV (typical of 137) l CLASS: 2 CATEGORY: C

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4 FUNCTION: Close in the event of a scram to prevent diversion of pressurized HCU accumulator water to the cooling water header.

. REQUIRED j 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.

3 BASIS FOR RELIEF: Normal control rod motion will verify that the associated cooling water check i

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 89-04, position 7.

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ALTERNATE i

TEST: During normal plant operation above 30 percent power, each partially or fully l 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 rod is successfully exercised.

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I COOPER NUCLEAR STATION !

THIRD INTERVAL !

INSERVICE TESTING PROGRAM RELIEF REQUEST RV-05 :

VALVES: CRD-SOV-SO120, SO121, SO122, and SO123 (Typical of 137) ;

i CLASS: 1 CATEGORY: B )

FUNCTION: Close to provide Class 1 to Non-Code Class boundary isolation.

REQUIRED TEST: OMa Part 10, 4.2.1.1 requires Category A and B 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. l BASIS FOR 1 RELIEF: During normal operation these valves are used for control rod insertion and !

withdrawal. They are normally closed and must remain closed to prevent diverting water during a scram. They are exercised open and closed during normal operation of the associated CRD. They are not equipped with position indication, j This testing method for the CRD insert and withdrawl solenoid valves is consistent I with GL 89-04, position 7.

ALTERNATE l 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). One pair of these solenoids is exercised when the associated CRD is withdrawn a notch, and the other pair is exercised when the CRD is inserted a notch. Proper operation of the CRD verifies the operation of the

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associated solenoid valves.

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'IIIIRD INTERVAL j INSERVICE TESTING PROGRAM -

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r RELIEF REQUEST RV-06

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VALVE: CS-CV-12CV, CS-CV-13CV, CS-CV-14CV, and CS-CV-15CV l CLASS: 2, A (outboard) CATEGORY: C i

l l FUNCTION: Core Spray (CS) Loop A and Loop B 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.

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 RELIEF: These valves are normally closed check valves (with two in series). They open as necessary to keep the CS system in a solid standby condition, which is not a safety function. When the CS pumps start, these valves close to ensure maximum flow to the reactor. The current system design does not allow testing to ensure both valves have closed.

l Only one valve is required to close to prevent diversion of flow. However, the l' valves cannot be tested individually. Thus both valves will be tested together.

l When a CS Pump is started, should both valves fail to close, a relief valve would l lift or a pressure sensor would alarm on the condensate supply side of the valves.

l ALTERNATE TEST: The check valves in each loop will be tested closed simultaneously to assess the j operational readiness of each pair of valves. ;

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!- COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-07 VALVE: HPCI-CV-18CV and HPCI-CV-19CV CLASS: 2, A (outboard) CATEGORY: C FUNCTION: High Pressure Coolant Injection (HPCI) pressure maintenance check valves from the condensate supply system. These valves open to maintain the HPCI system solid and close to prevent diversion of HPCI injection 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.

BASIS FOR RELIEF: These valves are normally closed check valves (in series). They are open as necessary to keep the HPCI system in a solid standby condition, which is not a safety function. When the HPCI pumps start, these valves close to ensure maximum flow to the reactor. The current system design does not allow testing to ensure both valves have closed.

Only one valve is required to close to prevent diversion of flow. However, the valves cannot be tested individually. Thus both valves will be tested together.

When a HPCI 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.

ALTERNATE TEST: The check valves will be tested closed simultaneously to assess the operational readiness of the pair of valves.

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THIRD INTERVAL

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INSERVICE TESTING PROGRAM i j RELIEF REQUEST RV-08 l

VALVE: HPCI-SOV-SSV-64 and HPCI-SOV-SSV87 CLASS: 2 CATEGORY: B i

] FUNCTION: The IIPCI turbine and exhaust steam drip leg drain to gland condenser (HPCI- !

SOV-SSV64) and HPCI turbine and exhaust steam drip leg drain to equipment i i

drain isolation valve (HPCI-SOV-SSV87) have an active safety function in the l closed position to maintain pressure boundary integrity of the HPCI turbine l exhaust line. These valves serve as a Class 2 to Non-Code boundary barrier. ;

i REQUIRED OMa Part 10,4.2.1 requires Category A and B power operated valves to be

j. TEST: individually full stroke exercised and stroked timed nominally every 3 months,

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4 except as provided by paragraphs 4.2.1.2,4.2.1.5, and 4.2.1.7.

i i 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 i accordance with the exercising frequency of paragraph 4.2.1.1.

BASIS FOR - These valves are rapid acting, encapsulated, solenoid operated valves. Their j RELIEF: 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 !

l received from the associated level switches HPCI-LS-98 and HPCI-LS-680. Both i valves receive a signal to change disc position during operability testing of drain j pot level switches. However, remote position indication is not provided for i positive verification of disc position.. Additionally, their design prohibits the l ability to visually verify the physical position of the operator, stem or internal

! components. Modification of the system to verify valve closure capability and j stroke timing is not practicable nor cost beneficial since no commensurate increase l in safety would be derived. Quarterly partial stroke exercising of these valves is impracticable for the same reasons.

ALTERNATE j

TEST: One solenoid valve shall be disassembled and inspected each refueling outage. If the disassembled valve exhibits signs of degradation of either valve internals or coil

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electrical characteristics, the other valve shall be disassembled and inspected prior i

to restart.

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, THIRD INTERVAL INSERVICE TESTING PROGRAM i

RELIEF REQUEST RV-09

i l VALVE: MS-RV-71 ARV, BRV, CRV, DRV, ERV, FRV, GRV, and HRV CLASS: 1 CATEGORY- B/C FUNCTION: 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. !

REQUIRED TEST: OMa Part 10,4.2.1 requires Category A and B 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.

BASIS FOR RELIEF: These valves are power actuated safety relief valves for the main steam lines.

Each valve is exercised during startup following refueling outages. Exercising these valves during power operations can cause pressure, temperature, and reactivity transients.

t Exercising during cold shutdown is impracticable since a minimum of 50 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. Successful exercising will verify operational readiness. Should a relief valve fail to function as designed, corrective action is required.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST RV-09 (Continued)

ALTERNATE TEST: Full stroke exercise tests of these valves open and closed, without stroke timing, will be performed during each refueling outage, in addition to testing to the requirements of OM-1987, Part 1, Paragraph 3.3.1.1.

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1 COOPER NUCLEAR STATION ;

THIRD INTERVAL INSERVICE TESTING PROGRAM i i

4 RELIEF REQUEST RV-10 ;

VALVES: Excess Flow Check Valves i i

CLASS: 1- CATEGORY: A/C I FUNCTION: The excess flow check valves are installed in instrument lines that provide signals i

_ for operation of safety-related pumps and valves. They prevent excess flow of reactor water should an instrument line break outside containment.

REQUIRED 4

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.

Testing in accordance with OMa Part 10,4.3.2.4 requires 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 j other indicators such as changes in system pressure, flowrate, level, temperature, i seat leakage testing or other positive means.

, BASIS FOR

RELIEF: Uninterrupted function of these valves is essential for safety. Routine testing in i accordance with Section'XI would cause instrument line interruptions. This would

disable instruments required for safe phnt operations, safety-system actuation, j reactor shutdown, or sensing accident conditions. In addition, these valves cannot

! be exercised during cold shutdown because removal of multiple instruments from i : service could prevent or intermpt the operation of systems required for decay heat

removal.

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The excess flow check valves are tested using a modified leak-rate test to assess !

operability. Testing is performed at least once each operating cycle in accordance with Technical Specification 4.7.D.1.c. Testing more frequently could jeopardize the safety of the reactor.

ALTERNATE TEST: In lieu of Section XI testing, a modified leak-rate test will be performed at least once each operating cycle.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l

RELIEF REQUEST RV-11 VALVE:

RCIC-CV-18CV and RCIC-CV-19CV CLASS: 2, A (outboard) CATEGORY: C l FUNCTION: Reactor Core Isolation Cooling (RCIC) pressure maintenance check valves from l the condensate supply system. These valves open to maintain the RCIC system solid and close to prevent diversion of RCIC injection flow.

L 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.

1 BASIS FOR l RELIEF: These valves are normally closed check valves (in series). They open as necessary l to keep the RCIC system in a solid standby condition, which is not a safety function. When the RCIC pumps start, these valves close to ensure maximum flow to the reactor. The current system design does not allow testing to ensure both

- valves have closed.

1 Only one valve is required to close to prevent diversion of flow. However, the valves cannot be tested individually Thus both valves will be tested together.

When a RCIC 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.

ALTERNATE TEST: The check valves will be tested closed simultaneously to assess the operational readiness of the pair of valves.

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COOPER NUCLEAR STATION - l THIRD INTERVAL I INSERVICE TESTING PROGRAM f

f RELIEF REQUEST RV-12 ,

VALVE: RHR-CV-18CV, RHR-CV-19CV, RHR-CV-24CV, and RHR-CV-25CV ;

CLASS: 2, A (outboard) CATEGORY: C !

FUNCTION: Residual Heat Removal (RHR) Imop A and Loop B pressure maintenance check valves from the condensate supply system. These valves open to maintain the j l

RHR system solid and close to prevent diversion of LPCI injection flow. !

I 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.

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BASIS FOR l RELIEF: These valves are normally closed check valves (with two in series). They open as ,

necessary to keep the RHR system in a solid standby condition, which is not a j safety function. When the RHR pumps start, these valves close to ensure '

maximum flow to the reactor. The current system design does not allow testing to ensure both valves have closed. i l 1 Only one valve is required to close to prevent diversion of flow. However, the l l valves cannot be tested individually. Thus, both valves will be tested together. I

When a RHR Pump is started, should both valves fail to close, a relief valve would l lift or a pressure sensor would alarm on the condensate supply side of the valves.

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! ALTERNATE l TEST: The check valves in each loop will be tested closed simultaneously to assess the operational readiness of each pair of valves.

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COOPER NUCLEAR STATION THIRD INTERVAL -

l INSERVICE TESTING PROGRAM i f

j RELIEF REQUEST RV-13 ;

I I VALVE: SW-MOV-MO89A and SW-MOV-MO89B i i i CLASS: 3 CATEGORY: 'B l

! FUNCTION: Loop A and Loop B outlet isolation for the Service Water booster pump cooling i l ' water to the RHR heat exchangers. These normally closed valves have an active i l safety function in the throttled position to provide a flow path for cooling water l l flow through the RHR heat exchangers during transient and ar.cident conditions. 3 REQUIRED TEST: OMa Part 10,4.2.1 requires Category A and B power operated valves to be !

j. 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 L i

! BASIS FOR l l RELIEF: These valves are exercised during quarterly Service Water Booster Pump flow ;

l testing to a throttled position required to satisfy Technical Specification flow l requirements. Valve stroke timing to the fully opened position is impracticable, j l Full opening will cause RHR Ser tice Water Booster 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 f repeat due to the absence of normal valve control switches and would not contribute meaningful data to utilize in monitoring valve degradation, l

ALTERNATE TEST: These valves will be exercised to their safety-related throttled position every three months, but stroke times will not be measured.

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THIRD INTERVAL {

INSERVICE TESTING PROGRAM )

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RELIEF REQCEST RV-14 i i

VALVE: HPCI-CV-24CV, HPCI-CV-25CV, HPCI-CV-26CV, HPCI-CV-27CV, RCIC- l CV-22CV, RCIC-CV-23CV, RCIC-CV-24CV, and RCIC-CV-25CV l 1

l CLASS: 2 CATEGORY: C !-

L FUNCTION: HPCI and RCIC Turbine Exhaust Line Vacuum Breakers open to prevent

! siphoning suppression pool water into the exhaust ime.

l REQUIRED l TEST: OM Part 1, 3.3.2.3(a) requires vacuum relief valves to be individually actuated to i verify open and close capability, set pressure, and performance of any pressure and

! position sensing accessories.

BASIS FOR '

l RELIEF: These valves are normally closed check valves with two in series. The RCIC !

l valves are lift clieck vahes, and the HPCI valves are swing check valves. In the closed position they prevent steam from the exhaust line entering the free space of ;

the suppression chamber. 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 i due to steam condensing when the associated HPCI or RCIC systems are isolated.

Each pair of valves is cross connected so that a single failure will not prevent the vacuum relief function. Due to the configuration neither a closure test nor a set pressure test cf the inboard valves or the RCIC outboard valves can be performed.

ALTERNATE TEST: Each valve will be disassembled, inspected, and manually exercised open and closed during each refueling outage. In addition, the outboard HPCI vacuum relief valves will be set point tested in place.

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COOPER NUCLEAR STATION i THIRD INTERVAL INSERVICE TESTING PROGRAM F. Augmented Valve Cold Shutdown Test Justifications ;

ACSJ No. Description ACSJ-01 CRD-CV-25CV and CRD-CV-26CV Closure Test Frequency ACSJ-02 DGSA-CV-14CV, DGSA-CV-15CV, DGSA-CV-16CV, and DGSA-CV- I 17CV Closure Test Frequency [

ACSJ-03 HV-AOV-263AV, HV-AOV-265AV, HV-AOV-267AV, HV-AOV-269AV, HV-MOV-262MV, HV-MOV-264MV, HV MOV-266MV, and HV-MOV-268MV Closure Test Frequency ;

i ACSJ-04 IA-CV-54CV, IA-CV-55CV, IA-CV-56CV, IA-CV-57CV, IA-CV-58CV, '

IA-CV-59CV, IA-CV-60CV, and IA-CV-111CV Closure Test Frequency l i

ACSJ-05 SGT-CV-14CV and SGT-CV-15CV Open and Closure Test Frequency 1

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I COOPER NUCLEAR STATION l THIRD INTERVAL -I INSERVICE TESTING PROGRAM l l

AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-01 VALVES: CRD-CV-25CV and CRD-CV-26CV i I

CLASS: A CATEGORY: A/C i

I FUNCTION: Close to prevent possible CRD bypass leakage from exiting secondary containment.

t 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.

l BASIS FOR DEFERRAL: 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 CRD

, pumps supplying drive water and charging water to the control rod's Hydraulic l Control Units (HCUs). During power operations these valves are open since drive water is constantly supplied to the HCUs. Closure or partial closure testing would I require the CRD pumps to be secured and the portion of the system containing l

these valves to be isolated. Isolating the valves or securing the CRD pumps '

I terminates the constant drive water supply to the HCUs, which causes all the !

control rods to be inoperable. All control rods inoperable during power operations puts the plant into a Technical Specification LCO requiring shutdown within 24 l hours, which is operationally undesirable. Also, without a continuous charging l water supply, HCU accumulators would eventually depressurize, since the associated accumulator check valves are not designed to be leak tight, j Administrative controls require a scram initiation upon depressurization of two L accumulators, which is a highly undesirable situation.

l The interruption of the drive water flow would also interrupt CRD seal water l cooling to the Reactor Recirculation pumps. Stopping of flow would impose a

! severe thermal transient on the RR pump seals, which could possibly lead to l premature seal failure.

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i l COOPEP. NUCLEAR STATION l

THIRD INTERVAL

! INSERVICE TESTING PROGRAM AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-01 (Continued) l l

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 ASME Section XI.

ALTERNATE-TEST: Valve exercising, to the closed position, will be performed during cold shutdown ;

by establishing a differential pressure across the valve seat. This test requires the J recirculation and reactor water cleanup pumps to be removed from service.

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l THIRD INTERVAL l INSERVICE TESTING PROGRAM )

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l l AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-02 l

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VALVES: DGSA-CV-14CV, DGSA-CV-15CV, DGSA-CV-16CV, and DGSA-CV-17CV !

CLASS: A CATEGORY: C i

l FUNCTION: Opens to provide sufficient starting air to start the diesel generators on loss of site l electrical power and closes to provide system isolation and redundancy.

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

l BASIS FOR _

DEFERRAL: Exercising these valves to the closed pc.,. tion requires isolating both emergency l diesel generator starting air receivers causing the related emergency diesel {

generator to be considered inoperable during the test. Due to the importance of the i diesel generator with respect to plant safety, intentionally creating an inoperable - 1 condition during plant operation is not justifiable. These valves are not within the scope of ASME Section XI. .

ALTERNATE TEST: Valve exercising to the closed position will be performed during cold shutdown.

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i l COOPER NUCLEAR STATION i THIRD INTERVAL INSERVICE TESTING PROGRAM l

l AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-03 VALVES: HV-AOV-263AV, HV-AOV-265AV, HV-AOV-267AV, HV-AOV-269AV, HV-MOV-262MV, HV-MOV-264MV, HV-MOV-266MV, and HV-MOV-268MV CLASS: A CATEGORY: B 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.

REQUIRED TEST: 1) OMa Part 10, 4.2.1.1 requires Category A and B 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 requires 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.

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BASIS FOR DEFERRAL: These valves are required to remain in the open position during power operation to 'I support reactor recirculation pump operation. Closure of these valves during reactor operation could result in overheating the MG set which would compromise l

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 ASME Section XI. !

1 ALTERNATE TEST: 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 be fail-safe tested during cold shutdowns when the reactor recirculation pumps are in I 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.

i Revision 1 Section V Page 138 of 153 l

j COOPER NUCLEAR STATION.

THIRD INTERVAL' INSERVICE TESTING PROGRAM AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-04

. I VALVE: IA-CV-54CV, IA-CV-55CV, IA-CV-56CV, I A-CV-57CV, IA-CV-58CV, IA-CV-59CV, IA-CV-60CV, and IA-CV-111CV

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FUNCTION: IA-CV-54CV, IA-CV-55CV, IA-CV-56CV, IA-CV-57CV, IA-CV-58CV, IA-CV-59CV, IA-CV-60CV, and IA-CV-111CV - 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 IA supplies are for various safety related H&V system l AOV's. l l REQUIRED I l TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally )

l every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and I

! 4.3.2.5.

i BASIS FOR )

DEFERRAL: The acceptance test for these check valves requires that the IA supply piping .

upstream of the check valves to the associated accumulators be isolated and 5' j depressurized. The accumulator pressure.is then monitored for one hour to verify j that the check valve will hold. Isolation and depressurization of these IA lines will place these systems in an inoperable condition. The following summarizes the :

specific system impacts.

IA-CV-54CV, -55CV, and -56CV are in the IA supply lines to the Reactor Building supply and exhaust isolation dampers. Isolation and testing of these valves affects the operation of the Reactor Building H&V system which controls area air flows and pressures.

i IA-CV-57CV, -58CV, -59CV, AND 60CV are in the IA supply lines to the H&V supply and exhaust for the MG Set 1 A and IB. Isolation and testing of these valves potentially affects the operation of the MG Sets.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-04 CONTINUED IA-CV-111CV is in the IA supply line for the Control Room Emergency Bypass Filter inlet valve. Isolation and testing of this valve affects the operation of this filter train. Therefore, it is impracticable to perfonn a reverse flow leakage test of these check valves during power operations. These valves are not within the scope of ASME Section XI.

ALTERNATIVE TEST: A reverse flow leakage test of these check valves will be performed during cold shutdown conditions.

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I' i l COOPER NUCLEAR STATION !

THIRD INTERVAL l INSERVICE TESTING PROGRAM AUGMENTED COLD SHUTDOWN JUSTIFICATION ACSJ-05 l 1

VALVES: SGT-CV-14CV and SGT-CV-15CV '

CLASS: A CATEGORY: C l

REQUIRED TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally i 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.

l; FUNCTION: Open to provide flow paths from their respective SGT filter trains. Close to prevent back flow from the operating SGT train discharge. ;

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BASIS FOR l DEFERRAL: The acceptance full flowrate for these valves is > 1602 cfm. During plant power l l operations, system conditions exist that prevent the SGT system from achieving a l flowrate of > 1602 cfm. Reactor building differential pressure and back pressure l from the Off Gas Dilution Fans act against SGT system pressure restricting SGT system flowrate. Therefore, it is impracticable to perform a full flowrate test of these valves at power operations. A full flow test is the only means to verify the closure of the idle train check valve. These valves are not within the scope of ASME Section XI.

ALTERNATE TEST: A partial open and closed 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, i

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! G. Augmented Valve Refueling Outage Justifications

! I AROJNo. Description l AROJ-01 IA-CV-17CV, IA-CV-18CV, I A-CV-19CV, IA-CV-20CV, IA-CV-21CV, IA-CV-22CV, IA-CV-36CV, and IA-CV-37CV Closure Test Frequency l AROJ-02 IA-CV-28CV through IA-CV-CV35 Closure Test Method and Frequency AROJ-03 Withdrawn l AROJ-04 SIL-CV-12CV and SLC-CV-13CV Opening Test Frequency i

i AROJ-05 SLC-CV-10CV and SLC-CV-11CV Opening and Closure Test Frequency i

, AROJ-M Withdrawn l

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l AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-01 i VALVE: IA-CV-17CV, IA-CV-18CV, IA-CV-19CV, IA-CV-20CV, IA-CV-21CV, l IA-CV-22CV, IA-CV-36CV, and IA-CV-37CV l CLASS: A CATEGORY: A/C !

r FUNCTION: Instnament Air / Nitrogen supply inlet check valves for Main Steam Relief Valve !

(SRV) accumulators. These check valves must be capable of closure to maintain l i accumulator integrity in the event of a loss of normal actuating air supply. )

i i REQUIRED L l TEST: OMa Part 10, 4.3.2.1 requires check valves to be individually exercised nominally :

l every 3 months, except as provided by paragraphs 4.3.2.2,4.3.2.3,4.3.2.4, and [

l 4.3.2.5. j BASIS FOR j DEFERRAL: These valves are located inside the drywell and are inaccessible during normal l operations or cold shutdowns. They cannot be exercised during each cold-shutdown because the drywell is not routir.ely deinerted each cold shutdown. ,

Valve exercising during cold shutdown, when the drywell is deinerted, could delay l 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 ASME Section XI.

l ALTERNATE

TEST: 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 refueling outage to verify valve closure.

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Revision 1 Section V Page 143 of 153 i

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l

l AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-02 ,

i VALVE: IA-CV-28CV through IA-CV-CV35 (

, CLASS: A CATEGORY: A/C i FUNCTION: Close to isolate individual Main Steam Isolation Valve accumulators for emergency l gas supply.

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 DEFERRAL: These eneck 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 i normal cold shutdowns. The complexity of the pressure decay test could delay plant startup after 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 ASME Section XI. .

ALTERNATE TEST: A pressure decay test will be performed each refueling outage to verify valve ;

closure.

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4 Revision 1 Section V Page 144 of 153

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, COOPER NUCLEAR STATION I

THIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-03

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l Revision 1 Section V Page 145 of 153

, COOPER NUCLEAR STATION THIRD INTERVAL r INSERVICE TESTING PROGRAM ,

AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-04 .!

VALVE: SLC-CV-12CV and SLC-CV-13CV i

l CLASS: 1 CATEGORY: A/C l

l FUNCTION: 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.

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l 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. ;

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BASIS FOR DEFERRAL: These valves are normally closed with reactor pressure on the downstream side. -

Exercising these valves to the open position during power operation would require l firing the upstream squib valve and injecting demineralized water from the test l tank to the reactor vessel. This activity would not only require flushing the system ,

of sodium pentaborate prior to testing, but would also subject the SLC injection nozzle to thermal transients due to the relatively cold demineralized water :

l 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 restart due to the measures required to prevent inadvertent admission of boron to the reactor coolant system resulting in the potential for an imbalance in reactor water chemistry. The open function of these valves is not within the scope of ASME Section XI.

ALTERNATE TEST: The opening capability of the SLC check valves will be verified during refueling

, outages by performing a vessel injection from the SLC system as required by l Technical Specification 4.4.A.2.c.

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Revision 1 Section V Page 146 of 153

l l COOPER NUCLEAR STATION

! THIRD INTERVAL INSERVICE TESTING PROGRAM l AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-05

! VALVE: SLC-CV-10CV and SLC-CV-11CV CLASS: A CATEGORY: C l FUNCTION: The SLC pump discharge check valves are required to open for sodium pentaborate ,

i 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.

l 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 l

4.3.2.5.

BASIS FOR l DEFERRAL: These pump discharge check valves are located in a segment of piping which is not f provided with upstream vent / drain connections 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 l 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 exposure is low, this is an undesirable ALARA practice. The burden of performing a quarterly RT is not justified based on the previous discussion. These valves are not within the scope of ASME Section XI.

j ALTERNATE l TEST: Valve closure capability shall be verified each refueling outage by performing radiography on the valve seating area.

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COOPER NUCLEAR STATION >

THIRD INTERVAL' l INSERVICE TESTING PROGRAM i AUGMENTED REFUELING OUTAGE JUSTIFICATION AROJ-06 l

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COOPER NUCLEAR STATION THIRD INTERVAL i

INSERVICE TESTING PROGRAM !

H. Augmented Valve Relief Requests ARV No. Description ARV-01 DGDO-FOV-FLTV10, DGDO-FOV-FLTV11, DGDO-SOV-SSV5028, and DGDO-SOV-SSV5029 Test Method l ARV-02 DGSA-SOV-SPV1, DGSA-SOV-SPV2, DGSA-SOV-SPV3, DGSA-SOV-SPV4, DGSA-AOV-AV5, DGSA-AOV-AV6, DGSA-AOV-AV7, and DGSA-AOV-AV8 Test Method ARV-03 DG-AOV-MB1 and DG-AOV-MB2 Test Method l

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Revision 1 Section V Page 149 of 153

COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED RELIEF REQUEST ARV-01 VALVE: DGDO-FOV-FLTV10, DGDO-FOV-FLTV11, DGDO-SOV-SSV5028, and DGDO-SOV-SSV5029 CLASS: A CATEGORY: B and C (FLTV-10/11)

FUNCTION:

The DG Day Tank Inlet valves ( DGDO-FOV-FLTV-10, FLTV-11) have an active safety function in the closed position to prevent overfilling of the associated Day Tank during fuel oil transfer operations. These float operated inlet valves also have j an active safety function in the open position to permit filling of the associated i Diesel Fuel Tanks.

i l 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-l FLTV-10, FLTV-11) 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 B 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.

l DGDO-SOV-SSV5028, and 50-29 also require testing to the fail safe open 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 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. '

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM !

l AUGMENTED RELIEF REQUEST ARV-01 (Continued) ;

i' BASIS FOR RELIEF: Float valves, DGDO-FOV-FLTV-10/11 are encapsulated float operated valves and I are not provided with remote position indication or remote manual switching i capability. DGDO-SOV-SSV-5028,5029 are encapsulated solenoid valves and

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are not provided with remote position indication or remote manual switches. Other l positive means such as flow or pressure indication are not provided in the piping circuit. The design of these valves prohibits visual verification of the physical l position of the valve operator, stem, or internal components. The float valve i closes at 54 inches. Should the float valve fail to close, the solenoid valve will i close at 58.5 inches. Modification of the system to verify individual valve exercising capability is not practicable nor cost beneficial since no commensurate t 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: i 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 open by observing resteration of day tank level. The float valves shall be verified closed by the lack of continuous rise i in level once proper volume is achieved. The sound of solenoid movement shall be used to verify valve movement to the closed position.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM l AUGMENTED RELIEF REQUEST ARV-02 f

VALVE: DGSA-SOV-SPV1, DGSA-SOV-SPV2, DGSA-SOV-SPV3, DGSA-SOV-SPV4, DGSA-AOV-AV5, DGSA-AOV-AV6, DGSA-AOV-AV7, and DGSA-AOV-AV8 CLASS: A CATEGORY: B FUNCTION: Diesel Generator Air Start Valves direct starting air to the emergency diesel generators.

REQUIRED TEST: OMa Part 10,4.2.1 requires Category A and B 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.

l BASIS FOR RELIEF: 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 XI. NRC approval of this relief request is not required.

l ALTERNATE l TEST: Starting the respective standby emergency diesel generator using the air start l 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 valves will be tested when the diesel generators are tested. Satisfactory diesel testing will

, satisfy valve exercising requirements. Each air start valve train will be exercised l during this testing at least quarterly.

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COOPER NUCLEAR STATION THIRD INTERVAL INSERVICE TESTING PROGRAM AUGMENTED RELIEF REQUEST ARV-03 VALVE: DG-AOV-MBI and DG-AOV-MB2 l CLASS: A CATEGORY: B FUNCTION: Diesel Generator Muffler Bypass Valves.

REQUIRED TEST: OMa Part 10,4.2.1 requires Category A and B 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.

BASIS FOR RELIEF: 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.

j 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.

ALTERNATE

. TEST: A pressure signal will be supplied to actuate the bypass valves. Each muffler bypass valve will be exercised open and fail safe tested at least quarterly. Stroke timing will not be performed.

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