ML17334B356

Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.

ML17334B356
Person / Time
Site:	Cook
Issue date:	02/05/1990
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17334B354	List: ML17334B353 ML17334B355 ML17334B356 ML17334B357
References
AEP:NRC:0969R, AEP:NRC:969R, PROC-900205-01, NUDOCS 9003090183
Download: ML17334B356 (373)

Text

ASME SECTION XI VALVE TEST PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D.C.COOK NUCLEAR POWER STATION UNIT NO 2 Revision No: 3 Date: 2-5-90 TABLE OF CONTENTS l.INTRODUCTION

-(FIGURE-l)2.LIST OF DRAWINGS-(FIGURE-2)3.NOMENCLATURE FOR TEST METHODS-(FIGURE-3)4.RELIEF REQUEST/COLD SHUTDOWN JUSTIFICATION NOTES 5.ATTACHMENT-A 6.VALVE

SUMMARY

SHEETS 7.FLOW DIAGRAMS 9003090183 9002ih PDR ADQCN, 050003i5 P PNU page l of Sl ASME SECTION XI VALVE TEST-PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D.C.COOK NUCLEAR POWER STATION UNIT NO.2 Revision No: 3 Figure-1 Date: 2-5-90 INTRODUCTION Valve Testin Pro ram A'-The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the 1983 edition of the ASME Boiler and Pressure Vessel Code through Summer 1983 Addenda, except for specific relief requests which are identified in the Valve Summary Sheet.B.The valve test program is applicable for the second 10 year inspection interval which commences on July 1, 1986.C.The valve test program was developed employing the classification guidelines contained in 10 CFR 50.2(v)for Quality Group A and Regulatory Guide 1.26,-Revision 3 for Quality Groups B and C.(Quality Group A is the same as ASME Class 1, Group B is 2, and Group C is 3).NRC staff guidance was provided by memorandum dated January 16, 1978.D-Figure 2 identifies the system flow diagrams which were used to develop this valve test program.,Valve Summary Sheets contain the following:

• E*Flow Dia ram: Unit Number-Flow diagram number-Revision Number (e.g., 2-5105B-42)

• Valve Number: Unique valve number (e.g., 2-DCR-310)

Page 2 of 81 D.C.Cook Nuclear Plant Revision No: 3 Date: 2-5-90 Valve Test Program Figure-l*Revision Number: Any change of valve description, function or test requirement.

• ~B~W'EL-CK BF GA GL DA 3W ND AG BL VB Relief and Safety Check Butterfly Gate Globe Diaphragm Three-Way Needle Angle Ball Vacuum Breaker (Reverse Check Valve)*Valve Size: Nominal valve size in inches*Valve Actuator T e: Type of actuator, one of the following:

SA-Self Actuated (e.g., CK or REL)MO-Motor Operated A-Air Operated M-Manual PO-Pneumatic SO-Solenoid Operated*Flow Dia ram Coordinates:

Alpha/Numeric grid location of valve Page 3 of Sl

Revision No: 3 D.C.Cook Nuclear Plan Valve Test Program Figure-l Date: 2-5-90*Valve osition during normal plant operation or during performance of its safety function, one of the following:

0 C 0/C Open Closed Open/Closed or vice versa*Code Class: ASME Code class of valve, either l, 2, or 3*Valve Status-A P: Active or passive w v defined in IWV-2200 NOTE: Combinations are possible (e.g., AC)Prima Test Re'd: Test required per Section XI*Test Performed:

Testing that will be performed NOTE: Test nomenclature is explained in Figure 3*Test Mode Test Fre enc: One of the following:

P-Every 3 months while system is required to be operable.C-Testing will be performed at cold shutdown frequency (See Note<(Fn)R-Testing will be performed at refueling outage frequency.

Page 4 of 8l D.C.Cook Nuclear Plan Valve Test Program Revision No: 3 Date: 2-5-90 Figure-1*Code Relief: Whether or not a code relief is being requested; will be one of the following:

NO NO, NOTE X NO, CSZ Y YES, NOTE Z Valve is to be tested per code, no comments.Valve is to be tested per code, but there are comments.Valve is to be tested per code at a cold shutdown frequency with cold shutdown justification provided in notes.Code relief is requested.

Alternate testing is proposed in lieu of that required by code, the note explains why the code relief is requested.

E.Alternative testing performed on'check valve in accordance with GL-89-04, Attachment 1, Item g2 is indicated under relief request notes.This testing is performed in lieu of stroke testing required by Section XI, IWV-3521.This is accomplished by disassembly method in the following manner: Disassembl Method The valve bonnet is removed, the disc is-manually full stroke exercised and the valve internals are visually examined.The results of this examination are documented.

This will be performed on a refueling outage frequency.

The valve groupings for sample disassembly is in accordance with GL-89-04.This alternative testing to be performed for a particular valve is indicated on the valve summary sheets and relief request notes.Page 5 of 81 D.C.Cook Nuclear Plan Valve Test Program=Revision No: 3 Date: 2-5-90 Figure-1 F.Schedulin of Valve Testin at Cold Shutdown Fre enc.Valves tested at a cold shutdown frequency shall be scheduled using the following criteria: 2~3.4~Valve exercising need not be done more often than once every 3 months in case of frequent cold shutdowns.

The testing shall commence as soon as the cold shutdown condition is achieved, but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power.Completion of all valve testing is not a prerequisite to return to power.Any testing not completed during one cold shutdown should be performed during any subsequent cold shutdowns starting from the last test performed at the previous cold shutdown.For planned cold shutdowns, where ample time is available and testing all the valves identified for the cold shutdown test frequency in the IST Program will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> commencement of testing is allowed.G.The following criteria have been used in developing limiting values of full-stroke time for the power operated valves: 0 0 o Review of valve's design specification and/or manufacturer's test stroke times Review of system response time requirements (Technical Specification, FSAR, etc.)Valve's historical stroke time values at various system conditions Page 6 of 81 D.C.Cook Nuclear Plant Revision No: 3 Valve Test Program Figure-1 Date: 2-5-90 Using the above criteria, the limiting stroke time for each valve is derived as follows: 1.Nominal Valve Stroke Time<2 Seconds*Historical Stroke Time Ran e in Seconds Established Base Line on Curves in Seconds Recommended Action Time (Limiting Stroke Time Values in Seconds Base Line Time x 2+1 Second=Recommended Action Time or Tech..Spec.

Limit, whichever is less.up to to 1.24 1.25 to 1.74 1.75 to 2.49 1.0 1.5 2.0=1 x 2+1=3 Seconds=1.5 x 2+1=4 Seconds=2 x 2+1=5 Seconds 2.Nominal Valve Stroke Time-3.0 to 10.0 Seconds 2.5 to 10.49 3 to 10 Base Line Time x 1.5=Action Time 3.Nominal Valve Stroke Time-11.0 Seconds and U 10.5 and Up 11.0 and Up Base Line Time x 1.25=Action Time (or 15 seconds, whichever is larger)*Excluding those valves designated as rapid valves per Paragraph"H" noted below.Page 7 of 81 0

Revision No: 3.D.C.Cook Nuclear Plan Valve Test Program Figure-1 Date: 2-5-'0 H.The stroke time limiting values for the power operated valves will be controlled via plant Technical Data Book.Stroke Time Measurements for Ra id Fast Actin Valves.In accordance with GL-89-04, Attachment 1, Item g6, power operated valves with normal stroke times of 2 seconds or less may be assigned 2 seconds limiting values.If a valve is assigned a 2 second limiting value, it shall be timed only and not trended in accordance with Section XI, IWV-3417a.

If the valve exceeds 2 second limit, it will be declared inoperable and corrective actions will be taken in accordance with DlV-3417(b).

The major influence in the stroke time testing of rapid acting valves is the operator's response.Therefore, the timing tolerances are influenced by the operator action and trending is not indicative of valve performance.

The valve limiting values will be documented in the plant Technical Data Book.The results of these tests will be documented via plant procedures.

page 8 of 81 4

DONALD C.COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF Revision No: 3 Date: 2-5-90 VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS Figure 2 NO.SYSTEM FLOW DIAGRAM NO.REVISION Main Steam Steam Generating System Feedwater Feedwater (Auxiliary)

Essential Service Water Non-Essential Service Water Station Drainage Containment Reactor Coolant Reactor Coolant CVCS-Reactor Letdown&Charging Component Cooling Component Cooling Component Cooling Nuclear Sampling Nuclear Sampling Post Accident Sampling-Containment Hydrogen 2-5105B 2-5105D 2-5106 2-5106A 2-5113 2-5114A 2-5124 2-5128 2-5128A 2-5129 2-5129A 2-5135 2-513 5A 2-5135B 2-5141 2-5141A 2-514 1D 42 2 34 41 36 27 20 19 34 32 20 34 30 14 27 30 Page 9 of 81 0 1

-Revision No: 3 Date: 2-5-90 DONALD C.COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS Figure 2 SYSTEM Emergency Core Cooling (SIS)Emergency Core Cooling (RHR)Containment Spray Containment Penetration

&Weld Channel Pressurization Ice Condenser Refrigeration Containment Ventilation Control Room Ventilation Emergency Diesel Generator Emergency Diesel Generator Emergency Diesel Generator Emergency Diesel Generator Make-Up Water&Primary Water System Compressed Air System FLOW DIAGRAM NO.2-5142 2-5143 2-5144 2-5145 2-5146B 2-5147A 2-5149 2-5151A 2-5151B 2-5151C 2-5151D 12-5115A 12-5120B REVISION NO.28 35 29 20 23 35 23 26 27 26 27 41 22 Page 10 of 81 i

DONALD C.COOK NUCLEAR PLA 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS'evision No: 3 Date: 2-5-90 Figure 2 SYSTEM CVCS-Boron Makeup Spent Fuel Pit Cooling&Clean-Up WDS Vents&Drains FLOW DIAGRAM NO.12-5131 12-5136 12-5137A REVISION NO.19 25 21 Post Accident Liquid&Gas Sampling Post Accident Liquid Sampling Inst.Panels 12-5141C 12-5141F 8 6 Page ll of 81 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Revision No: 3 Date: 2-5-90 Figure 3 1 CATEGORY A-B VALVES ASME CODE SECTION XI PARAGRAPH EF-1 EF-2 EF-3 EF-4 Exercise valve (full stroke)for operability quarterly (3 months).Exercise valve (full stroke)for operability at a cold shutdown frequency or refueling outage frequency as indicated.

Code relief requests and/or cold shutdown justification are provided in the corresponding valve notes.Exercise valve (part stroke)for operability quarterly; exercise (full stroke)at a cold shutdown frequency or refueling outage frequency as indicated.

Justification for exercising the valve at cold shutdown frequency is provided in the corresponding valve notes.Code relief request is provided if full stroke test is deferred to coincide with refueling frequency.

Exercise valve (full stroke)for operability prior to return to service (IWV-3 4 1 1)(IWV-3412)(IWV-3412)(IWV-3416)

EF-5 EF-6 EF-7 EF-8 Valves with remote position indicator shall be observed at least once every 2 years to verify that valve operation is accurately indicated.

This note was intentionally deleted.Exercise valve (with fail-safe actuators) to observe failure mode quarterly.

Exercise valve'with fail-safe actuators) to observe failure mode at a cold shutdown frequency or refueling frequency as indicated.(IWV-3300)(IWV-3415)(IWV-3415)

Page 12 of 81

Revision No: 3 Date: 2-5-90 DONALD C.COOK LEAR PLANT NOMENCLATURE FOR TEST MET D USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Figure 3 (cont'd)ET-XXX 1 CATEGORY A-B VALVES ASME CODE SECTION XI PARAGRAPH Exercise power operated valve (full stroke)to its safety position and measure time.The stroke time limiting values of these valves.including rapid acting valves will be identified and controlled per plant Technical Data Book and plant procedures.

Valves assigned 2 seconds limiting values are subject to relief specified'n"Paragraph H, Figure 1." 2 CATEGORY C VALVES (IWV-3413&3417)CF-1 CF-2 CF-3 CF-4 TF-1 Exercise valve (full stroke)for operability quarterly.

Exercise valve (full stroke)for operability at a cold shutdown frequency or refueling outage frequency as indicated.

Code relief requests and/or cold shutdown justification are provided in the corresponding valve notes.Exercise valve (part stroke)for operability quarterly; exercise (full stroke)for operability at a cold shutdown frecpxency or refueling frequency as indicated.

Justification for exercising valves at a cold shutdown frequency is provided in the corresponding valve notes.Code relief requests are provided if full stroke testing is deferred to coincide with refueling frequency.

Exercise valve (full stroke)for operability prior to return to service.Safety and relief valve tests (setpoint) to Section XI, Table IWV-3510-1.(IWV-3521)(IWV-3521)(IWV-3522)(IWV-3416)(IWV-3510)

Page 13 of 81 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHO USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Revision No'.3 Date: 2-5-90 Figure 3 SLT-1 SLT-2 3 CATEGORY A or AC VALVES Seat leakage test valve in accordance with requirements of paragraph IWV-3420 of ASME Code,Section XI, at refueling outage frequency but not less than once every two years.-Permissible leakage values for each category A or AC valve are listed in Attachment

->>A<<.Seat leakage test valve in accordance with 10CFR 50, Appendix J, in lieu of ASME Code Section XI except for paragraphs IWV-3426 and IWV-3427 which are applicable.

This is consistent with the NRC position described in GL-89-04, Attachment A, Item gl0.Permissible leakage values for each category A or AC valve are listed in Attachment->>A>>.

SLT-2A In lieu of the requirements of ASME Code Section XI, paragraphs IWV-3423 and IWV-3424, valves are seat leakage tested as part of the Appendix>>J>>containment isolation test by imposing a static head of water on the downstream side of the valve and verifying that the leakage within the specified value of Attachment

>>A>>for each category valve.This testing method demonstrates that the containment spray and RHR Check Valve leakage over 30 days is limited to the water resident in the containment spray headers downstream of the check valves.The leakage specified would not deplete the water inventory so as to expose these valves to a post-LOCA environment for a minimum of 30 days in the event that a spray system must be shut down and drained.This testing method is as stated in Response to Question 22.15(5)of the original FSAR Appendix>>Q>>, Amendment 81, dated August 1978.Page 14 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5105D-2 Revision No: 3 Date: 2-5-90 NOTE 1: FW-118-1 thru-4 Code Relief: These check valves are normally open during power operation to pass main feedwater flow to the steam generators.

Their safety function (close)prevents auxiliary feedwater backflow into the main feedwater system.These valves cannot be exercised during power operation because closing of these valves would require securing feedwater flow to the steam generators.

Main feedwater to the steam generators cannot be isolated on a loop basis because three loop operation is not allowed per Donald C.Cook Nuclear Plant Technical Specification 3.4.1.1.For these category"C" check valves, backflow cannot be quantified at cold shutdown due to system configuration.

The only practical method to verify valve closure is by disassembly.

Due to size, weight and close proximity to physical barriers (whip restraints);

valve disassembly at cold shutdown would impose constraints on the manpower and scheduling that may delay essential cold shutdown related activities and the plant start-up.The valves are not equipped with position indicators.

There has been no operational or maintenance adverse trend noted.Therefore, the valves will be disassembled (bonnet removed)and verified closed (disc against seat)on a.sampling basis (one of-four)at refueling outage frequency.

Page 15 of 81

DONALD C.COOK NUCLEAR PLAN VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5105D-2-Revision No: 3 Date:.2-5-90 NOTE 2: NOTE 3: MRV-210-220-230 and-240 Cold Shutdown Justification

These steam generator stop valves cannot be full stroke exercised during power operation because this would require securing steam from a steam generator which could result in a reactor trip.Three loop operation is not allowed for D.C.Cook per Technical Specification 3.4.1.1.Valves MRV-211,-221,-231,-241,-212,-222,-232, and-242 which activate MRV-210,-220,-230, and-240 are tested quarterly in accordance with INV-3410.MRV-210,-220,-230 and-240 are part stroke tested quarterly by use of hydraulics attached to valve operators.

and full stroke tested during hot standby (Mode 3 with RCS temperature

>541 F)at cold shutdown frequency.

MS-108-2 and 108-3 Code Relief: These check valves are located in the steam supply lines to the Auxiliary Feedwater Pump Turbine.These valves are part stroke tested during normal IST feedwater pump testing at least on a quarterly basis at approximately 700 gpm because flow is restricted to a maximum of approximately 700 gpm through the 3" test line used during pump test.The valves will be full stroke tested to open position.at a cold shutdown frequency.

The valve is not equipped with position indicator.

In addition, due to the plant design, the only method available to verify the valve closure is disassembly.

The valve will be disassembled (bonnet removed)and verified closed (disc against seat)and visually examined in accordance with GL-89-04, Attachment A, Item N2 on a sampling basis (one of two)once every other refueling frequency.

Page 16 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES.Flow Diagram No: 2-5106-34 Revision No: 3 Date: 2-5-90 NOTE 1 0 FMO-201-202-203-204&FRV-210-220-230-240 Cold Shutdown Justification

The function of these valves is to provide feedwater flow from the feedwater pumps to the steam generators.

These valves cannot be exercised (part or full stroke)during power operation because closing these valves would require securing feed flow to the steam generator which may cause instability of steam generator water level which could result in reactor trip.Further, three loop operation is not allowed per Donald C.Cook Nuclear Plant Technical Specification 3.4.1.1.These valves will be full stroke-exercised and timed during unit start-up or shutdown at cold shutdown frequency.

Page 17 of 81 DONALD C.COOK NUCLEAR.P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5106A-41 Revision No: 3 Date: 2-5-90 NOTE 1: NOTE 2 FW-132-1-2-3-4 Cold Shutdown Justification

These auxilzary feedwater (AFW)check valves function to supply AFW to the steam generators whenever the AFW System is caused to operate.These check valves cannot be full or partial stroke exercised during power operation without energizing the AFW System and delivering cold water to the steam generators..

This would result in thermal shock to the steam generator nozzles.These, valves are full stroke exercised during startup.The valves will be verified closed quarterly by monitoring temperature of Auxiliary Feed Line as required by the plant procedure during shift inspection tours.FW-134 6 FW-135 Cold Shutdown Justification

These valves are located on the suction and discharge lines of the turbine driven auxiliary feedpump.The maximum flow rate through the turbine driven auxiliary feedpump during IST is approximately 700 gpm using the pump test line.Passing the design flow of 900 gpm through these valves would require delivering cold auxiliary feedwater to the steam generators.

This would result in thermal shock to the-steam generator nozzles.Therefore, these valves will be part stroke exercised quarterly and full stroke exercised (passing design flow of 900 gpm through the valves)at cold shutdown frequency.

page 18 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5106A-41 Revision No: 3 Date: 2-5-90 NOTE 3: FW-138-1-2-3-4 Cold Shutdown Justification

These auxiliary feedwater (AFW)check valves function to supply AFW to the steam generators whenever the AFW System is caused to operate.These check valves cannot be full or partial stroke exercised during power operation without energizing the AFW System and delivering cold water to the steam generators.

This would result in thermal shock to the steam generator nozzles.The valves will be verified closed quarterly by monitoring temperature of Auxiliary Feed Line as required by the plant procedure during shift inspection tours.These valves are full stroke exercised when the plant is returned to power after cold shutdown.NOTE 4 FW-149 and 150 Comment: The required full stroking of these check valves is satisfied when Turbine Driven Auxiliary Feedpump completes its required testing.NOTE 5: FW-153 and 160 Comment: These check valves installed on the Emergency Leak Off (ELO)lines open when the Motor Driven Auxiliary Feedwater Pumps (MDAFP)start.This can be established when the MDAFP pump is operating through the test line.-A pressure decrease in the pump discharge line is verified by a local pressure indicator when the parallel path ELO is opened.The pressure decrease indicates that flow is established through the ELO line and that the check valve is opened..Page 19 of 81-DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5113-36 Revision No: 3 Date: 2-5-90 NOTE 1 NOTE 2: ESW-141-142-143-144 Comment;: These valves are full stroke exercised quarterly as required by IWV-3520.In addition, they are disassembled and inspected internally in accordance with IEB 85-03 at refueling outage frequency.

ESW-145-240-243 Cold Shutdown Justification

-These valves are normally closed and are required to be open when the condensate storage tank is exhausted.

Exercising the valves could cause lake water contamination of the steam generators.

Lake water chemistry can potentially impact steam generator tube integrity.

Therefore, the valves will be full stroke tested at a cold shutdown frequency.

Since the valves are manual, stroke timing is not required.Page 20 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES r Flow Diagram No: 2-5113-36 Revision No: 3 Date: 2-5-90 NOTE 3: WRV-722-724-726-728 Code Relief: These valves are located in the essential service water supply lines to the emergency diesel generators air after coolers.These three-way valves regulate water flow to maintain the temperature at which the after cooler air discharge thermostatic controller has been set.Water flow is regulated by passing a portion of the flow through the air coolers and bypassing the excess flow around the air after coolers.Code relief is being requested from the testing requirements since (1), these valves function only as regulating valves and not open/closed valves (2), these valves are demonstrated operable during diesel generator testing=(diesel generators are tested per Technical Specification 4.8.1.1.2);

and (3), these valves are demonstrated operable during diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs performed each refueling outage.The valves will be"fail-safe" tested using their control scheme that will remove air from the valve operators causing them to direct all ESW flow to the air after coolers.This proposed test for each valve will be performed at refueling frequency.

The valves cannot be stroke timed because they are thermostatic valves whose position is controlled by process fluid temperature.

There is no external control available.

Page 21 of 81 II' DONALD C.COOK NUCLEAR.P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5114A-27 Revision No: 3 Date: 2-5-90 NOTE 1:=HCR-900 throu h-915-920 throu h-935-941 throu h 948-951 throu h-958 and 960 throu h-967 Code'Relief See"Attachment-A" for permissible seat leakage values.Page 22 of 81

DONALD C.COOK NUCLEAR PLAN VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5124-20 Revision No: 3 Date: 2-5-90 NOTE 1: DCR-600 6-601 and NS-357 Code Relief: See<<Attachment-A<<

for permissible seat leakage values.NOTE-2: NS-357 Code Relief: This check valve is located on the return-line of the post accident sampling system inside the containment.

Since the line is, open-ended inside the containment and the check valve is not equipped with the position indication, the valve will be full stroke exercised in the open position by performing a flow test quarterly and will be confirmed closed in conjunction with Appendix J seat leakage testing at refueling frequency.

Page 23 of 81 I'1'I DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128-19 Revision No: 3 Date: 2-5-90 NOTE 1: NSO-021-022-023&-024 Cold Shutdown Justification

These four one-inch solenoid operated.isolation valves are installed (two in each leg in series)in the reactor head vent.These valves cannot be tested during power operation, hot standby, or hot shutdown because the valve design is such that testing of either valve can cause"burping" (momentary opening)of the second valve, resulting in the release of radioactive fluid and create an airborne situation in containment.

Therefore, the valves will be full stroke exercised and timed at cold shutdown frequency.

Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed at refueling frequency by a flow test through each valve because the valve stem is completely enclosed and cannot be observed.The reactor coolant discharged during the flow testing of the valves is collected in a container to minimize liquid contamination.

spill, radiation, and potential airborne situation in deference of ALARA consideration and personnel protection.

The above tests are consistent with Technical Specification requirements.

Page 24 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 3 Date: 2-5-90 NOTE 1: CS-442-1 thru 4 Code Relief: These containment.

isolation check valves are on the seal water supply line to the RC pumps.These valves cannot be part or full stroke exercised to the closed position during power operation because cooling flow is required to the RCP seals.During cold shutdown, seal water must be maintained to prevent backflow through the seals with possible damage from dirt.The valves will be full stroke exercised in conjunction with Appendix J seat leakage testing at refueling frequency.

NOTE 2: GCR-301 NCR-252 NPX-151 RCR-100&-101 CS-442-1 throu h 4 SI-189 PW-275 and N-159 Code Relief: See Attachment-"A" for permissible seat leakage values.NOTE 3: NRV-151-152-153 Cold Shutdown Justification

These pressurizer power operated relief valves are normally closed during power operation.

The valves cannot be exercised at power without inducing an RCS pressure transient which could result in reactor trip.The valves will be full stroke exercised and timed at cold shutdown frequency.

Page 25 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 3 Date: 2-5-90 NOTE 4: NOTE 5: PW-275 Code Relief: This containment isolation check valve is located in the primary water supply line to the pressurizer relief tank.The valve is not equipped with position indication.

The valve cannot be full stroke tested to closed position during power operation or at a cold shutdown frequency due to lack of sufficient differential pressure to back seat the valve.The valve and necessary test connections are located inside the containment.

Due to the plant design, the only method available to verify the valve closure is leak testing.The valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

N-159 Code Relief: This containment isolation check valve is located in the nitrogen supply line to the pressurizer relief tank.The valve is not equipped with position indication.

The valve cannot be full stroke tested to closed position during power operation or at a cold shutdown frequency due to lack of sufficient differential pressure to back seat the valve.The valve and necessary test connections are located inside the containment.

Due to the plant design, the only method available to verify the valve closure is leak testing.The valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

Page 26 of 81 I 0 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 3 Date: 2-5-90 NOTE 6: NSO-061-062-063-064 Cold Shutdown Justification

These four one-inch solenoid operated isolation valves are installed (two in each leg in series)in the pressurizer vent.These valves cannot be tested during power operation, hot standby, or hot shutdown because the valve design is such that testing of either valve can cause"burping" (momentary opening)of the second valve resulting in the release of radioactive fluid and create an airborne situation in containment.

The valves will be full stroke tested and timed at cold shutdown frequency.

Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed at refueling frequency by performing a flow test through each valve because the valve stem is completely enclosed and cannot be observed.The reactor coolant discharged during flow testing of the valves is collected in a container to minimize contaminated liquid spill, radiation, and potential airborne situation in deference of.ALARA consideration and personnel protection.

The above tests are consistent with Technical Specification recpxirements.

Page 27 of 81 DONALD C.COOK.-NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: ,3 Date: 2-5-90 NOTE 7: SI-189 Code Relief: This check valve is located in the safety valves discharge (Emergency Core Cooling SVs, RHR, SVs, centrifugal charging pump SVs, etc.)collection header leading to the pressurizer relief tank.Isolating this valve for testing would result in dead heading all safety valves in the above systems.This would result in loss of overpressurization protection and could put the plant in an unsafe condition.

Therefore, the valve will be part stroke exercised to open position using external source via test connection at a cold shutdown frequency.

The valve will be disassembled, manually full stroke tested and visually examined in accordance with GL-89-04, Attachment 1, Item g2 at every third refueling outage frecpxency.

The valve will also be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

Page 28 of 81 l,

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 3 Date: 2-5-90 NOTE 1: CS-292 Code Relief: This valve is in the emergency boration path from the boric acid system to the charging pump suction header.Flow through this path is normally not provided at power because of , the resultant large negative reactivity insertion.

The valve will be full stroke exercised in the open position at a cold shutdown frequency.

The check valve is not equipped with position indication.

Due to the plant design, the only methods available to verify the valve closure is either radiography or disassembly which will be performed at a refueling frequency when the system is not required to be operable.The radiography method is an acceptable method to verify the valve closure (disc against the seat)under no flow condition because it provides visual observation of the valve in the closed position.The flow testing of the valve verifies that it is open.This provides assurance that the disc is free to move from the open position with flow to the closed position with no flow or reverse flow.NOTE 2: CS-299E-299W Code Relief: These check valves located on the discharge lines of the'E'nd'W'harging pumps function as pressure isolation valves to protect the low pressure charging pump suction lines.These valves cannot be full-stroke exercised during: (1)power operation because the charging pumps cannot achieve maximum flow rate with the reactor at full pressure, and (2)cold shutdown because the flow required could cause a low temperature overpressure condition.

The valves will be part-stroke exercised quarterly and full stroke exercised at refueling frequency.

The valves will also be verified closed in conjunction with seat leakage testing per IWV-3420 at refueling frequency.

Page 29 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 3 Date: 2-5-90 NOTE 3: CS-321 QCR-300 and-301 Code Relief: See Attachment"A" for permissible seat leakage values.NOTE 4: CS-321 Code Relief: This containment isolation check valve's function is to supply borated water from the volume control tank to the regenerative heat exchanger through the charging pumps for chemical shim control and reactor coolant system makeup.Isolation of this system would result in loss of control of pressurizer level which could result in reactor trip.This valve is tested in the open direction quarterly and confirmed closed in conjunction with Appendix J seat leakage testing at refueling frequency.

NOTE 5: NOTE 6: CS-328Ll-329Ll-328L4-329L4 Comment: These check valves function to provide the interface point between the RCS and the CVCS.Since the discharge piping of the CVCS is designed to a pressure rating higher than the RCS, these valves do not perform a pressure isolation function.The higher pressure (RCS)to low pressure (CVCS Suction)isolation is accomplished by other valves which are tested to category"A" requirements.

The valves will be full stroke exercised to open position quarterly.

QCR-300-301 Cold Shutdown Justification

These air operated containment isolation valves are located on the letdown return line.Exercising these valves during power operation would result in letdown isolation which could result in loss of pressurizer level control which could result in a plant shutdown.The valves will be full stroke exercised, timed and fail safe tested at a cold shutdown frequency and seat leakage tested per Appendix J program at refueling frequency.

Page 30 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM Flow Diagram No: Revision No: 3 Date: 2-5-90 RELIEF REQUEST NOTES c 2-5129-32 NOTE 7: NOTE 8: QMO-200-201 Cold Shutdown Justification

These motor operated gate valves are installed on the CVCS charging line which provide borated water for RCS chemical shim control and reactor coolant system makeup.Isolation of this system would result-in loss of control of pressurizer level which could result in reactor trip.The valves will be full stroke tested and.timed at cold shutdown frequency..

QRV-200 Code Relief: This air operated valve is used to regulate charging header flow to the reactor coolant system and seal water flow to the reactor coolant pump seals.The valve cannot be full stroke exercised at power operation because it would interrupt the seal injection flow to the reactor coolant pumps which could result in reactor coolant pump seal damage.The valve will be part stroke exercised during power operation and full stroke exercised at a cold shutdown frequency.

The valve cannot be stroke timed because there is no local or remote position indicator available and cycle times are directly proportional to"how fast" the operator turns the control knob.Therefore, meaningful stroke times are not achievable.

This valve has no fail safe position.The alternative testing proposed is to locally observe the valve during full stroke testing for smooth operation and apparent problems which can affect the valve opexation.

Page 31 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 3 Date: 2-5-90 NOTE 9: NOTE 10 QRV-251 Code Relief: This air operated valve is used to regulate charging header flow to the reactor coolant system and seal water flow to the reactor coolant pump seals.The valve cannot be full stroke exercised at power operation because it would interrupt the.RCP seal injection flow and would also upset pressurizer level.The valve will be part stroke exercised during power operation and full stroke exercised at a cold shutdown frequency.

The valve cannot be stroke timed because there is no local or remote position indicator available and cycle times are directly proportional to"how fast" the operator can turn the control knob.Therefore, meaningful stroke times are not achievable.

The control scheme of this valve functions.to remove air from the valve oeprator, which duplicates the fail-safe condition, resulting in the valve going to fail-safe (open)position.Therefore, the alternative testing proposed will consist of locally observing the valve during full stroke testing for smooth operation and apparent problems which can affect the valve operation.

SI-185 Code Relief: This normally closed valve functions to transfer the suction source of the charging pumps to the refueling water storage tank.This valve cannot be full stroke exercised during: (1)power operation without introducing a high concentration of boric acid in the RCS, and (2)cold shutdown because the only full flow path available is into the reactor coolant system and the system does not have sufficient volume to accommodate that flow without a possible low temperature overpressure condition.

The valve will be full stroke exercised at refueling frequency.

Page 32 of 81 DONALD C.COOK NUCLEAR'LA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 3 Date: 2-5-90 NOTE ll: CS-299E&W Comment: See Attachment"A" for permissible seat leakage values.Page 33 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM Flow Diagram No: Revision No: 3 Date: 2-5-90 RELIEF REQUEST NOTES 2-5129A-20 NOTE 1: QCM-250-350 Cold Shutdown Justification

These motor-operated reactor coolant pump seal water return isolation valves cannot be exercised during power operation because it would interrupt reactor.coolant pump seal water flow and could cause damage to the seals.Therefore, the valves are full stroke exercised and timed at cold.-shutdown frequency.

NOTE 2: NOTE 3: QCM-250 and-350 Code Relief: See"Attachment-A" for permissible seat leakage values..QMO-451-452 Cold Shutdown Justification

These motor-operated gate valves function as volume control tank isolation valves.Exercising these valves during power operation could result in a loss of pressurizer level control which could cause a reactor trip.These valves are full stroke exercised and timed at cold shutdown frequency.

Page 34 of 81 IJ DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 3'Date: 2-5-90 NOTE 1 CCM-451-452-453-454-458 and-459 Cold Shutdown"'"ll operation without securing cooling water to the reactor Coolant Pumps (RCPs).Isolation of these valves could cause failure of the RCPs.The valves will be full stroke tested and timed at cold shutdown frecpxency.

NOTE 2 NOTE 3: NOTE 4: NOTE 5: CCM-451 throu h-454-458-459 CCR-455 throu h-457-460-462 and CCW-135 Code Relief See"Attachment-A" for permissible seat leakage values.CCR-455-456 and-457 Cold Shutdown Justification

These valves cannot be tested during power operation without securing cooling water to the reactor support coolers.These valves must remain open to prevent overheating of the concrete around the reactor supports during power operation.

The valves will be full stroke tested and timed at cold shutdown frequency.

CCW-135 Code Relief: This check valve cannot be tested during power operation without securing cooling water to the reactor support coolers.The valve must remain open to prevent overheating of the concrete around the reactor supports during power operation.

The valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

CRV-470 Code Relief: This air operated valve is used to regulate component cooling water (CCW)to the letdown heat exchanger.

The valve is normally in service during power operation.

Page 35 of 81 0

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 3 Date: 2-5-90 CRV-470 (continued)

This valve is controlled by an auto/manual station with auto input from the letdown heat exchanger outlet temeprature sensor (QTC-302).

The valve also trips closed from an SI signal via a solenoid valve.The valve will be full stroke exercised quarterly using auto/manual station which will permit rapid cycling of this regulating valve resulting in minimal impact on letdown temperature.

Meaningful stroke time data is not available since this valve does not have local or remote position indication.

Fail safe testing this valve closed requires a longer period of time than cycling the valve using the auto/manual station.The valve will be fail safe tested to its closed position at cold shutdown frequency with letdown flow out of service thus avoiding high letdown line temperatures that could cause flashing in the letdown heat exchanger and lifting of safety valves.Page 36 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135A-30 Revision No: 3 Date: 2-5-90 NOTE 1: CMO-411-412-413-414-415&-416 Comment: These valves remain open during initial safety injection, but may be closed during recirculation phase or passive failure.Therefore, the valve time will be recorded from open to close position.Page 37 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135B-14 Revision No: 3 Date: 2-5-90 NOTE 1: CCM-430 throu h-433 CCR-440 and-441;CCW-243-25

-243-72-244-25 and-244-72 Code Relief: See"Attachment-A" for permissible seat leakage values.NOTE 2: CCW-243-25 CCW-243-72 CCW-244-25 and CCW-244-72 Code Relief: These check valves are located xn the penetration cooling supply headers of the CCW System inside the containment.

The valves are open during power operation and cold shutdown to provide cooling water to the main steam penetrations.

These valves are not ecpxipped with position indication.

The valves will be confirmed closed in conjunction with Appendix J seat leakage testing at refueling frequency.

Page 38 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141-27 Revision No: 3 Date: 2-5-90 NOTE 1: ICR-5-6 NCR-105 throu h-110 Code Relief: See"Attachment-A" for permissible seat leakage values.Page 39 of 81 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141D-8 Revision"No:

3 Date: 2-5-90 NOTE 1: NOTE 2: ECR-10 throu h-29 and NS-283 Code Relief: See"Attachment-A" for permissible seat leakage values.NS-283 Code Relief: This containment isolation check valve is located in the.sample return line of the Post-Accident Containment Hydrogen Monitoring System.The valve cannot be full stroke exercised to closed position quarterly or at a cold shutdown frequency because the line is open ended in the containment.

This check valve is not equipped with position indicator.

The only method available to verify the valve closure is by seat leakage testing.The valve will be full stroke exercised to the open position by a flow test cpxarterly and will be confirmed closed in conjunction with Appendix Z seat leakage testing at refueling frequency.

Page 4'0 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-28 Revision No: 3 Date: 2-5-90 NOTE 1: ICM-250 and ICM-251 Cold Shutdown Justification

These normally closed valves cannot be operated during normal plant operation without introducing Boron into a nonheat traced line: Boron could crystallize and plug the line.The valves will be full stroke tested and timed at cold shutdown frequency.

NOTE 2: ICM-250-251-260 and-265 Code Relief: See"Attachment-A" for permissible seat leakage values.NOTE 3: IMO-261 Cold Shutdown Justification

This valve cannot be tested when SI pumps are required to be operable.Testing would result in isolation of the common suction line to both SI trains.This valve will be stroke tested and timed at cold shutdown frequency.

NOTE 4: IMO-262 and-263 Cold Shutdown Justification

These motor operated valves are located in series in the re-circulation line of the Safety Injection pumps.Exercising either of these valves will make both SI pumps inoperable.

These valves will be full-stroke exercised and.timed at cold shutdown frequency wheh SI pumps are not required to be operable.NOTE 5: SI-llON SI-llOS and SI-101 Code Relief: Safety Injection (SI)pump discharge valves, SI-110N and-llOS, cannot be exercised during power operation because the SI pumps cannot overcome reactor coolant system pressure.Therefore, no flow path exists and, because minimum flow lines branch off upstream of these valves, they cannot be part-stroke tested during pump testing.The common (SI pumps)suction check valve, SI-101 is part-stroke exercised at Page 41 of 81 DONALD C.COOK NUCLEAR P i VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-28 Revision No: 3 Date: 2-5-90 Note 5 (continued) power operation during pump testing.These valves cannot be exercised during cold shutdown because the SI pumps are required to be inoperable by Technical Specification 3.5.3 to protect against low temperature overpressurization of the reactor.These valves will be full-stroke exercised at refueling frequency.

NOTE 6: SI-142 Ll L2 L3 and L4 Code Relief: These check valves are located in the supply lines from the Boron Injection Tank to the reactor coolant cold legs (loop 1 through 4).These valves cannot be tested during power operation because this would require injecting highly concentrated boric acid solution from the Boron Injection Tank into the Reactor Coolant System resulting in probable plant shutdown.These valves cannot be partially-stroke exercised using the BIT bypass line because this could result in bypassing the BIT, thereby not achieving design flow through the BIT if an accident occurred.These valves cannot be full-stroked exercised during cold shutdown because this would require injecting the BIT into the RCS which could significantly delay startup from cold shutdown condition (the BIT would have to be brought to the proper Boron concentration and the RCS would have to be diluted sufficiently to allow startup).These valves will be full stroke exercised at refueling frequency.

Page 42 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 3 Date: 2-5-90 NOTE 1: SI-151E&W-152N&S-158-Ll throu h L4-161-Ll throu h L4-166-1 throu h 4-170Ll throu h L4 RH-133-134 and ICM-129 Comment: See"Attachment-A" for permxssible seat leakage values.NOTE 2: NOTE 3: NOTE 4: IMO-128 and ICM-129 Cold Shutdown Justification

These valves function as the normal return from the RCS to the-RHR for heatup and cooldown.These valves are normally closed and cannot be operated during normal plant operation because they are interlocked to remain closed at RCS pressure above 450 psig.The valves will be full stroke exercised and timed prior to placing them into service at cold shutdown frequency.

IMO-310-320-314-324 Comment: These valves remain open during injection phase of a safety injection, but will be closed during recirculation phase.Therefore, stroke timing will be from open to close position.IMO-315-316-325-326 Cold Shutdown Justification

Valves IMO-315 and-325 are normally closed valves, located in the RHR and SI Supply Header to RCS hot legs.Valves IMO-316 and-326 are normally open valves located in the RHR and Sl Supply Header to RCS cold legs.These valves should not be exercised during power operation because failure in a non-conservative position would result in less than minimum number of injection flow path as required by the FSAR.The valves will be full stroke tested and timed at cold shutdown frequency.

Page 43 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 3 Date: 2-5-90 NOTE 5: NOTE 6: SI-166-1 throu h 4 Code Relief: These check valves function to prevent backflow from the RCS xnto the accumulators during normal operation.

These valves function to supply flow from the accumulators to the RCS during an accident condition.

These valves cannot be exercised during power operation because the accumulators do not have sufficient head to overcome RCS pressure.These valves cannot be exercised during cold shutdown because this would result in a possible low temperature overpressurization of the RCS.Full stroke testing during re'fueling outages is not possible because of the resulting water surge into the reactor and the potential for high airborne radiation contamination.

These valves will be part stroke exercised at refueling frequency.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of four)per GL-89-04, Attachment, 1, Item g2, at refueling frequency.

SI-161 Ll L2 L3 L4 Code Relief: These check valves are located in the supply lines from the Residual Heat Removal and Safety Injection Pumps to the RCS cold legs (loop 1 through 4).These valves cannot be exercised during power operation because the RHR pumps and SI pumps do not develop sufficient head to overcome RCS pressure.Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow instrumentation is not available downstream of the flow split.These valves will be part stroke exercised at cold shutdown frequency and full stroke will be locally verified using portable instrumentation at refueling frequency.

Page 44 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 3 Date: 2-5-90 NOTE 7: NOTE 8: NOTE 9: RH-108E W Cold Shutdown Justification

These valves cannot be full stroke exercised quarterly because it would require design modification to existing instrumentation to accommodate the full flow test measurements.

The valves will be part stroke exercised quarterly and full stroke exercised at cold shutdown frequency (during RHR operation).

SI-148 Code Relief: Check valve SI-148 is located in the Refueling Water Storage Tank (RWST)supply line to the RHR system.The design flow through the valve is 6000 gpm.Flow to the core is not possible when the RCS pressure is above the shut-off pressure of the RHR pumps (195 psig).In order to full stroke exercise this valve, both RHR pumps must be operated and the RHR system manually aligned to recirculate flow back'to the RWST.This configuration places both RHR trains inoperable since neither train can provide design flow to the core.In order to preclude placing the unit in an unsafe condition, a partial stroke test is performed quarterly.

The valve cannot be full stroke exercised during cold shutdown since the RCS cannot-accommodate the introduction of 6000 gpm from the RHR system.In addition, during cold shutdown, the RHR system is required to be operable for RCS temperature control.The valve will be full stroke exercised when the reactor cavity is being flooded at refueling frequency.

SI-151 E W Cold Shutdown Justification

These check valves are located in the RHR supply lznes to either the hot or cold legs.These valves cannot be exercised during power operation because the RHR pumps do not develop sufficient head to overcome RCS pressure.These valves will be exercised at cold shutdown frequency.

Page 45 of 81 I,

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-29 Revision No: 3 Date: 2-5-90 NOTE 10: NOTE 11: SI-152 N S Code-Relief: These check valves function to provide Safety Injection pump discharge to either the hot or cold legs.These valves cannot be exercised during power operation because the SI pumps do not develop sufficient pressure to overcome RCS pressure.These valves cannot be exercised during cold shutdown because the safety injection pumps are required to be inoperable by Technical Specification Section 3.5.3, to protect against low temperature overpressurization of the reactor vessel.Also, during cold shutdown, there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke.These valves will be full stroke exercised at refueling frequency.

SI-158 Ll L2 L3 L4 Code Relief: Check valves SI-158 are located zn the supply lines from the Residual Heat Removal and Safety Injection Pumps to the RCS hot legs (loop 1 through 4).These valves cannot be exercised during power operation because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow i'nstrumentation is not available downstream of the flow split.These valves will be part stroke exercised at cold shutdown frequency.

Full stroke will'.be verified using portable instrumentation at refueling frequency.

Page 46 of 81 I'j 4 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 3 Date: 2-5-90 NOTE 12 SI-170 Ll L2 L3 and L4 Code Relief: These valves are located on the RCS cold leg (loops 1 through 4)injection lines from the accumulators, RHR, and SI systems.They cannot be exercised during power operations because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.The valves will be part-stroke exercised at a cold shutdown frequency.

Due to the plant design, the valves are sized such that full stroke testing cannot be attained without discharging the accumulators and operating SI and RHR pumps simultaneously.

The only method available to verify the full stroke is by disassembly.

The valves are not equipped with position indicators.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of four)per GL-89-04, Attachment 1, Item N2, at refueling frequency.

NOTE 13: N-102 Code Relief: This check valve is located in the nitrogen supply header to the accumulators for blanketing purposes.The valve cannot be full stroke tested to the closed position during power operation or cold shutdown because, due to the plant design, the only method available to verify the valve closure is leak testing.The valve and necessary test connections are located inside the containment.

The valve is not equipped with a position indicator.

The valve will be verified closed in conjunction with Appendix Z seat leakage testing at refueling frequency.

NOTE 14: GCR-314 ICM-305 and-306 N-102 SI-171-172 and-194 Code R~elref: See"Attachment-A" for permissible seat leakage values.page 47 of 81

~t DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 3 Date: 2-5-90 NOTE 15: IMO-340 and-350 Code Relief: Valves IMO-340 and IMO-350 are located in east and west RHR discharge headers to the suction of charging and SI pumps, respectively.

These valves are normally closed during power operation, and'ould be opened during the recirculation phase of a LOCA to allow the RHR pumps to provide water from the containment recirculation sump to charging and SI pumps.These valves cannot be full stroke exercised during power operation because they are interlocked with valves IMO-262 and-263, located in series, in the SI pump miniflow (recirculation) line to RWST.Closing of IMO-262 and-263 would render both SI pumps inoperable and, thus, places the unit in T/S 3.0.3, which allows one hour to restore the SI pumps to operable status or begin a unit shutdown.The complicated valve and equipment lineup to perform the valve testing in one hour is highly unlikely.Therefore, the valves will be full stroke exercised and timed on a cold shutdown frequency.(For additional details, refer to Code Relief granted by the NRC dated 1-30-89, AEP:NRC:09690.)

Page 48 of 81 IK DONALD C.COOK NUCLEAR T VALVE TEST'PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5144-29 Revision No: 3 Date: 2-5-90 NOTE 1: NOTE 2: CTS-138E&W Code Relief: These check valves are located in the lines which supply water from the RWST to the containment spray pumps.The valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.

The valves are part stroke exercised during containment spray pump testing on a quarterly basis.The only practical method available to verify full stroke of these valves is by disassembly.

These valves are not equipped with position indicators.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1, Item 52, once every other refueling frequency.

CTS-103 E&W Code Relief: These check valves are located in the discharge lines of containment spray pumps to the spray ring.headers in the containment.

These valves cannot be full stroke exercised during power operation, cold shutdown or refueling without spraying the containment.

The valves are part stroke exercised during containment spray pump testing on a quarterly basis.The only practical method available to verify full stroke of these valves is by disassembly.

The valves are not equipped with position indicators.

The valves will be disassembled; manually full stroke exercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1, Item g2, once every other refueling frequency.

Page 49 of 81 4

DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5144-29 Revision No: 3 Date: 2-5-90 NOTE 3: NOTE 4 CTS-131E&W Code Relief: These check valves are located in the supply lines to the (upper compartment) containment spray ring headers.These valves are in closed position during normal plant operation.

The valves are exposed.to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.

This could cause problems with wet lagging, corrosion of components inside the containment, etc.The only practical method available to exercise these valves is by disassembly.

The valves are not equipped with position indicators.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1,.Item g2, once every other refueling frequency.

CTS-127E&W Code Relief: These check valves are located in the supply lines to the (lower compartment) containment spray ring headers.These valves are in closed position during normal plant operation.

The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.

This could cause problems with wet lagging, corrosion of components inside the containment, etc.The only practical method available to exercise these valves is by Page 50 of 81 DONALD C.COOK NUCLEAR IT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5144-29 Revision No: 3 Date: 2-5-90 NOTE 5 NOTE 6: Note 4 (continued) disassembly.

The valves are not equipped with position indicators.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1, Item g2, once every other refueling frequency.

RH-141&-142 Code Relief: These check valves are located in the supply lines to the (upper compartment) containment spray ring headers from the RHR Heat Exchangers.

These valves are in closed position during normal plant operation.

The valves are exposed to containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by the closed motor operated valves.The valves cannot be part or full stroke exercised during power operation, cold shutdown or refueling because flow through these valves would result in spraying the containment.

This could cause problems with wet lagging, corrosion of components inside the containment, etc.The only practical method available to exercise these valves is by disassembly.

The valves are not equipped with position indicators.

The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of two)per GL-89-04, Attachment 1, Item g2, once every other refueling frequency.

CTS-109 and-110 Cold Shutdown Justification

These check valves function as vacuum breakers for spray additive tank.The check valves are closed during normal plant operation to maintain the tank pressurized.

The valves will be verified closed quarterly during power operation and will be verified open at.cold shutdown frequency.

Page 51 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5144-29 Revision No: 3 Date: 2-5-90 NOTE 7: CTS-127E&W CTS-131E&W RH-141-142 Code Relief: These valves are to be seat leakage tested in accordance with the unique testing methods established in the FSAR because of the configuration at D.C.Cook Plant.The permissible seat leakage values of these valves are listed in Attachment"A".Page 52 of 81

DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5145-20 Revision No: 3 Date: 2-5-90 NOTE 1: CA-181-N&S Code Relief: See"Attachment-A" for permissible seat leakage values.Page 53 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5146B-23 Revision No: 3 Date: 2-5-90 NOTE 1: R-156 and R-157 Code Relief: These check valves are installed in parallel lines to the glycol main supply and return lines to relieve glycol thermal expansion.

These valves and necessary test connections are located inside the.containment.

Due to the plant design, the only method available to verify valve closure is leak testing.The valves are not equipped with position indicators.

The valves will be full stroke exercised in the open direction quarterly and verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

NOTE 2: R-156 and-157 VCR-10-ll-20 and-21 Code Relief: See"Attachment-A" for permissible seat leakage values.Page 54 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5147A-35 Revision No: 3 Date: 2-5-90 NOTE 1: SM-4-6-8 and-10 VCR-101 throu h-107 and VCR-201 throu h-207 x" Page 55 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5149-23 Revision No: 3 Date: 2-5-90 NOTE 1: VRV-325-315 Code Relief: These thermostatically controlled valves are located at the outlet of the control room air conditioner water pump.These three-way valves function to modulate water flow through the air handler package based on cooling requirements.

These valves are normally in an intermediate position based on control room-cooling load.These valves can not be full stroke exercised because there is no provision to fully close the valves.The valves will be part stroke exercised from an intermediate position in conjunction with fail safe testing on quarterly basis.These valves are demonstrated operable during normal control room air conditioning operation.

The valves cannot be stroked timed because they are not equipped with position indicator and stroke times are not repeatable.

Page 56 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151A-26 Revision No: 3 Date: 2-5-90 NOTE 1: DF-108A-109A-114A-115A DL-114A-116A-126A-132A-158A W If satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.

NOTE 2: QT-114-2AB Code Relief: This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).

This three-way thermostatic valve functions to maintain the correct lube oil temperature by maintaining the correct proportion of oil flowing through the lube oil cooler and bypassing the lube oil cooler to maintain a preset lube oil temperature.

Ne are requesting exemption from testing requirements since (1)this valve functions only as a regulating valve and not opened/closed; (2)this valve is demonstrated operable during diesel generator testing.Diesel generators are tested basis per Technical Specification 4.8.1.1.2.

The valves will be verified operable by observing proper temperatures during diesel testing.Page 57 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B Revision No: 3 Date: 2-5-90 NOTE 1: DG-102A-104A-128A 130A-146A-152A and-154A Comment The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.

NOTE 2: NOTE 3: QT-132-2AB Code Relief: This valve is located at the discharge of the emergency diesel engine jacket water pump.This three-way.thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.

We are requesting exemption from the testing requirements since (1)this valve functions only as a regulating valve and not open/closed valve;(2)this valve is demonstrated operable during diesel generator testing.Diesel generators are tested per Technical Specification 4.8.1.1.2.

The valve will be verified operable by observing proper temperatures during diesel testing.XRV-221 and-222-Startin Air Code Relief: The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).The valves are not equipped with position-indication devices to directly measure valve stroke times.The valves function to provide starting air which rolls the EDG.The valves are functionally redundant to each other.These valves fail"as is," and, therefore, they have no fail safe position.Successful starting of the EDG in accordance with Technical Specification 4.8.1.1.2 (i.e., slow start at least quarterly and fast start once every 184 days within 10 seconds)will verify the valve performance.

The valve stroke timing will be verified by Page 58 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B-27 Revision No: 3 Date: 2-5-90 NOTE 4: Note 3 (continued) measuring diesel starting times during fast start testing of EDG.The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.

Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.

XRV-220-Jet Assist Code Relief: This valve's function is to facilitate the EDG fast start by providing an air boost to the turbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.The valve is not equipped with position indication devices;therefore, meaningful stroke times are not achievable.

The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4.8.1.1.2~v Page 59 of 81 DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151C-26 Revision No: 3 Date: 2-5-90 NOTE 1: DL-114C-116C-126C-132C and-158C Comment: The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required.testing per Technical Specification 4.8.1.1.2.

NOTE 2: QT-114-2CD Code Relief: This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).

This three-way thermostatic valve functions to maintain the correct lube oil temperature by maintaining the correct proportion of oil flowing through the lube oil cooler and bypassing the lube oil cooler to maintain a preset lube oil temperature.

We are requesting exemption from testing requirements since (1)this valve functions only as a regulating valve and not opened/closed valve;(2)this valve is demonstrated operable during diesel generator-testing.Diesel generators are tested per Technical Specification 4.8.1.1.2.

The valves will be verified operable by observing proper temperatures during diesel testing.Page 60 of 81 I'1 e DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151D-27 Revision No: 3 Date: 2-5-90 NOTE.1: DG-102C-104C-128C-130C-146C-152C and-154C Comment: The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.

NOTE 2 NOTE 3: QT-132-2CD Code Relief: This valve is located at the discharge of the emergency diesel engine jacket water pump.This three-way thermostatic valve functions to maintain the correct proportion of water flowing through the diesel engine water cooler and bypassing the diesel engine jacket water cooler to maintain a preset jacket water temperature.

We are requesting exemption from the testing requirements since (1)this valve functions only as a regulating valve and not open/closed valve;(2)this valve is demonstrated operable during diesel generator testing.Diesel generators are tested on a staggered basis, every 31 days per Technical Specification 4.8.1.1.2.

The valve will be verified operable by observing proper temperatures during diesel testing.XRV-226 and-227-Startin Air Code Relief: The starting air valves are installed on parallel air supply lines to the emergency diesel generator (EDG).The valves are not equipped with position indication devices to directly measure valve stroke times.The valves function to provide starting air which rolls the EDG.The valves are functionally redundant to each other.These valves fail"as is," and, therefore, they have no fail safe position.Successful starting of the EDG in accordance with Technical Specification 4.8.1.1.2 (i.e., slow start at least quarterly and fast start once every 184 days within 10 seconds)will verify the valve performance.

The valve stroke timing will be verified by Page 61 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM'ELIEF REQUEST NOTES, Flow Diagram No: 2-5151D-27 Revision No: 3 Date: 2-5-90 NOTE 4: Note 3 (continued) measuring diesel starting times during fast start testing of EDG.The valves on a staggered basis will be valved out one at a time to verify the operability of the opposite valve during slow start of EDG at least quarterly.

Position indication will be confirmed during the above testing when only one starting air train is used to start the diesel generators.

0 XRV-225-Jet Assist Code Relief: This valve's function is to facilitate the EDG fast start by providing an air boost to the turbo charger to assist in starting the EDG in its Technical Specification 4.8.1.1.2 time limitation of 10 seconds.The valve is not equipped with position indication devices;therefore, meaningful stroke times are not achievable.

The valves will be full stroke and fail safe tested by verifying EDG starting time once per 184 days in accordance with Technical Specification 4.8~1~1~2~Page 62 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5115A-41

-Unit-2 Revision No: 3 Date: 2-5-90 NOTE 1: QCR-919 and-920 Code Relief: See"Attachment-A" for permissible seat leakage values.Page 63 of Sl DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5120B-22

-Unit-2 Revision No: 3 Date: 2-5-90 NOTE 1: PA-342 Code Relief: This check valve is located in the maintenance air supply line into the containment.

The valve cannot be tested during power operation and cold shutdown because: 1)this line is generally isolated by removing a spool piece and inserting a blind flange, and 2)the valve and test connections are located inside the containment.

The valve is not equipped with position indicator.

Due to the plant design, the only method available to verify the valve closure is leak testing.The valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

NOTE 2: PA-342 PCR-40 XCR-100 throu h-103 Code Relief: See"Attachment-A" for permissxble seat leakage values.NOTE 3 XCR-100-101-102-103 Cold Shutdown Justification

These air operated containment isolation valves located in the control air supply lines to the containment.

These valves cannot be full stroke tested during power operation without causing a loss of containment control air.Testing of these valves can potentially cause: 1)disruption of air flow to air operated valves in the containment; as a result, they would go to their fail safe position, e.g., close position for containment isolation valves, 2)systems from performing their design function, i.e, termination of system flow and change in RCS pressure and temperature, and 3)challenge to system safeguard protection which may result.in a unit trip.The valves will be full stroke exercised and timed at cold shutdown frequency.

Page 64 of 81 DONALD C.COOK NUCLEAR PX~VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5131-19

-Unit-2 Revision No: 3 Date: 2-5-90 NOTE 1: CS-427S Cold Shutdown Justification

This valve is located in the emergency boration path.Thxs valve cannot be tested during power operation without inserting large negative reactivity which would result in unit shutdown.The valve will be full stroke exercised at cold shutdown frequency.

Page 65 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5136-25

-Unit 2 Revision No: 3 Date: 2-5-90 NOTE 1: SF-152 and-154 Code Relief: See"Attachment-A" for permissible seat leakage values.Page 66 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES-Flow Diagram No: 12-5137A-21

-Unit 2 Revision No: 3 Date: 2-5-90 NOTE 1: NOTE 2: DCR-201 throu h-207-610-611-620 and-621 N-160 SF-159 and-160 Code Relief: See"Attachment-A" for permissible seat leakage values.N-160 Code Relief: This containment isolation check valve is located in the Nitrogen Supply line to Reactor Coolant Drain Tank.This valve cannot be part or full stroke exercised due to lack of sufficient differential pressure to back seat the valve during power operation or cold shutdown.Due to the plant design, the only method available to verify the valve closure is leak testing.The valve is not equipped with position indicator.

This valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.

Page 67 of 81

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM Flow Diagram No: Revision No: 3 Date: 2-5-90 RELIEF REQUEST NOTES 12-5141C-8

-Unit 2 NOTE 1: ECR-416-417-496-497-535 and-536 Code Relief See"Attachment-A" for permissible seat leakage values.A Page 68 of 81 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5141F-6

-Unit 2 Revision No: 3 Date: 2-5-90 NOTE 1: NOTE 2: NOTE 3: ECR-36 Cold Shutdown Justification

This valve, located in the common sample return line of the lower containment radiation monitors, cannot be part or full stroke exercised during power operation or refueling because closure of the valve would isolate both radiation monitors, which are required to be operable (Technical Specification Table 3.3-6)during power operation (Mode 1 through.4)and refueling (Mode 6).The valve will be full stroke exercised at cold shutdown frequency.

ECR-31-32-33-35-36 and SM-1 Code Relief See"Attachment-A" for permissible leakage values.SM-1 Code Relief: This containment isolation check valve for the containment radiation monitors'sample return cannot be full or part stroke exercised during power operation because these monitors are required to be operable in Modes 1, 2, 3, 4, and 6.The valve is not equipped with position indication.

The valve is located in the open ended return line inside the containment.

The only method available to verify the valve closure is leak testing.The valve will be verified closed in conjunction with Appendix J seat leakage testing at refueling frequency.-

Page 69 of 81

DONALD C.COOK NUCLEAR P T ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 3 Date: 2-5-90 1.CONTAINMENT ISOLATION VALVES Cate o A or AC=Testing Method: (SLT-2)Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except for paragraphs IWV-3426 and IWV-3427, which are applicable (refer to Figure 3., Item N3).Valve No WCR-920,-922 WCR-921,-923 WCR-932,-934 WCR-933,-935 WCR-941,-945 WCR-944,-948 WCR-951,-955 WCR-954,-958 WCR-924,-926 WCR-925,-927 WCR-928,-930 Flow Diaciram Size 5114A 3 5114A 5114A 5114A 5114A 5114A 5114A 5114A 3 5114A 3 5114A 3 5114A~Te DA DA DA DA DA DA DA DA DA DA DA Permissible Leakage 900 900 900 900 900'900 900 900 900 900 900 Page 70 of 81 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 ATTACHMENT-A Revision No: 3 Date: 2-5-90 Valve No.WCR-929,-931 WCR-942,-946 WCR-952,-956 WCR-943,-947 WCR-953,-957 WCR-960,-962 WCR-961,-963 WCR-964,-966 WCR-965,-967 ECR-10,-20 ECR-11,-21 ECR-12,-22 ECR-13,-23 ECR-14,-24 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5141B 5141B 5141B 5141B 5141B 0'0 0.50 0.50 0.50 0.50 Flow~Dia ram Size~Te DA DA DA DA DA DA DA DA DA GL GL GL GL Permissible

.Leakage 900 900 900 900 900 750 750 750 750 750 750 750 750 750 Page 71 of 81 DONALD C.COOK NUCLEAR P T ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 3 Date: 2-5-90 Valve No.ECR-15,-25 ECR-16,-26 ECR-17,-27 ECR-18,-28 ECR-19,-29 CS-442-1 CS-442-2 CS-442-3 CS-442-4 SI-189 SM-1 N-102 N-159 PW-275 Flow Diaciram 5141B 5141B 5141B 5141B 5141B 5128A 5128A 5128A 5128A 5128A 5141F 5143 5128A 5128A Size 0'0 0.50 0.50 0'0 0.50 0.75~Te GL GL GL GL GL CK CK.CK CK CK CK CK CK CK Permissible Leakage 750 750 750 750 750 750 750 750 750 1200 750 750 750 900 Page 72 of 81 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 3 Date: 2-5-90 Valve No.CS-321 VCR-10,-11 VCR-20,-21 DCR-203,-207 N-160, DCR-201 DCR-610,-611 DCR-620,-621 DCR-205,-206 DCR-600,-601 QCR-300,-301 QCM-250,-350 QCR-919,-920 5146B 5146B 5137A 5137A 5137A 5137A 5137A 2.50 5124 5129 5129A 5115A Flow Diaciram Size 5129~Te CK DA DA DA, GL CK, DA DA DA DA DA GL DA Permissible Leakage 1800 1200 1200 750 1125 750 750 1200 900 750 1200 750 SF-152,-154 SF-159,-160 5136 5137A 2.50 DA, GL DA 750 900 Page 73 of 81 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 52 Revision No: 3 Date: 2-5-90 Valve No.NCR-105,-106 NCR-107,-108 NCR-109,-110 RCR-100,-101 DCR-202,-204 ICR-5,-6 ECR-33,-35 ICM-260 ICM-265 ECR-31,-32 XCR-100,-101 XCR-102,-103 GCR-301 GCR-314*Double Discs Flow Diaciram 5141 5141 5141 5128A-5137A 5141 5141F 5142 5142 5141F 5120B 5120B 5128A 5143 ATTACHMENT-A Size 0.50 0.50 0.50 0.375~Te GL-GL GL GL GL GL 0.75 DA GL 0'5 DA 0'0 GL 0.75,2 GL,DA GA (DD)*GA(DD)*GL Permissible Leakage 750 750 750 750 750 750 750'00 600 750 750 750 375 375 Page 74 of 81 DONALD C~COOK NUCLEAR, P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 Revision No: 3 Date: 2-5-90 ATTACHMENT-A Valve No.Flow Diaciram SI 171 g 172 g 194 5143 Size 0.75~Te GL Permissible Leakage NCR-252 CCR-460,-462 CCR-457,CCW-135 CCR-455,-456 SM-4,-6 ICM-251 ICM-250 CA-181S CA-181N SM-8,-10 CCW-243-25 CCW-244-25

• Double Discs 5128A 5135 5135 5135 5147A 5142 5142 5145 5145 5147A 5135B 5135B GL 0.50 GL 0.50 0'0 0.50 GA(DD)*~GA(DD)*CK CK ND CK CK 3 GL 2,2.50 GL,CK GL 450 900 1125 750 750 600 600 750 750 750 750 750 Page 75 of 81 l (

DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 ATTACHMENT-A Revision No: 3 Date: 2-5-90 Valve No.CCW-243-72 CCW-244-72 CCM-430 CCM-431 CCR-440 CCR-441 CCM-432 CCM-433-R-156 R-157 NS-357 ECR-496,-497 ECR-416 ECR-417 ECR-535 Flow Diaciram 5135B 5135B 5135B 5135B 513B 5135B 5135B 5135B 5146B 5146B 5124 5141C 5141C 5141C 5141C Size 1.50 1.50 1.50 1.50 1.50 1.50 0'75 0.375 0.50 0'0 0.50 0.50 0'0~Te CK CK GL GL GL GL GL GL CK CK CK GL GL GL GL Permissible Leakage 750 750 375 375 375 375 375 375 750 750 750 750 375 375 375 Page 76 of 81 0

DONALD C.COOK NUCLEAR P T ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 02 Revision No: 3 Date: 2-5-90 ATTACHMENT-A Valve No.Flow Diaciram Size~Te Permissible Leakage ECR-536 ECR-36 PCR-40 PA-342 NS-283 NPX-151 WCR-900,-902 WCR-901,-903 WCR-912,-914 WCR-913,-915 WCR-904,-906 WCR-905,-907 WCR-908,-910 WCR-909,-911 VCR-101,-201 5141C 5141F 5120B 5120B 5141D 5128A 5114A 5114A 5114A 5114A 5114A 5114A 0.50 0.50 0.50 5147A 14 5114A 5114A" 6 GL DA GA CK CK GL DA DA'A DA DA DA DA DA BF 375 375 375 750 750 375 1800 1800 1800 1800 1800 1800 1800 1800 4200 Page 77 of 81

DONALD C.COOK NUCLEAR NT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 Revision No: 3 Date: 2-5-90 ATTACHMENT-A Valve No.Flow Diaciram Size T~e Permissible Leakage VCR-102,-202 VCR-103,-203 VCR-104,-204 VCR-105,-205 VCR-106,-206 VCR-107,-207 ICM-305 ICM-306 5147A 14 5147A 5147A 5147A 5147A 5147A 24 30 30 24 14 5143 18 5143 18 8,4,8 8,4,8 CCM 452 g 454 I 458 5 1 35 CCM 45 1 I 453 g 459 5135*Double Discs BF BF BF BF BF BF GA(DD)*GA(DD)*-BF,GL,BF BF,GL,BF 4200 7200 9000 9000 7200 4200 2700 2700 3000 3000 Page 78 of 81 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 Revision No:.3 Date: 2-5-90 ATTACHMENT-A 2.CONTAINMENT SPRAY VALVES Cate or A or AC Testing Method: As described in"SLT-2A," Figure 3, Item N3.Valve No.CTS-131W CTS-131E CTS-127W CTS-127E RH-141 RH-142 Flow Diaciram Size 5144 5144 5144 5144 5144 5144~Te CK CK CK CK CK CK Permissible Leakage 35.00 35.00 22.55 21.21 20.70 23.00 Page 79 of 81

DONALD C.COOK NUCLEAR T ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 Revision No: 3 ATTACHMENT-A Date: 2-5-90 3.PRESSURE ISOLATION VALVES Cate o A or AC Testing Method: (SLT-1)Seat leakage test the valve per ASME Code Section XI (refer to Figure 3, Item N3).Valve No.CS-299E CS-299W SI-152-N SI-152-S ICM-129 SI-161-L1,-L4 SI-161-L2,-L3 SI-170-Ll SI-170-L2 SI-170-L3*Double Discs Flow Diaciram 5129 5129 5143 5143 5143 5143 5143 5143 5143 5143 Size 14 10 10 10 CK CK CK CK GA(DD)*CK CK CK CK CK Permissible Leakage 2.0 2.0 5.0 5.0 10.0 10.0 10.0 5.0 1.0 1.0 Page 80 of 81

DONALD C.COOK NUCLEAR P T ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 Revision No: 3 Date: 2-5-90 ATTACHMENT-A Valve No.SI-170-L4 SI-158-Ll,-L4 SI-158-L2,-L3 SI-151-E SI-151-N SI-166-Ll SI-166-L2 SI-166-L3 SI-166-L4 RH-133,-134 Flow Diaciram 5143 5143 5143 5143 5143 5143 P3.43 5143 5143 5143 Size 10 10 10 10 10~Te CK CK CK CK CK CK CK CK CK CK Permissible Leakage 5.0 10.0 10.0 5'5.0 5.0 5.0 5.0 5.0 1.0 Page 81 of 81 0 0 SYSTEM NAME: HAKE UP 8 PRIMARY-HATER UNIT 2 DONALD C.COOK.NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHMARY SHEET-UNIT 2 FLON DIAGRAM: 12-5115A-41 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-QCR-919 3 DA 2 A D/7 0/C C 2 A A EF1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-QCR-920 3 DA 2 A D/7 0/C C 2 A A EF1 E F-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R'ESp NOTE 1 U0e e e e o e e e e o e o e e e 0 SYSTEM NAME: COMPRESSED AIR SYSTEM-UNIT 2 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SURIARY SHEET-UNIT 2 FLON DIAGRAM: 12-5120B-22 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-PA-342 3 CK 2 SA K/7 0/C C 2 A AC CF-1 SLT-1 CF-2 SLT"2 R YESp HOTE 1 R YESp NOTE 2 2-PCR-60 3 GA 2 A M/7 0/C C 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5.EF-7 ET-XXX SLT"2 P NO NO P NO P NO R YESp NOTE 2 2-XCR-100 3 GL 1 A L/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 3 NO C NOp CSJ 3 C NOp CSJ 3 R YESp NOTE 22-XCR-101 3 GL 1 A L/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 3 NO C NOp CSJ 3 C NOp CSJ 3 R YESp NOTE 2 2-XCR-102 3 GL 1 A L/2 0 2 A A EF"1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C HOp CSJ 3 NO C NO, CSJ 3 C NOp CSJ 3 R YESp NOTE 2 2-XCR-103 3 GL 1 A L/2 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 3 NO C NOp CSJ 3 C NOp CSJ 3 R YESp NOTE 2 I I e~

00,000Io e e e e o e e e e e e o e e 0 SYSTEM NAME: CVCS-BORON HAKE-UP-UNIT 2 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHMARY SHEET-UNIT 2 FLON DIAGRAM: 12-5131-19 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SI2E ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE 2-CS-415"3 3 CK 2 SA K/6 0/C 0 3 A C CF1 CF-1 P NO 2-CS-415-4 3 CK 2 SA L/6 0/C 0 A C CF-1 CF-1 P NO 2-CS-426-S

.3 CK 1 SA M/6 0/C 0 A C CF1 CF-1 2-CS-427-S 3 CK 2 SA H/5 C 3 A C CF1 CF2 C NO)CSJ 1 2"QHO-420 3 GA 2 HO L/5 C A B EF1 EF 5 ET-XXX EF"1 EF"5 ET-XXX P NO NO P NO 2-QRV-421 3 GL 2 A H/6 0/C 0 3 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-QRV-422 3 GL 2 A H/7 0 3 A B EF1 EF-5 EF"7 ET-XXX EF-1 EF"5 EF-7 ET-XXX NO P NO 0 e e oe e o e e e o e e e0/8 000 00 0 0 00 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 SYSTEM NAHE: SPENT FUEL PIT COOLING 8 CLEANUP U2 FLON DIAGRAH: 12-5136-25 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION Xl NUMBER REV TYPE SIZE ACT F D I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-SF-152.3 DA 2.5 H K/9 C 2 P A SLT-1 SLT"2 R YES>NOTE 1 2-SF-154 3 GL 2.5 H K/9 C 2 P A SLT-1 SLT-2 R YES>NOTE 1 0 0 o o o e o e ee oe a o0 SYSTEM NAME: NDS VENTS&DRAINS-UNIT 2 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 12-51'37A-21 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F D t PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2DCR201 3 DA 1 A E/0 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2"DCR-202 3 DA 0.75 A E/5 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-203" 3 DA 1 A F/0 C 2.P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-204 3 DA 0.75 A F/5 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-205 3 GL A E/7 0/C C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 0 e o o e e e e e e e e e e e e 0 SYSTEM NAME: WDS VENTS 8 DRAINS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UNIT 2 FLOW DIAGRAM: 12-5137A-21 RUN DATE AND TIME: 15FEB90s16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F-D.I POWER SAFETY ICD A/P CAT TYPE COORD I OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-DCR-206 3 GL A E/B 0/C C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF"7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-207 3 DA 1 A F/4 0 2 A A EF-1 E F-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF"7 ET-XXX SLT-2 NO P NO HO R YES>NOTE 1 2"DCR-610 3 DA 2.5 A M/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-611 3 DA 2.5 A N/9 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-DCR-620 3 DA 1 A M/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P NO P NO R YES>NOTE 1 ea e e e ee00 00 000 iverSYSTEH NAHE: NDS VENTS&DRAINS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLON DIAGRAH: 12-5137A-21 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SI2E ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-DCR-621 3 DA 1 A N/9 0 2 A A EF1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF"5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-N-160 3 CK 1 SA F/4 0 2 A AC CF1 SLT-1 CF-2 SLT-2 R YES>NOTE 2 R YES>NOTE 1 2-SF-159 DA H E/5 C 2 P A SLT-1 SLT-2 R YESp NOTE 1 2"SF-160 3 DA 3 H F/5 C 2 P A SLT-1 SLT-2 R YESi NOTE 1 (0 0~~0~0~~0~~~0~0 0 SYSTEH NAHE: PAS LIQUID 8 GAS-UNIT-2 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLON DIAGRAH: 12-5141C-8 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.t PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED NODE 2-ECRW16 3 GL 0.5 A H/6 C 2 P A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-ECR-417 3 GL 0.5 A H/6 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES'OTE 1 2-ECR-496 3 GL 0.5 A H/8 C 2 P A EF-1 EF-5 EF-7 ET"XXX SLT-1 EF"1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2"ECR"497 3 GL 0.5 A H/8 C 2 P A EF"1=EF-1 EF-5 EF-5 EF-7 EF-7 P NO NO P NO ET-XXX SLT-1 ET-XXX SLT-2 P NO R YES>NOTE 1 2-ECR-535 3 GL 0.5 A H/2 C 2 P A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 Ef-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1

SYSTEM NAME: PAS LIQUID&GAS-UNIT-2-DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLOW DIAGRAM: 12-5141C-8 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUt&ER REV TYPE SI2E ACT F.D.I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-ECR-536 3 GL 0.5 A L/2 C 2 P A EF1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESi NOTE 1 o e ee e e e e e e e e e e0 0 o o e o e e e e o o e e.o e e 0 SYSTEM NAME: PAL SAMPLING 2 INST.PANELS-U-2 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUiiARY SHEET-UNIT 2 FLOW DIAGRAM: 12-5141F-6 RUN DATE AND TIME: 15FEB9D:16:14 VALVE I VALVE POSITION I ASME SECTION XI Ql$3ER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT TYPE COORD I OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MiODE 2-ECR-31 3 GL 1 A B/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 2-ECR-32"GL 1 A B/5 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF"7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 2-ECR-33 GL 0.75 A B/2 0 2 A A EF-1 EF-5 EF-7 ET"XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 2-ECR-35 3 GL 1 A B/2 0 2 A A EF-1'F-1 EF"5 EF-5 EF-7 EF-7 P NO NO P HO ET-XXX SLT-1 ET-XXX SLT-2 P NO R YESp NOTE 2 2-ECR-36 3 GL 1 A B/3 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 1 NO, C NOp CSJ 1 C YESp CSJ 1 R YESp NOTE 2 eoae DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VAlVE SUiiARY SHEET-UNIT 2 SYSTEM NAME: PAL SAMPLING&INST.PANELS-UNIT 2 FLON DIAGRAM: 12-5141F-6 RUN DATE AND TZHE: ISFEB90:16:10 VALVE I VALVE POSITION I ASHE SECTION XINUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE2-SH-1 3 CK 1 SA A/3 0 2 A AC CF 1 SLT-1 CF-2 SLT-2 R YESp NOTE 3 R YES>NOTE 2 0 0 e e e e e e e e e e e o e e e 4 SYSTEM NAME: HAIN STEAM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-51058-42 RUN DATE AND TIHE: ISFEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY!CD A/P CAT PRIH TEST TEST TEST RELIEF REQUESTERS)

TYPE COORDI OPER FUNCT ICL'-REQUIRED PERFORMED MODE 2-DCR-310 3 GL 2 A B/3 0 2 A B EF1 EF-5 EF-7 ET-XXX EF"1 EF-5 EF-7 ET-XXX P NO NO P NO P NO T 2-DCR-320.3 GL 2 A B/2 0 2 A B EF-1 Ef-5 EF-7 ET"XXX EF-1 E F-5 EF-7 ET-XXX P NO NO P NO P NO 2-DCR-330 3 GL 2 A B/1 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-DCR-340 3 GL 2 A B/2 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO P NO 2-QT-506 3 GL 4 HO A/8 C A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 0000 SYSTEM NAME: STEAM GENERATING SYSTEM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5105D"2 RUN DATE AND TIME: 15FEB90:16:14 VALVE VALVE POSITION I ASHE SECTION XI NOSER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-FN" 118-1 3=CK 14 SA B/9 0 2 A C CF1 CF"2 R YES>NOTE 1 2-FH"118" 2 3 CK 14 SA K/8 0 2 A C CF1 CF-2 R YES>NOTE 1 2-FN-118-3 3 CK 14 SA J/3 0 2 A C CF1 CF-2 R YES)NOTE 1 2-FH-ll8-4 3 CK 14 SA C/3 0 2 A C CF1 CF-2 R YES>NOTE 1 2-HCM" 221 3 GL HO K/4 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-HCH-231 3 GL HO K/4 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-HRV-210 3 GA 28 PO B/7 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-3 EF-5 EF-8 ET-XXX P NO>CSJ 2 NO C NOp CSJ 2 C NOp CSJ 2 2-HRV"211 3 AG 2 A A/5 C 2 A B EF 1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-HRV-212 3 AG 2 A A/5 C 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 0 0 e e e e o e o e o o e o e e e 0 SYSTEM NAME: STEAM GENERATING SYSTEM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL~VALVE

SUMMARY

SHEET-UNIT 2 FLOW DIAGRAM: 2-5105D-2 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-MRV-220 3 GA 28 PO L/7 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-3 EF"5 EF-8 ET-XXX P NO>CSJ 2 NO C NOp CSJ 2 C NOy CSJ 2 2-HRV-221 3 AG 2 A H/5 C 2 A B EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO NO P NO 2-MRV-222 3 AG 2 A M/5 C 2 A B EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2"HRV-230 3 GA 28 PO H/3 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-3 EF-5 EF-8 ET-XXX P NO)CSJ 2 NO C NO>CSJ 2 C NO>CSJ 2 2-MRV-231 3 AG 2 A H/1'C 2 A B EF-1 EF-5 EF-7 ET-XXX EF-1 EF"5 EF-7 ET-XXX P NO NO P NO P NO 2-HRV-232 3 AG 2 A H/1 C 2 A B EF"1 EF-5 EF-7 ET-XXX EF-1 Ef-5 EF-7 ET-XXX P NO NO P NO P NO J4 SYSTEM NAME: STEAM GENERATING SYSTEM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5105D-2 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUMBER REV TYPE SIZE ACT F.D.t POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-HRV-240 3 GA 28 PO 8/3 0 2 A 8 EF1 EF-5 EF-7 ET-XXX E F-3 EF-5 EF-8 ET-XXX P NOp CSJ 2 NO C NOp CSJ 2 C NOp CSJ 2 2-HRV-241 3 AG A A/1 C 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-HRV-242 3 AG 2 A A/1 C 2 A 8 EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF"7 ET-XXX P NO NO P NO P NO 2-HS-108-2 3 CK 4 SA K/4 C 0/C 3 A C CF-1 CF-2 R YESp NOTE 32-HS-108-3 3 CK 4 SA K/4 C 0/C 3 A C C F1 CF-2 R YESp NOTE 3 2-SV-1A-1 2-SV-1A-2 3 REL 6 3 REL 6 SA C/5 C SA K/5 C 0'A C TF-1 2 A C TF1 TF-1 TF-1 R NO 2-SV-1A-3 3 Rf L 6 SA K/1 C 2 A C TF-1 TF-1 R NO 2-SV-1A-4 3 REL 6 SA C/1 C 2 A C TF"1 TF-1 R NO e e e o o e o e e e e e o e e N SYSTEM NAME: STEAM GENERATING SYSTEM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMHARY SHEET-UNIT 2 FLON DIAGRAM: 2-5105D-2 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV.TYPE SIZE ACT F.D~I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDl OPER FUNCT ICL REQUIRED PERFORMED MODE 2-SV-1B"1 3 REL 6 SA B/5 C 2 A C TF-1 TF"1 2-SV-1B-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1 2-SV-1B-3 3 RE L 6 SA L/1 C 2 A C TF-1 TF-1 2-SV-1B-4 3 REL 6 SA B/1 C 2 A C TF1 TF"1 R NO 2-SV-2A-1 3 REL 6 SA B/5 C 2 A C TF-1 TF-1 2-SV-2A-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1 2"SV-2A-3 3 REL 6 SA L/1 C 2 A C TF-1 TF-1 R NO 2-SV-2A-4 3 REL 6 SA B/1 C 2 A C TF-1 TF-1 2-SV"2B-1 3 REL 6 SA B/5 C 2 A C TF-1 TF-1 2-SV-2B-2 3 REL 6 SA L/5 C 2 A C TF-1 TF-1 R NO 2"SV-2B-3 3 REL 6 SA L/1 C 2 A C TF1 TF-1 2-SV"2B-4 3 REL 6 SA B/1 C 2 A C TF1 TF-1 R NO e e oeo e e e-o e e0 o o e e e e e e e e e o e o e 0 SYSTEH NAME: STEAM GENERATING SYSTEM DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLON DIAGRAM: 2-5105D-2 RUN DATE AND TIME:)5FEB90:)6:)4 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F D t PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE 2-SV-3-1 3 REL 6 SA B/5 C 2 A C TF1 TF-1 R-NO 2-SV-3-2 3 REL 6 SA H/5 C 2 A C TF-1 TF-1 2-SV-3-3 3 REL 6 SA H/1 C 2'C TF1 TF-1 R NO 2-SV-3-4 REL 6 SA B/1 C 2 A C TF-1 TF-)R NO 0 e o o o e o e o o o e e e o e 0

~~SYSTEM NAME: FEEDHATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYHARY SHEET-UNIT 2 FLON DIAGRAM: 2-5106-34 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F~D.I PONER SAFETY)CD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-FHO" 201 3 GA 14 HO G/5 0 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 2-FHO-202 3 GA 14 HO E/9 0 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 2-FHO-283 3 GA 14 HD F/9 0 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 2-FHO-204 3 GA 14 HO H/5 0 2 A 8 EF-1 E F-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 2-FRV" 210 3 AG 14 A G/5 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 C NOp CSJ 1" 2-FRV-220 3 AG 14 A E/9 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF"8 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 C NOp CSJ 1 2-FRV-230 3 AG 14 A F/9 0 2 A B EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX C NOp CSJ 1 NO C NOp CSJ 1 C NOp CSJ 1

SYSTEM NAME: FEEDWATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHMARY SHEET-UNIT 2 FLOW DIAGRAM: 2-5106-Wt RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F D I POWER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED, PERFORMED MODE 2-FRV-260 3 AG 10 A , M/5 0 2 A B EF1 EF-5 EF-7 ET-XXX EF"2 EF-5 EF-8 ET-XXX C NO>CSJ 1 NO C NO>CSJ 1 C NO>CSJ 1 0e o 0 o i o ae e e ee 00 e e o e ee e e e e o o e e 0 SYSTEH NAHE: FEEDNATER DONALD C COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET" UNIT 2 FLON DZAGRAH: 2-5106A-41 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION)ASHE SECTION XZ NUiiBER REV TYPE SI2E ACT F~D)POHER SAFETY)CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HiODE 2-FHO-211 3 GL HO 8/4 0 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-FHO-212 3 GL HO 8/4 0 3 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-FHO-221 3 GL 4 HO C/5 0 3 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO P NO 2-FHO-222 3 GL 4 HO C/5 0 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-FHO-231 3 GL HO C/5 0 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P-NO 2-FHO"232 3 GL 4 HO C/5 0 3 A 8 EF1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO P NO 2"FHO-241 3 GL 4 HO 8/4 0 0 3 A 8 EF1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO o e oee o ee eeT illSYSTEM NAME: FEEDHATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5106AWl RUN DATE AND TIHE: 15FEB90:16:14 VALVE VALVE POSITION I ASHE SECTION XZ NUHBER REV TYPE SIZE ACT F~D I POHER SAFETY I CD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-FHO-242 3 GL MO B/4 0 3 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-FRV-247 3 GL 1 A H/9 0 C/0 3 A B EF-1 EF"5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 5 2-FRV-257 3 GL 1 A H/9 0 C/0 3 A B EF-1 EF"5 EF-7 ET-XXX EF-1 EF-5 EF<<7 ET-XXX P NO NO P NO P NO 2-FRV-258 3 GL 1 A E/9 0 C/0 3 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-FH-124 CK 8 SA F/7 C 3 A C CF1 CF-1 P NO 2"FH-128 3 CK 6 SA H/7 C 3 A C CF-1 CF-1 P NO 2-FN-132-1 3 CK SA C/4 C 0/C 2 A C CF-1 CF-2 NOp CSJ 1 2-FN-132-2 3 CK 4 SA D/5 C 0/C 2 A C CF-1 CF-2 NO>CSJ 1

0 SYSTEN NAHE: FEEDHATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLOH DIAGRAH: 2-5106A-41 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUNBER REV TYPE SIZE ACT F AD.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE 2-FH"132"3 3 CK SA D/5 C 0/C 2 A C CF-1 CF-2 NOp CSJ 1 2-FH-132-4 3 CK 4 SA C/4 C 0/C 2 A C CF-1 CF-2 NOy CSJ 1 2-FH-134 3 CK 10 SA 8/9 C 3 A C CF1 CF-3 C NO>CSJ 2 2-FH-135 3 CK 8 SA E/8 C 3 A C CF1 CF-3 C NOp CSJ 2 2-FH-138-1 3 CK SA C/4 C 0/C 2 A C CF-1 CF-2 2-FH-138-2 3 CK 4 SA D/5 C 0/C 2 A C CF-1 CF-2 NO>CSJ 3 2-FH-138"3 3 CK SA D/5 C 0/C 2, A C CF-1 CF-2 NOp CSJ 3 2-FH-138-4 3 CK 4 SA C/4 C 0/C 2 A C CF-1 CF-2 NO>CSJ 3 2-FH-149 3 CK 0.75 SA D/2 C 3 A C CF-1 CF-1 P NOr NOTE 2-FH-150 3 CK 0.75 SA D/3 C 3 A C CF1 CF-1 P NO~NOTE 4 2-FH-153 3 CK 1 SA N/9 C 0/C 3 A C CF-1 CF-1 P NO>NOTE 5 2-FH"159 3 CK 6 SA L/7 C 3 A C CF1 CF-1 P" NO 0 o o o o o o e e o o e e e o e SYSTEM NAME: FEEDNATER DOHALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UHIT 2 FLOH DIAGRAM: 2-5106A-41 RUH DATE AHD TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F~D.I POHER SAFETY}CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-FN-160 CK 1 SA M/9 C 0/C 3 A C CF-1 CF-1 P NO>NOTE 5 2-FN-161 3 CK 8 SA J/7 C 3 A C CF-1 CF-1 2-SV-140-1 3 REL 0.75 SA E/1 C 3 A C TF1 TF-1 R NO 2-SV-140-2 REL 0.75.SA D/1 C A C TF-1 TF"1 R NO 2"SV-169"A 3 RE L 0.75 SA K/9 C A C TF-1 TF-1 R HO 2-SV-169-B 3 REL 0.75 SA G/9 C 3 A C TF1 TF-1 R NO 0 e e0 o 0 o e00 0 0e e eo e e.ee e o e e e 0 SYSTEM NAME: ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5113-36 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION Xl NUMBER'EV TYPE SIZE ACT F~D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-ESH-102-2E 3 CK 20 SA M/8 C A C CF-1 CF-1 2-ESH-102-2H 3 CK 20 SA M/8 C 3 A C CF1 CF-1 2-ESH-141 3 CK 6 SA K/6 C 3 A C CF1 CF-1 P NO>NOTE 1 2" ESH-142 3 CK 6 SA L/6 C 3 A C CF1 CF-1 P-NO>NOTE 1 2-ESH-143 3 CK 6 SA M/6 C 3 A C CF1 CF-1 P NO>NOTE 1 2-ESH-144 3 CK 6 SA M/6 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-ESH-145 3 BF 4 M J/6 C 3 A B EF1 EF-2 C NO>CSJ 2 2-ESH-168-N 3 BF M H/I C 3 A B EF1 EF-1 2-ESH-168-S 3 BF 3 M M/I C 3 A B EF1 EF-1 P NO 2-ESH-169-N 3 BF M G/1 0 3 A B EF1 EF-1 2-ESH-169-S 3 BF 3 M G/1 0 3 A B EF1 EF"1 P NO 2-ESH-170-N 3 BF M F/1 0 3 A B EF1 EF"1 P NO

SYSTEM NAME: ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5113-36 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-ESW-170-S 3 BF 3 H F/1 0 3 A 8 EF1 EF-1 P NO 2-ESN-171-N 3 BF 3 H F/1 C A 8 EF1 EF-1 2-ESH-171-S 3 BF 3 H F/1 C 3 A 8 EF-1 EF-1 P NO 2-ESN-240 3 BF 6 H H/5 C 3 A 8 EF-1 EF-2 C NOp CSJ 2 2-ESN" 243 3 BF 4 H J/7 C 3 A 8 EF"1 C NO>CSJ 2 2-SV-14-2E 3 REL 1 SA L/1 C 3 A C TF1 TF-1 2-SV-14-2N 3 REL 1 SA H/1 C 3 A C TF1 TF-1 R NO 2-SV-15-2E 3 REL 0.75 SA G/3 C 3 A C TF1 TF"1 2-SV-15-2W 3 RE L 0.75 SA J/4 C A C TF-1 TF-1 R NO 2-SV-16-AB 3 RE L 1 SA L/8 C A C TF-1 TF-1 2-SV-16-CD 3 REL 1 SA L/8 C 3 A C TF1 TF-1 R NO 2-l00-703-2E 3 BF 20 HO N/8 C 3 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 00 0000 0 0 4 0 SYSTEM NAME: ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLOW DZASH: 2"5113-36 RUN DATE AND TIME: 15FEB90:16:10 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-WHO-704-2H 3 BF 20 HO H/8 C 3 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-WHO-706 3 BF 20 HO G/8 0 0/C 3 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-WHO-708 3 BF 20 MO G/6 0 0/C 3 A B EF"1 EF-5 ET"XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-WHO-714 3 BF 12 HO H/5 C 3 A B EF1 EF-5 ET-XXX EF-1 EF"5 ET-XXX P NO NO P NO 2-WHO-718 3 BF 12 HO N/5 C 3 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2"WHO-722 3 BF 6 HO H/6 C 3 A B EF1 EF"1 EF"5 EF-5 ET-XXX ET-XXX P NO NO P NO 2-WHO-724 3 BF 6 MO H/6 C 0 3 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 0e a ee0 oe.0 e e0 SYSTEH NAHE: ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5113-36~~RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.t PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE 2-HHO-726 3 BF 6 HO K/6 C A B EF1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO P NO 2-lOO-728 3 BF 6 HO L/6 C 3 A 8 EF-1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO P NO.2"NHO-734 3 BF 16 HO H/3 0/C 0 3 A B EF-)EF-5 ET-XXX EF-'1 EF-5 ET-XXX P NO NO 2-NHO-738 3 BF 16 HO K/3 0/C 0 3 A B EF1 EF-1 P NO EF-5 ET"XXX EF-5 ET-XXX NO P NO 2-NHO-744 3 BF HO J/6 C 3 A B EF1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO P NO 2-NHO-753 3 BF 6 HO H/5 C 3 A B EF1 EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO P NO 2-NHO-754 3 BF 4 HO K/6 C.3 A B EF-1EF-1 EF-5 EF-5 ET-XXX ET-XXX P NO NO eoeeeI 0 000 0 00 000 SYSTEM NAME: ESSENTIAL SERVICE HATER t DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5113-36 VALVE I VALVE POSITION I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-HRV-722-CD 3 3W A K/8 0 A B EF1 EF-7 ET-XXX NOTE 3 EF-8 NOTE 3 P YES>NOTE 3 R YES'OTE 3 YESp NOTE 3 2-HRV-724-CD 3 3H 4 A M/8 0 3 A B EF1 EF-7 ET-XXX NOTE 3 EF-8 NOTE 3 P YES>NOTE 3 R YESi NOTE 3 YES>NOTE 3 2-HRV"726-AB 3 3H A K/8 0 3 A B EF1 EF-7 NOTE 3 EF-8 P YES>NOTE 3 R YES>NOTE 3 ET-XXX NOTE 3 YES>NOTE 3 2-HRV-728-AB 3'H A M/8 0 EF-7 ET-XXX EF-8 NOTE 1 3 A B EF1 NOTE 3 P YESp NOTE 3 R YESi NOTE 3 YESp NOTE 3 0 e o e e e e e o e e o e e e e 0 SYSTEN NAME: NON-ESSENTIAL SERVICE HATER t DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SLMARY SHEET-UNIT 2 FLON DIAGRAN: 2-5114A-27 VALVE I VALVE POSITION I ASNE SECTION XI HURLER REV TYPE SIZE ACT F.D-I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUHCT ICL PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED-PERFORNED NODE 2-WCR-900-1 3 DA 6 A J/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P NO P NO R YESi NOTE 1 2-HCR-901-1 3 DA 6 A K/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P HO P NO R YES>NOTE 1 , 2-NCR" 902-1 3 DA 6 A J/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-NCR-903-1 3 DA 6 A K/4 0 2 A A EF"1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO NO P HO P NO R YES>NOTE 1 2-NCR-904-2 3 DA 6 A J/9 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>HOTE 1 0 e o e e e e o eeee 0 0 SYSTEH NAHE: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYiiARY SHEET-UNIT 2 FLOW DIAGRAH: 2-5114A-27 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUHBER REV TYPE SIZE ACT F~D I POWER SAFETY I CD A/P CAT TYPE COORDI OPER FUNCT ICL PRZH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED NODE 2-HCR-905-2 3 DA 6 A K/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF.-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-HCR-906-2 3 DA 6 A J/4 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES1 NOTE 1 2-HCR-907 3 DA 6 A K/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-HCR-908-3 3 DA 6 A J/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT"2 P NO NO P NO P NO R YES>NOTE 1 2-HCR"909-3 3 DA 6 A K/9 0 C2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 0 (0 o e o e e e e e e e e e o e e 0 0 SYSTEM NAME: NOH-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5114A-27 RUH DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTIOH XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE COORD I OPER FACT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2"NCR-910-3 3 DA 6 A J/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF"7 ET-XXX SLT-2 P NO HO P NO P HO R YES>NOTE 1 2-NCR-911-3 3 DA 6 A K/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P HO R YES>NOTE 1 2-NCR-912-4 3 DA 6 A J/9 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO'P NO R YES>NOTE 1 2-NCR-913-4 3 DA 6 A K/9 0 2 A A EF-1 EF-5 EF-7 ET"XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P NO P HO R YES>NOTE 12-NCR-914"4 3 DA 6 A J/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P HO P HO R YES'OTE 1 0e ea0o e0~,0 SYSTEN NAHE: HON-ESSENTIAL SERVICE HATER t DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SWARY SHEET-WIT 2 FLON DIAGRAN: 2-511%A" 27 RUN DATE AND TINE: 15FEB90tl6:14 VALVE I VALVE POSITION I ASNE SECTION XI HUNBER REV TYPE SIZE ACT F.D.I PONER SAFETYlCD A/P CAT TYPE COORD I OPER FUNCT ICL PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORNED NODE 2-HCR-915-0 3'A 6 A K/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF"7, ET-XXX SLT-2 P NO HO P HO P hO R YESi NOTE 1 2-HCR-920-1 3 DA A J/6 0 2 A A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P HO P NO R YES>NOTE 1 2-HCR-921-1 3 DA A K/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P HO P NO R YES>NOTE 1 2-HCR-922-1

-3 DA 3 A K/2 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-NCR-923-1 3 DA 3 A J/2 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 P HO EF-5 HO EF-7 P NO ET-XXX P HO SLT-2 R YES@NOTE 1 0 e e e e o e o e o o e o o e e~

SYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SURtARY SHEET-UNIT 2 FLOH DIAGRAM: 2-5114A-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUYBER REV TYPE SIZE ACT F.D.I POHER SAFETY tCD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-HCR-924-2 3 DA 3 A J/6 0 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-XXX ET-XXX P NO NO P NO P NO SLT-1 SLT-2 R YES>NOTE 1 2-HCR-925-2 3 DA 3 A K/6 0 2 A A EF-1 EF-1 P NO EF"5 EF-5 EF-7 EF-7 ET-XXX ET-XXX SLT-1 SLT-2 NO P NO P NO R YESp NOTE 1 2-HCR-926-2 3 DA A K/2 0 2 A A EF-1 EF-1 EF-5 EF"5 P NO NO EF-7 ET"XXX SLT-1 EF-?ET-XXX SLT-2 P NO P NO R YES>NOTE 1 2-HCR-927-2 3 DA A J/2 0 2 A A EF-1 EF-1 EF"5 EF-5 EF-7 EF-7 P NO NO P NO ET-XXX SLT-1 ET"XXX SLT-2 P NO R YESp NOTE 1 2"HCR-928"3 3 DA 3 A J/6 0 2 A A EF-1 EF-1 EF-5 EF"5 EF-7 EF-7 ET-XXX ET-XXX SLT-1 SLT-2 P NO NO P NO P NO R YESp NOTE 1 0 o o e e o e e e e e e e e o e 0 0 SYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5114A-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.DE I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM'TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-HCR-929-3 3 DA 3 A K/6 0 2 A A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF"5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-HCR-930-3 3 DA 3 A K/2 0 2 A A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YESp NOTE 1 2-HCR-931-3 3 DA 3 A J/2 0 2 A A EF"1 EF-5 EF"7 ET-XXX SLT-1 EF"1 EF-5 EF-7 ET"XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-HCR"932%

3 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX.SLT-1 EF-1-EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-HCR"933 3 DA 3 A K/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX'LT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1

, e o ee e e e ea e e0 o o e e e o e o o e o e o e a SYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5114A-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT lCL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-HCR-934 3 DA 3 A K/2 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF"5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-HCR-935 3 DA'A J/2 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES>NOTE 12-HCR-941-1 3 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF"1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-HCR-942-2 3 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-HCR-943-3 3 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF"7 ET-XXX SLT"2 P NO NO P NO P NO R YES>NOTE 1 0 o e e 0 oe a e e o e e

]IISYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL'ALVE

SUMMARY

SHEET-UHIT 2 FLOW DIAGRAM: 2-5114A-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITZOH I ASME SECTION XI HUYBER REV TYPE SIZE ACT F.D.t POWER SAFETY ICD A/P CAT TYPE COORDI OPER FUHCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-WCR-944-4 3 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P HO P NO R YES>NOTE 1 2"WCR-945 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 HO P NO P NO R YES>NOTE 1 2-WCR-946-2 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES>NOTE 1 2-HCR-947"3 3 DA 3 A J/3 0 2 A A EF"1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-m SLT-2 P NO HO P HO P NO R YES>NOTE 1 2-WCR-948-4 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P NO P HO R YES>NOTE 1

SYSTEH HAHE: NON-ESSENTIAL SERVICE WATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET-i%IT 2 FLOW DIAGRAH: 2-511%A-27 RUH DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUNBER REV TYPE SIZE ACT F AD t POWER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED NODE 2-WCR-951 3 DA 3 A K/6 0 2 A A EF"1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-WCR-952-2 3 DA 3 A K/6 0 2 A A EF-1 EF"5 EF"7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P.NO P HO R YESp NOTE 1 2-WCR-953-3 3 DA A K/6.0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES'OTE 1 2-WCR-954-4 3 DA 3 A K/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1 2-WCR-955 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO P NO R YES>NOTE 1 0 aa 0o aea0 eo o e e e e o o e e e e e 0

-SYSTEN NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE'SUWRY SHEET-UNIT 2 FLOH DIAGRAN: 2-5114A-27 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY!CD A/P CAT TYPE COORDI OPER FUNCT ICL PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PER FORHED VADE 2-HCR-956-2 3 DA A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO NO P NO P HO R YES>NOTE 1 2-HCR-957-3 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF-7 ET-XXX SLT-2 P NO HO P HO P NO R YES'OTE 1 2-HCR-958-4 3 DA 3 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO P NO R YES>NOTE 1 2-HCR-960 3 DA 2 A J/7 0 2 A A EF-1 Ef-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES>NOTE 1 2-NCR-961 3 DA 2 A J/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO P HO R YES>NOTE 1 00 a o N e oe0 e 0e SYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5114A-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE VALVE POSITION ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-HCR-962 3 DA 2 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES)NOTE 1 2-NCR-963 3 DA 2 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P HO ,P HO R YESi NOTE 1 2-HCR"964"3 3 DA 2 A J/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO P HO R YESp NOTE 1 2-NCR-965-3 3 DA 2 A J/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF"1 EF-5 EF-7 ET-XXX SLT-2 P HO NO P NO P HO R YES>NOTE 1 2-NCR-966-3 3 DA 2 A J/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO ND P HO P NO R YES7 NOTE 1 e e e 0e o ee ae.0 0 0 00 00 00 lllSYSTEM NAME: NON-ESSENTIAL SERVICE HATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SmDlARY SHEET-UNIT 2 FLON DIAGRAM: 2-5116A-27 RUN DATE AND TIME: 15FEB90l16l10 VALVE I VALVE POSITION I ASHE SECTION XZ NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-HCR-967-3 3 DA 2 A J/3 0 2 A A EF1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1

~0~~0 0 0 0~~~0~~~0~

SYSTEM NAME: STATION DRAINAGE-CONTAINMEHT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SRQRRY SHEET-UNIT 2 FLOH DIAGRAM: 2-5124-20 RUN DATE AND TIME: 15FEB90:16:14

~~VALVE I VALVE POSITION i ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE 2-DCR-600 3 DA A N/6 0 2 A A EF1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO P NO R YESp NOTE 1 2-DCR-601 3 DA 3 A N/6 0 2 A A EF1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF-7 ET-XXX SLT-2 HO P HO P HO R YESp NOTE 1 2-NS-357 3 CK 0.5 SA K/9 C 0/C A 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YESp NOTE 2 R YES>HOTE 1 ee 0e e e e e e e e e e0 0 o e o e e e e e o e e e e e e 0 SYSTEH NAHE: REACTOR COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5128-19 RUN DATE AND TINE: 15FEB90:16:10 VALVE I VALVE POSITZON I ASHE SECTION XZ NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE 2-NSO-021 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2 EF-5 EF-5 EF-7 EF-8 ET-XXX ET-XXX C NOp CSJ 1 NOp CSJ 1C NOp CSJ 1 C NOp CSJ 1 2-NSO-022 3 GL 1 SO J/6 C 0/C ,2 A B EF-1 EF-2 EF-5 EF-5 NOp CSJ 1 NOp CSJ 1 EF-7 ET"XXX EF-8 ET-XXX C NOp CSJ 1 C NOp CSJ 1 2-NSO-023 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2 EF-5 EF-5 EF"7 EF-8 ET-XXX ET-XXX C NOp CSJ 1 NOp CSJ 1 C NOp CSJ 1 C NOp CSJ 1 2-NSO-024 3 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2 EF-5 EF-5 C NOp CSJ 1 NOp CSJ 1 EF-7 ET-XXX EF-8 ET-XXX C NOp CSJ 1 C NOp CSJ 1 I00-00 000 SYSTEM NAME: REACTOR COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5128A-34 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUM3ER REV-TYPE SIZE ACT F.D.I PONER SAFETY I CD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE Z-CS-442-1 3 CK 2 SA B/4 0 A AC CF-1 SLT-1 CF"2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2"CS~Z-2 3 CK 2 SA B/4 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES'OTE 2 2-CS-44Z-3 3 CK 2 SA B/4 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2-CS-442-4 3 CK 2 SA B/4 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2-GCR-301 3 DA 0.75 A B/8 0 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF"7 ET-XXX ET-XXX SLT-1 SLT-2 P NO NO P NO P NO R YES>NOTE 2 2"N-159 CK 0.75 SA C/8 0/C C 2 A AC CF-1 SLT-1 CF-2-SLT-2 R YES>NOTE 5 R YES'OTE 2 2-NCR-252 3 GL A B/9 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 2 2-NHO-151 3 GA 3 HO K/7 0 1 A B EF-1 EF-1 EF-5 EF-5 ET-XXX ET-XXX e oeoea, 0 0 0 000 00 00 Ill 0 SYSTEH NAME: REACTOR COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMHARY SHEET-UNIT 2 FLOH DIAGRAM: 2-5128A-34 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F AD I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-%)0-152 3 GA 3 MO K/7 0 1 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-HYA)-153 3 GA MO K/6 0 1 A B EF"1 EF"5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-NPX-151 3 GL 0 5 H N/8 C 2 P A SLT-1 SLT-2 R YES>NOTE 2 2"NRV-151 3 GL 3 A K/7 C C/0 1 A B EF-1 EF-5 EF-7 ET-XXX EF"2 Ef-5 EF-8 ET-XXX NO>CSJ 3 NO NO>CSJ 3 NO>CSJ 3 2-NRV-152 3 GL 3 A K/7 C C/0.1 A B EF-1 EF-5 EF"7 ET-XXX EF-2 EF-5 EF-8 ET-XXX NO>CSJ 3 NO NOp CSJ 3 NO>CSJ 3 2-NRV-153 3 GL A K/6 C C/0 1 A B EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX NO>CSJ 3 NO NO>CSJ 3 NO>CSJ 3 2-NSO-061 3 GL 1 SO H/6 C 0/C 2 A B EF-1 EF"5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET"XXX C NO>CSJ 6 NO>CSJ 6 C NO>CSJ 6 C NO>CSJ 6 0 00 00 0 00 00 SYSTEH NAHE: REACTOR COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYMARY SHEET-UNIT 2 F LON DIAGRAH: 2-5128A-Wt RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIH TEST TEST TEST RELIEF REQUEST<S)

REQUIRED PERFORHED NODE 2-NSO-062 3 GL 1 SO H/6 C 0/C 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX C NOp CSJ 6 NOp CSJ 6 C NOp CSJ 6 C NOp CSJ 6 2"NSO-063 3 GL 1 SO H/6 C 0/C 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX C NOp CSJ 6 NOp CSJ 6 C NOp CSJ 6 C NOp CSJ 6 2-NSO-064 3 GL 1 SO H/6 C 0/C , 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-2 EF-5 EF-8 ET-XXX C NOp CSJ 6 NOp CSJ 6 C NOp CSJ 6 C NOp CSJ 6 2-PN-275 3 CK 3 SA 8/9 0/C C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YESp NOTE 0 R YESp NOTE 2 2-RCR-100 GL 0.375 A 8/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 2-RCR"101 3 GL 0.375 A 8/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 0'0 00 0 0 0 0 00 0 0 0 SYSTEM NAHE: REACTOR COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUKIARY SHEET-UNIT 2 FLON DIAGRAM: 2-5128A-34 RUN DATE AND TIME?15FEB90:16:14 VALVE I VALVE POSITION t ASHE SECTION XI tilPSER REV TYPE SI2E ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST REL1EF REtQESTlS)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE 2-SI-189 3 CK SA D/7 C 0/C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 7 R YES>NOTE 2 2-SV-45A 3 REL 6 SA K/6 C 1 A C TF-1 TF-1 R NO 2-SV-45B 3 REL 6 SA J/6 C 1 A C TF1 TF-1 R NO 2-SV-45C 3 REL 6 SA N/6 C 1 A C TF1 TF-1 R NO 2-SV-50 3 REL 2 SA 6/3 C A C TF-1 TF-1 R NO

SYSTEH NAHE: CVCS-LETDOHN 8 CHARGING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLOH DIAGRAH: 2-5129-32 RUiN DATE AND TINE: 15FE890:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUiiBER REV TYPE SIZE ACT F~D~f POHER SAFETY (CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUiNCT ICL REQUIRED PERFORHED NODE 2-CS-292 3 CK 2 SA H/6 C 0/C 2 A C CF-1 CF-2 C YESi NOTE 1 2-CS"297-E 3 CK 2 , 2-CS"297-H 3 CK 2 SA H/7 0/C 0 SA F/7 0/C 0 2 A C CF-1 2 A C CF1 CF-1 CF-1 P NO 2-CS-299-E 3 CK SA H/7 0 0/C 2 A AC CF-1 SLT-1 CF-3 SLT-1 P YESi NOTE 2 R NOi NOTE ll 2-CS-299-H

.3 CK 4 SA F/7 0 0/C 2 A AC CF-1 SLT"1 CF-3 SLT-1 P YESi NOTE 2 R NOi NOTE 11 2-CS-321 3 CK SA E/3 0 C/0 2 A AC CF-1 SLT-1 CF-2 SLT-2 YESi NOTE 4 R YESi NOTE 3 2-CS"328-Ll 3 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P NOi NOTE 5 2-CS-328-L4 3 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P NOi NOTE 5 2-CS-329-Ll 3 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P'oi NOTE 5 2-CS-329-L4 3 CKi 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P Noi NOTE 5 2-IHO-360 3 GA HO J/6 C 2 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 0

Ill 0 SYSTEH NAME: CVCS-LETDOHN 8 CHARGING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5129-32 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XZ'" NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY)CD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED MODE 2-ZMO-910 3 GA 8 MO L/5 C 2 A B EF-1 EF"5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IMO-911~3 GA 8 MO L/6 C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-QCR-300 3 GL 2 A E/1 0=C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 6 NO C NOp CSJ 6 C NOp CSJ 6 R YESp NOTE 3" 2-QCR-301 3 GL 2 A E/1 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 6 NO C NOp CSJ 6 C NOp CSJ 6 R YESp NOTE 3 2-QMO-200 3 GA 3 MO J/3 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 7 NO C NOp CSJ 7 2-QHO-201 3 GA 3 MO J/3 0 0/C 2 A B EF-1 EF-5 ET-XXX EF"2 EF-5 ET-XXX C NOp CSJ 7 NO C NO, CSJ 7 2-QHO-225 3 GA 2 MO J/7 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 0 ee e e e e e eeo e 0 SYSTEM NAME: CVCS-LETDOHN 8 CHARGING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLOH DIAGRAM: 2-5129-32 RUN DATE AND TIME: 15FEB90:16:10 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SI2E ACT F AD I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-QMO-226 3 GA 2 MO G/7 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2=QRV-200 3 GL 3 A H/3 0 2 A B EF1 EF-5 EF-7-ET-XXX EF-3 EF-5 NOTE 8 NOTE 8 P NO>NOTE 8 YES>NOTE 8 YES~NOTE 8 YES NOTE 8 2-QRV-251 3 GL 3 A N/5 0 2 A B EF1 EF-5 EF"7 ET-XXX EF-3 EF-5 EF-8 NOTE 9 P NO>HOTE 9 YES NOTE 9 YES>NOTE 9 YES>NOTE 9 2-QRV-61 3 GL A C/2 C 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO 2-QRV-62 3 GL 3 A C/2 0/C 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-$EF-7 ET-XXX P NO HO P NO P NO 2-SI-185 3 CK 8 SA K/5 C 2 A C CF-1 CF-2 R YES>NOTE 10 2-SV-51 REL 2 SA E/2 C 2 A C TF-1 TF-1 eoee e0 E (0 e o o e e e o e o o a e o e e 0 0 SYSTEH NAHE: CVCS-LETDOHN 8 CHARGZNG DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL-VALVE SUYNARY SHEET.-UNIT 2 FLON DZAGRAH: 2-5129"32 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ tiVHBER REV TYPE SI2E ACT F~D I POHER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST<S)TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE 2"SV-52 REL 2 SA K/1 C 2 A C TF1 TF-1 R NO 2-SV-55 3 REL 0.75 SA K/7 C 2 A C TF-1 TF-1 2-SV-56 3 REL 0.75 SA L/6 C 2 A C TF1 TF-1 R NO 0 0 0 0 0 0~0 00 0 SYSTEM NAME: CVCS-LETDONH 8 CHARGING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sly 4ARY SHEET-UHIT 2 FLON DIAGRAM: 2-5129A-20 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE 2-QCH-250 3 GA MO C/8 0 2 A A EF-1 EF-5 ET-XXX SLT-1 EF"2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 HO C NOp CSJ 1 R YESp NOTE 2 2-QCM-350 3 GA HO D/8 0 2 A A EF1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 HO C NOp CSJ 1 R YESp NOTE 2 2-QMO-451 3 GA HO J/5 0 2 A B EF1 EF-5 ET"XXX EF-2 EF-5 ET-XXX C HOp CSJ 3 NO C NOp CSJ 3 2-QMO-452 3 GA MO J/5 0 2 A B EF1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C HOp CSJ 3 HO C NOp CSJ 3 2-QRV-400-3 GL 2 A K/4 C 2 A B EF-1 EF-5 EF-7 ET"XXX EF-1 EF-5 EF-7 ET-XXX P NO P NO 2"SV-53 REL 3 SA M/2 C 2 A C TF-1 TF-1 2-SV-54'REL 2 SA E/4 C 2 A C TF-1 TF-1 R NO 0e0 o eo SYSTEH NAHE: COHPONENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5135"34 RUN DATE AND TINE: 15FEB9D:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT TYPE COORDI OPER FUiiCT ICL PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED NODE 2-CCH-451 3 BF 8 HO E/4 0 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-CCH-452 3 BF 8 HO E/5 0 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-CCH-453 3 GL HO E/4 0 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-CCH-454 3 GL HO E/5 0 2 A A EF"1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-CCH-458 3 BF 8 HO A/2 0 2 A A EF-1 EF-5 ET"XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-CCH-459 3 BF 8 HO B/2 0 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 0

SYSTEM NAME: COMPONENT COOLIHG DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UHIT 2 FLOH DIAGRAM: 2-5135-34 RUH DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUYBER REV TYPE SIZE ACT F-D~I POHER SAFETY ICD A/P CAT TYPE COORD I OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-CCRW55 3 GL'A B/3 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 3 NO C HOp CSJ 3 C NOp CSJ 3 R'ES NOTE 2 2-CCR-456 3 GL 2 A D/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-2 EF-5 EF-8 ET-XXX SLT-2 C HOp CSJ 3 NO C NOp CSJ 3 C HOp CSJ 3 R YESp NOTE 2 2-CCR-457 3 GL 2 A D/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF"2 EF-5 EF-8 ET-XXX SLT-2 C NOp CSJ 3 NO C NOp CSJ 3 C HOp CSJ 3 R YESp NOTE 2 2-CCR-460 3 GL 3 A C/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P HO P NO R YESp NOTE 2 2-CCR-462 3 GL 3 A A/4 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 2 0 e o e o e o e e e o e e e e e 0 0 SYSTEM NAME: COMPOHENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 F LOH DIAGRAM: 2-5135-34 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUiiBER REV TYPE SIZE ACT F.D~I PONER SAFETY ICD A/P CAT PRIM TEST TEST.TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUHCT ICL REQUIRED PERFORMED MODE 2-CCH-135 3 CK 2.5 SA B/3 0 2 A AC CF-1 SLT-1 CF-2 SLT"2 R YES)NOTE 4 R YESp NOTE 2 2-CRV-445 3 BL 6 A L/5 0 C/0 3 A B EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-XXX ET-XXX P NO NO P NO P NO 2-CRV-470 3 GL 6 A G/1 0 3 A B EF1 E F-5 EF-7 ET"XXX EF-1 NOTE 5 HOTE 5 NOTE 5 ii P NO>NOTE 5 YES>NOTE 5 YES'OTE 5 YESp NOTE 5 2-CRVW85 3 BF 10 A B/7 0 A B EF1 EF-1 EF"5 EF-5 EF-7 EF-7 ET-XXX ET-XXX P NO HO P NO P HO 2-SV-122 3 REL 1 SA D/3 C , 0 3 A C TF1 TF-1'-SV-62-1 3 REL 1 SA D/3 C 2-SV-62-2 3 REL 1 SA D/3 C A C TF 1 A C TF-1 TF-1 TF-1 R HO 2-SV-62-3 3 REL 1 SA D/3 C 3 A C TF-1 TF>>l R HO 2-SV-62<3 REL 1 SA D/3 C A C TF1 TF-1 R HO 000 00 0 SYSTEM NAME: COMPONENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5135-34 RUN DATE AND TIME: 15FE890:16:14 VALVE VALVE POSITION ASME SECTION XZ W NUMBER REV TYPE SIZE ACT F~D I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-SV-63 REL 1 SA E/3 C A C TF-1 TF-1 R NO 2-SV-64 REL 1 SA C/3 C 3 A C TF-1 TF-1 R NO 2-SV-65 3 REL 1 SA K/I C 3 A C TF-1 TF-1 2-SV-68 3 REL 1 SA J/2 C A C TF1 TF-1 2-SV-71 3'EL 1 SA L/3 C 3 A C TF-1 TF-1 R NO e 0 00 00 0 000 0

" SYSTEM NAHE: COMPONENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHMARY SHEET-UNIT 2 FLON DIAGRAM: 2-5135A-30 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED'ERFORMED MODE 2-CCH-176-E 3 CK 16 SA L/4 C/0 0 3 A C CF1 CF-1 2-CCN-176-N 3 CK 16 SA K/4 C/0 0 A C CF1 CF-1 2-CHO-410 3 BF 16 HO M/4 C/0 0 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-CHO-411 3 BF 18 HO H/5 0 3 A B EF-1 EF-5 ET-XXX EF-1 E F-5 ET-XXX P NO NO P NO>NOTE 1 2 CHO 412 3 BF 16 HO L/3 0 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO>NOTE 1 2-CHOW13 3 BF 18 HO L/5 0 3 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P P NO NO NOp NOTE 1 2-CHO&14 3 BF 16 HO K/3 0 3 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO>NOTE 1 2-CHO-415 3 BF 16 HO M/5 0 3 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET"XXX P NO NO P NOi NOTE 1

SYSTEM NAME: COHPONENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5135A-30 RUN DATE AND TINE: 15FEB90:16:14 VALVE t VALVE POSITION I ASHE SECTION XI HUiiBER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE'2-CHO-416 3 BF 16 HO G/5 0 3 A 8 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO>NOTE 1 2-CHO-419 3 BF 14 HO E/5 C 3 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-CHO-420 3 BF 16 HO H/4 C/0 0 3 A 8 EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-CMO-429 3 BF 14 HO E/5 C 0 3 A 8 EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO P NO 2-CRV-412 3 GL A K/1 0 A 8 EF-1 EF-5 EF"7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-SV-60 3 REL 3 SA L/1 C 3 A C TF"1 TF-1 R NO 2-SV-72 REL 1 SA E/5 C 3 A C TF-1 TF-1 0 o e e e e e e e e o e e e e a

eoe e eee e 0*I II0 0 o e e o e e o o e e e o o e e ill~~SYSTEM NAME: COMPONENT COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5135B-14 RUN DATE AND TIME: 15FEB9Dp16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SI2E ACT F.D.I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-CCH-243"25 3 CK 1 SA C/5 0 2 A AC CF-1 CF-2 SLT-1.SLT-2 R YESp NOTE 2 R YESp NOTE 1 2-CCH-Kt3-72 3 CK 1 SA C/5 0 2 A AC CF-1 CF-2 SLT-1 SLT-2 R YESp NOTE 2 R YESp NOTE 1 2-CCH-ZVt-25 3 CK 1 SA C/6 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES)NOTE 2 R YESp NOTE 1 2-CCH-WA-72 3 CK 1 SA C/6 0 2 A AC CF 1 SLT"1 CF-2 SLT-2 R YESp NOTE 2 R YESp NOTE 1 2-SV-122-25B 3 RE L 1.5 SA B/6 C 3 A C TF-1 TF-1 R NO 2-SV-122-72B 3 REL 1.5 SA B/6 C 0 3 A C TF-1 TF-1 R NO eee e0000000 SYSTEM NAME: NUCLEAR SAMPLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5141-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI ,NUHBER REV TYPE SIZE ACT F D.I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-ZCR-5 3 GL 0.5 A C/5 0 C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES NOTE 1 2-ICR-6 3 GL 0.5 A.D/5 0 C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-NCR-105 3 GL 0.5 A C/7 0 C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-NCR"106 GL 0.5 A C/7 0 C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES'OTE 1 2-NCR"107 3 GL 0.5 A D/6 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YESp NOTE 1

I I ISYSTEM NAME: NUCLEAR SAMPLING DONALD CD COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-5101-27 RUN DATE AHD TIME: 15FEB90:16:10 VALVE I VALVE POSITION I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F AD.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-NCR"108 3 GL 0.5 A D/6 0 2 A A EF1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES'OTE 1 2-NCR-109 3 GL 0.5 A D/5 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF-7 ET-XXX SLT-2 HO P HO P HO R YES>NOTE 1 2-HCR-110 3 GL 0.5 A D/6 0 2 A A EF1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT"2 P HO P HO R YES>NOTE 1 0 0 00 0 000 00 SYSTEM NAME: NUCLEAR SAMPLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLOH DIAGRAM: 2-5141A-30 RUN DATE AND TIME: 15FE890:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT lCL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED MODE 2-DCR-301 3 GL'.5 A 8/2 0 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF"1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-DCR-302 3 GL 0.5 A 8/3 0 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2"DCR-303 3 GL 0.5 A 8/3 0 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX NO NO P NO P NO2-DCR"304 3 GL 0.5 A 8/3 0 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-MCR-251 3 GL 0.5 A 8/2 0 2 A 8 EF-1 EF-5 EF"7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 2-HCR"252 GL 0.5 A 8/2 0 2 A 8 EF-1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO 0 e e e 0 e e e e e e e o o e e0 ea e e o o o o o e e o e e 0 SYSTEM NAME: NUCLEAR SAMPLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2"5141A-30 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.t PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-HCR-253 3 GL 0.5 A B/1 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 P NO EF-5 NO EF-7-P NO ET-XXX P NO2-MCR-254 3 GL 0.5 A 8/1 0 2 A 8 EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO NO P NO P NO e e e 0<<a e oe o e e e e0o~e o o o e~~~e~~o o e~

SYSTEM NAME: PAS CONTAINMENT HYDROGEN DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUKULRY SHEET-UNIT 2 FLOH DIAGRAM: 2-51410-8 RUH DATE AHD TIME: 15FE890:16:10 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORD I OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST[S)REQUIRED PERFORMED MODE 2"ECR"10 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF"5 EF-7 ET-XXX SLT-2 P NO NO P HO P-NO R YES>NOTE)2-ECR-ll 3 GL 0.5 A A/2: C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 HO P NO P NO R YESp NOTE 1 2-ECR"12 3 GL 0.5 A A/2 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO P HO R YES>NOTE 1 2-ECR-13 GL 0.5 A A/1 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2"ECR-10 3 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P HO R YES>NOTE 1

, e a0e ee e0

-SYSTEM NAME: PAS CONTAINMENT HYDROGEN DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUSRY SHEET-UNIT 2 FLON DZAGRAH: 2-5141D-8 RUN DATE AND TZHE: 15FEB90:16:14 VALVE VALVE POSITION ASME SECTION XI NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY I CD A/P CAT TYPE COORD I OPER FUNCT ICL PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED MODE 2-ECR-15 3 GL 0 5 A A/1 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES'OTE 1 2-ECR-16 3 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-ECR-17 3 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF-5 EF"1 EF-5 P NO NO EF-7 ET"XXX SLT-1 EF-7 ET-XXX SLT-2 P P R NO NO YES>NOTE 1 2"ECR"18 GL 0 5 A A/4 C 0/C 2 A A EF"1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 12-ECR-19 3 GL 0.5 A A/4 C 0/C 2 A A EF-1 EF-5 EF-7 ET"XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 00000 0 SYSTEM NAME: PAS CONTAINMENT HYDROGEN DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-51010-8 VALVE I VALVE POSITION I ASME SECTION XI NUTTER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE'2-ECR-20 3 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>, NOTE 1 2-ECR-21 GL 0.5 A B/2 C 0/C 2 A A EF-1 E F-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET"XXX SLT"2 P NO NO P NO P NO R YES'OTE 1 2-ECR-22 3 GL 0.5-A B/2 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-ECR"23 3 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 P NO NO P NO ET-XXX SLT-1 ET-XXX SLT-2 P NO R YESp NOTE 1 2"ECR-Vt 3 GL 0.5 A B/3 C 0/C 2 A A EF-1 EF"1 EF-5 EF-5 EF-7, EF-7 ET-XXX ET-XXX SLT-2 SLT-1 P NO NO P NO NO R YES>NOTE 1 0 oe oe e e ee e e e e 0 SYSTEH NANE: PAS CONTAINMENT HYDROGEN DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET-UNIT 2 FLOH DIAGRAN: 2"5141D-8 VALVE I VALVE POSITION I ASNE SECTION XI HUNBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORNED NODE 2-ECR-25 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P HO R YES'OTE 1 2-ECR-26 3 GL 0.5 A B/3 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 E F-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES'OTE 12-ECR-27 3 GL 0.5 A B/3 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET"XXX SLT-2 P NO P NO R YES>NOTE 1 g*2-ECR-28 GL 0.5 A B/4 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF"5 EF-7 ET-XXX SLT"2 P NO NO P'O P NO R YES'OTE 1 2-ECR-29 3 GL 0.5 A B/4 C 0/C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES)NOTE 1 0 o e e 0 e e e o e e e e e e e 0 00 0 000 0 0 SYSTEH NAME: PAS CONTAIt&ENT HYDROGEN DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SLRKARY SHEET-UNIT 2 FLON DIAGRAM: 2-51%ID-8 RUN DATE AND TIME: 15FEB90:16.14 VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE 2-NS-283 3 CK 0.5 SA C/8 C 0/C 2 A AC CF1 SLT-1 CF-2 SLT-2 R YES>NOTE 2 R YESp NOTE 1 H 4 0e e e o e0 eo a e 0 SYSTEH NAME: EMERGENCY CORE COOLING-SIS DONALD C COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-IPiGT 2 FLON DIAGRAM: 2-5142-28 Rll4 DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XZ%NBER REV TYPE SIZE ACT F AD.I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUiiCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED MODE 2-ICM-250 3 GA HO H/2 C 0/C 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-ICH-251 3 GA 4'O H/3 C 0/C 2 A A EF-1 EF-5 ET-XXX SLT-,1 EF-2 EF-5 ET-XXX SLT-2 C NOp CSJ 1 NO C NOp CSJ 1 R YESp NOTE 2 2-ZCM-260 3 GA MO C/9 0 0/C 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-1 EF-5 ET-XXX SLT-2 P P R NO NO NO YESp NOTE 2 2-ICH-265 3 GA 4 MO C/8 0 0/C 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-1 EF-5 ET-XXX SLT"2 P NO NO P NO R YESp NOTE 2 2-IHO" 255 3 GA 4 HO J/7 C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IHO-256 3 GA 4 HO J/6 C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IHO-261 3 GA 8 HO H/8 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NOp CSJ 3 NO C NOp CSJ 3 0 o o e e e o o e o o e e e e e 0 SYSTEH NAHE: EHERGEHCY CORE COOLING-SIS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLOW DIAGRAH: 2-5142-28 RUH DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI HUHBER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE 2-IHO-262 3 GL 2 HO L/8 0 0/C 2 A B EF-1 EF-5 ET-XXX EF"2 EF-5 ET-XXX C NO>CSJ 4 NO C NOp CSJ 42-IHO-263 3 GL 2 HO L/8 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C HOp CSJ 4 NO C NO>CSJ 4 2-IHO-270 3 GA HO E/9 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P HO HO P HO 2-IHO-275 3 GA HO E/8 0 0/C 2 A B EF-1 EF-5 ET"XXX EF-1 EF-5 ET-XXX P NO HO P NO 2-IHO-361 3 GA HO G/9 C C/0 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2"IHO-362 3 GA HO G/9 C C/0'A B EF-1/EF-5 ET-XXX EF-1 EF-5 ET-XXX P HO HO P NO 2-IRV-251 3 GL 1 A H/5 0 2 A B EF1 EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P HO NO P HO P NO 0

SYSTEM NAME: EMERGENCY CORE COOLING-SIS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOH DIAGRAM: 2-514'2-28 RUH DATE AND TIME t 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SI2E ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-IRV-252 3 GL 1 A J/5 0 3 A B EF)EF-5 EF-7 ET-XXX EF-1 EF-5 EF-7 ET-XXX P NO HO P NO P NO 2-IRV-255 3 GL 1 A H/6 0 2 A B EF1 EF-1 EF-5 EF-5 P NO NO EF-7 ET"XXX EF-7 ET-XXX P HO P HO 2-SI-101 CK 8 SA M/8 C 2 A C CF-)CF-3 R YES>NOTE 5 2-Sl-104-N 3 CK 0.75 SA E/9 C 2 A C CF-1 CF-1 2-SI-104-S 3 CK 0.75 SA J/9 C 2 A C CF1 CF-1 2"SI-110-N 3 CK SA E/9 C 2 A C CF1 CF-2 R YES>NOTE 5 2-SI-))O-S 3 CK SA H/9 C 2 A C CF)CF-2 R YES'OTE 5 2-SI-126 3 CK 1 SA H/6 0 2 A C CF)CF-1 2"SI-142-Ll 3 CK 1.5 SA C/)C 1 A C CF1 CF-2 R YES>NOTE 6 2-SI-142-L2 3 CK 1.5 SA C/2 C 1 A C CF1 CF-2 R YES>NOTE 6 0 000 III 0 SYSTEM NAME: EMERGENCY CORE COOLING-SIS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SKEET-UNIT 2 FLON DIAGRAM: 2-5142-28 RUN DATE AND TIME: 15FEB90:16t14 VALVE I VALVE POSITION I ASME SECTION XI HOYBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED HODE 2-SZ-142-L3 3-CK 1.5 SA C/2 C 1 A C CF-1 CF-2 R YES)NOTE 6 2-SI-142-L4 3 CK 1.5 SA C/1 C 1'A C CF1 CF-2 R YES'OTE 6 2-SV-96 REL 0.75 SA J/8 C A C TF-1 TF-1 2-SV"97 3 REL 0.75 SA J/4 C 2 A C TF-1 TF-1, R NO 2-SV-98-N 3 REL 0.75 SA C/9 C 2 A C TF"1 TF-1 R NO 2-SV-98-S 3 REL 0.75 SA E/8 C 2 A C TF1 TF-1

SYSTEH NAME: EMERGENCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET" UNIT 2 FLON DIAGRAM: 2-5143-35 RUN DATE AND TIME: 15FEB90:16:14

~~VALVE I VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F.D~I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUESTERS)

REQUIRED PERFORMED MODE 2-GCR-314 3 GL 1 A G/2 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF"5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES'OTE 14 2-ZCH-1'29 3 GA 14 HO E/8 C 1 P A EF-1 EF-5 ET-XXX SLT-1 EF-2 EF-5 ET-XXX SLT-1 C NO>CSJ 2 NO C NOp CSJ 2 R NO, NOTE 1 2-ICH-305 3 GA 18 HO D/9 C 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-1 EF-5 ET-XXX SLT-2 P NO NO P NO R YES NOTE 14 2-ZCH-306 3 GA 18 HO 0/9 C 2 A A EF-1 EF-5 ET-XXX SLT-1 EF-1 EF-5 ET-XXX SLT-2 P NO NO P NO R YESp NOTE 14 2-ZHO-128 3 GA 14 HO B/8 C 1 P B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NO>CSJ 2 NO C NO>CSJ 2 2-IMO-310 3 GA 14 HO H/9 0 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO>NOTE 3 a eeee e e0 o e o o e e e e e e e e e o e IIISYSTEM NAME: EMERGENCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMHARY SHEET-UNIT 2 FLON DIAGRAM: 2-5143-35 RUN DATE AND TIHE: 15FEB90:16:14 VALVE l VALVE POSITION I ASHE SECTION XI NUMBER REV TYPE SIZE ACT F-D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORHED HODE 2-IHO-312 3 GL 2 HO J/5 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF"5 ET"XXX P NO NO P NO 2-IMO-314 3 GA 8 HO K/6 0 2 A B EF-1 EF-5 ET-XXX EF-1 EF"5 ET-XXX P NO NO P NO>NOTE 3 2-IHO-315 3 GA 8 HO C/7 C C/0 1 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NO>CSJ 4 NO C NOp CSJ 4 2-IMO-316 3 GA 8 HO C/7 0 0/C 2 A B EF-1 EF-5 ET-XXX EF"2 EF-5 ET-XXX C NO>CSJ 4 NO C NO>CSJ 4 2-I HO-320 3 GA 14 MO L/9 0 2 A B EF-1 EF-5 ET-XXX EF"1 EF-5 ET"XXX P NO NO P NOp NOTE 3 2-IHO"322 3 GL 2 HO H/5 0 0/C 2 A B EF"1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IHO"324 3 GA 8 MO H/6 0 2 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET"XXX P NO NO P NOp NOTE 3 0 0 0 0 0 0 0 0 00 0 0 000 SYSTEM NAME: EHERGENCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UiNIT 2 FLON DIAGRAM: 2-5143-35 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NVK3ER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE-2-IHO-325 3 GA 8 HO C/7 C C/0 1 A B EF-1 EF-5 ET-XXX EF"2 EF"5 ET"XXX C NO>CSJ 4 NO C NO>CSJ 4 2-ZHO-326 x', 3 GA 8 HO C/7 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C NO>CSJ 4 NO C NO>CSJ 4 2-IHO-330 3 GA 8 HO G/4 C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IHO-331 3 GA 8 HO L/5 C 2 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX 2-I HO-340 3 GA 8 HO H/5 C 2 A B EF1 EF"5 ET-XXX EF-2 EF-5 ET-XXX C YES>NOTE 15 NO C YES>NOTE 15 2-IHO-350 3 GA 8 MO L/5 C 2 A B EF1 EF-5 ET-XXX EF-2 EF-5 ET-XXX C YES>NOTE 15 NO C YESp NOTE 15 2-N-102 3 CK 1 SA F/5 0/C C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 13 R YES>NOTE 14 2-RH-108E 3 CK 8 SA K/9 C 2 A C CF-1 CF-3 C NOp CSJ 7 r 0 o e e o e e e e e e e'o e0 SYSTEM NAME: EMERGEHCY CORE COOLING;RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET" UNIT 2 FLOH DIAGRAM: 2-5143-35 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUHCT ICL REQUIRED PERFORMED MODE 2-RM-108M 3 CK 8 SA N/9 C 2 A C CF1 CF-3 C NOp CSJ 7 2-RH-133 3 CK 8 SA C/5 C 1 P AC SLT-1 SLT-1 R NO>>NOTE 1 2-RH-134 3 CK 8 SA C/5 C 1 P AC SLT-1 SLT-1 R NOp NOTE 1 2-SI-148 CK 12 SA G/7 C 2 A C CF1 CF-3 YESp NOTE 8 2-SI-151-E 3 CK 8 SA D/7 C 2 A AC CF-1 SLT-1 CF-2 SLT-1 C NOp CSJ 9 R HOp NOTE 1 2-SI-151"H 3 CK 8SA 0/7 C A AC CF-1 SLT-1 CF-2 SLT-1 C NOp CSJ 9 R NOp NOTE 1 2-SZ-152-N 3 CK'SA D/8 C 2 A AC CF-1 SLT"1 CF-2 SLT-1 R YESp NOTE 10 R NOp NOTE 1 2-SI-152-S 3 CK 4 SA D/7 C 2 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 10 R HOp NOTE 1 2-SI-158-Ll 3 CK 6 SA B/8 C 1 A AC CF-1 SLT-1 CF-2 SLT"1 YESp NOTE ll R HOp NOTE 1 2-SI-158-L2 3 CK 6 SA B/7 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 YESp NOTE ll R NOp HOTE 1

SYSTEH NAHE: EHERGEKCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SmARY SHEET-UNIT 2 FLON DZAGRAH: 2-5143-35 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NASSER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-SI-158-L3 3 CK 6 SA B/7 C 1 A AC CF-1 SLT"1 CF-2 SLT-1 YESp NOTE ll R NOp NOTE 1 2-SI-158-L4 3 CK 6 SA B/7 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 YESp NOTE ll R NOp NOTE 1 2-SI-161-Ll 3 CK 6 SA B/6 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 YESp NOTE 6 R NOp NOTE 1 2-SZ-161-L2 3 CK 6 SA B/5 C 1 A AC CF1 SLT-1 CF-2 SLT-1 YESp NOTE 6 R NOp NOTE 1 2-SI-161-L3 3 CK 6 SA B/5 C 1 A AC CF 1 SLT-1 CF-2 SLT-1 YESp NOTE 6 R NOp NOTE 1 2"SI-161-L4 3 CK 6 SA B/6 C 1 A AC CF-1 SLT-1 CF-2 SLT"1 YESp NOTE 6 R NOp NOTE 1 2-SZ-166-1 3 CK 10 SA C/4 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 5 R NOp NOTE 1 2-SI-)66-2 3 CK 10 SA C/4 C 1 A AC CF 1 SLT"1 CF-2 SLT"1 R YESp NOTE 5 R NOp NOTE 1 2-SI-166-3 3 CK 10 SA C/4 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 5 R NOp NOTE 1 0 e e e o e e e e e e e e e e e 0 SYSTEH NAHE: EHERGENCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUSRY SHEET-UNIT 2 FLON DIAGRAH: 2-5143-35 RUN DATE AND TZHE: 15FEB90:16:14 VALVE VALVE POSITION ASHE SECTION XZ NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDl OPER FUNCT ICL REQUIRED PERFORHED HODE 2-SZ-166M 3 CK 10 SA C/4 C 1 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 5 R NOp NOTE 1 2-SZ-170-Ll 3 CK 10 SA A/4 C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R YESp NOTE 12 R NOp NOTE 1 2-SZ-170-L2 3 CK 10 SA A/5 C 0/C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R YESp NOTE 12 R NOp NOTE 1 2-SI-170-L3 3 CK 10 SA A/5 C 0/C 1 A AC CF-1'LT-1 CF-3 SLT-1 R YESp NOTE 12 R NOp NOTE 1 2-SZ-170-L4 3 CK 10 SA A/4 C.1 A AC CF-1 SLT-1 CF-3 SLT-1 R YESp NOTE 12 R NOp NOTE 1 2-SI-171 3 GL 0.75 H H/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14 2-SI-172 3 GL 0.75 H H/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14 2-SI-194 3 GL 0.75 H G/6 C 2 P A SLT-1 SLT-2 R YESp NOTE 14 2-SV-100-1 3 REL 1 SA D/1 C 2 A C TF"1 TF-1 2-SV-100"2 3, REL 1 SA D/1 C 2 A C TF-1 TF-1

tll 0 SYSTEH NAHE: EHERGENCY CORE COOLING-RHR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5143-35 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ HRBER REV TYPE SI2E ACT F D I PONER SAFETY tCD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE 2-SV-100-3 3 Rf L 1 SA D/1 C 2 A C TF-1 TF-1 R NO 2-SV-100"4 3 REL 1 SA 0/1 C 2 A C TF1 TF-1 R NO2-SV-102 3 REL 0.75 SA E/5 C 2 A C TF-1 TF-1 2-SV-103 3 REL 3 SA F/8 C 2 A C TF-1 TF-1 2-SV-104E 3 RE L 2 SA G/4 C 2 A C TF1 TF-1 R NO 2-SV-104N 3 REL 2 SA K/4 C 2 A C TF1 TF-1 R NO 2-SV-105E 3 REL 2 SA D/9 C 2 A C TF-1 TF-1 R NO 2-SV-105N 3 REL 2 SA D/9 C 2 A C TF-1 TF-1 R NO 00 00 0 0 0 0 0.0 00 SYSTEH NAHE: CONTAINHENT SPRAY DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUii'SARY SHEET UNIT 2 FLOW DIAGRAH: 2-5144-29 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUHBER REV TYPE SI2E ACT F.D.I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-CTS-103-E 3 CK 10 SA J/9 C 2 A C CF1 CF-3 YESp NOTE 2 2-CTS-103-W 3 CK 10 SA L/9 C 2 A C CF1 CF-3 YESp NOTE 2 2-CTS-109 3 VB 1 SA H/6 C 2 A C CF-1 CF-2 C NOp CSJ 6 2-CTS-110 3 VB 1-SA H/6 C 2 A C CF1 CF-2 C NOp CSJ 6 2-CTS-120-E 3 CK 2 SA H/8 C 2 A C CF1 CF-1 2-CTS-120-W 3 CK 2 SA K/8 C 2 A C CF-1 CF-1 2"CTS" 127-E 3 CK'SA E/5 C 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YESp NOTE 4 R YESi NOTE 7 2"CTS"127-W 3 CK 6 SA E/4 C 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YESp NOTE 4 R YES1 NOTE 7 2-CTS-131-E 3 CK 8 SA E/2 C 2 A AC CF"1 SLT-1 CF-2 SLT-2A R YESp NOTE 3 R YESp NOTE 7 2-CTS-131-W 3 CK 8 SA E/2 C 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YESp NOTE 3 R YESp NOTE 7 2-CTS-138-E 3 CK 12 SA G/9 C 0/C 2 A C CF-1 CF-3 YESp NOTE 1

~~o e e e e e e e o e e o e e~

SYSTEH NAHE: CONTAINMENT SPRAY t DONALD C~COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMHARY SHEET-UNIT 2 FLON DIAGRAM: 2-51&1-29 RUN DATE AND TIME: 15FEB90:16:10 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-CTS-138-N 3 CK 12 SA J/9 C 0/C 2 A C CF-1 CF-3 YES)NOTE 1 2-IHO-202 3 GA 2.5 MO H/7 C 2 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-ZHO-204 3 GA 2.5 MO H/7 C 2 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2"ZHO-210 3 GA 10 HO J/8 C 2 A B EF1 EF-5 ET-XXX EF"1 EF-5 ET-XXX P NO NO P NO 2-ZHO-211 3 GA 10 MO J/8 C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET"XXX P.NO NO P NO 2-ZHO-212 3 GA 2 HO H/8 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P.NO 2-ZMiO-215 3 GA 12 HO G/9 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-ZHO"220 3 GA 10 HO L/8 C 2 A B EF1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 4 0 0 e e o o e e o o e o o e e e e SYSTEM NAME: CONTAIHMENT SPRAY DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 F LON DIAGRAM: 2-5144-29 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION ASME SECTION XZ NUMBER REV TYPE SI2E ACT F.D.I POMER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUESTERS)

TYPE COORDI OPER FUNCT ICL RMUIRED PERFORMED MODE 2-ZMO" 221 3 GA 10 MO L/8 C 2 A B EF-1 EF"5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-IMO-222 3 GA 2 MO L/9 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P HO 2-IMO-225 3 GA 12 MO J/9 0 0/C 2 A B EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P NO NO P NO 2-RH-141 3 CK 8 SA E/3 C 2 A AC CF 1 SLT-1 CF-2 SLT-2A R YES>NOTE 5 R YESp NOTE 7 2-RM-142 CK 8 SA E/3 C 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YES>NOTE 5 R YES>NOTE 7 2-SV-107 REL 1 SA H/5 C 2 A C TF-1 TF-1 R HO

SYSTEH NAHE: CPN/HELD CHAFCIEL PRESSURI2ATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5145-20 RUN DATE AND TZHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SZ2E ACT F.D.l POHER SAFETY ICD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-CA"181-N 3 CK 0.5 SA F/2 C 2 P AC SLT-1 SLT-2 R YES>NOTE 1 2-CA-181-S 3 CK 0.5 SA F/3 C 2 P AC SLT-1 SLT-2 R YES>NOTE 1 e oee0e IIISYSTEM NAME: ICE CONDENSER REFRIGERATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOW DIAGRAM: 2-5166B-23 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F~D~I POWER SAFETY I CD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2"R"156 3 CK 0.375 SA L/0 C 0/C 2 A AC CF"1 SLT-1 CF-2 SLT-2 R YES'OTE 1 R YES'OTE 2 2-R-157 CK 0.375 SA L/6 C 0/C 2 A AC CF-1 SLT-1 CF"2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2-VCR-10 DA A M/5 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 2 2-VCR-ll 3 DA A L/5 0 2 A A EF-1 EF"5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 HO P NO P HO R YES>NOTE 2 2-VCR-20 3 DA cj A M/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO HO P NO P HO R YES'OTE 2 2-VCR"21 3 DA A L/7 0 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO NO P HO P NO R YES'OTE 2 o e e e o o e o o e e o o o e 0 SYSTEM NAME: CONTAINMENT VENTILATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHMARY SHEET-UNIT 2 FLOH DIAGRAM: 2-5147A-35 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION ASME SECTION XI NOSER REV TYPE SIZE ACT F.DE I POMER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT ICL PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-SH-10 3 GA 0.5 H A/4 C 2 P A SLT-1 SLT-2 R YES>NOTE 1 2-SH-4 3 GA 0.5 H A/2 C C 2 P A SLT-1 SLT-2 R YES>NOTE 1 2-SH-6 3 GA 0.5 H A/2 C 2 P A SLT"1 SLT-2 R YES>NOTE 1 2"SH"8 3 GA 0.5 H A/4 C 2 P A SLT-1 SLT-2 R YES>NOTE 1 2-VCR-101 3 BF 14 A J/8 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT"2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-102 3 BF 14 A J/9 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES>NOTE 1 2-VCR-103 3 BF 24 A J/5 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT"2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-104 3 BF 30 A J/6 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT"2 P NO NO P NO P NO R YES>NOTE 1 0 0 e e e o e e e e e e o e e e e 0 SYSTEH HAHE: CONTAINHENT VENTILATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VAlVE SUHHARY SHEET-UNIT 2 FLON DIAGRAH: 2-5147A-35 RUN DATE AND TINE: 15FE890:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NUHBER REV TYPE SIZE ACT F~DE I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT lCL PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED NODE 2-VCR-105 3 BF 30 A J/3 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO HO P NO P NO R YES7 NOTE 1 2-VCR-106 3 BF 24 A J/3 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 NO P NO P NO R YES>NOTE 1 2-VCR" 107 3 BF 14 A J/4 0/C C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT"1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES1 NOTE 1 2-VCR-201 3 BF 14 A J/8 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P HO NO P NO P HO R YES>NOTE 1 2-VCR-202 3 BF 14 A J/9 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P HO P NO R YES'OTE 1

SYSTEM NAHE: CONTAINMENT VENTILATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMHARY SHEET-UNIT 2 FLON DIAGRAM: 2-5147A-35 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUMBER REV TYPE SIZE ACT F~D~I PONER SAFETY I CD A/P CAT TYPE COORD I OPER FUNCT ICL PRIM TEST TEST TEST RELIEF RE@JEST(S)

REQUIRED PERFORMED MODE 2-VCR-203 3 BF 24 A J/5 C 2 P A 4, EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-204 3 BF 30 A J/6 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF<<l EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-205 3 BF 30 A J/3 C 2 P A EF-1 EF-5 EF"7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-206 3 BF 24 A J/3 C 2 P A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P NO P NO R YES>NOTE 1 2-VCR-207 3 BF 14 A J/4 0/C C 2 A A EF-1 EF-5 EF-7 ET-XXX SLT-1 EF-1 EF-5 EF-7 ET-XXX SLT-2 P NO NO P N)P NO R YES NOTE 1 o e0e-oe N 0 , 0 0 0 00 0 0 0 000 IIISYSTEH NAHE: CONTROL ROOH VENTILATION DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2 FLOW DZAGRAH: 2-5149-23 RUN DATE AND TINE: 15FEB90:16:10 VALVE VALVE POSITION ASHE SECTION XZ NUHBER REV TYPE SI2E ACT F AD I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-DW-163-N 3 GA 2.5 H F/2 0 0/C 3 A B EF-1 EF-1 2-DW-163-S 3 GA 2.5 H G/2 0 0/C 3 A B EF-1 EF-1 P NO 2-DW"166-N 3 GA 2.5 H E/5 0 0/C 3 A B EF-1 EF-1 P NO 2-DW"166-S 3 GA 2.5 H J/5 0 0/C 3 A B EF-1 EF-1 P NO 2-VRV-315 3 3W 2.5 A F/5 0 3 A B EF-1 EF-7 ET-XXX NOTE 1 EF"7 NOTE 1 P YES>NOTE 1 P NOp NOTE 1 YES>NOTE 1 2-VRV-325 3 3W 2.5 A G/5 0 A B EF1 EF-7 ET-XXX NOTE 1 EF-7 NOTE 1 P YESp NOTE 1 P NOi NOTE 1 YES NOTE 1 o e o e e e e e e e e o e e e SYSTEM NAME: EMERGENCY DIESEL GENERATOR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5151A-26 RUN DATE AND TIHE: I5FEB90:16:14 VALVE I VALVE POSITION I ASME SECTION XI NUHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-DF-108A 3 CK 1.5 SA L/3 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-DF-109A 3 CK 1.5 SA K/3 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-D F-114A 3 CK 1.5 SA J/3 C 3 A C CF-1 CF"1 P" NOR NOTE 12-DF-115A 3 CK 1.5 SA H/3 C 3 A C CF-1 CF-1 P NOiNOTE 1 2-DL-114A 3 CK 1.5SA B/9 0 3 A C CF-1 CF-1 P NO>NOTE 1 2-DL-116A 3 CK 1.5 SA B/9 C 3 A C CF1 CF-1 P NOp NOTE 1 2-DL-126A 3 CK 2.5 SA E/9 0 3 A C CF1 CF-1 P NO>NOTE 1 2"DL-132A 3 CK 1 SA F/9 0 3 A C-CF 1 CF-1 P NOp NOTE 1 2-D L-158A 3 CK 6 SA G/6 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-QT-114-2AB 3 3H 6 SA H/5 0 3 A B EF1 NOTE 2 P NOp NOTE 2

0 SYSTEH NAHE: EHERGENCY DIESEL GENERATOR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET" UNIT 2 FLOH DZAGRAH: 2-51518-27 RUN DATE AND TZHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED HODE 2-DG-102A 3 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NOi NOTE 1 2-DG-104A 3 CK 1.5 SA G/4 0 0/C 3 A C CF-1 CF-1 P NOp NOTE 1 2-DG-128A 3 CK 1 SA C/4 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-DG-130A 3 CK 1 SA C/4 C 3 A C CF1 CF-1 P NO>NOTE 1 2-DG-140A CK 0.5 SA a F/1 C f 0/C 3 A C CF-1 CF-1 2-DG-142A 3 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1/2-DG-146A 3 CK 2 SA A/8 0 3 A C CF1 CF-1 P NO>NOTE 1 2-DG-152A 3 CK 4 SA D/8 C 3 A C CF1 CF-1 P NO>NOTE 1 2-DG-154A 3 CK SA C/8 C A C CF-1 CF-1 P NO>NOTE 1 2-QT-132-2AB 3 3N 6 SA E/8 0 3 A B EF-1 NOTE 2 P NOp NOTE 2 J 2-SV-120-AB 3 REL 0.25 SA G/2 C 3 A C 7 F1 TF-1 2-SV-139-AB 3 REL 1 SA B/2 C 3 A C TF1 TF-1 0

0 SYSTEH NAHE: EHERGENCY DIESEL GENERATOR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET-UNIT 2 FLOH DIAGRAH: 2-5151B-27 RUN DATE AND TINE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUHBER'EV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORHED NODE 2-SV-61-AB 3 REL 1 SA A/8 C 3 A C TF-1 TF-1 2-SV-78-AB1 3 REL 1 SA E/3 C 3 A C TF-1 TF-1 2-SV-78-AB2 3 REL 1 SA D/3 C 3 A C TF-1 TF-1 2-SV-79-ABl 3 REL 0.5 SA E/1 C 3 A C TF-1 TF-1 R NO 2-SV-79-AB2 3 RE L 0.5 SA E/1 C 3 A C TF-1 TF-1 2-XRV-220 3 GA 1 A B/3 C EF-7 ET-XXX EF-7 NOTE 4 3 A B EF1 EF-1 YES>NOTE 4 YES'OTE 4 YES>NOTE 4 2"XRV-221 3 GL 3 A B/4 C 3 A B EF-1 EF-7 ET-XXX EF-1 NOTE 3 NOTE 3 YESp NOTE 3 YES>NOTE 3 YES>NOTE 3 2"XRV-222 3 GL A B/4 C 3 A B EF1 EF-7 ET-XXX EF-1 NOTE 3 NOTE 3 YES)NOTE 3 YES>NOTE 3 YES>NOTE 3 0~00 00 0 0 00 I 0 SYSTEH NAME: EMERGENCY DIESEL GENERATOR DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUmRY SHEET-UNIT 2 FLON DIAGRAM: 2-5151C-26 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XZ NUiiBER REV TYPE SIZE ACT F D I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-DL-114C 3 CK 1.5 SA B/9 0 3 A C CF-1 CF-1 P NOs NOTE 1 2-DL-116C 3 CK 1.5 SA B/9 C 3 A C CF-1 CF-1 P NOp NOTE 1 2-D L-126C 3 CK 2.5 SA E/9 0 3 A C CF1 CF-1 P NO>NOTE 1 2-DL"132C 3 CK 1 SA F/9 0 3 A C CF1 CF-1 P NO>NOTE 1 2-DL-158C 3 CK 6 SA G/5 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-QT-114-2CD 3 3H 6 SA H/5 0 3 A B EF1 NOTE 2 P NOp NOTE 2 0 0 e o e e o o e e ee e o e e 0 SYSTEM NAME: EMERGENCY DIESEL GENERATOR"CD" DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLOW DIAGRAM: 2-51510-27 RUN DATE AND TIHE: 15FEB90:16:14 VALVE I VALVE POSITION I ASHE SECTION XI NRSER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FUNCT ICL REQUIRED PERFORMED MODE 2-DG"102C 3 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NO>NOTE 1 2-DG-104C 3 CK 1.5 SA F/4 0 0/C 3 A C C F1 CF-1 P NO>NOTE 1 2-DG-128C 3 CK 1 SA C/3 C 3 A C CF1 CF-1 P NO>NOTE 1 2-DG-130C 3 CK 1 SA C/3 C 3 A C CF1 CF-1 P NOp NOTE 1 2DG140C 3 CK 05 SA F/1 C 0/C 3 A C CF-1 CF-1 P NO 2-DG-142C 3 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1 2-DG-146C 3 CK 2 SA A/9 0 A C CF1 CF-1 P NO>NOTE 1 2-DG-152C 3 CK SA D/9 C 3 A C CF1 CF-1 P NO>NOTE 1 2-DG-154C 3 CK 4 SA C/9 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-QT-132-2CD 3 3N 6 SA E/8 0 A B EF1 NOTE 1 P NO>NOTE 2 2-SV-120-CD 3 REL.0.25 SA N/2 C 3 A C TF1 TF-1 2-SV-139-CD 3 REL 1 SA B/2 C 3 A C TF1 TF-1 00 te e o e e e o e o e e o e e e;J SYSTEM NAME: EMERGENCY DIESEL GENERATOR"CD" DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 FLON DIAGRAM: 2-5151D-27 RUN DATE AND TIME: 15FEB90:16:14 VALVE I VALVE POSITION l ASME SECTION XZ NUMBER R V TYP ZE ACT F.DE I PONER SAFETY lCD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-SV-61-CD 3 REL 1 SA A/8 C A C TF-1 TF-1 R NO 2-SV-78-CD1 3 REL 1 SA E/3 C 3 A C TF-1 TF-1 2-SV-78-CD2 3 REL 1 SA 0/3 C 3 A C TF1 TF-1 2-SV-79-CD1 3 REL 0.5 SA E/1 C 3 A C TF1 TF-1 2-SV-79-CD2 3 REL 0.5 SA E/1 C 3 A C TF1 TF-1 R NO 2-XRV-225 3 GA 1 A B/3 C 3 A B EF1 EF-7 ET-XXX EF-1 E F-7 NOTE 4 YES'OTE 4 YES>NOTE 4 YES>NOTE 4 2"XRV-226 3 GL A B/4 C 3 A B EF-1 EF-7 ET-XXX EF-1 NOTE 3 NOTE 3 YES'OTE 3 YES>NOTE 3 YES>NOTE 3 2-XRV-227 3 GL 3 A B/4 C A B EF-1 EF-7 ET-XXX EF-1 NOTE 3 NOTE 3 P YES NOTE 3 YES>NOTE 3 P YES~NOTE 3 0 e o e.0 e e e e o e e e e o e.,'ae o 0o o eo e e

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LOENTLFICAYROS ()ST3 DCRLVED BY AOOIHG TO olsf RUN(NT LIL)V SELL FC)t SLNCLE OCCLCEYL FTLT (tttfLS IHPLASESTLFSSLT LEIFO R.D-FS 4 I~I'~F I C;~e'~av ttCCTOC COHfcllMtNT'TDCOCCH CLMFLOLS LOCS Tl 0 N 4 tsa I I)a'S vpptacoslf volvet w Nt atter ala sl ev N W DOll C SSLSISIC CLASS 1Bf ((NsiP INC (Te:6')(S(4EP.fOR REVISOR DESCRFTON SEE SEPARATE REVLSLON RECOLO FDR l)95 DRAOLNO Lt oaveat Itre la Ta caereessl st Sl~ow t'lose Ctr VISS I I Vt lC aca sowPPC I..(TC lf)IO 111~ct ca (Tt:s)Steel OC Tllf Caw I Crew Osa Nc P lit~CC Nota)>'e'ee stews e'M Mweet w'M aeltcaa afcnec toet~Natscc Coat.Iw N ae Ne Ma aeeeee~~e e ser ee sr epwMse se area w ews w N INS se eve eee eee epw see ew se ew ester<<peer M~etsfr ewwe\M 4 I p ll eeet Step Na ew eeww wte t\\N w eee eeprel,~w r II N serswe ew pwwe OtOIANA~MICNIOAN CLCOTIIIC CCA DONALD C.COOK NUC(EAR F(ANT~tsVDCNAII IISCIOCLA FLOW OIAGEAM POST hCCIDEHT SLMPLLH6 COHTAD()LENT LSYDEOGEII y UHII'foe OIL NO t SLALD O~saeva APC~J P>>s I~I Nr S<<s D I E I I M I wacs e)etawa.C<<ese w 800 3 0 9.0183-I,I~ef .l g" l.4 C 1I J l ~~er*I e C I'F G I N 2O 15 2 Terr'pro!I-COLO LE G LOOP I/2)/Q 0/5 (YVR)st ii1 la 514 ILI I'/zj I SEE OWG Stz(F F/4, F/2, G/B,N/4!COLD LEG SII~ttl LOOP I I'lt y!L COLO LE G lar2J stiiNL LOOP Z~.r strits I'/zy/t COLO LOOP LEG l,QX535 I.In[in z 0 IFI 3/4 ng n)LID521 I V}3/4 I'Iz (5'5 r/I'II 2 Ei/ZMO 5(5/4'1 I-2 UI 2 C i 2 0 V/.IMO-54 u I 2 2 C I 2 0 I/0 i 0 C v/l c ln 5/~IF I CO in 2)'/2 n 0 41 IPX I'HEAT~4CING r r TOPS MCRR 51ISO~r T(SIGN>>Sft T~HISQWL(//4 I~lit Ci t 5/4'ISINC VKNT SHits$1 li SM~5 Eri Sliics st ri CM~4 NO1112 DRiiH~NE rr itl51HVQRIIN~/ SIIASS SIIES F6R dtsYRUSI K NTATI 04 SCK TAISLFT Srt/5~%4'SUCTION BAY VCNT mSIMIM Miii'S I)SI5K PLA'IK DIIIIH 2'KAI AND DRIP POCKET DRAIN FRSCTNN ILDW'TAPS~(TYPCAL)IE IRSsgd I~It)2.Ih-/cpN 44 CL Oit'O'rcAT YR Acr 46 BTDP5 MCRC 3 IP 231\Irscw St I SS SKK THIS QSTC.K/6 rlttr Cbrr4 SIISY SIC TNrd MISC.INSTRUMENTATIQM AT 5AFETY DIJECTCDN PIAU'5 NORTH SOUTH I TA 2 5 I ITA-253 FUNCTION 00420 5(AL NQUSIN/I HICN TEMP il.iRM AT I'10 F BiT RCCIRC.Stt THI5DWG.@SSI CC t VE~tTA 252 ITA-254 LTI-2(i0 LTI-Zf 2 LTT-261 LTZ-26'3 LPI-250 LPK 262 IePRIHIRV WATER fLU5HOILIIIL'tN 5(LDW6.Defi, SI ISI I J40 Qfl A QRIFI(K, A 103 (s>>ss TO IVLS HOLD UPTArIKS SCK DWG.SIstr+/r, LI IN I~i 250 Ii 5V 51 Sttlt 1155~EEI DIBODRD S(AL NOUS'INC HIGH TEMP>LARMAT 120'F QN tÃL C(KCZR PISCHAR6E LIANIFOLQ 30.240 F RANCE QN THRUST SKARPI6 HOUSING, 30.240 F IEANGE AT THRUST SEARlhIG HOUSING DL INLET.O 30 PSI~SIDY ISX LSICIS M 209 511M<<Fe'SIISO 1RV 251~FC+F.L IRV 25st MTQ BORIC ACID TANKS Eea SEE DWG 513(, D/5 5 EL'EC'TRIC STRIP III El E EEICHLNWAV~BQRQN INJKCTKN TANK 4ÃDIA I I I'rrNICH (QVK RALL)CAPACITY 900CALS (TK'I I)FROM BQRC ACID TRANSFER PUMPS SKK DYYC 5131, K/5 3'IMY N 5141 s~SI S 5131 5.5123A.F/5 D,K,I/B.i 5 CAD'VED C OEurrrn'S (CCS P.C F K~~2 ARRICT.QE Nisi."PI PIN(r AT sit KTY IN JKKTIQN PUMPS r~I'0 I GENERAL NOTES L E a E II E tf AIIJ FLOW AUXILIIRY FLOW Q BY WESTINGHOUSE FQR VALVK~INSTRUMKNTE r SAMPLIVQ.PIPE MAT(RIAL AND QINKR SVMSQ'LS'NQT'XOLAINKQ ON THIS QV/0 ANQ FOR MARK NUMB'KR CQQKS.SKK QV/0 5104 MOTE: A A'L KDLSOrrENT.VLLVKS I-NstverrRNTs svoPVCO IPF-AS NOTE.D NSPVESLVCS IN FICLD TD Lrrsiy IEUEISO EIUNO'JT TISLN Locrc IN POSITION.IOYC.C ippsRNY StsspNG CLASS Z CY" SOT AS NOTCD.NOTE~CLASS t SNSYILV~IEIKNT CDMNSATCNSI TVC.XCZ BIEPEDARY DxtcND5'YD g IICLYD(5 TMS FIRST R/DT MACVC IVITC C ITCCC CCOSra 2 lCNTS I Dcatrcs Tvc,xsz sraovbacY CFYXVQS'TO! 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SKK.tssvG 5143.o/8 4 INI CC L~51'IDN~CPNCC (CMkfg 54vevr~-I 205 St~4 Krg NNIRVIJ YFcrr~'is fs DRAI/I CVSBIIO EED LSD Sf KSCN IIOS CI'1046 I)'%'IS(CE I 2 POg,.TCEEVOAART NYNAM~lnscTeeecaE) f4 lair'4 I IIV reit nsccuareicac, ccai.ucaT eacaraNDUCS aero CEM cooecccs sac diosaITwpicaaf IlŽMlnV (2 SAFETY INEIECTIQ 4DOQPNK=(btdiCN) teobFTNT I U'650CPM (MAX)1353PRI (QH (D'MAK QISCHAIICK pR LNUT (NQTEI FQ'IL MISC PIPR 2 SVAKE t PO-261 P 3510 RPM VIDO NP F)510 15P K SEVR)5KE 5.M t.OUTSIDE RKACTQR CONTAINMENT INSLDE RKDCTQR CONTAINMENT ~.A i e I~c I/D~-I E...,..F~.I..~~~=-G.DVM.~E~..EE u~L.~n~~N tdt CC't I l or XMn.zr I".+FROM REFUELING WATE fL 510 RAG f Irt~St'ANK.SEE OV/G~~5144 r E/CS TO REFUELING WA'(ER STORAGE TANK.SEE Ov/G.5144.E/7 ELSSV'W'/'T H(5 DV/G.II3ADE Lsre'IOsJE FOR (J(EIIT42 ERND SUPERSEDES DVECV NO I I Z.-5142 ICEV 16.FDR RCVISON DCSCICPTCYI 5CK SC/YVIAYC RCVI SON RCCDRD FDR TIRS DRARSNO e>>E e~Ee aewnr Er ee Eernrre TIETrprc reeii Mnrra Iree<<e e~nn uweu,rev a e<<r Ee rr e~~Ee~ne rn ewu~Eee re nr f n EeaM ev~wire Sneer v aa~I~Mrriii orer~Ee nt wne~~n a ii n niner nn ennp~iraslAMA a svorlcarr 222CYNic cDE DONA(J)C.COOK NUCLEAR FIJI(I oarocnaa SIIOOCAO F LOW D!AGRAM ER(ACORE COOKINGtslS 0 UNIT No<<JP.CENTI Iaaf 2-5 14 2-ZB.IY/E;rs.~W~'I IS WEEECEEI CICCIAIC OOITIA OCOTKY CD oaoaovlY~Iw Yoat../Frr~..a.-=-...:(y'A>>ir+Nadir S'eeCE'>>r4 '5 I I t' N H 4 I A 1%>(S-K 2 DISCHARCE To ATMOS, 54CXI.I (N')54X)0.2 (N'I)54XO 3 (N 3)SV'XD'4 (AA4)5$1 AY YOO Pst~OLA$$~4 4'pt$vrapttitv Ecvacevs vrc ELI scavttoAAv crecteA'vo caae44$vt\c VCAST tcoatv vra,vc loc OGAOP t vcve$Atto ErattpS vite'l$'I ENAaoeare crvctto$vat rees ptcLatoc$4 c Sccaetto erereraAv cLEDScse vrlvc oA ENT(ato$vo Alto avcaato4$vpc svateae VLALAc cA cAA ApvcA A Ioeiverarv CLOLGP vra.vc~tataSC EAAAL~5 4 vCite$Avo NAAA4$'4 c E~E sceaeaoAAv crvcvc$w>>Atra caaestc$vpc rtAST ttoraaaAAV cao$co VALVC liat.SV lot DKT At TOO PQf I IIA.(2(DFZ)IOA (31(NO3)fDA 141 (NE4)I I I 5 r FC r IRV-NZ vl 4 UIIT I AL PORC(Y(NT r rtoM IMTROCIN (P SUPPLY MANIFOLD SKE DYI(L dlldde Pgtegl!RV.122(NO2)I Rv-132(HES) IRV M'2044)He~~t'ji~-i I-ACCUMULATDR I (He I)TANK ()atf C 3 fkF3i 0-ODEK 6 4(N44)TO Rf ACTOR COOLANT DRAW TANEC SKD DWFL 5 1'37 A, LASS CC.CVI 4 STILL 5 SMSI I lfa ee~taS Ere NLL I PA-(20(N42) IDA 130(IFQ I IDA 140(N(41 I Cav 313 (2)R 6 S I D U A L N K AT K X C I(A IJ G K$(5 DA IIC)LCRQM CQMPQH'(NT CEVP.eet SYSTEM SEE E4't DwO 5135ACCVSL Ers Oar ow (4 CLS ILA.I'21 (NOK)ILA-131(NO31 ILA.141 (IF4)I(A IZV (N'It)t(JQ ISO (N 4'Sl (IA tto (NFCI L IIQ Nt I 3'70 PRESSUR)IER REUEF.TANK.SE'K/OWV 51'KBA, br>>Nc ()W 17K pd'tveOA (reset Ee(l Etv eeo (vlt t4$(Li'el 5 TQ patssvattta RELIEF TANK.SIE Qwo 5$2(VLDC'OD R(O)t IIIILV SII LCD STIL(M 483'SV-OL Vrl SV-N4W SET loll.f AT 600PSl STNio 4 SXICL!5 Sttoxat SLISC I IRV'lto IRV tto(NYZ)IRV 130(IF 3)STNse SLECN Prso SIICN sires KFiSM fRY lll IRV 121(N42)IRV 13$(NO3)IRV'41(N(ll v ISX-2(HSZ)~ Mt~IS X.3 (IF 3)psst(NO ISX.4 (H$4'1 311 r LC IQ IRVULO(MYC) T IO SIIU.4 SIIL)5 Sfltl I 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a(UEF TANK'SEK OWC5128 E(6 ro C FROM OTHE(I ACCUMULATOR TANKS d TO QJTTY INJECTION RHR LOOPS Ntt K 3 CQR COO(DOWN O'RAIN CSN SI Stt Oa(Sate Cats t(5'tst fa)N Slrot K IAZCIKN FL SEE QEA$I 51 ()PCS~eLE I 511)l ttt g.q NV)I ('(g"4)3, Sf.113 2 5'NR IVlP MIN CLQYI LINE PUMP SUCJION.'I'EK PWO SI424K(D 2'10 CREEL C VOLVME CQNTRQL SYSTEM FOR PUNIC ICATIQN.SKE OWC 51'29, F(2 SIIOILI r rr~Ae ale CLC CL)ACCUMULATOR FRL Loa SEE DWC 5142.5!Q f~tea StlOILC 6 Ve di RNV7 Iav r)7 IMO.326 St I SCOW t(40 3'24 A, 4as F DRAIN SIICOE 6'OW MEAD SAFETY DMECTKH Kl N(tf LECS (REAC'toa COOLANT SYSTEM).SEK DWO.CPN 58 1 VENT 4 FROM SAFETY I(ODNQ IN)ECTION PUMP'5'S(E OVSQ 5142DSIS i te)51155 rst Qw~4 I ILDOODO IMO tts 8 OE~51157 L'I 5(2da fldaN(6~SI(STLS Stlsdt'I LDW N'EAO SAFETY R(IICTIQN TO NQT LICS (D (RKACTO$(COOLANT SII5QLS SY St E M 3 SEE QWC SIZQ, F(5, Nls lOOP IFS SI a57($IMO I'20 St(tot IM043$4 RNISV RNNLt Va'bx 301 QL RNIISW RNRLW L I Isx'c,30 2 d'NR PVMD MOL FLOW UHK ELCQS V'L.4 V&1st-<<Ž~I(M.321 stlsZS 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I AVÃILIAR'Y FLOW fOR VALVE INSTRUMENT SAM)EL(NB/PE MATERIAL g)V(PD(ENT SEISMIC CLA55 j EXCEPT Jove DKZYK(2 (P BY WESTINCI(OUSE ALLIOMF HINT tAL$SS SUPPLISD er 9 EXCEPT AS NQTK(r VA(vd INTKRIDCKED WITH$$EACT()R (IQOLANF SY5)%ld Pl)ESKVRK SISNAL (4 A/0 5 SI ERYURE CARD Al Available On erture Card Pat(tat O(54CHSIYI Oat CSCN CoaAPONCNT IOCNYIISCA~N <<VDAQRR IO'4: VNLCSO OYNC+wesa HO'Yto ele Parve~tcc ervetf p$4 trace taeere etta Nese Eepa Ar 4 atw Ne eeerr Se 4 4 et te e eweae e~we~pet 44.r evc<<w te~tepee eervee te tp Aee arete$4 eeae mme e ee 4(~eeae Etv ee ee seve eaeveeA et~carel ae 4 seve Peeve ptt~Nso(ANA 4 EececCAN (ttctloc ca DONAU)C.COOK NUCLEAR P(ANT NCSNNO~o(NOAE FLOW DIAGRAM QAERGL CORE COO UNGI()S(UNIT bto 2 DaNa 3 5143 35 4 te P DVAPV p CAW(s F pa e vt EN(NNJN IICCYCEC tov(S I(CIS(t COSEC t OSblovly ICC VOCE Yeiao ceres ttADc atvacv e(atl Ver r 4 AeeO$VtCE(5COCC (eteL E.t SDOS, Ntv.Ct N t SCT Vl IotcetetscAYECN NLENS t CNLY'(OC(KC VALVE NV Vsf Ns AFPCAN ON YNIS CEISNSSR 5ff 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