ML17334B150

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

ML17334B150
Person / Time
Site:	Cook
Issue date:	10/05/1987
From:	INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17326B298	List: ML17326B297 ML17334B149 ML17334B150
References
AEP:NRC:0969H, AEP:NRC:969H, PROC-871005-01, NUDOCS 8710130278
Download: ML17334B150 (317)

Text

ASME SECTION XI VATVF: TEST PROG 2ND TEN YEAR INSPECTION INTERVAL FOR THE D.C.COOK NUCLEAR POWER STATION UNIT NO.2 Revision No: 2 Date: 8-31-87 TABLE OF CONTENTS 1.INTRODUCTION

-(FIGURE-1)2.LIST OF DRAWINGS-(FIGURE-2)3.NOMENCLATURE FOR TEST METHODS-(FIGURE-3)4.RELIEF REQUEST NOTES 5.ATTACHMENT-A 6~VALVE

SUMMARY

SHEETS 7.FLOW DIAGRAMS~-87-l01,30278.

87l005~PDR.-ADOCN,'05000315 P PDR~Page 1 of 7p ASME SECTION XI VALVE TEST PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D.C.COOK NUCLEAR PONER STATION UNIT NO.2 Revision No: 2 Date: 8-31-87 1.Valve Testin Pro ram INTRODUCTION Figure-1 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 systems flow diagrams which were used to develop this valve test program.Valve Summary Sheets contain the following:

Y t il.,*(e.g., 2-5105B-42)

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

• Revision Number: Any change of valve description, function or test requirement.

Page 2 of 70 Revision No: 2 Date: 8-31-87 D.C.Cook Nuclear Plan Valve Test Program Figure-1 h 1 REL-Relief and Safety CK-Check BF-Butterfly GA-Gate GL-Globe DA-Diaphragm 3W-Three-Way ND-Needle AG-Angle BL-Ball VB-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*Valve osition during normal plant operation or during performance of its safety function, one of the following:

0-Open C-Closed 0/C-Open/Closed or vice versa*Code Class: ASME Code class of valve, either 1, 2, or 3 Page 3 of 70 D.C.Cook Nuclear Plant Valve Test Program Revision No: 2 Date: 8-31-87 Figure-1*Valve Status-A P: Active or passive'P V defined in INV-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: One of the following:

P-Power Operation (Every 3 months when unit is at power)C-Cold Shutdown (Testing will be performed at cold shutdown frequency)

See Note"F" R-Refueling (Testing will be performed at refueling outage frequency)

• Code Relief: Whether or not a code relief is being requestedl will be one of the following:

NO NO, NOTE X comments YES, NOTE Y proposed in code relief-Valve is to be tested per code, no comments-Valve is to be tested per code, but there are Code relief is requested.

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

E.Alternative testing is to be performed on a check valve as indicated under relief request notes in lieu of stroke.testing required by Section XI, IWV-3521.It is accomplished by disassembly or radiography method as explained below: Page 4 of 70 D.C.Cook Nuclear Plan Valve Test Program Revision No: 2 Figure-1 Date: 8-31-87 a.Disassembl Method The valve bonnet is removed, the disc is manually full-stroke exercised, and the valve internals are visually inspected.

The results of this test are documented.

b.Radio ra h Method This method is used as an alternative testing method to determine the disc position under no flow or reverse flow conditions (i.e., valve seated).This, in conjunction with the full forward flow testing of the valve, can provide assurance that the disc was free to move from full-open position with the forward flow to the closed position with no flow or reverse flow conditions.

The results of this test are documented.

The valve grouping for sample disassembly or radiography under alternative testing is done based on the following criteria: 1.2~3.4~5.etc.)valve type and design similarities system design, flow, and service conditions frequency of valve operation manufacturer size range (i.e.up to 2", 2-1/2" to 4", 4" and 6" 6" and 8" The alternative testing to be performed for a particular valve is indicated on the valve summary sheets and relief request notes.This will be accomplished by selecting one representative valve from each group of valves during refueling outages.If the inspection results are unacceptable, all the valves in that group will be inspected.

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Revision No: 2 Date: 8-31-87 D.C.Cook.Nuclear Plan Valve Test Program Figure-1 F.Conditions for Valve Testing During.Cold Shutdowns Cold shutdown testing of valves identified in the IST Program.is acceptable when the following conditions are met: 1.Valve exercising need not be done more often than once every 3 months in case of frequent cold shutdowns.

2.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.3~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.I 4.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 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 70 Revision No: 2 D.C.Cook Nuclear Plan Valve Test Program Figure-1 Date: 8-31-87 Using the above criteria, the limiting stroke time for each valve is derived as follows: 1.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 up to.74.75 to 1.24 1.24 to 1.74 1.75 to 2.49 0.5 1.0 1.5 2'Based Line Time x 2+1 Second=Recommended Action Time or Tech.Spec.Limit, whichever is less...5 x 2+1=2 Seconds=1 x 2+1=3 Seconds=1.5 x 2+1=4 Seconds=2 x 2+1=5 Seconds 2.Valve Stroke Time-2.5 to 10.49 Seconds 2.5 to 10.49 3 to 10 Base Line Time x 1.5=Action Time Page 7 of 70 Revision No: 2 Date: 8-31-87 D.C.Cook Nuclear Plant.Valve Test Program Figure-1 3.Valve Stroke Time-10.5 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)H.Code relief is requested for timing tolerance and trending per paragraphs IWV-3413(b) and IWV-3417(a) for fast acting valves (those with the maximum limiting stroke times of five seconds or less, determined from historical stroke time values and/or valve design specification).

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

The fast acting valves have been identified as"ETF" and acceptance criteria has been defined in the program.Page 8 of 70 0

DONALD C.COOK NUCLEAR P Revision No: 2 Date: 8-31-87 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS Figure 2 NO.SYSTEM Main Steam Steam Generating System Feedwater Feedwater (Auxiliary)

Essential Service Water Non-Essential Service Water Station Drainage Containment Reactor Coolant Reactor Coolant FLOW DIAGRAM NO.2-5105B 2-5105D 2-5106 2-5106A 2-5113 2-5114A 2-5124 2-5128 2-5128A REVISION 42 2 34 41 36 27 20 19 34 CVCS-Reactor Letdown&Charging Component Cooling Component Cooling Component Cooling Nuclear Sampling Nuclear Sampling Post Accident Sampling-Containment Hydrogen Emergency Core Cooling (SIS)2-5129 2-5129A 2-5135 2-5135A 2-5135B 2-5141 2-5141A 2-5141D 2-5142 32 20 34 30 14 27 30 28 Page 9 of 70 Revision No: 2 Date: 8-31-87 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 (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 FLOW DIAGRAM NO~2-5143 2-5144 2-5145 2-5146B 2-5147A 2-5149 2-5151A 2-5151B 2-5151C 2-5151D REVISION NO.35 29 20 23 35 23 26 27 26 27 Make-Up Water&Primary Water System Compressed Air System CVCS-Boron Makeup Spent Fuel Pit Cooling&Clean-Up WDS Vents&Drains Post Accident Liquid&Gas Sampling Post Accident Liquid Sampling Inst.Panels 12-5115A 12-5120B 12-5131 12-5136 12-5137A 12-5141C 12-5141F 41 22 19 25 21 8 6 Page 10 of 70 Revision No: 2 Date: 8-31-87 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI 1 CATEGORY A-B VALVES Figure 3 ASME CODE SECTION XI PARAGRAPH EF-1 EF-2 Exercise valve (full stroke)for operability every 3 months.(IWV-3411)

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

Code relief requests are Requested) provided in the flow diagram notes.EF-3 EF-4 Exercise valve (part stroke)for operability during operation; Exercise (full stroke)at a cold shutdown or refueling outage frequency as indicated.

Justification for exercising the valve during cold shutdowns is provided in the flow diagram notes.Code relief request is provided if full stroke test is deferred to coincide with refueling outages.Exercise valve (full stroke)for operability prior to return to'service (IWV-3412)(IWV-3416)

EF-5 Valves with remote position indicator shall-be observed at least once every 2 years to verify that valve operation is accurately indicated.(IWV-3300)

EF-6 EF-7 EF-8 ET-XXX ETF-YYY This note was intentionally deleted.Exercise valve (with fail-safe actuators) to observe failure mode every 3 months Exercise valve (with fail-safe actuators) to observe failure mode at a cold shutdown or refueling frequency, as indicated.

Exercise valve-power operated (full stroke)and measure time.(E.G., ET-015 means recommended action stroke time is 15 seconds)Exercise valve-power operated (full stroke)and measure time for fast acting valves.Code relief is requested in Item H.(E.G., ETF-005 means recommended action stroke time is is 5 seconds)Page ll of 70 (IWV-3415)(IWV-3415)(IWV-3413&3417)(IWV-3413'&3417)

Revision No: 2 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Figure 3 Date: 8-31-87 2 CATEGORY C VALVES ASME CODE SECTION XI PARAGRAPH CF-1 Exercise valve (full stroke)for operability every 3 months.(IWV-3521)

CF-2 Exercise valve (full stroke)for operability at a cold shutdown or refueling outage frequency as indicated.

Code relief requests are provided in the flow diagram notes.(Code Relief Requested)

CF-3 Exercise valve partial stroke during plant operation and full stroke (IWV-3522) for operability at a cold shutdown or refueling outage frequency as indicated.

Justification for exercising valves during cold shutdown is provided in the flow diagram notes.Code relief requests are provided if full stroke testing id deferred.to coincide with refueling outages.CF-4 TF-1 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-34 16)(IWV-3 5 10)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.

Permissible leakage values for each category A or AC valve are listed in Attachment-"A".

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Revision No: 2 Date: 8-31-87 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Figure 3 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'Q" 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 13 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5105D-2 Revision No: 2 Date: 8-31-87 NOTE 1: NOTE 2: FW-118-1 thru-4: The function of these valves is to provide feed-water flow from the main feedwater pumps to the steam generators.

These valves cannot be exercised during power operation because closing of these valves would require securing feedwater flow to the steam generator and partial stroking may cause instability of steam generator water level which could result in reactor trip.Further three loop operation is not allowed per D.C.Cook Nuclear Plant Technical Specification 3.4.1.1.These valves will be confirmed closed by disassembly on a sampling basis during refueling outages.MRV 210-220-230 and-240: 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 IHV-3410.MRV-210,-220,-230 and-240 are part stroke tested quarterly by use of external hydraulics and full stroke tested during hot standby (Mode 3)at cold shutdown frequency.

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DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5105D-2 Revision No: 2 Date: 8-31-87 NOTE 3: MS-108-2 and 108-3: These check valves are located in the steam supply lines to the Auxiliary Feedwater Pump Turbine.These valves operate during normal IST feedwater pump testing.Normal design flow rate for this pump is 900 GPM..However, flow is restricted to a maximum of approximately 700 GPM through the 3" test line used during pump test.The check valves are therefore stroked to the extent that they pass the required steam flow to drive the turbine driven auxiliary feedpump at a flow rate of 700 GPM.Steam flow through these valves to the auxiliary feedwater pump turbine is verified to within 104 (at 900 GPM flow to SG's, 31,000 lbs/hr steam vs.700 GPM flow through test line, 28,000 lbs/hr steam)of the maximum requirement.

This is considered adequate for full stroke testing.In addition, due to the plant design, the only method available to verify the valve closure is disassembly.

The valve is not equipped with position indication.

The valves will be verified closed by disassembly on a sampling basis at a refueling frequency.

Page 15 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5106-34 Revision No: 2 Date: 8-31-87 NOTE 1: FMO-201-202-203-204&FRV-210-220-230-240: The function of these valves is to provide feedwater flow from the feedwater pumps to the steam generators.

These valves cannot be exercised during power operation because closing these valves would require securing feed flow to the steam generator and partial stroking may cause instability of steam generator water level which could result in reactor trip.Further, three loop operation is not allowed per D.C.Cook Nuclear Plant Technical Specification 3.4.1.1.These valves will be full stroke exercised during unit start-up or shutdown.Page 16 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diag'ram No: 2-5106A-41 Revision No: 2 Date: 8-31-87 NOTE 1: FW-132-1-2-3-4: 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.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.NOTE 2 FW-.134&FW-135: 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.The design flow rate is 900 gpm.In order to pass design flow of 900 GPM through, these valves would require delivering cold auxiliary feedwater to the steam generator nozzles.This would result in thermal shock to the steam generator nozzles.We consider that 700 GPM (784 of design flow)is sufficient to demonstrate full stroke operability.

In addition, these valves are full stroke tested with flow rate of 900 GPM at a refueling outage frequency.

Page 17 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5106A-41 Revision No: 2 Date: 8-31-87 NOTE 3: FW-138-1-2-3-4: 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: NOTE 5: FW-149 and 150: The required full stroking of these check valves is satisfied when Turbine Driven Auxiliary Feedpump completes its required testing.FW-153 and 160: 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 18 of 70 I

DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5113-36 Revision No" 2 Date: 8-31-87 NOTE 1: ESW-141-142-143-144: These valves will be disassembled and inspected internally per procedure no.12MHP-5021.032.00ZL during every refueling outage.NOTE 2: NOTE 3 ESW-145-240-243: 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.

We believe that testing at a refueling outage frequency is sufficient to demonstrate operability of this long term valve.The valves will be full stroke tested during refueling outages.Since the valves are manual, stroke timing is not required.I WRV-722-724-726-728: 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.We are requesting code relief 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 on a staggered basis, every 31 days 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 during refueling outages.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 19 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Plow Diagram No: 2-5114A-27 Revision No: 2 Date: 8-31-87 NOTE 1: See<<Attachment-A<<

for permissible seat leakage values.Page 20 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5124-20 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.NOTE-2: NS-357: 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 during refueling outages.Page 21 of 70 e DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128-19 Revision No: 2 Date: 8-31-87 NOTE 1: NSO-021-022-023&-024: 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.

The valves also cannot be tested during cold shutdown unless RCS is operating at half loop, because testing of these valves can create a similar situation as that described above.Since half loop operation of the RCS is not a normal evolution during cold shutdowns, full stroke test for these valves will be scheduled at refueling frequency.

Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed during each refueling outage by performing 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 22 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 2 Date: 8-31-87 NOTE 1: NOTE 2: NOTE 3 NOTE 4: NOTE 5: CS-442-1 thru 4: 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 at refueling outage frequency.

See Attachment-"A" for permissible seat leakage values.NRV-151-152-153: These pressurizer power operated relief valves are normally closed during power operation (passive valves).The system is considered out of service (as defined per INV-3416)during power operation.

The valves will be full stroke exercised prior to placing them into service for RCS cold overpressurization protection.

PN-275: 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 during seat leakage testing per Appendix"J" program at refueling frequency.

N-159: 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 during seat leakage testing per Appendix"J" program at refueling frequency.

Page 23 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 2 Date: 8-31-87 NOTE 6: NOTE 7 NSO"061-062-063-064: These four one-inch 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 also cannot be tested during cold shutdown unless RCS is operating at half loop, because testing of these valves can create a similar situation as that described above.Since half loop operation of the RCS is not a normal evolution during cold shutdowns, full stroke test for these valves will be scheduled at refueling frecpxency.

Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed during each refueling outage 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 requirements.

SI-189: 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.

Test will be run at a refueling frequency when there is not potential for overpressurization.

Page 24 of 70

&0 Vl OI 0~W 0 4 W A 4,H O A I~~0 Q nI nI pl A CV~~g)0 I I 0 co~8 N 0~~g Ql 8 nI C4 A~0 OA>0 H Q 0 SA 8~+8 A 8 t0 A NOg ld>>g&SgO WWNnI Nnl&~rl A ldQSMN g>SAHg ONA 0 nI NN Hww NN N 4 td td%td-H NNtdgO&5~O'tI N 8 A nI N 8 N NQAAP RAeg 0 A't5 8 8 0 5&I'd 0 Q N Ql 54 8.rl Ul~4~A Q 0 8 4'tI 8~0.8 8 NgNNO 8 0 f40&8~A 5 nI 8 k.R f4&g f40440>N'd 0 nI Q 0 54 R.H g 8 8 54 tP 0 Ul I4 t0 A 8 M I4$big+0 0&f44 I4A 0 H'tI~P I4 0 8~H 4.rl R nI 0 rl't5 8 4't5~8 8~nI 0 8 8 8 gA 4 8 g 4&8 Q M M SN SAWQOI4 P-H 4 4&nI td w 0 Q 0 OMS~00 0 SAS 8 N'tf N A~8 A 8.R<H 0 N.R~SA.RN 8 WN gNP SW 0 8 td N g nI N~R g 0 0 P&.rl.H 4%4-H4 Q g 4888 td td 8 0 f4 4't5 8 A 0 A>8 H'd 0 8 g>N 4l N AO>0+ANN&8 OnINS>0 08>0 areal 8 ow H A&040 08&&0 0 0 4'tI+A.R 8 8<H 0&A 4 Mw 8 0~4't5 A S-R.H AAwse~o&P Ul&nI I4 4 8 g 0 0 0 HQ SNI4~$5 Qg>8~g 8~b 8 8 0W't5%NO A SWN'R nI Ql OH%N4A gN>8 N g&W nlgnI AQ 8 nl NgNN 5 SAM g 0'tH 0 0 A~4 A 0~R.R g ep spA 8'tI4g Old M nial 4genINOSAWAA A.rl>0-8 n$N 0 0 4 4~H g Ql&0 0 8't5 0 SW 5 QW M CA OPcP~N nI 0 Ql't5~SAW ARK&0 N 8 0 g4td 8~4 egg gA 0 ON 0 g4-rt Id-8 g A ON 4 g nI-H rd 8 0 M H 0 0'tI gN N'5 N~H 40 0 f4 5 N I4 gQOH SQQ~g tPI4&H 8 8&N 0 0 Q g 0 nI Sdgee 4A 84%A Idee WA~>g 0 td-rl-rl~HeÃe A 0 tPQl M~g 8 N 0 N 0 848 8 4 tP 8 W QA 4 X nI 8&td 8~N n5~MI4 8 NN NA.rl N N g 0.rl nI 4~rE Q A N 0 nIA NW Ul 8 W 0540-8 0 44$OAA 8 Ql Ol F4 I 8 nI'dN 0 g 0 rd4N I4 8 W W 0~N nI 8 N Aee M W 8 nI A 0>H 5 54 0 0<H td&0 08~q5 SA Sg A&84rd N N 0~NW~RH884 N 4 Ql AenIEC SNOenI OVA08~0 N 8 q5 8~8 0~0 N M Q 8 8'tH g 0~Stdgh Q 4N tPWROHO$$4 0 W f4 5't5 X tP AN Q&Sld g~r4 0 Q~XA$85 N 8-a~nI N 4A 0 Q 0 0'550~.N5&SWtd&g Ql M M g~0 54 N.R As leos I f4%Ql f4Q OA~Q 4 5 5'tf 0&8 td&0 N f4 td~&I4$td'5&SN'5 5 8 8 g g N 0 g OA&4J 0.8.8 g td&g nI.R tp 0 g OQAWtd~n$+4.00tde08 4 8 WN OSMIUM N<H g4M 5 M'5 Ql ealHMnlale

~M 4A 5 8 0~M r I f45 0 f44 nI H M 4 I4<nl 0 55M>&I4 Ql N g W 5 8 A 4 I.RWOSX 0 tP I4W tP 5 0 A 8 Ql g rl H<H A.+55td'5 8 0%OMAN 8 A 0 nI 4~0 Ql nI 8 MA SA 8 4 5 ON 8 0 A A 0 O'A N NNNN Ql>0 04&&8 nI't5&OgNS 8 pl N N~IPI 0 I 8 Q A 0 8 8 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 2 Date: 8-31-87 NOTE 4: NOTE 5: NOTE 6: CS-321: This containment isolation check valve's function is to supply borated water from the volume control tank to the regenera-tive 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 during refueling outages in deference to ALARA consideration.

CS-328Ll-329Ll-328L4-329L4: These check valve's function is 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 iso-lation function.The higher pressure (RCS)to low pressure (CVCS Suction)isolation is accomplished by other valves which are tested to category"A" requirement.

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

QCR-300-301: 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 and fail safe tested at a cold shutdown frequency and seat leakage tested during refueling outages.NOTE 7: QMO-200-201: These motor operated gate valves are i.nstalled on the CVCS charging line to 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 tested at a cold shutdown frequency.

Page 26 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 2 Date: 8-31-87 NOTE 8: NOTE 9: QRV-200: This control valve is required for emergency boration in Modes 5 and 6.The valve is normally open to permit.charging.The valve cannot be full stroke tested during power operation because it would interrupt charging flow which could effect pressurizer level.The valve will be part stroke exercised during power operation and will be full stroke exercised at cold shutdown frequency.

The valve cannot be"fail safe" tested nor stroke timed since position indication is not provided.QRV-251: This control valve is required for emergency.boration in Modes 5 and 6.The valve is normally open to permit charging flow when the centrifugal charging pumps are running.The valve cannot be.full stroke tested during power operation because it would interrupt both charging and seal water flow which could effect the pressurizer level and damage the reactor coolant pump seals.The valve will be part stroke exercised during power operation and full stroke exercised at cold shutdown frequency.

This valve cannot be"fail safe" tested nor stroke timed since no position indication is provided.NOTE 10: SI-185: This normally closed valve functions to transfer the suction source of the charging pumps to the refueling water storage tanks.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 during refueling outages.Page 27 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129A-20 Revision No: 2 Date: 8-31-87 NOTE 1'CM-250-350: 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 at cold shutdown frequency.

NOTE 2: See"Attachment-A>>

for permissible seat leakage values.NOTE 3: QMO-451-452: 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 at cold shutdown frequency.

Page 28 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 2 Date: 8-31-87 NOTE 1: CCM-451-452-453-454-458 and-459: These valves cannot be tested during power operation without securing cooling water to the RC pump.Isolation of these valves could cause failure of the RCP.Valves to be tested at cold shutdown frequency.

NOTE 2: See"Attachment-A" for permissible seat leakage values.NOTE 3: NOTE 4: NOTE 5: CCR-455-456 and-457: These valves cannot be tested during power operation without securing cooling water to reactor the support coolers.These valves must remain open to prevent overheating of the concrete around the reactor supports during the normal opera-tion.Valves to be tested at a cold shutdown frequency.

CCW-135: 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 the normal operation.

The valve will be verified closed by seat leakage testing during refueling outages.CRV-470: This air-operated valve is located in the Component Cooling Water (CCW)return from the letdown heat exchanger and controls the temperature of the letdown flow leaving the heat exchanger.

The position of this valve is set by QTC-302.The valve cannot be"fail-safe" tested nor stroke timed since no control switches are installed to perform those tests.The valve will be full stroke exercised quarterly.

Page 29 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135A-30 Revision No: 2 Date: 8-31-87 NOTE 1: CMO-411-412-413-414-415&-416: 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 30 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135B-14 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.NOTE 2: CCW-243-25 CCW-243-72 CCW-244-25 and CCW-244-72:

These check valves are located in 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 equipped with position indication.

The valves are confirmed closed by seat leakage testing in accordance with Appendix"J" during refueling outage.Page 31 of 70

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141-27 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 32 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141D-8 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.NOTE 2: NS-283: 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: 1)due to the plant design (line is open ended in the containment), the only method available to verify the valve closure is leak testing, and 2)check valve is not equipped with position indication.

The valve will be full stroke exercised in the open position by performing a flow test quarterly and will be confirmed closed during the seat leakage testing per Appendix"J" program at a refueling frequency.

Page 33 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-28 Revision No: 2 Date: 8-31-87 NOTE 1 ICM-250 and ICM-251: 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.Valves will be tested at cold shutdown frequency.

NOTE 2: See"Attachment-A" for permissible seat l'eakage values.NOTE 3: NOTE 4: NOTE 5: IMO-261: This valve cannot be tested when SI pumps are required to be operable.Testing would result in isolation of both pumps.This valve will be tested at cold shutdown frequency.

IMO-262 and-263: These motor operated valves are located in series in the re-circulation line of the Safety Injection pumps.Exercising any of these valves will make the SI pumps inoperable.

These valves will be full-stroke exercised at cold shutdown frequency.

SI-110N SI-110S and SI-101: Safety Injection (SI)pump discharge valves, SI-llON and-llOS, cannot be exercised during power operation because SI pumps cannot overcome reactor 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 power operation during pump testing.These valves cannot be exercised during cold shut-downs because SI pumps are required to inoperable by Technical Specification 3.5.3 to protect against low temperature over-pressurization of the Reactor Coolant System.These valves will be full-stroke exercised at refueling frequency in conjunction with the full flow test.Page 34 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-28 Revision No: 2 Date: 8-31-87 NOTE 6: SI-142 Ll L2 L3 and L4: 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 concen-trated 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 during refueling outages.Page 35 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A>>

for permissible seat leakage values.NOTE 2 NOTE 3: IMO-128 and ICM-129: 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 prior to placing them into service at a cold shutdown frequency.

IMO-310-320-314-324: These valves remain open during injection phase of a safety injection, but will be closed during r'ecirculation phase.Therefore, stroke timing will be from open to close position.NOTE 4: IMO-315-316-325-326: 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 SI 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 at cold shutdown frequency.

Page 36 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 5: SI-166 Ll L2'3 L4: These check valves function to prevent back-flow from the RCS into 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 suf-ficient 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 refueling 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 partially-stroke exercised during refueling outages and disassembled for internal inspection on a sampling basis.NOTE 6: SI-161 Ll L2 L3 L4: 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.The valves cannot be full stroke exercised during cold shutdown due to potential low temperature overpressurization damage to reactor vessel.These valves will be part stroke exercised at a cold shutdown frequency and will be full stroke exercised at the refueling frequency when reactor vessel head is removed.Page 37 of 70

DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 7: RH-108E and RH-108W: These valves cannot be full stroke exercised quarterly because no full flow path exists.The valves will be full stroke exercised at cold shutdown frequency (during RHR operation).

NOTE 8: RH-133-134: These check valves function to circulate water from the RHR pumps to the RCS cold legs when the RHR system is aligned for heat removal operation.

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 during start up pursuant to Technical Specification 3.4.6.2.NOTE 9: SI-148: 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 with both trains operable.The valve cannot be full stroke exercised during cold shutdown since water solid 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 a refueling frequency.

Page 38 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGBAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-29 Revision No: 2 Date: 8-31-87 NOTE 10 NOTE 11: SI-151 E.W: These check valves are located in the RHR supply lines 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 a cold shutdown frequency.

SI-152 N S: 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 RCS.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 in conjunction with full flow test.page 39 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 12 NOTE 13: NOTE 14: SI-158 Ll L2 L3 L4: Check valves SI-158 are located in 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.The valve cannot be full stroke exercised during cold shutdown due to potential low temperature cold overpressurization damage to the reactor vessel.These valves will be part stroke exercised at a cold shutdown frequency and will be full stroke exercised at the refueling frequency when reactor vessel head is removed.Sl-170 Ll L2 L3 and L4: 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 as 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 exercising is disassembly method.The valve is not equipped with position indication.

The valves will be disassembled on a sampling basis during refueling outages to verify full stroke exercising.

N-102 This check valve is located in the nitrogen supply header to the accumulators for blanketing purposes.The valve cannot be full stroke tested to 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 position indication.

The valve will be verified closed during seat leakage testing per Appendix"J" program at refueling frequency.

Page 40 of 70 DONALD C.'OOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5144-29 Revision No: 2 Date: 8-31-87 NOTE 1: CTS-138E&W CTS-103E&W: These check valves are located in the lines supply water from the RWST to the Containment Spray Pumps suction CTS-138E&W)and the discharge line from the Containment Spray Pumps (CTS-103E&W)to the ring header in containment.

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

These valves are partial stroked during Containment Spray Pump Testing.These valves are identical in type, design, and operate at similar'requencies, flows, and temperatures.

Since the design conditions and size are sufficient to warrant grouping them, the valves will be disassembled during refueling on a sample basis.NOTE 2: CTS-131E&W CTS-127E&W RH-141 RH-142: These check valves.are located in the supply lines to the containment spray ring headers.During normal plant operation, they are in the closed position.They are exposed to the containment atmosphere on the downstream side and are isolated from fluid pressure in the upstream side by closed MOVs.These valves cannot be 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 containment, etc.The only practical method of verifying operability of these check valves is by disassembly.

These valves are identical in type and design and operate at similar conditions and frequencies.

Since the design conditions and size are sufficiently similar to warrant grouping them, the valves will be disassembled on a sample basis during refueling outages.NOTE 3: CTS-127E&W CTS-131E&W RH-141 RH-142: These valves are to be seat leakage tested in accordance with the special testing procedure because of the configuration at D.C.Cook Plant.The permissible seat leakage values of these valves are listed in Attachment-"A".

Page 41 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5145-20 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 42 of 70 DONALD C.COOK NUCLEAR PLM VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5146B-23 Revision No: 2 Date: 8-31-87 NOTE 1: R-156 and R-157: These check valves are installed in parallel lines to the gycol main supply and return lines mainly to relieve gycol 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 indication.

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

NOTE 2: See"Attachment-A" for permissible seat leakage values.I Page 43 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5147A-35 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible leakage values.Page 44 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5149-23 Revision No: 2 Date: 8-31-87 NOTE 1: VRV-325-315: These 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 recpxirements.

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 45 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151A-26 Revision No: 2 Date: 8-31-87 NOTE 1: 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-114-2AB:

This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).

This three-way thermo-static 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; (2)this valve is demon-.strated operable during diesel generator testing.Diesel generators are tested every 31 days on a staggered basis per Technical Specifi-cation 4.8.1.1.2.

The valves will be verified operable by observing proper temperatures during diesel testing.Page 46 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B-27 Revision No: 2 Date: 8-31-87 NOTE 1: 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:

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 tempera-ture.We are requesting exemption from the testing requirements since (1)this valve functions only as 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-220 Jet Assist-221 and-222 Startin Air: The starting air valves are installed on parallel air supply lines to a diesel generator.

The valves are not equipped with position indication devices to directly measure valve stroke times.Stroke timing is verified by measuring diesel starting times (Technical Specification acceptance ten seconds or less).The valves on a staggered basis are valved out one at a time to verify the operability of the opposite valve during diesel testing.The consistent compliance of the diesel generator start times (typically seven to nine seconds)demonstrates the valve performance.

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

The starting air valves do not require or have a fail safe position because there is a redundant starting air supply system for each diesel generator.(continued)

Page 47 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B-27 Revision No: 2 Date: 8-31-87 (Note 3 continued)

Similarly, stroke timing of jet assist valve XRV-220 is verified by measuring diesel starting times.The jet assist valve s fail safe position is"closed".The jet assist valve's function is to facilitate diesel generator quick start.Its failure to open upon a diesel start signal could cause the effected diesel generator to achieve operating conditions more slowly.Based on single failure criteria, the other diesel will start within the required ten seconds, thereby meeting system requirements.

If this valve were to fail open, (open is the position to assist diesel generator starting)then the starting air reservoirs would bleed down, rendering that diesel generator inoperable.

Therefore, in order to assure the starting air supply, the fail safe mode for this valve is closed.Page 48 of 70 DONALD C.-COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151C-26 Revision No: 2 Date: 8-31-87 NOTE 1: 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:

This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).

This three-way thermo-static 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 every 31 days on a staggered basis per Technical Specification 4.8.1.1.2.

The valves will be verified operable by observing proper temperatures during diesel testing.Page 49 of 70 DONALD C.COOZ NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151D-27 Revision No: 2 Date: 8-31-87 NOTE 1: 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:

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.'iesel 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-225 Jet Assist-226 and-227 Startin Air: The starting air valves are installed on parallel air supply lines to a diesel generator.

The valves are not equipped with position indication devices to directly measure valve stroke times.Stroke timing is verified by measuring diesel starting times (Technical Specification acceptance ten seconds or less).The valves on a staggered basis are valved out one at a time to verify the operability of the opposite valve during diesel testing.The consistent compliance of the diesel generator start times (typically seven to nine seconds)demonstrates the valve performance.

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

The starting air valves do not, require or have a fail safe position because there is a redundant starting air supply system for each diesel generator.(continued)

Page 50 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151D-27 Revision No: 2 Date: 8-31-87 (Note 3 continued)

Similarly, stroke timing of=-jet assist valve XRV-225 is verified by measuring diesel starting times.The jet assist valve s fail safe position is"closed".The jet assist valve's function is to facilitate diesel generator quick start.Its failure to open upon a diesel start signal could cause the effected diesel generator to achieve operating conditions more slowly.Based on single failure criteria, the other diesel will start within the required ten seconds, thereby meeting system requirements.

If this valve were to fail open, (open is the position to assist diesel generator starting)then the starting air reservoirs would bleed down, rendering that diesel generator inoperable.

Therefore, in order to assure the starting air supply, the fail safe mode for this valve is closed.Page 51 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5115A-41

-Unit-2 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 52 of 70 DONALD C.COOK NUCLEAR P VALUE TEST PROGRAM REL1EF REQUEST NOTES Flow Diagram No: 12-5120B-22

-Unit-2 Revision No: 2 Date: 8-31-87 NOTE 1 NOTE 2: NOTE 3 PA-342: 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 indication.

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

See"Attachment-A" for permissible seat leakage values.XCR-100-101-102-103: 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))challenge to system safeguard protection which may result in a unit trip.The valves will be full stroke exercised at a cold shutdown frequency.

• Page 53 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:-12-5131-19

-Unit-2 Revision No: 2 Date: 8-31-87 NOTE 1'S-427S: This valve is in the emergency boration path.This valve is not normally operated at power because of the resulting large reactivity insertion.

The valve will be full stroke exercised at a cold shutdown frequency.

Page 54 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5136-25 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 55 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELlEF REQUEST NOTES Flow Diagram No: 12-5137A-21 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible-seat leakage values.NOTE 2: N-160: 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 indication.

This valve will be tested during seat leakage testing per Appendix"J" at-a refueling frequency.

Page 56 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5141C-8 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 57 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 12-5141F-6 Revision No: 2 Date: 8-31-87 NOTE 1: ECR-36: 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 a cold shutdown frequency.

NOTE 2: See"Attachment-A" for permissible leakage values.NOTE 3: SM-1: This containment isolation check valve for the containment radiation monitors'ample 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 tested during seat leakage testing per Appendix"J" at a refueling frequency.

Page 58 of 70 DONALD C.COOK AR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 ATTACHMENT-A Revision No: 2 Date: 8-31-87 1.CONTAINMENT ISOLATION VALVES Cate or 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.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 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A DA DA DA DA DA DA DA DA DA DA DA 900 900 900 900 900 900 900 900 900 900 900 Flow Permissible Leakage Diaciram Size~e Page 59 of 70

DONALD C.COOK N EAR PLANT ASME,SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 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 ECR-15,-25 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5141B 5141B 5141B 5141B 5141B 5141B 0'0 0'0 0.50 0.50 0.50 0.50 Flow Diaciram Size 5114A 3 DA DA DA DA DA DA DA DA DA GL GL GL GL GL GL Permissible Leakage 9 0 0 900 900 900 900 750 750 750 750 750 750 750 750 750 750 Page 60 of 70 DONALD C.COOK N EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT$2 ATTACHMENT-A

'Revision No: 2 Date: 8-31-87 Valve No.ECR-16,-2'6 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 CS-321 VCR-10,-11 Flow~Dia ram 5141B 5141B 5141B 5141B 5128A 5128A 5128A 5128A 5128A 5141F 5143 5128A 5128A 5129 5146B Size 0.50 0.50 0.50 0.50 0.75 GL GL GL GL CK CK CK CK CK CK CK CK CK CK DA Permissible Leakage 750 750 750 750 750 750 750 750 1200 750 750 750 900 1800 1200 Page 61 of 70 DONALD C.COOK EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.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 SF-152,-154 SF-159,-160 Flow Diaciram 5146B 5137A 5137A 5137A 5137A 5137A 5124 5129 5129A 5115A 5136 5137A Size ,4 2.50 2.50~Te DA DA, GL CK, DA DA DA DA DA GL GA DA DA, GL DA Permissible Leakage 1200 750 1125 750 750 1200 900 750 1200 750 750 900 Page 62 of 70 DONALD C.COOK EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 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)g Flow Diaciram 5141 5141 5141 5128A 5137A 5141 5141F 5142 5142 5141F 5120B 5120B 5128A 5143 Size 0.50 0.50 0.50 0.375 0'5 0.50~Te GL GL GL GL DA GL GL GL 0.75 DA GL 0'5,2 GL,DA GA(DD)*GA(DD)*~GL Permxsszble Leakage 750 750 750 750 750 750 750 600 600 750 750 750 375 375 Page 63 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.SI 171 I 172 I 194 Flov Diaciram 5143 Size 0.75~Te GL Permissible Leakage 1125 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 t g 5128A 5135 5135 5135 5147A 5142 5142 5145 5145 5147A 5135B 5135B GL 0'0 GL 0.50 0.50 0.50 GA(DD)*GA(DD)*CK CK ND CK CK 3 GL 2,2'0 GL,CK 2 GL 450 900 1125 750 750 600 600 750 750 750 750 750 Page 64 of 70 I'ONALD C.COOK LEAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No:-2 Date: 8-31-87 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 513'5B 5135B 5146B 5146B 5124 5141C 5141C 5141C 5141C Size 1'0 1.50 1.50 1.50 1.50 1.50 0.375 0.375 0'0 0.50 0.50 0.50 0.50~Te CK CK GL GL GL GL GL GL CK CK CK GL GL GL GL Permxsszble Leakage 750 750 375 375 375 375 375 375 750 750 750 750 375 375 375 Page 65 of 70 DONALD C.COOK LEAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT$2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 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 VCR-102,-202 5141C 5141F 5120B 5120B 5141D 5128A 5114A-5114A 5114A 5114A 5114A 5114A'114A 5114A 5147A 5147A.0.50 0.50 0.50 14 14 GL DA GA CK CK GL DA DA DA DA DA DA DA DA BF BF 375 375 375 750 750 375 1800 1800 1800 1800 1800 1800 1800 1800 4200 4200 Page 66 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.VCR-103,-203 VCR-104,-204 VCR-105,-205 VCR-106,-206 VCR-107,-207 Flow Diaciram 5147A 5147A 5147A 5147A 5147A Size 24 30 30 24 14 BF BF BF BF BF Permissible Leakage 7200 9000 9000 7200 4200 ICM-305 ICM-306 5143 5143 CCM 452 g 454 I 458 5135 CCM 45 1 I 453 I 459 5135*Double Discs 18 18 8,4,8 8,4,8 GA(DD)*GA(DD)*BF, GL, BF BF,GL,BF 2700 2700 3000 3000 Page 67 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 2.CONTAINMENT SPRAY VALVES Cata o A or AC Testing Method: As described in"SLT-2A," Figure 3.Valve No.CTS-131W CTS-131E CTS-127W CTS-127E RH-141 RH-142 Flow Diaciram 5144 5144 5144 5144 5144 5144 Size~Te CK CK CK CK CK CK Permissible Leakage 3'3 3.00 22.55 21.21 20.70 23.00 Page 68 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 3.PRESSURE ISOLATION VALVES Cata or A or AC Testing Method: (SLT-1)Seat leakage test the valve per ASME Code Section XI.Valve No.'CS-299E Flow~Dia ram 5129 Size~Te CK Permissible Leakage 2'CS-299W SI-152-N SI-152-S ICM-129 5129 5143 5143 5143 14 CK 2.0 CK 5.0 CK 5.0 GA(DD)*~~10.0 SI-161-Ll,-L4 SI-161-L2,-L3 SI-170-L1 SI-170-L2 SI-170-L3 SI-170-L4 SI-158-L1,-L4

• Double Discs 5143 5143 5143 5143 5143 5143 5143 10 10 10 10 CK CK CK CK CK CK CK 10.0 10'5'1.0 1.0 5.0 10'Page 69 of 70 DONALD C.COOK NUCLEAR P.ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.SI-158-L2,-L3 SI-151-E SI-151-N SI-166-L1 SI-166-L2 SI-166-L3 SI-166-L4 Flow~Dia ram 5143 5143 5143 5143 5143 5143 5143 Size 10 10 10 10 CK CK CK CK CK CK CK Permissible Leakage 10.0 5.0 5.0 5.0 5.0 5.0 5~0 RH-133,-134 5143 , 8 CK 1.0 Page 70 of 70

0 DONALD C.CCK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SRC1ARY SHEET-UihIT 2 SYSTEN=NAHE:

EHERGEHCY=DIESEI GENERATOR="CD"--

--=-FLOH-DIAGRAN:---2-51510-27 RUiH DATE AHD TINE: 14SEP87:13:28 VALVE-----=------I VALVE-POSITION I-=------ASNE-SECTION XI----.-I I NUi'GER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

=TYPE-COORD (-OPER----FUHCT---(CL--=----REQUIRED--PERFORHED--YiODE 2-SV-120-CD 0 RE L 0.25 SA H/2 C 0 3 A C TF1 TF-1 R HO 2-SV-139-CD-

--0=-REI==-D---SA---B/2 C=-0=---:-3-=-A.C=TF=.l-=TF-1 2-SV-61-CD 0 REL 1 SA A/8 C 0 3 A C TF-1 TF-1 2-SV-78-CD1 0 REL 1 SA E/3 C 0 3 A C TF1 TF-1 2"SV"78-CD2 0 REL 1 SA D/3 C 0 3 A C TF-1 TF"1 R HO 2-SV-79-CDI -REL=0.5-==SA E/1---C----=0------=-3-A-C=-==-TF=1=-

-TF-1---R---NO 2-SV-79-CD2 0 REL 0.5 SA E/1 C 0 3 A'TF-1 TF-1 R NO 2-XRV-225 0 GA 1 A B/3 C 0=3 A B EF-1 EF-1 EF-7 EF-7--ET-010----NOTE 3 P NO P NO-P----YES>NOTE 3--2-XRV-226 0 GL 3 A B/4 C 0 3 A B EF1 ET-010 EF-1 NOTE 3 P YESp NOTE 3 P YES>NOTE 3 2-XRV-227 0 GL A B/4 C 0 3 A B EF1 EF"1 P YES>NOTE 3---ET=010==--NOTE-3-P YES NOTE 3-

0~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU6)QSRY SHEET-UNIT 2 SYSTEMIZE:

EME RGENCY'DIESEL GENERATOR'!CD" FLOH DIAGRAM:.2=5151D"27 RUN DATE AND TIME: 14SEP87:13:28 VALVE---------=I VALVE POSITION I I I ASME SECTION XZ---HU66BER 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-DG-102C 1 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NOp NOTE 1 2=DG=104C~=.CK=1.5 SA...F/4 0 0/C 3 A C CF-1 CF-1 P.HO)NOTE 1 2-DG-128C 0 CK 1 SA C/3 C 0 3 A C CF1 CF-1 P HOp NOTE 1 2-DG-130C 0 CK 1 SA C/3 C 0 3 A C CF1 CF-1 P NOp NOTE 1 2-DG-132C 0 CK 3 SA B/4 C 03 A C CF-1 CF-1 P HOp NOTE 1 2<<DG-M4C===

-O==CK-~----SA--B/4--C--0 3 A C CF 1-CF 1 P-HOp NOTE 1=2-DG-140C 0 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF"1 2-DG" 142C 0 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1 P NO 2-GG-166C 0 CK 2 SA A/9 0 C 3 A C CF1 CF-1 P HOp HOTE 1 2"DG~2C-0--CK 4-.-.SA.D/9.-C-=--0=-3 A C=CF-1=CF-1.P HO NOTE 1 2-DG-154C 0 CK SA C/9 C 0 3 A C CF-1 CF-1 P NOp NOTE 1 2-QT-132-2CD 0 3H 6 SA E/8 0 0 3 A B EF"1 NOTE 1 P NO)NOTE 2

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHiNRY SHEET-UNIT 2 SYSTEH-NAHE:

-EHERGENCY=DIESEl GENERATOR=

-=--==FLOW-DZAGRAH:---2"515)C=26.

---

=RUN DATE ANO TINE:)4SEP87:)3:28 VALVE=---I-VALVE=POSITION-I-I I ASHE SECTION-XZ

---

MISER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF RWJEST(S)----------TYPE-COORDI-OPER-=

=FUNCT-=-ICL

---

REQUIRED

---

PERFORHED

--HODE-.2-OL-))4C 0 CK 1.5 SA B/9 0 C 3 A C CF1 CF-1 P NOp NOTE 1 5=01=116C 0-CK.M.5---56-0/9-0-0-A C.CF=)...CF-1 P-NOp NOTE 1 2" D L-132C 0 CK 1 SA F/9 0 C 3 A C CF-1 CF-1 P Nop NOTE 1 2-DL-158C 0 CK 6 SA G/5 C 0 3 A C CF-1 CF-1 NOp NOTE 1 2-QT-))6'p-2CD 0 3H 6 SA H/5 0 3 A B EF)NOTE 2 NOp NOTE 2 4

0 DONALD C.COCK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET-UNIT 2 SYSTEN-NANE:-=-ENERGEHCY-.DIESEI GENERATOR--------FLON DIAGRAtt:=-

2-51518"27

=RUN DATE AND TINE: 14SEP87)13:28

-VALVE-----=-=----=I-VALVE POSITION-I I I ASNE-SECTION XI HUYd)ER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I-OPER-FUNCT ICL.-REQUIRFD PERFORMED NODE 2-SV-120-AB 0 REL 0.25 SA G/2 C 0 3 A C TF1 TF-1 R NO 2-SV=139-.AB

-0=-REI.-1-.-.SA.B/2-C-0--3 A C-TF.-l--TF-1-R NO 2-SV-61-AB 0 RE L 1 SA A/8 C 0 3 A C TF-1 TF-1 2-SV"78"AB1 0 REL 1 SA E/3 C 0 3 A C TF1 TF-1 R HO 2-SV-78-AB2 0 REL 1 SA D/3 C 0 3 A C TF1 TF"1 2-SV-79-ABl REL-0.5---SA-: E/A---C==--0-====D--A=---C-===-TF-1--.-==-=TF"1 2-SV-79-AB2 0 REL 0.5 SA E/1 C 0 3 A C TF-1 TF"1 R NO 2-XRV"220 0 GA 1 A B/3 C 0 3 A B EF1 EF-7 ET-010 EF"1 EF-7 NOTE 3-P HO P NO P-YES>-NOTE 3----2-XRV"221 0 GL 3 A B/0 C 0 3 A B EF-1 ET-010 EF-1 HOTE.3 P NO P.YES>NOTE 3.2-XRV-222 0 GL A B/0 C 0 3 A B EF-1 EF-1 P NO--=--ET=010--=

==NOTE 3=-==P--YES>HOTE 3

.~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYttARY S)IEET-UiNIT 2 SYSTEN=NAME t-EHERGENCY-DIESEL-GENERATOR

---

=-FLOl$-DIAGRAN:-2-51518-27=-

RUN DATE AND TlttE: 14SEP87:13:28

--VALVE-I VALVE-POSITION-I

==------.--------ASIDE-SECTION XI---I I HmtBER REV TYPE SIZE ACT F.D I POHER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF RE(%EST(S).TYPE-COORDt OPER-=FUNCT-.ICL=.REQUIRED PERFORttED ttODE 2-DG-102A 0 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NO>NOTE 1 2=DG-.104A

-=0-.C~.S-=SA-G/4 0.--0/C 3 A C-CF=l-CF-1 P HO>NOTE 1 2-DG-128A 0 CK 1 2-DG-130A 0 CK 1 SA C/4 C SA C/4 C 0 0 A C CF1 A C CF-1 CF-1 CF-1 P NO>NOTE 1 P NO>NOTE 1 2-DG-132A 0 CK 3 SA B/4 C 3 A C CF-1 CF-1 P NO>HOTE 1 2.-DG-134A---

=0=---CK-- =SA B/4-C 0 3--A C---CF 1-CF-1--P-HO>NOTE 1-2 DG 140A 0 CK 0 5 SA F/1 C 0/C 3 A C CF 1 CF"1 P NO 2-DG-142A 0 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1 P HO 2-DG>>146A 0 CK 2 SA A/8 0 C A C CF1 CF-1 P NO>HOTE 1 2=DG~2A=-=.0-CK==4=-=SA 0/8=--C'0==-3-A C.CF-.1.CF-1 P=t40>HOTE 1-2-DG-154A 0 CK 4 SA C/8 C 0 A C CF 1 CF-1 P HO>NOTE 1 2-QT" 132-2AB 0 3H 6 SA E/8 0 0 A B EF1 NOTE 2 P NO>NOTE 2

e DONALD C COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU%>ARY SHEET-UNIT 2 SYSTEN-NANE:

-ENERGEHCY-DIESEL-.GENERATOR=-

---

FLOH-DIAGRAN: 5151A-26 RUH DATE AND TINE: 14SEP87:13:28

--VALVE-=------=--==-I.VALVE POSITION-I----=-=-----..---.=-.=ASNE SECTION XI-I I NUHBER REV TYPE SIZE ACT F~D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI OPER--FUST-=ICI--=-===-REQUIRED

---

PERFORNED-NODE 2-DF-108A 0 CK 1.5 SA L/3 C 0 3 A C CF-1 CF-1 P HO)HOTE 1 2=DF=109A=O CK.=1.5 SA K/3-C.0 A C.CF-1.CF=1 P NO>HOTE 3.2-DF-114A 0 CK 1.5 SA J/3 C 0 3 A C CF1 CF-1 HO)NOTE 1 2-DF-115A 0 CK 1.5 SA N/3 C 0 3 A C CF1 CF"1 HO>NOTE 1 2-DL-114A 0 CK 1.5 SA B/9 0 C 3 A C CF-1 CF-)NOp NOTE 1 2-DL-116A-0--CK.--~.5---SA--B/9---C-----0.------3---A-C.--CF-1---.---.CF-1 P-NO>NOTE-1-2-D L-132A 0 CK 1 SA F/9 0 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-DL-158A 0 CK 6 SA G/6 C 0 3 A C CF1 CF-1 P NO>HOTE 1 2-QT-114-2AB 0 3H 6 SA H/5 0 0 A B EF-1 NOTE 2 P NO>HOTE 2

DONALD C.COOK tmCLEAR PLANT SECOND TEtf YEAR INTERVAL VALVE SUGARY SHEET-UNi IT 2 SYSTEH-NAHE:=CONTROL=ROOM-VENTILATION

-=----==-FLOH=DIAGRAN:-2-5149-23-=---RUN DATE AND TZttE: 14SEP87:13:28 VALVE-=-----I VALVE-POSITION-I-I I=ASttE SECTION-Xl=

NUttBER REV TYPE SIZE ACT F AD I POttER SAFETY LCD A/P CAT PRItt TEST TEST TEST RELZEF REQUEST(S)-TYPE-COORD I OPER--FU'tCT-ICL----REQUIRED---PERFORNED l%DE-2-DH-163-N 0 GA 2.5 H F/2 0 0/C 3 A B EF-1 EF-1 P NO 2-.DH-163-S=

--0-=GA---2.5--.-tt--G/2-=-=0 0/C==--M-A-B..-EF-1--------EF-1 2-DH-166-N 0 GA 2.5 H E/5 0 0/C 3 A B EF"1 EF-1 2-DH-166-S 0 GA 2.5 t 1 J/5 0 0/C 3 A B EF-1 EF-1 2"VRV-315 0'H 2.5 A F/5 0 0 A B EF-1 EF-7 ET-NA EF"1 EF-7 NOTE 1 P P HOp NOTE 1 NO>NOTE 1 YES>NOTE 1 2-VRV-325 0 3H 2.5 A G/5 0 0 A B EF1 EF"1.EF-7 EF"7 ET-NA---NOTE 1 P P NO>HOTE 1 NO>HOTE 1.YES>-NOTE 1

~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUt0tARY SHEET-UNIT 2 SYSTEN-NAtfEt

-CONTAZHNEHT-.VENTILATION-

---

=-FLOH-DZAGRAtt: 5147A-35--

--RUH DATE AND TZt<E 14SEP87: 13: 28 VALVE-=-=-===-=-I VALVE-POSITION=I

--====-===----ASHE SECTION XI I I NEWER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT-TYPE-COORDI OPER--FUttCT-ICL----PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED---PERFORHED-

==-ttODE------=-2-VCR-203 0 BF 24 A J/5 C C 2 P A EF-1 EF-5 EF-7.ET-005=SLT-1 EF-)EF-5 EF-7 ET-005 SLT-2 P-P R NO HO HO NO-YES>NOTE 1 2-VCR-204--0=BF=-==30

=---=A--J/6=-C-2--P=A EF-1---EF"5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET"005 SLT-2 P HO HO P HO P HO R YES, NaTE 1 2-VCR-205 0 BF 30 A J/3 C C 2 P A EF-1=EF-5=EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P ttO P HO R YESJ NOTE 1 2-VCR-206 0 BF 24 A J/3 C 2 P A EF-1 EF-5 EF-7 ET"005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO HO HO-HO YES>HOTE 1 2-VCR-207 0 BF 14 J/4 0/C C 2 A A EF-1 EF-5 EF-7-ET-005=SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P HO P.--HO R YESp NOTE 1

0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ZNTERVAL VALVE SUiiARY SHEET-UNIT 2 SYSTEtt-NAttE:=-COWTADNENT-VENTILATION-

---

=-=FLS'I DIAGRAN:-2-5147A-35 RUH DATE AHD TINE: 14SEP87:13:28

=-VALVE---=-----=-==I=VALVE-POSITION-I I I HUYBER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT-TYPE COORD l=-OPER-FUHCT-I CL-=--ASME SECTION XZ--PRIN TEST TEST TEST RELIEF RECQEST(S)

RE@GRED-PERFORHED--tfODE 2-VCR-105 0 BF 30 A J/3 C C 2 P A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7.ET-005 SLT-2 P P P R NO HO HO tiO YESp ROTE 1 2-VCR-106-0-==BF-=-24---=-A---J/3---C--=---C--==-=-2--P-A---EF-I, EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R I')O-NO tiO HO YES>NOTE 1 2-VCR"107 0 BF 14 A J/4 0/C C 2 A A EF-1 EF-5---EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO-HO HO N)YES>NOTE 1 2-VCR-201 0 BF 14 A J/8 C 2 P A EF-1 EF"5.EF-7 ET-005 SLT-1 EF-1 EF-5---EF-7 ET-005 SLT-2 P P R HO HO NO t$0 YES>NOTE 1 2-VCR-202 0 BF 14 A J/9 C C 2 P A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7=-=ET-005-SLT-2 P P=--R HO HO HO-HO-YESp NOTE 1 DOttALD C.COO<AD NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE

SUMMARY

SflEET-UNIT 2 SYSTEM NAME'COHTAINtENT VENTILATIOH

==.FLOH..DIAGRAM:

2=514?A-35 RUH DATE AHD TIHE: 14SEP87:13:28 VALVE---..-=-==-I-.VALVE-POSITION I I I NUt'GER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE-COORDI-OPER--

-FUNCT-ICL==--ASME SECTION.XI--PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED.PERFORHED=MODE 2-SH-10 0 GA 0.5 H A/4 C C 2 P A SLT-1 SLT-2 R YES NOTE 1 2=SM=4=-==O=GA=0.5 H=A/2=C..C.=2 P A SLT=l.SLT"2 R.=YES>NOTE 1 2-SH-6 0 GA 0.5 M A/2 C C 2 P A SLT-1 SLT-2 YES>NOTE 1 2-SH"8 0 GA 0.5 H A/4 C C 2 P A SLT-1 SLT-2 YES>NOTE 1 2-VCR-101 0 BF 14 A J/8 C 2 P A EF"1 EF"5 EF"7-ET-005--SLT-1 EF-1 EF-5 EF-7-ET-005-SLT 2 P-P=-R HO NO NO-NO YES>HOTE 1 2=VCR".102==0=BF=== ==-A--J/9 C C.2 P.A EF-1 EF-5 EF-7 ET-005-SLT-1-EF-1=EF-5 EF-7 ET-005 SLT-2-P P=-R HO NO NO NO-.YES'.HOTE 1-----2-VCR-103 0 BF 24 A J/5 C 2 P A EF-1-EF-5--==--EF-7 ET-005 SLT-1 EF-1 EF"-5----EF-7 ET-005 SLT-2 P NO HO P NO P NO R YES>NOTE 1 2-VCR-104 0 BF 30 A J/6 C C 2 P A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7 ET-004 SLT-2 P NO NO P HO P HO R YES>HOTE 1

DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR INTERVAL VALVE SUiiu ARY SHEET-LAIT 2 SYSTEM-NAttE:

-ICE-CONDENSER REFRIGERATIOH

=,.=FLON DIAGRAM:.2=5146B=23 RUH DATE AHD TIMiE: 14SEP87:13:28-VALVE===---=---I=VALVE-POSITION I I I HUMBER REV TYPE SIZE ACT F.D I POttER SAFETY I CD A/P CAT TYPE COORDI OPER FUNCT ICL.-ASitE SECTION.XI.PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED.NODE.2-R-156 2 CK 0.375 SA L/4 C 0/C 2 A AC CF-1 SLT-1 CF-1 SLT-2 R YES>NOTE 1 R YES>HOTE 2 2"R-157 2 CK 0.375 SA L/6 C 0/C 2 A AC CF-1 SLT-1 CF-1 SLT-2 R YES>NOTE 1 R YES>HOTE 2 2-VCR-10 0 DA 4 A M/5 0 C 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF"5 EF-7 ET"005 SLT"2 P P R HO NO ttO NO YES>NOTE 2 2=VCIL11 O=DA==4=A L/5 0 C-.2.A A=EF=l EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-.2 P P R NO NO HO HO YES>NOTE 2 2-VCR-20 0 DA A tt/7 0 2 A A EF-1-EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO NO NO NO YES>NOTE 2 2-VCR-21 0 DA 4 A L/7 0 2 A A EF-1 EF-5 EF"7-ET-006 SLT-1 EF"1 EF-5 EF=7 ET-006 SLT-2 P P P R NO HO NO NO YES>NOTE 2

.

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUN1ARY SHEET-UNIT 2 SYSTEM-NAME:

-CPN/MELD..CHANNEL PRESSURIZATION.=

-=--FLIC DIAGRAM:=2-5145"20.

=-=-==RUN DATE AND TIME: 14SEPB7:15:28

--VALVE---=-=-==-----I-VALVE POSITION I-I I ASME SECTION-XI NU1$ER 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-CA-181-N 0 CK 0.5 SA F/2 C 2 P AC SLT-1 SLT"2 R YES)NOTE 1 2"-CA&81-.S===O----CK--=.0.5--=---SA-F/5 C--=C-.2--P=AC-SLT=1---SLT-2-R YES)NOTE 1 4

0~DOHALD C.COOK NUCLEAR PLAttT SECOM)TEtt YEAR INTERVAL VALVE SCD)ARY SHEET-UtlZT 2 SYSTEM-NAME:

-.CONTAINtlENT--SPRAY,=FLOH DIAGRAM: 2-5144-29 RUH DATE AND TIME: 14SEP87:13:28 VALVE=-------=.-=-I VALVE POSZTZ(N-I---

I I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F 0 l POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI.OPER FUNCT--ICL.--REQUIRED.PERFORl'lED MODE 2-IMO-221 0 GA 10 MO L/8 C 0 2 A B EF1 EF-5 ET-066 EF-1 EF"5 ET-066 P P HO NO NO 2-ZtlO-222 0 GA 2 MO L/9 0 0/C 2 A B EF-1 EF-1 EF-5 EF-5 ET-030---ET-030 P NO NO P--HO 2-ZMO-225 0 GA 12 MO J/9 0 0/C 2 A B EF-1 EF-1 EF=5-EF"5 ET-074 ET-074 P NO NO P NO 2=RH"..141

==0 CK-.8.SA E/3-C.--0=-2 A AC.CF-1 CF-2 SLT-1 SLT-2A R R YES>-NOTE 2.--.-YES>NOTE 3 2=RH=142----0 CK 8..SA E/3 C 0.2.A AC=CF-1 SLT-1 CF-2 SLT-2A R YESi NOTE 2 R YESp HOTE 3 2=SV=107-0=REL=1--=SA-=-H/5 C---0:==2-A-C---.-TF"1---=-=-=TF=l=-R-NO SYSTEH NAttE: CONTAIHtL~tfT=SPRAY DONALD C.COOK NUCLEAR PLANT RUN DATE AND TINE: SECOND TEN YEAR INTERVAL VALVE SL?AAARY SttEET-UNIT 2 FLO'A DIAGRAtt:-2=5144-29..14SE P87: 13: 28 VALVF I VALVE POSITION I I I ASttE SECTION XI NlÃKER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE-.COORDI-OPER

-.FUHCT=ICL.=.REQUIRED.PERFORttED NODE 2-CTS-138-N 2 CK 12 SA J/9 C 0/C 2 A C CF-1 CF-3 YESp NOTE 1 2550=202 0 GA=2.5 HO-5/?=-C.=..-

0=,.--2.A=B EFM EF-5 ET-018 EF-1 EF-5 ET-018-NO HO HO 2-IttO-204 0 GA 2.5 ttO H/7 C 0 2 A B EF-1 EF-5 ET-018 EF-1 EF-5 ET-018 P HO HO P HO 2-Zt jO-210 0 GA 10 N80 J/8 C 0 2 A B EF-1 EF-5 ET-066 EF-1 P HO EF-5 tiO ET-066=P NO 2-It'.0-211 0 GA 10 NO J/8 C 0 2 A B E F-1 EF-1 EF-5..EF-5: ET-065 ET-065 P HO HO=P HO~50=212 0 GA.2----.--HO--H/8--0--0/0=--2=A-5 2?=1 EF-5 ET-033 EF>>l.P NO EF-5 HO ET-033 P HO 2-ZttO-215 0 GA 12 NO G/9 0 0/C 2 A B EF-1 EF-5 ET-074 EF-1 EF-5 ET-074 NO NO HO 2-INO-220 0 GA 10 HO L/8 C 0 2 A B EF1 EF-5 ET=065.EF-1 EF-5 ET-065 NO HO NO 08 0

SYSTEM-NAME:

-CONTAINMENT-SPRAY DONALD C.COOK NUCLEAR PLANT SECOND TEth YEAR INTERVAL VALVE SEC)ARY SHEET-UNIT 2 FLON=DIAGRAM: 2-5144"29 RW DATE AND TIME: 14SEP87:13:28 VALVE=I-VALVE-POSZTZON

-I I I---=ASME SECTIOLN XZ NUMBER REV TYPE SIZE ACT F~D I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-=COORDI-OPER

---FUHCT---ICL

---

=-REQUIRED

---PERFORMED=----.

MODE 2-CTS-103-E 2 CK 10 SA J/9 C 0 2 A C CF-1 CF-3 YES>NOTE 1 2=CTS=103=M=2 CK 10.SA L/9-C.0..=2==-A-C.CF-l.CF"3.=.YES'OTE 1 2-CTS-109 0 VB 1 SA M/6 C 0 2 A C TF"1 TF-1 2-CTS-110 0 VB 1 SA tt/6 C 0 2 A C TF-1 TF-1 2-CTS-120-E 0 CK 2 SA H/8 C 0 2 A C CF-1 CF-1 P NO 2=CTS=120=H 0-CK-2=-=SA K/8-C--0--.2.A-.C..--CF-1--CF"1.2-CTS-127-E 0 CK 6 SA E/5 C 0 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YES>NOTE 2 R YES>ttOTE 3 2-CTS-127-N 0 CK 6 SA E/4.C 0 2 A AC CF-1 CF"2 SLT-1---=-SLT-2A.-R YES>NOTE 2--R YES>NOTE 3 2-CTS-131-E 0 CK 8 SA-E/2 C 0 2 A AC CF1 SLT=1 CF-2 SLT-2A R YES>NOTE 2 R YES>ttOTE 3 2-CTS-131-N 0 CK 8 SA E/2 C 2 A AC CF-1 CF-2=R YES>N)TE 2 SLT-1-SLT-.2A R-YES>NOTE 3 2-CTS" 138-E 2 CK 12 SA G/9 C 0/C 2 A C CF-1 CF-3 YESy NOTE 1

e~DOHALD C.COOX NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHi1ARY SHEET-UNIT 2 SYSTEN-HAl5E:

-EHERGEHCY=CORE-COOLING RHR---=-=--FLOH-DZAGRAN:-

2-5143 RUiH DATE AHD TZHE: 14SEP87:13:28

.0-VALVE I-VALVE-POSITZOH-I I I ASME SECTION Xl HUi'iDER REV TYPE SZZE ACT F.D I POHER SAFETY ICD A/P CAT PRZN TEST TEST TEST RELIEF REQUEST(S)

---

=TYPE COORDI OPER-FUHCT-.-ICL---REQUZRED PERFORHED---NODE 2-SV-100"3 0 REL 1 SA 0/1 C 0 2 A C TF-1 TF-1 2-SV-100-4=

--0--REI~---.SA-D/1-C=0 2 A-C.-TF-1 TF-1 2-SV-102 0 , REL 0.75 SA E/5 C 0 2 A C TF1 TF-1 2-SV-103 0 REL 3 SA F/8 C 0 2 A C TF-1 Tf-1 2-SV-104E 0 RE L 2 SA G/4 C 0 2 A C TF-1 TF"1 R HO 2=SV-104H-0-=-REI 2.------SA-K/4-C------0----2-A--C----TF"1-----TF-1 R HO-2-SV-105E 0 REL 2 SA D/9 C 0 2 A C TF-1 TF-1 2-SV-105H 0 REL 2 SA D/9 C 0 2 A C TF-1 TF-1

=0 0 DONALD C COOK NUCLEAR PLANT SECOHD TEN YFAR INTERVAL VALVE SU)0)ARY SHEET-UNIT 2 SYSTEN-HANE:

-ENERGENCY-CORE-COOLING RHR-=-----.--==FLON DIAGRAN:=--2-5143-35=

RUH DATE AND TINE: 14SEP87:13:28 VALVE--I-VALVE POSITZOH-I-I I-ASNE SECTION-Xl

--NUiE)ER REV TYPE SIZE ACT F.D.I PINER SAFETY ICD A/P CAT PRZH TEST TEST---------TYPE-COORDI OPER--FUiiCT-ICL-------REQUIRED---PERFORNED TEST RELIE F REQUEST(S)

NODE.2-SZ-166-L4 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF"2 SLT-1 R YESp NOTE 5 R NO>NOTE 1 2-SI-170-Ll 2 CK 10 SA A/4 C 0 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>HOTE 13 N)p NOTE 1 2-SI-170-L2 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>HOTE 13 NO>NOTE 1 2-SI-170-L3 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>NOTE 13 HO>NOTE 1 2"SI-170-L4 2 CK 10 SA A/4 C 0 1 A AC CF-1 SLT-1 CF-3 SLT-1 R YES>HOTE 13 R NOp NOTE 1 2-SI-171 0 GL 0'5 N H/6 C C 2 P A SLT-1 SLT-2 R YES, HOTE 1 2-Sj-172-0-GL-0..75-ii-H/6 C.C 2-P=-A--SLT-1--SLT-2 R-YES NOTE 1 2-SI-194 0 GL 0.75 N G/6 C C 2 P A SLT-1 SLT-2 R YES>NOTE 1 2-SV-100-1 0 REL 1 SA 0/1 C 0 2 A C TF1 TF-1 R NO 2-SV-100-2 0 REL 1 SA D/1 C 0 2 A C TF-1 TF-1 e

0 DONALD C.COOK ttUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2 SYSTEtt NAt1E:-EMERGENCY=CORE COOLItlG-RtlR=..FLOH DIAGRAM:-2-5143-35 RUH DATE AND TIME: 14SEP87:13:28 VALVE-=----------I-VALVF-POSITION-I--=---.-------ASME SECTION XZ--I I NRRER REV TYPE SIZE ACT F.D.I POttER TYPE COORDI OPER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

FUNCT.ICL-=-REQUIRED--PERFORMED.-MODE 2-SZ-158-L3 0 CK 6 SA B/7 C A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 12 R ttO>NOTE 1 2-SZ-158-L4 0 CK 6 SA B/7 C 0 1 A AC CF-1 SLT"1 CF-2 SLT-1 C YES>HOTE 12 R HO>NOTE 1 2-SI-161-L1 0 CK 6 SA B/6 C 0 1 A AC CF-1 CF-2 C YES>HOTE 6 SLT-1 SLT-1 R HOp HOTE 1 2-SZ-161-L2 0 CK 6 SA B/5 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 6 R NOp NOTE 1 2-SI-161-L3 0 CK 6 SA B/5 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YESp NOTE 6 R NOp HOTE 1 2-SI-161-L4 0 CK 6 SA B/6 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 6 R NOp NOTE 1 2-SI-166-L1 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF"2 SLT-1 R YES>NOTE 5 R NO NOTE 1 2-SZ-166-L2 0 CK 10 SA C/4 C 0 A AC CF-1 SLT-1 CF-2 SLT-1 R R YESp HOTE 5 NOp NOTE 1 2-SI-166-L3 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 5 R t<0>NOTE 1

~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sinai HARY SHEET-UiHIT 2 SYSTEM-HAME' EMERGENCY CORE-COOLING.=

RHR=..=,FLOH DZAGPJtH:=-2-.5103=35=

RUiH DATE AHD TIME: lOSEP87:13:28 VALVE-=-=---I-VALVE-POSITION-I-I I ASME-SECTION.XZ HU953ER REV TYPE SIZE ACT F~D I PS'(ER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

---=TYPE-COORDI.OPER-

=--FUHCT==ICL-=-=-

-..--.REQUIRED

-=PERFORMED-MODE--2-RH-108M 0 CK 8 SA N/9 C 0 2 A C CF-1 CF-3 C HOp NOTE 7 2=RH=133------O=.CK 8-..=.SA.C/5 C.C..=-=1..P AC.CF=1--CF-2 SLT-1 SLT-1.C.YES NOTE 8 R HOp NOTE 1 2-RH-134===-0=-CK--8=-=-SA--C/5 C-.-.C-------1-P-AC--CF-I=----CF-2 SLT-1 SLT-1 C--YESp-NOTE 8--R HOp NOTE 1 222SL=108 2 C~R GA-G/F-=C-.-0 2 A.--C-.CF-2=-CF-3.-.-.--YEG.EGYE 9.2-SZ-151-E 0 CK 8 SA D/7 C 0 2 A AC CF 1 CF-2--.-=-SLT-1.---.SLT-1 C YESp NOTE 10 R-=-HOp.NOTE 1 2-SI-151-W 0 CK 8 SA D/7 C 0 2 A AC CF1 CF-2 SLT-1---=SLT-1 C YESp NOTE 10 R-HOp NOTE 1 2"SZ-152-N 0 CK SA 0/8 C 0 2 A AC CF-1 CF-2 SLT-L=SLT-1 R YESp NOTE ll==R=-=--NOp NOTE 1-2"SI-152-S 0 CK SA 0/7 C 0 2 A AC CF-1 SLT.-1 CF-2 R YESp NOTE ll SLT-1=.R.==HOp NOTE 1 2-SZ-158-Ll 0 CK 6 SA B/8 C 0 1 A AC CF-1 CF-2 C YESp NOTE 12-----SLT-1==--=

-SLT-1----R---HOp NOTE--1.2-SI-158-L2 0 CK 6 SA B/7 C 0 1 A AC CF-1 CF-2 SLT-1.-=SLT-1 C YESp NOTE 12 R.HOp.HOTE 1 0

~~DONALD C.COOK HUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUt0tARY SHEET" UtGT 2 SYSTEM-NAME-'

EMERGENCY-CORE-COOLING=

RHR====FLOH-DIAGRAM:

-2"5143-.35

-==--.RUN DATE AND TIME: 14SEP87:13:28 VALVE=-t-VALVE-POSITION-I-I 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"ZMO-325 0 GA 8 MO C/7 C C/0 1 A B EF"1 EF-5 ET-028 EF-2 EF-5 ET-028 C YESF HOTE 4 NO C HO 2"ZMO-326 0 GA 8 MO C/7 0 0/C 2 A B EF1 EF-2 EF-5 EF-5-ET-028-=-=---ET-028-C YES>NOTE 4 NO C NO 2-Z MAO"330 0 GA 8 MO G/4 C 0 A B EF1 EF-1 EF"5 EF.-5 ET-053 ET-053 P NO NO P HO 5=150-551.0 GA.5-.MO 1/5 C..0--E..A-5 EF-1-.EF-1---.P-NO EF-5 EF-5 NO ET" 051 ET-051 P HO 2"Zt'0-340 0 GA 8 MO H/5 C 0 2 A B EF-1 EF"5 ET-015 EF-1 EF-5 ET-015 P NO HO P HO 2-IMO-350 0 GA 8 MO L/5 C 0 B EF-1 EF-5 ET-015 EF-1 EF-5 ET=015 P HO HO.P HO 2-H-102 2 CK 1 SA F/5 0/C C 2 A AC CF-1 CF-2 R YESP NOTE 14 SLT-1-SLT-2-----R YESP NOTE 1--2-RH-108E 0 CK 8 SA K/9 C 0 2 A C CF1 CF-3 C HOP NOTE 7

0..~DONALD C.COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SU@DRY SHEET-UNIT 2 SYSTEN-NA)K'EMERGENCY=CORE COOLING" RHR---FLOH DIAGRAM: 2"5143"35 RUN DATE AND TIME: 14SEP87:13:28 VALVE--=--

---

I VALVE-POSITION-I

-=--=-=.ASME SECTION XZ-I I NASSER REV TYPE SIZE ACT F.D.I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER-.FUiiCT ICL RE@IZRED-PERFORMED-MiODE 2-IMiO-312 0 GL 2 MO J/5 0 0/C 2 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P NO HO P NO 2-ZMO-314 0 GA 8 MO K/6 0 0/C 2 A B EF"1 EF-5-ET-034 EF-1 EF-5 ET"034 P NO NO=P==--HOp HOTE-3 2-ZMO-315 0 GA 8 MO C/7 C C/0 1 A B EF-1 EF-2=EF=5.--EF=5 ET-033 ET-033 C YES'OTE 4 HO C HO 2=ZMO=316.

-.0-=-GA---8=.-MO-C/7-0.-.-0/C--2 A B EF-1====-EF"2..--C=-YES>HOTE-4 f F-5 EF-5 HO ET-033 ET"033 C NO 2-IMiO-320 0 GA 14 MiO" L/9 0 0/C 2 A B EF-1 EF-5 ET-128 EF-1 EF-5 ET-128 HO NO HOp NOTE 3 2-ZMO-322 0 GL 2 MO M/5 0 0/C 2 A B EF-1 EF"1 EF-5 EF"5 ET-011..ET-Oll P HO NO P HO 2-ZMO-324 0 GA 8 MO M/6 0 0/C 2 A B EF1 EF-5=ET-035 EF-1 P EF-5-ET-035 P NO HO=HOp NOTE 3 0 DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU)C)ARY SHEET-UNIT 2 SYSTEMIZE EMERGENCY CORE COOLING=RHR====FLON DIAGRAlk:~143."35 RUH DATE AND TIMiE: 14SEP87:13:28 VALVE=.I.VALVE.POSITION I I I HUtiBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT=ICL=ASME SECTION XI PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-GCR-314 0 GL 1 A G/2 0 2 A EF-1 EF-5 EF-7 ET=003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P NO HO P HO P HO R YES>ti'OTE 1 LCM=129 2 GA 14=MO E/8 1==-P--A=EF-1-EF-5 ET-121 SLT-1 EF-2=EF"5 ET"121 SLT"1=YES>NOTE 2 HO HO R HOp NOTE 1 2-ICM-305 0 GA 18 MO D/9 C 0 2 A A EF-1 EF-1 EF-5 EF-5 ET=049..=ET-049 SLT-)SLT-2 P NO tR P HO R YES>NOTE~CM=306--O=GA.=-18.MO.=D/9 C===0 2 A A EF=l EF-5 ET-049 SLT-1 EF-1 EF-5 ET-049 SLT-2 P HO NO P HO R YES'OTE 1 2-IMiO-128 2 GA 14 MO B/8 C 1 P B EF-1 EF"2 EF"5 EF-5 ET=134 ET"134 YES>NOTE 2 HO HO 2-IMO-310 0 GA 14 MO M/9 0 0/C 2 A B EF-1 f F-1 EF=5..EF=5 ET-148 ET-148 P NO HO P ttO~NOTE 3

0..0 DONALD C.COOK NUCLEAR PLANT SECOHD TEH YEAR INTERVAL VALVE SVYd&RY SHEET-UNIT 2 SYSTEM-NAME:

-EMERGENCY-CORE-COOLIHG=

SZS=.==FLON DIAGRAM:-2=5142-28 RUN DATE AHD TIME: 14SEP87:13:28 VALVE=-.---.--I-.VALVE POSITION-I--

I I=ASMEMECTION XZ HUM8ER 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-SI-142" L3 0 CK 1.5 SA C/2 C 0 1 A C CF-1 CF-2 R YES1 NOTE 6~~42=L4 0=CK M.5==SA.=C/1 C.0 1=A=C CF-1 CF-2 R YES>NOTE 6 2"SV-96 0 REL 0.75 SA J/8 C 0 2 A C TF-1 TF-1.R HO 2-SV-97 0 REL 0.75 SA J/4 C 0 2 A C TF"1 TF-1 R HO 2"SV-98-N 0 REL 0.75 SA C/9 C 0 2 A C TF-1 TF-1 HO~VM8-S 0.--REL=0.75 SA-E/8 C=-0==-2 A C-TF-1 TF-L=R NO DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SV>SORY SHEET-UNIT 2 SYSTEN-NAHE:=EHERGENCY-CORE COOLING-=SZS-=-FLON DZAGSN:=2-5142=28.=.

RUiN DATE AND TZHiE: 14SEP87:13:28 PEEVE=----l SAEVA POSITIiil I---.---ASEENESTIii.XI I I NASSER REV TYPE SIZE ACT F~D I POHER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

TYPE=COORD I OPER-RLCT I CL--.REQUIRED-..PERFORHED NODE 2-IRV-252 0 GL 1 A J/5 0 3 A B EF-1 EF"1 EF-5 EF-5 EF-7 EF-7 ET=.005---.ET-005 P P NO NO NO NO 2-IRV-255 0 GL 1 A H/6 0 2 A B EF1 EF-1---EF-5--=-=--EF--5-EF-7 EF-7 ET-004 ET"004 P NO W-P NO P NO 2-SZ-101 0 CK 8 SA H/8 C 0 2 A C CF-1 CF-3 R YESE NOTE 5 2-S1-104-N=O~K=-0..75=SA

-E/9--=C--=---0--.--2-=A=C--CF-1=--=--.CF-1-=.---P.N)-2-SZ-104-S 0 CK 0.75 SA J/9 C 0 2 A C CF-1 CF-1 P NO 2-SI-110-N 0 CK SA E/9 C 0 2 A C CF-1 CF-2 R YESP NOTE 5 2-SI-110-S 0 CK SA H/9 C 0 2 A C CF-1 CF-2 R YESS NOTE 5 2=S~26-----0=-CK==~--SA-H/6=0-C 2 A-C=-CF=i===CF-1=P NO 2-SI-142-L1 0 CK 1.5 SA C/1 C 0 1 A C CF-1 CF-2 R YES>N)TE 6 2-SI-142-L2 0 CK 1.5 SA C/2 C 0 1 A C CF-1 CF-2 R YES>NOTE 6

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUY!CRY SHEET" UiHIT 2 SYSTEM=NAME

=-EMERGENCY-CORE=-COOLING-SIS--=-=-

-FLOH-DIAGRAM:=-2-5142-28----

RUH DATE AHD TIME: 14SEP87:13:28 VALVE===---==---I=VALVE POSITXON I-I I AStiE-SECTION-XZ NUiiBER REV TYPE SIZE ACT F.D.I POWDER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

--TYPE-COORD I-OPER.FUii'CT--ICL--=------REQUIRED PERFORMED..-MODE 2-IMO-262 0 GL M0 L/8 0 0/C 2 A B EF-1 EF-5 ET-012 EF-2 Ef-5 ET-012 YES>NOTE 4 NO NO 2-ZMiO-263 0 GL 2 MO L/8 0 0/C 2 A B EF-1 EF-5=ET-012 EF-2 EF-5 ET-012-C YESp NOTE 4 NO C-NO 2-ZMiO-270 0 GA 4 MO E/9 0 0/C 2 A B EF"1 EF-1 P NO EF"5 EF-5=..-=-HO ET-024 ET-024 P HO 2=Z)0=275=0-GA-4.-----MiO-.E/8 0--=-0/C---2-A--B--=EF-1-----EF-5 ET-020 Ef-1 EF-5 ET-020 NO HO NO 2-ZMO-361 0 GA 4 MO G/9 C C/0 2 A EF-1 EF-5 ET"009 EF-1 EF-5 ET-009 2-ZMO-362 0 GA 4N)G/9 C C/0 2 A B EF-1 EF-5-.---ET-009 EF-)EF-5 ET-009.=NO NO-NO 2-IRV-251 0 GL 1 A H/5 0 2 A EF-1 EF-5--=---EF-7 ET-004 EF-1 P-EF-5---------EF-7 P ET-004 P

DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE StRQARY SHEET-UNIT 2 SYSTEM-NAME:=EMERGEHCY-CORE--COOLING=-SZS--

---FLON-DZAGRAM:

2-5142-28=.RUN DATE AHD TIME: 14SEP87:13:28 VALVE I--VALVE-POSITION-I-=----------=-=--A%1E SECTION XZ-I I HOSER REV TYPE SIZE ACT F AD.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

--TYPE-COORDI-OPER

---

FUui:T

--ICL------REQUIRED.

-PERFORMED..

MODE 2-ICM-250 0 GA H/2 C 0/C 2 A A EF-1 EF-5 ET-012 SLT-1=.EF-2 EF-5 ET-012 SLT-2 C C R YESp NOTE NO NO-YES>=NOTE 2-ZCM"251 0 GA MO H/3 C 0/C 2 A A EF-1 EF-2 C YES>NOTE 1 EF-5-.-==---EF-5----==-.-=-=-=-NO ET-012 ET-012 C HO SLT-1 SLT-2 R YES@NOTE 2"ZCM-260 0 GA 4 MO C/9 0 0/C 2 A A EF-1 EF-5 ET-012 SLT-l...EF-1 EF-5 ET-012.SLT-2 P HO NO P HO R--YES>NOTE 2 2-ICM"265 0 GA MO C/8 0 0/C 2 A A EF-1-EF=5-----ET-012 SLT"1 EF-1 E F--5-=----ET-012 SLT"2 P NO-=---HO=P NO R YES>NOTE 2 2-IMO-255 0 GA MO J/7 C 0 2 A 8 EF-1 EF-5 ET-015 EF-1 EF-5 ET-015 P NO HO P HO 2-IMO"256 0 GA 4 MO J/6 C 0 2 A B EF-1 EF-1 P HO EF-5 EF"5 HO ET-012-=-ET-012----==-=P=-NO-2-IMO-261 0 GA 8 MO M/8 0 0/C 2 A B EF-1 EF"2 C YES>HOTE 3 E F-5----=--E F-5-=-.------NO=--ET-015 ET-015 C HO e

~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUt%JARY SHEET-UtlIT 2 SYSTEH-NAHE:

-PAS-CONTAItCiEttT-.HYDROGEN--===

---

=--FLON DIAGRAH:--2-5141D-8

---

RUiil DATE AND TIHiE: 14SEP87:1'5:28 VALVE-=--=-------I-VALVE-POSITION-I---..---------ASt4E-SECTION XI I I NJJEJER REV TYPE SIZE ACT F.D~I PONER SAFETY I CD A/P CAT PRItl TEST TEST TEST RELIE F REQUEST(S)

--TYPE-COORDI=OPER

--FUNCT-ICL-------REQUIRED=--PERFORHED HODE-2-ttS-283 2 CK 0.5 SA C/8 C 0/C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 2 R YES>NOTE 1 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUm)ARY SHEET-UNIT 2 SYSTEN-NAHE:

-PAS-CONTAI)RENT=HYDROGEN.-

---=-----F LON-DIAGRAH:

-2"5141D-8 RUH DATE AND TINE: 14SEP87:13:28-VALVE I=-VALVE-POSITION

-I----I I ASNE-SECTIOH XX--NU)SER REV TYPE SIZE ACT F~D I PONER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUESTERS)

--TYPE-COORDI-OPER---

-FUHCT---ICL--:=-----REQUIRED----PERFORNED

--.-NODE 2-ECR-25 0 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-5 EF-7-ETF-002--SLT-1 EF-1 EF-5 EF-7 ETF-002.-SLT-2 P P-P R NO NO HO NO-----YES'OTE 1 2-ECR-26-=O=GL--0.5==-A----B/3-----C

=-----0/C-----2----.A--A

---EF-1=-----.--EF-1 EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT-1-==-=-=-SLT-2--P-=-HO NO P HO P HO-R--=-YES>NOTE 1--2"ECR"27 0 GL 0.5 A B/3 C 0/C 2 A EF-1-EF-5-EF-7 ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P HO NO P HO P HO R YES>NOTE 1 2-ECR-28 0 GL 0.5 A B/4 C 0/C 2 A EF-1 EF-5=EF-7----ETF-002 SLT-1.EF-1 EF-5 EF-7------ETF-002 SLT-2 P---P P R HO Na WO NO YES'OTE 1 2-ECR-29 0 GL 0.5 A B/4 C 0/C 2 A A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO-=ETF-002-=-.---ETF-002-------P-==HO SLT-1 SLT-2 R YESp NOTE 1 0~DOHALD C.CNK NUCLEAR PLANT SECOiND TEH YEAR INTERVAL VALVE SU2 fARY SHEET-U22)IT 2 SYSTEH-HA)fE:=-PAS-CONTAZtRENT HYDROGEN===FLOH DIAGRA)f: 2221410-8.=RUN DATE AND TINE: 14SEP87:13:28 VALVE=---===-I-VALVE-POSITION I-I I ASNE-SECTIOH XI-NU00BER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRZH TEST TEST TEST RELIEF RE@JEST(S).TYPE COORD I-OPER-=-FUAACT=ICL.REQUIRED PERFOR'fED JfODE-2-ECR-20 0 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ETF=002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P NO N)P NO P=tiO R YESB NOTE 1 2-000-21 0-Gl-0.0-.-2-.-0/2-C-..-.0/0-.A=-A EF-1 EF-5 EF-7 ETF-002-SI.T-1-EF-1 EF"5 EF-7 ETF-002 SLT-2 P---W-HO P NO P NO R YES>NOTE 1 2-ECR-22 0 GL 0.5 A B/2 C 0/C 2 A EF-1.-EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5-EF-7 ETF-002 SLT-2 P P R NO NO NO NO YES>NOTE 1 2-ECR-23 0 GL 0.5 A B/1 C 0/C 2 A EF-1 EF-5----=-EF-7-ETF-002 SLT-1 EF"1 EF-5 EF-7-ETF"002 SLT-2 P P R HO NO NO I)YESB NOTE 1 2-ECR-24 0 GL 0.5 A B/3 C 0/C 2 A EF-1 EF-5 EF-7 ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P P P R NO HO NO NO-YESB NOTE 1 0

0 0 DOHALD C.COOiti NUCLEAR PLANT SECOHD TEH YEAR INTERVAL VALVE SURSLRY SHEET-UHIT 2 SYSTEH-NAHE:

-PAS-CONTAICKNT=HYDROGEN--.-

=-=---FLOH-DZAGRAH:

..2=5141D-.8-RUH DATE AND TINE: 14SEP87:13:28 VALVE I-=VALVE-POSITION-I I l AS!%-SECTION-XL HOSER 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-.-PERFORHED--

-NODE.2"ECR-15 0 GL 0.5 A A/1 C 0/C 2 A A EF"1 EF-5 EF-7 ETF.=002 SLT-1 EF-1 EF-5 EF-7=.ETF.-002 SLT-2 P NO HO P HO P HO R YES>HOTE 1 2-ECR-16--0-GL-=0.5=----A---A/3==C--0/C-----2---A---A.----EF-1----EF-1 EF-5 EF-5 EF-7 EF"7 ETF-002 ETF-002 SLT-1.NLT=2-..-=-.--P----.-VQ HO P HO P HO R=-..YESp NOTE.3-=2-ECR-17 0 GL 0.5.A A/3 C 0/C 2 A A EF1 EF-.5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P P R NO HO HO HO YES>HOTE 1 2-ECR-18 0 GL 0.5 A A/4 C 0/C 2 A A EF-1 EF-5 EF-7=-ETF-002 SLT-1 EF-1 EF-5-=EF=?=ETF-002 SLT"2 P==P R HO HO HO-HO YES>NOTE 1 2-ECR-19 0 GL 0.5 A A/4 C 0/C 2 A A EF-1 EF-5 EF-7-ETF-002-SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P HO HO P HO P---..HO R YES'OTE 1 e'

0=D(NALD CD COOK NUCLEAR PLANE SECOND TEN YEAR IttTERVAL~VALVE SvtuQRY SHEET-UiiIT 2 SYSTEtl-NAttE:

-PAS-COttTAIt"tENT-HYDROGEN-=-

-==-=-FLON DIAGRAtt t--2-51410-8 RWi DATE AND TIHiE: 14SEP87:13:28

---

VALVE---I-VALVE-POSITION-I-

---

=--I.I--.ASHE SECTION Xl-tmiiSER REV TYPE SIZE ACT F~D.I POHER SAFETY ICD A/P CAT PRltt TEST TEST TEST RELIEF REQUEST(S)

=-.-TYPE-COORDt--OPER-==-FUMCT--ICL-----=-RE@JIRED--:

-PERFORHED HiODE-2-ECR-10 0 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ETF-002 SLT-1 EF-1 EF"5 EF-7 ETF-002 SLT-2 P P R HO HO HO HO YESp NOTE 1 2-ECR-ll-.-0-GL=0.5---A--==A/2=-C

--0/C--=2--A=-A-===-EF-1-----

---

EF-1 EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT-1=-----.SLT-2-P--HO-NO P NO P HO R--=-YES'OTE 2-ECR-12 0 GL 0.5 A A/2 C 0/C 2 A A EF1--EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF"002 SLT-2 P P P R HO-HO---HO HO YES'OTE 1 2-ECR-13 0 GL 0.5 A A/1 C 0/C 2 A A EF-1 EF-5-EF-7---ETF-002 SLT-1 EF-1 EF-5 EF-7-ETF-002 SI.T-2 P P R tiO HO HO HO YESp NOTE 1 2-ECR-14 0 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF-5 EF-7.ETF-002 SLT-1 EF-1 EF-5 EF-7-ETF-002 SLT-2 P-P-R NO NO NO NO YESp NOTE 1

SYSTEM-NAME-:

-NUCLEAR-SAHPLING-DONALD C.COOK NUCLEAR PLANT SECOND TEll YEAR INTERVAL VALVE S~~RY SHEET-UNIT 2-F LON-DIAGRAH: 5141A-30 RUN DATE AND TIME 14SEP87:13:28-VALVE I VALVE-POSITION-I-=-------=----=--ASHE SECTION-XI--

==--I I tiKRSER 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-HODE 2-MCR-253 0 GL 0.5 A B/1 0 2 A B EF-1 EF-5 EF-7 ETF-002-EF"1 EF-5 EF-7 ETF-002 P NO NO P NO--P NO 2-HCR-254 0 GL 0.5 A B/1 0 2 A B EF-1 EF-5--EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P NO NO P NO P NO

SYSTEH-NAHE:

-NUCLEAR-SAttPLItiG DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SSDtARY SHEET-UNIT 2 FLOH=DZAGRAtt:.2-5141A-30 RUiH DATE AND TItlE: 14SE F87:13: 28-.-VALVE--------=---I-VALVF-POSITION-I I I hÃltSER REV TYPE SIZE ACT F.D.I POHER SAFETY I CD A/P CAT TYPE COORDI-OPER

--RPitCT--ICL ASHE-SECTION XZ PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUZRED PERFORHED HODE-2-DCR-301 0 GL 0.5 A 8/2 0 C 2 A 8 EF-1 EF-5 EF-7 ET-003 EF-1 EF-5 EF-7 ET-003.P NO NO P HO P-NO--2-DCR-302 0 GL 0.5 A 8/3 0 C 2 A 8 EF"1 EF-5----EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P HO----=-t'O-=-P NO P NO 2-DCR"303 0 GL 0.5 A 8/3 0 A 8 EF-1 EF-5 EF-7 ETF-002-EF-1 EF-5 EF-7-ETF--002 P NO HO P NO P--=HO=--2-DCR"304 0 GL 0.5 A 8/3 0 C A 8 EF"1=-EF-5 EF-7 ETF-002 EF-1 EF-5--EF-7 ETF-002 P NO NO P NO P HO 2-MCR-251 0 GL 0.5 A 8/2 0 2 A 8 EF-1 EF-5 EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P NO HO P HO P NO 2-ttCR-252 0 GL 0.5 A 8/2 0 C 2 A 8 EF"1-EF-5 EF-7 ETF-002 EF-1-=-EF-5-EF-7 ETF-002 P NO HO-.P HO P NO C SYSTEtl-NAttE:

-NUCLEAR-SANP LING DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR IttfERVAL VALVE S4tt&RY SHEET-UNIT 2 FLON-.DIAGRAtt: 5141 ----RUiN DATE AHD TINE: 14SEP87t13:

28 VALVE----I-VALVE-POSITION I I I ASNE-SECTION-XZ HlESER REV TYPE SZ2E ACT F.D.I PONER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI-OPER-

--FUNCT--ICL-=-----==--REQUIRED

-=PERFORttED

---

tlODE--2-HCR-108 0 GL 0.5 A 0/6 0 2 A A EF-1 EF-5 EF-7 ETF=002-.-SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P NO HO P NO...P--NO R YES'OTE 1 2-NCR-109-0-Gl 0.5-A-D/5--0--C---2---A--A==-EF-1--=-=---EF-1---=EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT"1----SLT-2-.P--HO-=NO P HO P NO-R--YES>NOTE 1 2-HCR-110 0 GL 0.5 A D/6 0 C 2 A A EF-1 EF=-5------EF-7 ETF-002 SLT-1 EF-1 EF-5--EF-7 ETF-002 SLT"2 P P P R NO-NO-NO HO YES>NOTE 1 0

DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMttARY SHEET-UNIT 2 SYSTEM-NAME:=NUCLEAR-SAMPLIHG

--.------.-----=-FLON DIAGRAM:=2"5141-27

-.--RUH DATE AHD TIME: 14SEP87:13:28 VALVE I--VALVE-POSITION I I ASME-SECTION-XZ HKtDER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

---

TYPE COORDI-OPER----FLNCT--ICL---==REQUIRED-PERFORMED=*MODE 2-ICR-5 0 GL 0.5 A C/5 0 C 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF-5 EF"7 ETF-002 SLT-2 P HO NO P HO P NO R YES'OTE 1 2-ZCR-6-=0-Gl 0.5----A--D/5-=0-----C-2--A--=A-=-EF-1--" EF-5 EF-7 ETF-002 SLT-1=--EF-1-EF-5 EF-7 ETF-002 SLT-2 P=-HO NO P NO HO-:R-----YES'OTE 1 2-HCR-105 0 GL 0.5 A C/7 0 C 2 A EF-1-EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P P P R NO HO HO HO YES>NOTE 1 2-HCR"106 0 GL 0.5 A C/7 0 EF-1 EF-5 EF-7 ETF>>002 SLT-1 EF"1 EF-5-EF-7=-=-ETF-002 SLT-2=----P-P R HO NO.HO.-HO YES>HOTE 1 2-HCR-107 0 GL 0.5 A D/6 0 C 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P-P R NO HO HO HO YESp HOTE 1 SYSTEtt=NANE:

-CONPONENT-COOLIHG

--DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR IHTERVAL VALVE SUtCtARY SHEET-UNIT 2 FLON-DIAGRAN:=-2"51358-14

---.==-=RUN DATE AND TlttE: 14SEP87: 13: 28 VALVE-=---------=I VALVE-POSITION I=-------I I ASttE=SECTION-XZ-HUttBER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)

---

TYPE-COORD I OPER--FLRCT-ICL----------=REQUIRED-----PERFORttED

--l40DE=-2-CCI't-243-25 2 CK 1 SA C/5 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp NOTE 2 YESp NOTE 1 2-CCN-243-72 2 CK 1 SA C/5 0 2 A AC CF-1 SLT"1 CF-2 SLT"2 R R YESp NOTE 2 YESp NOTE 1 2-CCN-244-25 2 CK 1 SA C/6 0 2 A AC CF1 SLT-1 CF-2 SLT-2 R R YESp ttOTE 2 YESp NOTE 1 2-CCW-244-72 2 CK 1 SA C/6 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp HOTE 2 YESp NOTE 1 2-SV-122-258 0 REL 1.5 SA B/6 C 0 3 A C TF1 TF-1 R HO 2-SV-122-728

-0=-REL=1.5-.--SA=-B/6---C-.--0---=3--A---C-=-==TF-1=-----TF-1-R NO

SYSTEM-NAME:

-COMPONENT-COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE St&DARY SHEET-UtGT 2 FLOH DIAGRAM:-2-51358-14 RUH DATE AHD TIME: 14SEP87: 13: 28-VALVE-=---=----.-=I-VALVE-POSITION-I I I HUAABER REV TYPE SIZE ACT F.D.I POHER SAFETY!CD A/P CAT-TYPE COORDI OPER=--FACT-ICL ASME-SECTZOiN

=Xl-=-----PRIM TEST TEST TEST RELIEF RE@JEST(S)

REQUIRED PERFORMED.MODE 2-CCM-430 0 GL 1.5 MO D/6 C 0/C 2 A A EF-1 EF-5 ET-018---SLT=1 EF-1 EF-5 ET-018 SLT-2 P P R HO NO NO YES'OTE 1 2-CCM"431 0 GL 1.5 MO D/6 C 0/C 2 A'EF-1 EF-1-==---=--EF-5-.-=EF-5 ET-015 ET-015 SLT-1 SLT-2 P NO NO P HO R YES>HOTE 1 2-CCM&32 0 GL 1.5 MiO D/6 C 0/C 2 A A EF-1 EF-5 ET-018 SLT-1 EF-1 P NO EF-5 NO ET-018 P HO SLT-2-R YES HOTE 1 2-CCM-433 0 GL 1.5 MiO D/6 C 0/C 2 A A EF-1-=-EF-5 ET-019 SLT-1 EF"1 EF"5 ET-019 SLT-2~P P R NO NO HO YES>NOTE 1 2-CCR-440 0 GL 1.5 A D/6 0 A EF-1 EF-5 EF-7 ET-008 SLT-1 EF-1 EF"5 EF-7 ET-008 SLT-2 P P R NO NO NO HO YESR NOTE 1 5-CCR-441 0-51--1.5 A..5/6 0---2--A--A--EF-1----EF-5 EF-7 ET-005 SLT-1 EF-1 EF-.S EF"7 ET-005 SLT-2 P P P R HO NO HO NO YES>NOTE 1

0 0 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SmDQRY SHEET-UHZT 2 SYSTEM NAME-'COMPONENT.

COOLING FLOH DIAGRlL): 2"5135A"30 RUN DATE AND TIME: 14SEP87:13:28 VALVE-==-=.I..VALVE=POSITION I.-.-..---I I--ASME SECTION XZ-NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST.TYPE COORDI OPER-FACT ICL.REQUIRED TEST PERFORMED TEST RELIEF REQUEST(S)

MODE 2-CYA)-416 0 BF 16 MO G/5 0 0/C 3 A B EF-1 EF-5 ET-103 EF-1 EF"5 ET"103 P NO HO P NOp NOTE 1 2-CYiO-419 0 BF 14 MO E/5 C 3 A B EF1 EF-1 P HO EF-5 EF-5 HO ET-053--ET"053--P NO-2-CMO-420 0 BF 16 ViO H/4 C/0 0 3 A B EF-1 EF-1 EF-5 EF-5 ET-066 ET-066 P HO HO P NO 2=CM0=429 0=BF==14 MO E/5 C 0 A B EF 1 EF-1 EF-5 Ef"5 ET-054 ET-054 P NO HO P HO 2-CRV-412 0 GL 4 A K/1 0 C A B EF"1 EF-5 EF-7-ET-019-EF-1 EF-5 EF-7 ET-019 P NO NO P NO-P-.-NO---2-SV-60 0 REL 3 SA L/1 C 0 3 A C TF1 TF-1 R HO 2-SV-72 0 REL 1 SA E/5 C 0 A C TF-1 TF-1

SYSTEH-NAME:

-COMPOiNENT-COOLING

---==---DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE

SUMMARY

SHEET-UNIT 2.=-====-=*-FLOH DIAGRAH: 2-5135A RUN DATE AND TIHE: 14SEP87:13:28-VALVE-------=-I--VALVE=POSITION I I I NUiSER REV TYPE SIZE ACT F.D I POHER SAFETY LCD A/P CAT PRIM TEST TYPE-COORDI OPER-=-FUNCT-ICL--.------REQUIRED ASHE-SECTION-XZ TEST TEST RELIEF REQUEST(S)

PERFORMED-MODE 2-CCN-176-E 0 CK 16 SA L/4 C/0 0 3 A C CF1 CF-1 HO 2=CCN=176=N=O CK=--16===SA-K/4 C/0.0==3=A C.--CF-l.CF"1 P.NO 2-CHO-410 0 BF 16HO H/4 C/0 0 A B EF"1 EF-l.P HO--=-=--EF=5-----EF-5---=-NO-ET-055 ET"055 P KO 8=888881i=0

-88~8==80=H/8--8.EF-1 EF-5 ET-053--P=---HO NO P NOp NOTE 1 2-CHiO"412 0 BF 16 HO L/3'0/C A B EF1 EF-5 ET-054 EF-1 EF-5 ET-054 NO NO NO>NOTE 1 2-CYA)-413 0 BF 18 HO L/5 0 0/C 3 A B EF-1 EF-1 EF-5 EF-5---=-ET-053--=--ET-053 P HO NO--=P-----NO 8 HOTE 1 2"CHO&14 0 BF 16 MO K/3 0 0/C 3 A B EF-1 EF"1 EF-5--EF-5 ET-054 ET-054 P NO NO P NOp NOTE 1 2=CH0=415 0 BF~6.-HO.H/5-0..0/C-.3-.A B.--EF.-1..--EF-5 ET-054 EF-1---P HO EF-5 NO ET-054 P NO>NOTE 1 SYSTEH-NAt%:

-CC fPONENT-COOLING=

DONALD C.COOK NUCLEAR PLANT RUN DATE AND TINE: lOSEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SlM1ARY SHEET-UNIT 2=FLOH.DIAGRAH: 2-5135-30.--VAlVE-=---------I-VALVE-POSITION I---l I ASHE SECTION XI NEVER REV TYPE SI2E ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF RE(PEST(S)

TYPE-.COORD)

OPER-=-.FUINCT.ICL=..REQUIRED PERFORHED HODE 2-SV-68 0 REL 1 SA J/2 C 0 3 A C TF-1 TF-1 R NO E=RII.-.T1 0-REI 3-:--EA--..-LF3 C-0-3..A.-0..TF-3.TF-3 R RC

SYSTEtt-NAME.CO'tPONEttT-COOLING

~~DONi ALD C.COOK NUCLEAR PLAttT SECOitD TEtt YEAR INTERVAL VALVE SUGARY SHEET-UittIT 2 FLO)L DIAGRAM: 2-5135-34 RUN DATE AND TIME: 14SEP87:13:28-VALVE-.I VALVE.POSITION-I

.-ASME=SECTIOH

=XZ I I NUtiBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRZt1 TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI.OPER FUNCT ICL REQUIRED PERFORMED MODE 0 2-CCH-135 0 CK 2.5 SA B/3 0 2 A AC CF1 SLT-1 CF"2 SLT-2 R YESp NOTE 4 R YESp NOTE 2 2-CRY-445 1 BL 6 A L/5 0 C/0 3 A B EF-1 EF-5 EF-7 ET-034 EF-1 EF-5 EF-7 ET-034-P P NO ttO NO HO 2-CRV-470 0 GL 6 A G/1 0 3 A B EF1 EF-7.ET-HA EF-1 P N)ttOTE 5-YESp HOTE 5 HOTE 5-YESp NOTE 5 2=CRY=485=

0.BF 10--A B/7 0 A-B-EF I EF-5 EF-7 ET-018 EF-1 E F-5 EF-7 ET-018 P-HO HO P NO P HO 2"SV"122 0 REL 1 SA D/3 C 0 A C TF"1 TF-1 R NO 2-SV-62 0 REL 1 SA 0/3 C 0 A C TF-1 TF-1 R HO 2=SV"63--O==REL=1.=SA E/3.C*0 3 A C TF-1 TF-1 R HO 2-SV-64 0 REL 1 SA C/3 C 0 A C TF-1 TF-1 R HO 2-SV-65 0 REL 1 SA tt/I C 0 3 A C TF"1 TF-1 R NO

=0 DONALD C.COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SUt01ARY SHEET-UNIT 2 SYSTEN-NAt tE.:-CfRPONENT-COOLItiG

--=----==-----FLOtL DIAGRAIH--2-5135-34

--=-=--RUN DATE AND TIttE: 14SEP87:13:28 VALVE---------------I-VALVE=POSITIOtt=l I I MEMBER REV TYPE SIZE ACT F.D I POttER SAFETY I CD A/P CAT TYPE-COOROI-OPER

-FWCT ICL=-----ASttE SECTION XZ-PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED----PERFORMED-

-.tlODE 2-CCR-455 0 GL 2 A 8/3 0 C A A EF-1 EF"5 EF-7 ET-005 SLT-1 EF-2 EF"5 EF-8 ET-005 SLT-2 C C C..R YESp ti'OTE 3 ttO HOp NOTE 3 HO YESp HOTE 2 2-CCR-456=0=GL- --=-A==D/4"--0 EF-5 EF-5 EF-7 EF-8 ET-005 ET-005-SLT-1---SLT" 2 C C R-2-==A---A=

-==EF-L--=--

==EF-2-=--------C--YESp HOTE 3--HO HOp NOTE 3 NO YESp NOTE 2 2-CCR-457 0 GL A D/4 0 C EF-1 EF-5-EF-7 ETF-005 SLT-1 EF-2-EF-5 EF-8 ETF-005 SLT-2 C C R YESp NOTE 3 NO HO NOTE 3 HO YESp NOTE 2 2-CCR-460 0 GL 3'C/4 0 C 2 A A EF-1 EF-5-EF-7--ET-010 SLT-1 EF-1 EF-5-----EF-7 ET-010 SLT-2 P-P P R HO NO-NO-=N)YESp NOTE 2 2-CCR-462 0 GL 3 A A/4 0 C 2 A A EF-1 EF-5 EF-7 ET-009---SLT-1 EF-1 EF-5 EF-7 ET-009-SLT-2 P P P R NO HO HO HO YESp HOTE 2

SYSTEM-NAHE-.-

COMPONENT-COOLING DOttALD C.COOK hRJCLEAR PLANT SECOND TEN YEAR ZttTERVAL VALVE SUtStARY SHEET-UttIT 2-FLON-DIAGRAH:-2-5135-34

-=-RUN DATE AND TIHE: 14SEP87:13:28 VALVE=-----l VALVE POSITION-I

--I I ttUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY!CD A/P CAT TYPE COORDI OPER---FUttCT--ICL

--ASHE SECTION XZ PRIH TEST TEST TEST RELIEF RWUEST(S)-REQUIRED-

-==-PERFORMED-HODE 2"CCH"451 0 BF 8 HO E/4 0 C 2 A A EF-1 EF-5 ET-026-SLT-1-EF-2 EF-5 ET-026-SLT-2 C YES'OTE 1 NO C NO R-YES'OTE 2 2-CCH-452 0.BF HO E/5 0 C 2 A A EF-1 EF-5==------ET-023 SLT-1 EF-2 EF>>5 ET-023 SLT-2 C R YES'OTE 1-tiO-ttO YES>NOTE 2 2-CCH-453 0"GL 4 HO E/4 0 2 A A EF-1 EF-5 ET-030 SLT-1=----EF-2 EF-5 ET-030 SLT-2 C C R YES'OTE 1 NO NO YES>ttOTE 2-2-CCH-454 0 GL HO E/5 0 C 2 A A EF-1 EF-2 EF-5-===-=EF-5-ET-030 ET-030 SLT-1 SLT-2 C R YES>NOTE NO NO YES>NOTE 2-CCtf-458 0 BF 8 HiO A/2 0 2 A A EF-1 EF-5 ET-023 SLT-1 EF-2 EF-5 ET-023 SLT-2 C C R YES>NOTE NO NO---YES'OTE 2-CCH-459 0 BF 8 HO B/2 0 2 A EF-1 EF-2-EF-5-----EF-5 ET-024 ET-024 SLT-1 SLT-2 C YESi NOTE 1 NO-C NO R YES>NOTE

DONALD C.COOi<NUCLEAR PLAtA'ECOND TEN YEAR INTERVAL VALVE SUl01ARY SHEET-UNIT 2 SYSTEM=NAME:

-CVCS-LETDOWN-8-CHARGING--

--=-=-==--=-FLOW=DIAGRAM: 5129A-20--

RUH DATE AND TIME: 14SEP87:13:28

-VALVE-I VALVE-POSITION I I I ASME%ECTION-XI-NUMBER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI-OPER

--FUiiiCT--ICL-=--------REQUIRED-

--=-PERFORMED-

--MODE.-2-QCM-250 0 GA MO C/8 0 2 A A EF-1 EF-2 E F-5 EF-5 ET-015 ET-015 SLT-1------SLT-2-C-R YES>NOTE 1 NO HO YES>NOTE 2 2-QCM-350 0 GA 4 MiO D/8 0 2 A A EF-1---EF-5 ET-009 SLT-1 EF-2---E F-5---ET-009 SLT-2 C R YES>NOTE 1 HO HO YES>NOTE 2 2-QMO-451 0 GA 4 MO J/5 0 2 A B EF"1 EF-5 ET-009 EF-2 EF-5 ET"009 C YES>HOTE 3 NO C HO 2-QMO-452 0 GA MO J/5 0 2 A B EF-1 EF-5-.-ET-006=-=-

EF-2 EF-5--ET-006 C YES>NOTE HO C-NO 2-QRV-400 0 GL 2 A K/4 C 0 2 A B EF-1 EF-1 P HO--EF-5-=-EF-5--------"=-=HO EF-7 EF"7 P HO ET-005 ET-005 P NO 2-SV-53 0 REL 3 SA M/2 C 0 2 A C TF-)TF-1 R-.SV-&i-.-0-REI~->A--E/4--C----.0----2 A---C---TF"1-=----TF-1 R--HO 4

~DOiRLD C.COOK NUCLEAR PLANT SECOND TEN YFAR INTERVAL VALVE SUED'RRY SHEET-UNIT 2 SYSTEH-NAHE:=-CVCS-LETDO'ruN-8-CHARGING-

---=-==-=-FLON-DZAGRAH:--2-5129"32-RUN DATE AND TINE: NSEP87: 13: 28-VALVE---I VALVE=POSITION I I I-ASHE-SECTION-XZ NLPiBER REV TYPE SIZE ACT F.D~(POHER SAFETY!CD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)-TYPE COORD I-OPER-FUNCT--ICL----REQUIRED-PERFORHED--HODE 2-SV-55 0 REL 0.75 SA K/7 C 0 2 A C TF-1 TF-1 R NO 2-SV-56=-=-0-REL==--0'5-SA--L/6 C-----0---2-A-C-TF-1----TF-1 R-NO 0-DOiiALD C.COOK NUCLEAR PLANT SECOiND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UiNZT 2 SYSTEH=NAHE:

-CVCS.=-=LETDORI-S-CHARGING

---

==---FLOil-DZAGRAH:=-

2-5129 RUN DATE AND TINE: 14SEP87:13:28

-=VALVE I VALVE-POSITION I I I ASi lE=SECTION=XZ--HUl&ER REV TYPE SIZE ACT F.D.t POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD)OPER--FUHCT ICL----REQUIRED..PERFORHED-HiODE 2-QHO-226 0 GA 2 Y>D G/7 0 0/C 2 A B EF-1 EF-5 ET-011 EF-1 EF-5 ET-Oll P NO NO P HO 2-QRV-200 1 GL 3 A H/3 0 0 A B EF-1 EF-3 EF-7 NOTE 8--ET-NA-----NOTE 8-P NO>HOTE 8 YES>NOTE 8-YES>NOTE 8-2-QRV-251 1 GL A H/5 0 0 2 A B EF1 EF-3 P HOp NOTE 9-EF-7-:----HOTE=9-------YESp NOTE 9 ET-NA NOTE 9 YES>NOTE 9 2-QRV-61---0=-GL-----3----A---C/2--C---0-----2 A--B--EF-1 EF-5 EF-7 ET-008 EF-1 EF-5 EF-7 ET-008 P-HO-NO P NO P HO 2-QRV"62 0 GL 3 A C/2 0/C 0 2 A B EF-1 EF-1 EF-5 EF-5 EF-7=-=---EF-7-=-ET-009 ET-009 NO NO HO-HO 2-SI-185---0--CK-.-.-8----SA K/5-C-0 2.--A--C--CF-1-Cf-2 R-YES'OTE 10 2"SV-51 0 REL 2 SA E/2 C 0 2 A C TF-1 TF"1 R HO 2-SV-52 0 REL 2 SA K/1 C 0 2 A C TF-1 TF-1 R HO 0~DONALD C.COOK NlCLEAR PLANT SECO'ND TEN YEAR INTERVAL VALVE SUYu'1ARY SHEET-UiHIT 2 SYSTEM-NAME:--CVCS--LETDOWN-8-CHARGING

---=----FLOH DIAGRAM:--2"5129-32 RUH DATE AND TIME: 14SEP87:13:28 VALVE-.-=-=-=--=.-.I VALVE POSITION I-I I----ASME SECTION Xl HUi'SER REV TYPE SIZE ACT F~D.I POHER SAFETY I CD A/P CAT-TYPE COORDI-OPER FUHCT ICL PRIM TEST REQJIRED TEST TEST RELIEF REQUEST(S)

PERFORMED MODE-2-IMO-910 0 GA 8 MO L/5 C 0 2 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P NO NO P NO 2-IMO-911 0 GA 8 MO L/6 C 2 A B EF-1 EF-5-ET-012 EF-1'F-5--ET-012 P NO HO P---HO 2-QCR-300 0 GL 2 A E/1 0 A A EF-1 EF-5 EF-7 ET"003 SLT-1 EF-2 EF-5 EF-8 ET-003 SLT-2 C YES>NOTE 6 HO C NO>NOTE 6 C NO R YES>HOTE 3 2-ACR-301 0 GL 2 A E/1 0 C 2 A A EF-1 EF-5 EF-7-,ET-005 SLT"1 EF-2 EF-5 EF-8 ET-005 SLT-2 C--C R YES>NOTE 6 NO NOp-NOTE 6 NO YES'OTE 3 2-QMO-200 0 GA 3 MO J/3 0 0/C 2 A B EF"1 EF-5 ET-012 EF-2 EF-5 ET-012 YES'OTE 7 NO NO 2-QMO-201 0 GA 3 MO J/3 0 0/C 2 A B EF-1 EF-5 ET-012 EF-2 EF-5-ET-012 YES>NOTE 7 NO HO-2-QMO"225 0 GA 2 MiO J/7 0 0/C 2 A B EF-1 EF"5 ET-012 EF-1 EF-5 ET-012 P NO--HO P NO

.~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUl~RRY SHEET" LAIT 2 SYSTEH-NAHE:=-CVCS==LETDOHN-8-CHARGING

=-.FLON-DIAGRAll:.

2-5129"32 RUH DATE AND TINE 14SEP87:13:28 VALVF==----=-=----I=VALVE POSITION-I

---

=---=ASHE-SECTION-XZ-I I NURSER REV TYPE SIZE ACT F D I PONER SAFETY I CD A/P CAT PRZH TEST TEST TEST RELIEF RE@lEST(S)

---.TYPE-COORDI-OPER-

-=-FUHCT--ICL---REQJIRED--PERFORHiED

---NODE 2-CS"292 0 CK 2 SA H/6 C 0/C 2 A C CF-1 CF-2 C YESp NOTE 1 2=CS-297-"E=O=-CK-----2--

-==SA=-H/7 0/C-0--2 A=C-CF-1 CF"1 2-CS-297-H 0 CK 2 SA F/7 0/C 0 2 A C CF1 CF-1 2-CS-299-E 0 CK 4 SA H/7 0 0/C 2 A AC CF-1 SLT"1 CF-3 SLT-1 P YESp NOTE 2 R HOp NOTE 3 2-CS-299-H 0 CK SA F/7 0 0/C 2 A AC CF-1 SLT-1 CF-3 SLT-1 P YESp NOTE 2 R HOp NOTE 3 2-CS-321 0 CK 3 SA E/3 0 C/0 2 A AC CF-1 SLT-1 CF-2 SLT-2 YESp NOTE 4 R YESp NOTE 3 2-CS-328-L1 0 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P NOp NOTE 5 2-CS-328-L4 0 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P NOp HOTE 5 2=CS=329=.L1=.0 CK D====SA.8/2.0/C 0 1.A C CF-1 CF-1 P NOp NOTE 5 2-CS"329" L4 0 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P HOp NOTE 5 2-IHO-360 0 GA 4 HO J/6 C 0 2 A 8 EF-1 EF-5 ET-009 EF-1 EF-5 ET-009 P P NO NO NO SYSTEH-t4NEt=REACTOR-COOLANT-DONALD C.COOK NUCLEAR PLAtR SECOND TEN YEAR INTERVAL VALVE SUi~0'NRY StlEET-UNIT 2 F LOtt-DIAGRAH:-2-5128A-34 Rmt DATE AND TIHE: 14SEP87-.13:28-VALVE-=----------I.-VALVE POSITION I I I-ASHE SECTION XI----NUYBER REV TYPE SIZE ACT F.D.I PtNER SAFETY ICD A/P CAT PRItk TEST TEST TEST RELIEF REQUEST(S)

---

TYPE COORD I-OPER-=FUitiCT=ICL REQUIRED PERFORHED.

HODE 2"SI"189 2 CK SA D/7 C 0/C 2 A AC CF-1 CF-2 SLT-1 SLT-2 R YES>NOTE 7 R YESs NOTE 2 2-SV-45A 0 REL 6 SA K/6 C 0 A C TF-1 TF-1 R NO R-SV.-468 0--RRI 6----SA.-J/6-C----..-0---6-A C-TF-1 TF-I R---=NO 2-SV-45C 0 REL 6 SA H/6 C 0 1 A C TF-1 TF-1 2-SV-50 0 REL 2 SA G/3 C 0 A C TF"1 TF-1 R NO I 0 ,

SYSTEN-HARE:

-REACTOR-COOLANT=

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiQRY SHEET-UiiIT 2 FLOH DIAGRAH:-=.2=5128A-34..

RUN DATE AND TINE: 14SEP87:13:28 VALVF=--=--=-==-==-I--VALVE-POSITION-l

---

=l I NAKER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT-TYPE COORDI OPER---FUNCT-ICL-ASNE SECTION XZ-PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORNED MDE 2-NSO-062 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 6 NOp NOTE 6 R YESp HDTE 6 R YESp NOTE 6 2-NSO-063 2 GL 1 SO N/6 C 0/C EF-1--EF-5---EF"7 ETF-002 EF-2---EF-5------EF-8 ETF-002 R R YESp NOTE 6 HOp NOTE 6--YESp NOTE 6 YESp NOTE 6 2-NSO-064 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-2 R EF-5 EF-5 EF-7 EF-8 R ETF-002 ETF-002---R YESp HOTE 6 HOp NOTE 6 YESp NOTE 6 YESp-NOTE 6 2-PN-275 2 CK SA B/9 0/C C 2 A AC CF-1 CF"2 SLT=1=-=-=-SLT-2 R YESp HOTE 4 R-YESp NOTE 2 2-RCR-100 0 GL 0.375 A B/7 0 C 2 A A EF-1---EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5-EF-7 ETF-002 SLT-2 P P P R HO HO NO NO YESp NOTE 2 2-RCR-101 0 GL 0.375 A B/7 0 C 2 A EF-1 EF-5-EF-7-ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P P P R HO NO NO--NO YESp NOTE 2

SYSTEN-NAHC:

-REACTOR-COOLANT DOHALD C.COOK NUCLEAR PLICA SECOND TEN YEAR INTERVAL VALVE SVi'DIARY SHEET-UNIT 2 FLON-DIAGRAN:-2"5128A-34 RUN DATE AND TINE: 14SEP87:13:28 VAI.VE=--=-I-VALVE=POSITION I I I ASYiE SECTIOiN XI HL~iER REV TYPE SIZE ACT F~D I PONER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

---TYPE-COORD I-OPER--=-FUHCT-ICL--REQUIRED---PERFORHED NODE 2-NlO-152 0 GA HO K/7 0 C 1 A B EF-1 EF-5 ET-014 EF-1 EF-5 ET-014 2-h~iO-153 0 GA 3 NiO K/6 0 C 1 A B EF-1 EF<<1 EF-5 EF-5 ET-014---ET-014-=-P N)N)-P-NO 2-NPX-151 0 GL 0.5 N N/8 C C 2 P A SLT-1 SLT"2 YESp hN)TE 2 2-HRV-151 0 GL 3 A K/7 C C/0 1.A B EF-1 EF"4 EF-5 EF"5 Ef-7-=-==-EF-0=ET-008 ET"008 HOp NOTE 3 NO NOp NOTE 3 NO 2-NRV-152-

=-;-O=GL~=.

=-=-A-K/7--C.----C/0-1-A-B-EF 1 EF-5 EF-7 ET"008 EF-4 EF-5 EF-8 ET-008 NOp NOTE HO HOp NOTE NO 2-HiRV-153 0 GL 3 A K/6 C C/0 1 A 8 EF1 EF-5 EF-7 ET-008 EF"4 EF-5 EF-8 ET-008 NOp NOTE NO NOp hOTE NO 2-NSO-061==2

-Gl~SO--N/6---C------0/C=-2 A-B--EF-1-----=EF-2=-----EF-5 EF-5 EF-7 EF-8 ETF-002 ETF-002 R R R YESp h'OTE 6-=HOp NOTE 6 YESp HOTE 6 YESp NOTE 6

SYSTEH-NAME:

-REACTOR-COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2-FLOH=DIAGRAH:- 5128A RUN DATE AND TINE: 14SEP87:13:28

-VALVE I VALVE-POSITION-I I ASHE SECTIOH=XZ-

---

==-HUYBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORDI-OPER

--FUNCT.ICL PRZH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORHED-NODE 2-CS-442-1 0 CK 2 SA B/4 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YESp NOTE 2 2-CS-442"2 0 CK 2 SA B/4 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2-CS-442-3 0 CK 2 SA B/4 0 C 2 A AC CF"1 SLT-1 CF-2 SLT-2 R R YES>NOTE 1 YES'OTE 2 2-CS-442-4 0 CK 2 SA B/4 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp NOTE 1 YES NOTE 2 2-GCR-301 0 DA 0.75 A B/8 0 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF"5 EF"7 ETF-002 SLT-2 P P P R HO NO HO HO YES'OTE 2 2-N-159=--2=-CK-=-0.75--SA-C/8-0/C---C----=2--A--AC---CF-1-------CF-2-SLT-1 SLT-2 R-=----YES>-HOTE=5 R YESp HOTE 2 2-HCR-252 0 GI A B/9 C C 2 P A EF-1 EF-5 EF-7 ET-004-.SLT-1.==EF-1 EF-5 EF-7 ET-004 SLT-2-P P P-R-HO HO NO HO YES>NOTE 2 2-QiO-151 0 GA 3 VO K/7 0 1 A B EF-1-EF"5 ET-015 EF-1 EF-5 ET-015 P NO HO P NO

SYSTEM-NAME:

-REACTOR-COOLANT-

~~DONALD C COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SU'i~RY SHEET-UihIT 2-FLOH-DIAGRAM:

2-5128 RUH DATE AND TIME: 14SEP87:15:28

--.VALVE=---==---==-I-VALVE POSITION-I---I I ASME-SECTION-XZ-tiIPiSER REV TYPE SZ2E ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD,I OPER=---FUNCT=-ICL--REQUIRED---PERFORMED

-MODE 2-HSO-021 2 GL 1 SO J/6 C 0/C 2 A B EF"1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 1 HOp NOTE 1 R YESp NOTE 1 R YES NOTE 1 2-NSO-022 2 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2-EF-5------EF-5 EF-7 EF-8 ETF-002 ETF-002 R YESp NOTE 1 HOp HOTE 1--R YESp NOTE 1 R YESp NOTE 1 2-NSO-025 2 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 1 NOp NOTE 1 R YESp NOTE 1 R YESp NOTE 1 2-NSO-024 2 GL 1 SO J/6 C 0/C 2 A B EF1 EF-5-EF-7 ETF-002 EF-2 EF-5-EF-8 ETF-002 R R YESp HOTE 1--HOp NOTE--1=-===---

-=YESp NOTE 1 YESp NOTE 1 0.~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ZNTERVAL VALVE SUNDRY SHEET-UHIT 2 SYSTEM-NAME:=STATZOH-DRAINAGE,CONTAI%!ENT=-

---

FLON=DIAGRAM:-=2-5124-20 RUN DATE AND TIME: 14SEP87:13:28 VALVE---=---==-------I-VALVE-POSITION=

I=I 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--FWCT--ICL-----REQUIRED-PERFORMED MODE 2-DCR-600 0 DA 3 A N/6 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 f F"5 EF-7 ET-004 SLT-2 P P P R HO NO NO NO YESD NOTE 1 3-000-601= DA-3 A-N/6-0-0-3 A=-A----EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7 ET-004 SLT-2 P P R HO HO NO HO YES NOTE 1 2-NS-357 2 CK 0.5 SA K/9 C 0/C 2 A AC CF-1-SLT-1-CF-2 SLT-2 R YES>NOTE 2 R YESR N)TE 1 M 00

0DO?QLD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UiNIT 2 SYSTEM-NAME:--NON-ESSENTIAI SERVICE HATER..-..-=-FLON DIAGRAM:=2"5114A-27

..RUN DATE AND TIMiE: 14SEP87:13:28

--VALVE.-.-------=-I-VALVE=POSITION I I I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDl-OPER

---FUNCT ICL---=-REQUIRED PERFORMED MODE 2-NCR-967-3 0 DA 2 A J/3 0 C 2 A A EF1 EF-5 EF-7.ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT"2 P P P R NO NO NO NO YES NOTE 1

~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sinai'RORY SHEET-UNIT 2 SYSTEH-NAlK:

-NOH-ESSENTIAL-SERVICE HATER---=.FLOH DIAGRAN:=2-.5114A-27 RUN DATE AND TINE: 14SEP87:13:28 VALVE---===--===-=

---I VALVE POSITION=I--I I HRSER REV TYPE SIZE ACT F~D~I PONER SAFETY t CD A/P CAT TYPE-COORD I-OPER--FACT-=ICL ASHE=SECTION-XI==--=---PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED-PERFORNED NODE 2"NCR"962 0 DA 2 A J/3 0 2 A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO ET-004.ET-004=P HO SLT-1 SLT-2 R YES>NOTE 1 R-HCR=965 0-OA-2-.--A=J/3---0-=-C-.---2--A=A=-EF-1-EF-5 EF-7 ET-004 SLT-1 EF-1--EF-5 EF-7 ET-004 SLT-.2 P P R HO HO HO HO YES>NOTE 1--2-HCR-964-3 0 DA 2 A J/7 0 2 A EF-1 EF-5=EF-7 ET-005 SLT"1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO NO=P NO P NO R YES>NOTE 1 2-HCR-965-3 0 DA 2 A J/7 0 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5 EF-7-ET-005 SLT-2 P NO HO P---NO-P HO R YES'OTE 1 2-hCR-966-3 0 DA 2-A J/3 0 2 A A EF-1 EF-5 EF-7=-==ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO HO P NO P=--HO R YES>HOTE 1

.e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU&lARY S)IEET-LPi)IT 2 SYSTEH-HA))Et=NON-ESSENTIAL-SERVICE-HATER-

=---=--.-FLON-DIAGRAH: 5114A-.27 RUH DATE AND TINE: 14SEP87:13:28 VALVE)-VALVE POSITION-I..I I------=------ASNE-SECTION XI NU)GER 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-HCR-956-2 0 DA A J/3 0 C 2 A A EF-1 EF-5 EF-7.ET-004 SLT-1 EF-1 EF-5 EF-7-ET=004-SLT-2 P P P R HO NO HO HO YES'OTE 1 2-HCR-957-3= -DA=-3---A---J/3-=-0=-=--C--.---2--A EF-1----==EF-1=--

EF-5 EF-5 EF-7 EF"7 ET-003 ET-003 SI T-1 SLT-2-P P P R---HO NO NO NO YES>NOTE 1.2-HCR-958-4 0 DA 3 A J/3 0 C 2 A A EF-1-EF-5-=EF-7 ET-005 SLT-1 EF-1 EF=5=EF-7 ET-005 SLT-2 P P R HO HO HO HO YES'OTE 1 2-HCR-960 0 DA 2 A J/7 0 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5-EF-7 ET-005 SLT-2 P-P R NO NO NO NO YES>HOTE 1 2-HCR-961 0 DA 2 A J/7 0 C 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R HO HO HO-HO YES>NOTE 1

DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR INTERVAL VALVE SmNARY SHEET-UthZT 2 SYSTEM-NAttE:

-NON=ESSENTIAL-SERVICE HATER-..FLOW DIAGRAM: 2=5114A=27

.RUN DATE AND TIME: 14SEP87:13:28

--VALVE-.-

-=-=-=-=-----I-VALVE-POSZTZON-I I I HUYBER REV TYPE SIZE ACT f D I POWER SAFETY ICD A/P CAT TYPE-COORDI OPER FUNCT ICL ASME SECTION XZ PRIM TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORMED MODE 2-WCR-951 0 DA 3 A K/6 0 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF"5 EF-7 ET-005 SLT-2 P NO NO P NO P.NO R YES'OTE 1 2=ttCR-452=2 DA-3=----A---.K/6=-" 0-==C EF-1------=EF-1 EF"5 EF"5 EF-7 EF-7 ET-004 ET-004 2 A-A.---SLT-1-=-SLT-2 P.--HO-NO P NO P NO R YES>NOTE 1 2-WCR-953-3 0 DA A K/6 0 2 A EF-1 EF-5--EF-7 ET-005 SLT"1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO-HO NO NO YES>NOTE 1 2-WCR-954-4 0 DA A K/6 0 C 2 A A EF-1 EF-5 EF.-7 ET-005 SLT-1 EF-1 EF-5.EF-7-=ET"005 SLT-2 P NO HO=P-=-HO-P NO R YES>NOTE 1 2-WCR-955 0 DA 3 A J/3 0 C 2 A A EF"1 EF"5 EF-7 ET-005-SLT-1 EF-1 EF-5 EF"7 ET-005 SLT-2 P NO NO P NO P-NO.R YES>NOTE 1

0 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE QPiRKRY SHEET-UNIT 2 SYSTEM HAME-:-NON=ESSENTIAL SERVICE..HATER

=FLON DIAGRAM:.2"5114A-27 RUN DATE AHD TIME: 14SEP87:13:28-VALVE----=-I VALVE-POSITION-I I I NUMBER REV TYPE SIZE ACT F~D.I POKER SAFETY I CD A/P CAT TYPE COORD I-OPER.=FUtKT I CL=ASME-SECTION-Xl PRlt1 TEST TEST TEST RELIEF REQUEST(S)

REQUIRED.PERFORMED=MODE 2-NCR"944-4 0 DA 3 A J/6 0 C 2 A A EF-1 EF"5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7.ET-004 SLT-2 P P R NO HO HO NO YESp NOTE 1 2=NClL945 0 DA==3=-=-A:=J/3 0-----C 2--A---A-EF.-)EF-5 EF-7 ET-005 SLT-1--EF-l.-EF"5 EF"7 ET"005 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2-NCR-946-2 0 DA A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-)EF-1 EF-5 EF-7 ET-004 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2"NCR-947-3 0 DA 3 A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO NO P NO P HO R YESp NOTE 1 2-NCR-948M 0 DA 3 A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET"005.SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO t/0 P HO P NO-R YESp NOTE 1 0!1 I I

=0 e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sly IARY SHEET-UNIT 2 SYSTEN-NANE:

-NOH=ESSENTIAL-SERVICE-HATER-.

-=---.=.FLOH DZAGRAH: 2-5114A-27 RUN DATE AND TINE: 14SEP87:13:28-VALVE I--VALVE POSITION-I I I ASNE SECTION XZ HU)0)ER REV TYPE SIZE ACT F D I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORD I OPER FACT I CL REQUIRED PERFORNED tiODE 2"HCR-934 0 DA 3 A K/2 0 C 2 A A EF-1 EF-5 EF-7 ET=005 SLT-1 EF-1 EF-5 EF-7 ET=005 SLT-2 P HO NO P HO P NO R YES'OTE 1 2=HCR-$35==-0-DA-=-3--.=-A-=J/2--0-=----.C-.-----2--A EF-1-EF-5 EF-7 ET-005 SLT-1---EF-1 EF-5 EF-7 ET-005 SLT-2 P P R NO HO HO HO YESp HOTE 1 2"HCR" 941"1 0 DA A J/6 0 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5-EF-7 ET-005 SLT-2 P P R NO HO HO HO YES>NOTE 1 2-HCR-942-2 0 DA A J/6 0 2 A A EF-1 E F-5 EF-7-ET-004 SLT-1 EF-1 Ef-5-EF"7 ET-004 SLT-2 P P P R NO hN)HO=HO YES>NOTE 2-HCR"943-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-5 EF-7--ET"004 SLT-1 EF-1 EF"5 EF"7 ET-004.SLT-2 P P P R HO HO NO NO YES>NOTE 1

0~DONALD C.COCC NUCLEAR PLAtti SECOND TEt(YEAR INTERVAL VALVE SC0)ARY SHEET-UNIT 2 SYSTEN-HAtfE:=-HON-ESSENTIAL=-

SERVICE-HATER==-

==-=--'=--FLON-DZAGRAN) 5114A-27 RUN DATE AHD TINE: 14SEP87:13:28

---VALVE-----==--I VALVE-POSITION-I I I ASt)E SECTION-XI-HETER REV TYPE SIZE ACT F AD I PONER SAFETY ICD A/P CAT PRZN TEST TEST TYPEiCOORDI OPER----FUHCT=ICL--REQUZRED-----PERFORMED TEST RELiEF REQUEST(S)

ViODE 2-)')CR-929-3 0 DA 3 A K/6 0 C 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7--ET=005==-ET=005 SLT-1 SLT-2 P P R HO HO NO ti'0 YES>NOTE 1 2"NCR-930"3=0-=DA

--=3-=---=-A==-K/2-0-=-=C-----2.-A-A-EF-1-EF"5 EF-7 ET-004 SLT-1---=EF=1-EF-5 EF-7 ET-004.SLT-2 P P R-HO HO NO N)YES>NOTE 1 2"NCR-931-3 0 DA 3 A J/2 0 2 A A EF-1-=EF-5=--EF-7 ET-004 SLT-1 EF"1--EF-5 EF-7 ET-004 SLT"2 P P P R HO HO NO HO YESp NOTE 1 2-NCR-932-4 0 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7---.--ET-004 SLT-1 EF-1 EF-5--EF-7 ET-004 SLT-2 P P-P R NO HO HO HO YES>NOTE 1 2-HCR-933 0 DA A K/6 0 C 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-005-=---=ET-005 SLT-1 SLT-2 P P P R NO HO YES>NOTE 1 0 0 DOHALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE S!RCIARY SHEET-UNIT 2 SYSTEM=NAME:

-NN-ESSENTIAL-SERVICE-WATER-=--=-=-.FLOW.DIAGRAM:--

2-511%A-.27-RUH DATE AND TIME: lOSEP87:13:28 VALVE-=----=--I VALVE-POSITION-I-I I Nk)DER REV TYPE SIZE ACT F~D t POWER SAFETY I CD A/P CAT TYPE-COORDI OPER=-FLNCT ICL-=AQK SECTION-XZ PRIM TEST TEST REQUIRED PERFORMiED TEST RELIEF REQUEST(S)

MiODE 2-WCR-924-2 0 DA A J/6 0 2 A A EF-1 E F-5 EF-7----------ET-"005 SLT-1 EF"1 EF-5 EF-7 ET-005 SLT"2 P P P R NO NO HO NO YESp NOTE 2-WCR-925-2=-=0-

-DA---3---A--=K/6-=O.=--=--C--==---2.-A--A--EF-1=---EF-5 EF-7 ET-005 SLT-1-EF-1-EF-5 EF-7 ET-005 SLT-2 P NO HO P NO P NO R YES>NOTE 1 2-WCR;926-2 0 DA A K/2 0 C 2 A EF-1 EF-5--EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO HO HO HO YES'OTE 1 2-WCR-927-2 0 DA 3 A J/2 0 C 2 A EF-1 EF-5-----EF-7=ET-005 SLT-1 EF-1 EF-5 EF-7=-ET-005 SLT-2 P P R NO NO HO-NO YESp NOTE 1 2-WCR-928-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-5 EF-7*--ET-005-.SLT-1 EF-1 EF-5 EF-7--ET-005-SLT-2 P P R HO HO N)HO YESp NOTE 1

0 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtD!ARY SHEET-t)NZT 2 SYSTEM-NAME:

-ttON-ESSENTZA~ERVZCE-HATER

.--==------FLON DIAGRAM:-2-5114A-27 RUN DATE AND TIME: 14SEP87:13:28 VALVE-=-=----I-VALVE POSITION-I I I NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE=COORDI-OPER

-FUHCT---ICL=

---

ASME SECTION XZ PRIM TEST TEST TEST RELZEF REQUEST(S)

REQUIRED PERFORMED MODE 2-HCR-915-4 0 DA 6 A K/4 0 C 2 A A EF"1 EF-5 EF-7 ET-006 SLT-1 EF-1 EF-5 EF-7 ET-006 SLT"2 P P P R HO ltO NO NO YES>NOTE 1 2-HCR"=920-1==0

-DA=~=-A--J/6-0----C---=-2-==A=--EF-1 EF"5 EF-7 ET-005 SI.T.-1 EF-1 EF-5 EF-7 ET-005 SLT=2 P P R HO HO NO HO YESi HOTE 1-=-2-HCR-921-1 0 DA A K/6 0 2 A A'F-1 EF-5--EF-7 ET"005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R HO HO-HO NO YES>NOTE 1 2-NCR-922-1 0 DA 3 A K/2 0 C 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF"1 EF-5 EF-7=ET-005 SLT-2 P P P R HO NO NO-NO YES>HOTE 1 2-HCR-923-1 0 DA 3 A J/2 0 2 A A EF"1 EF-5 EF-7-ET-006 SLT-1 EF-1 EF-5 EF-7-ET-006-SLT-2 P ttO HO P th)-P---HO R YES>HOTE 1 0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ItfTERVAL VALVE SLMKRY SHEET-UHIT 2 SYSTEtt-HANE:=ttON-ESSEtlTZA~ERVZCE-HATER==-

--=-FLOtl DZAGRAH:---

2-5114A-27 RUN DATE AHD TINE: 14SEP87:13:28 VALVE I VALVE POSITION I I I-ASNE-SECTION XZ-HUtlDER REV TYPE SIZE ACT F.D~I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)

-TYPE COORDI OPER---FUNCT=ICL--=----REQUIRED-

---

PERFORHED

-MODE 2-HCR-910-3 0 DA 6 A J/4 0 C 2 A A EF-1 EF-5 EF"7 ET-006-SLT"1 EF-1 EF-5 EF"7 ET-006 SLT-2 a NO HO a NO P-NO-----=-R YES>HOTE 1 2-HCR-911-3 DA=--6--A---K/4-=0--=-C--=-=-2.-=--A=--A=-EF-1---EF-5 EF-7 ET-005 SLT-1-EF-1 EF-5 EF-7 ET-005 SLT-2 P--=NO HO P HO P NO R YES>HOTE 1 2-HCR-912-4 0 DA 6 A J/9 0 2 A A EF-1 EF-5 EF-7 ET-009 SLT-1 EF"1-EF"5-EF-7 ET-009 SLT-2 P P R NO HO-HO HO YES'OTE 1 2-lCR-913-4 0 DA 6 A K/9 0 2 A A EF-1 EF-5--EF-7-ET-008 SLT-1 EF-1 E F-5 EF-7-ET-008 SLT-2 P P P R HO HO HO HO YESp HOTE 1 2-HCR-914&

0 DA 6 A J/4 0 C 2 A A EF-1 EF-5 EF-7 ET-005----.SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P NO P--=NO R YES>NOTE 1

0~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtCtARY SHEET-UiiIT 2 SYSTEtt-HAttE:

-NOH"ESSENTIA~ERVICE-HATER--

--===--FLON DIAGRAH:-2=5114A RUN DATE AND TINE: 14SEP87:13:28 VALVE---------I-VALVE-POSITIOH I---=-I I HUiiSER REV TYPE SIZE ACT F~D.I POHER SAFETY I CD A/P CAT TYPE COORD i=OPER=-FUHCT

--I CL---ASHE-SECTION-Xl PRIN TEST TEST TEST RELIEF REQUEST(S)

REQUIRED PERFORNED NiODE 2-ItCR-905-2 0 DA 6 A K/9 0 C 2 A A EF-1 EF-5 EF-7 ET-006 SLT-1 EF-1 EF-5 EF-7 ET=006 SLT-2 P P R ttO NO ttO HO YESp NOTE 1 2-HCR-906-2 -DA-=-6----A.--J/4-0-==-=C=--=--2=--A-A.---EF-1-EF-5 EF-7 ET"006=SLT-1 EF-1-EF-5 EF"7 ET-006 SLT-2---P NO HO P NO P HO-R---YES>NOTE 1 2-HCR-907 0 DA 6 A K/4 0 C EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO NO t<0 NO YES>NOTE 1 2-HCR-908-3 0 DA 6 A J/9 0 C 2 A EF-1 EF-5--EF-7----ET-008 SLT-1 EF-1 EF-5-.--EF"7==ET-008 SLT-2 P-=-P R t<0 HO NO HO YES>HOTE 1 2-HCR-909-3 0 DA 6 A K/9 0 C 2 A EF-1 EF-5 EF-7--ET-006-SLT-1 EF-1 EF-5 EF-7-ET-006 SLT-2 P P P R HO HO HO HO YES'OTE 1

O.DOHALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SlPiOARY SHEET-UiHZT 2 SYSTEM NAME'NON=ESSENTIAL SERVICE HATER=-FLOH DIAGRAM:..2".5114A-.27 RUN DATE AND TIME: 14SEP87:15:28 VALVE.=....I.VALVE.POSITION I..I 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.COORDl-OPER

-FUHCT=ICL------

---

REQUIRED.PERFORMED HiODE 2-HCR-900-1 0 DA 6 A J/9 0 C 2 A A EF-1 EF-5 EF-7 8 ET 00 SLT-1 EF-1 EF-5 EF-7 ET-008 SLT-2 P P P R NO NO NO.NO.YES>NOTE 1 2=HCR"BOl"I=-

0-DA 6.-A.=-K/9-.-0 C 2 A A-=--EF"1.-

---

EF-5 EF-7 ET"008 SLT-1-EF"l.EF-5 EF"7 ET-008.SLT-2------P=HO NO P NO P NO R YES>.NOTE 2-HCR-902-1 0 DA 6.A J/4 0 C 2 A EF-1 EF-5 EF"7 ET-005 SLT-1 EF-1 EF,-5 EF-7 ET-005 SLT"2 P P P R HO HO HO NO YES>NOTE 1 2-HCR-905-1 0 DA 6 A K/4 0 2 A A EF-1 EF"5 EF=7-, ET"006 SLT-1 EF-1 EF-5 EF-7-ET-006 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2-HCR-904-2 0 DA 6 A J/9 0 C 2 A A EF-1 EF-1 P EF-5 EF-5 EF"7 EF-7 P ET==008 ET.=008.P SLT-1 SLT-2 R NO HO NO NO=YES>NOTE 0

0 0 DONALD C.COOK NUCLEAR PLANT SECOttD TEN YEAR INTERVAL VALVE SL.uSRY SHEET-UittZT 2 SYSTEH-NAttE:=-ESSEttTXAL=SERVICE-HATER-

-=-===.-FLOH DIAGRAH:-2-5113=36 RUN DATE AND TINE: 14SEP87:13:28 VALVE--==-=----=I-VALVE-POSZTXON I I I=ASNE SECTXOtt XZ HURDLER REV TYPE SI2E ACT F.D.I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)

==--TYPE COORDI-OPER.---FUNCT-ICL==---REQUIRED PERFORHED--

ttODE=2-l'tRV-722-CD 0 3H 4 A K/8 0 0 3 A B EF-1 EF-7 ET-NA NOTE EF-8 NOTE P R YESp NOTE 3 YESp NOTE 3 YESp NOTE 3 2-HRV-724-CD 0 3H A H/8 0 0 A B EF1 NOTE EF-7 EF-8--ET-NA=-=---NOTE P R 3-YESp NOTE 3 YESp NOTE 3=-=YESp NOTE-3-2-HRV-726-AB 0 3H 4 A K/8 0 0 3 A B EF-1 NOTE 3 EF=7=-EF-8 ET-NA NOTE 3 P YESp NOTE 3 R YESp NOTE 3 YESp NOTE 3 2=WRY=.728"AB 0=MH=4=A H/8-0=-0..3-A--B-EF-1---NOTE 3 P.YESp NOTE3 EF-7 EF-8 R YESp NOTE 3 ET-ttA NOTE 1 YESp NOTE 3

.~DONALD CD COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiARY SllEET" UiNIT 2 SYSTEN-NAHE:

-ESSENTXA~ERVICF=-ttATER

---

==--=--FLON DIAGRAM:--2=5113-36 RUiN DATE AND TINE: 14SEP87t13:28 VALVE--------I-VALVE-POSITION-I----------------ASttE-SECTION XI-I I NUBBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRItl TEST TEST-TYPE-COORDI-OPER-

--FLDtCT ICL--==-REQUIRED-

--PERFORtlED TEST RELIEF REQUEST(S)

N)DE 2-Ã~iO-726 0 BF 6 HO K/6 C 0 3 A B EF1 EF-5 ET-023 EF-1 EF-5 ET"023 P HO NO P NO 2-HMO-728 0 BF 6 HO L/6 C 3 A B EF1 EF-5=-==--ET-024-EF-1 EF-5 ET-024-=-2-Htl0-734 0 BF 16 HO H/3 0/C 0 3 A B EF-1 EF-1 EF"5=EF-5 ET-054 ET-054 P HO HO P NO 2=)D'i0=738

---0---BF--.16----N)-K/3--0/C-0--3 A-B-EF-1-EF"5 ET-055 EF-1 EF-5 ET-055 P-HO-HO P HO 2-RtO"744 0 BF 4 HO J/6 C 0 A B EF-1 EF-5 ET-036 EF-1 EF-5 ET-036 P HO HO P NO 2-IC iO-753 0 BF 6 HO H/5 C 0 3 A B EF-1 EF"5 ET-024.EF-1 EF-5 ET-024 P NO NO P.HO 2-Ht40-754 0 BF 4 HO K/6 C 0 3 A B EF-1 EF-1--EF-5-----EF-5-ET-026 ET-026 P HO tlO=P HO

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAiR INTERVAL VALVE SU)IIRRY SHEET-UiNIT 2 SYSTEN=NANE:=.ESSENTIAI SERVICE-HATER=-=

--.=--FLOH-DIAGRAlf: 5113-36 RUN DATE AND TINE: 14SEP87:13:28 VALVE--===----t VALVE POSITION=I

=-------I I-AS)K SECTION XI NUN)ER REV TYPE SIZE ACT F~D.I POKER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REIWEST(S)

=------TYPE-COORDI OPER--FUHICT-ICI.------REQUIRED PERFORHED---HiODE-2-H)lO-704-2H 0 BF 20 HO H/8 C 0 3 A B EF1 EF-1 EF-5 EF-5 ET-054 ET-054 P P 2-)040-706 0 BF 20 HO e/8 0 0/C 3 a e EF-1 EF-5 ET-056--EF-1 P NO EF-5 HO--ET-056----P HO 2-HNIO-708 0 BF 20 HO 6/6 0 0/C 3 A B EF-1 EF-1.EF-5-EF-5 ET-055 ET-055 P HO HO P NO 2-IOIO-215 BF-12-MO--M/5.C.-0-3--A-B=-EF-1 EF-5 ET-034 EF-1-EF-5 ET-034 P-N)NO P HO 2-hYiO-718 0 BF 12 HO N/5 C 0 A B EF-1 EF-5 ET-036 EF-1 EF-5 ET"036 P N)NO P HO 2-NlO-722 0 BF 6 HO H/6 C 0 3 A B EF-1 EF-1 P NO EF-5 EF-5 NO---ET-023-ET-023---.P-NO 2-h~O-724 0 BF 6 HO N/6 C 0 3 A B EF-1-EF"5-ET-020 EF-1 P EF-5------=------ET-020 P HO NO HO 0'

0.~DONALD C.COOK NUCLEAR PLANT SECOttD TEN YEAR INTERVAL VALVE SLPi~tARY SHEET-UiNZT 2 SYSTEH-NANE:

-ESSENTIAL-SERVICE-HATER

---=-.--FLOH-DZAGRAtt:

-=2-5113-36 RUiN DATE AND TZttEt 14SEP87:13:28-VALVE==----==--=I--VALVE-POSITION I I I-ASttE.=SECTION-XX NUiiBER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD I OPER=FUiN'CT-ICL--=REQUIRED-PERFORttED

--t'iOOE 2-ESH-170-S 0 BF 3 H F/1 0 3 A B EF1 EF"1 P NO 2=ESH-171-N

---0 BF-D tt-.-F/<-C-0-=--.3=-A=B.EF-1 EF-1 P=NO 2-ESH-171"S 0 BF 3 H F/1 C 0 3 A B EF"1 EF-1 P NO 2-ESH-240 0 BF 6 H H/5 C 0 3 A B EF1 EF-2 R YES'OTE 2 2-ESH-243 0 BF 4 H J/7 C 0 A B EF"1 EF-2 R YES>NOTE 2 2=SV.-14-2E

-.---0=-REL--1-----SA---L/1-C---=-0=-3-=A C--TF-1---TF-1 2-SV-14"2H 0 REL 1 SA lVl C 0 3 A C TF-1 TF-1 2-SV-15-2E 0 REL 0.75 SA G/3 C 0 3 A C TF-1 TF-1 2-SV-15-2H 0 RE L 0.75 SA J/4 C 0 3 A C TF"1 TF-1~V=16=AB 0 REL D~A=L/8..C-0.3 A C TF=1 TF-1 2-SV-16-CD 0 REL 1 SA L/8 C 0 A C 7 F1 TF-1 NO 2-hYiO-703-2E 0 BF 20 NO N/8 C 0 A B EF1 EF-5 ET-053 EF"1 EF-5 ET-053 NO NO HO

0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUi81ARY SHEET-UNIT 2 SYSTEM-NAME:

-ESSENTIAL-SERVICE-HATER

-=-=-=-.--=FLOW-DIAGRAM: 5113 -==RUN DATE AND TIME: 14SEP87:13:28 VALVE-I VALVE POSITION I---------AQ)F=SECTZON-XZ-I I NLRGER REV TYPE SIZE ACT F.D~I POWER SAFETY (CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

---TYPE-COORDI OPER---FUNCT=ICL---=------REQUIRED--=-PERFORMED-

--MODE------2-ESW-102-2E 0 CK 20 SA H/8 C 0 3 A C CF-1 CF-1 P HO 2-EN(-102-2W=-0=-CK= =-SA H/8 C===.0-3-A-.C-CF-L CF-1 P NO 2-ESH-141 0 CK 6 SA K/6 C 0 A C CF1 CF"1 P NO>NOTE 1 2-ESH-142 0 CK 6 SA L/6 C 0 3 A C CF1 CF-1 P NO)HOTE 1 2-ESH-143 0 CK 6 SA M/6 C 0 3 A C CF-1 CF-1 P NO>NOTE 1 2=ESW-144=0=CF~6

---

SA--H/6----C-----

--0----3-A-C-===CF-1-=---CF-1--.P NOp NOTE 1---2"ESW-145 0 BF 4 M J/6 C 0 3 A B EF-1 EF-2 R YES>NOTE 2 2-ESW-168-N 0 BF 3 M H/1 C 0 3 A B EF-1 EF-1 P NO 2-ESW"168-S 0 BF M H/1 C 0 3 A B EF1 EF-1 P HO 2-ESW-169-N -BF=3=--H=-=-G/1-=0 C-----3-A-B----EF.-l-EF-1---=--P-NO 2-ESW-169-S 0 BF 3 M G/1 0 A B EF1 EF-1 2"ESW-170-N 0 BF 3 M F/1 0 C 3 A B EF-1 EF-1 P HO SYSTEN-NANE:=FEEDHATER DOiNALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiHARY SHEET-i%IT 2=FLON-DZAGRAH:=--2-5106A-41--

RUN DATE AHD TINE: 14SEP87:13:28

---

VALVE--=

-==-=-=-=I=VALVE-POSITION I--I I--ASME SECTION XZ--HU'SER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIt1 TEST TEST TEST RELIEF REQUEST(S)

-TYPE COORD I OPER--FUHCT-I CL---.--REQUIRED-PERFORNED-NiODE 2-FN"160 2 CK 1 SA N/9 C 0/C 3 A C CF 1 CF-1 P NO>NOTE 5 2-FN-161-=0

--CK--8-----SA-J/7 C-.0---3--A--C---.CF-1-CF-1 P HO 2-SV-160-I 0 REL 0.75 SA E/1 C 0 3 A C TF-1 TF-1 R HO 2"SV-140-2 0 REL 0.75 SA D/I C 0 3 A C TF-1 TF-1 2-SV-169-A 0 REL 0.75 SA K/9 C 0 3 A C TF-1 TF-1 R N)2-SV-169-8--

--0--=-REL-=0.75 SA G/9--C 0----3 A C TF-I-=TF-1 R HO--

SYSTEM-NAMF:.--FEE DNATE R DOiNALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET" UiNIT 2--=FLOM.DIAGRAM:-

.2=5106A>>41 RUN DATE AND TZtfE)14SEP87:13)28

-VALVE-----------=-=I-=VALVE POSITION-I-I I AstlE SECTION XZ NUMBER REV TYPE SZ2E ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI-OPER

-=-FUiiCT ICL=----REQUIRED PERFORMED-

---

MODE 2-FN-132-3 2, CK SA D/5 C 0/C 2 A C CF-1 NOTE 1 YES>NOTE 1 2-FH"132 =2=CK=~---SA C/4.C--0/C-2.A=..C----CF.-1-.-NOTE 1=---=---YES>NOTE 1 2" FH-134 0 CK 10 SA B/9 C 0 3 A C CF1 CF-1 P NO>NOTE 2 2-FN-135 0 CK 8 SA E/8 C 0 A C CF1 CF-1 P NO>NOTE 2 2-FM-138-1 2 CK 4 SA C/4 C 0/C 2 A C CF1 NOTE 3 YESp NOTE 3 2-FH-138-2

-2=CK--4:-.--=SA=D/5-C=-0/C---2--A C----CF-1-ROTE 3--=--=-YES>HOTE 3--2-FH"138-3 2 CK SA D/5 C 0/C 2 A C CF-1 NOTE 3 YES>N)TE 3 2-FW-138-4 2 CK 4 SA C/4 C 0/C 2 A C CF-1 HOTE 3 YES>NOTE 3 2-FH-149 0 CK 0.75 SA D/2 C 0 3 A C CF1 CF-1 P hN)p NOTE 4 2"FN"150=-

=-0-CK--0.75---SA=-D/3 C-0 3 A C---CF-1-CF-1 P NO>HOTE 4 2-FH-153 2 CK 1 SA tt/9 C 0/C 3 A C CF-1 CF-1 P HOp NOTE 5 2-FH-159 0 CK 6 SA L/7 C 0 3 A C CF1 CF-1 P HO 4

SYSTEM NAME:=FEEDHATER DOiiALD C.COOK NUCLEAR PL)80'ECOiHD TEN YEAR INTERVAL VALVE SUi'IMARY SHEET-UNIT 2 FLOH DIAGRAM: 2&106A=41 RUH DATE AHD TIME: 14SEP87:13:28 VALVE--=--..---I-VALVE-POSITION-I---.-.---.----.--.-----ASME=SECTIOH-XI I I 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--FUHCT-ICL----REQUIRED

=PERFORMED.MODE 2"FMiO-242 0 GL 4 MO B/4 0 0 3 A B EF-1 EF-1 EF-5 EF-5 ET"030 ET-030 NO NO NO 2-FRV-247 0 GL 1 A M/9 C C/0 3 A B EF-1 EF-5 EF=7==-ET-008 EF-1 EF-5 EF=7=ET-008-P P HO NO.NO 2=F.RV=257 0-G~A H/9 C C/0 3 A B.EF-1 EF"5 EF-7 ET-005 EF-1 EF-5 EF-7 ET-005 P P P HO.N)HO NO 2-FRV"258 0 GL 1 A E/9 C C/0 3 A B EF-1 EF-5 EF=-7==ET-005 EF-1 EF-5 EF-7 ET-005 P P P NO HO NO HO 2"FHD24 0 CK-8---=SA.F/7-C--0-3-=A-C=CF-1-------CF"1-----P.-HO 2"FN-128 0 CK 6 SA H/7 C 0 3 A C CF-1 CF-1 P HO 2-FH-132-1 2 CK 4 SA C/4 C 0/C 2 A C CF-1 NOTE 1 YESp NOTE 1 2-FH-132-2 2 CK SA D/5 C 0/C 2 A C CF-1 II',OTE 1 YES>NOTE 1

SYSTEM-NAME:

-FEEDNATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET UiiIT 2 FLON DIAGRAH: 2-5106A"41 RUN DATE AND TIHE: 14SEP87:13:28 VALVE----I-VALVE-POSITION=I

--.----.---ASHE S CTION XZ I I NRlBER 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-HODE-2" FHO-211 0 GL 4 ViO B/4 0 0 3 A B EF)EF-5 ET-025 EF-1 EF-5 ET-025 P NO NO P NO 2-FHO" 212 0 GL HO B/4 0 0 A B EF1 EF-1 EF-5 EF-5=ET.-031.-ET-031 2FH0221 0 GL 4 HO C/5 0 0 3, A B EF)EF-1.EF-.5..EF-5 ET-021 ET-02)P NO NO P NO 2=FH0=222 0 GL 4..HO C/5 0 0 3..A=B--EF-1-----EF-1 P NO EF-5.EF-5 NO ET-036 ET-036 P NO 2" FHi 0"23)0 GL 4 HO C/5 0 0 A B EF-1 EF-5 ET-026 EF-)EF-5 ET-026 P NO NO P NO 2-FHO-232 0 GL 4 HO C/5 0 0 3 A B EF-)EF-1 EF-5 EF-5 ET-034=-=ET=034.=P NO NO P NO 2-FHiO-241 0 GL 4 HO B/4 0 0 3 A B EF-1-EF"5.ET-024 EF-1-EF-5 ET"024 P NO NO P NO

SYSTE!1-NAttEt

-FEEDHATER-DONALD C.COOK NUCLEAR PLAttT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UNIT 2 FLON DZAGRAtt:--2-5106 "34-RUN DATE AHD TIttE: 14SEP87:13:28 VALVE---=--I VALVE-POSITIOtt I------.-------ASttE SECTION XZ I I tlUt%ER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)

-TYPE COORDI OPER--FUNCT--ICL---.---REQUIRED----PERFORttED

-ttODE 2-FRV-240 0 AG 14 A H/5 0 2 A B EF-1 EF-5 EF-7 ET"005 EF-2 EF-5 EF-8 ET-005=-C YES7 NOTE 1 ,NO C ttO)NOTE 1 C-HO 0

SYSTEH-NAHE:=

FEEDklATER--

DOiNALD C.COOK NP'LEAR PLANT SECOND TEH YEAR INTERVAL VALVE SVC%RY SHEET-UNIT 2-.-FLOH.DIAGRAH:=-2-.5106.-34 RUN DATE AND TINE: 14SEP87:13:28 VALVE---=----==-.-=-=-I VALVE-POSITION=-I-I I NUHBER REV TYPE SIZE ACT F D.I POHER SAFETY LCD A/P CAT-TYPE-COORDI OPER-FUNCT.--ICL-

-==--ASME SECTION XI PRIH TEST TEST TEST RELIEF REQUEST(S)

REQUIRED.-==-PERFORHED--NODE 2-FHO-201 0 GA 14 HiO G/5-0 C 2 A EF-1 EF-5 ET-020 EF-2 EF-5 ET-020 YESp NOTE 1 HO NO 2-FN)-202 0 GA 14 HO E/9 0 2 A B , EF-1 EF"5 ET-018==EF-2 EF-5=--ET-018=--YES>NOTE 1 NO-.HO 2-FHO"203 0 GA 14 HO F/9 0 C 2 A B EF-1--EF"5 ET-019 Ef-2 EF-5 ET-019 C YES>NOTE 1 HO C HO 2-FHO-204-=0-GA~4=---N)=-H/5--0---C=-2=-A-B-EF-l.-EF-5 ET-019--EF=2----==-EF"5 ET-019 YESi NOTE 1--HO NO 2-FRV-210 0 AG 14 A G/5 0 EF-1 EF-5 EF-7 ET-005--EF-2 EF-5 EF-8-ET-005 C YES>HOTE 1 NO C NOi HOTE 1 C--NO-2-FRV-220 0 AG 14 A E/9 0 C 2 A 8 EF-1 EF-5 EF-7 ET-005 f F-2 EF-5 EF-8 ET-005 C YES>HOTE 1 NO C HOp HOTE 1 C NO 2-FRV-230 0 AG 14 A F/9 0 2 A B EF-1 EF-5 EF-7 ET-005 EF-2 EF-5 EF-8 ET-005 C C C YES>NOTE 1 NO HOp NOTE 1 HO 0 DONALD C.COOY.NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SALARY SHEET-UNIT 2 SYSTEM-NAllE:~TEAM GEHERATIHG.SYSTEM-

-.-..-=.=-.=FLOH DZAGRJQJ: 2=5105D=2 RUN DATE AND TZME: 10SEP87:13:28

-=VALVF-I-VALVE-POSITION

=I I I ASME=SECTION XZ.NUMBER REV TYPE SIZE ACT F.D.l POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE=COORDI OPER---FUHCT.-ICL REQJZRED PERFORMED MODE 2-SV-3-1 0 REL 6 SA B/5 C 0 2 A C TF-1 TF-1 2=SV."3=2 0-REL.6==SA==M/5=C.

=0=..2=A C TF-1.TF-1 R HO 2-SV-3-3 0 REL 6 SA M/1 C 0 2 A C TF-1 TF-1 R HO 2-SV-3W 0 REL 6 SA B/1 C 0 2 A C TF-1 TF-1

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UI'lIT 2 SYSTEM-NAMEMTEAM

=GENE RATING-SYSTEM-==--=-===----FLOH-DIAGRAM:=2-51059-2 RUN DATE AHD TIME: 14SEP87:13:28 VALVE-==-==I.VALVE POSITIOH I I I-ASME SECTIOH Xl=--NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

-=-------TYPE-COORDI OPER-=FULNCT=-ICL-

---=--REQUIRED--PERFORMED--MODE 2-SV-18-1 0 REL 6 SA 8/5 C 0 2 A C TF-1 TF-1 2-SV-18-2-=-0=-REL--6----SA---L/5---C--0-----=2--A--C-TF-1-TF-1 R NO 2-SV-18-3 0 RE L 6 SA L/1 C 0 2 A C TF-1 TF-1 R NO 2-SV-18-4 0 REL 6 SA 8/1 C 0 2 A C TF-1 TF-1 2"SV-2A-1 0 RE L 6 SA 8/5 C 0 2 A C TF-1 TF-1 2-SV.-RA-2=.0

-.REL-6..-.--SA-.-L/5.C--0.---2-A 0-TF-2 TF-1-R HO 2-SV-2A-3 0 REL 6 SA L/1 C 0 2 A C TF-1 TF"1 R HO 2-SV"2A-4 0 REL 6 SA 8/1 C 0 2 A C TF-1 TF-1 2-SV-28-1 0 REL 6 SA 8/5 C 2 A C TF1 TF-1 2-SV-25-2-0-REI-6---.SA-: L/5.0-0 2 A C TF-1---TF-1 2-SV"28-3 0 REL 6 SA L/1 C 0 2 A C TF1 TF-1 2-SV-28&0 REL 6 SA 8/1 C 0 A C TF-1 TF-1 R HO l

SYSTEtt-NAttE:=STEAtt-GENERATING-SYSTEtt

---0 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVF SUi'tttARY SHEET-UNIT 2--==FLON-DIAGRAtt:=-2-51050 2-=-RUN DATE AHD TINE: 14SEP87:13:28 VALVE-I-VALVE-POSITION-I I I AStfE-SECTION-XL-HUiitER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRZtt TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI-OPER==FUHCT=ICL=-""--" REQUIRED PERFORHED-NODE 2-tkRV-240 1 GA 28 PO B/3 0 2 A B EF-1 EF-3 EF-5 EF-5 EF-7 EF-8 ET" 005-.-=----ET-005 C C-HOp NOTE NO t<0>HOTE 2 NO 2-HRV-241 0 AG 2 A A/1 C 0 2 A B EF-1 EF-5-EF"7 ETF-002 EF-1 EF-5-=EF-7 ETF"002 P HO-==-=HO P HO P HO 2-ttRV-242 0 AG 2 A A/1 C 0 B EF-1 EF-5 EF-7 ETF-002---

EF-1 EF-5 EF-7 ETF"002-P HO HO P ttO P--HO 2-NS-108-2 2 CK SA K/4 C 0/C 3 A C CF"1 CF-2 R YES'OTE 3 2" HS" 108-3 2 CK 4 SA K/4 C 0/C 3 A C CF-1 CF-2 R YES>HOTE 3 2-SV-ZA-1 0 REL 6 SA C/5 C 0 2 A C TF-1 TF"1 2-SV-1A-2-0-RE L-6-SA=-K/5--C---==0--.2-A=C TF-1 TF-1 R-HO-=-=----2-SV-1A-3 0 REL 6 SA K/1 C 0 2 A C T F1 TF-1 R NO 2-SV-1A-4 0 RE L 6 SA C/1 C 0 2 A C TF 1 TF-1 R HO

DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUPssQRY SHEET UNIT 2 SYSTEM-NAME:=-STEAH-GENERATING=SYSTEM--=---

---=-=-=FLON-DIAGRAM:-=

2"51050 RUN DATE AND IIHE: 14SEP87:13:28

---

VALVE-----I-VALVE-POSITION-I-=-=-----------ASHE SECTION-XL-I I NUi'SER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

===--TYPE-COORDI

-OPER-=-FUiNCT

-ICL------REQUIRED PERFORMED=MODE 2-HRV-220 0 GA 28 PO L/7 0 2 A EF-1 EF-5 EF-7=---ET.-005 EF-3 EF-5 EF-8 ET-005 P C C NOp NOTE 2 NO NOp NOTE 2-NO 2-HRV-221 0 AG 2 A H/5 C 0 EF-1--EF-5-EF-7 ET-003 EF-1--EF-5-EF-7 ET-003 P NO NO P NO P NO 2-HRV-222 0 AG 2 A H/5 C 0 EF-1 EF-5 EF-7-.--ET-003 EF-1 EF-5 EF-7 ET-003 P NO NO P NO-P NO 2"HRV"230 0 GA 28 PO H/3 0 C EF-1--=-EF-5 EF-7 ET-005 EF"3 EF-5 EF-8 ET-005 P NO NOTE 2 NO C NOp NOTE 2 C NO 2-HRV-231 0 AG 2 A H/1 C 0 2 A B EF-1 EF-5 EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002=P P-P-NO NO NO=NO 2-HRV-232 0 AG 2 A H/1 C 0 2 A B EF 1=-EF-5-EF-7 ET-003 EF-1 EF-5--EF"7 ET-003 P P P NO NO---NO NO

~~DONALD C.COOK tRCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUtDIARY SHEET UNIT 2 SYSTEM-NAME:

-STEAN.GENERATING SYSTEM-=-.----:--FLON DIAGRAM:-..2-.5105D=2 RUN DATE AND TIME: 14SEP87:13:28

-VALVE I-VALVE=POSITION-I I I AStK SECTION-XZ tmHBER 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.PERFORttED HiODE 2-FN-118-1 0 CK 14 SA B/9 0 2 A C CF-1 CF-2 R YESp NOTE 1 2=FH=118=2=-2=-

CK==14-SA K/8.-0=..C=.2-.A-C.-.CF-1 CF-2 R.YES>NOTE=1 2-FH-118-3 0 CK 14 SA J/3 0 C 2 A C CF-1 CF"2 R YES>NOTE 1 2-FW-118-4 0 CK 14 SA C/3 0 C 2 A C CF"1 CF-2 R YES>HOTE 1 2-MCH-221 0 GL 4 HO K/4 0 0/C 2 A B EF-1 EF-5 ET"049 EF-1 EF.-5 ET-049 P HO NO P NO 2-HCH-231 0 GL 4 HO K/4 0 0/C 2 A B EF-1 EF-5 ET-050 EF-1 EF-5 ET-050 P NO HO P HO 2-HRV-210 0 GA 28 PO 8/7 0 C 2 A B EF-1 EF-3-EF"5---==EF-5---EF-7 EF-8 ET-005 ET-005 C C HOi NOTE 2 NO-HOW HOTE 2 NO 2-MRV-211 0 AG 2 A A/5 C 2 A B EF-1 EF-5 EF-7 ET-003=EF-1 EF-5 EF-7 ET-003 P P--2-HRV-212 0 AG 2 A A/5 C 0 2 A B EF"1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-004 ET-004 P NO HO P HO P NO SYSTEtt-NANE:

-tQIN-STEAN DONALD C.COOK tRCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SViNARY SHEET" UNIT 2---FLOH DIAGRAN: 2-51058 --RUiN DATE AND TINE: lOSEP87tl3:28

--YAivE------I YALYE.POszTIO>l-I I I-ASNE SECTION Xl HUNBER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

=TYPE=COORDI OPER-FLIiCT=ICL------REQUIRED--PERFORNED NODE 2-DCR-310 2 GL 2 A B/3 0 C 2 A B EF-1 EF-5 EF-7 ET-006-EF-1 EF-5 EF-7 ET-006 P ttO NO P HO P NO 2-DCR-320 2 GL 2 A B/2 0 C 2 A B EF-1-EF=5=--=EF-7 ET-006 EF-1 P EF-5-EF-7 P ET-006 P HO-HO--HO HO 2-DCR-330 2 GL 2 A B/1 0 C A B EF"1 EF-5 EF-7 ET-008--EF-1 EF-5 EF-7 ET-008 P HO HO P NO-P NO 2-DCR-300 2 GL 2 A B/2 0 2 A B EF-1 EF-5=-EF-7 ET-009 EF"1 EF-5 EF-7 ET-009 P NO-HO-P HO P NO 2-QT-506 0 GL HO A/8 C 0 3 A B EF1 EF-5 ET-023 EF-1 EF-5 ET"023 P HO NO P HO

~e DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE Sly~>ARY SHEET-UNIT 2 SYSTEM=SQ1E:

-PAL-SAMPLING=S--INST-.

=PAHELS=U-2=--FLIN-DIAGRAM:-.--12-5141F-6

---

RUH DATE AHD TIME: 14SEP87:13:28

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

-=FUHCT-.--lCL--=-

---

REQUIRED PERFORMED-MODE-2-SM-I 0 CK 1 SA A/3 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES'OTE 3 R YES>NOTE 2

DONALD C.COOK NlCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SlMCARY SHEET-UNIT 2 SYSTEN-HANE:

-PAI NlNPLZHG-8=INST.-

PANELS==U-2=FLON-DZAGRAN:.

~2-5141F-6 RUH DATE AND TINE: 14SEP87:13:28 VALVE I VALVE.POSITION.I I I ASNE=SECTIOH-XZ==

=----HUYBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

=--==TYPE-COORDI=OPER--=-

-FACT-ICL-------REQUIRED PERFORMED-NEODE 2-ECR-31 2 GL 1 A B/3 0 2 A A EF-1 EF-5 EF-7-=-ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO HO P HO P NO R YES>NOTE 2 2-ECR-.32-2-GL-5.-2-B/5--5----2-=2-=A=-=-A===EF-1 EF-5 EF-7 ET-005-----SLT-1--EF-1-EF-5 EF-7 ET-005-SLT" 2 P P P R NO HO HO HO YES>HOTE 2 2"ECR-33 2 GL 0.75 A B/2 0 C A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5-EF-7 ET-004 SLT-2 P P R HO HO-NO HO YES>NOTE 2 2-ECR-35 2 GL 1 A B/2 0 C 2 A A EF-1 EF-5 EF=-7-ET-004 SLT-1 EF-1 EF-5-----EF-7 ET-004 SLT-2 P R HO HO NO NO YES>NOTE 2 2-ECR-36 2 GL 1 A B/3 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-2 EF-5 EF-8 ET-004 SLT-2 C C R YES'OTE 1 HO NOR NOTE 1 YESR NOTE 1.YES'OTE 2 0 f 0 o DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UNIT 2 SYSTEH-NANE:

-PAS-LIQUID 2-GAS==UNIT=2

==-=.FLON DIAGRAN:...

12=5141C-.8

.RUH DATE AHD TINE: 14SEP87:13:28 VALVF----t--VALVE-POSITION I I ASME..SECTION.

XZ NEER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIN TEST TEST--TYPF COORD I-OPER=.-.FACT ICL-=-.--REGUIRED PERFORNED TEST RELIEF RE@JEST(S)

NODE 2-ECR-536 0 GL 0.5 A L/2 C A EF-1 EF-5 EF-7 ET-003..SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P P R HO HO HO HO YES>HOTE 1 0

0.DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtaaARY StlEET-UNIT 2 SYSTEH-NAHE-:=-PAS-LIQUID GAS-UNIT-2----------FLON.DZAGRAH 5141C-8

=RUN DATE AND TINE: 14SEP87:13:28-VALVE---=----I VALVE POSITION=-I

-=--=I I ASttE SECTXON XL--h REER REV TYPE SZZE ACT F AD I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI-OPER

-FUNCT---ICL---==--=-=----REQUIRED---PERFORHED-

-tlODE 2-ECR-416 0 GL 0.5 A H/6 C 2 P A EF-1 EF-5 EF-7 ETF-002 SLT"1 EF-1 EF-5'EF-7 ETF-002-SLT"2 P P R HO t<0 HO NO YES'OTE 1 2-ECR-417--0-GL--0.5--A---H/6--C.=-------C

---2----P=-A--EF-1==-==-=-EF-5 EF-7 ETF-002 SLT-1 EF-1====-==-=-=P---HO-EF-5 NO EF"7 P NO FTF"002 P NO SLT-2 R YES>NOTE 1 2-ECR-496 0 GL 0.5 A H/8 C 2 P EF-1-EF-5 EF-7 ETF-002 SLT-1 Ef-1=-=-EF-5=EF-7 ETF-002 SLT-2 P P R NO-HO NO HO YESp NOTE 2-ECR-497 0 GL 0.5 A H/8 C C 2 P EF-1 EF-5-EF-7-=ETF-002 SLT-1 EF"1 EF"5=EF-7-ETF-002 SLT-2 P P P R tm tlO NO ND YES>NOTE 2-ECR-535 0 GL.0.5 A H/2 C C 2 P A EF-1 EF-5 EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P R NO NO HO ttO--YESp NOTE

'

DONALD C.COOK NUCLEAR PLANT SECOiND TEN YEAR INTERVAL VALVE SUEEENRY SHEET-UiNIT 2 SYSTEH-NAME:

=HDS<<VENTS-2i-DRAINS

--FLON-DIAGRAH:=12-5137A RUN DATE AND TIHE: 14SEP87:13:28 VALVE-I VALVE-POSITION I I I=-ASHE=SECTION

=Xl-AMBER 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

---HiODE---2" DCR-621 0 DA 1 A N/9 0 2 A A EF-1 EF"1 EF"5 EF-5 EF-7 EF"7-ET-005=---

--ET-005-SLT-1 SLT-2 P=P R NO NO NO NO YESp NOTE 1 2-N-160-O=CK=l==SA=

--F/4-0--==-C--=2=-A--AC-:-CF ---=----CF-2---=-SLT-1 SLT-2--.-2-..TER.MOTE 2 R YESp NOTE 1 2-SF-159=-==--=0 DA-3=----H---'/5--C----

==---C----.-

=2---P--A--SLT-1--..-.-SLT-2---.---.--R----YESp-NOTE 1 2-SF-160 0 DA 3 H F/5 C 2 P A SLT-1 SLT 2 R YESp NOTE 1 0 IP SYSTEN-NANE:-HDS-VEttTS-tt-DRAINS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE RPittARY SHEET-UHIT 2 F LOlt-DIAGRAtt:-=%2-5137A-2l=-

RUH DATE AND TINE: 14SEP87:13:28

-VALVE-=-----l VALVE-POSITIOiN j I I ASttE SECTION XI ttUtSER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

=--=TYPE-COORD I=-OPER:---FUitCT I CL--------REQJIRED-=--PERFORYiED

.ttODE 2-DCR-206 0 GL A E/8 0/C 2 A A EF-1 EF-5 EF-7 ET=-005--SLT-1 EF-1 EF-5 EF-7-ET-005 SLT-2 P P P R NO HO NO NO-YESp NOTE 1 2-DCR-207-O=DA---I--=A---F/4--0---=-C==-=--2-A--A-=---EF-1-EF-5 EF-7 ETF-002 SLT-1-EF-1-EF-5 EF-7 ETF-002 SLT-2 P P P R HO=HO N)NO YES'OTE=1 2-DCR-610 0 DA 2.5 A M/9 0 2 A A EF1--=EF=S=EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P R NO HO t<O NO YESp NOTE 1 2-DCR-611 0 DA 2.5 A N/9 0 2 A A EF-1 EF-5 EF-7---ET-004 SLT-1 EF-1 EF"5 EF"7 ET-004 SLT-2 P-P P R NO NO NO-NO YESp NOTE 1 2-DCR-620 0 DA 1 A tt/9 0 2 A A EF-1 EF-5 EF"7-ET-004-=-SLT-1 EF"1 EF-5 EF-7 ET-004 SLT-2 P P P R HO NO NO t,'0 YESp NOTE

SYSTEM-NAME:=NDS-VENTS-8-DRAINS DOHALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUta>ARY SHEET-UNIT 2 FLON.DIAGRAM:

.-12-5137A-21

==RUN DATE AND TIME: 14SEP87:13:28 VALVE I-VALVE POSITXOAN-I-I I-ASME SECTION XZ NlRSER REV TYPE SIZE ACT F~D.I PWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD I=OPER=-=--

FUNCT=-I CL-----REQUIRED--PERFORMED--MODE 2-DCR-201 0 DA 1 A E/4 C 2 P A EF-1 EF-5 EF-7 ETF=002 SLT-1 EF-1 EF-5 EF"7 ETF-002 SLT-2 P P P R HO HO NO HO YES>NOTE 1 2-000-202 0-02-.0..75--2--0/5 0-A=A--EF=l EF-5 EF-7 ETF-002.SLT-1.-EF-1=--=-EF-5 EF-7 ETF-002 SLT-2 P P R.NO--NO HO NO YES>NOTE 1 2"DCR-203 0 DA 1 A F/4 C 2 P EF-1 EF-5-EF-7 ETF-002 SLT-1 EF-1 EF"5 EF-7 ETF-002 SLT"2 P HO NO P HO P NO R YES>NOTE 1 2-DCR-204 0 DA 0.75 A F/5 0 C 2 A EF-1 EF-5 EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7-ET-003 SLT-2 P NO NO P---HO P HO R YES>HOTE 1 2-DCR-205 0 GL 4 A E/7 0/C C 2 A EF-1 EF-5 EF-7 ET-005--SLT"1 EF-1 EF-5 EF"7 ET-005 SLT-2 P==P-R HO HO NO HO-YES>NOTE 1

0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SLMSRY SHEET-LAIT 2 SYSTEN-NANE:

-SPENT-FUEL-PIT-COOLING-8-CLEAN/P-U2

-=-FLSI-DIAGRAN:=-12-5136 -=RUN DATE AND TINE: 14SEP87:13:28 VALVE---=------I VALVE-POSITION I I I AWE SECTION XX NUNBER REV TYPE SIZE ACT F.D.I PFIZER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)-TYPE.COORDI OPER---=FUNCT--ICL------REQUIRED PERFORMED NiODE 2-SF-152 0 DA 2.5 N K/9 C 2 P A SLT-1 SLT-2 R YESp NOTE 1 2-SF--154--0=-GL-2.5=-=N--K/9 C-C-2-P=-A---SLT-1--SLT-2-R YES'OTE 1

0 o DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SCARY SHEET-UNIT 2 SYSTEM-NAME.=CVCS--.-.BORON-MAKE-UP==UHITS

~8 2=.FLON DIAGRAM:~2.-.5131=19 RUN DATE AND TIME: 14SEP87:13:28 VALV VALVE-POSITION I I I ASME SECTION XI HRKER 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

=I CL=-=.==REQUIRED.PERFORMED-MODE 2-CS-415-3 1 CK 2 SA K/6 0/C 0 A C CF-1 CF-1 P HO R=CG-413%~K

-2.GA L/6--0/C.-.-0-.-E,--A..2.-CF-1-CF-1...P BO 2-CS-026-S 1 CK 1 SA M/6 0/C 0 A C CF-1 CF-1 P NO 2-CS-027-S 1 CK 2 SA M/5 C 0-3 A C CF1 CF-2 C YESP NOTE 1 2-QMO-420 1 GA 2 MO L/5 C 0 3 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P HO HO P NO 2-QRV-421 1 GL 2 A M/6 0/C 0 3 A B~EF-1 EF-5-EF-7-ET-006 EF-1 EF-5 EF-7 ET-006 P HO NO P HO P HO 2-ERG-422-~GL-

-.2.----A.=-0/2--0..--0.--3-A-0---EF=1.-----EF-1-.EF-5 EF-5 EF-7 EF-7 ET-005 ET-005-==.=P=--=-=HO HO HO HO

0=e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUE)ARY SllEET-UNIT 2 SYSTEN HANE'=CO)PRESSED~RMYSTEN UNIT 2-==.FLON DIAGRAM:=12"51208=22 RUN DATE AHD TINE: 14SEP87:13:28 VALV I-VALVE=POSITION-.I

.-I I ASNE SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)-TYPE COORD I OPER---FUHCT--ICL------REQUIRED-PERFORHED-NODE 2-PA-342 2 CK 2 SA K/7 0/C C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2"PCR-40 2 GA 2 A H/7 0/C C 2 A A EF-1 EF-5 EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7-.ET=003 SLT"2 P P P R HO HO HO NO-YES>NOTE 2 2=XCR"100==

-0 GL.=..1., A..L/3 0.=C====-2==A A EF-1 EF"5 EF"7 ET-004 SLT-1-EF"2 EF-5 EF-8 ET-OOI+SLT-2 C C C R-YES>NOTE 3 HO NOp NOTE 3 NO YES>NOTE 2 2-XCR-101 0 GL 1 A L/3 0 C 2 A A EF-1 EF-.5 EF-7 ET-005 SLT-1 EF-2 EF-5 EF-8 ET-005 SLT-2 C C C R YES>NOTE 3 HO HOp NOTE 3 HO YES NOTE 2 2-XCR-102 0 GL 1 A L/2 0 C 2 A EF-1 EF"5.EF-7 ET-004 SLT-1 EF-2 EF-5 EF.-8 ET-004 SLT-2 C YES>HOTE 3 HO C.HOp NOTE 3 C HO R YES'OTE 2 2-XCR-103 0 GL 1 A L/2 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-2 EF-5 EF-8 ET-004 SLT-2 C YES'OTE 3 HO C NO>NOTE 3 C HO R YES>HOTE 2 e DONALD C.COOK NUCLEAR PLAttT SECOND TEN YEAR ZtlTERVAL VALVE SUt$1ARY SKEET-UNIT 2 SYSTEH-NAHEt

-HAKF UP=tt-PRIltARY-HATER-&ilZT-=2=--.-

-=FLOH-DZAGRAH: 5115A-41=

=RUN DATE AND TINE t 14SEP87t 13: 28 VAlVE I-VAlVE-.POSITION-I-I I ASHE-SECTZOtt-XZ

--t'UtSER REV TYPE SI2E ACT F.D.I PONE R SAFETY ICD A/P CAT PRIM TEST TEST------TYPE COORD I-OPER---FUNCT=--lCL

=-----REQUIRED-PERFOR!tED TEST RELIEF REQUEST(S)

NODE 2-QCR-919 0 DA 2 A D/7 0/C C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF"7 ET-004 SLT-2 P P P R NO NO NO NO YESR NOTE 1 2=002&20-0-OA-2 A=O/7-0/C-C-2 2-A EF"1 EF-5 EF"7 ET-004 SLT-1-EF-2 EF-5 EF-7 ET-004 SLT-2 P P P R NO NO NO t<O YESO NOTE 1 e

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~COOLING SVPPI.Y HEADERS$(E TRIS DWG Cld, Gld MAIM S'f(AM PEHETRATIOM 4'VTO Tt ccscrcc*>>CCHN!01t 514ECIEW cva COOLING COILS ccwtct 54 CCH 141.11 lh'X Ih'S.KD5 SKTAT ISOPIC rxi@'Ov-tcc.

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'SEE SKKTOI'0-4~CPM.1 C tll IK'W 5'K 114'O 6 FSDII ASC RECIECpl~SKIMNIER FCAN ($.6))IXIXI CPH-1$AT EAST SIDE OF COHTAIXNKNT SEE SK'D 4 PH.S CPN.15~CS'HK SKIS 4'$K SK'H.S CK SK'(hc'h Toe FROM CFN 3 e 4 TKPII CPH.YK AT WEST SIDE Cr CONTAINMEMT

.SEE SKETCH'D-4Ž~o CPM-9 CPH-5 14K SX'H-5 SKK SK 04 0)'10 6 f SDMAQ.RKGIRC/Hs SKIMNER F1EE54 Oct~CPTI-Tt Al WKU SIDE or COHTAIHMKNT SKE SKETCH'0-4 CPH 6 Ctti 1$CPH-Tl CPH:5 CP'H 4 5K Sr.'H-5 SK sx'M S S(K SK'M 5 SKE cx NI.S SE'K SK'NS CPM-3)CPH.41 SK SK'4-$'KE SK'N-O'(K SK'N'5'PH-CC S(E CK'HC'(K SK'J-)tfe'I)K~K)

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~ISX-3(N13'I toast(ala)Sx~4 (N$4)IVllldt(IF LC F (0 ZRV.IIO ZRV 120(Htt)f RV 130(HC3)2'RVC)40185 4)Fl'll I STICS 4 SZ(633 M (4SN RNttdt I VI Ci 10 St(at.l 51141 3 Sl ICI 2 SIIGI's T 10 IRV-310)RV-320 8'O IO REACTOR COOI.ANT SYSTEM COLDLECS SEE II a aclalaae SUDS(I SZI)OU 7 LOOP Nt I ia ra~r.c.ttt OYHCR 8'tt!14t tta(L ra~a F.C.NOT SY 9 ACCVsJVLATDRS Net Ned r NJ s t(OT Gt v I'Vf H'j ANI25 2, sLKS SSO 8)stew LO (tet 3'C Ssi NOT SY OW DOS)l lactea Sa s vo s to(vs sws.as<<arel 1 t Nt4 REACH AOD RKGViAKO Rdtidw ttlt3ta(l/(Pr I t(tt Casa)R NXXL~s aye (Sx 303 AEACe(RDD RK()V!REO'le C'V~COAAIN tte2 (VENT~I 3ZIGSLS 1 RHI33 I 1 ACC VMUIATO R TA:(KS.Ss 4.8'tt)OL4 LOOP H14'Oetta W SRV$$~RT&$Wlt ace~1$S SS stv I~L(vai)CM IH se aaff tata[MO 349~1'OL SY W RNttCL 8'J 8'10 CH/iRCIHG IUPP t ea IO(ta SUCTION HEADER.SKE DWG st29!H/5 bt4 DRAIN 8 TO UPIKL CCNTA(Hsa(NT TO FLOORJ SPRAY HEADER.V(A CDH.SI Stt DLG Se<<C/3 5(1)4 3/4'I(s)UN fft)H St/fit SLKCTKN IUVCOS SEE Dtft SI42.0/8~~~1.5IDI)Zft I()C.5)lt)It f r I I t/6', LC)I PI 3(DIAM IO I LOD Sf(i)3 r/s I-N tl)t (3VHieA<<etsw TCRT VO aesLSS.t,tM'R'csvsv NITIJ LOOD HVR:Sx 30 RNitlt g Stl 0 2 loop N$3 IAV 320/-RvtttW 1'aa RLE't~/seasoz aaLtw'sl Qt At (TO PAESSVAIRKR Vse Vari t<<tat(a Dtae(taatlte(YACC CcvtOHCHY (DO(lett(AVVOL NVelatatR 1$2 VNLCSS OYHA<<ett&Notta (P j RH 132 iii I xr>,5 SZIGi(t SZIGI 1.3 I LC F.8'tO SAFETY INJECTION A'LUEF TANK.SKE OWG 5128 A.E/6)M0.3tt TO Uttf A (ONTAIHMKKT SPRAY HEADER.V(A Cfat 50 Sat Dwt Celt FI9 RHR LOOPS Hat C 3 COR COOLDOWN IMO 322 V<<IS csaao MApc asceovc VDR LRRt 2 AND Svtcaaacocc owo.t'2 se<<$RC<<22/4'RAIN TO'C FROM OTHKI)ACCUMVLATO'R TANKS PUMP SUCT(ON.SKE PWG SICR(K/9 2'TO CNE'4 C VOLUME CONTROL SYZIEM COA PVRIC ICATION.SEK DWG 5129, F/t 5'4 10 CHEMICAL Y(KVME (CHTROL SYSTEM HOLD VP TANKS.SKE DWG SIMVN/6 R J SZIGILI~J r~6\els Cat CLS SZIGDW HA t Rat Vl toactstecltsoc HUsss Rs Nt3 N$4~tja ACCUMULATOR ALL Lttat SEE DWG SICLB!9 glAV-fit S.SZIGILC~'el ANA f!3(P M!H CLOW LINE RNII)L DNLYYACOVC VALVE Nvva(RS AFFCSR Dst VN(s DRAwtvtL szt SZFARatt VALVE IOCNVStCAYKW UST FOR tC(RVALO(t DZSICN (VCR)HVltStttS.

teteva HVHStRS VOOIAZD fOR DRawteC itst AS FOLLOWS.TAC Rt: t tesW VKD W AFFCA(t5$5'SWSOSW 3 CVSIA($sOVY RCOV YALYC t(ARK HVS HOT$HowN ow.oltawwc(szt VALVE IDCHttF(CAT(oct USVI DZRSVZD SV ADOWC TO~RvetoE(t Hvsssot'(tt so(alt twaAs&YI FDR (XXXXC$4445C SPSVRCJM)AV 132 IteO 324~St tsow SZIGDE~]LJ Yr 8'all C.O.LDW HEAD SAFETY DUKCTO(5)NOT LEC5 (REACTOR COOLANT SYSTKM1 SEE DWG.Cfit 48 I'ENT 4'f ROM 4AFETY)AV 14S IHJECT1011 DUMD'9'SIK D't(O 51421818 SZeaa (MO-14 I(IAtSt At(liat Va'SX 301 (TY tsttkkl I N 51 155W rsz Sw:1)St is)32 sltds F/6VN/6~SLISTL3 SZISSLC LOW N'(AD SACET'Y Dtt(CTIOH tO HOT LKCS IDOP Ntt g (tt'EACTOR (DOLAN't St 15&Lb SYStFM1 SEE OwG 51'28, f/S.H/5-lOOP Hts SZ LSTL4 IMO I'R8 GUS&a RN('ISW RHllawc I ISX aa30R FC.SZISSW aa'Q IF I.t 3)'192&)M93%S Rtt 125 TR 31 ANR PUMP Mila CLOW LtNK KLCOS 0 1st I'Vf HT ICM 321 SY IS)TCM)ti~521525 SET AT Cfo FSI tO PRESSURIZER Afai(C TANK SEE CCG SIRSILX/6 F.C ELBOW C LOW'ELKMKHT 1 FVPICAL)IM0.325+I t(t (t 5'eat(5)taat NN.d IC, VDA vtcttofiUI atatUC sa SF AavttoN At(oo saves~tr RECUEU'NC WATER AETVAH SKE DWG 5144,\fb SKE NOTE'A Cfs 14'FAOM LOOP Ntt IeOT LKC SOR COOLOOwN SKK DWG sit&a E/6 Ft NG SCACZI(Csoct LOOP N$4 52(SIV LOOP Ntl IM0.315 tt sac<LSZISCt SZ1542 F.C lifat Lt(K.Stia&3 It.tt 35 alet ga/ttf VOL Sttai'I iDX/~e~st e 129 Ca\8 a la CDN.49 IO(t RLVIS(ON CRIFTTCS(SCC SCFARAIK RCVt5ON RCCO(O tDR T145 DRawes(C~r vfvt N Caela$1145 14 Rfa(3(AOD Rfr(U RED RHIISW~rz)AKSIDUAI.HEAI'D RKMOYIL DVMPS 30&(1 CIM 3SOFT TDH CESIGI)4,500 CPM Sg)f f t(Z(c(a)C l)80 RPH CJO H.P..MAY.DISZIL Pg(SSUAC 7ZS CSI(t wav sww~elc vvwet'w$<<lvNNR&spec Nw tww tsa w o avw vaa~veaw sw w R w sa el swwvw v R vale<<wwcaeeww

~www asa<<woes ss aw s<<ol avw w v<<nw e<<wt w w let ewvs tw el w w twwt aasvvs<<a es Rw ttwwa w R sect wwo ww swoL ICM It5 SEE NOTE'A FS Vr teLV coNN, CPN CtGDM I(IAOM REFUELING WAT(A SIOAA(C TV:K SKE DWC 5144sf/5 (IIEACH ROD AKO))(SC f(aa(AL wAIER 10 C f ASM I'ECILSKSL R(AT EXCI(ANGER (SUPPLIED bl DUMP MAI(USA()SEE OWG 5I)SA.G/5 GYP)Rveo W(01 I!B LC twl 41st AOO t(rt)N.se al TO'E YALYS ENCLOSURE~I~1 ICM 305 af'CM'306 LC 2'Xs'SY.IOSW, SV 1058 SET AT 35PSIG RNslaw a FROM'E VALVE AH(eat ENAIDSVAS PV(tata (REACH.JC AKOUIAP)~st 6 VENT E QbLAS LDN.45 SIDIK vcNAHA 4 socsccaN ltcctR(c ca.=(X)MAU)C.COOK NUCLEAR PtAHT (ZVstst SCIIIN FD('E SCAE(H 3'ENT LC.I)r 0(atat 3(ZLJ/4 Cveoa HICK ALARM KL.589(tt) ib'X'R Afh 4500CPM juAX (tet.46 77OOGtM tbs R H soawq SCVCNI 4 51))sJ/6 Rsesosw pcHssst F lQW DIAGRAM EMERGVCQRE CQQUNGI56(UNIT No 2 D N 2-5)43-35 r AHsatw A<<salt 32OO CPM (SOLATION SLOPE MOTOR LOCATED D(SICK ENCLOSURE~

IPX 8 IPX-305'E'Netttt Vacl RCIO)t RNIO45 (AKALH AOO AEO'JIAEO)-

t f~)110.310/~I'CAPPED DRAINS to S(3 (REALM ROD AEO D)DA D I RNIDSW TO (OHtAINMEN't f/tUMt S(AL Ic(KJG((ttt)

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0" (C (D 1 P I CS K j , l4 (N 0, r r.'GES(ERICL'NOTES f<>I~-'"t I-" 23('E'12'N 4 L r----~~TPX~Ij I OUTSIDE REACTOR CONTAINMKNT INSID'E REACTOR CDNTAIIIMENT AT")SPRAY HOZZLFS (ZPReMO TYPE tll3A e TOTALLSI HOZZLES P(R 8'HEADER)(IP(40-7, fs pt Srcfectet TEGEND~MAIN CLOJY AUXILIARY FLOW PIP INC 24 MANHOLf.JIVEOIT SKE DETAIL'%4.$

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SAMPVOGIPIPC Hat(RIAL AHD DTNIR SYI4SOLS NDT CKPIAUITD 014 THIS DV40.>AND CDR OJAR K NvubcR coots,stc DYCG)2 503 C 124 SJOJS.ALL EOU(FONT.AVD P(PTN(s.-YJS)/(C CLASS I EXCEPT AS NOTED OW eV WESTINGHOUSE REFUCVNG VATflt STORAGE-TANK FRKCZC PROTCCT(D DRAINS FROM SPRAYAOCKYIYE TANKS TDSPRAYICDOITIVK TANK RDGM DLO40$137 IC/S N~'IS,CIS.CIO CLOwS SHOWN ARE REDUCED BY 25.5GPM WHEN f(LDH EDUClQRS ARK IN ZERVKK TNC~T PRCFIKlJESSCNLY SON Csscu CdfaOOSJCN 1 I DINT IP KAVION~JLPCCCC4 IS'?r CPILC'SS OINUR VVSSC NOTED.~Oe OOCL csa\%LA\alclals4411 COM4L 111 OVMMf%sures Ncascusisa fec~la%1 Iaaf fasfL Na COOL Css\s susfc COIILI%fst 1%1~pleae eitllos%0 c a@loess%4%Vela%epslaawlUes40 fasft est%%lac's

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>ut CA Z30.ARSC'h SREAKVIC, FLANCt 1lf PICAL1~cat s)cat 17 3~'Lcatto CL.CSO'KSP KL.511'Cr E I Pt ttlf CO<<>C<~ETCH 8-1 ARRANCKHKMT Ctf PIPN>6 fOR Ptu\TRI>TIDN .PRKSSUECZATION AT EOQIPICENT WICK>4 I IS I C I I I tg l>c Sv¹xf TP ftaspuaLA<<L r.Doo>R Stal TLGT)SPIEL.S16'ao.K-SLOSC.cats>'/R Yt't CAt1 1 Cat)0 couu.KTY 8)>>-CAPPED TEST v>v CAB>SS ZONK 4 CAtat PA FFA CSC tS tll ff FFA 15 n tll CA141 Ca 1 0 6 PSO ZSI~PL f PARICYI 116 p I Satt>ft tONE S Vt 1DEICCFRICAL PKNCTtxATIDN CANISTK'tS SEE TSWG.SSNS>Lal'\ G I I t~jt to ptpp4pfutrpar>ou 1 CANXSrCRC SKE DWG Z.CHS))A>4 t TO PEutfetttouS SEE DwG.SHSA>u/>L uffte CfltuoKR wELD CuxuuEl tl toutS t I Stavrluo PIATE ttfP)/8105 IMG(bf 6txftlt)I Route.CYLINDER Wtlo OIAMMKL flvf)1 I I WKLQ CNAN>l'KL ZONES>>Lxtrl'TLLLD o>>tr ta<<DC V><<Oaxr'OR V>t>T t g AL>O DL>P<<>454D<<D Ottr I'1 6>4>>RC>ALO INNDE INSIIRVNKMT ROOM C41410 CCIOI N calo<<1 cata<<It CCIOI W~Catot'catt>ta~I$catt<<t~Catrts~at<<LC)r Capxl 1 l EI Cltlo calot'5 CAIOI>>I calls>>1 ca'1st 1 clips N cattl\EL.S'18'1/s (<<let'I 1 CCNI 9 Cata<<>0 C<<101 5 f Iasts4 cat>>p f CASNttf I N~LNPR~ttl 4~ltlltt Cll tstt lalal f ill t4 sit NOT f 4, CYI N4ND OP ttatto VA 1 ovLY v>cove valvE NvMBKRS APPEAR Ow THIS DRAWINC.SCC SKPAR41C VALVC lotwttf>CAttCN Usr foR Kovtvalcwr ocslcu INCR I NVMSKRS Z.FAC I'VMBKRS MCOFIKD FOR DR4w>NC VSK 4$FOLLOwS: 144 N t: 1 t>SW VK>S'W APPEARS AS'KW>OSW 3 P>STRVMKNT RDOC VALVE NARK Nrs Not suoww Du cwawtt>0(SKK YALYE IDEN'ftrtcattou Ustt DCRIVKD Sf ADDING TO IwstRVMKNT NVMBCR'DR SINGLE Fat)ASC)tt FDR CKAKLK awxrsc:ttxpstRKAMI ~RSC IDCNttrtcal>ON Wul>SCRS loR lvcaotllll status scl P BKVISKPI41(DIO FOR THIS DW tt-f.?6 ZD fOR REVISOR CCSCRIPf>ON SKE SEPARATE REVISION RECORD FQR TINS DRAWING>>>>>>4>>>>>>>t>>>>t l>>jt>tat tttlt>>4 ta<<>a lta>wl la~t>>>>>>>>>¹t>><<<<¹~~>>~>>t>t K>>>>>>>L>>¹>>>tt>><<t¹>>N>>¹&t>>>>t<<~¹t¹>t I>>>>¹>>tt<<4 KL.SCRLIIS/; 4 ala 4'>~C4105'10 COMTASNIIEMT flDOZ NKLD CIIAMMKLSg TTP.FOR'RS ZONES)cal)I Ialal 5 101'I C410~15 salas tl Cata'I4~H>>>tat>>>>>t t>>alt it>>>tl aW aa~t>>¹>>>>>>tl L>>>>>>>>>>>¹¹>>¹>>t>>W two>AHA 4 a>>ocoaN txKcf Rtc Do.DONALD C.COOK NUCLEAR PLANT 4>t>ocwav N>C>>>Cut FLOW DIAGRAM NTAINMKNT PKNEI RA)ION 8 EIO PIANNKK PRESSURIZATION N K?CO w UNI 2-514 5 F40 REAftCR CAYIYT i>alt@f FIDOR wtlo 3 tovKS CF.N I I>L C>.>>(awlv IXIC t<<>C rot ta slaw(I Cxat~ho>PV lf afv foa>L M" I N I 0 l3o'P,'V8 P v 4 TI I APERTURE CARD AvaBable On Kysrture.Cara I zlP, h Jl l"~g I I J k 0 .89P(S'-E y)N TIO lvcNI((YR) MR (39 (30)FAN COOLER tt5ITS 1'I PLENUtt LOCATCD t ROUND COHTAlHMEHl't Cl Cl CPSI I C~~g 3)1 OvaiRCLOVI I~TD FAN COOLCIS DRLPI NE ADER~ca 5c c DvtroSIS)tst/I ~LC"J 2'fi.GLYCOL ELPAH MON Thsssy Tsa Pl~vt I VLL ID Stl tr s D.stoa t'aca=H I O GENERAL IC)ICS L'EGE ND ETIIILENC GLYCOL I AIR UARf PIPItIG I s.FVL40L)((ttoKIA 'slNE R I 3(t tert I;((t I I ISLL~r(L-'tto'I Hl VSD LO c/5 3.'~s/30 Zt~y f's (.)S14 S (tls Sscatt LR24L fOYPICAL)((ttPICe)RICL.I'T<<'tuel I-3O~OUTCR RIC 4 ITNSIV Rtfat 3O VD&21 TNFU clo I YTC I THRU/ro~CPSI)2>(CDSIIS~IVP V(X TIIEU (CPSltl Stt tett'1', tt/3 I+/'C Ill lc till tv (SI(s3 I THRU RIC3'3P frtr)SEE NOTE 2 RICS ITNRU RIG5 30 I YSO 30(-360 I 4 ovtsloc let.CAMotsasch DNTLR csvraavwcMTI svssot Icc covtessath 1-2 Cl 7 2~=0 SI t/0 LI~s MS O-159 Ol 2 NOT DYOw I-7 CI 5 2 l 2 0 LI 0 V t)0 Q,NCCXKtl ttcsT I (UY CKE)OY'ip(SCOttsktt to DhsvlPCR IL\11 s (TYPscl,L) ~0 RIISTRTNLU RIG'0+(4'\VDLC OAMovCO)I+--I t s/I Act Ct)TRISUTCN (NE ROE 2 Tt)DIKTS t(K LIE D At(OUNO L'c CONDENSE(S VOS-I.vOS l t I I).C Drs FROST I COHDCN'SLTC A~AT TEACCD)I ELE(TEIL EE(2((s (TYPCA()g I g LTYPL.Al)l'5ps tp a&~FF t.E Ih'DCATI NOR.S 1 513)A.J(t, K(1,L(pcs(T 'VT)'tot TNCU 2GO IEIGC"ltstRU RISC 30 ff)tvayoaa Rcsaovca)Vlt flv cooctR oltact stcovs ltc cossotvscR POLMVih FAtl CCIOLC R TITAKC F ROSA KC ODHOCNSEf(PLEHUSI BArK¹FT GAL(POR.t t t VPX tssvtCos)LPPCR 1't~.4 tvv5~1$5vhslhfsov tLSsle lt olac\DF S)r44~lhvs 4~l C ID 4 ll lt VOX QS,DLV 4 yc'si.ct.oh>> ss aoa Os Tvav It Al ClsteSDVTSDOSMLACCR 5'arts Lh'J TED AC)caco Ko tossOIHSt<, 5/tro OOt'Mollcts tlVPICOL)OME-t(30 (2)FLOPs(OcrrsOST 3OKW (Tv os CAL)HEAT ry'5 acC.Elt.2~a (Yz,~fl csco4 9 EL CAZ'C(~a VPX ll+8 (4 GL'CCOL SUPPLY r COLA GL'ICCL CHILLBRG g,', SCRUFF.SIA/o,LI/S,A/9 i I VFNT c NOT DYOW I32EOS 10 IO V IC.IO CC.G F~Q ts((2: IK)t tsy O roeh~~ts'S I!Ill I a ls Xi~t tTESICOClt t>l LTESTCDNII.RICI vr&VPX I HOT tsvow~TC ST COllrL 5'T t ISI55 RPg i to VCA.CDO'I O149 lo~'.-I'(/"~i'E-COS.LSSsSEE NOTE I,'O!3 vts FTR VTC VTS 31 41" 4 FLYENT.)IG(]F.Rll'1 t 32 31 T I PRESSURE SETTING t3/l Y(NI 2)SPSIG Sv-t(5 RLIL/a I)(~R20(o I L/Fs I DRAllt R 2sSS G I'e A os~&LS Q tCST CONN.,RIS2.)ttictt CostN,RIS3 O'TO PtAIN 01YCOL PUMPS 568 OWG 914&l t4/9OA/O.A.l OPEEATIICS FlOOR EL.G'52'Y2'l.. O'4 l'C'/4=tvOTEI FOR KC COHDCHSCIS DRAINS Sit DWO.5124s4/2 f VENT~MMC E 2)G A 32 scLZ R)63 Rtst r Rllo VOX 4 2-J<<E>>R-)OS 5/22 M RCMDVC SESSSSRC>>INAD/VALVC Ssctotvaas CLOT l'/2 (Ls()FLOOR StAB COOUNQi Ut((ts 1(2 (TYP)EL21 ITNEU~r---IC'E COL)DEQSER5IOB STALL COOLIE I (Ttt)2223)TNCULA l'LI(215)~vt4 vPL I<<RZDB FEZ(I.R ZIP 2 vP(158 Io./1 vlf L.LLI tstRU tsf I/2 (IVP)'R l 8T WEST INCNPUS\:I lo 4 I 1.,4~I I.'~Ossttcco SENSORS QR-sos M vl e~tc 5 Ytf 5155 VCA.LSD STRA(t(D IO FLDDA VTIS LDS VFA.LLL STRAPPED TOVALL O DCC Dtltt.II3E45l.fOR HT 4 LOCATIOH Sit vsESTTVGIIOUSC DWG.OSC452 TO TVVO 40PI DECOR\RSSC LSC tt)FLODLO SLAEO OH Phtvt t'SV'OOL IL)$L)l/IY (1YPICAL)Vol tST V PI ISO clt203 VOX 155 RSDI~VRV IS 6/Zs 2'SDD (Z)FLCIDQ Ct)CCIL)G PuMPS 100 GOIA Z04 FT1t)I4~3 vvaf Tt oERATURC zotcvf s)45'spcA'MbX D15CS(ARGGPR85 (15PSEGs yhLVC.PP-/33 (SC.IIQ CCFIOCINaCNT CND VcALL CFv,+ttANe, VILIL t/CC.'m T<JKE CAcRD RZT3 RZT4 440 AVQQEEMB OD-'perture Card 1 SthtVLD CAP FDR FRLSsSC PLATE E.L.5 4220 I..F., (~4 ('I,, 3 (K I I, sc., I~~~CCIR SiALVE,CtsTRVMtttt SALPLING.PIPE PSLTCISIAL AND OTNCR StacDOLS HOT~,XP(.AltlED OH TINS DvAo AHD COR MARK tsuac(3CIS CODES, SCC Dw4 EssO4.ALL EOSPL(ENT VALUES At(P k(STRUMEt(TATIDV ~DY V/ESTOLOIIOUSE IFILE5S OTUERcS1SE R)TED All PIPING C Zt EXCEPT.AS tt)TEP Al(EQCttts(TNT SEISMIC~.QLSSE EXCEPT AS NOTED~TE)al'/2. E/7 GLYCOL P)PING PEL)='liCAl&5 LZ5 E,ND Ls/ALL ONLY.~+."2'.D/S,C/SC/3 GLYCOl.CONNECTION> FOR IÃSASIIET WATER ADDITION EQUIP)(EI(T SEEP)(T.5107, s~,4 a Siolys tto~fOR (OO(CLASS Lt t S SMLTSCV~craft CoaattctsOats.ttsC151 80sssDhht cattasss TD vvoo WELLES tat FAN tcCOT MaLVC.FTR C DC CsASC I ytatts/MD tscasys.Toc tsl csavsoacv tFtta'Dsaato WCAVDCS ISC St~COCV vasav closto vaaw ol tctcMos Tossaso sasoasscs toc DMOID Roacg CC CCPAF ICR sa atosttatAT OSO50F VALVG tlh essa caass 2 C 3 vtvts Mao Dtcsass toc 1st tsooatDOCT CAttMDS TS sayo sastaVDCS Tsst Fleas lsolllhav tl ito sscavt NOTF'HIS Otv HADE VNI0'J-FOR UN(T2 wo Sv PCKSCDES DVC s~aso~Ost 1-I/.Ff cs3 a FOR REYISION OCSCtcptsDN SEC SEPARATE I%VISION RECORD FOR TICS DRAWWC TM Ov o 4 M MMsr 4'OMow OscMOFMo ssMO cor.44~OMRo Ova cMVOO Ms 4 4<<\so M sssvoviso aa ovaa 4 vvac aa 4 Ms, oa'Mo ssa~rowsoa sa M scoM ovvrs M Msss saM~MM acr M cc cs oo ssa avs Ovvw OMM4ia la OOO Ovacoa cw 4 so M soMM Ooo oasvaa INDIANA 4 alsCNltatl CLCCTIVC DO..DONAlD C.COOK NVCLEAR FLAIIT FLOW 0)AGRAM ICE CONDENSER REFRIGERATION Iaot sOT SsVtflOS 5 2-51468-25 ~W~'a4 VC Q'.-..VF~.n C OMIRKAV tttctRsc tOV IR ltATKE coar.t CIIOloalf~IRW TDVC Ot.NANO OP RATED VA V lOENTIFICATSDN NVMSCRS L ONLY IODOVU YSILYE NVMDERS APPEAR ON lCNIS DRAWWC.SEE SCPARATC YALYC IDENTtflCA'IKlt LIST FOR EOVIVALENF DESICN INCR)NVMSCRS.4 Z.th IAIMDERS MOIXFIEO FDR ORAWWC VSE AS fOLLOW: TAC N~'-NSW YSDS.W APPEARS AS NSWIOSW SWStRVMENT ROOT.VSlLVE MARK NC'5 Not SHOWN Ctl DRA45N ISEE VAI.VE IOCNllFICAtlDN LIST)OCRIVEO DT ADDMIC TD WSTIIVMENT NVMSER'OR SINCLE OCPIASCVI ICR DOIAIC OCPIASEVttVOSIREASO 'tssCUsOTPRtfll DESsCMhttoat COR Eaos ccsv pov CMT sofNtt Fsch fsosf NVSCCERSS't IPRLSStfytCVOSE Ntta" 8710130878-P~ "l jl' A I o I 0 I E F, I G I.N I J I K V KIPIS t cw l>o s'Cttl IJD 4 CCLASI tslslsawidtcrwlCI>ONS IM tv>>VSLLZLR>L>L4 ID AND ta4'>0>EGXNPMENr 5EI5>LIIC 1>451 VDCHRLf CLVSLD>4>VL s>v'Crv I>lf C>PK s Hf Cf't s Mv.Crr HVCOCCZC>>>f4>>'acrcl lif Cf'tctCI NVCrrCYCS Hf<<PRCTCC Hf C>PKCYC?Hf CFTCYCZ Isf.tftCZCC HvcpRcrcs Hv cfcfcrcs Hf cf tcrcd Hv cf'tctc1 Hr crRczc4 Hv c>pic'fc4 Hv<<rrcrcc ssr crtcfcs I W 4>l>ltAK(HOOD IIV"LPSH (2)CO>JTA)NMENT PURGE 5VPPLV FhfJS (l>>.OQQ Ct'tA'EACH)~CS.C.K-ROOF ELKV L3t OID(FH~asr.tr GENERAL'.,NQTE5 Lccaac*R LDR D sill Ft tftutN L>a>f TO 76 lvsf Rv>>KNI>>DD>4 Pu>M fsHAVSI Stt, rlcs Csatc.4/S~~sac>>4>XOC<<os~~~cr>~N sla~/saa'>s (5>>>ac>aawst raw>>Is.CL fat to x 0 0 0 TABLE G I tDc".IJTICICATIQN Or TEST CAN(STERS ASS~A/RTKD WITH AIR HL>QLING U I:Ts P~l(tro>yctIAR~L r>LTKRS.S4~34 At/>DLIJI Y.PIPING SYMBOLS Qt.II>LET GRI I.I.C BACK DRAFT DAMPER REGIS((5CQlTK OPP05(D dt(O(DAMP(A D'5 ELECTI(IC Nf ATKIZ L'HARCQA'L FILTER g HKPA FILTER L Q ROUGHING FJLTER I td(DIULI'KFFICIKNt FIL'TKR Q H(ATIHG COIL g COOLING COIL Q INTAICP.lOUVER VOIDMK DAMPtR IIONMALLY CLDSf 0 VDLUM'f DAMPtR.NOR>AALLY OP(N , A>R CPCNLZCD Dca>PCK 42 XZI~Zr>5tfhht(SUPPLY FRQS$E AUX>U~V Dlfh>$HER.S(E DNY.51ZCE.LY/>I>rst Hr Lrsssf>t.l I NOZC'I I DVCYWPNK S.c.vt C va CPSSP 4~'+tg I~a Irv 5/f I I>>Salts'.Ct'<!'IIII\/PPK>Z COMDARi>AEtsT I~~I~~I~I~I~a~DVRGE.EX$$AVST AIR JEST.'TH'Lg QwG.WA, F24<<3 5 2 PX 20 HV<P54 g HV CPS 2>'1 cca<<<<vscrc vrrvcH ICP l4 vTC>rrcs>ccapfcvrl<<ur cauacc ccwusr 4>4 Ac rvls>>vc tl/2 Is>K>OO Cr>4)...I li vp CDvm vs<<D>vSD I GA'TF w<<o fl I W-CD>>tr i RCMDVADLC t>VLKHCAP ar csr sc REACTOR.WE'l I I GRILLE (tvt)w LDP.SL 4,/Hv cov5 w csa Hc tl/)OO-'I Cf)4..s Sasf..DI VERE 5EE 5E'E QWG,SIZCK C'>G.5 I 48.A/2, N/2 h h i,.RCFVCLl>R'CAVITY'6>SC>>LJ3>Al>(ft>LXZ 04LCPCRS.DCVS>VCOFACCNV CtfC~(azp PLAT fsccpvr<PD J.~1>>J>>R<ee 0 v u)5)5)ZO cs V/I X P."t'-t-t Z<<PsrOS act 34 XN)szETGM A.t'RRANGE MENT.DF..DJ ST RUMKFJT ROOM A>R SLLIILE:PIPING s I IS R(TURN UNE FROM/.FOttLSLK RAO>AI ION MO>dtORDIG GEAR.S(E T>45 DWG.5>LA 4 V(R.IOC t 1J'IOS VPPE R CDMPLRTHIKNT g.PURGE SVPPLY AIR>(ZI,QOO CFshl-I ELEV.440'-0'.c lt PCIVSN L>NC 10 VPPCRl CCVIA>>lac'4'I KC>>RVSI Stl'tNIL Drafs a/5 af>C cor rro a~IZ IZ C PN.DS P.5$5);),)i W~a L~KLCL>PLI(t 1 POR PON res c l'L 2 C tPt F(201 FC N'7 UPPER>CRLS CoccPART MC>JT VCK UMC(LODQCfM) Sac>>vc~~1D PLCNf VCVZ DLS, Dsu wsv>s st 5>>>spa/5>4 J 0'5 FOR Ca>>LRCOAl c>LYRIC D>Rc.PRDZCCZ>ON SCC DD44>'>2 S>5ZR40/I HV-Ct'R-I VVI r facCSSVCC'wrsatr ovoYcr>racs(<<cp c/al))F CL YC>>IDI j H.C DA L'O LD'YIER (ONDARTMKIFF F.C./>PURGE.5'UPPLY AIR H.C.(I IPODO CF$$)I'4 I')'L 444 , SROSOK CfCNA>tp~lt TRASH DCIICZN~I>P>S>4>O/Swcvs~FG f L CSCF4'K IFPP44~cT copcgrtdctcsN scU QYC>fscst>DH tccra>stsc>cN AIL DLKT SIZES SHOWN.ARK NDN>HAL.TH(Y DO t>OT>NCLIX>f TRANSIT>DHS lif CESSARY TO AVOID PHYSICAL 03$ISCI(S FOR VALVE, INSTILL, SAMPLING.tt>PE MATERIA(.AND OTHER SYI>IDOLS HDT'EXPLAINED DN THIS DWD K FOR MARK NUMd(R CODES,SKE DWC SI04P.15 Z.I,QQO CCM 30 Vpt ZOS CL LCO'Os>aupap.5LETCH A.4 Atf>AHCF>>KHT OF VPPCR COJTA>NLfLNZ A>A SRMPLC FIPIHC CONT OV DNG>2-S>ZSS K/2 LOWER CQMPART ENT et>pc rppvvcvr rav/4 cat>>aust Lpao>sv ooo cpricpcvt SKETCH E 3 PLAt(QF REPCX(B.>NE.L L K RE.FU'EL'IG CA>/ITY: PQ>3LVEttTIL>>LTION SYSTEM*(5 C"QZ)PURGE EXHAUST AIC OUTLET SEK THIS DWG AT JIS DHfR CDHPARIN(NI) PURCLK EIHLUST A>Z ff t>>>S Dts>4.E/5 I CFM)SCXIB w tvDVC 1st DDatls Dec>>cur PLVSL 41 f'P 1 Duct test>ac Y.~4 (21,000'l a>>w~t I.FRQ$4 T(>P OF 50'4>e;>OUTSIDE REACTOR CO>ITAINNEtIT \4 a>>N W W?~~>L VCR IDC FROM STK>LM GENERATOR NS3~ENCLOSURE (ZSDCCM EACH)Hrsffl SKK DWC 5I47RM/Z~7 f vr'C>>srDS)N5(D'E R'KACTO'R EONTAINIJENT Hfs>OS 7 JZ)40'X40: Iba60 FNO Ca>L 50 XSC>>s>4 t t>>/FROM TOP OF~CO>ITAIN>lf ttr DDHE (I.OOO.CFLJ )~NZPPH 2 CONTAINLIf HT DOME (I.OOO CFM)FROM STEAM GENERATOR VFX Nt2 ENCLOSURE 6'l 6'250 Cf M EACH)NW~7 NYS>dt~/SKE Olde.5147,N/2 XRDDW>I ca ls t Sl 0>FRO>l STEAM GENERATOR/f N!'I EIKLQSVRK,',/w (ZSO CFM EACH)'&~VFX 5EE DYIC CI47C/2 Ytx 23 a>9 VFX YFX IVL>saHpu 514RI Of VFX YF a~Id'P co vr 4 prsl+rfsrsr DuCt'LDDw>DG 9>>~cps rv4 0 LC>p>OVZ.Piv>t/vcr t>tsotss>I-IDCNtff>C41>DN NVSSDFRS II;o O<<Pcsfc VCX 20 87 L ONLY'VN>DVC VAI.YC NVVOCRS APPEAR CPI YH>S Dtsw>NC.SCC SEPARAtE VALVE ID(HZ>f>CAT>ON List FDR ccv>YALKNF Dcs>CN FHCAI NVHOCRS, Z.tsar>AHdCRS HOO>f>CD FOR DRAVSCC Vsr AS FDLLCWS~144 Nit 2 NSWVPS>f/>'PC4RS AS;4'sr>DSW J.DCSZRVHCNZ ROOt YALYC Ns>>K Nrs HOY SHOWN ON Dt>AW>fsctstf VALVE'DCN1>f>CAY>ON Ustt.DCR>YCD DY ADD>dc'tD~~INSt>>V>>CNY NVHdtA: ff>A$>S>CLZ PNXLSCVI fOR tt>Sly St>ASC: tPSS>>CAVI >43&va+Dcrss NV-CPX.2 IZ'q I I I.2 DCD 144K>IT DRLDI PLUGS (TYP)FIV-CPA.I VMO.I02 I H1$>0><<LDSDC 4't ALD>~WD.IOI~N1$ldl vpccDfcla Cess 1 AV SDDV Na s, 4>avaav lvac cs!Isp cpac catv>..Hrsf>cg NEST FAN ROON Ns SKIIIMKR INTAKES (50 KFN EACH)H15>>rwv~8 I<<LL ,4~4>>I.OV/f R COMPARTM[NT (lXIISDK'M>SSILEI SARRIE Rl EL.655'Hrtlll af+~<<>I 44 X44~arcaosrs/tp JV SZLCLC'fI.Eg,'f@RE CARD-Also AvaBsMe 0))6'Car(I LSD>at>>>,l.VCN Zot I C>SR4 VFX I6 I.I 4'Nrsl>s~NYS Izz 4'rst2>~HV<<:KO-I>SCUD fON CDNN>P>LVZ l cccNpsc w*f cf!So I rs>>HP CCS 1 44.MC>f CIR Pl>R CCC$CR~ffsgzrp>cci.) I=E(.CZSLQ q FOR INCtdfNN SICIVL ttt-SI ttv>SCN ttco>>D FD(IN>5:w.-tNSTRV.ROON o(~Hf 5>VUNER IC u>)NtAXKS.g I>u (50(CN fAQI)x(5 4 35 K HZSIJD~4'X 8'2)4;R HECUtG/HYDROGEN SHIRKER FANS (I 51ANDDZ)4I.OLD Cl'M (ACH EMFRGENCY OPERATION ONI Y', 9 (5:C.I,)Daft aa.4ppvt>afp HYSI ZS~VFX FDR ACYISON DKSCA>PFCN SIX'zfa>>41K I>KV>$>ON RECORDS FDA TISS DRAWN>C'1, AU(RECIR"VLATION s/HYDROGEN SKINNER SYSTEM (s.C.r)OUTSIDE tN5TRUMEtJTATIotJ ROOM.t.INS'IQE INSTRVME'ON.E55EFJTlAL SERVCE l<<l>>R>DPPLY l.aalula.SEE OWG.Gll4A,G/F (TYP.)TATI ON Rot(>4 YCR 101 QipCFRQT~vfosccrsc sva wm 4 sas p>>v>>a w vv av>a<<ca a>pap>>tva scar>>c crap~<<>>w~>>a C>>LW aa>>W>4 4>Sa'4>>p>>>>a>>~Hvc pa>>vu w>>PHL aa rw paa sw W>>~aaa la<<Iwa awe>>>~vs>>a DH>>1 w a>>4>~Haavf carr W&W 4 EC!S.C.m 8 YDC ZQC S>4>IZCNI>rvs)~ Nrt>SDD>14 Sacs'L.L>t'>Cf ~>>I~la>>ww>>a a>>a>>vps>s FRC4l Jafs$05PHE lot..TO PLANT V Nr, ONG-SI48>'PV2 og I><<KANA 4 H>pc>GRN LXCIR>c Cp.IX))JALD (COOK, t>UCIKAR FtANT llf>DC Nl 4 sl>CN>cv>I I ss>l>2'MV.CIR-4 CI HV CIR 3 CP548 2.PCRrwi oft pcvc 20 5>I I I 2 ctg NrMZS~V HISNC r a (6 2 lpga>L Hs>A 4/a(rd I Z', cprcDcs>L. ~af>C AH Ptfc?'.C5Z f(.DA AM~JMENT VENT EAT)olat UNIT'2 2 FC HV-Ktt-2 HV Cft I Hvr CIPS-J~~(C.C~)..s 2-.5 I 4 7A-5S ELKV 6IZLO Vcf>vt)O-Ko/I ZO krSNf>>f.Hlsltd VCR Iot Qo (FOR CHARCOAL FILTER O.VMQ-BI slr.s>4RS rs S~3 SCR tf12.D c 4~a INSTR.RM'>>FICE Spar>LVL VN>1 DODO CCM).FIRK FPDtKCTION SF K DtIC 12 SISZKPM/3 vr Vtl Nr pvvsrpc NV RHR'5-2>SPIV>s>cac fpv Arrccvapcvf csp'K>acv>44 1>L>LN r pscact OR CHARCOAL f Art A Sff DS>C>25>$2(.SAIS>D OWG.I25lSZK WF>tf O fpf~l P acr'cg+4~P>>LSJP>PRT al 5>~l lfaa P>>EC>4 DLS4~>u>O>J RH>CLCN covawp>LNY tdclsracf Lr<<>v sr ss cc 4'4'Or ll>+PSC.ls'ICP.~a>W El 5'98L91 (2)INSTR Roft>l VEtltll ATION UNITS'fs>pr>Hov rc>4 Asrscvvcs>r (9.400 CCM EA.I STAND BY)'T s,c.3()I RCZlt/R>f L>NC CILQ12 PC>RZLSLC RAD>LT>ODI PSQN>ZOR>NG GEAR,SKG THIS DaJP, S>L">L.z:-2 DAAlHS CONT, CIN I Oa>>$>2'S>ZSSu/2 12)CQNTADILIEMT AVXILIARY CHARCOAL FILTER SYSTEM (CLEAN UP UNITS)(8.000 CCM EACH)(5.6.3()lpga~cue LTN cD$stc>PLY, Xx I 5>pc ts ppo cfs(esp>szsvppr)~JQIKI', IRIS,QWG.LSAQK UNIQI,'K FCFZ, U>JItt~IH> 2 t SVDCRSC KS Uv/6 1.2.5I42A I(tv.>4~v(4<<44 ccf C I 4>C PDa it sf 41<<c cstvr.4 7 pE)tOM STKful>C ENERATDR pFRDN PRESSURIZER tl!4 E>KLC>SURE .'HZS>dc/HOUS)NC (500 CCN)//'250CFM EACH).j SEEDIG.SI41 FJLL/t Vtt, ur 4 SEE DIVC.GI47.0/2 f L,.K>1 24 LHrdros.'.4'VPPER KOVPAHTHEN 6'S o I C I 0 I E I F I G I*T'1 0'l 3 0"5'T 8='" \:g I I a V e 1 I I I 1, l~A I 0 e)ES-C"1 ss<<>><<sr a vo<<s(LLs\Ae V 5 Seta tst SIGHT GIA'A VGG 3K)I Vfut To ATMOS.ow 1 os 4 g SV-54.Sf.'I AT 3OFSsc r I o*c jr I DKSFNERAUXED WSZCSLG SC Drrt s'51st Lift st rwrttrv Cl(OANSIDN TANK (TK.)CI I 3 CALI Sc 12 (CAP Crj fSEFLC SOISS ocssors f5 rsr.NKrf I VENT T (Wl tftgl 54.EEI I Ows)ru+0414111 Zp C)VCR(LE I'(tf)5))DwsOOH 5 O<<$4 SC ON 9<<r sls'ret<<sa Cse va+scVs)I Oc swaoacrtco vasvtra zo ttfseortsts 3 To RE'fVRN HEADER.5 FROsa ESMN'flAL SCCDrrfessfl).5KVL t I/f SLAVKE WatCR.SIC SSH)s 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cfe<<ccfscws fw.(ct 5&r Oat((sf(vs)foa<<OI<<OVO($ I c Nail twf eacvs tfosc~CLSc Svlsrlr<<Ottas<<C O 4 15'I Oosr<<O<<t tsrl<<ot'IO~r D Os(LVOS 5 t<<t Fr(Sf vocral'c Gosao va vt Ar I VENT To AlssGSPHCRK A85()LUZC FILTER 1 el CHARCOAL FILTER I c)GENERAL NOTES LCG'CND l<<t~Kv tR tlsRKsttaslt FOE VALYC ItISTRUMEHT, SAM)LING,PIZ t MATERIAL'ND DZHCR SZNSOLS, NOT EXPLAINED DN THIS f)VIG<<AND R)RMARK NtCDDCS, SCC DRG.IE-SIDS Ctt-DIDA O-MANUAL V(XISCC DAMPER g MORA(ALLY ODCH-NDE(MALLY CLOUD MOTOR OPERATED VOLUME DAMPER-ZACE E)KAFT CAMPER CLIASS<<A'AE DA)r(PERCtsLDRINK DCZKCT02 2 SENSOR RO(ICHING FILTER 2 MEDIUM KFFICIKIIT FILTE R FIL'fcR Dl(YER HVFSOI v 5511 I445s EZPA)(SICH VALVE ttv Sas EVAPORATOR TL 31'2 I~eeet<<)C tv\st<<et st<<$<<<<s tea I DNICSV Pt A5 Voj vvc VZX 315 I 53 VTX)25 Pl t VIA Sjt Vt2 YT 322 YAPORATOR cease\esca awwws we I~wwtt I vrl I[(esl 1$GD PRESSDR otlfcs ssetrr ss v I I 0 I I)FILZE)c VRY<<R W Fest Vso SCI f XPANSKN VALVE~vtv'553 CHILL'CD WATER;COIL EICCTRICJ)EAST COIL 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s~<<sr'I<<tacat s~va ar r t tacat CN 5 ra(tr Cft 4 IJOTE:RR c<<ctcoAL TcST (Asst CTLR ssfoaKL(RW FCR CCNX SEE SCE CHART<<A.)SKETCH<<s 9 Hv A(Coo)A HV A(RFVIA 8-=Big)fr I I 4~to I ltusft ZL ICIt Croft(f)AL VII.ZER NsR'C DRDZ<<CTION SCE DVIG 12-5)52E, Jh FsLTCR LIMIT HV ACRF vÃVPA I w(5'f st'v Act c VL<<t NIOAIV tot CO<<V.Ost Sr(cog<()1 s)co'II f 5<<V Actf~4.:e I.C.-1 cast<<v.Loaf<<so t<<a j4 rl (1 Cfo.o 24 sr 24 HV AOAO$$$tr lttltCR TO(ET ca<<avstfars o(octal twftoco (I 4)l.o<<I Lett i 2 PAN$(C (rsvo.rt Ss<<rl DETAIL C.D'O<<law. <<err<<refssuart(arts(L<<<<r NLV(1 t IL<<s (s tva<<o ts)1,000 cess~~!<<e srsoAtses r<<0<<sacr~ov Oec<<Avssso) scf TCN K>Co<<vsoa tooae Toa(T ROOM vfNTKAfsore ($<<ae(O COVsrv(rsf) <<Gv 4 0)E~stirp~tc ltl af RAT st w mrs's s w pA L~L 5 tvlfo'vfc oe rwrsv (r WJL sea Aasea<<t'i$:)ig~-'Q.,l~east F.C tL't(L 3(tf ACRDVI~esses\<<sc ce sees te<<v Lea<<s vlc'tta tccofcK sslsc ce<<rssoa eet ee~t vfc Sss e e~lts res<<aee<<L L 4<<<<wset vb oos (swee<<L AHM ee<<r orer>>.seo sa.As 4 COO LCD COLIOC rrerrSC UNIV 21NsA(fsrU I usaf<<AR<<srMtt.'s foals c (tl NvusostKt taccrG(vtc SC.O 5((fwSD<<CD(ILL O'Ws art tsr rac<<as(t 5N tet~1<<v Lca sic$4 smA(ea IJ Root'4 g0 I I w.a(ales IIISVLC f)ARRIK R LDVVC'R (Off)T)DE)~ ff ENTARC)'570'Cl M 5 loafs 514.cce<<$10 tc csFctt toc)sr cfsoo Cfw tAN COIL vest)IVOVss UNC stsst'f t(fulN<<sN(aetNv.accost to 1st rsvA(fo.s N Sort<<Ak<<aw<<st 4(F<<'ZC ILCCL45 ttt ttt<<4 IAIR;CORD)nONIN c-SV5fcll S(C DCK1Kr vf tts W Ltt<<t oc Vtc Oettts 1 lt'I st'CTSrae taew WLO tosert NCC<<a (thos cf rs)~<<ere LS<<VSsre\Acre sfeecese 4OA ja CONTRsDL ROOM eJEC 5 SEER)EATH) N/C LEAN Vfr IHV.VC)(F)SEC DKT.C.%'fc oeoafs s3$<<otsow LINC ANo I VII)f 0<<fu E I twv HV ACROVt F)KTKICsYstcH vct Ioa Ru Sf s ROON 4)EISSI(fsBAWIER LDNICR (Omoanni)C INTAKE)/24 24'occttarsfovs oscvrsis,l(L <<TOTK Ot IPOO Cfas (1$5s 4 (c CSDIL w acaovs f(C->)HVAElt()at~ .24 AZC;.vtc'vtt-OO Cstsctfs Oor HtfcACRDA IC ELCSDSF ssfa(RL(eot L Hvrrtrro sfr'T(FCORHDXRDDII AIR 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REVfstON~Btt SEPIVIAtt Rtvl 5 tON)I(CO((f foa flc5 DRARINC lsr kkseke~er erevrr ee cc kerscv fsktpc seve scree cko.OO~svvk oee~frere svf r 4 ev kk c roveksv ee ewe 4~ke revcee~~kkvtske ek kee scesle essscc pc ww creak v pc etc fleer cer~\eke kv eseloc NIswIC.~kcrsc kc r kk c kosssck oc~IICHANA a SNCNIOAN CCL (K)/(AU)C COOK NUClEAR Ft))crt FLO(//DIAGR'AM EMERGEN(:Y D(ESEE GENERATOR'A8 ss ofL No 2-5'1 5 l 8-27 e'L J lLC K ET WATER HEATE.R I'-4%CIA.X 5L3 NIGN 75 KW 8 sc-t or f)4'Ab AUX.JACKE)'ATER PUMP 95 HP 175ORPM IOGPM 20FT.TPN Q SC.~t Of s)5 AS 5tr US'kc'f s)akks-fp RFROM ESSENTIAL (s)ACKET WATER DGEOCsa SERVICE, WATER.SK~E IHLE.T PWG.5113,M/0, LI/9 O'ACKer WAVER PVsats 2$HP sOOCk a7sa 9to Psk ,O PT Tor t Oskt s5O ka DIESEL ENGINE S,CNZ A ANK I 2 3 4 S i 6 4 lttR I 4 NSIE'ssd OTC<<kct Vert)VC fta vert 4)SLO setccutts=OsC 4 SSMta Pttc tl StatSCC JJ cof sl seer AMtal(PN EIICTRIC KttRfxt BROAPWAV N ter Tsttt t I O 8 7 1 0 1 3 0 2 7 8-ktv(ft s s 0~A A I\J ~~~~k C~'~i~~0~Tt~'~~~0 (.1 494Jl 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Etta COCVROC%5CC Oar'rg.S IVCJSCS SSA);R-=TO ATMOS.8 1 (SCTAT SOPSI)DC, ISOC SV'79 CD2 V2 250 PS I C)ISIS.1 KKC SICS SET AT ltSPSI~KN 0 BREATHER PIPING XR.V 231 IO I.DGI9?G PRESSINE REOVCIKC DGI41C XDI VALVES BY Q srtSCOI v50%AT m C 2 I/2 Ca'ts PSI LEGEHD STAQT INC I IQ AuxILIAQY PIPING VCH'1 TO C'Talcts.ISI 041 it', 2,.Cta CRV.CSG-~B~~j Ii Dl see CAS e Di CSCC.(t)AIR DQYCRS SV.TO CDI 35-.TQ(01.143<ot)<SID'CD xct 151 SKT Al taaoPCI IC (cAT 143coo ssc viiataaCISV VC'P~COCCDIK CDC Raut~StaaDLY IO llR IAJC To alMos g DGISIC Vt AiR VPPIYI IK'E TO t SVDI CIC 50'I Scc TH IS'm HI), rp Ih 7 8IXLDI:Cs WALL DGCOoC+at BCPSI JCY ASSIT VICvc XRV ZRS l, tta l i C)P 2 CO FLEXI~c COSH HOT KSYtI/I rSa"1d COX TI APEHVURE CAII'9-I Also AvadabIe Oa'(5pertare Cora ll Av to TVRSG CHARCTR fl5g RC PRESSURE RKOOCIKC VALVE I 5KT AT co pel IXRV-CCO t I t SV.SSCDC , 5 I SC.TAT 21$PSI DGIIOC~SECAT/I CT,HTRIFVGAL KXRAUSCKR@TIHP 3400 RPM 313 CFM TC WATER Gtrtco&O Doicec-I4 4 Co uses (rsxwva(vts' I LOCATED SHX luh f Cs-I ROSC CtvAFRISSO 0 SUCTION ALTER~1st\41 Oi ra'0 Jr 6-ro 4 R'RIFICE f(SILE BY FIKLP FOil)t S50 INCH i w.G.vacvuMI OIL 5'KPAQATO R MOUNTED OH f HCINE ICI M50 DGIOAC~'2 STARTIHG Alit hWltFOLD)la I DGltSC OGISOC DOICCC RKAR SANK 5~f R(FIT BANK Z.CD Oci61C DGILLC V SIIRTOIC SIR vstvt Kt I Stl TOIC IR.CRT~5 Ov ici COC 00 iaicsi DGIICC Fcvcefo V('Nte DIESEL EHCIHC, 8 I'CRatts(DGIIOC PLUGGED VENT 1RV.R r ST RAIHrJI OGICCC Dcitt4'G I I4C 14 Dsaarc OACS SC KI SOW Occscc DIESEL Kwctaac Oasr.ISDCO W4 FQWHEEL A'lC~CX(HECTIOH TRAP, g ttIARC RECEIVERS' R, CDCwc oeoet 1-50 CO2 STIISe.cot SLGptAXIS3'.S.Crt T.HO.Col OCCIGK FQCSSVRK 250PSI I'RAIN I DRAIN IS)AIR COMPO(5SORS FCR.KKNHE.TIC'HP 960RPDI (115CRPM Aa&TOR)I SCFM 2SOPSI CCC ti45 tor ctl ,AIR CDSTAICDIIDAS 1WO StaCCS Le)AIR CCOLKO S.C.-ZI I I SYH Se col ISI DOCS aaOY Aertv 3/8'ENT LLS g~~I'CAPPCO~GKHO INTAKK ISIQ T.XHAUST CAS'UXILIARY PI PIN C LECEMP UACKKT VIATEQ SUPPLY IIACKE'f WATER RETIIR I fLOCT@YILYE r JACKET waTKR MAKE UP, 5EC DSVG.51l s.PI/GIKL.COK G~Oaf RATING L(VEL.KL.COt t DW?SOC~ae Oe~H AIIXILIRRY PIPING, 3Cr VENT 5TACK TO ATMOS.EXHAUST SILENCER (fr lot co'C SO LOW ALARM, KL.COI 5 CCC Alt 504 soac 4 1st (3Ctttotvt C.5 KL 539'3 Ia/ICCFOSCOIJACKCT lilaTCR 5VRGK TANK 5 C~I 5':G Dll.s 5:0 100 GALS.GK)V Pa'.XTCAO SIGH'S.C-K Q>>KOTEI MIXIMVM ALLCVIABLE TOTAL PRESSV'RE PROP IHTAICC SYSTKM I 5 INCHES WG ECRAVST SYirSTKM 10 INCHES WG~C~ad~f 55;OPE/IING tulAKK, AIR FILTER QT Coco EXHAUST MANIFOLD~TYPICAL FORll2)'fEMP RfCOROERS XT AK tatLK 3'Z 101 Crt 910GPM ISO F 7 XOI CPS rd tera~ew eaaal oavccsc 2 Ir8 rcIACROCIICY MAICC')5 3 scRvicc wAYcR~aJI'ISfccs Csat DAC~I TIGRIOC CD~5 CSW.CI~IOCS HtGN E)s.crt'I Av Cc DVVCACC OG RCGC 910CPMrlso F 3 TI VO VKNt 4 5 OG.I'12C lu BING$Qvt PWCCto OvIRFLO4~'KE DECAL.L/5 S rccIN lo L FROM ESSENTIAL SERVICE WATER, SKK PWG.5 I(3, K/7(TYPICAL) IIIYAKC MASOFOLOS Wlvit AJa TCRCOOARIIS I 26/LEXIS(C COKH.I Jec coIISCIVD at IO2-CD 2C 30<13350 CCH-SOT T 3 41 IIE.47.CON% IHYAICC MANI FOLCI ERONT 9 HK47-CDS CY I Crt ss CRAPE KLGOB'0'SvvAVTDCRIAO5TACIC VDAVR ev EI(cN.tsc.co IO aOet.tst'SF r 4 4 I I FSi CCS%to Orat.too 335~Ioicwals Cavratra)I)g I I ELECTRIC 8 I Ilo G PM Ies F C I c 5 HEATER 3KW OT.SOO-CD I TVXHKL I I I I~I aTC TA a)ccv tts DSIIS CDYC rvckr tts Ftooc CII sac)cave cata444 DOYTLC 5+GICCISI sltlt<5 g s t31 gl f Cr 8 SILKHCf R l KFO 535622 Q.S.c.-z Qtcal CD ate 8~e 8 e K3 Stt I OT.S02-CD TLFR8ct CHARGCR~KET Wu(R AlZSf\s ri ia a Deil 184 PIPE 8 Ir)HISVCAT COR SOO f HOT BY Q 0~v~a Icrcllsvt r Otr DGCDAC carcccac Ca C ODD IA\~IC 55'CD OGISOC ts a r~3 r 5o f l.EL.596'-0 QT lsl CD XT PIPE SY Q IHSUL'ATIOH,FO+ ~e itt)'F HOt BY LHI (ff-soZ.CD 4~--3(COGCFN.SCFKS 100F CXPAIISKIH JOCIT DSKIBS QT-103 CD 2'CC.YVDC Dviiclli A,R (vve)~5YH'RIO COR I OGROOC R SLSdt:o'BUILDING&ALL Ft CL.SBY 0'GISLC 8" DGI GCC Ja(KCT'WATER cooLER 8 OKSICN'SCOK TubE SIPK SHELL SIDE 150 PSI ICO.PSI 350 F 350 F SPEED Rtt)ICATOR SUPP(5 KD WITH ROUHTKP ON KHGIHE S.C A CT e-TABLE.J 9 ExHauet MANIFOLD TEMP.IHSTRVMENtS LTC Ca'I f Lf 8567 0 W Al'O IHT K I 2'3 4 5 6 JACKET WATER IHL'KT BOSCH.RIC.COI 10 4 FROM ESSENTIAL DC toec SEQYICC wATCR.5EC DWG Sll'SiMIdiMI9 JACKCY WAYCR IsuaAOS 2$Ite IOOO Rsia4 vt (GTISO coL)g Sc.t (O-.-iso col)JACKfl'WAtKR HEATf.R T-CVSPIA.X sts HIGH 15KW Is)sc.-t-'(ot I34 CCI)AUX.4 AC'KE'f WATT R DVMP Y3 HP ITSORPM IOGPIC 20Ft.TPH 8 S.C-C (ols(35'CO)(OME.ISO.CD) DIESEL ENGINE S.crt CC CR I I t 3 4 5 6 inlet cec Isisc weve 004 VID tCO AIIS svrectCCS Oac C'SISOA Dcc II~ESID AS NOTED~Mt~0 I BY WORTHINGTON PIPIHG AHO VALVES FURNISHKP 8Y Q A'QC HOTEP.FOR VALVE.IKSTRVMKKT. SattptJHG ptpE MaTKRIAL AKP OCHER SYMBOLS NOT ECPCAIKED ok THIS OvtG AHO FOR MaRK NUMBER COODS SEK OFIG.5106~E/8 KHCIRCIKO LETTERS ARE SHOVtH FGR ORIKKTATIOK VALVE SI PIPING laf SK LETTERS REFLECT SIMILAR MARKOIGS ON VALVE BODY~Oi Yttb U tet pR E pl x Des toata IIOFt RACHGODIOOKKNTCGHYI FICAtvok HV04GEIC IS R Uk LCSS OTHCQWISR HOTCO.F.A.X OIOKACCS VAIVC CAIIVRC PDSITKW SAIC A5 l5 ALL OIKSKL CEHERatoas INCLUOSIC TXKIR AUXILIARIESI STORAGE TANKS K PIPING ARE SEISMIC CLASS l EXCEPT AS NOTED ALL PIPING l'0 SE CLASS OR, FOE KH EXCEPT AS NOTED.vc ACS~DD 6 ec.sea oaaac cares crccee~awvve carer'D v e sea D~4 a~C c c reira aeccv oc are we I cl eraeeacc Aiaveraee'ae 4 cccv caosco vceav'va I CIItl ICA IOR 45 L OSRV KSOOOC VlLVX IWCSCCRC CH CIOS ORAIISDC OCC tc YALvc KscsttpKcttoR ~LNT PCCt COISVICXICC OCSIOK Coot)ICOtocRS, z.'car HACCKRS lscotr leo FDR OCSOsra OSC l5 FOLLO05: CA 4 Ra: tlarvccr%lrrcARS A5: Itccctsw Xttmsccstxt ooor lvscvc HNtc RCS SOC Slvoctt CSI CSC CSCX vlcvc Kcstcpt accst)tcatvto Sv loor45 to~ttsOOIOET CIASNst: ICCI 5OIICC COCASCVI" FCtt CCICCR 1 FOC SCCROCICH CIAIIIC Ccttlctl RCCIXIO RR 11\5.-It.tc 27 IOR'IICVI50OH ~~Colt TIC5 ORCIC505'04 aww~ae awwa e w aaegel Caaa+c aaw aeeeaaei ae 0 ww aw eww ce 0~ae ia 4 Deeaaae aa D eea aa 4 wt.4 aw w Ieeaw ewrw la ari aaaia ewe Dc wile<<eea 4 ca a as area oe M ei leave~asaas w 0 e ia aeaee eaa ewe, FI.OW DIAGRA/v(EMERGENCY DESK GENERATOR CD OIL No Z-S.I S ID-27 CAN CCCCIRK Isccastcnac csea Hoasaatt Ice'Ieaa C o C I I 4 H I K L I H I SV 1.0 18 02 V8-gg I I'1 0 fi 4+I~I pp (~g~~4 f V C 0 C2C.()EMERJ(L NOTES LEG END~MAKE Ur vIATER Itis OI(IIIE CAUS'tlC 70 ANION KSI EXCHANGER AIC3 MO(KD EKD Cat DEMIN'ERALIIER sEE Dwo CfAK 51is LIS KEV 720 taft to v',)F5 I I 5.-K I RECEI:EKATION CueiCLE 6V QP~j 2)C'itufe AACID To 50'YEHT ACIDS j KSX I)2'I I 0 1 Xf3 20'10(24 MANHOLE rCAFFED Cot(st (UNIT H (ONLV)PRIMARY WA'1 f R 151 TO Af laos SKETCH J-3 ACO AND CAUSTIC EOUIPMEMT AND PIPING FOR DEMINERALIZATIOM 5557 M (CLASS III)CUEICLE NEATER ev Qp DC I I'I, IKW'ATION E'kCHANCEIL Sff DWC 5IIS,MI4 Ift DILUTE ACID 10 MIXED SED DKMIN.ERALIIER.ME Dwo 5115, HIS.I j KFA j.,I o.REGEM.PIPING e~CONC.=ACID 2)c FILTERED wa,f ER.Kf SEE DIIC.St(5,J/3 TS9 3(5(VITIO SY.3$SI'.7 AT 150 PSIC Caf Csf P Sst YEMI rACLcstt C KRV 252 Ntusr TEE Kaa/.16 coscaaa rstt fat cat sar s JT (1)ELECTRIC CCOS(K IICAIERS ID KW EACH CONC.CAUSTIC r lasso r MLSS rs-rtoLTC Na ls 1 AVXILIARY PIPING HOT WATFR TANK Sto'NA XD'0 SKID Oaat I ID~ASTC HD SPIIr LEADED CCS5(JRE'2" Cf(XKWG VALVE(IYP. I I))ACKMIStolultSDM ~csatf 2(sctsaaL) sfE P a KJJCA OI IS'/0 OCIISS~COON 1(NT 515.SKE DW DVE-IISr1 Oif 254 a~ass (g~4 Nl-~3/42 KRYg29)<<Is I'h DRAI KRV-7 IVN f r esASCN soS'g", YL toc co~5'es fad oeasscasar SKETCH'A-3 Et(52 faccfaao fccaac Itcaatas (aostaaaa rises 5 ae Saaot stasaasc ccassc((sat~'2 aaa SYM80LS OP PERMUTIT H.t.Hof 2 CONNKLTIOMS FDC, YALVECINSTCVMENT SAMPLIMG PIPE MATERIAL, AND OTHER SYUSOLS NOT EXPLAIN((S OH THIS DW(L s AMD FOR MARK N(NICE(K CODES,SEE DW(L 6104.OP CC Nes C.SC Ze I~~Lfl.CECEN.CASINET(((510r) 113~MIXING TEE..FILSA~0+f&4k L'NCATIOACCOM'C 990 32: KLY-950 OWESS OP I2(759 6 OW I54g 4(AT fit Acts 2 10 ROON VKNTSVS,%5 DIGSAIER)Io(tssJDKfxcasac ~'I 0 I 4 ftLsatcst Duyutt tffrscat)~(Iy Psctc)EL 591-0 KRISS f4 10'Ir A(CO DWEEB 22r AIIKEKD c (ttncea VJIIIC(ltt(JINATT SEC KLI~~IE~L 707 02 t OJECFLOC/KKA'f TRACKO 0(.5 950VI KS sl OLS'l S I ZJL MANHOLE~e~~KF Ffttoo Sts SCC KPI 1 7 CARDS((STEEL 2'KCKK CN(SL 10 (NIT I C 2 IFNacvcs sts(KN 5(E otG 5(fo,t/4 att Jc,sao 2'REEFJL 0(KSL KFI c 5 sct ts r Jrass r INN(HXE I I cttas vaavf I (ftrtsssNKO I Ws14 TANK I OVf RFLOW TO FLOOR DCAIN.j---Pwta'Eaulrtt EIIT SE I sut C CLASS AS NOTED I gANHOLE I'JS(Cfn~(ffRP I$.<F(txf va(36'I C.EL cod HF TO CVCS SEE 2'WC 513(,L/L OVKC 0 fLOOR DRAIN, EL SC920 2 ah¹I I 5 24~u ITHSI I ftullARY t(ATER STORtGE TR.NK 3740'OIA.XSth)P HIGN CAPACITY ZSO,OOO GALS.SEISVK CLASS 2 (TK'31)(VNST No.t SJNILAR)TAIIK AREA Fst'5 Tat44tl CAIN TO flOOR Or IUNIIEL H'ss OR DKIAI L ANS LO(At(ON of N(RGKNcv sHOMERSI Eft 4 t(asifatt\ AT ScXSUCK ACO CAVMiC 31DRACE AREAS Stt D'Vra.l ftlt;5'K.K 5 (2)HAI(E UP SYSTK24 At lb PVH'PS ('PP-aS)ecr Is'I HP.I(ICON CAUSTIC STORAG'E TANK-(Tk-45)CAPACITY 10.000 GALS CVCS CAUSTIC PUMP NOTDV(g (PP (e7)'C CC~$32 HP Ss art(,~rsaaccasa es cavaac tsrrsc aca cast.tace.sass Ie'aacsL aaaa codec sasaavt aca ss Secs SULFURIC ACID STORAGE TANK (TK 44 3 Acsa eaarrsrttc .CAPACITY 10,000 GA(3 cas aasLKJS I 5 TO UNIT N 2 I cos(fso4 f 4 I COOLINC SURCE TANK S(E DWC.5ISSAs J/2.j 7 Owls I OWI92~AT SPQA'IJKL PIT I)'KC~g tl ILC lg TO UNIT'ice 2 COL(FOMENT. COOVNC SURGE TANK SEE OWC.5136A, J/2 Teaasaaaacf eaascc aaae1 ceca~I DRAIN F<o.ON542 (awlbtg TO ICC MACHINES SORAK MIXINC TA4K SEE DNC.5 I 4 6A, I(/3 tat aaasf et(tat arc~stc casa claaAaaaf eccaasaascassa Na d tact aascaa era casa asseca km~KMCKOS(S(E EAST (560(2 ELII CR ELGZTCS')FW (34 I)t1(C Lc ATVKSTISV(t UHIK Nt I I Hc octtsKRtttus HAIK IYK)~~CJSCIAtsot(IIT AFC1usaKKL DR2137 r ELC'50 0 001st 017103 F w25C Ra.I~OWI06~2~177~CrW107 I'O 6OROM IN/ECTIOM TAHK SAFE'f Y VALVC'SEC PWC StctsK/4')) FWI32 I 10 bORON INJECTIOal TANK SAS ETY VALV(a SEE DCCC.C(42.W+ IOOT Nt2 I tsf CSCCfaos asasattat (32 NC.L ONLY 1ts(RK VALVC ttttaststr APPEAR otl fwss I7tatte(L ttt SttlLRAft VALVE tottsttf scaf Xsc Msf FOR co(lvacst(f otcttd.(ttcRI RJICOCRS E.TAA~IIRCICRS IKINFt(0 FOR ORartat ldC as FOL(otti TAO Ical 2 SWLSISSW AFFCAJt5 A5: tdtltXW SattRJCCDCT Roof vatvc IMR lets Nof ssaoow 04 CRawsao(scc VALVE IOCNTIFICAflON (JSTI ofotfco tf AOOJNC 10 sRTJaccocf NJsatctt'tst 5PKRC ssttscYI lcR (axtxc sr(LKwcrs IRENR (tstsC LCO~~M4(AT Y(sfttiRK SKE~UNlf Mtt Caests 2'ttlf 0 I ILC.IO YCSf tbULE.ARIA (fOR ftuls(SNC potNK04(tf ocavN HKAT (X(HAM(s/Fw(35 2'tost(N1 Rtsst seasact KANscbtaoa Ntcoca.stt ELC)YLF tao A Ot'I I 4'(CSO lt(SN ILL<mews,~Ž~W 2 TO SPENT fuf t.PIT Kt(IN.SKE PWC.51SCaAIC Itt N.C.see)31 Stc csd 1 s41a.0 I'O DCSORATINC CATiost SEO JCJID NIJ(EO SCP DEacsL SEE DWC 5(SO,A/1 aa 2 s 3*2~2'WI96 I tlo ocaoao 2 o[.I-as IJN(f Nai I'.2 acs I Oss IH'70 tVIFORATOR trade((KR 2(E (ahw 504als EENC.ca 1CL A 2 Otc(90 I'/2 4 5 bNCCNS OKLAtoct fL IL612%DW207 pes 20$I2W CHH Net FNltf IP~ISED CCNCEN TRAIES'TRAN sf CR FUCCP5.5)a 2 1'o IAUNJRf ROOat FJCIUIY SIK Caetlt 5(72 Ifrsc I Ib'ILG r Ta 1 TJN K OW20(SEE.PWC.6133 Cl 3 O'Allo cacs tstgall Pw(2C EL tsOY-(f AT Stet(7 Ftaa.DC CCKI vosctNS DowN saNINNaas al\V~Dsvtts fat sc%T ccaesaf aaeaaa~States Sao OSIS, SC Sac ataoat ccrrto.f<<as~A~n eea.r(OCSCCN eaA aaaa<<aa oa<<aeAJ wdc(Efat a aiaaa Caa act.aaeaaas sea~+Oleo S(3(JIYI.lp STAT NH SKE CWO SISS.MJG sc lo tiats4'rl(N(OCN&10 SCPCOCLKG GsattaaNs laser aasdast arc sst oat Nsts,us lt.t-fc 4(.Jsay ls Cec 410 CW oft Cat 1st laaaesaat tccssc sssc ols CARK lif satsrPINO Ig aft e+oc 10 SCRJC MSD.EYAPORA7(SLut- ~Otso 313%, L(7 ICXCIM EVSP.61 557 W fOSI RCVI5ON DCICIIFIXS(SCC SCFSRATC IKYISJON RKC(NO fOR lit 5 CRAIWS~tct S I C SIOi f c I DRAOI 3 fRDlt ttalofDR TANK PVNPSSEE I Cdt CS102 DIJG.(134,MJJS. 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