Text

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)
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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

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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 INTRODUCTION Revision No: 2 Figure 1 Date: 8-31-87

1. Valve Testin Pro ram A. The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the 1983 edition of the ASME Boiler and Pressure Vessel Code through Summer 1983 Addenda, except for specific relief requests which are identified in the Valve Summary Sheet.

B. The valve test program is applicable for the second 10 year inspection interval which commences on July 1, 1986.

C. The valve test program was developed employing the classification guidelines contained in 10 CFR 50.2(v) for Quality Group A and Regulatory Guide 1.26, Revision 3 for Quality Groups B and C.

(Quality Group A is the same as ASME Class 1, Group B is 2, and Group C is 3). NRC staff guidance was provided by memorandum dated January 16, 1978.

D. Figure 2 identifies the 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

D. C. Cook Nuclear Plan Valve Test Program Revision No: 2 Figure 1 Date: 8-31-87 h 1 REL Relief and Safety CK Check BF Butterfly Gate GA 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 Figure 1 Date: 8-31-87

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 Valve is to be tested per code, no comments NO, NOTE X Valve is to be tested per code, but there are comments YES, NOTE Y Code relief is requested. Alternate testing is proposed in lieu of that required by code, the note explains why the code relief is requested.

E. Alternative testing 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. valve type and design similarities 2 ~ system design, flow, and service conditions

3. frequency of valve operation 4 ~ manufacturer

5. size range (i.e. up to 2", 2-1/2" to 4", 4" and 6" 6" and 8" etc.)

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.

Page 5 of 70

D. C. Cook. Nuclear Plan Valve Test Program Revision No: 2 Figure 1 Date: 8-31-87 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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:

Review of valve's design specification and/or manufacturer's test stroke times 0 Review of system response time requirements (Technical Specification, FSAR, etc.)

0 Valve's historical stroke time values at various system conditions Page 6 of 70

D. C. Cook Nuclear Plan Valve Test Program Revision No: 2 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 Established Recommended Action Time Stroke Time Base Line on Curves (Limiting Stroke Time Ran e-in Seconds in Seconds Values in Seconds Based Line Time x 2 + 1 Second=Recommended Action Time or Tech. Spec. Limit, whichever is less..

up to .74 0.5 .5 x 2 + 1 = 2 Seconds

.75 to 1.24 1.0 = 1 x 2 + 1 = 3 Seconds 1.24 to 1.74 1.5 = 1.5 x 2 + 1 = 4 Seconds 1.75 to 2.49 2 ' = 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

D. C. Cook Nuclear Plant.

Valve Test Program Revision No: 2 Figure 1 Date: 8-31-87

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 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT 2 LIST OF DRAWINGS Revision No: 2 Figure 2 Date: 8-31-87 SYSTEM FLOW DIAGRAM NO. REVISION NO.

Main Steam 2-5105B 42 Steam Generating System 2-5105D 2 Feedwater 2-5106 34 Feedwater (Auxiliary) 2-5106A 41 Essential Service Water 2-5113 36 Non-Essential Service Water 2-5114A 27 Station Drainage Containment 2-5124 20 Reactor Coolant 2-5128 19 Reactor Coolant 2-5128A 34 CVCS-Reactor Letdown & Charging 2-5129 32 2-5129A 20 Component Cooling 2-5135 34 Component Cooling 2-5135A 30 Component Cooling 2-5135B 14 Nuclear Sampling 2-5141 27 Nuclear Sampling 2-5141A 30 Post Accident Sampling-Containment Hydrogen 2-5141D Emergency Core Cooling (SIS) 2-5142 28 Page 9 of 70

DONALD C. COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT 2 LIST OF DRAWINGS Revision No: 2 Figure 2 Date: 8-31-87 SYSTEM FLOW DIAGRAM NO ~ REVISION NO.

Emergency Core Cooling (RHR) 2-5143 35 Containment Spray 2-5144 29 Containment Penetration & 2-5145 20 Weld Channel Pressurization Ice Condenser Refrigeration 2-5146B 23 Containment Ventilation 2-5147A 35 Control Room Ventilation 2-5149 23 Emergency Diesel Generator 2-5151A 26 Emergency Diesel Generator 2-5151B 27 Emergency Diesel Generator 2-5151C 26 Emergency Diesel Generator 2-5151D 27 Make-Up Water & Primary Water System 12-5115A 41 Compressed Air System 12-5120B 22 CVCS-Boron Makeup 12-5131 19 Spent Fuel Pit Cooling & Clean-Up 12-5136 25 WDS Vents & Drains 12-5137A 21 Post Accident Liquid & Gas Sampling 12-5141C 8 Post Accident Liquid Sampling Inst. Panels 12-5141F 6 Page 10 of 70

DONALD C. COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Revision No: 2 Figure 3 Date: 8-31-87 ASME CODE SECTION XI 1 CATEGORY A-B VALVES PARAGRAPH EF-1 Exercise valve (full stroke) for operability every 3 months. (IWV-3411)

EF-2 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 Exercise valve (part stroke) for operability during operation; (IWV-3412)

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 refueling outages.

if full stroke test is deferred to coincide with EF-4 Exercise valve (full stroke) for operability prior to return to (IWV-3416)

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

EF-6 This note was intentionally deleted.

EF-7 Exercise valve (with fail-safe actuators) to observe failure mode (IWV-3415) every 3 months EF-8 Exercise valve (with fail-safe actuators) to observe failure mode at (IWV-3415) a cold shutdown or refueling frequency, as indicated.

ET-XXX Exercise valve power operated (full stroke) and measure time. (IWV-3413 &

(E.G., ET-015 means recommended action stroke time is 15 seconds) 3417)

ETF-YYY Exercise valve power operated (full stroke) and measure time for (IWV-3413 '&

fast acting valves. Code relief is requested in Item H. 3417)

(E.G., ETF-005 means recommended action stroke time is is 5 seconds)

Page ll of 70

DONALD C. COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Revision No: 2 Figure 3 Date: 8-31-87 ASME CODE SECTION XI 2 CATEGORY C VALVES 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 (Code Relief refueling outage frequency as indicated. Code relief requests are Requested) provided in the flow diagram notes.

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 Exercise valve (full stroke) for operability prior to return to ( IWV-3416) service.

TF-1 Safety and relief valve tests (setpoint) to Section XI, Table (IWV-35 10)

IWV-3510-1.

3 CATEGORY A or AC VALVES SLT-1 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".

SLT-2 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".

Page 12 of 70

DONALD C. COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Revision No: 2 Figure 3 Date: 8-31-87 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: 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.

NOTE 2: 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.

Page 14 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 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 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: FW-149 and 150: The required full stroking of these check valves is satisfied when Turbine Driven Auxiliary Feedpump completes its required testing.

NOTE 5: FW-153 and 160: 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: 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 NOTE 3 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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: 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.

NOTE 2: See Attachment-"A" for permissible seat leakage values.

NOTE 3 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.

NOTE 4: 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.

NOTE 5: 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: 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.

NOTE 7 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

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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: 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.

NOTE 5: 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.

NOTE 6: 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: 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.

NOTE 9: 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: 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.

NOTE 4: 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.

NOTE 5: 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: 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.

NOTE 4: 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.

NOTE 5: 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 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.

NOTE 3: 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 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.

NOTE 11: 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 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.

NOTE 13: 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.

NOTE 14: 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: 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.

NOTE 3: 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: 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.

NOTE 3: 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 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.

NOTE 2: See "Attachment-A" for permissible seat leakage values.

NOTE 3 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.

Flow Permissible Leakage Valve No Diaciram Size ~e WCR-920,-922 5114A DA 900 WCR-921,-923 5114A DA 900 WCR-932,-934 5114A DA 900 WCR-933,-935 5114A DA 900

, WCR-941,-945 5114A DA 900 WCR-944,-948 5114A DA 900 WCR-951, -955 5114A DA 900 WCR-954,-958 5114A DA 900 WCR-924,-926 5114A DA 900 WCR-925,-927 5114A DA 900 WCR-928,-930 5114A DA 900 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 Flow Permissible Leakage Valve No . Diaciram Size WCR-929,-931 5114A 3 DA 900 WCR-942,-946 5114A DA 900 WCR-952,-956 5114A DA 900 WCR-943,-947 5114A DA 900 WCR-953,-957 5114A DA 900 WCR-960,-962 5114A DA 750 WCR-961,-963 5114A DA 750 WCR-964,-966 5114A DA 750 WCR-965,-967 5114A DA 750 ECR-10,-20 5141B 0 '0 GL 750 ECR-11,-21 5141B 0 '0 GL 750 ECR-12,-22 5141B 0.50 GL 750 ECR-13,-23 5141B 0.50 GL 750 ECR-14,-24 5141B 0.50 GL 750 ECR-15,-25 5141B 0.50 GL 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 Flow Permissible Leakage Valve No. ~Dia ram Size ECR-16,-2'6 5141B 0.50 GL 750 ECR-17,-27 5141B 0.50 GL 750 ECR-18,-28 5141B 0.50 GL 750 ECR-19,-29 5141B 0.50 GL 750 CS-442-1 5128A CK 750 CS-442-2 5128A CK 750 CS-442-3 5128A CK 750 CS-442-4 5128A CK 750 SI-189 5128A CK 1200 SM-1 5141F CK 750 N-102 5143 CK 750 N-159 5128A 0.75 CK 750 PW-275 5128A CK 900 CS-321 5129 CK 1800 VCR-10,-11 5146B DA 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 Flow Permissible Leakage Valve No. Diaciram Size ~Te VCR-20,-21 5146B ,4 DA 1200 DCR-203,-207 5137A DA, GL 750 N-160, DCR-201 5137A CK, DA 1125 DCR-610,-611 5137A 2.50 DA 750 DCR-620,-621 5137A DA 750 DCR-205,-206 5137A DA 1200

~ DCR-600,-601 5124 DA 900 QCR-300,-301 5129 GL 750 QCM-250,-350 5129A GA 1200 QCR-919,-920 5115A DA 750 SF-152,-154 5136 2.50 DA, GL 750 SF-159,-160 5137A DA 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 Flow Permxsszble Leakage Valve No. Diaciram Size ~Te NCR-105,-106 5141 0.50 GL 750 NCR-107,-108 5141 0.50 GL 750 NCR-109,-110 5141 0.50 GL 750 RCR-100,-101 5128A 0.375 GL 750 DCR-202,-204 5137A 0 '5 DA 750 ICR-5,-6 5141 0.50 GL 750 ECR-33,-35 5141F 0 '5,2 GL,DA 750 ICM-260 5142 GA(DD)

600

~

ICM-265 5142 GA(DD)

600 ECR-31,-32 5141F ~

GL 750 XCR-100,-101 5120B GL 750 XCR-102,-103 5120B GL 750 GCR-301 5128A 0.75 DA 375 GCR-314 5143 GL 375

Double Discs )g 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 Flov Permissible Leakage Valve No. Diaciram Size ~Te SI 171 I 172 I 194 5143 0.75 GL 1125 NCR-252 5128A GL 450 CCR-460,-462 5135 3 GL 900 CCR-457,CCW-135 5135 2,2 '0 GL,CK 1125 CCR-455,-456 5135 2 GL 750 SM-4,-6 5147A 0 '0 GL 750 ICM-251 5142 GA(DD)

600 ICM-250 5142 GA(DD)

600 CA-181S 5145 0.50 CK 750 CA-181N 5145 0.50 CK 750 SM-8,-10 5147A 0.50 ND 750 CCW-243-25 5135B CK 750 CCW-244-25 5135B CK 750

Double Discs t g Page 64 of 70

C. COOK LEAR PLANT I'ONALD ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: -2 Date: 8-31-87 Flow Permxsszble Leakage Valve No. Diaciram Size ~Te CCW-243-72 5135B CK 750 CCW-244-72 5135B CK 750 CCM-430 5135B 1 '0 GL 375 CCM-431 5135B 1.50 GL 375 CCR-440 513B 1.50 GL 375 CCR-441 5135B 1.50 GL 375 CCM-432 513'5B 1.50 GL 375 CCM-433 5135B 1.50 GL 375 R-156 5146B 0.375 CK 750 R-157 5146B 0.375 CK 750 NS-357 5124 0 '0 CK 750 ECR-496,-497 5141C 0.50 GL 750 ECR-416 5141C 0.50 GL 375 ECR-417 5141C 0.50 GL 375 ECR-535 5141C 0.50 GL 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 Flow Permissible Leakage Valve No. Diaciram . Size ~Te ECR-536 5141C 0.50 GL 375 ECR-36 5141F DA 375 PCR-40 5120B GA 375 PA-342 5120B CK 750 NS-283 5141D 0.50 CK 750 NPX-151 5128A 0.50 GL 375 WCR-900, -902 5114A- DA 1800 WCR-901,-903 5114A DA 1800 WCR-912,-914 5114A DA 1800 WCR-913,-915 5114A DA 1800 WCR-904,-906 5114A DA 1800 WCR-905,-907 5114A DA 1800 WCR-908,-910 '114A DA 1800 WCR-909,-911 5114A DA 1800 VCR-101,-201 5147A 14 BF 4200 VCR-102,-202 5147A. 14 BF 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 Flow Permissible Leakage Valve No. Diaciram Size VCR-103,-203 5147A 24 BF 7200 VCR-104,-204 5147A 30 BF 9000 VCR-105,-205 5147A 30 BF 9000 VCR-106,-206 5147A 24 BF 7200 VCR-107,-207 5147A 14 BF 4200 ICM-305 5143 18 GA(DD)

2700 ICM-306 5143 18 GA(DD)

2700 CCM 452 g 454 I 458 5135 8,4,8 BF, GL, BF 3000 CCM 45 1 I 453 I 459 5135 8,4,8 BF,GL,BF 3000

Double Discs 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.

Flow Permissible Leakage Valve No. Diaciram Size ~Te CTS-131W 5144 CK 3 '3 CTS-131E 5144 CK 3.00 CTS-127W 5144 CK 22.55 CTS-127E 5144 CK 21.21 RH-141 5144 CK 20.70 RH-142 5144 CK 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.

Flow Permissible Leakage Valve No. ~Dia ram Size ~Te

'CS-299E 5129 CK 2 '

CS-299W 5129 CK 2.0 SI-152-N 5143 CK 5.0 SI-152-S 5143 CK 5.0 ICM-129 5143 14 GA(DD)* ~

~ 10.0 SI-161-Ll,-L4 5143 CK 10.0 SI-161-L2,-L3 5143 CK 10 '

SI-170-L1 5143 10 CK 5' SI-170-L2 5143 10 CK 1.0 SI-170-L3 5143 10 CK 1.0 SI-170-L4 5143 10 CK 5.0 SI-158-L1,-L4 5143 CK 10 '

Double Discs 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 Flow Permissible Leakage Valve No. ~Dia ram Size SI-158-L2,-L3 5143 CK 10.0 SI-151-E 5143 CK 5.0 SI-151-N 5143 CK 5.0 SI-166-L1 5143 10 CK 5.0 SI-166-L2 5143 10 CK 5.0 SI-166-L3 5143 10 CK 5.0 SI-166-L4 5143 10 CK 5~0 RH-133,-134 5143 , 8 CK 1.0 Page 70 of 70

= DONALD C. CCK NUCLEAR PLANT SECOND TEN YEAR INTERVAL 0 RUiH DATE AHD TINE: 14SEP87:13:28 VALVE SRC1ARY SHEET - UihIT 2 SYSTEN=NAHE:= EHERGEHCY=DIESEI GENERATOR="CD"-- -=-FLOH-DIAGRAN:---2-51510-27 VALVE =-----

I I

VALVE-POSITION I I

= -ASNE-SECTION XI----.

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= -- : =-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 0--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 P NO EF-7 EF-7 P NO

-- ET-010 --

NOTE 3 P --YES> NOTE 3--

2-XRV-226 0 GL 3 A B/4 C 0 3 A B EF1 EF-1 P YESp NOTE 3 ET-010 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

~ RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SU6)QSRY SHEET - UNIT 2 SYSTEMIZE: EME RGENCY 'DIESEL GENERATOR '!CD" FLOH DIAGRAM: .2=5151D "27 VALVE - -- = I VALVE POSITION I ASME SECTION XZ --

I I 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 0 3 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 RUN DATE ANO TINE: )4SEP87:)3:28 SYSTEH-NAHE: EHERGENCY=DIESEl GENERATOR= = SECOND TEN YEAR INTERVAL VALVE SUHiNRY SHEET - UNIT 2

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

VALVE= I-VALVE=POSITION-I-I I ASHE SECTION-XZ----

MISER REV TYPE SIZE ACT F.D. I POWER

TYPE-COORDI-OPER-=

SAFETY ICD A/P

=FUNCT-=-ICL -

CAT PRIH TEST

--REQUIRED - -- TEST

-PERFORHED TEST HODE-.

RELIEF RWJEST(S) 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 RUN DATE AND TINE: 14SEP87)13:28 SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET - UNIT 2 SYSTEN-NANE:-=-ENERGEHCY-.DIESEI GENERATOR ----- -FLON DIAGRAtt:=- 2-51518"27 =

VALVE --=-=- =

I -VALVE POSITION- I ASNE-SECTION XI I I HUYd)ER REV TYPE SIZE ACT F.D. I POHER TYPE COORD I-OPER SAFETY ICD A/P FUNCT ICL .

CAT PRItt TEST REQUIRFD TEST PERFORMED TEST NODE RELIEF REQUEST(S) 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 0 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"1 P HO EF-7 EF-7 P NO ET-010 NOTE 3- P - YES>-NOTE 3--

2-XRV"221 0 GL 3 A B/0 C 0 3 A B EF-1 EF-1 P NO ET-010 HOTE .3 P . YES> NOTE 3.

B/0 EF-1 EF-1 2-XRV-222 0 GL A C 0 3 A

--= --ET=010--=

B

= NOTE 3 =-

P

=P NO YES> HOTE 3

DONALD C. COOK NUCLEAR PLANT

~ RUN DATE AND TlttE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUYttARY S)IEET - UiNIT 2 SYSTEN=NAME t EHERGENCY- DIESEL-GENERATOR - --=-FLOl$ -DIAGRAN: 51518-27=

--VALVE- I I

VALVE- POSITION-I I

= =- - ---.-- -- - - - -ASIDE-SECTION XI---

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 SA C/4 C 0 A C CF1 CF-1 P NO> NOTE 1 2-DG-130A 0 CK 1 SA C/4 C 0 A C CF-1 CF-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

DONALD C COOK NUCLEAR PLANT e RUH DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SU%>ARY SHEET - UNIT 2 SYSTEN-NANE: ENERGEHCY- DIESEL-.GENERATOR=- - FLOH-DIAGRAN: 2-5151A-26

-VALVE -- -

= =- -==-I .VALVE POSITION-I I

I

=-=--- --.. --.= . =ASNE SECTION XI-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 1.5 B/9 0 3 CF-1 CF-) NOp NOTE 1 0 CK SA C A C 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 RUN DATE AND TZttE: 14SEP87:13:28 SECOND TEtf YEAR INTERVAL VALVE SUGARY SHEET - UNi IT 2 SYSTEH-NAHE:=CONTROL=ROOM-VENTILATION =--- - =

=-FLOH =DIAGRAN: 2-5149-23 =-

VALVE = -- I I

VALVE- POSITION- 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)

-TYPECOORD 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= =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 t1 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"1 P HOp NOTE 1 EF-7 EF-7 P NO> NOTE 1 ET-NA NOTE 1 YES> NOTE 1 2-VRV-325 0 3H 2.5 A G/5 0 0 A B EF1 EF"1 P NO> HOTE 1

. EF-7 EF"7 P NO> HOTE 1 ET-NA -- NOTE 1 . YES>-NOTE 1

~

DONALD C. COOK NUCLEAR PLANT RUH DATE AND TZt<E 14SEP87: 13: 28 SECOND TEH YEAR INTERVAL SYSTEN-NAtfEt CONTAZHNEHT-.VENTILATION--- - VALVE SUt0tARY SHEET UNIT 2

-- =-FLOH-DZAGRAtt: 2-5147A-35--

VALVE =

=- = = ==- I VALVEPOSITION=I = = == == =- -- ASHE SECTION XI I I NEWER REV TYPE SIZE ACT F.D. I PONER

-TYPE-COORDI OPER FUttCT-ICL SAFETY ICD A/P CAT PRIH TEST REQUIRED -

TEST TEST PERFORHED- ==ttODE-RELIEF REQUEST(S)

=-

2-VCR-203 0 BF 24 A J/5 C C 2 P A EF-1 EF-) NO EF-5 EF-5 HO EF-7 EF-7 P HO

.ET-005 = ET-005 P NO-SLT-1 SLT-2 R YES> NOTE 1 2-VCR-204 -0=BF=-==30 =-- =A -- J/6

- = -C 2 --P = A EF EF"5 EF-7 EF-1 EF-5 EF-7 P

P HO HO HO ET-005 ET"005 P HO SLT-1 SLT-2 R YES, NaTE 1 2-VCR-205 0 BF 30 A J/3 C C 2 P A EF-1 EF-1 P HO

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

0 DONALD C. COOK NUCLEAR PLANT RUH DATE AHD TINE: 14SEP87:13:28 SECOND TEN YEAR ZNTERVAL SYSTEtt-NAttE:=-COWTADNENT-VENTILATION- VALVE SUiiARY SHEET

=-= FLS'I

- UNIT 2 DIAGRAN:2-5147A-35

=-VALVE =-

- = ==I=VALVE-POSITION -I = --ASME SECTION XZ--

I I HUYBER REV TYPE SIZE ACT F.D. I POWER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF RECQEST(S)

TYPE COORD l=-OPER FUHCT - I CL- RE@GRED PERFORHED tfODE 2-VCR-105 0 BF 30 A J/3 C C 2 P A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 .ET-005 P tiO SLT-1 SLT-2 R YESp ROTE 1 2-VCR-106 0-==BF-= 24 -- =-A J/3- -- C--

=- C-- ==-= 2-- P A--- EF-I, EF-1 I')O-EF-5 EF-5 NO EF-7 EF-7 P tiO ET-005 ET-005 P HO SLT-1 SLT-2 R YES> NOTE 1 2-VCR"107 0 BF 14 A J/4 0/C C 2 A A EF-1 EF-1 HO EF-5-- EF-5 -HO EF-7 EF-7 P HO ET-005 ET-005 P N)

SLT-1 SLT-2 R YES> NOTE 1 2-VCR-201 0 BF 14 A J/8 C 2 P A EF-1 EF-1 HO EF"5 EF-5 HO

.EF-7 --- EF-7 P NO ET-005 ET-005 P t$ 0 SLT-1 SLT-2 R YES> NOTE 1 2-VCR-202 0 BF 14 A J/9 C C 2 P A EF-1 EF-1 HO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 =- = ET-005 P =-- -HO-SLT-1 SLT-2 R YESp NOTE 1

DOttALD C. COO<AD NUCLEAR PLANT RUH DATE AHD TIHE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL SYSTEM NAME' COHTAINtENT VENTILATIOH = =

VALVE

SUMMARY

SflEET

.FLOH..DIAGRAM:

UNIT 2 2=514?A-35 VALVE -.. -=-==- I I

-.VALVE-POSITION I I

-ASME SECTION. XI -

NUt'GER 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 . 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-1 HO EF"5 EF-5 NO EF"7 EF-7 P NO

-ET-005 - ET-005- P=- -NO SLT-1 SLT 2 R YES> HOTE 1 2=VCR".102==0=BF=== ==-A - J/9 C C . 2 P . A EF-1 EF-1 = HO EF-5 EF-5 NO EF-7 EF-7 P NO ET-005 ET-005 P NO

- SLT-1 SLT =- R .YES'.HOTE 1 - --

2-VCR-103 0 BF 24 A J/5 C 2 P A EF-1 EF-1 P NO

-EF-5--= = EF"-5 HO EF-7 EF-7 P NO ET-005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 1 2-VCR-104 0 BF 30 A J/6 C C 2 P A EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P HO ET-004 ET-004 P HO SLT-1 SLT-2 R YES> HOTE 1

DONALD C. COOK HUCLEAR PLANT RUH DATE AHD TIMiE: 14SEP87:13:28 SECOND TEtt YEAR INTERVAL VALVE SUiiu ARY SHEET - LAIT 2 SYSTEM-NAttE:ICE-CONDENSER REFRIGERATIOH =, . = FLON DIAGRAM:. 2=5146B=23

-VALVE== = = -- I =VALVE-POSITION I ASitE SECTION. XI.

I I HUMBER REV TYPE SIZE ACT F. D I POttER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI OPER FUNCT ICL. REQUIRED PERFORMED . NODE .

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

- EF-5 EF-5 NO EF-7 EF-7 P NO ET-005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 2 2-VCR-21 0 DA 4 A L/7 0 2 A A EF-1 EF"1 P NO EF-5 EF-5 HO EF"7- EF=7 P NO ET-006 ET-006 P NO SLT-1 SLT-2 R YES> NOTE 2

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEPB7:15:28 SECOND TEN YEAR INTERVAL VALVE SUN1ARY SHEET - UNIT 2 SYSTEM-NAME:CPN/MELD..CHANNEL PRESSURIZATION.= -= FLIC DIAGRAM:= 2-5145"20. =- =- = =

-VALVE---= =-==- ----I-VALVEPOSITION I- ASME SECTION- XI I I 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 RUH DATE AND TIME: 14SEP87:13:28 SECOM) TEtt YEAR INTERVAL VALVE SCD)ARY SHEET - UtlZT 2 SYSTEM-NAME:.CONTAINtlENT--SPRAY, = FLOH DIAGRAM: 2-5144-29 VALVE=------ =.-= I VALVE POSZTZ(N-I-- ASME SECTION XZ I I 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-1 P HO EF-5 EF"5 NO ET-066 ET-066 P NO 2-ZtlO-222 0 GA 2 MO L/9 0 0/C 2 A B EF-1 EF-1 P NO EF-5 EF-5 NO ET-030 -- ET-030 P --HO 2-ZMO-225 0 GA 12 MO J/9 0 0/C 2 A B EF-1 EF-1 P NO EF=5 - EF"5 NO ET-074 ET-074 P NO 2=RH"..141 ==0 CK -.8 . SA E/3 - C. 0 = 2 A AC . CF-1 CF-2 R YES>-NOTE 2. --.-

SLT-1 SLT-2A R 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

R YESi NOTE 2 YESp HOTE 3 2=SV=107 0 = REL= 1 =SA -=-H/5 C -- 0: == 2 -A - C-- . -TF"1- --=- =-=TF=l = R - NO

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SE P87: 13: 28 SECOND TEN YEAR INTERVAL VALVE SL?AAARY SttEET - UNIT 2 SYSTEH NAttE: CONTAIHtL~tfT=SPRAY FLO'A DIAGRAtt: 2=5144-29 ..

VALVF I VALVE POSITION I ASttE SECTION XI I I 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-1 NO EF-5 EF-5 HO ET-018 ET-018 HO 2-IttO-204 0 GA 2.5 ttO H/7 C 0 2 A B EF-1 EF-1 P HO EF-5 EF-5 HO ET-018 ET-018 P HO 2-Zt jO-210 0 GA 10 N80 J/8 C 0 2 A B EF-1 EF-1 P HO EF-5 EF-5 tiO ET-066 ET-066 = P NO 2-It'.0-211 0 GA 10 NO J/8 C 0 2 A B E F-1 EF-1 P HO EF-5.. EF-5: HO =

ET-065 ET-065 P HO

~50=212 0 GA. 2- .--HO-- H/8- -0 0/0=- 2=A 5 2?=1 EF>>l . P NO EF-5 EF-5 HO ET-033 ET-033 P HO 2-ZttO-215 0 GA 12 NO G/9 0 0/C 2 A B EF-1 EF-1 NO EF-5 EF-5 NO ET-074 ET-074 HO 2-INO-220 0 GA 10 HO L/8 C 0 2 A B EF1 EF-1 NO EF-5 EF-5 HO ET=065 . ET-065 NO 08

0 DONALD C. COOK NUCLEAR PLANT RW DATE AND TIME: 14SEP87:13:28 SECOND TEth YEAR INTERVAL VALVE SEC)ARY SHEET - UNIT 2 SYSTEM-NAME: CONTAINMENT-SPRAY FLON= DIAGRAM: 2-5144"29 VALVE= I -VALVE-POSZTZON- I --- =ASME SECTIOLN XZ I I 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 CF-2 R YES> NOTE 2 SLT-1 SLT-2A R YES> ttOTE 3 2-CTS-127-N 0 CK 6 SA E/4 . C 0 2 A AC CF-1 CF"2 R YES> NOTE 2 SLT =- SLT-2A. --R YES> NOTE 3 2-CTS-131-E 0 CK 8 SA E/2 C 0 2 A AC CF1 CF-2 R YES> NOTE 2 SLT=1 SLT-2A 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 RUiH DATE AHD TZHE: 14SEP87:13:28

.0 SECOND TEN YEAR INTERVAL VALVE SUHi1ARY SHEET - UNIT 2 SYSTEN-HAl5E: EHERGEHCY=CORE-COOLING RHR---=- =-- FLOH-DZAGRAN:- 2-5143 VALVE I-VALVE-POSITZOH-I ASME SECTION Xl I I 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 DONALD C COOK NUCLEAR PLANT SECOHD TEN YFAR INTERVAL 0 RUH DATE AND TINE: 14SEP87:13:28 VALVE SU)0)ARY SHEET - UNIT SYSTEN-HANE: ENERGENCY-CORE-COOLING RHR =----. -==FLON DIAGRAN: =--2-5143-35= 2 VALVE -I- VALVE POSITZOH -I- -ASNE SECTION-Xl I I NUiE)ER REV TYPE SIZE ACT F.D. I PINER SAFETY ICD A/P CAT PRZH TEST TEST TEST RELIE F REQUEST(S)

--- --- TYPE- COORDI OPER -- FUiiCT - ICL - --- -- REQUIRED- - - PERFORNED NODE.

2-SZ-166-L4 0 CK 10 SA C/4 C 0 1 A AC CF-1 CF"2 R YESp NOTE 5 SLT-1 SLT-1 R NO> NOTE 1 2-SI-170-Ll 2 CK 10 SA A/4 C 0 1 A AC CF-1 CF-3 R YES> HOTE 13 SLT-1 SLT-1 R N)p NOTE 1 2-SI-170-L2 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 CF-3 R YES> HOTE 13 SLT-1 SLT-1 R NO> NOTE 1 2-SI-170-L3 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 CF-3 R YES> NOTE 13 SLT-1 SLT-1 R HO> NOTE 1 2 "SI-170-L4 2 CK 10 SA A/4 C 0 1 A AC CF-1 CF-3 R YES> HOTE 13 SLT-1 SLT-1 R NOp NOTE 1 2-SI-171 2-Sj-172 2-SI-194 0

0 0

GL GL GL 0 '5 0..75 0.75 N

N H/6 ii H/6 G/6 C

C. C C 2 2

2 P

P =-

A A- -

SLT-1 SLT SLT-1 SLT-2 SLT-2 SLT-2 R

R YES, HOTE 1 YES NOTE 1 C C P A 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 RUH DATE AND TIME: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE

SUMMARY

SHEET UNIT 2 SYSTEtt NAt1E: EMERGENCY=CORE COOLItlG - RtlR= .. FLOH DIAGRAM: 2-5143-35 VALVE -=- -- - --- - I- VALVF-POSITION -I I I

--=- -- . --- - -- ASME SECTION XZ--

NRRER REV TYPE SIZE ACT F.D. I POttER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

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

~ DONALD C. COOK NUCLEAR PLANT RUiH DATE AHD TIME: lOSEP87:13:28 SECOND TEN YEAR INTERVAL VALVE Sinai HARY SHEET - UiHIT 2 SYSTEM-HAME' EMERGENCY CORE-COOLING.= RHR = ..= ,FLOH DZAGPJtH: =-2-.5103=35=

VALVE= = I -VALVE-POSITION- I-I I ASME-SECTION .XZ HU953ER REV TYPE SIZE ACT F ~ D I PS'(ER

- -=TYPE COORDI.OPER- =--

SAFETY I CD A/P CAT PRIM TEST FUHCT==ICL-=-=- ..--.REQUIRED - =

TEST PERFORMED TEST MODE--

RELIEF REQUEST(S) 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 .C . YES NOTE 8 SLT-1 SLT-1 R HOp NOTE 1 2-RH-134= = = -0=-CK- 8=-=- SA -- C/5 C . .C------- 1 P- AC- -CF-I =-- CF-2 C YESp-NOTE 8 SLT-1 SLT-1 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 C YESp NOTE 10

- . = SLT-1. . SLT-1 R- = -HOp. NOTE 1 2-SI-151-W 0 CK 8 SA D/7 C 0 2 A AC CF1 CF-2 C YESp NOTE 10 SLT-1 = SLT-1 R - HOp NOTE 1 2"SZ-152-N 0 CK SA 0/8 C 0 2 A AC CF-1 SLT-L =

CF-2 SLT-1 ==

R YESp NOTE R =-=--NOp NOTE 1-ll 2"SI-152-S 0 CK SA 0/7 C 0 2 A AC CF-1 SLT.-1 CF-2 SLT-1 R

. R. =

YESp NOTE HOp NOTE 1 ll 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 R -- -HOp NOTE--1 .

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

0

~ ~

DONALD C. COOK HUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUt0tARY SHEET " UtGT 2 SYSTEM-NAME-' EMERGENCY-CORE-COOLING= RHR==== FLOH-DIAGRAM: -2"5143-.35 -== - -.

VALVE= -t-VALVE-POSITION-I- ASME SECTION.XI I I 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-2 C YESF HOTE 4 EF-5 EF-5 NO ET-028 ET-028 C HO 2"ZMO-326 0 GA 8 MO C/7 0 0/C 2 A B EF1 EF-2 C YES> NOTE 4 EF-5 EF-5 NO ET-028-=- =- ET-028 C NO 2-Z MAO "330 0 GA 8 MO G/4 C 0 A B EF1 EF-1 P NO EF"5 EF.-5 NO ET-053 ET-053 P HO 5=150-551 . 0 GA .5 . MO 1/5 C .. 0- E.. A- 5 EF-1-.

EF-5 EF-1 EF-5

.P -NO 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-1 P NO EF"5 EF-5 HO ET-015 ET-015 P HO 2-IMO-350 0 GA 8 MO L/5 C 0 B EF-1 EF-1 P HO EF-5 EF-5 HO ET-015 ET=015 .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 SYSTEN-NA)K'EMERGENCY=CORE COOLING VALVE--=-- -

RHR

--I VALVE SU@DRY SHEET VALVE- POSITION-I =

~

DONALD C. COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL FLOH DIAGRAM: 2"5143"35 UNIT 2

= -= . ASME SECTION RUN DATE AND XZ TIME: 14SEP87:13:28 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-1 P NO EF-5 EF-5 HO ET-012 ET-012 P NO 2-ZMO-314 0 GA 8 MO K/6 0 0/C 2 A B EF"1 EF-1 P NO EF-5 EF-5 NO

- ET-034 ET"034 = P==-- HOp HOTE-3 2-ZMO-315 0 GA 8 MO C/7 C C/0 1 A B EF-1 EF-2 C YES'OTE 4

EF=5. EF=5 HO ET-033 ET-033 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 fF-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-1 HO EF-5 EF-5 NO ET-128 ET-128 HOp NOTE 3 2-ZMO-322 0 GL 2 MO M/5 0 0/C 2 A B EF-1 EF"1 P HO EF-5 ET-011 .. EF"5 ET-Oll P NO HO 2-ZMO-324 0 GA 8 MO M/6 0 0/C 2 A B EF1 EF-1 P NO EF-5 = EF-5 HO

ET-035 ET-035 P HOp NOTE 3

0 DONALD C. COOK HUCLEAR PLANT RUH DATE AND TIMiE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SU)C)ARY SHEET - UNIT 2 SYSTEMIZE EMERGENCY CORE COOLING= RHR = = = =FLON DIAGRAlk: ~143."35 VALVE = . I. VALVE. POSITION I ASME SECTION XI I I HUtiBER 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-GCR-314 0 GL 1 A G/2 0 2 A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ET=003 ET-003 P HO SLT-1 SLT-2 R YES> ti'OTE 1 LCM=129 2 GA 14= MO E/8 1==P -A = EF EF-2= = YES> NOTE 2 EF-5 EF"5 HO ET-121 ET"121 HO SLT-1 SLT"1 R HOp NOTE 1 2-ICM-305 0 GA 18 MO D/9 C 0 2 A A EF-1 EF-1 P NO EF-5 EF-5 tR ET=049. . = ET-049 P HO SLT-) SLT-2 R YES> NOTE

~CM=306- O=GA =-18.

. MO. =D/9 C ===0 2 A A EF=l EF-1 P HO EF-5 EF-5 NO ET-049 ET-049 P HO SLT-1 SLT-2 R YES'OTE 1 2-IMiO-128 2 GA 14 MO B/8 C 1 P B EF-1 EF"2 YES> NOTE 2 EF"5 EF-5 HO ET=134 ET"134 HO 2-IMO-310 0 GA 14 MO M/9 0 0/C 2 A B EF-1 EF=5 ET-148

.. fF-1 EF=5 ET-148 P

P NO HO ttO~ NOTE 3

0 ..0 DONALD C. COOK NUCLEAR PLANT SECOHD TEH YEAR INTERVAL RUN DATE AHD TIME: 14SEP87:13:28 VALVE SVYd&RY SHEET - UNIT 2 SYSTEM-NAME: EMERGENCYCORE-COOLIHG= SZS =. == FLON DIAGRAM: 2=5142-28 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 RUiN DATE AND TZHiE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SV>SORY SHEET - UNIT 2 SYSTEN-NAHE:=EHERGENCY-CORE COOLING- = SZS = FLON DZAGSN:= 2-5142=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 NO EF-5 EF-5 NO EF-7 EF-7 P NO ET=.005- . ET-005 P NO 2-IRV-255 0 GL 1 A H/6 0 2 A B EF1 EF-1 P NO

-- -EF-5 --=- =- EF- W-EF-7 EF-7 P NO ET-004 ET"004 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 .- = 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 RUH DATE AHD TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL SYSTEM=NAME =-EMERGENCY-CORE=-COOLING -SIS--=-=- VALVE SUY!CRY SHEET " UiHIT 2 FLOH-DIAGRAM:=-2-5142-28----

VALVE=== ==- -- I=VALVE POSITXON I-I I AStiE- SECTION- XZ NUiiBER REV TYPE SIZE ACT F.D. SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

-TYPE-COORD I POWDER 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-2 YES> NOTE 4 EF-5 Ef-5 NO ET-012 ET-012 NO 2-ZMiO-263 0 GL 2 MO L/8 0 0/C 2 A B EF-1 EF-2 C YESp NOTE 4 EF-5 EF-5 NO

= ET-012 ET-012- C -NO 2-ZMiO-270 0 GA 4 MO E/9 0 0/C 2 A B EF"1 EF-1 EF"5 ET-024 EF-5 ET-024

= .. P NO

=- HO P HO 2=Z)0=275 =0 -- .

GA 4.- - MiO E/8 0 =-0/C --- 2- A -- B- -= EF --

EF-5 Ef-1 EF-5 NO HO ET-020 ET-020 NO 2-ZMO-361 0 GA 4 MO G/9 C C/0 2 A EF-1 EF-1 EF-5 EF-5 ET"009 ET-009 2-ZMO-362 0 GA 4 N) G/9 C C/0 2 A B EF-1 EF-) NO EF-5 EF-5 NO

.- -- ET-009 ET-009. = NO 2-IRV-251 0 GL 1 A H/5 0 2 A EF-1 EF-1 EF =-- -EF-5-- --P EF-7 EF-7 P ET-004 ET-004 P

DONALD C. COOK NUCLEAR PLANT RUN DATE AHD TIME: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE StRQARY SHEET UNIT 2 SYSTEM-NAME:=EMERGEHCY-CORE--COOLING=-SZS-- -

FLON-DZAGRAM: 2-5142-28 =.

VALVE I- -VALVEPOSITION- I-= -- --- -= -= - A%1E SECTION XZ-I I HOSER REV TYPE SIZE ACT F AD. I PONER TYPE- COORDI-OPER ----FUui:T --ICL SAFETY ICD A/P CAT PRIM TEST

-- -REQUIRED.

TEST PERFORMED..

TEST MODE RELIEF REQUEST(S) 2-ICM-250 0 GA H/2 C 0/C 2 A A EF-1 EF-2 C YESp NOTE EF-5 EF-5 NO ET-012 ET-012 C NO SLT-1 =. SLT-2 R -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 ---==-

= . =-=-=-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-1 P HO EF-5 EF-5 NO ET-012 ET-012 P HO SLT-l... .SLT-2 R- -YES> NOTE 2 2-ICM"265 0 GA MO C/8 0 0/C 2 A A EF-1 EF-1 P NO

-EF=5 -- E F- =- -=--- HO=

ET-012 ET-012 P NO SLT"1 SLT"2 R YES> NOTE 2 2-IMO-255 0 GA MO J/7 C 0 2 A 8 EF-1 EF-1 P NO EF-5 EF-5 HO ET-015 ET-015 P HO 2-IMO"256 0 GA 4 MO J/6 C 0 2 A B EF-1 EF-1 P HO EF-5 ET-012 =- EF"5 ET-012 ---==-=P HO

=-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 RUiil DATE AND TIHiE: 14SEP87:1'5:28 SECOND TEN YEAR INTERVAL VALVE SUt%JARY SHEET - UtlIT 2 SYSTEH-NAHE:

PAS-CONTAItCiEttT-.HYDROGEN--=== -- -= FLON DIAGRAH: 5141D VALVE-=- = -- I-VALVE-POSITION-I

- .. -- -- ASt4E-SECTION XI I I SIZE ACT F.D ~ I PONER SAFETY I CD A/P CAT PRItl TEST NJJEJER REV TYPE

-TYPECOORDI=OPER -- FUNCT- ICL -- -- --- REQUIRED=

TEST

-PERFORHED TEST RELIE F REQUEST(S)

HODE 2-ttS-283 2 CK 0.5 SA C/8 C 0/C 2 A AC CF-1 CF-2 R YES> NOTE 2 SLT-1 SLT-2 R YES> NOTE 1

DONALD C. COOK NUCLEAR PLANT RUH DATE AND TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUm)ARY SHEET UNIT 2 SYSTEN-NAHE: PAS-CONTAI)RENT=HYDROGEN.-=-----FLON-DIAGRAH:2 "5141D-8

-VALVE I =-VALVE-POSITION- I -- - ASNE- SECTIOH XX--

I I NU)SER REV TYPE SIZE ACT F ~ D I PONER SAFETY I CD A/P TYPE-COORDI-OPER--- FUHCT --ICL-CAT PRIH TEST

-:=---- REQUIRED -

TEST

--PERFORNED .

TEST

-NODE RELIEF REQUESTERS) 2-ECR-25 0 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P HO

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

=- ----.-- EF-1 EF-5

-P =- HO NO EF-7 EF-7 P HO ETF-002 ETF-002 SLT-1 ==- =-= - SLT-2 -

P HO R -- = YES> NOTE 1--

2"ECR"27 0 GL 0.5 A B/3 C 0/C 2 A EF-1 EF"1 P HO EF EF-5 NO EF-7 EF-7 P HO ETF-002 ETF-002 P HO SLT-1 SLT-2 R YES> NOTE 1 2-ECR-28 0 GL 0.5 A B/4 C 0/C 2 A EF-1 EF-1 P HO EF-5 EF-5 Na

=EF-7 -- EF-7-- - -- --- P WO ETF-002 ETF-002 P NO SLT-1. SLT-2 R 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 RUN DATE AND TINE: 14SEP87:13:28 SYSTEH-HA)fE:=-PAS -CONTAZtRENT HYDROGEN = = =

SECOiND TEH YEAR INTERVAL VALVE SU2 fARY SHEET - U22)IT 2 FLOH DIAGRA)f: 2221410-8 . =

VALVE=- = == I-VALVE-POSITION I- ASNE -SECTIOH XI-I I 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-1 P NO EF-5 EF-5 N)

EF-7 EF-7 P NO ETF= 002 ETF-002 P= tiO SLT-1 SLT-2 R YESB NOTE 1 2-000-21 0 Gl -0.0- .2-. -0/2 -C- .. .0/0- .A =-A EF-1 EF-5 EF-1 EF"5 P-- W-HO EF-7 EF-7 P NO ETF-002 ETF-002 P NO SI.T-1 SLT-2 R YES> NOTE 1 2-ECR-22 0 GL 0.5 A B/2 C 0/C 2 A EF-1 EF-1 NO

. EF-5 EF NO EF-7 EF-7 P NO ETF-002 ETF-002 P NO SLT-1 SLT-2 R YES> NOTE 1 2-ECR-23 0 GL 0.5 A B/1 C 0/C 2 A EF-1 EF"1 HO EF-5 EF-5 NO

= EF EF P NO ETF-002 ETF"002 P I)

SLT-1 SLT-2 R YESB NOTE 1 2-ECR-24 0 GL 0.5 A B/3 C 0/C 2 A EF-1 EF"1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO ETF-002 ETF-002 P NO-SLT-1 SLT-2 R YESB NOTE 1

0 0 DOHALD C. COOiti NUCLEAR PLANT 0 RUH DATE AND TINE: 14SEP87:13:28 SECOHD TEH YEAR INTERVAL SYSTEH-NAHE: PAS-CONTAICKNT=HYDROGEN--.- ==- FLOH-DZAGRAH: ..2=5141D-.8 VALVE SURSLRY SHEET UHIT 2 VALVE I -=VALVE- POSITION-I AS!%- SECTION-XL I l HOSER REV TYPE SIZE ACT F.D I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI-OPER FUHCT--

ICL - -- - =-- REQUIRED - . - PERFORHED-- NODE.

2"ECR-15 0 GL 0.5 A A/1 C 0/C 2 A A EF"1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ETF.=002 = .ETF.-002 P HO SLT-1 SLT-2 R YES> HOTE 1 2-ECR-16 -0 GL- =0.5 =--- - A - - - A/3 == C-- 0/C--- - -A--- A.--- -EF-1

--- EF-1 P-- --.-VQ EF-5 EF-5 HO EF-7 EF"7 P HO ETF-002 ETF-002 P HO SLT-1 . NLT=2- ..-=-.-- R =- ..YESp NOTE.3-=

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

e' D(NALD CD SECOND TEN YEAR 0=

COOK NUCLEAR PLANE IttTERVAL ~

RWi DATE AND TIHiE: 14SEP87:13:28 VALVE SvtuQRY SHEET - UiiIT 2 SYSTEtl-NAttE:PAS-COttTAIt"tENT-HYDROGEN-=- ==-= FLON DIAGRAttt-- 2-51410-8

--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-1 HO EF-5 EF"5 HO EF-7 EF-7 P HO ETF-002 ETF-002 P HO SLT-1 SLT-2 YESp NOTE 1 R

2-ECR-ll .-0 GL=0.5 -A--==A/2=-C -0/C -- = 2-- A =-A-===-EF-1----- -

EF-5 EF-7

--EF-1 EF-5 EF-7 P

-HO-NO NO P

ETF-002 ETF-002 P HO SLT-1 = ---. SLT R- = YES'OTE 2-ECR-12 0 GL 0.5 A A/2 C 0/C 2 A A EF1 EF-1 P HO

-- EF-5 EF-5 - HO---

EF-7 EF-7 P HO ETF-002 ETF"002 P HO SLT-1 SLT-2 R YES'OTE 1 2-ECR-13 0 GL 0.5 A A/1 C 0/C 2 A A EF-1 EF-1 tiO EF-5 EF-5 HO

-EF-7--- EF P HO ETF-002 ETF-002 P HO SLT-1 SI.T-2 R YESp NOTE 1 2-ECR-14 0 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF-1 NO EF-5 EF-5 NO EF-7 EF-7 P NO

.ETF-002 - ETF-002 -P- NO SLT-1 SLT-2 R YESp NOTE 1

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

-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"1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO ETF-002- ETF-002 --P NO 2-HCR-254 0 GL 0.5 A B/1 0 2 A B EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO ETF-002 ETF-002 P NO

DONALD C. COOK NUCLEAR PLANT RUiH DATE AND TItlE: 14SE F87:13: 28 SECOND TEH YEAR INTERVAL VALVE SSDtARY SHEET - UNIT 2 SYSTEH-NAHE:NUCLEAR-SAttPLItiG FLOH = DZAGRAtt: . 2-5141A-30

.-VALVE ----- = - I- VALVF -POSITION-I ASHE- SECTION XZ I I hÃltSER REV TYPE SIZE ACT F.D. I POHER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE COORDI-OPER -- RPitCT- ICL REQUZRED PERFORHED HODE 2-DCR-301 0 GL 0.5 A 8/2 0 C 2 A 8 EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P HO ET-003 ET-003. P -NO 2-DCR-302 0 GL 0.5 A 8/3 0 C 2 A 8 EF"1 EF-1 P HO EF-5---- EF-5 --- -= -t'O-=

EF-7 EF-7 P NO ETF-002 ETF-002 P NO 2-DCR"303 0 GL 0.5 A 8/3 0 A 8 EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO ETF-002- ETF--002 P - -=HO=-

2-DCR"304 0 GL 0.5 A 8/3 0 C A 8 EF"1 EF-1 P NO

=-EF-5 EF-5-- NO EF-7 EF-7 P NO ETF-002 ETF-002 P HO 2-MCR-251 0 GL 0.5 A 8/2 0 2 A 8 EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ETF-002 ETF-002 P NO 2-ttCR-252 0 GL 0.5 A 8/2 0 C 2 A 8 EF"1 EF-1 P NO EF-5 -=-EF HO-.

EF-7 EF-7 P HO ETF-002 ETF-002 P NO

DONALD C. COOK HUCLEAR PLANT RUiN DATE AHD TINE: 14SEP87t13: 28 SECOND TEtt YEAR IttfERVAL VALVE S4tt&RY SHEET - UNIT 2 SYSTEtl-NAttE:NUCLEAR-SANPLING C

FLON-.DIAGRAtt:2-5141 -- --

VALVE I I

VALVEPOSITION 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"1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO ETF=002- .- ETF-002 ... P - -NO SLT-1 SLT-2 YES'OTE R 1 2-NCR-109 0 Gl 0.5 A D/5--0 C 2---A-- A==- EF-1--

EF-5

=-=-- EF EF-5

--= P -HO NO

-=

EF-7 EF-7 P HO ETF-002 ETF-002 P NO SLT"1

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

0 DONALD C. COOK HUCLEAR PLANT RUH DATE AHD TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUMttARY SHEET UNIT 2 SYSTEM-NAME:=NUCLEAR-SAMPLIHG=- - .---- . -- -=- FLON DIAGRAM: =2"5141-27= .--

VALVE I--VALVE-POSITION ASME -SECTION-XZ I I HKtDER REV TYPE SIZE ACT

TYPE F.D. I POHER SAFETY )CD A/P COORDI- OPER --- FLNCT-- ICL---

CAT

=

PRIM TEST

REQUIRED TEST PERFORMED

TEST MODE RELIEF REQUEST(S) 2-ICR-5 0 GL 0.5 A C/5 0 C 2 A A EF-1 EF-1 P HO EF-5 EF-5 NO EF-7 EF"7 P HO

- ETF-002 ETF-002 P NO 2-ZCR-6 =0 Gl 0.5---- A - D/5-= 0 -- C-SLT-1 2- A--=A=-EF -"

EF-5 EF-7 SLT-2 EF EF-5 EF-7 R

P P

=

YES'OTE HO NO NO 1

ETF-002 ETF-002 HO SLT-1 =- SLT-2

R- --- YES'OTE 1 2-HCR-105 0 GL 0. 5 A C/7 0 C 2 A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ETF-002 ETF-002 P HO SLT-1 SLT-2 R YES> NOTE 1 2-HCR"106 0 GL 0.5 A C/7 0 EF-1 EF"1 HO EF-5 EF-5 NO EF-7 -EF-7= -=- =-- P- .HO.

ETF>>002 ETF-002 P HO SLT-1 SLT-2 R YES> HOTE 1 2-HCR-107 0 GL 0.5 A D/6 0 C 2 A A EF-1 EF-1 NO EF-5 EF-5 HO EF-7 EF-7 P HO ETF-002 ETF-002 -P HO SLT-1 SLT-2 R YESp HOTE 1

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TlttE: 14SEP87: 13: 28 SECOND TEN YEAR IHTERVAL VALVE SUtCtARY SHEET - UNIT 2 SYSTEtt=NANE: CONPONENT-COOLIHG FLON-DIAGRAN:=-2"51358 . ==-=

VALVE ---

= - -= I VALVE- POSITION I =-

I

- - - ASttE=SECTION- XZ-I 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 CF-2 R YESp NOTE 2 SLT-1 SLT-2 R YESp NOTE 1 2-CCN-243-72 2 CK 1 SA C/5 0 2 A AC CF-1 CF-2 R YESp NOTE 2 SLT"1 SLT"2 R YESp NOTE 1 2-CCN-244-25 2 CK 1 SA C/6 0 2 A AC CF1 CF-2 R YESp ttOTE 2 SLT-1 SLT-2 R YESp NOTE 1 2-CCW-244-72 2 CK 1 SA C/6 0 C 2 A AC CF-1 CF-2 R YESp HOTE 2 SLT-1 SLT-2 R 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

DONALD C. COOK NUCLEAR PLANT RUH DATE AHD TIME: 14SEP87: 13: 28 SECOND TEN YEAR INTERVAL VALVE St&DARY SHEET - UtGT 2 SYSTEM-NAME:COMPONENT-COOLING FLOH DIAGRAM: 2-51358-14

-VALVE-= - -=----. =I -VALVE-POSITION- I I I ASME-SECTZOiN =Xl -=-

HUAABER REV TYPE SIZE ACT F.D. I POHER SAFETY !CD A/P CAT PRIM TEST TEST TEST RELIEF RE@JEST(S)

TYPE COORDI OPER =- -FACT ICL REQUIRED PERFORMED . MODE 2-CCM-430 0 GL 1.5 MO D/6 C 0/C 2 A A EF-1 EF-1 P HO EF-5 EF-5 NO ET-018 ET-018 P NO

-SLT=1 SLT-2 R YES'OTE 1 2-CCM"431 0 GL 1.5 MO D/6 C 0/C 2 A' EF-1 EF-1 P NO

= =---=-EF-5 . -= EF-5 NO ET-015 ET-015 P HO SLT-1 SLT-2 R YES> HOTE 1 2-CCM&32 0 GL 1.5 MiO D/6 C 0/C 2 A A EF-1 EF-1 P NO EF-5 EF-5 NO ET-018 ET-018 P HO SLT-1 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"1 P NO

= -EF-5 EF"5 NO ET-019 ET-019 P HO SLT-1 SLT-2 ~ R YES> NOTE 1 2-CCR-440 0 GL 1.5 A D/6 0 A EF-1 EF-1 NO EF-5 EF"5 NO EF-7 EF-7 P NO ET-008 ET-008 P HO SLT-1 SLT-2 R YESR NOTE 1 5-CCR-441 0 -1.5 51 A.. 5/6 0-- - 2--A-- A -EF-1 --

EF-5

- EF-1 EF-.S P HO NO EF-7 EF"7 P HO ET-005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 1

0 0 DONALD C. COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL RUN DATE AND TIME: 14SEP87:13:28 SYSTEM NAME'COMPONENT. COOLING VALVE SmDQRY SHEET FLOH DIAGRlL): 2"5135A"30 UHZT 2 VALVE- = = -=. I.. VALVE=POSITION I .... --ASME SECTION XZ I I NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY )CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

. TYPE COORDI OPER -FACT ICL .REQUIRED PERFORMED MODE 2-CYA)-416 0 BF 16 MO G/5 0 0/C 3 A B EF-1 EF-1 P NO EF-5 EF"5 HO ET-103 ET"103 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 P HO EF-5 EF-5 HO ET-066 ET-066 P NO 2=CM0=429 0= BF== 14 MO E/5 C 0 A B EF 1 EF-1 P NO EF-5 Ef"5 HO ET-054 ET-054 P HO 2-CRV-412 0 GL 4 A K/1 0 C A B EF"1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO

-ET-019- ET-019 -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

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIHE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE

SUMMARY

SHEET - UNIT 2 SYSTEH-NAME:COMPOiNENT-COOLING-- ==

- . =-====-= *-FLOH DIAGRAH: 2-5135A -VALVE - =I--VALVE=POSITION I

I I

ASHE -SECTION-XZ NUiSER REV TYPE SIZE ACT F.D I POHER SAFETY LCD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI OPER -=-FUNCT- ICL --. -- --REQUIRED 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 16 HO 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 P=-- HO EF-5 NO ET-053 P NOp NOTE 1 2-CHiO "412 0 BF 16 HO L/3 ' 0/C A B EF1 EF-1 NO EF-5 EF-5 NO ET-054 ET-054 NO> NOTE 1 2-CYA)-413 0 BF 18 HO L/5 0 0/C 3 A B EF-1 EF-1 P HO EF-5 EF-5 NO

---= -ET-053 -- =- - ET-053 -- = P- -- -- NO 8 HOTE 1 2 "CHO&14 0 BF 16 MO K/3 0 0/C 3 A B EF-1 EF"1 P NO EF-5 -- EF-5 NO ET-054 ET-054 P NOp NOTE 1 2=CH0=415 0 BF ~6. - HO. H/5 - 0 .. 0/C-. 3 .A B. - EF.-1..--

EF-5 EF EF-5 P HO NO ET-054 ET-054 P NO> NOTE 1

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: lOSEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SlM1ARY SHEET - UNIT 2 SYSTEH-NAt%:CC fPONENT-COOLING= = FLOH. DIAGRAH: 2-5135-30 .

--VAlVE- = -- -- --- I -VALVE- POSITION l

I--

I ASHE SECTION XI NEVER REV TYPE SI2E ACT F.D. I PONER SAFETY ICD A/P TYPE-.COORD) OPER =-. FUINCT . ICL = ..

CAT PRIH TEST REQUIRED TEST PERFORHED TEST HODE RELIEF RE(PEST(S) 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

DONi ALD C.~ COOK NUCLEAR PLAttT

~ RUN DATE AND TIME: 14SEP87:13:28 SECOitD TEtt YEAR INTERVAL VALVE SUGARY SHEET - UittIT 2 SYSTEtt-NAME .CO'tPONEttT-COOLING FLO)L DIAGRAM: 2-5135-34

-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 CF"2 R YESp NOTE 4 SLT-1 SLT-2 R YESp NOTE 2 2-CRY-445 1 BL 6 A L/5 0 C/0 3 A B EF-1 EF-1 NO EF-5 EF-5 ttO EF-7 EF-7 P NO ET-034 ET-034- P HO 2-CRV-470 0 GL 6 A G/1 0 3 A B EF1 EF-1 P N)

EF-7. ttOTE 5 YESp HOTE 5 ET-HA HOTE 5 - YESp NOTE 5 2=CRY=485= 0. BF 10- - A B/7 0 A - B - EF EF-5 I EF-1 E F-5 P- HO HO EF-7 EF-7 P NO ET-018 ET-018 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 RUN DATE AND TIttE: 14SEP87:13:28 SYSTEN-NAttE.: SECOHD TEN YEAR INTERVAL VALVE SUt01ARY SHEET - UNIT 2 CfRPONENT-COOLItiG -=---== - -- FLOtL DIAGRAIH - 5135 - =-=--

VALVE- ----- ---- I- VALVE=POSITIOtt=l ASttE SECTION XZ-I I MEMBER REV TYPE SIZE ACT F. D I POttER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

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

EF-5 EF-5

-- --- - C -YESp HOTE HO 3--

EF-7 EF-8 C HOp NOTE 3 ET-005 ET-005 C NO SLT-1 SLT"2 R YESp NOTE 2 2-CCR-457 0 GL A D/4 0 C EF-1 EF-2 YESp NOTE 3 EF-5 EF-5 NO EF-7 EF-8 C HO NOTE 3 ETF-005 ETF-005 C HO SLT-1 SLT-2 R YESp NOTE 2 2-CCR-460 0 GL 3

' C/4 0 C 2 A A EF-1 EF-1 P HO EF-5 EF-5 NO EF-7-- --EF-7 -P NO =

ET-010 ET-010 P N)

SLT-1 SLT-2 R YESp NOTE 2 2-CCR-462 0 GL 3 A A/4 0 C 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-009--- ET-009- P HO SLT-1 SLT-2 R YESp HOTE 2

DOttALD C. COOK hRJCLEAR PLANT RUN DATE AND TIHE: 14SEP87:13:28 SECOND TEN YEAR ZttTERVAL VALVE SUtStARY SHEET - UttIT 2 SYSTEM-NAHE-.COMPONENT-COOLING -FLON -DIAGRAH: 5135-34 -=

VALVE = -- l VALVE POSITION-I --ASHE SECTION XZ I I ttUHBER REV TYPE SIZE ACT F.D. I POHER SAFETY !CD A/P CAT PRIH TEST TEST TEST RELIEF RWUEST(S)

TYPE COORDI OPER -- FUttCT--ICL -REQUIRED- -==

PERFORMED- HODE 2 "CCH "451 0 BF 8 HO E/4 0 C 2 A A EF-1 EF-2 C YES'OTE 1 EF-5 EF-5 NO ET-026 ET-026 C NO

-SLT-1 -SLT-2 R -

YES'OTE 2 2-CCH-452 0 . BF HO E/5 0 C 2 A A EF-1 EF-2 YES'OTE 1 EF-5 =--- -- EF>>5

=

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

ET-024 EF-2

-EF-5 ET-024 C

C YESi NOTE 1 NO-NO SLT-1 SLT-2 R YES> NOTE

DONALD C. COOi< NUCLEAR PLAtA'ECOND RUH DATE AND TIME: 14SEP87:13:28 TEN YEAR INTERVAL VALVE SUl01ARY SHEET - UNIT 2 SYSTEM=NAME:CVCS -

LETDOWN-8-CHARGING---=-= ==

-=FLOW=DIAGRAM: 2-5129A VALVE- I VALVE-POSITION I ASME %ECTION-XI I I SIZE ACT F.D. I POWER SAFETY I CD A/P PRIM TEST TEST TEST RELIEF REQUEST(S)

NUMBER REV TYPE TYPE-COORDI-OPER - FUiiiCT-- ICL-=--- CAT

-- -REQUIRED- -- =- PERFORMED- - -MODE .-

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

.-ET-006=-=- --ET-006 C - NO 2-QRV-400 0 GL 2 A K/4 C 0 2 A B EF-1

--EF-5 EF-7 ET-005 EF-1

=-EF-5 ---

EF"7 ET-005

"=-=HO P

P P

HO HO NO 2-SV-53 0 REL 3 SA M/2 C 0 2 A C TF-) TF-1 R-.SV-&i.-0 ~->A-E/4-- C---.0--

REI -2 A-- C- --TF"1- = -- TF-1 R -- HO

4

~

DOiRLD C. COOK NUCLEAR PLANT RUN DATE AND TINE: NSEP87: 13: 28 SECOND TEN YFAR INTERVAL VALVE SUED'RRY SHEET - UNIT 2 SYSTEH-NAHE:=-CVCS -LETDO'ruN- 8-CHARGING- -= = =- =- FLON -DZAGRAH:--2-5129"32-

-VALVE--- I VALVE=POSITION I ASHE-SECTION -XZ I I 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- A -C TF-1 -- - TF-1 R NO

0

DOiiALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOiND TEN YEAR INTERVAL

- UiNZT 2 SYSTEH=NAHE: CVCS.=-=LETDORI-S-CHARGING VALVE SUHHARY SHEET

-- -==--- FLOil-DZAGRAH:=- 2-5129 = VALVE I I

VALVE-POSITION I I

ASi lE= SECTION =XZ--

HUl&ER REV TYPE SIZE ACT F.D. t POHER SAFETY ICD A/P TYPE COORD ) OPER - FUHCT ICL -

CAT PRIH TEST REQUIRED .. TEST PERFORHED TEST HiODE RELIEF REQUEST(S) 2-QHO-226 0 GA 2 Y>D G/7 0 0/C 2 A B EF-1 EF-1 P NO EF-5 EF-5 NO ET-011 ET-Oll P HO 2-QRV-200 1 GL 3 A H/3 0 0 A B EF-1 EF-3 P NO> HOTE 8 EF-7 NOTE 8 YES> NOTE 8

-- ET-NA -- -- 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- --- -A-

--C/2- -C - 0 -- -- - 2 A- - B -EF-1 EF-5 EF-7 EF-1 EF-5 EF-7 P

P

-HO-NO NO ET-008 ET-008 P HO 2-QRV"62 0 GL 3 A C/2 0/C 0 2 A B EF-1 EF-1 NO EF-5 EF-7=-=

ET-009 EF-5

-- EF ET-009

=-

NO HO-HO 2-SI-185 - CK-..-8-- - - SA K/5 C - 0 2.- -A- -C -- CF 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 RUH DATE AND TIME: 14SEP87:13:28 SECO'ND TEN YEAR INTERVAL VALVE SUYu'1ARY SHEET UiHIT 2 SYSTEM-NAME:- -CVCS- -LETDOWN-8-CHARGING -- =

FLOH DIAGRAM: --2"5129-32 VALVE-. =-= =- =.. I VALVE POSITION I -ASME SECTION Xl I I HUi'SER 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 REQJIRED PERFORMED MODE 2-IMO-910 0 GA 8 MO L/5 C 0 2 A B EF-1 EF-1 P NO EF-5 EF-5 NO ET-012 ET-012 P NO 2-IMO-911 0 GA 8 MO L/6 C 2 A B EF-1 EF-1 P NO EF-5 'F-5 HO ET-012 -ET-012 P - --HO 2-QCR-300 0 GL 2 A E/1 0 A A EF-1 EF-2 C YES> NOTE 6 EF-5 EF-5 HO EF-7 EF-8 C NO> NOTE 6 ET"003 ET-003 C NO SLT-1 SLT-2 R YES> HOTE 3 2-ACR-301 0 GL 2 A E/1 0 C 2 A A EF-1 EF-2 YES> NOTE 6 EF-5 EF-5 NO EF-7 EF-8 C-- NOp- NOTE 6

,ET-005 ET-005 C NO SLT"1 SLT-2 R YES'OTE 3 2-QMO-200 0 GA 3 MO J/3 0 0/C 2 A B EF"1 EF-2 YES'OTE 7 EF-5 EF-5 NO ET-012 ET-012 NO 2-QMO-201 0 GA 3 MO J/3 0 0/C 2 A B EF-1 EF-2 YES> NOTE 7 EF-5 EF-5 NO ET-012 - ET-012 HO-2-QMO"225 0 GA 2 MiO J/7 0 0/C 2 A B EF-1 EF-1 P NO EF"5 EF-5 --HO ET-012 ET-012 P NO

. ~

DONALD C. COOK NUCLEAR PLANT RUH DATE AND TINE 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUl~RRY SHEET " LAIT 2 SYSTEH-NAHE:=-CVCS==LETDOHN-8-CHARGING =- . FLON -DIAGRAll:. 2-5129 "32 VALVF = = -- -= -=- -I =VALVE POSITION-I ---- = = ASHE-SECTION-XZ-I I NURSER REV TYPE SIZE ACT F D I PONER

-.TYPE-COORDI-OPER- - =-

SAFETY I CD FUHCT --ICL A/P CAT PRZH TEST REQJIRED -

TEST PERFORHiED -

TEST

- -NODE RELIEF RE@lEST(S) 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 CF-3 P YESp NOTE 2 SLT"1 SLT-1 R HOp NOTE 3 2-CS-299-H 0 CK SA F/7 0 0/C 2 A AC CF-1 CF-3 P YESp NOTE 2 SLT-1 SLT-1 R HOp NOTE 3 2-CS-321 0 CK 3 SA E/3 0 C/0 2 A AC CF-1 CF-2 YESp NOTE 4 SLT-1 SLT-2 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-1 P NO EF-5 EF-5 NO ET-009 ET-009 P NO

DONALD C. COOK NUCLEAR PLAtR Rmt DATE AND TIHE: 14SEP87-.13:28 SECOND TEN YEAR INTERVAL VALVE SUi~0'NRY StlEET - UNIT 2 SYSTEH-t4NEt=REACTOR-COOLANT- F LOtt- DIAGRAH: 2-5128A-34

-VALVE -= -- I.-VALVE POSITION I -ASHE SECTION XI--

I I 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 R YES> NOTE 7 SLT-1 SLT-2 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

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUiiQRY SHEET - UiiIT 2 SYSTEN-HARE: REACTOR-COOLANT= FLOH DIAGRAH: =.2=5128A-34..

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

TYPE COORDI OPER- -FUNCT- ICL REQUIRED PERFORNED MDE 2-NSO-062 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-2 R YESp NOTE 6 EF-5 EF-5 NOp NOTE 6 EF-7 EF-8 R YESp HDTE 6 ETF-002 ETF-002 R YESp NOTE 6 2-NSO-063 2 GL 1 SO N/6 C 0/C EF-1 EF-2 YESp NOTE 6 EF-5-- --EF - -- HOp NOTE 6--

EF"7 EF-8 R YESp NOTE 6 ETF-002 ETF-002 R YESp NOTE 6 2-NSO-064 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-2 R YESp HOTE 6 EF-5 EF-5 HOp NOTE 6 EF-7 EF-8 R YESp NOTE 6 ETF-002 ETF-002 -- R YESp-NOTE 6 2-PN-275 2 CK SA B/9 0/C C 2 A AC CF-1 CF"2 R YESp HOTE 4 SLT=1=-= = -SLT-2 R YESp NOTE 2 2-RCR-100 0 GL 0.375 A B/7 0 C 2 A A

-- EF-1 EF-5 EF-1 EF-5 EF-7 P HO HO EF-7 P NO ETF-002 ETF-002 P NO SLT-1 SLT-2 R YESp NOTE 2 2-RCR-101 0 GL 0.375 A B/7 0 C 2 A EF-1 EF"1 P HO EF-5 EF-5 NO EF EF-7 P NO--

ETF-002 ETF-002 P NO SLT-1 SLT-2 R YESp NOTE 2

DOHALD C. COOK NUCLEAR PLICA RUN DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SVi'DIARY SHEET - UNIT 2 SYSTEN-NAHC: REACTOR-COOLANT FLON -DIAGRAN: 2"5128A-34 VAI.VE =--=- I -VALVE=POSITION I ASYiE SECTIOiN XI I I 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-1 EF-5 EF-5 ET-014 ET-014 2-h~iO-153 0 GA 3 NiO K/6 0 C 1 A B EF-1 EF<<1 P N)

EF-5 EF-5 N)

ET-014 ET-014

-=- -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 HOp NOTE 3 EF-5 EF"5 NO Ef-7 -= ==-EF-0= NOp NOTE 3 ET-008 ET"008 NO 2-NRV-152- =-;-O=GL~=. =- =-A K/7- -C . - -C/0 -1 -A B EF 1 EF-4 NOp NOTE EF-5 EF-5 HO EF-7 EF-8 HOp NOTE ET"008 ET-008 NO 2-HiRV-153 0 GL 3 A K/6 C C/0 1 A 8 EF1 EF"4 NOp NOTE EF-5 EF-5 NO EF-7 EF-8 NOp hOTE ET-008 ET-008 NO 2-NSO-061==2 Gl ~ SO-- N/6 --- C---- --0/C =- 2 A -B- - EF-1---

EF-5 EF-7

- -=EF-2 =-----

EF-5 EF-8 R

R YESp h'OTE 6-=

HOp NOTE 6 YESp HOTE 6 ETF-002 ETF-002 R YESp NOTE 6

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 2 SYSTEH-NAME:REACTOR-COOLANT -

FLOH =DIAGRAH:- 5128A VALVE I VALVE -POSITION -I ASHE SECTIOH=XZ- --= =

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

TYPE COORDI-OPER -- FUNCT .

ICL REQUIRED PERFORHED - NODE 2-CS-442-1 0 CK 2 SA B/4 0 2 A AC CF-1 CF-2 R YES> NOTE 1 SLT-1 SLT-2 R YESp NOTE 2 2-CS-442"2 0 CK 2 SA B/4 0 C 2 A AC CF-1 CF-2 R YES> NOTE 1 SLT-1 SLT-2 R YES> NOTE 2 2-CS-442-3 0 CK 2 SA B/4 0 C 2 A AC CF"1 CF-2 R YES> NOTE 1 SLT-1 SLT-2 R YES'OTE 2 2-CS-442-4 0 CK 2 SA B/4 0 C 2 A AC CF-1 CF-2 R YESp NOTE 1 SLT-1 SLT-2 R YES NOTE 2 2-GCR-301 0 DA 0.75 A B/8 0 2 A A EF-1 EF-1 P HO EF-5 EF"5 NO EF-7 EF"7 P HO ETF-002 ETF-002 P HO SLT-1 SLT-2 R YES'OTE 2 2-N-159= 2 =- CK-= 0.75-SA C/8 0/C - C-- -=2-- A AC--- CF-1 --

SLT-1

--- CF-2 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-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO ET-004 ET-004 P HO

.SLT-1.== SLT -R YES> NOTE 2 2-QiO-151 0 GA 3 VO K/7 0 1 A B EF-1 EF-1 P NO

- EF"5 EF-5 HO ET-015 ET-015 P NO

DONALD C ~ COOK NUCLEAR PLANT

~ RUH DATE AND TIME: 14SEP87:15:28 SECOHD TEN YEAR INTERVAL VALVE SU'i~RY SHEET - UihIT 2 SYSTEM-NAME:REACTOR-COOLANT- -FLOH-DIAGRAM: 2-5128-19

- - .VALVE=- - - = =- -== I-VALVE POSITION I- -

- ASME- SECTION-XZ-I I 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-2 R YESp NOTE 1 EF-5 EF-5 HOp NOTE 1 EF-7 EF-8 R YESp NOTE 1 ETF-002 ETF-002 R YES NOTE 1 2-NSO-022 2 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2 R YESp NOTE 1 EF - -- - EF-5 HOp HOTE 1 --

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

EF-7 EF-8 R YESp NOTE 1 ETF-002 ETF-002 R YESp NOTE 1

0 . ~

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR ZNTERVAL VALVE SUNDRY SHEET - UHIT 2 SYSTEM-NAME:=STATZOH-DRAINAGE,CONTAI%!ENT=--- -- FLON= DIAGRAM: -=2-5124-20 VALVE-

-=---==-- --I I

-VALVE-POSITION= 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-1 P HO EF-5 fF"5 NO EF-7 EF-7 P NO ET-004 ET-004 P NO SLT-1 SLT-2 R YESD NOTE 1 3-000-601=0 DA- 3 A- N/6 0 0 3 A =- A--- EF-1 EF-1 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 2-NS-357 2 CK 0.5 SA K/9 C 0/C 2 A AC CF-1 CF-2 R YES> NOTE 2

-SLT SLT-2 R YESR N)TE 1 M

00

0 DO?QLD C. COOK NUCLEAR PLANT RUN DATE AND TIMiE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET - UiNIT 2 SYSTEM-NAME:--NON-ESSENTIAI SERVICE HATER .. .. =- FLON DIAGRAM: = 2"5114A-27 ..

VALVE .. --- --= I I

-VALVE=POSITION 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-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO

. ET-005 ET-005 P NO SLT-1 SLT"2 R YES NOTE 1

~

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL NOH-ESSENTIAL-SERVICE HATER =

VALVE Sinai'RORY SHEET UNIT 2 SYSTEH-NAlK: . FLOH DIAGRAN: = 2-.5114A-27 VALVE- -===--===-= -- -I I

VALVE POSITION= I--

I ASHE =SECTION -XI== =-

HRSER REV TYPE SIZE ACT F ~ D ~ I PONER SAFETY t CD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE- COORD I-OPER FACT-= ICL 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-- = C-.- 2-- A =A=- EF EF-5 EF-1 EF-5 HO HO EF-7 EF-7 P HO ET-004 ET-004 P HO SLT-1 SLT-.2 R YES> NOTE 1-2-HCR-964-3 0 DA 2 A J/7 0 2 A EF-1 EF-1 P NO EF-5 = EF-5 NO =

EF-7 EF-7 P NO ET-005 ET-005 P NO SLT"1 SLT-2 R YES> NOTE 1 2-HCR-965-3 0 DA 2 A J/7 0 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF P --- NO-ET-005 ET-005 P HO SLT-1 SLT-2 R YES'OTE 1 2-hCR-966-3 0 DA 2 - A J/3 0 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO

= -= = ET-005 ET-005 P=- -HO SLT-1 SLT-2 R YES> HOTE 1

e .

DONALD C. COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL RUH DATE AND TINE: 14SEP87:13:28 VALVE SU&lARY S)IEET - LPi)IT 2 SYSTEH-HA))Et=NON-ESSENTIAL-SERVICE-HATER- = -- = - - .-FLON-DIAGRAH: 2-5114A-.27 VALVE ) -VALVE POSITION I.. --

--=-- --ASNE-SECTION XI I I NU)GER REV TYPE SIZE ACT F,D. I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

TYPE=COORDI OPER - FUNCT- ICL- REQUIRED =. PERFORHED NODE 2-HCR-956-2 0 DA A J/3 0 C 2 A A EF-1 EF-1 P HO EF-5 EF-5 NO EF-7 EF-7 P HO

.ET-004 ET=004- P HO SLT-1 SLT-2 R YES'OTE 1 2-HCR-957-3= 0- DA=-3 A J/3- =-0 =- =--C--. 2 --A

- EF-1 --- -==EF-1=-

EF-5 EF-5 P --- HO NO EF-7 EF"7 P NO ET-003 ET-003 P NO SI T-1 SLT-2 R YES> NOTE 1 .

2-HCR-958-4 0 DA 3 A J/3 0 C 2 A A EF-1 EF-1 HO EF-5 = EF=5= HO EF-7 EF-7 P HO ET-005 ET-005 P HO SLT-1 SLT-2 R YES'OTE 1 2-HCR-960 0 DA 2 A J/7 0 A A EF-1 EF-1 NO EF-5 EF-5 NO EF -EF-7 P- NO ET-005 ET-005 P NO SLT-1 SLT-2 R YES> HOTE 1 2-HCR-961 0 DA 2 A J/7 0 C 2 A A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 ET-005 P -HO SLT-1 SLT-2 R YES> NOTE 1

SYSTEM-NAttE:NON=ESSENTIAL-SERVICE HATER .. DONALD C. COOK HUCLEAR PLANT SECOND TEtt YEAR INTERVAL VALVE SmNARY SHEET - UthZT 2 FLOW DIAGRAM: 2=5114A=27 .

RUN DATE AND TIME: 14SEP87:13:28

--VALVE-.-=-= -= --

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

TYPE-COORDI OPER FUNCT ICL REQUIRED PERFORMED MODE 2-WCR-951 0 DA 3 A K/6 0 2 A A EF-1 EF-1 P NO EF-5 EF"5 NO EF-7 EF-7 P NO ET-005 ET-005 P. NO SLT-1 SLT-2 R YES'OTE 1 2=ttCR-452=2 0 DA 3= -- A-- .K/6= -" 0 == C 2 A -A.EF-1 EF"5

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

SLT-1 SLT-2 R YES> NOTE 1

0 DONALD C. COOK NUCLEAR PLANT RUN DATE AHD TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE QPiRKRY SHEET - UNIT 2 NON=ESSENTIAL SERVICE..HATER SYSTEM HAME-: = FLON DIAGRAM: . 2"5114A-27

-VALVE - =- I VALVE- POSITION-I I I ASME- SECTION - Xl NUMBER REV TYPE SIZE ACT F ~ D. I POKER SAFETY I CD A/P CAT PRlt1 TEST TEST TEST RELIEF REQUEST(S)

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

0 1

I I

=0 e DONALD C. COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL RUN DATE AND TINE: 14SEP87:13:28 VALVE Sly IARY SHEET UNIT 2 SYSTEN-NANE: NOH=ESSENTIAL-SERVICE-HATER-. - = --- .= . FLOH DZAGRAH: 2-5114A-27

-VALVE I--VALVE POSITION-I ASNE SECTION XZ I I 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-1 P HO EF-5 EF-5 NO EF-7 EF-7 P HO ET=005 ET=005 P NO SLT-1 SLT-2 R YES'OTE 1 2=HCR-$ 35==-0 DA-=-3 . = -A= J/2 =-- .C-. -- --2 A EF -- EF-1 NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 ET-005 P HO SLT-1 SLT-2 R YESp HOTE 1 2 "HCR"941 "1 0 DA A J/6 0 2 A A EF-1 EF-1 NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 ET-005 P HO SLT-1 SLT-2 R YES> NOTE 1 2-HCR-942-2 0 DA A J/6 0 2 A A EF-1 EF-1 P NO E F-5 Ef-5 hN)

EF-7 EF"7 P HO=

ET-004 ET-004 P HO SLT-1 SLT-2 R YES> NOTE 2-HCR"943-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-1 P HO EF-5 EF"5 HO EF-7 EF"7 P NO

--ET"004 ET-004 . P NO SLT-1 SLT-2 R YES> NOTE 1

0 ~

DONALD C. COCC NUCLEAR PLAtti RUN DATE AHD TINE: 14SEP87:13:28 SECOND TEt( YEAR INTERVAL VALVE SC0)ARY SHEET UNIT 2 SYSTEN-HAtfE:=-HON-ESSENTIAL=-SERVICE-HATER==- ==-=--'=--FLON-DZAGRAN) 5114A-27

-VALVE-- -==-- I I

VALVE-POSITION-I I

ASt)E SECTION-XI HETER REV TYPE SIZE ACT F AD I PONER SAFETY ICD A/P CAT PRZN TEST TEST TEST RELiEF REQUEST(S)

TYPEiCOORDI OPER ----FUHCT =ICL- REQUZRED -- -- PERFORMED ViODE 2-)')CR-929-3 0 DA 3 A K/6 0 C 2 A A EF-1 EF-1 HO EF-5 EF-5 HO EF-7 EF-7 P NO

-- ET=005 == ET=005 P ti'0 SLT-1 SLT-2 R YES> NOTE 1 2"NCR-930"3=0-=DA -=3-=-- =-A==- K/2 0 =-= C - ---2 . -A -A EF =EF=1- -HO EF"5 EF-5 HO EF-7 EF-7 P NO ET-004 ET-004 P N)

SLT-1 -- .SLT-2 R YES> NOTE 1 2 "NCR-931-3 0 DA 3 A J/2 0 2 A 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 YESp NOTE 1 2-NCR-932-4 0 DA 3 A J/6 0 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF -.- EF-7 P- HO ET-004 ET-004 P HO SLT-1 SLT-2 R YES> NOTE 1 2-HCR-933 0 DA A K/6 0 C 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P ET-005- = --=ET-005 P SLT-1 SLT-2 R YES> NOTE 1

0 DOHALD C. COOK HUCLEAR PLANT 0 RUH DATE AND TIME: lOSEP87:13:28 SECOND TEN YEAR INTERVAL SYSTEM=NAME:NN-ESSENTIAL-SERVICE- WATER-=- -= VALVE S!RCIARY SHEET

=-. FLOW .DIAGRAM:-- 2-511%A-.27 UNIT 2 VALVE -= ---- =- -

I VALVE-POSITION-I- =AQK SECTION-XZ I I Nk)DER REV TYPE SIZE ACT F ~ D t POWER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

TYPE-COORDI OPER = FLNCT ICL- REQUIRED PERFORMiED MiODE 2-WCR-924-2 0 DA A J/6 0 2 A A EF-1 EF"1 P NO E F-5 EF-5 NO EF-7 EF-7 P HO

--- -------ET-"005 ET-005 P NO SLT-1 SLT"2 R YESp NOTE 2-WCR-925-2=-=0- DA - - - A- -= K/6 = O.= =-- C -==-- -2. -A-A- EF-1 =--- EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO ET-005 ET-005 P NO SLT SLT-2 R YES> NOTE 1 2-WCR;926-2 0 DA A K/2 0 C 2 A EF-1 EF-1 P NO EF-5-- EF-5 HO EF-7 EF-7 P HO ET-005 ET-005 P HO SLT-1 SLT-2 R YES'OTE 1 2-WCR-927-2 0 DA 3 A J/2 0 C 2 A EF-1 EF-1 NO EF-5 EF-5 NO

- - ---EF-7 = EF-7=- P HO-ET-005 ET-005 P NO SLT-1 SLT-2 R YESp NOTE 1 2-WCR-928-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-1 HO EF-5 EF-5 HO EF-7 EF-7 P N)

-- ET-005 . -- ET-005- P HO SLT-1 SLT-2 R YESp NOTE 1

0 DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUtD!ARY SHEET - t)NZT 2 SYSTEM-NAME:ttON-ESSENTZA~ERVZCE-HATER .--==-- -- --FLON DIAGRAM:2-5114A-27 VALVE = -= --- I-VALVE POSITION-I I I

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

TYPE=COORDI-OPER - FUHCT---ICL= ------ REQUIRED PERFORMED MODE 2-HCR-915-4 0 DA 6 A K/4 0 C 2 A A EF"1 EF-1 P HO EF-5 EF-5 ltO EF-7 EF-7 P NO ET-006 ET-006 P NO SLT-1 SLT"2 R YES> NOTE 1 2-HCR"=920-1==0 DA=~= J/6 A 0 - C --=-2 -==A =- EF-1 EF"5 EF-1 EF-5 HO HO EF-7 EF-7 P NO ET-005 ET-005 P HO SI.T.-1 SLT=2 R YESi HOTE 1- =-

2-HCR-921-1 0 DA A K/6 0 2 A A'F-1 EF-1 P HO EF EF-5 HO-EF-7 EF-7 P HO ET"005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 1 2-NCR-922-1 0 DA 3 A K/2 0 C 2 A A EF-1 EF"1 P HO EF-5 EF-5 NO EF-7 EF-7= P NO-ET-005 ET-005 P NO SLT-1 SLT-2 R YES> HOTE 1 2-HCR-923-1 0 DA 3 A J/2 0 2 A A EF"1 EF-1 P ttO EF-5 EF-5 HO EF-7 EF-7 P th)

ET-006 -ET-006 -P-- -HO SLT-1 SLT-2 R YES> HOTE 1

0 DONALD C. COOK NUCLEAR PLANT RUN DATE AHD TINE: 14SEP87:13:28 SECOND TEN YEAR ItfTERVAL

- UHIT 2 SYSTEtt-HANE:=ttON-ESSEtlTZA~ERVZCE-HATER==- -= VALVE SLMKRY SHEET

-FLOtl DZAGRAH:--- 2-5114A-27 VALVE I VALVE POSITION I ASNE- SECTION XZ-I I 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-1 a NO EF-5 EF-5 HO EF"7 EF"7 a NO ET-006- ET-006 P NO - - =-

SLT"1 SLT-2 R YES> HOTE 1 2-HCR-911-3 0 DA=--6 A- --K/4 -=0- -=- C--= -=-2.-=-A=-- A=- EF-1---

EF-5 EF-1 EF-5 P -=NO HO EF-7 EF-7 P HO ET-005 ET-005 P NO SLT-1 SLT-2 R YES> HOTE 1 2-HCR-912-4 0 DA 6 A J/9 0 2 A A EF-1 EF"1 NO EF-5 EF"5 HO-EF-7 EF-7 P HO ET-009 ET-009 P HO SLT-1 SLT-2 R YES'OTE 1 2-lCR-913-4 0 DA 6 A K/9 0 2 A A EF-1 EF-1 P HO EF-5 E F-5 HO

- EF-7 EF-7 P HO ET-008 ET-008 P HO SLT-1 SLT-2 R YESp HOTE 1 2-HCR-914& 0 DA 6 A J/4 0 C 2 A A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO ET-005- . ET-005 P --= NO SLT-1 SLT-2 R YES> NOTE 1

0 ~

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SUtCtARY SHEET - UiiIT 2 SYSTEtt-HAttE:NOH"ESSENTIA~ERVICE-HATER-- ===- FLON DIAGRAH: -2=5114A VALVE -- -- - I VALVE-POSITIOH I =- ---ASHE- SECTION-Xl I I HUiiSER 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=-FUHCT -- I CL REQUIRED PERFORNED NiODE 2-ItCR-905-2 0 DA 6 A K/9 0 C 2 A A EF-1 EF-1 ttO EF-5 EF-5 NO EF-7 EF-7 P ttO ET-006 ET=006 P HO SLT-1 SLT-2 R YESp NOTE 1 2-HCR-906-2 0-- DA-=-6 A .-- J/4 0-==- =C= -=-- 2=- -A A. -- EF EF-5 EF-1 EF-5

-- P NO HO EF-7 EF"7 P NO ET"006 ET-006 P HO

=SLT-1 SLT-2 R- -YES> NOTE 1 2-HCR-907 0 DA 6 A K/4 0 C EF-1 EF-1 HO EF-5 EF-5 NO EF-7 EF-7 P t<0 ET-005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 1 2-HCR-908-3 0 DA 6 A J/9 0 C 2 A EF-1 EF-1 t<0 EF-5 EF-5 HO

--EF . -EF"7 == P-=- NO ET-008 ET-008 P HO SLT-1 SLT-2 R YES> HOTE 1 2-HCR-909-3 0 DA 6 A K/9 0 C 2 A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P HO ET-006- -ET-006 P HO SLT-1 SLT-2 R YES'OTE 1

O.

DOHALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:15:28 SYSTEM NAME' NON=ESSENTIAL SERVICE HATER =

SECOND TEN YEAR INTERVAL VALVE SlPiOARY SHEET - UiHZT 2 FLOH DIAGRAM:.. 2".5114A-.27 VALVE . = .... I I

.VALVE.POSITION 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-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO ET 00 8 ET-008 P . NO.

SLT-1 SLT-2 R YES> NOTE 1 2=HCR"BOl"I=- 0 DA 6 . - A. = - K/9 .- 0 C 2 A A-=--EF"1.----

EF-5

- EF"l.

EF-5

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

SLT-1 SLT-2 R YES> NOTE

0 0 DONALD C. COOK NUCLEAR PLANT 0 RUN DATE AND TINE: 14SEP87:13:28

==.

SECOttD TEN YEAR INTERVAL VALVE SL.uSRY SHEET UittZT 2 SYSTEH-NAttE:=-ESSEttTXAL=SERVICE-HATER- =-= FLOH DIAGRAH: 5113=36 VALVE-== =--- =I-VALVE-POSZTXON I

I I

= ASNE SECTXOtt XZ SI2E ACT F.D. I POHER HURDLER REV TYPE

=-- SAFETY ICD TYPE COORDI- OPER. ---FUNCT- ICL

A/P CAT

=--

PRItl TEST REQUIRED TEST PERFORHED--

TEST ttODE=

RELIEF REQUEST(S) 2-l'tRV-722-CD 0 3H 4 A K/8 0 0 3 A B EF-1 NOTE P YESp NOTE 3 EF-7 EF-8 R YESp NOTE 3 ET-NA NOTE YESp NOTE 3 2-HRV-724-CD 0 3H A H/8 0 0 A B EF1 NOTE P YESp NOTE 3 EF-7 EF-8 R YESp NOTE 3 ET-NA=- =- - NOTE 3- =-=YESp NOTE-3 2-HRV-726-AB 0 3H 4 A K/8 0 0 3 A B EF-1 NOTE 3 P YESp NOTE 3 EF=7= EF-8 R YESp NOTE 3 ET-NA 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 RUiN DATE AND TINE: 14SEP87t13:28 SECOND TEN YEAR INTERVAL VALVE SUiiARY SllEET " UiNIT 2 SYSTEN-NAHE: ESSENTXA~ERVICF=-ttATER - -= = - =--FLON DIAGRAM:2=5113-36 VALVE -- I- VALVE- POSITION -I I I

-- - -- --- --- ASttE-SECTION XI-NUBBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)

-TYPE-COORDI-OPER- -FLDtCT ICL -= = -REQUIRED- PERFORtlED N)DE 2-Ã~iO-726 0 BF 6 HO K/6 C 0 3 A B EF1 EF-1 P HO EF-5 EF-5 NO ET-023 ET"023 P NO 2-HMO-728 0 BF 6 HO L/6 C 3 A B EF1 EF-1 EF-5 EF-5

-==-- ET-024 ET-024 -

2-Htl0-734 0 BF 16 HO H/3 0/C 0 3 A B EF-1 EF-1 P HO EF"5 = EF-5 HO ET-054 ET-054 P NO 2=)D'i0=738 0 -- -BF --. 16 -- - N) - K/3 -- 0/C 0 3 A - B EF-1 EF"5 EF-1 EF-5 P HO-HO ET-055 ET-055 P HO 2-RtO "744 0 BF 4 HO J/6 C 0 A B EF-1 EF-1 P HO EF-5 EF-5 HO ET-036 ET-036 P NO 2-IC iO-753 0 BF 6 HO H/5 C 0 3 A B EF-1 EF-1 P NO EF"5 EF-5 NO ET-024. ET-024 P. HO 2-Ht40-754 0 BF 4 HO K/6 C 0 3 A B EF-1 EF-1 P HO EF-5 - - -- EF tlO=

ET-026 ET-026 P HO

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAiR INTERVAL VALVE SU)IIRRY SHEET - UiNIT 2 SYSTEN=NANE:=.ESSENTIAI SERVICE-HATER=-= -.= -FLOH-DIAGRAlf: 5113-36 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 P EF-5 EF-5 ET-054 ET-054 P 2-)040-706 0 BF 20 HO e/8 0 0/C 3 a e EF-1 EF-1 P NO EF-5 EF-5 HO ET-056-- -ET-056 -- P HO 2-HNIO-708 0 BF 20 HO 6/6 0 0/C 3 A B EF-1 EF-1 P HO

. EF-5 EF-5 HO ET-055 ET-055 P NO 2-IOIO-215 2 BF 12 MO -M/5 .

C . 0 - 3 -A- B = -EF-1 EF-5 EF EF-5 P N)

NO ET-034 ET-034 P HO 2-hYiO-718 0 BF 12 HO N/5 C 0 A B EF-1 EF-1 P N)

EF-5 EF-5 NO ET-036 ET"036 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-1 P HO EF"5 EF -- -=- - - NO ET-020 ET-020 P HO

0' 0 . ~

DONALD C. COOK NUCLEAR PLANT RUiN DATE AND TZttEt 14SEP87:13:28 SECOttD TEN YEAR INTERVAL VALVE SLPi~tARY SHEET UiNZT 2 SYSTEH-NANE: ESSENTIAL-SERVICE-HATER = .

FLOH-DZAGRAtt: =2-5113-36

-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 = . 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"1 NO EF-5 EF-5 NO ET-053 ET-053 HO

0 DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUi81ARY SHEET UNIT 2 SYSTEM-NAME: ESSENTIAL-SERVICE-HATER=-= -=. = FLOW-DIAGRAM: 2-5113 -==

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= 20 =- 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 . 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=-

0- -H =-=- G/1-=0 C - A -B- - --EF.-l EF -= -- 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

DOiNALD C. COOK NUCLEAR PLANT RUN DATE AHD TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUiiHARY SHEET - i%IT 2 SYSTEN-NANE:=FEEDHATER =FLON-DZAGRAH:=--2-5106A-41--

--VALVE--= == =-= - = I=VALVE-POSITION I-- -- ASME SECTION XZ--

I I 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 -CK8 - ---SA - J/7 C . 0- - A -- C- - -.CF 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- -=-REL- = 0.75 SA G/9 --C 0 ---3 A C TF-I = TF-1 R HO--

DOiNALD C. COOK NUCLEAR PLANT RUN DATE AND TZtfE) 14SEP87:13)28 SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET " UiNIT 2 SYSTEM-NAMF:.--FEE DNATE R =FLOM .DIAGRAM:- .2=5106A>>41 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 0.75 CK- -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 DOiiALD C. COOK NUCLEAR RUH DATE AHD TIME: 14SEP87:13:28 TEN YEAR INTERVAL PL)80'ECOiHD VALVE SUi'IMARY SHEET - UNIT 2 SYSTEM NAME:= FEEDHATER FLOH DIAGRAM: 2&106A=41 VALVE-=- .. ---IVALVE-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 NO EF-5 EF-5 NO ET"030 ET-030 NO 2-FRV-247 0 GL 1 A M/9 C C/0 3 A B EF-1 EF-1 HO EF-5 EF-5 EF=7==- EF=7= -P NO.

ET-008 ET-008 P NO 2=F.RV=257 0 G~ A H/9 C C/0 3 A B . EF-1 EF"5 EF-1 EF-5 P HO.

N)

EF-7 EF-7 P HO ET-005 ET-005 P NO 2-FRV"258 0 GL 1 A E/9 C C/0 3 A B EF-1 EF-1 P NO EF-5 EF-5 HO EF=-7== EF-7 P NO ET-005 ET-005 P 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

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIHE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET UiiIT 2 SYSTEM-NAME:FEEDNATER FLON DIAGRAH: 2-5106A "41 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-1 P NO EF-5 EF-5 NO ET-025 ET-025 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-.5 ET-021

.. EF-1 EF-5 ET-02)

P P

NO NO NO 2=FH0=222 0 GL 4 .. HO C/5 0 0 3..A = B - EF-1---

EF-5 .

-- EF-1 EF-5 P NO NO ET-036 ET-036 P NO 2" FHi0"23) 0 GL 4 HO C/5 0 0 A B EF-1 EF-) P NO EF-5 EF-5 NO ET-026 ET-026 P NO 2-FHO-232 0 GL 4 HO C/5 0 0 3 A B EF-) EF-1 P NO EF-5 EF-5 NO ET-034 == ET=034 .= P NO 2-FHiO-241 0 GL 4 HO B/4 0 0 3 A B EF-1 EF-1 P NO

- EF"5 . EF-5 NO ET-024 ET"024 P NO

DONALD C. COOK NUCLEAR PLAttT RUN DATE AHD TIttE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET - UNIT 2 SYSTE!1-NAttEt FEEDHATER- FLON DZAGRAtt:--2-5106 "34-VALVE- =-

I I

VALVE-POSITIOtt I I

-- . - - ASttE SECTION XZ 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-2 C YES7 NOTE 1 EF-5 EF-5 ,NO EF-7 EF-8 C ttO) NOTE 1 ET"005 ET-005 = C HO

0 DOiNALD C. COOK NP'LEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE SVC%RY SHEET - UNIT 2 SYSTEH-NAHE:= FEEDklATER- .FLOH. DIAGRAH:=-2-.5106.-34 VALVE-- = ---==-. -=- = -

I I

VALVE-POSITION=-I-I

--ASME SECTION XI NUHBER REV TYPE SIZE ACT F D. I POHER SAFETY LCD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)

- TYPE-COORDI OPER FUNCT.--ICL- == REQUIRED. -== PERFORHED NODE 2-FHO-201 0 GA 14 HiO G/5 0 C 2 A EF-1 EF-2 YESp NOTE 1 EF-5 EF-5 HO ET-020 ET-020 NO 2-FN)-202 0 GA 14 HO E/9 0 2 A B , EF-1 EF-2 YES> NOTE 1 EF"5 EF-5 NO ET-018== =-- ET-018=-- -. HO 2-FHO"203 0 GA 14 HO F/9 0 C 2 A B EF-1 Ef-2 C YES> NOTE 1 EF"5 EF-5 HO ET-019 ET-019 C HO 2-FHO-204 =0 GA~4= ---N)=- H/5 - C =- 2 =- A B -EF-l.

EF-5

-- EF=2-EF"5

- ==- YESi NOTE HO 1--

ET-019 ET-019 NO 2-FRV-210 0 AG 14 A G/5 0 EF-1 EF-2 C YES> HOTE 1 EF-5 EF-5 NO EF-7 EF-8 C NOi HOTE 1 ET-005-- ET-005 C - NO-2-FRV-220 0 AG 14 A E/9 0 C 2 A 8 EF-1 fF-2 C YES> HOTE 1 EF-5 EF-5 NO EF-7 EF-8 C HOp HOTE 1 ET-005 ET-005 C NO 2-FRV-230 0 AG 14 A F/9 0 2 A B EF-1 EF-2 C YES> NOTE 1 EF-5 EF-5 NO EF-7 EF-8 C HOp NOTE 1 ET-005 ET-005 C HO

0 DONALD C. COOY. NUCLEAR PLANT RUN DATE AND TZME: 10SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SALARY SHEET - UNIT 2 SYSTEM-NAllE:~TEAM GEHERATIHG.SYSTEM- .- ..-= .=-.= FLOH DZAGRJQJ: 2=5105D=2

= VALVF I -VALVE-POSITION= I ASME= SECTION XZ.

I I 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 RUN DATE AHD TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET - UI'lIT 2 SYSTEM-NAMEMTEAM=GENE RATING-SYSTEM =-- === ---

= = - FLOH -DIAGRAM: =2-51059-2 VALVE ==-== .

I VALVE POSITIOH I -ASME SECTIOH Xl=--

I I NUMBER REV TYPE SIZE ACT F.D.

------- TYPE-COORDII POHER OPER-

SAFETY )CD A/P CAT FULNCT=-ICL- -= --

PRIM TEST REQUIRED -

TEST PERFORMED TEST MODE RELIEF REQUEST(S) 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 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. - 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 8/5 TF1 0 REL 6 SA C 2 A C TF-1 2-SV-25-2 0 REI -- . 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 0

DONALD C. COOK NUCLEAR PLANT RUN DATE AHD TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVF SUi'tttARY SHEET UNIT 2 SYSTEtt-NAttE:=STEAtt-GENERATING-SYSTEtt -- ==FLON-DIAGRAtt:=-2-51050 2 =-

VALVE - VALVE-POSITION-I I AStfE-SECTION-XL I I HUiitER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRZtt TEST TEST TEST RELIEF REQUEST(S)

TYPECOORDI OPER== FUHCT=ICL = -""-- " REQUIRED PERFORHED - NODE 2-tkRV-240 1 GA 28 PO B/3 0 2 A B EF-1 EF-3 HOp NOTE EF-5 EF-5 NO EF-7 EF-8 C t<0> HOTE 2 ET"005 -=--

. ET-005 C- NO 2-HRV-241 0 AG 2 A A/1 C 0 2 A B EF-1 EF-1 P HO EF EF-5-= -==-= HO EF"7 EF-7 P HO ETF-002 ETF"002 P HO 2-ttRV-242 0 AG 2 A A/1 C 0 B EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P ttO ETF-002--- ETF"002- 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 RUN DATE AND IIHE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL SYSTEM-NAME:=-STEAH-GENERATING=SYSTEM--=--- -=-=- =

VALVE SUPssQRY SHEET FLON-DIAGRAM:-=2"51050 UNIT 2

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-3 P NOp NOTE 2 EF-5 EF-5 NO EF-7 EF-8 C NOp NOTE 2

=- ET.-005 ET-005 C NO 2-HRV-221 0 AG 2 A H/5 C 0 EF-1 EF EF-7 EF-1

-EF-5 EF-7 P

P NO NO NO ET-003 ET-003 P NO 2-HRV-222 0 AG 2 A H/5 C 0 EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO

-ET-003 ET-003 -P NO 2"HRV"230 0 GA 28 PO H/3 0 C EF-1 EF "3 P NO NOTE 2

=-EF-5 EF-5 NO EF-7 EF-8 C NOp NOTE 2 ET-005 ET-005 C NO 2-HRV-231 0 AG 2 A H/1 C 0 2 A B EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P NO ETF-002 ETF-002 = -P =NO 2-HRV-232 0 AG 2 A H/1 C 0 2 A B EF 1 EF-1 P NO

=- EF EF-5-- NO---

EF-7 EF"7 P NO ET-003 ET-003 P NO

~ ~

DONALD C. COOK tRCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUtDIARY SHEET UNIT 2 SYSTEM-NAME:STEAN.GENERATING SYSTEM-=. :-- FLON DIAGRAM:..2-.5105D=2 VALVE I -VALVE=POSITION-I AStK SECTION-XZ I I tmHBER 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. 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-1 P HO EF-5 EF.-5 NO ET"049 ET-049 P NO 2-HCH-231 0 GL 4 HO K/4 0 0/C 2 A B EF-1 EF-1 P NO EF-5 EF-5 HO ET-050 ET-050 P HO 2-HRV-210 0 GA 28 PO 8/7 0 C 2 A B EF-1 EF-3 HOi NOTE 2

-EF"5- --= =EF-5-- NO-EF-7 EF-8 C HOW HOTE 2 ET-005 ET-005 C NO 2-MRV-211 0 AG 2 A A/5 C 2 A B EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 P ET-003 = ET-003 P--

2-HRV-212 0 AG 2 A A/5 C 0 2 A B EF"1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-004 ET-004 P NO

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

-YAivE- I YALYE.POszTIO>l -I -

ASNE SECTION Xl I I 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-1 P ttO EF-5 EF-5 NO EF-7 EF-7 P HO ET-006- ET-006 P NO 2-DCR-320 2 GL 2 A B/2 0 C 2 A B EF-1 EF-1 P HO

- EF=5= = EF-5 HO-EF-7 EF-7 P HO ET-006 ET-006 P HO 2-DCR-330 2 GL 2 A B/1 0 C A B EF"1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO ET-008-- ET-008 -P NO 2-DCR-300 2 GL 2 A B/2 0 2 A B EF-1 EF"1 P NO EF-5 = EF-5 -HO-EF-7 EF-7 P HO ET-009 ET-009 P NO 2-QT-506 0 GL HO A/8 C 0 3 A B EF1 EF-1 P HO EF-5 EF-5 NO ET-023 ET"023 P HO

~ e DONALD C. COOK NUCLEAR PLANT RUH DATE AHD TIME: 14SEP87:13:28 SECOND TEH YEAR INTERVAL SYSTEM=SQ1E: PAL-SAMPLING=S--INST-. =PAHELS= U-2= VALVE Sly~>ARY SHEET - UNIT 2 FLIN-DIAGRAM:-.--12-5141F -

-VALVE -I=VALVE-POSITION I -- ASME SECTION XI I I 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 CF-2 R YES'OTE 3 SLT-1 SLT-2 R YES> NOTE 2

DONALD C. COOK NlCLEAR PLANT RUH DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SlMCARY SHEET - UNIT 2 SYSTEN-HANE:PAI NlNPLZHG-8=INST.PANELS== U-2= FLON-DZAGRAN:.~2-5141F-6 VALVE I VALVE. POSITION. I ASNE=SECTIOH-XZ== =----

I I HUYBER REV TYPE

= SIZE ACT F.D. I PONER

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

SAFETY ICD FACT A/P CAT PRIN TEST ICL-- REQUIRED TEST PERFORMED-TEST NEODE RELIEF REQUEST(S) 2-ECR-31 2 GL 1 A B/3 0 2 A A EF-1 EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO

=-ET-005 ET-005 P NO SLT-1 SLT-2 R YES> NOTE 2 2-ECR-.32 2 GL- 5 . 2 -B/5- 2- =2 =A=-=-A ===EF-1 -EF-1 P NO EF-5 EF-5 HO EF-7 EF-7 P HO ET-005 ET-005 P HO

- -SLT-1 SLT" 2 R YES> HOTE 2 2"ECR-33 2 GL 0.75 A B/2 0 C A A EF-1 EF-1 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 2 2-ECR-35 2 GL 1 A B/2 0 C 2 A A EF-1 EF-1 HO EF-5 EF-5 HO EF=-7 -----EF-7 NO ET-004 ET-004 P NO SLT-1 SLT-2 R YES> NOTE 2 2-ECR-36 2 GL 1 A B/3 0 C 2 A A EF-1 EF-2 YES'OTE 1 EF-5 EF-5 HO EF-7 EF-8 C NOR NOTE 1 ET-004 ET-004 C YESR NOTE 1.

SLT-1 SLT-2 R YES'OTE 2

0 f

0 o DONALD C. COOK HUCLEAR PLANT RUH DATE AHD TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET - UNIT 2 SYSTEH-NANE:PAS-LIQUID 2-GAS==UNIT=2 == = . FLON DIAGRAN:... 12=5141C-.8 .

VALVF - t- -VALVE-POSITION ASME..SECTION. XZ I I NEER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF RE@JEST(S)

- -TYPF COORD I -OPER =..FACT ICL-= . REGUIRED PERFORNED NODE 2-ECR-536 0 GL 0.5 A L/2 C A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P HO ET-003.. ET-003 P HO SLT-1 SLT-2 R YES> HOTE 1

0 0 .

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEH YEAR INTERVAL SYSTEH-NAHE-:=-PAS-LIQUID2-GAS UNIT-2 -- -- -- -

VALVE SUtaaARY StlEET FLON.DZAGRAH -

UNIT 2 12-5141C-8 =

-VALVE =-

- -- I VALVE POSITION=-I -=--= ASttE SECTXON XL-I I 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-1 HO EF-5 EF-5 t<0 EF-7 'EF-7 P HO ETF-002 ETF-002- P NO SLT"1 SLT"2 R YES'OTE 1 2-ECR-417 0 GL -0.5 -A---H/6 -- C.=-------C 2---- P =-A-EF-1 EF-5 EF-7

==-==-=- EF-1= ===-==-=-

EF-5

P HO-NO EF"7 P NO ETF-002 FTF"002 P NO SLT-1 SLT-2 R YES> NOTE 1 2-ECR-496 0 GL 0.5 A H/8 C 2 P EF-1 Ef-1 NO EF-5 =- =- EF-5

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

SLT-1 SLT-2 R YESp NOTE

DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIHE: 14SEP87:13:28 SYSTEH-NAME:=HDS<<VENTS-2i-DRAINS SECOiND TEN YEAR INTERVAL VALVE SUEEENRY SHEET -

FLON-DIAGRAH:=12-5137A-21 UiNIT 2 VALVE- I VALVE-POSITION I =-ASHE=SECTION =Xl-I I AMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD

--TYPE-COORDI-OPER==- FUNCT--ICL A/P CAT PRIH TEST TEST

REQUIRED-. -PERFORHED TEST

-HiODE---

RELIEF REQUEST(S) 2" DCR-621 0 DA 1 A N/9 0 2 A A EF-1 EF"1 NO EF"5 EF-5 NO EF-7 EF"7 P NO

-ET-005=--- ET-005 =P NO SLT-1 SLT-2 R YESp NOTE 1 2-N-160 O=CK=l==SA= -F/4 -==-

0 C - =2= A- AC-:-CF SLT-1

---=- ---CF-2 SLT-2

---=- . R

..TER .MOTE 2 YESp NOTE 1 2-SF-159=-==--=0 DA ---

3=- H ---'/5--C---- ==---C----.- =2 ---P- -A -SLT - .. .-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

DONALD C. COOK NUCLEAR PLANT RUH DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE RPittARY SHEET - UHIT 2 SYSTEN- NANE:HDS-VEttTS-tt- DRAINS F LOlt-DIAGRAtt:-=%2-5137A-2l=

VALVE =- -- - l VALVE-POSITIOiN j ASttE SECTION XI I I 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-1 P NO EF-5 EF-5 HO EF-7 EF-7 P NO ET=-005- ET-005 P NO-SLT-1 SLT-2 R YESp NOTE 1 2-DCR-207 O=DA- -I=A--F/4-- 0 --- =- C== -= -2 - A-A - =- --EF-1 EF-5

-EF EF-5 P HO HO

=

EF-7 EF-7 P N)

ETF-002 ETF-002 P NO SLT-1 SLT-2 R YES'OTE =1 2-DCR-610 0 DA 2.5 A M/9 0 2 A A EF1 EF-1 NO

-=EF=S= EF-5 HO EF-7 EF-7 P t<O ET-003 ET-003 P NO SLT-1 SLT-2 R YESp NOTE 1 2-DCR-611 0 DA 2.5 A N/9 0 2 A A EF-1 EF-1 P NO EF-5 EF"5 NO EF-7-- EF"7 -P NO-ET-004 ET-004 P NO SLT-1 SLT-2 R YESp NOTE 1 2-DCR-620 0 DA 1 A tt/9 0 2 A A EF-1 EF"1 P HO EF-5 EF-5 NO EF"7 EF-7 P NO ET-004-=- ET-004 t,'0 P

SLT-1 SLT-2 R YESp NOTE

DOHALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUta>ARY SHEET - UNIT 2 SYSTEM-NAME:=NDS-VENTS-8-DRAINS FLON.DIAGRAM: .-12-5137A-21 ==

VALVE IVALVE POSITXOAN I -ASME SECTION XZ I I 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-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 YES> NOTE 1 2-000-202 0 .

02 0..75 0/5 0 A=AEF=l EF-5 EF-1 =-- =-

EF-5

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0 DONALD C. COOK NUCLEAR PLANT RUN DATE AND TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL SLMSRY SHEET - LAIT 2 SYSTEN-NANE: SPENT-FUEL-PIT-COOLING CLEAN/P-U2 VALVE

FLSI-DIAGRAN:=-12-5136 -

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0 o DONALD C. COOK NUCLEAR PLANT RUN DATE AND TIME: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SCARY SHEET - UNIT 2 SYSTEM-NAME.=CVCS--..BORON-MAKE-UP==UHITS ~8 2 =.FLON DIAGRAM:~2.-.5131=19 VALV VALVE-POSITION I ASME SECTION XI I I HRKER REV TYPE SIZE ACT F.D. I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)

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0 = e DONALD C. COOK NUCLEAR PLANT RUN DATE AHD TINE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SUE)ARY SllEET - UNIT 2 SYSTEN HANE'= CO)PRESSED~RMYSTEN UNIT 2-= =. FLON DIAGRAM:= 12"51208=22 VALV I - VALVE=POSITION-.I.- ASNE SECTION XI I I NUMBER REV TYPE SIZE ACT F.D. I POHER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

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e DONALD C. COOK NUCLEAR PLAttT RUN DATE AND TINE t 14SEP87t 13: 28 SECOND TEN YEAR ZtlTERVAL VALVE SUt$ 1ARY SKEET - UNIT 2 SYSTEH-NAHEtHAKF UP=tt-PRIltARY-HATER-&ilZT-=2=--. = FLOH-DZAGRAH:

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Cs<ll.a 1 FROM PU)/45 csas< I~ ~ Of t 10 ttt4 P 4! t 15'SV50 JIVA NVA <st(etc t) 4 f v/+as 4 teatw.a-IOO~T PIPING DES)GM To FOL(raver f5<$ 1 NO.Z'ROM !Oi t.t> Puv I Ne 3 . 54 YKNT 2 >(tat ISO 3 tlua l4 tl N < 4 ) ~ I lea I CRITERIA INDICATEP IM PUMP N0.4 0 RV.20 PUMP Mat. altcotuptp lt<4 la ~a< <Il ~ 1 Yt'e Qtl ZDPUMPND.Z QRV 30PUMP M0.5 I 11451 ~ CS<TS< Call<< I QAEW.)tlt C, AEW-'6)C. 34 QT(.30 PUMP Np 5 QRV.(0 POMP Npcy Cs<$ $ $ as<$ 5< r 5UVI< ad a/1 ~ 3 5<.ISMIC CLASS 2 EXCEPT Qtl 40 PUMP N0.4i CRV <O ~ <ra<\ AS '(NDIGATKD. SKCOMDARl'EAL 3 CPM ale al 2 2 I Rue $ '2 r Cs<SS Na,'2 L fAK.OFf ~ L 4'I ~ Nea NO~I, C/f LEAKAGE,TO REAC'(OR Ct>DLANT D/4 Mo. I LEAK.Of F ovav <oe 5 f <all 1'sar 10 II h 5 ~ lt St ~ <<o ver< ffw retf ee 3 <44 <<Tee ~ 3 0<If K ( Is 4 Hlk Of 1 1 E About COVK TO)RE RK)ztf)2 Koouvt fttt D'RA)H TANK. SE.E Q R PUMPN0.2 I DWG 51 '5'T At A/S<8/5 (Ct/3 t Dj3 13<40 <4$ <$ << QCR 21 5IPUMP ND.S <5<Is I 2 I2 RtacTDR I ~ Le 1 ll <L tv MP. '/Ot(1. 1/T.H/r Cltlt ~ Mt 5 LEAK SPOOL <a.<1$ .1 acR ll PUMP NDA <<<et e" t ~L<43<Iteet 0 CONN.AT LOOP Nt5 t 1 <O ~ 1 0<1 lta ruup teat Qft 4<a<<.$ OCF 8)ECC ((YP) 1 e V Vlb( %Hat( ftl(N)TOM STOl arltsopu r tats T cs<tlc GT (54<1.l QDA tatvsIOHOt FRQM O(IIER REACTOR o ONLY 3 vtf <<NY 10 6( DtfRAT(D Olds)DK OF FRD< TLV 0 f 1 t <0 fta<p Sac 110 IG Claal 1 ODA )0 PVMP N<3'OOLANT PUMPS TJ 6/ REACTOR uk<eh h< t<e Tt a 4<a Dtl(EZ EMC(056(K AT ELC)214: (NR ftvt Dh 441 csea< ~ (sacs 4 Cpauo tvut 414 0 COOLAN)'v<<P ~ ot<e Tra NOEL3 ~ H/1 I oacl 3 45<<1 I f5<at IO su<.I c$ <lo4 Tp vo(UME caulROL 1'ANK. THRU SEAL 0 f<V* It'2 (4< I ) scott 511AY tiff oowuwatD to afl'110 taut CGBU 3/4 Ga 4 </4 (54ll 3 S Csee< t CS<$ <pS WATER CIL'IKR. SE(t I K 4) Iuva.ftt (ue NVA 14'1 (Nl 4) t) (0M<1 I) I 4<sffll PtotlOK wal(t 514L 6(TW((M Of1 1)O tuut VT '1 QT E-2'10 PUMP NOR csuf.a Cr//G 5)ZBA (5/(L S Tr twlb A ft('S>utltlt AMD 5124Y tait(s. N< 5 le af(-25QFUMF)as Csea<a Csa<tkl 0( ~ ae-<e 4 '< ~ llY NOTE 5, N/C ~ 4rcr K/C ~ GU 1lotuut v<4 '/4 ',,.,' a f1 0 /4 tel 110 DRY ISO kt ot t-240TR34PNa4 AA(l 0(1(c(oes AT 601(0$ 4 61 TO OTHER REACTOR stl SEAL 5'15(EM 61 Dr 0 'I<. $ $<p<e ~ </4 v < T 'I capt ttfl COO(AHT PUMPS r Ll)L t at gS pa55 At staR( op "" aft 30 taffaf II<) I 3]e C.C. 0 pet Rtclf ssv alt f 144<a 6 f1 .'llo f 11. ffhh<1 S' NOTE C ~ K/S Hac Na.s No.t Cl<'ll4 Cl ~ $ ae ef p 4, ks 5 OC I/t SLNFFlt( oowu'ka'tD To tIOYIDK Waif 2 S(AL OV 2'(OKF VA(VKS.
aa'I ~ 1 cs<<4'4 OTHER k'<I T)LV e<$ 33<T<D k Cl ~ I ~ I CMSlff I ) F ROM =!0 ev'<lhv av a<Ol <VS<Le< 'IlOTQT, 0/1, J/'1 (lull <ut<<I est<5'4 REACTOR 5 K ETC N L14 ca(ate)ltt20YIMAT(LT MIDWAY cs<<II I cs<<s 'tI Nla COOLANT PUMPS M))ff(M laat AMO tt($)att(KR.
(tu lt taut Ir1 <la<el csaal <a 1 v ~ lac< pre ARRGT FOR ONE REACTOR COOLAM't CtM 0 fOMt (I<a<<<csa<$ I ae< <<a< Sf rata LOOP IN CONTAINMEHT N'1 2 Natf 6, 4/Te J/le 2/9 H tualt IP4 II<)'FM )t(a(tot ccolavT tot<f5 II CDA)It<a/P) <I D at<4<us fag )5ASMITTED SAMtlf 5(K c<tr ~ csea<<< t.45.1 Pt 413 1 ILPDP Nes supwN) Clara ~ St<I. Cia<$ 4 cs<<av pp.ab 5 ppuD 4 5 K S T C H 'C$ -3 4 vt'ec rveft<KISDI acc strow<< Ov Dee/I '1'i<lb ~TK '5. E/2 nOM 1NARCING FVMFS <la<Dc taf local 9CNEMATIC ARRANGEME.MT OF REACTOR COOLANT'UMP VAI.VC bpNNET AND ItllTRttaLS S(f OIIG. Sit)< 6/1 l)011(ION VALVE TKST (CLht 8csuo"1t 15014110'0 DRAIal T(ST (pull eatctttee . SEAL WATER SYST'M Cw QR 1<1 CR Nla ARE TD 6K REMOVED AND 6OND VALVE ta HEAD INSTallep 'EXCEPT wucu / RK5)DUAL H'EAT R'EMDVAL ltOM l(TDONN'Ulk R(ulf trp<psfaftu Tsu fl.hv f PRESSUR)ZER N A <5 ltl TKSTula vaLvl St)Os HEAT RXCIL SAFETY VAlVE . e .NO)f 5,(/4' G D)SCH. SEE DWG. S)43,L/5,G/3 Va(VK S(f DNG.SUS< l/t 1 l t RELIEF LINE. 153 <Tert< / 5 ~teat/0 op R41fo vacv+ KMERG. CORK CPPLIHG Vc Nla MOTE 5,(fl 0 'NO)( f. ((4 I vhrgal IDCNT<ftact<ON NVNSCR5 SYS. ((KLIKF VA DISCH. F FROM (ll SL'Cf(R tflueV SY 45A <<3 law <I<1 slf ARG(MG PUMP $ SVMSS ~ 1 orlct '<paovK vaLvc Nuubces SKK DWK S(432< C/Br J/8 SUCTION SAFETY 111<(f tattt N( 5(.'l 3;)I/1 ID TO 24 STRAIGNt Sy,45( 151 e AP<faR ON tt<<S ORawr<G. S(C SECTION (TY 0 1 CAL) 5(paRatf vaLvt fo(Nt<FKat<GN 0 , 0/Sr(/8 VA(3/E DISCH.SGE K)tf(s 5129 1./G ftOM R(SIOVAL N(a'I R(MOVll lOOP 'lit 014. Stl), t/5, 1/6 Ntt
51. 119 (atf I <eaas ctree<<<4) 2 AUX. SPRAY DWG 5) 2 9,6/3 5( E,
/4'OOP SEOEL )Lee! C ISI c<vfarlt ~ tsDO<< 7 Lest FOR (OV<VaLCNT CCSIGN (MORI ttu<es(RS. 2, 'faa'NVNO(PS a<a(aft(0 FOR DR<<WC<a Vsc Ph fOLI.OWS r F 5 s. 1 STC<4 L($KOOFp) <cot< sff I tat Afu I 2 taa Ne'2.45W.VKI> a< pcaas as: Nswtosw I 5110B Sl<1'1 I L '~l h< 4414 Nplf 1, $ .C Atwstptprfrf Root vacvf uaRK \Il>O Nol( G.pfc 5(( (fat( 6, 0/5 I&X 102 l)I/rt HPX I pl suls HP 0 4 Stt Nate'Sa/S (Pl)-15 M ( . C. ~ SEE NpTE9 afs (I 0/3 ~ FG 3K<Is 1-3 Nato 1st ) pe(ssvsl zKR fvsT (f 0 0 I t U U K af Nasactatlst<PIN at< DR<w<aalstt VaLVC eu(NI<F<tat<ON Ust) DCR<v(0 bt u<stwvuftlt'Nvtls(R: 400<10 FOR SINGLE I<PTAS(.VI ta St<SO~.IV Lfff-ICS PRAY list( t,(fs ~RV )52~ AN cctuoLK <<<<hast.vtarstftcavt y; CLV-)DZ PCOOOIT VKN. C = g(V ~ COHT COL VOTR 5,(f 4 I f I, LV Ctublg <<tLfDROSTAT)C s/4 t I(S I
52. I TO YKH't
)50LATON VALVE TK5T CDalu(CTIGN ~ ~2K)(T TRST FLANGE 3< tf utpeaet Nasf V43LVES 5/'4 NSX 104 4444 ~ I lOM N I )MS)DE,INSTRUMEHTAT(OH ROOM ' ~ oc <<Kaort<t< cfa'lus 51( alee<el <<cork <ao <tv<cero VRV IS4 RCR 101 DWGSI)lltb<9 30) ~ I FOR flu) CRDNR($ ()DI( Nta SKK NO)C 6,0/5 (0 3 SF 4-1/.t) 34 RCR KO V(550. HKAD VKMT 9 NStlt-r Y 0 ~e m trNS EIZS,H/IA Ncrlsttt II 0- Sate <<0 rvteTP 3'/0 ~ XQXATIDMV<LVK /4 Nla 11sT Cuuvcat<04 t>OLSTIONhA) 1(ST CONM. Lllv. Na'llR ((V(l fl. 451 .NLPI5>ft II 15 fOR RKVISON 0(SGR<Plfw SKK st/<<Rate R(VISOR RKGGRD 9 p%%d 2 $ $ 4$ RSWK 3/; tRS)0)~Ra V f99 RAY LINES PRESSVR)ZER I I- NPP r ~ FX)R.TTOS DRAW<NO ek~ tv4 <<ve av<ee FROM WITRQGKN SUPPLY MANCPLD X~g ~GK+50) tg >/4 51AVO tiff I >e ve Cfu 24 ~ ee SEE DWG.SIIGB,C/3,)I/3 ast h< - Pt ttc 5 5(E SRKTKN 'D-5 0/2 NYDRDSTAT)C TE.S'1 FLANGE FROM REACTOR 15 IS ! ~ ~ ~ ve t~ <<vr ~ vvw'etc< p<<ve<<<<<eve<< a< ~ v aller< <tpp eeevv COOLANT LOOP tSI NLPISITI t C'ROM REACTOR Nac sst ~520M/5 I FROM PRIMARY WATER , QIK'.C; trtlf COOLANT L00P NLPIHTI 151 131 = I <re<war<a I 4<OH<CAN caacffw<G ctOL SE'E Ov/G 5))5h J/6 3<e /4 ((Tf) )ILNWAYAVD Rut(UZK HaD.SEE OwG.S) >G//) ...,I DONALD C. <wctc L O. RSR~ t ~ Wt ls NIKY tel Disc. BURST PR(s>VCE 100 PSI GPS-3UTI IF
Nua
)St G 311 f(KK025.9 1 aa (t<RFOR Se)<eas) J ~ atocuar l tvvft COOK'vc(KAR ~ tctoc<R NCR Serif'I 2 SC<)G ' DEAD WEIGHt ~ F LOW D)AGRAMhr f1 1'I ~ CALIBR43TOR . . REACtOR SC+ COOLANT; U<hDT 2 rg 1501ATIOV VALVR Sl St NOTE ZO/4 SHEE) 2 OF 2 . ~ ' T(ST.(0</k~ ~s >I ~ )( t<A ss<T1 ts:0 $ (EATS.'R CONTROL PIPING BYQ 102 St( NOtt 6,0/5 4) 4) 2 -5128 A-.3+ NIA <H.te Ceo< CCI E)f tvGTCT frt tri-M< Sft Ow PRE SsuR)ZEIZ RELIEF lit>00 STS IOO PSI-54O F. TANK O(V.I PRE,SSORIZER SURGE ~ttf<Attt r<ccfftc Kstaataf<>4 fore f/4>< LIME FROM LOOP Na3 o//puett tlt Ipevt<FTGAT<>4 Ntp<bcc t<f ak 1 SEISMIC CLASS (( 1 C. SEE DWG.S)2O)~ I'5 '1 If\raesb Gtf tee<flu 5 6 <lutCO evf Ir r. a<\'/ V-; 4 ~O H <G-9< OUTSIDE Co NTA)NME)4 RKIL<CTOR j )HS)DE REACTOR CO) (TABL(ZK)KT DRA)H R ACTOR LINE-5(K DWf<.S(STA,LVC COOLANf Qt K Q T G sc)IE.MAT)c /RRAHGEMEHT. 05 I >>luG AT PREssIJRIZE<K tt>'fvt tees cew N/DLvrtava FOR vtttt 1 ~ ~ ~a 'A. p f." ~ e AuD PRE.SSORIZKIK REVE.F TAuK . Av> 5.~5<Of> ct<<G T-1 sttShwcv f) ~ fettcat< calf<OK to<1< st<<wc cvr, ~ ltpapraf alr Tofr A I 0 C I - o ~ R I G I H I . J I . ~ l rr p kt<<ve 3 0 '3 C el '3 e ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ 6 ~ I ~ ~ ~ ~ ~ ~ ~ I I ' 4 ~ ~ ~ 4 ~ 4 ~ I ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' I ~ ~ ~ ~ ~ ~4 a~i 4 ~ t.w . t tA I ~ 4 ' ~ ~ ~ ~ ~ 4 Q+555t' ~ ~ ~ ~ ~ 4 ~ ) 4 - ~ i 4 ~ ' le ~ I~ ~ 44 I ~ ' ~ ~ ~ II~ ~ &g~g% ~ ' I Vaimem' l~ ~ ~ III I I YL'tIG-2 ON vo 0 I P I I, t 1 M ) N I 0 C>fcNfRAL NOTES I I LfCRND 10 CDL>PO>RNT C00LPIG SYSTEM < M>>,N FLOW stt tslrC Nl 513$ >CJ/3 0 Kl I lll tc>JJ<< le c>>c ALA Z AVL, FLOV/ t>CESS Ltt 00/JN JS<<N tc <<55111 DOWN 0 SCDM LOOP A Qwvtat trav>>ace il TO HOLDUP TANKP>> St( (JXDI(G)$(E Dws ~ I, f/~ . 4' oI ir 0J ~ 'svc 53 SET AT TSPSli .OWG N> 5132,N/6 FOR VALVE, HISTRUMENT, aav)05 SAMPLING. PIP(, MATERIA' ra0>r EOMOOAR Nt IL> I OLT ND 0TH(R SYM80LS NDT COOL>NC SYSTEM IS 3> aw> QI A Stt DAC N SI)).C/4 FAILTD RE'acTDR
I FA SCRD CAD EXPLAIN(D FDR Stt DwCS DN THIS DWC MARK NVM8(R CODES It 5>33(12.5>04 AND la COOLANT DIEAIN 2 FOR FLUSISIN(t
>10 >10 TANK 3/8'RV Sc DR4$ 1 TD Rf EJR)R t SIRM i Ltatafgf aRV ITI H(AD(ITS(t SEISMIC CLASS I (IXX.INT D(4$ 4 AIL(t / C>lct 0 RSO 300 Cslll TO 'VENT N(AD(R $ (~(DWG. I I O~>I>Ill,JI> EKCfPT AS NOtED 512 0, (/3 f. 200 REGULATOR PRESSURE I Kacf >IO << V4'>IN \L. CSAOO C)$ 1} LsLV. CIE.O N>DCDCRN GVPPLY Cs ))t st t DW<< N> 5118(LHIt VIOS t~G / Vive Httt DSK l CL.C 10 'ae OCTO'R CDOLAN'I NITRDG'EN Sal PLV 'Iaa(IN>o DRAIN TANK SE~S SEE OWCi N>SVsb,f/3 30 DYIG. 513T A, ()rt NJ51 Vise I'HP.Y(vt 5'10$ $ H(at csssc QRV csl~ QW bY WEST>NCHOVSe GW.302 FCG c A TD AND f RDM CD>APD'N(NT AIL 10 VOLV>N ALL vALvts E INSTRUMENT-CDDUHG SYSt(M Stt DWG ~<<> >s 1 CONTROL TANK S AT10>4 SUPPUED SYQw Sg 54 9>'I 5135> F/4 ~ G/4. AT 150 PSI >S>>>>>>>>>><<>O COV 0 ' 3 cs Ill Cslls 4 3 faIRPMONT SVPPLlf 0 BT Qw l )ARLY He(lit DCV)0) AS NDTfD 37 l DIA<<ll>IAA4 >CALO C51$ C TO HDLO.VP TONES. h (A ec*CCO) C.J / so<< Df>(> NI SISI,H/6, ~F FROM SAMPL>NG ~ 1 Q Z VOLVMt CDNIIOL 0LC . OLC NJ I'KP. Y(IIT SYSTE>4 4 DV 5) 0 $ (H TAN> ~ l $ 1E DWC 5129,M/3~ T)fsl t50'P 4$ > 45 gaKV.400 Rla(N RDD 4 400 CLEF T. Cs)ll RED D.t 3 FRDM 5652 (T K-10) TRANS>V>>CRS ARL D>$ (>CSEE 0 AC O>IYSIDR COLAD>lc 5129. )413 3> ROD<<$ Cslll 1 8>p MANWAY SEAL WAT(R QIC$ NOTES: H(A'I (XCHAHG(R H 8.1 "+s (¹-H) 0>O<<COO>. CLt>$ <<>S>e>>>AV> CO>>os cs}co DH ~ STE>A LEAKDIF IP <<4 IIL~ no c<<c 111 1>1 <<V>>OOAV C>1> ~ IO> 1>A>JO ><<c>>JOL$ 1<<L >>es> >vr>> v>LJ> 0>oo cool CLI>sec>>1$ >o<<>>>>s 1<<c. I'l >>Asc oooo<<ec CSlae Xvag~)~ 0~ . 1>c. LI>c>>oc >of LA>Aft>JLY aascb vocvcl >K>>44> WD r 4 Jr .4 Csl>$ ~r 0>ID AS> as>CA452 >n~eC g ata(H acD awo t GTI SI)l>F/$ >> o>>J>> >4><<~>>> ~oool >oc >A>>F ooo ~ l l <<A>>> 3 I OO ><<> 3 css>o ~ 4 ~>> o>>>>e 4 oo>><< 'EL. 609.0 Cs 5l1 vav0 I\p(RAYED vALYE TO HOLD VP IDEN>>F>CA'I>OI> VVVOERS TANKS. 5'EE trACe 1 OWLY'l>V>DOE VALVE 51st, K/5, cw T>ws DRAWP>c. SEE HVVOERS'pptaR s(PARATE VALVE IDEVTIF>CATNN Ust fOR KDV>VALKWfDESICN lvcRI Hvve(RS t, tAC'A>VS(AS v00>FIED PDR DRAWJHC vsc as FOLLOW): H(AT T RA(IN fo YAC V>: R.VIW VI0$ W J AppKARS As; vsw>0$ w 5TDPS HER( swlsYRVNEVT ROOf VALVE NARK Nfs Vvt SHOWN Pw Isa TD C HA R G IN G PUMPS )j UM,>l 'scAKR VP TD RTFU>LLNCI WATER STORK(>T. TANK~ DERIVED 8Y ADDwC TD ON DRAWINClscc VALVE >DEVllflCat>DH USt) FROM CHARGING PUMPS 5(t DWG )l>5111, >)/6 <<<<v>>v>> W ><<\ 51 PRIMAR'Y W/'T(R. DWG H>5131,$ 41(R Stf gI w4 ~ l }I'DIA'R'ORIFICE, RO 101 SEE DWG. 5129, G/6 Haf DVOW ) 05)L 4DT ~ cslce SEE, DWC.SI44,0/6. HDS5 CONN- POR PILLINC> 00 SPCNT )VEL PIT. a>stRLAAE>IT Ao vvveER: FIR 5l>KLK >APLAJJVI fOR COLDLY OWSISCVKLPSTRFAWI FDR ORCHANT IRSC L'>040/ILH.SLLIVS Sto FLNNRL~ .IL>"50K E(~ ' YENI 10 A1>>05, PR.L V(NT TO ~FR0$ DWC.SISI/ SEG $ BORIC ACID SLENDER >EYP IJP /0 ST JIP 104 DS) CW I'Y(NT N01 8Y Ow At M05. o)J)B cll ll 3/4') gba I'FO VOU/HE COAITRDL TAhlc THOl 5(AI. WATER FL'TER> SEE Dfl($ 5128A,(I/3 QSq 1 0$ 1 351 ST( Ofc 351 0 351 I ')50 cspssc ~Ttltss cs set 0'>I I'Y(vt 3 FR DA LETDOWN H<
PTK}I SEE SEI>vtatE REVISION RECINO FDR Ysos DRaww0 OCM t50 ((AKCAg ki 4 DITAIN TO PLO4R L)111 ~ 5<<cf Drr(<< 'Na 5129, N/2 ~ c>cn>>c le<<co ~ >>>O>>1 ~ >>>>>>>>>>~ <<e >1>>>c>e stew ce>>J. 1>> << lo>>o ~sj ftace I"Actoa C00LANT PIAAP p 3> ~ >o>>o>>>>> o> ~ >>>>, ~ o<<o >>>>> ~ ~>><< ~ SEAL. I>AIRa CJECL}t (4 PV>E<<S} (CA$$ )2) C f+0>A'CM>NtRALIZERS WOWI JO >>>>>>> <<O<<JI <<4 56>LS ,11>>ll >>><<>>>> 1>> o( ~ Vollg CO>J oo 5(f SK:0 3 ON DWG Nssltel H/3 CAP ll cs>>$ CPM-37 Les)vs 0 II Cssll 8 0; $ tal. ~ Essa> c))es CS) +Cssla a(ACH R00 O>> ~>> ~ IO>>>>I>><<O>>>>>>>>>>> I~ >>>>>>><<>>>C )la C)$ $1 Ow ~R(ACH RDD R(0'D REACTOR 3 1 WATER f>LI(R Rlavlatb IVD>A>>A ~ C)LOO )~ , COOLANT lllCV>OAVCLKCY>>JC CO QCMeSO QC 109 1 HT(a. DOtIALD C. COOK (DC IOC) IVCIEAR PEART 8 CS) $ $ )/4' ) $1 Cssdl ~ A>OCVAO VK>OCAI> I, ~ G C$ $ 10 AM ~cs)ec C)/CS - REACtOR cr LHDO v REACH R00 R(0'D CHARGING Lr 8 R(ACH Re REOD~<cs)$ 4 Jl<<l V> (L Iw>>10>1 WD Cs'$40 ~ 41 EL'(V, 58130 REACH RDO Ol SIIT.HIO REDVIRED 2-5 I2 9A->IP IPI Ol $0 41 ~OJ - TH:5($ /G )LL)2 I/NIOUE 51134>WC FOR utsli 2 AND 3(IIR~(4/G )-2-5(29A-8 ~ ~ l<<I<<K>1 eccl>AK >Oece l>A>KI COA>. I >AO>OAAY AtW YOAA C I ) I I tl H ) J I L I $4 4 ...,.8.. I 0 P 0 +() I 4 t II f
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's<<*r I I N Sf Sl tate)Cpx tsc ~ 't dtt 4) EPX aSs) 0 CXJTSIDE REACTOR CO)ITAINMc.x)T ssevlsssi teN)ICPX ~ St " ~ (N fl CI'X ~ S) ~ fJENERAL NOTE5 5 F t 5-2 DNstO Crl LSS(evft 8 S 1 ler))CPCaos) ~ (N)S)LPX ~ 456 crw)N t' IHS)D1 REACTOR.COL)TAIS)ARES)T Cv1 ast(V t) LEf END '8 Cti aia(HO CPX ~ 1! I 14) REACTOR I'ENtq CPA 41 SEE O'NC. S)29.C I ) 451 (OL(DONKNT IWU) to RLLC(DR COOLANT PVestos CF( CODit Rtxt)DR 424 CCWI')I I r.f wt)t I ccw)M-4 cwtio 4 COOLIIIC SUPPLY coot.AHT pvaeps f vtsset(a) COOLANT PVaeo) H!I (f 5 Ccwtresv I'8' Ccwl)CC Ccwesl-t Cwt)SS CCHISS ccv set I Ccwt)D 4 I (stL. "8'~:> tcsvecse C ~ 5 )~as r Ic ., LETDOWN 4EAT ~ ) ~J,.~ CCHI)S 1 CCGLtttC RKfURN AUXILIARY PIPINC cc'K))r LCH)2) 1 5 CCWNC.( LCWIR CUIDL SIXRotc COO.LR rl t-4 53(t('.3'. 10 COMPONLN'( (00ttttG ~ rtfrttcs Cll 1 'L47) CCwtct L5'xLNAIICER II ccwltr Ccx.aiasva tt<54LN!4) COR VALVE, INStRUMENT, I Cfw)ts 4 $ VPP(A D(L'RiNC SUADE tlNK (RCM Ctto M 470 I OO CPM CL.45)LXI)s SAMPLING. PIPE MATERIAL CCwtts.l DW05135A.NI2 g rfoaotc ISOLATiON VALVE 'f KSt CONNKC(eOet att w CCwlto.l CCwlt5 I q N12 CCA 45 fra est CCN22) ~ $ CCW)11 ) isrts Fsx-SEK 7I CCwtt,l ~ 4 Zr Z. rr K'L.C 3350' g atto OTHER SvM80LS NOT EXPLAINFD ON TNis DArA ANO FOR MARK AXIIABKR 5 LP ORAiN-i tp ffW160 Lcl ) Cf 1 Ossa C(3 ~T 1 I 1 CCW)t) 2 sf TX CPA t 9, I2-Jeos CCWI21 Ilsc )I f I (tttc lgccwtt) 4 I r 2(XOCDsss 410 4 0 At rd& prot 46( COD SEE OIVG ~ I it Sade M49 avt av 4 OCCet gl 492 492 ro St I ~Peed CPX 464 (Nt 41 CPX dtq Ovt BY 'w EsTINGNOUSE CCwt)).x ts(R)XAL OXRICtctt 'IOS CPM J 8- CPX' Lr (Nt 2) CCX esl <<ot CCHI)t ' tl ).') A Cf W151 DIESEL()C5,2/5 1 <<R < C Cw ccwltt.t CCWI'SO 4 t)2 cpx.ocs (N) s) cpx.oce EOUIPUENT SUPPLIED SY f ccwts(r's aa) CCNI)72 Ccwttol CCW)14 (CH2) ~ 1 4 = COWISO.t CCWISO i I,"II C1 49 11 txOwe 15 ~sw.SKtTC)t 1 s aa era~6-Are 9 AS NOTED 4 310 Lc RoM Rt LctcR svppon CCWI)t ~ I = ('DRAIN s ga'VENT fd A!estele )s)-2'43 ALL PIPINC to et f(ass*.(t f Ccwtsh j~I C DAN~ ~s rat ax Coo(ILK.S(t Ttos cwc.stt el 2 CC'Kt'N fcw267 1(EKE.TON COO(.ERS AL'L TU)INL to et LLAss P42 2% CCWI)i") Ccwlse w CCVIECG (1 YPICAlg EXCEPT As NOTED Cwt)S CFI CCWI)1.4 1 7 IN I>> I 2K% cs. L . 1 0 45C CCI 1551st!I) 5. CTX ALL EQUIPMENT .5215M+ ~ 0( CAeo 821 PP) sead oxr e std roe ~ t Xg SVCt CCI ~ 511M!St t=l V)CAIN 5(29A.FI4 P HEAT EX(RANGER I X IP,'GAFETV valvE ClASS t KXC'KPt AS No(to assay~ / 1 t' Srt At 2485PSI SKT At 125PSIG Sv- I FROM SPENT FVKL P,T PUMPS DA-451(N!I) CFA as C DL.453 ttr )I td ftOOR DRLD( CTA C sEK, ONG.Stsc~/5~ IQ COR CODt CLASS EASIDS O)SRIC CDMsstcrsosso.)H\ lsl Dcuecsaev, 4$ LCR11$ $ IX Pa'v A vtisa ~FI- .CDL 454(x!4) Cfx.del(N!I). 452 C 1 AM5 51 Na I) 1"KIse cxfLeKs fd AMD tsKLscc5 fxc f)RSC Iiddf Va LVC ISOLAtON VALVE t j tvcvaa wae cH 4'ea 0 0 CTA&scitcl) Ccorcot Cg EST CONN(fTON ~ r CPB.15) ter Ccwlll 1 1 ~ ~ I sf 122 cftoLI Rtxcfot Coo.ANT NE4 I IC IO (C) rDR coo( CLAss R( svEM)s DRA1NS TH( ISI DOUssOARV cxltiscs fo Aeo McMttcs fvc t ,,I I /4. ptccecpAV eve SKT At 150 PS) 21 FSR'L'f NORMWV CLOSE D VALVE ssr.cxessac )tie, Ff, IPN-e2 '9'DRAIN TO FLO(N Cot(ste~ CCwll C /HOSP(NT FVKL PIT I txv 1st ftRUV, a(XS))t cpx CPN ')5 v I 2 tr(3.456 4 SEE. OIIC.SISC.J/5 A 8 w LCN'tj) pxvcwstQc nw%v vso wasrc FA es CPX 4 tsO ~r+ rccwteORP(tq150(ATION I I'seSs Ccaswecoodst5 rla SCC VIA 45 ast Ava care VA, Z ICCrrt14 c'r.'CAP () CH ee ~ 1 crA TR / 2ets 4)d fFA IIOfrtda l'LP 44 C 44 f1 CPX Cfc 418 CCA 55 as vc DLLIN 44C ~ ral CtCAM OC.H Ssasaac S ssr Katxasow, 'I Also Av@Hable Oa 6 CRY 445 HofO'ec vvtf po(rsx D sscvxtxw covrew(vf cnstsncaf Kw Ht 0 ~r t ttt R twa ooos A sr occ r 1.2SOCPM SPENT FUEL PIT VHLt$5 t)fts(XWssc Hdtfo. ~ CC 51.45 IS Lie)e ~ )I F 45 1 VG tsaa c svaa& 9s 1 J LC~Slj~> N 7(35CPM Aperture Card F.C. NEAT EXCNLNCER 5 srto / P SftSsoC CIASS K Qu t)t Lp ECW ~ccwsos r L~wi ~ < IC. FXCU KDNPON/Nt K(SLING f(AT'E'R PUMPS IC (2 ~T THIS CkiCsNAOE t)t) )QUE COR Wali ocf cc( )SEE Ofa. 51354,JesG CCW I 11 EL. 604)-0 LN(t 2 ANO SUPGP5EC)8% CCH eao Soe LPH SCHOrtt E)tsV(S I ~ 6 SISS RCSI I7 oe O'af, wciUKH rwoas Ft. tr vd coaseoacr waste.cAs coHpvcssdr s I'Sexd fstta 1 Stt IK (NIS DWC.N('I Cft 475 coossvo aatcw rvesps SXC.XSIC DO Cxee IDEN)trecxttoN NUNS(PS AAOA LIS ~~ OXC trsC. C ~~ . 425 )rt cc )or Cf( 8)ES(S,MI 1Uosst Al e)OP)I CLMI(v DRAWXVC VSE AS F(X tOeS: Nso GPM( TAC Ne: APPEARS AS tAsweoe SSWVX)S.W ID 314 Oototswc SV-CC SIT I' t SK'ETON S,tsesfRVM(NT Roof VA'VE )1ARK Ccwtie NVS Hof SHOWN DK Dekwotc(SEE ~ s Af 110 Pst FUEL OKTKCTO(3 SC Xt M.G'altto VALVE IDEN)tt'ICAlsott UST) I'O 6 FROM P(NT)RAT)ctl Ditaewri 3't) st SAMPLE IIEAT KXCNANGER DERIVED ef ADOINC fo 1 COOLINC Cdste 4 Ct 0 FXN F.f tMO1OO Atc COOLCR S INSTRVMLNf NVMSER: 6EE.DWO.,R'SISD>sPS CFI 1 r Kcaa rasLCD CLCL 4 'a A IIE>> ~st'Ctw)aa I vcHf d ft)R SIN(LE SVSLSCVI .FOR Dtxxxx oetxscvtrxpslttfxlrc CCVtdf tcrccfcw oasspac wcAT CLHSteotvaHA~itOO> )1 CCsvtsr KOS XfCssasCLA NC 7 1'ae te'cwdt2 ccwRN &5~ 5 S V2CX)KNSI)t)C GRI 465 Ccwsete rcowsdo I r" "' 1 r C 1 TX I I ~~ Ccwseo O I CCISOS'7 'C ~ Stf EPx Ii I FOR MKCorttN Stxltls ~~~ Cfesttt I h Ip H ?I 'sa ~~ ~ 48(r I ~ coraov ( rvCMT 1 clrtssDN R(coro rdR i)os Otic I CC'f std Covedo'tso 'oewokl 11 )CIX ccsveos 1 I Cfasr~ ()re CPX Q'cow sos o~ j sf / I ccwedse Crx Sate asrvrvtr I . 48Cs %fr g I)"j I 2K' A~ 0 x cgg I rt I. -;; II d Q~ fOR RfvtstON DESCRtPTXCI SEE SEIIXRA(E REVIS)ON RECORD 1 I C'(X 48 VALE)2ATCR I 3 PVMP 0)SCHARCEIO CFI RKGENERA(IVL NEAT 422 IX 5 IQ oc= l~ E ccwocHoc)L ~ fOR t)4$ ~I DRAwtNC ELSBTLO'f EXCHANGE(L SEE I~~ TRIA H vv aweraa I "'I I ~ PK I 48 CO((of Nst R I OWG 8(29>LIB <4 CI -. 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~ ~ ~ Ia rpa ~ sv eassw aeasw IH HHA vaasw H wv ear sewer ca ~1000 GPM 487 482 M sae sewH emH IA A pwe I Id Cooaitt ~ t+CW)tsl stew~ asvvea aA ~ er H wwwv HA aawwc ~dt)0 GPM ffw294 4' I FLU(O C(1 I'- I- CP CPA 401 u,at~ I INDIANA~ NICHICXN IXXC(wtoCo. I'.,'- otst I DRIVE tc- 1 I B-1 I DONALD C. COOK:- I COOL't R L(A Ii, .) ,9= NUC(XA)tPtANT i,.l CP 1 tt ccwtss I IRP SEARING OI esa 1M I olI sAsdvfass - I dec ON. COOLER .FL IA A CPX trxfstxarC. COMPONENT COOLING I CCwlto (5 CPS(j EO(XER 3" p," I Cotta CC UNIT NRZ .Ilg(J J (asc(SE) ' I VENT C.DNOE,N N H r t' (~ Sew) S ttf/ I t ccas o osr pvscxsstsUK +lfxxrsct tRAM VCeCCWJ 41 I 50GPM7 (fer) (fsvsc*L) Af 1)O PS( CTI 'scree seto sess)as) IE 2-5 L35-3t) .I adt cpx ~oor x I L "( I 40 ado fL 587 ot O'PUMP SUC (toN CAOed Qr( RKCIPROCAtl)sC SANPLE RACK A" SAMPLE PACK B 'ar t)ORIG ALGID cvA RAToR VOLUME coN(ROC TANK KIIARGINc PUMP Qttscpt4wxsrK cvapoRArf)ittov txoarccnl) SE(5L(lc CCASS XE . 5'LE trwo 5129,LIB. CtaLSS Xrt (SCL F)Ptt)C ISTO DEC~ Alp 'CISMIC 1- )UNSCKLLAN'EOUS SEI'r 5 \ '(v AatotKAK llxclRKrvv(x Mxrtcc Crsttr. t ossoeowxf T0%t ~ 1 ~ Ha ~ 'r Ia, D I 6 o I Iif 1 I J I 5 Cg I I I n A 'I D I f 0 I I H I .. N I L I aa ) ~ O V5 E I5 2 'ON lc() CNCVIXAL CHARrlafe TANK S GALLOK 4'VKNT 4)SD Dt((sFLDFF ccv-412~ fa(vvM SA(AK(R~ C(wt IS ~5 x'Y.Go GENER AL NOTE 5 LEGEND s(ISMI( c(A')$ 22 FCCwtos 4'teat 1 4 'ee SKt AT )9 Psl g(cwttf cave CCvttoa ccwteo (vteC ~VENT ~~ EoouNG -\vPPI Y couroMENr COOLING RETURN ~/'-.: (CCWSOS ccwstco Lccvltlw CL III o) 0 (LA ae CEDJPONWN CO)LING II e. CT e INC 5/4 Dcs(vaao( fts(a(c fCwsltc ~O'iaSV(float NOTE(K DRaeM (tYR) tvv 411 CC 410 WCTK R SURGE TANe( ae BAF Fl.'f Oaaeel (tvfaea() (ard(G SRk't. DRATN(tYP)w CCWS(CW V BASKFLATE DRAIN (rfR) al x vg zZ ~ ~ 9 ae CLA 415 4el
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d. 14 vK Lccw)M 401 400 LCGftsd ALL PIPING TO B' CCVCNV t F<~ EXCKP)'S NOTED SD C fax C<<ara(S gv(tel t C "A IG 'O COMPOHKNT C(XX.ING ALL EOUIDMKNT SEISMIC S(253, Ats HIS NEAT EXCHANGER e)f ~SG CLASS) KXCEPt AS NOTED Ctwlt)y I vevr Cartew 'A'fs SVETCS) <<E).Dr. I- CPS
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I 14 CCWI DOC g (we(FCY 15; ClaSS) C(rel5t 4 Id ).I .I ccweao /-fYKNt(EXOLw ~Y) CNO 40 C PD ~ ~ 5 rsvv sr vcc Tvpc etcvea CVD CZC(N) ceavli FDA H(at Ct 2 E w avrceavac% eaceeerD(Tvr. L pvvccd) r/ T &4 tevwt CTIC ll etc'sat(I av Kaof sk'CN(Y C CPX Ct9(HI SETO at'5 vM -Cf(.429(W) 411 etttg 'B ~ Et CP 41'9 cr PVF(tar.oa.v C(eel(5'd t(C>>COSH C I 419 <5.00O G Ptl CTR 4 15 ts atc tee TR 0.3)Y FOR ateSC tetaIC AT ~ ((4199 Cf If(st ) 419 C(wtlaw 'TA 1 rite(Is 5(( (5 TQ REAGTO() C(X)LANT foe v. (w w'(al ~SC CSX LSX (c(aaeaf a cell ~ SYSTE M. SEE DIPG.5 5 43, al 9 Ceaeaeaa 40( ~ f'fll4't Nal Ceaaaa 4ccc(t 4D Ncfa, )N4 Ja DP w lraavca CoeIM'5 Pole DCKAT f'lieT XJ ZO la '5 tvfVTM cvav S(t ref(-4 Dtt FROIl CONPONKNT EFCHAMGKR 'tf ('e'ceca.oaeavt CMO 419 cooLINGi HEAT h (51F&55u i K, 'E gt 8 C Cet aa 6C CNO 429(fit XJ 20 I CC'tl('( Ea(eaoafal) CCat lai c ( 1 )~t VCMT w ~ccwltew ~C(ret4f Ill CC, C Ia . 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Sf E 7(.loGPM /IG feaavep SEPARATE VALVE IDENtlFICATI(71 L.GD')' TSGPtt~ IC LIST I'DR EDINVALffftDESICN (accfcl NvaadcRs Mvce SAoclv aettccveoea (ltccee4ocvacvv cceovavc eeaert Peawc ~ CCA4 E ta hVNOERS tte(SPIED I'OR ~ e pveae ccL Soatrea e cafe c ceatvaaceas (ec <5) ~ CCCTCH(ea aaCA.DCO. vet GIO GPII DRAeftec Vif A5 FOLLOWS: <<WE, cw)G 2 SISS f/6 tao Na I 2 Nsea'los w CCwl!51 ZSZgCCACSS '8 APPEARS a5'SWOSW Isla e~ CD CPM C(ve1liw~ 3 ee 3 Xfeeitwvvfwt R00T vacvf NARK ~~ NYS feet SHOWN DN DRAWING(S(f Creel 1 3 3q VALVE IDENfetlcatcoec Ust) T(S AND FROM CENTRIFUGAL CCwldaw DERIVED BY ADOCNC to CHARGING PUMP 'W INSIRVCICNT Nvrdc R ]t)(' ~ 41) CT)WZI(N) If)I, ~ (we (Z w~ aeaaaava Ireevwew ~ vore I f oca THKAaea oeoeetc. CD BC'0, SCCRRta feet SINGLE ArlLEvt FDR Dcaltcf dcafsf 'apstRR(fwt I CFA - 0 CFA-423 G) I 41 CF KFO.423(S fea re(aefeaw Slafvi 5(l a C(wl'llf C(riser 3 41 ( P.P -101 t(wlewc ale(co toa tref eeet' l Cft0949 'lf tf 8'f Vf.t(DORT Cll C wl94M 3D jtvat I C(radar CCWldt W CFA tt(w) ccrc ac I CCwedtt 'VO'P)(~ FDR REVISOR DESCRTPTKW Sff C(wllor f 5 GPM "SfRVIAIC REVISOR RECORD FDR ttds DRAWJIO CCNIDO(v ~ all( C(waar C(rldlt 5 GPM~ CCW17CS ((weDCN C(v Tls 6 CCeecllr OIL TI llv vvw 4 ev wwww ar er awwae faweat ewee ewwe Crr. av 4 aawe ava - C(endlW (2) MECHANICAL IS GPM .APERTUBE . ~ evvaw avf v 4 ve ee N arveaaev ea carve, r w we et ev wrew awrv cr ev r Awww eeev wr ea tvvea wracerevavw to et ccawa crv tea SEAL NEAT K.XCNANGERS a CARD- ~ ea aae ewvaa eteeww4 W evr vewaw, vv 4 ev w eaeeww vve eaaeeec 'K. 4 )4 ~ Ss) C(ASS) EL SST(O IN(NACA ~ SCICHIDatf (LECTIVC CCX DOt(ALD C. COOK- . GEAR.OIL (2) CENTR(FUGAL STARING OIL ,(2) SAFETY (NJECTION )CVC(EAIIt(ANf COOLER '(IO GI'MS CHARGING PUMPS COOLER. (20 GP(f) PVSIPS 2Q 2 IO GPM ~80 Ava)(Iable Oa rWI), / )I C(evlet>> -Cf( 429(W) Apexfare FL'OW DIAGRAM TZ) ll(CHANICALSEAL 'f(.4(5(vt) CCTCIOt( CL SNC(4155 C Caela COh(PONENT COOLING )IEAT'XCNANGERS TO ( fRO Ill ( FRDH UN(t NR 2 ~ f r 5 Grvl TO ( IO GPN) w PVI(P CF) " 'W fataap F3 (SS OA55) 415 I SEAL VIAnR tOAND C ofc ff(x 2-5 ( 3 5 A -30 KAK3T(KT(RTD L . fROII CONIAINM(NT ~C KftOSS JT)(KP)It(P PUMPS. SKE ~ ~ 2'PRAY ~E3Dat(e Jl(s.xj) KN/9 Ea owG-5<<<.t(ft ((/) E t fd 4;7;~ t COC f ~ aaAA f.rs c(wtoef ~ CCwt20 4 C HC5 DWG MADf I CICOV f cail( fl STS~ foR vvet'l svg svtacs(CKS ~ aa ~ t2) RKSIDVAL N(AT Rf lcDYAL PVVJ (2) COIITAIHllEMtSPRAY PUMP DWG I-E.ACSSA RFV 16 wee a ) ei CCKCHCTMICAL SEAL HKlT EXCHAI{G'KRS VK(HANICALSEAL NEAT EXCHANG'KR'S aa(focal otctaec tor(R f(wf4( coat. 1 aaoaewaf atw l(voc C . D 'R r .J .....8+t+.0.,$ 130 3'7 ~ I O~ 1 -r N .)1....... 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Pass'4' HI COX Hl Cl'X Nl ~~ COOUHG SVDPLY pASS 'tr ~ EEvsgl ~ GEEEW ~ hr awttc I avxt 4 ar Ttht CCVIOht CCW Tshc fr(HT DISC'lc 10 SLOOR XCL r ccwtll K 'K-53355 635'-0'PX SASS'4 PASS A 510 50'1 511 PASS 5043 5lt COMPONENT COOLING RETURN AUXILIARYPIPING ICWESWE ~~ TYPICAL EEEerEE CCSI-Z (CAST SIDE) Sts CSH.4(WEST Slot)SGS 1 PA'SS E4 c< CCEE 2tht CCwt)'I'4 COE 504 5 PASS'A'ASS h'CW 55 2 CCWIOS 10 AHD FROM PEt4ETRATIOH COOLING SVPPIY 604( 0'KC-S 513 524 514 Sld 515 5 IS 523 546 5$ 0 554 FOR VALVE, INSTRUMF.NT SAMPLD40 PIPE MATERIAL AND OTNKR SYMBOLS NOT KXPLAIMED ON THIS OWG EXTER14AL SEK DETAIL 'M 11EAOER SK 536 5t'I 5td AND FOR MARK NUMBER PIPE COIL Cox CPX I f h THIS OWC Njd 531 53t CO'O'ES, SKK DWG. 5104 Q KJ'M.i 534 536 I TO K FROM PKMKTRATS)H cr 0'1'1 531 53$ 535 539 540 PKHKTRATKX4 COOUHG COII 5 ARE SEISUHC CLASS I COOUHG COIL 16 COOLTHC SVPPLY HEADERS l (Crt IO l SEK THIS DWG AIB, Fld. MAIN STEAM PFNETRATION CPN.66 A PASSsd $ 54 541 '551 555 '5t 546 556 ~NO =I SEE OETAII. 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ML17334B150

Contents

Text

SUMMARY

= NOTE 3 =-

ASttE SECTION-Xl

SUMMARY

SUMMARY

. R. =

REQUIRED TEST PERFORMED

SUMMARY

=-- SAFETY ICD TYPE COORDI- OPER. ---FUNCT- ICL

-==-- ET-024 ET-024 -

------- TYPE-COORDII POHER OPER-

P HO-NO EF"7 P NO ETF-002 FTF"002 P NO SLT-1 SLT-2 R YES> NOTE 1 2-ECR-496 0 GL 0.5 A H/8 C 2 P EF-1 Ef-1 NO EF-5 =- =- EF-5

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ML17334B150

Text

SUMMARY

= NOTE 3 =-

ASttE SECTION-Xl

SUMMARY

SUMMARY

. R. =

REQUIRED TEST PERFORMED

SUMMARY

=-- SAFETY ICD TYPE COORDI- OPER. ---FUNCT- ICL

-==-- ET-024 ET-024 -

------- TYPE-COORDII POHER OPER-

P HO-NO EF"7 P NO ETF-002 FTF"002 P NO SLT-1 SLT-2 R YES> NOTE 1 2-ECR-496 0 GL 0.5 A H/8 C 2 P EF-1 Ef-1 NO EF-5 =- =- EF-5

FLSI-DIAGRAN:=-12-5136 -

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