ML17334B150: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter: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
{{#Wiki_filter: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
-(FIGURE-1)2.LIST OF DRAWINGS-(FIGURE-2)3.NOMENCLATURE FOR TEST METHODS-(FIGURE-3)4.RELIEF REQUEST NOTES 5.ATTACHMENT-A 6~VALVE  
: 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==
==SUMMARY==
SHEETS 7.FLOW DIAGRAMS~-87-l01,30278.
SHEETS
87l005~PDR.-ADOCN,'05000315 P PDR~Page 1 of 7p ASME SECTION XI VALVE TEST PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D.C.COOK NUCLEAR PONER STATION UNIT NO.2 Revision No: 2 Date: 8-31-87 1.Valve Testin Pro ram INTRODUCTION Figure-1 A.The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the 1983 edition of the ASME Boiler and Pressure Vessel Code through Summer 1983 Addenda, except for specific relief requests which are identified in the Valve Summary Sheet.B.The valve test program is applicable for the second 10 year inspection interval which commences on July 1, 1986.C.The valve test program was developed employing the classification guidelines contained in 10 CFR 50.2(v)for Quality Group A and Regulatory Guide 1.26, Revision 3 for Quality Groups B and C.(Quality Group A is the same as ASME Class 1, Group B is 2, and Group C is 3).NRC staff guidance was provided by memorandum dated January 16, 1978.D.Figure 2 identifies the systems flow diagrams which were used to develop this valve test program.Valve Summary Sheets contain the following:
: 7. FLOW DIAGRAMS
Y t il.,*(e.g., 2-5105B-42)
      ~ l01,30278. 87l005~
*Valve Number: Unique valve number (e.g., 2-DCR-310)
PDR .- ADOCN,'05000315 P                 PDR~
*Revision Number: Any change of valve description, function or test requirement.
Page 1 of 7p
Page 2 of 70 Revision No: 2 Date: 8-31-87 D.C.Cook Nuclear Plan Valve Test Program Figure-1 h 1 REL-Relief and Safety CK-Check BF-Butterfly GA-Gate GL-Globe DA-Diaphragm 3W-Three-Way ND-Needle AG-Angle BL-Ball VB-Vacuum Breaker (Reverse Check Valve)*Valve Size: Nominal valve size in inches*Valve.Actuator T e: Type of actuator, one of the following:
SA-Self Actuated (e.g., CK or REL)MO-Motor Operated A-Air Operated M-Manual PO-Pneumatic SO-Solenoid Operated*Flow Dia ram Coordinates:
Alpha/Numeric grid location of valve*Valve osition during normal plant operation or during performance of its safety function, one of the following:
0-Open C-Closed 0/C-Open/Closed or vice versa*Code Class: ASME Code class of valve, either 1, 2, or 3 Page 3 of 70 D.C.Cook Nuclear Plant Valve Test Program Revision No: 2 Date: 8-31-87 Figure-1*Valve Status-A P: Active or passive'P V defined in INV-2200 NOTE: Combinations are possible (e.g., AC)*Prima Test Re'd: Test required per Section XI*Test Performed:
Testing that will be performed NOTE: Test nomenclature is explained in Figure 3*Test Mode: One of the following:
P-Power Operation (Every 3 months when unit is at power)C-Cold Shutdown (Testing will be performed at cold shutdown frequency)
See Note"F" R-Refueling (Testing will be performed at refueling outage frequency)
*Code Relief: Whether or not a code relief is being requestedl will be one of the following:
NO NO, NOTE X comments YES, NOTE Y proposed in code relief-Valve is to be tested per code, no comments-Valve is to be tested per code, but there are Code relief is requested.
Alternate testing is lieu of that required by code, the note explains why the is requested.
E.Alternative testing is to be performed on a check valve as indicated under relief request notes in lieu of stroke.testing required by Section XI, IWV-3521.It is accomplished by disassembly or radiography method as explained below: Page 4 of 70 D.C.Cook Nuclear Plan Valve Test Program Revision No: 2 Figure-1 Date: 8-31-87 a.Disassembl Method The valve bonnet is removed, the disc is manually full-stroke exercised, and the valve internals are visually inspected.
The results of this test are documented.
b.Radio ra h Method This method is used as an alternative testing method to determine the disc position under no flow or reverse flow conditions (i.e., valve seated).This, in conjunction with the full forward flow testing of the valve, can provide assurance that the disc was free to move from full-open position with the forward flow to the closed position with no flow or reverse flow conditions.
The results of this test are documented.
The valve grouping for sample disassembly or radiography under alternative testing is done based on the following criteria: 1.2~3.4~5.etc.)valve type and design similarities system design, flow, and service conditions frequency of valve operation manufacturer size range (i.e.up to 2", 2-1/2" to 4", 4" and 6" 6" and 8" The alternative testing to be performed for a particular valve is indicated on the valve summary sheets and relief request notes.This will be accomplished by selecting one representative valve from each group of valves during refueling outages.If the inspection results are unacceptable, all the valves in that group will be inspected.
Page 5 of 70


Revision No: 2 Date: 8-31-87 D.C.Cook.Nuclear Plan Valve Test Program Figure-1 F.Conditions for Valve Testing During.Cold Shutdowns Cold shutdown testing of valves identified in the IST Program.is acceptable when the following conditions are met: 1.Valve exercising need not be done more often than once every 3 months in case of frequent cold shutdowns.
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
2.The testing shall commence as soon as the cold shutdown condition is achieved, but not later than 48 hours 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 hours commencement of testing is allowed.G.The following criteria have been used in developing limiting values of full-stroke time for the power operated valves: 0 0 Review of valve's design specification and/or manufacturer's test stroke times Review of system response time requirements (Technical Specification, FSAR, etc.)Valve's historical stroke time values at various system conditions Page 6 of 70 Revision No: 2 D.C.Cook Nuclear Plan Valve Test Program Figure-1 Date: 8-31-87 Using the above criteria, the limiting stroke time for each valve is derived as follows: 1.Valve Stroke Time<2 Seconds Historical Stroke Time Ran e-in Seconds Established Base Line on Curves in Seconds Recommended Action Time (Limiting Stroke Time Values in Seconds up to.74.75 to 1.24 1.24 to 1.74 1.75 to 2.49 0.5 1.0 1.5 2'Based Line Time x 2+1 Second=Recommended Action Time or Tech.Spec.Limit, whichever is less...5 x 2+1=2 Seconds=1 x 2+1=3 Seconds=1.5 x 2+1=4 Seconds=2 x 2+1=5 Seconds 2.Valve Stroke Time-2.5 to 10.49 Seconds 2.5 to 10.49 3 to 10 Base Line Time x 1.5=Action Time Page 7 of 70 Revision No: 2 Date: 8-31-87 D.C.Cook Nuclear Plant.Valve Test Program Figure-1 3.Valve Stroke Time-10.5 Seconds and U 10.5 and Up 11.0 and Up Base Line Time x 1.25=Action Time (or 15 seconds, whichever is larger)H.Code relief is requested for timing tolerance and trending per paragraphs IWV-3413(b) and IWV-3417(a) for fast acting valves (those with the maximum limiting stroke times of five seconds or less, determined from historical stroke time values and/or valve design specification).
: 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.
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.
B. The   valve test program is applicable for the second    10 year inspection interval which commences on July 1, 1986.
The fast acting valves have been identified as"ETF" and acceptance criteria has been defined in the program.Page 8 of 70 0
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.
DONALD C.COOK NUCLEAR P Revision No: 2 Date: 8-31-87 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS Figure 2 NO.SYSTEM Main Steam Steam Generating System Feedwater Feedwater (Auxiliary)
(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.
Essential Service Water Non-Essential Service Water Station Drainage Containment Reactor Coolant Reactor Coolant FLOW DIAGRAM NO.2-5105B 2-5105D 2-5106 2-5106A 2-5113 2-5114A 2-5124 2-5128 2-5128A REVISION 42 2 34 41 36 27 20 19 34 CVCS-Reactor Letdown&Charging Component Cooling Component Cooling Component Cooling Nuclear Sampling Nuclear Sampling Post Accident Sampling-Containment Hydrogen Emergency Core Cooling (SIS)2-5129 2-5129A 2-5135 2-5135A 2-5135B 2-5141 2-5141A 2-5141D 2-5142 32 20 34 30 14 27 30 28 Page 9 of 70 Revision No: 2 Date: 8-31-87 DONALD C.COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT-2 LIST OF DRAWINGS Figure 2 SYSTEM Emergency Core Cooling (RHR)Containment Spray Containment Penetration
D. Figure   2 identifies the   systems flow diagrams which were used    to develop    this valve test  program.
&Weld Channel Pressurization Ice Condenser Refrigeration Containment Ventilation Control Room Ventilation Emergency Diesel Generator Emergency Diesel Generator Emergency Diesel Generator Emergency Diesel Generator FLOW DIAGRAM NO~2-5143 2-5144 2-5145 2-5146B 2-5147A 2-5149 2-5151A 2-5151B 2-5151C 2-5151D REVISION NO.35 29 20 23 35 23 26 27 26 27 Make-Up Water&Primary Water System Compressed Air System CVCS-Boron Makeup Spent Fuel Pit Cooling&Clean-Up WDS Vents&Drains Post Accident Liquid&Gas Sampling Post Accident Liquid Sampling Inst.Panels 12-5115A 12-5120B 12-5131 12-5136 12-5137A 12-5141C 12-5141F 41 22 19 25 21 8 6 Page 10 of 70 Revision No: 2 Date: 8-31-87 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI 1 CATEGORY A-B VALVES Figure 3 ASME CODE SECTION XI PARAGRAPH EF-1 EF-2 Exercise valve (full stroke)for operability every 3 months.(IWV-3411)
Valve Summary Sheets contain the following:
Exercise valve (full stroke)for operability at a cold shutdown (Code Relief or refueling outage frequency as indicated.
Y      t il.,
Code relief requests are Requested) provided in the flow diagram notes.EF-3 EF-4 Exercise valve (part stroke)for operability during operation; Exercise (full stroke)at a cold shutdown or refueling outage frequency as indicated.
(e.g., 2-5105B-42)
Justification for exercising the valve during cold shutdowns is provided in the flow diagram notes.Code relief request is provided if full stroke test is deferred to coincide with refueling outages.Exercise valve (full stroke)for operability prior to return to'service (IWV-3412)(IWV-3416)
* Valve Number: Unique valve number (e.g., 2-DCR-310)
EF-5 Valves with remote position indicator shall-be observed at least once every 2 years to verify that valve operation is accurately indicated.(IWV-3300)
* Revision Number: Any change of valve description, function or           test requirement.
EF-6 EF-7 EF-8 ET-XXX ETF-YYY This note was intentionally deleted.Exercise valve (with fail-safe actuators) to observe failure mode every 3 months Exercise valve (with fail-safe actuators) to observe failure mode at a cold shutdown or refueling frequency, as indicated.
Page 2  of 70
Exercise valve-power operated (full stroke)and measure time.(E.G., ET-015 means recommended action stroke time is 15 seconds)Exercise valve-power operated (full stroke)and measure time for fast acting valves.Code relief is requested in Item H.(E.G., ETF-005 means recommended action stroke time is is 5 seconds)Page ll of 70 (IWV-3415)(IWV-3415)(IWV-3413&3417)(IWV-3413'&3417)
Revision No: 2 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Figure 3 Date: 8-31-87 2 CATEGORY C VALVES ASME CODE SECTION XI PARAGRAPH CF-1 Exercise valve (full stroke)for operability every 3 months.(IWV-3521)
CF-2 Exercise valve (full stroke)for operability at a cold shutdown or refueling outage frequency as indicated.
Code relief requests are provided in the flow diagram notes.(Code Relief Requested)
CF-3 Exercise valve partial stroke during plant operation and full stroke (IWV-3522) for operability at a cold shutdown or refueling outage frequency as indicated.
Justification for exercising valves during cold shutdown is provided in the flow diagram notes.Code relief requests are provided if full stroke testing id deferred.to coincide with refueling outages.CF-4 TF-1 Exercise valve (full stroke)for operability prior to return to service.Safety and relief valve tests (setpoint) to Section XI, Table IWV-3510-1.
(IWV-34 16)(IWV-3 5 10)SLT-1 SLT-2 3 CATEGORY A or AC VALVES Seat leakage test valve in accordance with requirements of paragraph IWV-3420 of ASME Code, Section XI, at refueling outage frequency but not less than once every two years.Permissible leakage values for each category A or AC valve are listed in Attachment
-~~A".Seat leakage test valve in accordance with 10CFR 50, Appendix J, in lieu of ASME Code Section XI except for paragraphs IWV-3426 and IWV-3427 which are applicable.
Permissible leakage values for each category A or AC valve are listed in Attachment-"A".
Page 12 of 70  


Revision No: 2 Date: 8-31-87 DONALD C.COOK NUCLEAR P NOMENCLATURE FOR TEST METHOD USED IN COLUMNS FOR PRIMARY TEST REQUIRED AND TEST PERFORMED UNDER ASME SECTION XI Figure 3 SLT-2A In lieu of the requirements of ASME Code Section XI, paragraphs IWV-3423 and IWV-3424, valves are seat leakage tested as part of the Appendix'Q" containment isolation test by imposing a static head of water on the downstream side of the valve and verifying that the leakage within the specified value of Attachment"A" for each category valve.This testing method demonstrates that the containment spray and RHR Check Valve leakage over 30 days is limited to the water resident in the containment spray headers downstream of the check valves.The leakage specified would not deplete the water inventory so as to expose these valves to a post-LOCA environment for a minimum of 30 days in the event that a spray system must be shut down and drained.This testing method is as stated in Response to Question 22.15(5)of the original FSAR Appendix"Q", Amendment 81, dated August 1978.Page 13 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5105D-2 Revision No: 2 Date: 8-31-87 NOTE 1: NOTE 2: FW-118-1 thru-4: The function of these valves is to provide feed-water flow from the main feedwater pumps to the steam generators.
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)
These valves cannot be exercised during power operation because closing of these valves would require securing feedwater flow to the steam generator and partial stroking may cause instability of steam generator water level which could result in reactor trip.Further three loop operation is not allowed per D.C.Cook Nuclear Plant Technical Specification 3.4.1.1.These valves will be confirmed closed by disassembly on a sampling basis during refueling outages.MRV 210-220-230 and-240: These steam generator stop valves cannot be full stroke exercised during power operation because this would require securing steam from a steam generator which could result in a reactor trip.Three loop operation is not allowed for D.C.Cook per Technical Specification 3.4.1.1.Valves MRV-211,-221,-231,-241,-212,-222,-232, and-242 which activate MRV-210,-220,-230, and-240 are tested quarterly in accordance with IHV-3410.MRV-210,-220,-230 and-240 are part stroke tested quarterly by use of external hydraulics and full stroke tested during hot standby (Mode 3)at cold shutdown frequency.
* Valve Size: Nominal valve size in inches
Page 14 of 70  
* 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


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.
D. C. Cook  Nuclear Plant Valve Test Program Revision No:     2                                                     Figure 1 Date:   8-31-87
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.
* Valve Status-A P:       Active or passive
The valve is not equipped with position indication.
                                        'P V defined in INV-2200 NOTE:   Combinations are possible (e.g., AC)
The valves will be verified closed by disassembly on a sampling basis at a refueling frequency.
* Prima      Test  Re  'd: Test required per Section XI
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.
* Test Performed: Testing that will be performed NOTE:  Test nomenclature    is explained in Figure 3
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.
* Test Mode:      One  of the following:
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.
P  Power    Operation (Every  3 months  when  unit is at   power)
In addition, these valves are full stroke tested with flow rate of 900 GPM at a refueling outage frequency.
C  Cold Shutdown (Testing    will be performed at cold shutdown frequency) See Note "F" R  Refueling    (Testing  will be performed at refueling outage frequency)
Page 17 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5106A-41 Revision No: 2 Date: 8-31-87 NOTE 3: FW-138-1-2-3-4: These auxiliary feedwater (AFW)check valves function to supply AFW to the steam generators whenever the AFW System is caused to operate.These check valves cannot be full or partial stroke exercised during power operation without energizing the AFW System and delivering cold water to the steam generators.
* Code Relief:          Whether or not a code relief is being requestedl will be one of the following:
This would result in thermal shock to the steam generator nozzles.The valves will be verified closed quarterly by monitoring temperature of Auxiliary Feed Line as required by the plant procedure during shift inspection tours.These valves are full stroke exercised when the plant is returned to power after cold shutdown.NOTE 4: NOTE 5: FW-149 and 150: The required full stroking of these check valves is satisfied when Turbine Driven Auxiliary Feedpump completes its required testing.FW-153 and 160: These check valves installed on the Emergency Leak Off (ELO)lines open when the Motor Driven Auxiliary Feedwater Pumps (MDAFP)start.This can be established when the MDAFP pump is operating through the test line.A pressure decrease in the pump discharge line is verified by a local pressure indicator when the parallel path ELO is opened.The pressure decrease indicates that flow is established through the ELO line and that the check valve is opened.Page 18 of 70 I
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


DONALD C.COOK NUCLEAR T VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5113-36 Revision No" 2 Date: 8-31-87 NOTE 1: ESW-141-142-143-144: These valves will be disassembled and inspected internally per procedure no.12MHP-5021.032.00ZL during every refueling outage.NOTE 2: NOTE 3 ESW-145-240-243: These valves are normally closed and are required to be open when the condensate storage tank is exhausted.
D. C. Cook  Nuclear Plan Valve Test Program Revision No:     2                                                     Figure 1 Date:     8-31-87
Exercising the valves could cause lake water contamination of the steam generators.
: 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.
Lake water chemistry can potentially impact steam generator tube integrity.
: 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.
We believe that testing at a refueling outage frequency is sufficient to demonstrate operability of this long term valve.The valves will be full stroke tested during refueling outages.Since the valves are manual, stroke timing is not required.I WRV-722-724-726-728: These valves are located in the essential service water supply lines to the emergency diesel generators air after coolers.These three-way valves regulate water flow to maintain the temperature at which the after cooler air discharge thermostatic controller has been set.Water flow is regulated by passing a portion of the flow through the air coolers and bypassing the excess flow around the air after coolers.We are requesting code relief from the testing requirements since (1), these valves function only as regulating valves and not open/closed valves (2), these valves are demonstrated operable during diesel generator testing.Diesel generators are tested on a staggered basis, every 31 days per Technical Specification 4.8.1.1.2; and (3), these valves are demonstrated operable during diesel generator 24 hour 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.
The   valve grouping for sample disassembly or radiography under alternative testing is     done based on the following criteria:
There is no external control available.
: 1. valve type and design similarities 2 ~    system design, flow, and service conditions
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<<
: 3. frequency of valve operation 4 ~    manufacturer
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.
: 5. size range (i.e. up to 2", 2-1/2" to 4", 4" and 6" 6" and 8" etc.)
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   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.
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.
Page 5  of 70
Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed during each refueling outage by performing a flow test through each valve because the valve stem is completely enclosed and cannot be observed.The reactor coolant discharged during the flow testing of the valves is collected in a container to minimize liquid contamination spill, radiation, and potential airborne situation in deference of ALARA consideration and personnel protection.
The above tests are consistent with Technical Specification requirements.
Page 22 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 2 Date: 8-31-87 NOTE 1: NOTE 2: NOTE 3 NOTE 4: NOTE 5: CS-442-1 thru 4: These containment isolation check valves are on the seal water supply line to the RC pumps.These valves cannot be part or full stroke exercised to the closed position during power operation because cooling flow is required to the RCP seals.During cold shutdown, seal water must be maintained to prevent backflow through the seals with possible damage from dirt.The valves will be full stroke exercised at refueling outage frequency.
See Attachment-"A" for permissible seat leakage values.NRV-151-152-153: These pressurizer power operated relief valves are normally closed during power operation (passive valves).The system is considered out of service (as defined per INV-3416)during power operation.
The valves will be full stroke exercised prior to placing them into service for RCS cold overpressurization protection.
PN-275: This containment isolation check valve is located in the primary water supply line to the pressurizer relief tank.The valve is not equipped with position indication.
The valve cannot be full stroke tested to closed position during power operation or at a cold shutdown frequency due to lack of sufficient differential pressure to back seat the valve.The valve and necessary test connections are located inside the containment.
Due to the plant design, the only method available to verify the valve closure is leak testing.The valve will be verified closed during seat leakage testing per Appendix"J" program at refueling frequency.
N-159: This containment isolation check valve is located in the nitrogen supply line to the pressurizer relief tank.The valve is not equipped with position indication.
The valve cannot be full stroke tested to closed position during power operation or at a cold shutdown frequency due to lack of sufficient differential pressure to back seat the valve.The valve and necessary test connections are located inside the containment.
Due to the plant design, the only method available to verify the valve closure is leak testing.The valve will be verified closed during seat leakage testing per Appendix"J" program at refueling frequency.
Page 23 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 2 Date: 8-31-87 NOTE 6: NOTE 7 NSO"061-062-063-064: These four one-inch operated isolation valves are installed (two in each leg in series)in the pressurizer vent.These valves cannot be tested during power operation, hot standby, or hot shutdown because the valve design is such that testing of either valve can cause"burping" (momentary opening)of the second valve resulting in the release of radioactive fluid and create an airborne situation in containment.
The valves also cannot be tested during cold shutdown unless RCS is operating at half loop, because testing of these valves can create a similar situation as that described above.Since half loop operation of the RCS is not a normal evolution during cold shutdowns, full stroke test for these valves will be scheduled at refueling frecpxency.
Exercising the solenoid operated valves for verification of valve position (valve stem movement)will be performed during each refueling outage by performing a flow test through each valve because the valve stem is completely enclosed and cannot be observed.The reactor coolant discharged during flow testing of the valves is collected in a container to minimize contaminated liquid spill, radiation, and potential airborne situation in deference of ALARA consideration and personnel protection.
The above tests are consistent with Technical Specification requirements.
SI-189: This check valve is located in the safety valves discharge (Emergency Core Cooling SVs, RHR, SVs, centrifugal charging pump SVs, etc.)collection header leading to the pressurizer relief tank.Isolating this valve for testing would result in dead heading all safety valves in the above systems.This would result in loss of overpressurization protection and could put the plant in an unsafe condition.
Test will be run at a refueling frequency when there is not potential for overpressurization.
Page 24 of 70  


&0 Vl OI 0~W 0 4 W A 4,H O A I~~0 Q nI nI pl A CV~~g)0 I I 0 co~8 N 0~~g Ql 8 nI C4 A~0 OA>0 H Q 0 SA 8~+8 A 8 t0 A NOg ld>>g&SgO WWNnI Nnl&~rl A ldQSMN g>SAHg ONA 0 nI NN Hww NN N 4 td td%td-H NNtdgO&5~O'tI N 8 A nI N 8 N NQAAP RAeg 0 A't5 8 8 0 5&I'd 0 Q N Ql 54 8.rl Ul~4~A Q 0 8 4'tI 8~0.8 8 NgNNO 8 0 f40&8~A 5 nI 8 k.R f4&g f40440>N'd 0 nI Q 0 54 R.H g 8 8 54 tP 0 Ul I4 t0 A 8 M I4$big+0 0&f44 I4A 0 H'tI~P I4 0 8~H 4.rl R nI 0 rl't5 8 4't5~8 8~nI 0 8 8 8 gA 4 8 g 4&8 Q M M SN SAWQOI4 P-H 4 4&nI td w 0 Q 0 OMS~00 0 SAS 8 N'tf N A~8 A 8.R<H 0 N.R~SA.RN 8 WN gNP SW 0 8 td N g nI N~R g 0 0 P&.rl.H 4%4-H4 Q g 4888 td td 8 0 f4 4't5 8 A 0 A>8 H'd 0 8 g>N 4l N AO>0+ANN&8 OnINS>0 08>0 areal 8 ow H A&040 08&&0 0 0 4'tI+A.R 8 8<H 0&A 4 Mw 8 0~4't5 A S-R.H AAwse~o&P Ul&nI I4 4 8 g 0 0 0 HQ SNI4~$5 Qg>8~g 8~b 8 8 0W't5%NO A SWN'R nI Ql OH%N4A gN>8 N g&W nlgnI AQ 8 nl NgNN 5 SAM g 0'tH 0 0 A~4 A 0~R.R g ep spA 8'tI4g Old M nial 4genINOSAWAA A.rl>0-8 n$N 0 0 4 4~H g Ql&0 0 8't5 0 SW 5 QW M CA OPcP~N nI 0 Ql't5~SAW ARK&0 N 8 0 g4td 8~4 egg gA 0 ON 0 g4-rt Id-8 g A ON 4 g nI-H rd 8 0 M H 0 0'tI gN N'5 N~H 40 0 f4 5 N I4 gQOH SQQ~g tPI4&H 8 8&N 0 0 Q g 0 nI Sdgee 4A 84%A Idee WA~>g 0 td-rl-rl~He&#xc3;e A 0 tPQl M~g 8 N 0 N 0 848 8 4 tP 8 W QA 4 X nI 8&td 8~N n5~MI4 8 NN NA.rl N N g 0.rl nI 4~rE Q A N 0 nIA NW Ul 8 W 0540-8 0 44$OAA 8 Ql Ol F4 I 8 nI'dN 0 g 0 rd4N I4 8 W W 0~N nI 8 N Aee M W 8 nI A 0>H 5 54 0 0<H td&0 08~q5 SA Sg A&84rd N N 0~NW~RH884 N 4 Ql AenIEC SNOenI OVA08~0 N 8 q5 8~8 0~0 N M Q 8 8'tH g 0~Stdgh Q 4N tPWROHO$$4 0 W f4 5't5 X tP AN Q&Sld g~r4 0 Q~XA$85 N 8-a~nI N 4A 0 Q 0 0'550~.N5&SWtd&g Ql M M g~0 54 N.R As leos I f4%Ql f4Q OA~Q 4 5 5'tf 0&8 td&0 N f4 td~&I4$td'5&SN'5 5 8 8 g g N 0 g OA&4J 0.8.8 g td&g nI.R tp 0 g OQAWtd~n$+4.00tde08 4 8 WN OSMIUM N<H g4M 5 M'5 Ql ealHMnlale
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:
~M 4A 5 8 0~M r I f45 0 f44 nI H M 4 I4<nl 0 55M>&I4 Ql N g W 5 8 A 4 I.RWOSX 0 tP I4W tP 5 0 A 8 Ql g rl H<H A.+55td'5 8 0%OMAN 8 A 0 nI 4~0 Ql nI 8 MA SA 8 4 5 ON 8 0 A A 0 O'A N NNNN Ql>0 04&&8 nI't5&OgNS 8 pl N N~IPI 0 I 8 Q A 0 8 8 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 2 Date: 8-31-87 NOTE 4: NOTE 5: NOTE 6: CS-321: This containment isolation check valve's function is to supply borated water from the volume control tank to the regenera-tive heat exchanger through the charging pumps for chemical shim.control and reactor coolant system makeup.Isolation of this system would result in loss of control of pressurizer level which could result in reactor trip.This valve is tested in the open direction quarterly and confirmed closed during refueling outages in deference to ALARA consideration.
: 1. Valve exercising need not be done more often than once every    3 months  in   case  of frequent cold shutdowns.
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.
: 2. The testing shall commence as soon as the cold shutdown condition is achieved, but not later than 48 hours after shutdown, and continue until complete or the plant is ready to return to power.
The valves will be full stroke exercised to open position quarterly.
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.
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.
I
Page 26 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 2 Date: 8-31-87 NOTE 8: NOTE 9: QRV-200: This control valve is required for emergency boration in Modes 5 and 6.The valve is normally open to permit.charging.The valve cannot be full stroke tested during power operation because it would interrupt charging flow which could effect pressurizer level.The valve will be part stroke exercised during power operation and will be full stroke exercised at cold shutdown frequency.
: 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 hours commencement of testing is allowed.
The valve cannot be"fail safe" tested nor stroke timed since position indication is not provided.QRV-251: This control valve is required for emergency.boration in Modes 5 and 6.The valve is normally open to permit charging flow when the centrifugal charging pumps are running.The valve cannot be.full stroke tested during power operation because it would interrupt both charging and seal water flow which could effect the pressurizer level and damage the reactor coolant pump seals.The valve will be part stroke exercised during power operation and full stroke exercised at cold shutdown frequency.
G.      The following criteria have been used in developing limiting values of full-stroke time for the power operated valves:
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.
Review of valve's design specification and/or manufacturer's test stroke times 0      Review of system response time requirements (Technical Specification, FSAR, etc.)
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.
0      Valve's historical stroke time values at various system conditions Page 6  of 70
NOTE 2: See"Attachment-A>>
for permissible seat leakage values.NOTE 3: QMO-451-452: These motor-operated gate valves function as volume control tank isolation valves.Exercising these valves during power operation could result in a loss of pressurizer level control which could cause a reactor trip.These valves are full stroke exercised at cold shutdown frequency.
Page 28 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 2 Date: 8-31-87 NOTE 1: CCM-451-452-453-454-458 and-459: These valves cannot be tested during power operation without securing cooling water to the RC pump.Isolation of these valves could cause failure of the RCP.Valves to be tested at cold shutdown frequency.
NOTE 2: See"Attachment-A" for permissible seat leakage values.NOTE 3: NOTE 4: NOTE 5: CCR-455-456 and-457: These valves cannot be tested during power operation without securing cooling water to reactor the support coolers.These valves must remain open to prevent overheating of the concrete around the reactor supports during the normal opera-tion.Valves to be tested at a cold shutdown frequency.
CCW-135: This check valve cannot be tested during power operation without securing cooling water to the reactor support coolers.The valve must remain open to prevent overheating of the concrete around the reactor supports during the normal operation.
The valve will be verified closed by seat leakage testing during refueling outages.CRV-470: This air-operated valve is located in the Component Cooling Water (CCW)return from the letdown heat exchanger and controls the temperature of the letdown flow leaving the heat exchanger.
The position of this valve is set by QTC-302.The valve cannot be"fail-safe" tested nor stroke timed since no control switches are installed to perform those tests.The valve will be full stroke exercised quarterly.
Page 29 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135A-30 Revision No: 2 Date: 8-31-87 NOTE 1: CMO-411-412-413-414-415&-416: These valves remain open during initial safety injection, but may be closed during recirculation phase or passive failure.Therefore, the valve time will be recorded from open to close position.Page 30 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135B-14 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.NOTE 2: CCW-243-25 CCW-243-72 CCW-244-25 and CCW-244-72:
These check valves are located in the penetration cooling supply headers of the CCW System inside the containment.
The valves are open during power operation and cold shutdown to provide cooling water to the main steam penetrations.
These valves are not equipped with position indication.
The valves are confirmed closed by seat leakage testing in accordance with Appendix"J" during refueling outage.Page 31 of 70  


DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141-27 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.Page 32 of 70 DONALD C.COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5141D-8 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A" for permissible seat leakage values.NOTE 2: NS-283: This containment isolation check valve is located in the sample return line of the Post-Accident Containment Hydrogen Monitoring System.The valve cannot be full stroke exercised to closed position quarterly or at a cold shutdown frequency because: 1)due to the plant design (line is open ended in the containment), the only method available to verify the valve closure is leak testing, and 2)check valve is not equipped with position indication.
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:
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.
: 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..
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.
up to .74                    0.5                      .5 x 2 + 1 = 2 Seconds
NOTE 2: See"Attachment-A" for permissible seat l'eakage values.NOTE 3: NOTE 4: NOTE 5: IMO-261: This valve cannot be tested when SI pumps are required to be operable.Testing would result in isolation of both pumps.This valve will be tested at cold shutdown frequency.
.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
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.
: 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 hour 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
 
                                              >OA0H                        0 N
8                          q5
                                  ~ H          SA Q8        8
                                                                    ~
A8
                                                                      +
8 0 ~            0 8
                              & g0
                                                                                  ~                            N Ql 0 8't5 t0 ld>>g& Nnl&  A      NOg SgO                  M Q 8 8      'tH  g      0 ~
0 SW 5 WWNnI
                                              ~ rl A Stdgh tPWROHOQ 4N QW M CA OPcP~N ldQSMN ONA g>SAHg                                  4 0 AN W f4    5  't5    X tP Sld nI 0 Ql 't5 0 nI NN Hww NN N    4 td td% td-H            0 g  ~ Q&
Q~XA$    r4 85 SAW NNtdgO&5                                        N    8-a~nI          N  4A    0 ARK&0 N 8
                            ~
O 'tI N 8 A nI N 8 N 0 NQAAP RAeg
                                          ~
                                                                                  '550        ~ . Q 0 0 0 A 't5 8 8 0 5 &I 'd 0                      N5&SWtd&g g4td 8 egg        ~ 4 gA 0 ON A Q 0 8 4'tI 8 ~0.84 Ql 54 Q N 8 .rl    Ul
                                                                      ~      8
                                                                                ~ AsM M leos Ql        g ~ 0 N.R    54 f4%
I Ql 0
                    -8 g g4-rt Id                        NgNNO 8 0 f40&
f4Q 5'tfOA~Q 0&        4 5 8 td&
A      ON 4 g 8 ~              A5    nI 8 k.R          f4&    0 N f4          td~&      I4$
nI-H rd 8 0 M H 'd 0 g  f40440>
nI    Q0    54  R.H N
g 8  '5 td
                                                                                            &SN'5 5 8 0    0'tI      gN 8            54 tP 0  Ul I4 A t0    8 M    8 g g N 0 g OA &
4J 0.8.8 g td &
N'5              I4$ bigH 'tI I4A .rl  0
                                                          + 0
                                                              ~ P I4  0& f44 0 8    nI.R tp 0 g g
H    40 N H4          R nI 0 rl                  OQAWtd ~n$ +4 8 8 .00tde08
                              ~          ~
0 f4 5 N I4                  't5 8 4        't5    ~
gQOH                        ~nI 0      8 8 8 gA 4                                4 8 WN SQQ~g tPI4&H 8 P-H 4 SAWQOI4 8 g 4& 8 Q M M SN N<H OSMIUM g4M 5 M'5 8 &N 0 0              OMS        4 & nI td w 0 Q 0
                                                              ~00 0                Ql
                                                                                    ~    M ealHMnlale 4A      5 8 0 ~ M          8 Sdgee Q    g 0      nI          SAS
                                              'tf N A 8        N      r  I  f45 H M 4 0 f44 I4<      0
                                                    .R~ SA8 A 8
                                                                        .R <H 0                                nl 84%            4A N .RN 8
                                                            ~
WN gNP SW 55M>&
nI I4 N g W 5 Ql                    8 pl N
A      Idee                                  0                A        4  I.RWOSX                N 0  &                WA~              >  g 8 td N g nI N~R g 0 td-rl-rl P&.rl.H 4%4-H4 Q g 0 0    0 tP I4W tP Ql g      rl    H<H 5 0A 8      ~ IPI 0
Vl OI
                    ~ He&#xc3;e                  td 4888 8 0 f4 4 't5 8 A 0 A td      A.+55td '5 8 0    %OMAN              8 A A 0 tPQl          > 8 H 'd 0 8 g > N 4l N                                  0 nI 4        0 0
~ W 4
M~ g 8 N AO ANN&8              >0+OnINS>            Ql nI      8 MA SA 8 4 5O'A
                                                                                                                ~
ON A  4,H W
848  0 N          0 0 8 4 8 ow H 08>0            areal        8 0    A NNNN  A Ql> 0        N    0 W QA 4 X 0 tP 8 A&040 08&&0  0 4 'tI + A.R 0        04&&
8 nI 't5&
nI 8 & td 8                8 8<H        0&A 4S-R.H    Mw            OgNS O                    ~NMI4 8 8 0 ~ 4 't5 A n5~
AAwse~o&P                                        8 nI 5
                                                                                        'dN 0 td 54 &0      0 0 <H A        I                                                                    Ul 08~ Sgq5            I NN
                    .rl N N g 0 NA      &        nI I4 4 8 g 0 HQ 0 0 SNI4 Ql g 0 Ol rd4N SA
                              .rl nI 4            ~    $ 5      Qg>8              F4      I4 8 A&84rd                8
                                            ~ g 8 ~ b 8 8 0W't5 %                  I  W                              Q
                        ~ rE Q A N NO A 0
SWN'R nI Ql OH% N4A gN > 8 N W  0~
N nI 0~
N N NW A 0 nIA NW g& W nlgnI SAM Ul 8 W 8 nl NgNN                      5 AQ          8  N
                                                                                                  ~ RH884  N 4
        ~~
0                0540
                        -8 0              g R.R 0 'tH 0 0 A~ 4 A 0 g ep spA AeeM AenIEC                Ql CV 44$              8'tI4g
                                              ~
4genINOSAWAA OAA 8 A.rl > 0-8 n$ N 0 0 4 4 Old M nial                    W  8 A
SNOenI            8 Q
nI
              ~~
0 g)
I                                                                      0 nI
                                                                                            >H      OVA08              8 nI      I pl  0  co  ~0                                                            ~0 A  ~ 8 N  0~
            ~ g  Ql 8  nI C4  A
 
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.
These valves will be full-stroke exercised at cold shutdown frequency.
SI-110N SI-110S and SI-101: Safety Injection (SI)pump discharge valves, SI-llON and-llOS, cannot be exercised during power operation because SI pumps cannot overcome reactor pressure.Therefore, no flow path exists and, because minimum flow lines branch off upstream of these valves, they cannot be part-stroke tested during pump testing.The common (SI pumps)suction check valve, SI-101 is part-stroke exercised at power operation during pump testing.These valves cannot be exercised during cold shut-downs because SI pumps are required to inoperable by Technical Specification 3.5.3 to protect against low temperature over-pressurization of the Reactor Coolant System.These valves will be full-stroke exercised at refueling frequency in conjunction with the full flow test.Page 34 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-28 Revision No: 2 Date: 8-31-87 NOTE 6: SI-142 Ll L2 L3 and L4: These check valves are located in the supply lines from the Boron Injection Tank to the reactor coolant cold legs (loop 1 through 4).These valves cannot be tested during power operation because this would require injecting highly concen-trated boric acid solution from the Boron Injection Tank into the Reactor Coolant System resulting in probable plant shutdown.These valves cannot be partially-stroke exercised using the BIT bypass line because this could result in bypassing the BIT, thereby not achieving design flow through the BIT if an accident occurred.These valves cannot be full-stroked exercised during cold shutdown because this would require injecting the BIT into the RCS which could significantly delay startup from cold shutdown condition (the BIT would have to be brought to the proper Boron concentration and the RCS would have to be diluted sufficiently to allow startup).These valves will be full stroke exercised during refueling outages.Page 35 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 1: See"Attachment-A>>
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.
for permissible seat leakage values.NOTE 2 NOTE 3: IMO-128 and ICM-129: These valves function as the normal return from the RCS to the RHR for heatup and cooldown.These valves are normally closed and cannot be operated during normal plant operation because they are interlocked to remain closed at RCS pressure above 450 psig.The valves will be full stroke exercised prior to placing them into service at a cold shutdown frequency.
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.
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 34 of 70
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.
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 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 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 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  
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 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).
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.
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.
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.
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.
NOTE 2: See    "Attachment-A"  for permissible seat leakage values.
Page 38 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGBAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-29 Revision No: 2 Date: 8-31-87 NOTE 10 NOTE 11: SI-151 E.W: These check valves are located in the RHR supply lines to either the hot or cold legs.These valves cannot be exercised during power operation because the RHR pumps do not develop sufficient head to overcome RCS pressure.These valves will be exercised at a cold shutdown frequency.
I Page 43 of  70
SI-152 N S: These check valves function to provide Safety Injection pump discharge to either the hot or cold legs.These valves cannot be exercised during power operation because the SI pumps do not develop sufficient pressure to overcome RCS pressure.These valves cannot be exercised during cold shutdown because the safety injection pumps are required to be inoperable by Technical Specification Section 3.5.3, to protect against low temperature overpressurization of the RCS.Also, during cold shutdown, there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke.These valves will be full stroke exercised at refueling frequency in conjunction with full flow test.page 39 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5143-35 Revision No: 2 Date: 8-31-87 NOTE 12 NOTE 13: NOTE 14: SI-158 Ll L2 L3 L4: Check valves SI-158 are located in the supply lines from the Residual Heat Removal and Safety Injection Pumps to the RCS hot legs (loop 1 through 4).These valves cannot be exercised during power operation because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.The valve cannot be full stroke exercised during cold shutdown due to potential low temperature cold overpressurization damage to the reactor vessel.These valves will be part stroke exercised at a cold shutdown frequency and will be full stroke exercised at the refueling frequency when reactor vessel head is removed.Sl-170 Ll L2 L3 and L4: These valves are located on the RCS cold leg (loops 1 through 4)injection lines from the accumulators, RHR, and SI systems.They cannot be exercised during power operations because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.The valves will be part-stroke exercised at a cold shutdown frequency.
 
Due to the plant design, the valves are sized as such that full stroke testing cannot be attained without discharging the accumulators and operating SI and RHR pumps simultaneously.
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.
The only method available to verify the full stroke exercising is disassembly method.The valve is not equipped with position indication.
Page 44 of 70
The valves will be disassembled on a sampling basis during refueling outages to verify full stroke exercising.
 
N-102 This check valve is located in the nitrogen supply header to the accumulators for blanketing purposes.The valve cannot be full stroke tested to closed position during power operation or cold shutdown because, due to the plant design, the only method available to verify the valve closure is leak testing.The valve and necessary test connections are located inside the containment.
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.
The valve is not equipped with position indication.
Page 45  of 70
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.
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.
The valves cannot be full stroke exercised during power operation, cold shutdown, or refueling without spraying the containment.
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-.
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.
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.
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.
Page 46 of 70
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.
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.
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".
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.
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.
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.
These valves and necessary test connections are located inside the containment.
(continued)
Due to the plant design, the only method available to verify valve closure is leak testing.The valves are not equipped with position indication.
Page 47 of 70
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.
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)
These valves are demonstrated operable during normal control room air conditioning operation.
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.
The valves cannot be stroked timed because they are not equipped with position indicator and stroke times are not repeatable.
Page 48  of 70
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:
DONALD C.
This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).
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.
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.
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.
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.
Page 49 of 70
The valves will be verified operable by observing proper temperatures during diesel testing.Page 46 of 70 DONALD C.COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B-27 Revision No: 2 Date: 8-31-87 NOTE 1: The required full stroking of the check valves is satisfied when the diesel generator successfully completes its required testing per Technical Specification 4.8.1.1.2.
 
NOTE 2: NOTE 3: QT-132-2AB:
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.
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.
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
The valve will be verified operable.by observing proper temperatures during diesel testing.XRV-220 Jet Assist-221 and-222 Startin Air: The starting air valves are installed on parallel air supply lines to a diesel generator.
          '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.
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.
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)
Position indication is confirmed during the above testing when only one'starting air train is used to start the diesel generators.
Page 50 of 70
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)
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-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.
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.
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.
Page 51 of  70
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:
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.
This valve is located at the discharge of the engine driven lube oil pump (diesel-generator).
Page 52 of 70
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.
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.
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.
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: NOTE 3: QT-132-2CD:
NOTE 2:  See  "Attachment-A"  for permissible seat  leakage values.
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.
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.
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
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.
'operable during diesel generator testing.'iesel generators are tested on a staggered basis, every 31,days per Technical Specification 4.8.1.1.2.
* Page 53    of 70
The valve will be verified operable by observing proper temperatures during diesel testing.XRV-225 Jet Assist-226 and-227 Startin Air: The starting air valves are installed on parallel air supply lines to a diesel generator.
 
The valves are not equipped with position indication devices to directly measure valve stroke times.Stroke timing is verified by measuring diesel starting times (Technical Specification acceptance ten seconds or less).The valves on a staggered basis are valved out one at a time to verify the operability of the opposite valve during diesel testing.The consistent compliance of the diesel generator start times (typically seven to nine seconds)demonstrates the valve performance.
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.
Position indication is confirmed during the above testing when only one starting air train is used to start the diesel generators.
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.
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 54 of 70
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.
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.
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.
Page 55 of 70
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
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.
-Unit-2 Revision No: 2 Date: 8-31-87 NOTE 1 NOTE 2: NOTE 3 PA-342: This check valve is located in the maintenance air supply line into the containment.
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.
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.
Page 56  of 70
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.
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.
See"Attachment-A" for permissible seat leakage values.XCR-100-101-102-103: These air operated containment isolation valves located in the control air supply lines to the containment.
Page 57 of 70
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
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).
-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.
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.
NOTE 2:   See "Attachment-A" for permissible leakage values.
This valve will be tested during seat leakage testing per Appendix"J" at-a refueling frequency.
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 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.
Page 58 of 70
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.
DONALD C. COOK         AR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 ATTACHMENT-A Revision No:   2 Date: 8-31-87
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.
: 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.
Page 58 of 70 DONALD C.COOK AR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT 42 ATTACHMENT-A Revision No: 2 Date: 8-31-87 1.CONTAINMENT ISOLATION VALVES Cate or A or AC Testing Method: (SLT-2)Seat leakage test the valve in accordance with 10CFR50, Appendix J, in lieu of ASME Code Section XI except for paragraphs IWV-3426 and IWV-3427.Valve No WCR-920,-922 WCR-921,-923 WCR-932,-934 WCR-933,-935
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 WCR-944,-948 WCR-951,-955 WCR-954,-958 WCR-924,-926 WCR-925,-927 WCR-928,-930 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A DA DA DA DA DA DA DA DA DA DA DA 900 900 900 900 900 900 900 900 900 900 900 Flow Permissible Leakage Diaciram Size~e Page 59 of 70  
  , 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 g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.WCR-929,-931 WCR-942,-946 WCR-952,-956 WCR-943,-947 WCR-953,-957 WCR-960,-962 WCR-961,-963 WCR-964,-966 WCR-965,-967 ECR-10,-20 ECR-11,-21 ECR-12,-22 ECR-13,-23 ECR-14,-24 ECR-15,-25 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5114A 5141B 5141B 5141B 5141B 5141B 5141B 0'0 0'0 0.50 0.50 0.50 0.50 Flow Diaciram Size 5114A 3 DA DA DA DA DA DA DA DA DA GL GL GL GL GL GL Permissible Leakage 9 0 0 900 900 900 900 750 750 750 750 750 750 750 750 750 750 Page 60 of 70 DONALD C.COOK N EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT$2 ATTACHMENT-A
DONALD C. COOK N     EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT $ 2 ATTACHMENT-A
'Revision No: 2 Date: 8-31-87 Valve No.ECR-16,-2'6 ECR-17,-27 ECR-18,-28 ECR-19,-29 CS-442-1 CS-442-2 CS-442-3 CS-442-4 SI-189 SM-1 N-102 N-159 PW-275 CS-321 VCR-10,-11 Flow~Dia ram 5141B 5141B 5141B 5141B 5128A 5128A 5128A 5128A 5128A 5141F 5143 5128A 5128A 5129 5146B Size 0.50 0.50 0.50 0.50 0.75 GL GL GL GL CK CK CK CK CK CK CK CK CK CK DA Permissible Leakage 750 750 750 750 750 750 750 750 1200 750 750 750 900 1800 1200 Page 61 of 70 DONALD C.COOK EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.VCR-20,-21 DCR-203,-207 N-160, DCR-201 DCR-610,-611 DCR-620,-621 DCR-205,-206
'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
~DCR-600,-601 QCR-300,-301 QCM-250,-350 QCR-919,-920 SF-152,-154 SF-159,-160 Flow Diaciram 5146B 5137A 5137A 5137A 5137A 5137A 5124 5129 5129A 5115A 5136 5137A Size ,4 2.50 2.50~Te DA DA, GL CK, DA DA DA DA DA GL GA DA DA, GL DA Permissible Leakage 1200 750 1125 750 750 1200 900 750 1200 750 750 900 Page 62 of 70 DONALD C.COOK EAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.NCR-105,-106 NCR-107,-108 NCR-109,-110 RCR-100,-101 DCR-202,-204 ICR-5,-6 ECR-33,-35 ICM-260~ICM-265 ECR-31,-32 XCR-100,-101 XCR-102,-103 GCR-301 GCR-314*Double Discs)g Flow Diaciram 5141 5141 5141 5128A 5137A 5141 5141F 5142 5142 5141F 5120B 5120B 5128A 5143 Size 0.50 0.50 0.50 0.375 0'5 0.50~Te GL GL GL GL DA GL GL GL 0.75 DA GL 0'5,2 GL,DA GA(DD)*GA(DD)*~GL Permxsszble Leakage 750 750 750 750 750 750 750 600 600 750 750 750 375 375 Page 63 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT g2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.SI 171 I 172 I 194 Flov Diaciram 5143 Size 0.75~Te GL Permissible Leakage 1125 NCR-252 CCR-460,-462 CCR-457,CCW-135 CCR-455,-456 SM-4,-6 ICM-251 ICM-250 CA-181S CA-181N SM-8,-10 CCW-243-25 CCW-244-25
*Double Discs t g 5128A 5135 5135 5135 5147A 5142 5142 5145 5145 5147A 5135B 5135B GL 0'0 GL 0.50 0.50 0.50 GA(DD)*GA(DD)*CK CK ND CK CK 3 GL 2,2'0 GL,CK 2 GL 450 900 1125 750 750 600 600 750 750 750 750 750 Page 64 of 70 I'ONALD C.COOK LEAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No:-2 Date: 8-31-87 Valve No.CCW-243-72 CCW-244-72 CCM-430 CCM-431 CCR-440 CCR-441 CCM-432 CCM-433 R-156 R-157 NS-357 ECR-496,-497 ECR-416 ECR-417 ECR-535 Flow Diaciram 5135B 5135B 5135B 5135B 513B 5135B 513'5B 5135B 5146B 5146B 5124 5141C 5141C 5141C 5141C Size 1'0 1.50 1.50 1.50 1.50 1.50 0.375 0.375 0'0 0.50 0.50 0.50 0.50~Te CK CK GL GL GL GL GL GL CK CK CK GL GL GL GL Permxsszble Leakage 750 750 375 375 375 375 375 375 750 750 750 750 375 375 375 Page 65 of 70 DONALD C.COOK LEAR PLANT ASME SECTION XI VALVE TEST PROGRAM FOR UNIT$2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.Flow Diaciram.Size~Te Permissible Leakage ECR-536 ECR-36 PCR-40 PA-342 NS-283 NPX-151 WCR-900,-902 WCR-901,-903 WCR-912,-914 WCR-913,-915 WCR-904,-906 WCR-905,-907 WCR-908,-910 WCR-909,-911 VCR-101,-201 VCR-102,-202 5141C 5141F 5120B 5120B 5141D 5128A 5114A-5114A 5114A 5114A 5114A 5114A'114A 5114A 5147A 5147A.0.50 0.50 0.50 14 14 GL DA GA CK CK GL DA DA DA DA DA DA DA DA BF BF 375 375 375 750 750 375 1800 1800 1800 1800 1800 1800 1800 1800 4200 4200 Page 66 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.VCR-103,-203 VCR-104,-204 VCR-105,-205 VCR-106,-206 VCR-107,-207 Flow Diaciram 5147A 5147A 5147A 5147A 5147A Size 24 30 30 24 14 BF BF BF BF BF Permissible Leakage 7200 9000 9000 7200 4200 ICM-305 ICM-306 5143 5143 CCM 452 g 454 I 458 5135 CCM 45 1 I 453 I 459 5135*Double Discs 18 18 8,4,8 8,4,8 GA(DD)*GA(DD)*BF, GL, BF BF,GL,BF 2700 2700 3000 3000 Page 67 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 2.CONTAINMENT SPRAY VALVES Cata o A or AC Testing Method: As described in"SLT-2A," Figure 3.Valve No.CTS-131W CTS-131E CTS-127W CTS-127E RH-141 RH-142 Flow Diaciram 5144 5144 5144 5144 5144 5144 Size~Te CK CK CK CK CK CK Permissible Leakage 3'3 3.00 22.55 21.21 20.70 23.00 Page 68 of 70 DONALD C.COOK NUCLEAR P ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 3.PRESSURE ISOLATION VALVES Cata or A or AC Testing Method: (SLT-1)Seat leakage test the valve per ASME Code Section XI.Valve No.'CS-299E Flow~Dia ram 5129 Size~Te CK Permissible Leakage 2'CS-299W SI-152-N SI-152-S ICM-129 5129 5143 5143 5143 14 CK 2.0 CK 5.0 CK 5.0 GA(DD)*~~10.0 SI-161-Ll,-L4 SI-161-L2,-L3 SI-170-L1 SI-170-L2 SI-170-L3 SI-170-L4 SI-158-L1,-L4
*Double Discs 5143 5143 5143 5143 5143 5143 5143 10 10 10 10 CK CK CK CK CK CK CK 10.0 10'5'1.0 1.0 5.0 10'Page 69 of 70 DONALD C.COOK NUCLEAR P.ASME SECTION XI VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No: 2 Date: 8-31-87 Valve No.SI-158-L2,-L3 SI-151-E SI-151-N SI-166-L1 SI-166-L2 SI-166-L3 SI-166-L4 Flow~Dia ram 5143 5143 5143 5143 5143 5143 5143 Size 10 10 10 10 CK CK CK CK CK CK CK Permissible Leakage 10.0 5.0 5.0 5.0 5.0 5.0 5~0 RH-133,-134 5143 , 8 CK 1.0 Page 70 of 70  


=0 DONALD C.CCK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SRC1ARY SHEET-UihIT 2 SYSTEN=NAHE:=
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
EHERGEHCY=DIESEI GENERATOR="CD"--
  ~ 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
--=-FLOH-DIAGRAN:---2-51510-27 RUiH DATE AHD TINE: 14SEP87:13:28 VALVE-----=------I VALVE-POSITION I-=------ASNE-SECTION XI----.-I I NUi'GER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
=TYPE-COORD (-OPER----FUHCT---(CL--=----REQUIRED--PERFORHED--YiODE 2-SV-120-CD 0 RE L 0.25 SA H/2 C 0 3 A C TF1 TF-1 R HO 2-SV-139-CD-
--0=-REI==-D---SA---B/2 C=-0=---:-3-=-A.C=TF=.l-=TF-1 2-SV-61-CD 0 REL 1 SA A/8 C 0 3 A C TF-1 TF-1 2-SV-78-CD1 0 REL 1 SA E/3 C 0 3 A C TF1 TF-1 2"SV"78-CD2 0 REL 1 SA D/3 C 0 3 A C TF-1 TF"1 R HO 2-SV-79-CDI -REL=0.5-==SA E/1---C----=0------=-3-A-C=-==-TF=1=-
-TF-1---R---NO 2-SV-79-CD2 0 REL 0.5 SA E/1 C 0 3 A'TF-1 TF-1 R NO 2-XRV-225 0 GA 1 A B/3 C 0=3 A B EF-1 EF-1 EF-7 EF-7--ET-010----NOTE 3 P NO P NO-P----YES>NOTE 3--2-XRV-226 0 GL 3 A B/4 C 0 3 A B EF1 ET-010 EF-1 NOTE 3 P YESp NOTE 3 P YES>NOTE 3 2-XRV-227 0 GL A B/4 C 0 3 A B EF1 EF"1 P YES>NOTE 3---ET=010==--NOTE-3-P YES NOTE 3-  


0~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU6)QSRY SHEET-UNIT 2 SYSTEMIZE:
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)
EME RGENCY'DIESEL GENERATOR'!CD" FLOH DIAGRAM:.2=5151D"27 RUN DATE AND TIME: 14SEP87:13:28 VALVE---------=I VALVE POSITION I I I ASME SECTION XZ---HU66BER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE COORDI OPER-.-FUHCT-ICL------REQUIRED---PERFORMED-MODE 2-DG-102C 1 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NOp NOTE 1 2=DG=104C~=.CK=1.5 SA...F/4 0 0/C 3 A C CF-1 CF-1 P.HO)NOTE 1 2-DG-128C 0 CK 1 SA C/3 C 0 3 A C CF1 CF-1 P HOp NOTE 1 2-DG-130C 0 CK 1 SA C/3 C 0 3 A C CF1 CF-1 P NOp NOTE 1 2-DG-132C 0 CK 3 SA B/4 C 03 A C CF-1 CF-1 P HOp NOTE 1 2<<DG-M4C===
* 600
-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
    ~
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 PLANT SECOND TEN YEAR INTERVAL VALVE SUHiNRY SHEET-UNIT 2 SYSTEH-NAHE:
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)
-EHERGENCY=DIESEl GENERATOR=
* 600 ICM-250                5142                  GA(DD)
-=--==FLOW-DZAGRAH:---2"515)C=26.
* 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
----=RUN DATE ANO TINE:)4SEP87:)3:28 VALVE=---I-VALVE=POSITION-I-I I ASHE SECTION-XZ
* Double Discs    t g Page 64 of 70
-----MISER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF RWJEST(S)----------TYPE-COORDI-OPER-=
=FUNCT-=-ICL
-----REQUIRED
----PERFORHED
--HODE-.2-OL-))4C 0 CK 1.5 SA B/9 0 C 3 A C CF1 CF-1 P NOp NOTE 1 5=01=116C 0-CK.M.5---56-0/9-0-0-A C.CF=)...CF-1 P-NOp NOTE 1 2" D L-132C 0 CK 1 SA F/9 0 C 3 A C CF-1 CF-1 P Nop NOTE 1 2-DL-158C 0 CK 6 SA G/5 C 0 3 A C CF-1 CF-1 NOp NOTE 1 2-QT-))6'p-2CD 0 3H 6 SA H/5 0 3 A B EF)NOTE 2 NOp NOTE 2 4
0 DONALD C.COCK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET-UNIT 2 SYSTEN-NANE:-=-ENERGEHCY-.DIESEI GENERATOR--------FLON DIAGRAtt:=-
2-51518"27
=RUN DATE AND TINE: 14SEP87)13:28
-VALVE-----=-=----=I-VALVE POSITION-I I I ASNE-SECTION XI HUYd)ER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)
TYPE COORD I-OPER-FUNCT ICL.-REQUIRFD PERFORMED NODE 2-SV-120-AB 0 REL 0.25 SA G/2 C 0 3 A C TF1 TF-1 R NO 2-SV=139-.AB
-0=-REI.-1-.-.SA.B/2-C-0--3 A C-TF.-l--TF-1-R NO 2-SV-61-AB 0 RE L 1 SA A/8 C 0 3 A C TF-1 TF-1 2-SV"78"AB1 0 REL 1 SA E/3 C 0 3 A C TF1 TF-1 R HO 2-SV-78-AB2 0 REL 1 SA D/3 C 0 3 A C TF1 TF"1 2-SV-79-ABl REL-0.5---SA-: E/A---C==--0-====D--A=---C-===-TF-1--.-==-=TF"1 2-SV-79-AB2 0 REL 0.5 SA E/1 C 0 3 A C TF-1 TF"1 R NO 2-XRV"220 0 GA 1 A B/3 C 0 3 A B EF1 EF-7 ET-010 EF"1 EF-7 NOTE 3-P HO P NO P-YES>-NOTE 3----2-XRV"221 0 GL 3 A B/0 C 0 3 A B EF-1 ET-010 EF-1 HOTE.3 P NO P.YES>NOTE 3.2-XRV-222 0 GL A B/0 C 0 3 A B EF-1 EF-1 P NO--=--ET=010--=
==NOTE 3=-==P--YES>HOTE 3


.~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUYttARY S)IEET-UiNIT 2 SYSTEN=NAME t-EHERGENCY-DIESEL-GENERATOR
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
------=-FLOl$-DIAGRAN:-2-51518-27=-
RUN DATE AND TlttE: 14SEP87:13:28
--VALVE-I VALVE-POSITION-I
==------.--------ASIDE-SECTION XI---I I HmtBER REV TYPE SIZE ACT F.D I POHER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF RE(%EST(S).TYPE-COORDt OPER-=FUNCT-.ICL=.REQUIRED PERFORttED ttODE 2-DG-102A 0 CK 1.5 SA H/4 0 0/C 3 A C CF-1 CF-1 P NO>NOTE 1 2=DG-.104A
-=0-.C~.S-=SA-G/4 0.--0/C 3 A C-CF=l-CF-1 P HO>NOTE 1 2-DG-128A 0 CK 1 2-DG-130A 0 CK 1 SA C/4 C SA C/4 C 0 0 A C CF1 A C CF-1 CF-1 CF-1 P NO>NOTE 1 P NO>NOTE 1 2-DG-132A 0 CK 3 SA B/4 C 3 A C CF-1 CF-1 P NO>HOTE 1 2.-DG-134A---
=0=---CK-- =SA B/4-C 0 3--A C---CF 1-CF-1--P-HO>NOTE 1-2 DG 140A 0 CK 0 5 SA F/1 C 0/C 3 A C CF 1 CF"1 P NO 2-DG-142A 0 CK 0.5 SA F/1 C 0/C 3 A C CF-1 CF-1 P HO 2-DG>>146A 0 CK 2 SA A/8 0 C A C CF1 CF-1 P NO>HOTE 1 2=DG~2A=-=.0-CK==4=-=SA 0/8=--C'0==-3-A C.CF-.1.CF-1 P=t40>HOTE 1-2-DG-154A 0 CK 4 SA C/8 C 0 A C CF 1 CF-1 P HO>NOTE 1 2-QT" 132-2AB 0 3H 6 SA E/8 0 0 A B EF1 NOTE 2 P NO>NOTE 2


e DONALD C COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU%>ARY SHEET-UNIT 2 SYSTEN-NANE:
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
-ENERGEHCY-DIESEL-.GENERATOR=-
------FLOH-DIAGRAN: 5151A-26 RUH DATE AND TINE: 14SEP87:13:28
--VALVE-=------=--==-I.VALVE POSITION-I----=-=-----..---.=-.=ASNE SECTION XI-I I NUHBER REV TYPE SIZE ACT F~D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
TYPE-COORDI OPER--FUST-=ICI--=-===-REQUIRED
----PERFORNED-NODE 2-DF-108A 0 CK 1.5 SA L/3 C 0 3 A C CF-1 CF-1 P HO)HOTE 1 2=DF=109A=O CK.=1.5 SA K/3-C.0 A C.CF-1.CF=1 P NO>HOTE 3.2-DF-114A 0 CK 1.5 SA J/3 C 0 3 A C CF1 CF-1 HO)NOTE 1 2-DF-115A 0 CK 1.5 SA N/3 C 0 3 A C CF1 CF"1 HO>NOTE 1 2-DL-114A 0 CK 1.5 SA B/9 0 C 3 A C CF-1 CF-)NOp NOTE 1 2-DL-116A-0--CK.--~.5---SA--B/9---C-----0.------3---A-C.--CF-1---.---.CF-1 P-NO>NOTE-1-2-D L-132A 0 CK 1 SA F/9 0 C 3 A C CF-1 CF-1 P NO>NOTE 1 2-DL-158A 0 CK 6 SA G/6 C 0 3 A C CF1 CF-1 P NO>HOTE 1 2-QT-114-2AB 0 3H 6 SA H/5 0 0 A B EF-1 NOTE 2 P NO>HOTE 2


DONALD C.COOK tmCLEAR PLANT SECOND TEtf YEAR INTERVAL VALVE SUGARY SHEET-UNi IT 2 SYSTEH-NAHE:=CONTROL=ROOM-VENTILATION
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)
-=----==-FLOH=DIAGRAN:-2-5149-23-=---RUN DATE AND TZttE: 14SEP87:13:28 VALVE-=-----I VALVE-POSITION-I-I I=ASttE SECTION-Xl=
* 2700 ICM-306                5143        18        GA(DD)
NUttBER REV TYPE SIZE ACT F AD I POttER SAFETY LCD A/P CAT PRItt TEST TEST TEST RELZEF REQUEST(S)-TYPE-COORD I OPER--FU'tCT-ICL----REQUIRED---PERFORNED l%DE-2-DH-163-N 0 GA 2.5 H F/2 0 0/C 3 A B EF-1 EF-1 P NO 2-.DH-163-S=
* 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
--0-=GA---2.5--.-tt--G/2-=-=0 0/C==--M-A-B..-EF-1--------EF-1 2-DH-166-N 0 GA 2.5 H E/5 0 0/C 3 A B EF"1 EF-1 2-DH-166-S 0 GA 2.5 t 1 J/5 0 0/C 3 A B EF-1 EF-1 2"VRV-315 0'H 2.5 A F/5 0 0 A B EF-1 EF-7 ET-NA EF"1 EF-7 NOTE 1 P P HOp NOTE 1 NO>NOTE 1 YES>NOTE 1 2-VRV-325 0 3H 2.5 A G/5 0 0 A B EF1 EF"1.EF-7 EF"7 ET-NA---NOTE 1 P P NO>HOTE 1 NO>HOTE 1.YES>-NOTE 1
* Double Discs Page 67 of  70


~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUt0tARY SHEET-UNIT 2 SYSTEN-NAtfEt
DONALD C. COOK NUCLEAR P ASME SECTION  XI  VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No:  2 Date: 8-31-87
-CONTAZHNEHT-.VENTILATION-
: 2. CONTAINMENT SPRAY VALVES      Cata o  A or AC Testing Method:    As  described in "SLT-2A," Figure 3.
--------=-FLOH-DZAGRAtt: 5147A-35--
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
--RUH DATE AND TZt<E 14SEP87: 13: 28 VALVE-=-=-===-=-I VALVE-POSITION=I
--====-===----ASHE SECTION XI I I NEWER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT-TYPE-COORDI OPER--FUttCT-ICL----PRIH TEST TEST TEST RELIEF REQUEST(S)
REQUIRED---PERFORHED-
==-ttODE------=-2-VCR-203 0 BF 24 A J/5 C C 2 P A EF-1 EF-5 EF-7.ET-005=SLT-1 EF-)EF-5 EF-7 ET-005 SLT-2 P-P R NO HO HO NO-YES>NOTE 1 2-VCR-204--0=BF=-==30
=---=A--J/6=-C-2--P=A EF-1---EF"5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET"005 SLT-2 P HO HO P HO P HO R YES, NaTE 1 2-VCR-205 0 BF 30 A J/3 C C 2 P A EF-1=EF-5=EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P ttO P HO R YESJ NOTE 1 2-VCR-206 0 BF 24 A J/3 C 2 P A EF-1 EF-5 EF-7 ET"005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO HO HO-HO YES>HOTE 1 2-VCR-207 0 BF 14 J/4 0/C C 2 A A EF-1 EF-5 EF-7-ET-005=SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P HO P.--HO R YESp NOTE 1


0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ZNTERVAL VALVE SUiiARY SHEET-UNIT 2 SYSTEtt-NAttE:=-COWTADNENT-VENTILATION-
DONALD C. COOK NUCLEAR P ASME SECTION  XI  VALVE TEST PROGRAM FOR UNIT N2 ATTACHMENT-A Revision No:  2 Date: 8-31-87
----=-=FLS'I DIAGRAN:-2-5147A-35 RUH DATE AHD TINE: 14SEP87:13:28
: 3. PRESSURE  ISOLATION VALVES    Cata or  A or  AC Testing Method:    (SLT-1) Seat leakage  test the valve per  ASME Code Section XI.
=-VALVE---=-----=-==I=VALVE-POSITION-I I I HUYBER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT-TYPE COORD l=-OPER-FUHCT-I CL-=--ASME SECTION XZ--PRIN TEST TEST TEST RELIEF RECQEST(S)
Flow                          Permissible Leakage Valve  No.        ~Dia ram    Size      ~Te
RE@GRED-PERFORHED--tfODE 2-VCR-105 0 BF 30 A J/3 C C 2 P A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7.ET-005 SLT-2 P P P R NO HO HO tiO YESp ROTE 1 2-VCR-106-0-==BF-=-24---=-A---J/3---C--=---C--==-=-2--P-A---EF-I, EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R I')O-NO tiO HO YES>NOTE 1 2-VCR"107 0 BF 14 A J/4 0/C C 2 A A EF-1 EF-5---EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO-HO HO N)YES>NOTE 1 2-VCR-201 0 BF 14 A J/8 C 2 P A EF-1 EF"5.EF-7 ET-005 SLT-1 EF-1 EF-5---EF-7 ET-005 SLT-2 P P R HO HO NO t$0 YES>NOTE 1 2-VCR-202 0 BF 14 A J/9 C C 2 P A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7=-=ET-005-SLT-2 P P=--R HO HO HO-HO-YESp NOTE 1 DOttALD C.COO<AD NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE  
  '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==
==SUMMARY==
SflEET-UNIT 2 SYSTEM NAME'COHTAINtENT VENTILATIOH
SflEET
==.FLOH..DIAGRAM:
                                                        .FLOH..DIAGRAM:
2=514?A-35 RUH DATE AHD TIHE: 14SEP87:13:28 VALVE---..-=-==-I-.VALVE-POSITION I I I NUt'GER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE-COORDI-OPER--
UNIT 2 2=514?A-35 VALVE -..     -=-==-   I I
-FUNCT-ICL==--ASME SECTION.XI--PRIM TEST TEST TEST RELIEF REQUEST(S)
                                              -.VALVE-POSITION   I I
REQUIRED.PERFORHED=MODE 2-SH-10 0 GA 0.5 H A/4 C C 2 P A SLT-1 SLT-2 R YES NOTE 1 2=SM=4=-==O=GA=0.5 H=A/2=C..C.=2 P A SLT=l.SLT"2 R.=YES>NOTE 1 2-SH-6 0 GA 0.5 M A/2 C C 2 P A SLT-1 SLT-2 YES>NOTE 1 2-SH"8 0 GA 0.5 H A/4 C C 2 P A SLT-1 SLT-2 YES>NOTE 1 2-VCR-101 0 BF 14 A J/8 C 2 P A EF"1 EF"5 EF"7-ET-005--SLT-1 EF-1 EF-5 EF-7-ET-005-SLT 2 P-P=-R HO NO NO-NO YES>HOTE 1 2=VCR".102==0=BF=== ==-A--J/9 C C.2 P.A EF-1 EF-5 EF-7 ET-005-SLT-1-EF-1=EF-5 EF-7 ET-005 SLT-2-P P=-R HO NO NO NO-.YES'.HOTE 1-----2-VCR-103 0 BF 24 A J/5 C 2 P A EF-1-EF-5--==--EF-7 ET-005 SLT-1 EF-1 EF"-5----EF-7 ET-005 SLT-2 P NO HO P NO P NO R YES>NOTE 1 2-VCR-104 0 BF 30 A J/6 C C 2 P A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7 ET-004 SLT-2 P NO NO P HO P HO R YES>HOTE 1  
                                                                                                -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 Nl&#xc3;KER    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


DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR INTERVAL VALVE SUiiu ARY SHEET-LAIT 2 SYSTEM-NAttE:
e                                                                        ~
-ICE-CONDENSER REFRIGERATIOH
DOHALD C. COOX NUCLEAR PLANT                         RUiH DATE AHD TZHE: 14SEP87:13:28
=,.=FLON DIAGRAM:.2=5146B=23 RUH DATE AHD TIMiE: 14SEP87:13:28-VALVE===---=---I=VALVE-POSITION I I I HUMBER REV TYPE SIZE ACT F.D I POttER SAFETY I CD A/P CAT TYPE COORDI OPER FUNCT ICL.-ASitE SECTION.XI.PRIM TEST TEST TEST RELIEF REQUEST(S)
                                                                                                                                                  .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)
REQUIRED PERFORMED.NODE.2-R-156 2 CK 0.375 SA L/4 C 0/C 2 A AC CF-1 SLT-1 CF-1 SLT-2 R YES>NOTE 1 R YES>HOTE 2 2"R-157 2 CK 0.375 SA L/6 C 0/C 2 A AC CF-1 SLT-1 CF-1 SLT-2 R YES>NOTE 1 R YES>HOTE 2 2-VCR-10 0 DA 4 A M/5 0 C 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF"5 EF-7 ET"005 SLT"2 P P R HO NO ttO NO YES>NOTE 2 2=VCIL11 O=DA==4=A L/5 0 C-.2.A A=EF=l EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-.2 P P R NO NO HO HO YES>NOTE 2 2-VCR-20 0 DA A tt/7 0 2 A A EF-1-EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO NO NO NO YES>NOTE 2 2-VCR-21 0 DA 4 A L/7 0 2 A A EF-1 EF-5 EF"7-ET-006 SLT-1 EF"1 EF-5 EF=7 ET-006 SLT-2 P P P R NO HO NO NO YES>NOTE 2
                          ---- --=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
DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUN1ARY SHEET-UNIT 2 SYSTEM-NAME:
-CPN/MELD..CHANNEL PRESSURIZATION.=
-=--FLIC DIAGRAM:=2-5145"20.
=-=-==RUN DATE AND TIME: 14SEPB7:15:28
--VALVE---=-=-==-----I-VALVE POSITION I-I I ASME SECTION-XI NU1$ER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-,COORDI OPER=-FUNCT=ICL-==-REQUIRED==PERFORMED---MODE-2-CA-181-N 0 CK 0.5 SA F/2 C 2 P AC SLT-1 SLT"2 R YES)NOTE 1 2"-CA&81-.S===O----CK--=.0.5--=---SA-F/5 C--=C-.2--P=AC-SLT=1---SLT-2-R YES)NOTE 1 4
0~DOHALD C.COOK NUCLEAR PLAttT SECOM)TEtt YEAR INTERVAL VALVE SCD)ARY SHEET-UtlZT 2 SYSTEM-NAME:
-.CONTAINtlENT--SPRAY,=FLOH DIAGRAM: 2-5144-29 RUH DATE AND TIME: 14SEP87:13:28 VALVE=-------=.-=-I VALVE POSZTZ(N-I---
I I ASME SECTION XZ NUMBER REV TYPE SIZE ACT F 0 l POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE COORDI.OPER FUNCT--ICL.--REQUIRED.PERFORl'lED MODE 2-IMO-221 0 GA 10 MO L/8 C 0 2 A B EF1 EF-5 ET-066 EF-1 EF"5 ET-066 P P HO NO NO 2-ZtlO-222 0 GA 2 MO L/9 0 0/C 2 A B EF-1 EF-1 EF-5 EF-5 ET-030---ET-030 P NO NO P--HO 2-ZMO-225 0 GA 12 MO J/9 0 0/C 2 A B EF-1 EF-1 EF=5-EF"5 ET-074 ET-074 P NO NO P NO 2=RH"..141
==0 CK-.8.SA E/3-C.--0=-2 A AC.CF-1 CF-2 SLT-1 SLT-2A R R YES>-NOTE 2.--.-YES>NOTE 3 2=RH=142----0 CK 8..SA E/3 C 0.2.A AC=CF-1 SLT-1 CF-2 SLT-2A R YESi NOTE 2 R YESp HOTE 3 2=SV=107-0=REL=1--=SA-=-H/5 C---0:==2-A-C---.-TF"1---=-=-=TF=l=-R-NO SYSTEH NAttE: CONTAIHtL~tfT=SPRAY DONALD C.COOK NUCLEAR PLANT RUN DATE AND TINE: SECOND TEN YEAR INTERVAL VALVE SL?AAARY SttEET-UNIT 2 FLO'A DIAGRAtt:-2=5144-29..14SE P87: 13: 28 VALVF I VALVE POSITION I I I ASttE SECTION XI Nl&#xc3;KER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
TYPE-.COORDI-OPER
-.FUHCT=ICL.=.REQUIRED.PERFORttED NODE 2-CTS-138-N 2 CK 12 SA J/9 C 0/C 2 A C CF-1 CF-3 YESp NOTE 1 2550=202 0 GA=2.5 HO-5/?=-C.=..-
0=,.--2.A=B EFM EF-5 ET-018 EF-1 EF-5 ET-018-NO HO HO 2-IttO-204 0 GA 2.5 ttO H/7 C 0 2 A B EF-1 EF-5 ET-018 EF-1 EF-5 ET-018 P HO HO P HO 2-Zt jO-210 0 GA 10 N80 J/8 C 0 2 A B EF-1 EF-5 ET-066 EF-1 P HO EF-5 tiO ET-066=P NO 2-It'.0-211 0 GA 10 NO J/8 C 0 2 A B E F-1 EF-1 EF-5..EF-5: ET-065 ET-065 P HO HO=P HO~50=212 0 GA.2----.--HO--H/8--0--0/0=--2=A-5 2?=1 EF-5 ET-033 EF>>l.P NO EF-5 HO ET-033 P HO 2-ZttO-215 0 GA 12 NO G/9 0 0/C 2 A B EF-1 EF-5 ET-074 EF-1 EF-5 ET-074 NO NO HO 2-INO-220 0 GA 10 HO L/8 C 0 2 A B EF1 EF-5 ET=065.EF-1 EF-5 ET-065 NO HO NO 08 0
SYSTEM-NAME:
-CONTAINMENT-SPRAY DONALD C.COOK NUCLEAR PLANT SECOND TEth YEAR INTERVAL VALVE SEC)ARY SHEET-UNIT 2 FLON=DIAGRAM: 2-5144"29 RW DATE AND TIME: 14SEP87:13:28 VALVE=I-VALVE-POSZTZON
-I I I---=ASME SECTIOLN XZ NUMBER REV TYPE SIZE ACT F~D I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-=COORDI-OPER
---FUHCT---ICL
-----=-REQUIRED
---PERFORMED=----.
MODE 2-CTS-103-E 2 CK 10 SA J/9 C 0 2 A C CF-1 CF-3 YES>NOTE 1 2=CTS=103=M=2 CK 10.SA L/9-C.0..=2==-A-C.CF-l.CF"3.=.YES'OTE 1 2-CTS-109 0 VB 1 SA M/6 C 0 2 A C TF"1 TF-1 2-CTS-110 0 VB 1 SA tt/6 C 0 2 A C TF-1 TF-1 2-CTS-120-E 0 CK 2 SA H/8 C 0 2 A C CF-1 CF-1 P NO 2=CTS=120=H 0-CK-2=-=SA K/8-C--0--.2.A-.C..--CF-1--CF"1.2-CTS-127-E 0 CK 6 SA E/5 C 0 2 A AC CF-1 SLT-1 CF-2 SLT-2A R YES>NOTE 2 R YES>ttOTE 3 2-CTS-127-N 0 CK 6 SA E/4.C 0 2 A AC CF-1 CF"2 SLT-1---=-SLT-2A.-R YES>NOTE 2--R YES>NOTE 3 2-CTS-131-E 0 CK 8 SA-E/2 C 0 2 A AC CF1 SLT=1 CF-2 SLT-2A R YES>NOTE 2 R YES>ttOTE 3 2-CTS-131-N 0 CK 8 SA E/2 C 2 A AC CF-1 CF-2=R YES>N)TE 2 SLT-1-SLT-.2A R-YES>NOTE 3 2-CTS" 138-E 2 CK 12 SA G/9 C 0/C 2 A C CF-1 CF-3 YESy NOTE 1  


e~DOHALD C.COOX NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHi1ARY SHEET-UNIT 2 SYSTEN-HAl5E:
  =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)
-EHERGEHCY=CORE-COOLING RHR---=-=--FLOH-DZAGRAN:-
                      --- ---     TYPE- COORDI OPER     -- FUiiCT - ICL - ---   --   REQUIRED- - -  PERFORNED    NODE.
2-5143 RUiH DATE AHD TZHE: 14SEP87:13:28
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-VALVE I-VALVE-POSITZOH-I I I ASME SECTION Xl HUi'iDER REV TYPE SZZE ACT F.D I POHER SAFETY ICD A/P CAT PRZN TEST TEST TEST RELIEF REQUEST(S)
0 0
-------=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=
GL GL GL 0  '5 0..75 0.75 N
--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  
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


=0 0 DONALD C COOK NUCLEAR PLANT SECOHD TEN YFAR INTERVAL VALVE SU)0)ARY SHEET-UNIT 2 SYSTEN-HANE:
e 0
-ENERGENCY-CORE-COOLING RHR-=-----.--==FLON DIAGRAN:=--2-5143-35=
DONALD C. COOK ttUCLEAR PLANT                         RUH DATE AND TIME:   14SEP87:13:28 SECOND TEH YEAR INTERVAL VALVE  
RUH DATE AND TINE: 14SEP87:13:28 VALVE--I-VALVE POSITZOH-I-I I-ASNE SECTION-Xl
--NUiE)ER REV TYPE SIZE ACT F.D.I PINER SAFETY ICD A/P CAT PRZH TEST TEST---------TYPE-COORDI OPER--FUiiCT-ICL-------REQUIRED---PERFORNED TEST RELIE F REQUEST(S)
NODE.2-SZ-166-L4 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF"2 SLT-1 R YESp NOTE 5 R NO>NOTE 1 2-SI-170-Ll 2 CK 10 SA A/4 C 0 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>HOTE 13 N)p NOTE 1 2-SI-170-L2 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>HOTE 13 NO>NOTE 1 2-SI-170-L3 2 CK 10 SA A/5 C 0/C 1 A AC CF-1 SLT-1 CF-3 SLT-1 R R YES>NOTE 13 HO>NOTE 1 2"SI-170-L4 2 CK 10 SA A/4 C 0 1 A AC CF-1 SLT-1 CF-3 SLT-1 R YES>HOTE 13 R NOp NOTE 1 2-SI-171 0 GL 0'5 N H/6 C C 2 P A SLT-1 SLT-2 R YES, HOTE 1 2-Sj-172-0-GL-0..75-ii-H/6 C.C 2-P=-A--SLT-1--SLT-2 R-YES NOTE 1 2-SI-194 0 GL 0.75 N G/6 C C 2 P A SLT-1 SLT-2 R YES>NOTE 1 2-SV-100-1 0 REL 1 SA 0/1 C 0 2 A C TF1 TF-1 R NO 2-SV-100-2 0 REL 1 SA D/1 C 0 2 A C TF-1 TF-1 e
0 DONALD C.COOK ttUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE  


==SUMMARY==
==SUMMARY==
SHEET-UNIT 2 SYSTEtt NAt1E:-EMERGENCY=CORE COOLItlG-RtlR=..FLOH DIAGRAM:-2-5143-35 RUH DATE AND TIME: 14SEP87:13:28 VALVE-=----------I-VALVF-POSITION-I--=---.-------ASME SECTION XZ--I I NRRER REV TYPE SIZE ACT F.D.I POttER TYPE COORDI OPER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
SHEET UNIT 2 SYSTEtt NAt1E: EMERGENCY=CORE COOLItlG -   RtlR=         .. FLOH DIAGRAM: 2-5143-35 VALVE -=- -- -   ---   - I- VALVF-POSITION -I I                  I
FUNCT.ICL-=-REQUIRED--PERFORMED.-MODE 2-SZ-158-L3 0 CK 6 SA B/7 C A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 12 R ttO>NOTE 1 2-SZ-158-L4 0 CK 6 SA B/7 C 0 1 A AC CF-1 SLT"1 CF-2 SLT-1 C YES>HOTE 12 R HO>NOTE 1 2-SI-161-L1 0 CK 6 SA B/6 C 0 1 A AC CF-1 CF-2 C YES>HOTE 6 SLT-1 SLT-1 R HOp HOTE 1 2-SZ-161-L2 0 CK 6 SA B/5 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 6 R NOp NOTE 1 2-SI-161-L3 0 CK 6 SA B/5 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YESp NOTE 6 R NOp HOTE 1 2-SI-161-L4 0 CK 6 SA B/6 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 C YES>NOTE 6 R NOp NOTE 1 2-SI-166-L1 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF"2 SLT-1 R YES>NOTE 5 R NO NOTE 1 2-SZ-166-L2 0 CK 10 SA C/4 C 0 A AC CF-1 SLT-1 CF-2 SLT-1 R R YESp HOTE 5 NOp NOTE 1 2-SI-166-L3 0 CK 10 SA C/4 C 0 1 A AC CF-1 SLT-1 CF-2 SLT-1 R YESp NOTE 5 R t<0>NOTE 1  
                                                                        --=- --   . --- - --   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


~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sinai HARY SHEET-UiHIT 2 SYSTEM-HAME' EMERGENCY CORE-COOLING.=
0
RHR=..=,FLOH DZAGPJtH:=-2-.5103=35=
          ~                                                              ~
RUiH DATE AHD TIME: lOSEP87:13:28 VALVE-=-=---I-VALVE-POSITION-I-I I ASME-SECTION.XZ HU953ER REV TYPE SIZE ACT F~D I PS'(ER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
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       -== - -.
---=TYPE-COORDI.OPER-
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)
=--FUHCT==ICL-=-=-
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-.
-..--.REQUIRED
EF-5 EF-1 EF-5
-=PERFORMED-MODE--2-RH-108M 0 CK 8 SA N/9 C 0 2 A C CF-1 CF-3 C HOp NOTE 7 2=RH=133------O=.CK 8-..=.SA.C/5 C.C..=-=1..P AC.CF=1--CF-2 SLT-1 SLT-1.C.YES NOTE 8 R HOp NOTE 1 2-RH-134===-0=-CK--8=-=-SA--C/5 C-.-.C-------1-P-AC--CF-I=----CF-2 SLT-1 SLT-1 C--YESp-NOTE 8--R HOp NOTE 1 222SL=108 2 C~R GA-G/F-=C-.-0 2 A.--C-.CF-2=-CF-3.-.-.--YEG.EGYE 9.2-SZ-151-E 0 CK 8 SA D/7 C 0 2 A AC CF 1 CF-2--.-=-SLT-1.---.SLT-1 C YESp NOTE 10 R-=-HOp.NOTE 1 2-SI-151-W 0 CK 8 SA D/7 C 0 2 A AC CF1 CF-2 SLT-1---=SLT-1 C YESp NOTE 10 R-HOp NOTE 1 2"SZ-152-N 0 CK SA 0/8 C 0 2 A AC CF-1 CF-2 SLT-L=SLT-1 R YESp NOTE ll==R=-=--NOp NOTE 1-2"SI-152-S 0 CK SA 0/7 C 0 2 A AC CF-1 SLT.-1 CF-2 R YESp NOTE ll SLT-1=.R.==HOp NOTE 1 2-SZ-158-Ll 0 CK 6 SA B/8 C 0 1 A AC CF-1 CF-2 C YESp NOTE 12-----SLT-1==--=
                                                                                                          .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
-SLT-1----R---HOp NOTE--1.2-SI-158-L2 0 CK 6 SA B/7 C 0 1 A AC CF-1 CF-2 SLT-1.-=SLT-1 C YESp NOTE 12 R.HOp.HOTE 1 0
~~DONALD C.COOK HUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUt0tARY SHEET" UtGT 2 SYSTEM-NAME-'
EMERGENCY-CORE-COOLING=
RHR====FLOH-DIAGRAM:
-2"5143-.35
-==--.RUN DATE AND TIME: 14SEP87:13:28 VALVE=-t-VALVE-POSITION-I-I I ASME SECTION.XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE-COORDI=OPER==-=FUNCT=
ICL=--REQUIRED.PERFORMED..MODE 2"ZMO-325 0 GA 8 MO C/7 C C/0 1 A B EF"1 EF-5 ET-028 EF-2 EF-5 ET-028 C YESF HOTE 4 NO C HO 2"ZMO-326 0 GA 8 MO C/7 0 0/C 2 A B EF1 EF-2 EF-5 EF-5-ET-028-=-=---ET-028-C YES>NOTE 4 NO C NO 2-Z MAO"330 0 GA 8 MO G/4 C 0 A B EF1 EF-1 EF"5 EF.-5 ET-053 ET-053 P NO NO P HO 5=150-551.0 GA.5-.MO 1/5 C..0--E..A-5 EF-1-.EF-1---.P-NO EF-5 EF-5 NO ET" 051 ET-051 P HO 2"Zt'0-340 0 GA 8 MO H/5 C 0 2 A B EF-1 EF"5 ET-015 EF-1 EF-5 ET-015 P NO HO P HO 2-IMO-350 0 GA 8 MO L/5 C 0 B EF-1 EF-5 ET-015 EF-1 EF-5 ET=015 P HO HO.P HO 2-H-102 2 CK 1 SA F/5 0/C C 2 A AC CF-1 CF-2 R YESP NOTE 14 SLT-1-SLT-2-----R YESP NOTE 1--2-RH-108E 0 CK 8 SA K/9 C 0 2 A C CF1 CF-3 C HOP NOTE 7  


0..~DONALD C.COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SU@DRY SHEET-UNIT 2 SYSTEN-NA)K'EMERGENCY=CORE COOLING" RHR---FLOH DIAGRAM: 2"5143"35 RUN DATE AND TIME: 14SEP87:13:28 VALVE--=--
0 SYSTEN-NA)K'EMERGENCY=CORE COOLING VALVE--=--    -
-----------I VALVE-POSITION-I
RHR
-=--=-=.ASME SECTION XZ-I I NASSER REV TYPE SIZE ACT F.D.I POHER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
                                              --I VALVE SU@DRY SHEET VALVE- POSITION-I         =
TYPE COORDI OPER-.FUiiCT ICL RE@IZRED-PERFORMED-MiODE 2-IMiO-312 0 GL 2 MO J/5 0 0/C 2 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P NO HO P NO 2-ZMO-314 0 GA 8 MO K/6 0 0/C 2 A B EF"1 EF-5-ET-034 EF-1 EF-5 ET"034 P NO NO=P==--HOp HOTE-3 2-ZMO-315 0 GA 8 MO C/7 C C/0 1 A B EF-1 EF-2=EF=5.--EF=5 ET-033 ET-033 C YES'OTE 4 HO C HO 2=ZMO=316.
                                                                                      ~
-.0-=-GA---8=.-MO-C/7-0.-.-0/C--2 A B EF-1====-EF"2..--C=-YES>HOTE-4 f F-5 EF-5 HO ET-033 ET"033 C NO 2-IMiO-320 0 GA 14 MiO" L/9 0 0/C 2 A B EF-1 EF-5 ET-128 EF-1 EF-5 ET-128 HO NO HOp NOTE 3 2-ZMO-322 0 GL 2 MO M/5 0 0/C 2 A B EF-1 EF"1 EF-5 EF"5 ET-011..ET-Oll P HO NO P HO 2-ZMO-324 0 GA 8 MO M/6 0 0/C 2 A B EF1 EF-5=ET-035 EF-1 P EF-5-ET-035 P NO HO=HOp NOTE 3 0 DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU)C)ARY SHEET-UNIT 2 SYSTEMIZE EMERGENCY CORE COOLING=RHR====FLON DIAGRAlk:~143."35 RUH DATE AND TIMiE: 14SEP87:13:28 VALVE=.I.VALVE.POSITION I I I HUtiBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORDI OPER FUNCT=ICL=ASME SECTION XI PRIM TEST TEST TEST RELIEF REQUEST(S)
DONALD C. COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL FLOH DIAGRAM: 2"5143"35 UNIT 2
REQUIRED PERFORMED MODE 2-GCR-314 0 GL 1 A G/2 0 2 A EF-1 EF-5 EF-7 ET=003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P NO HO P HO P HO R YES>ti'OTE 1 LCM=129 2 GA 14=MO E/8 1==-P--A=EF-1-EF-5 ET-121 SLT-1 EF-2=EF"5 ET"121 SLT"1=YES>NOTE 2 HO HO R HOp NOTE 1 2-ICM-305 0 GA 18 MO D/9 C 0 2 A A EF-1 EF-1 EF-5 EF-5 ET=049..=ET-049 SLT-)SLT-2 P NO tR P HO R YES>NOTE~CM=306--O=GA.=-18.MO.=D/9 C===0 2 A A EF=l EF-5 ET-049 SLT-1 EF-1 EF-5 ET-049 SLT-2 P HO NO P HO R YES'OTE 1 2-IMiO-128 2 GA 14 MO B/8 C 1 P B EF-1 EF"2 EF"5 EF-5 ET=134 ET"134 YES>NOTE 2 HO HO 2-IMO-310 0 GA 14 MO M/9 0 0/C 2 A B EF-1 f F-1 EF=5..EF=5 ET-148 ET-148 P NO HO P ttO~NOTE 3  
                                                                                        =   -= . 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..0 DONALD C.COOK NUCLEAR PLANT SECOHD TEH YEAR INTERVAL VALVE SVYd&RY SHEET-UNIT 2 SYSTEM-NAME:
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)
-EMERGENCY-CORE-COOLIHG=
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
SZS=.==FLON DIAGRAM:-2=5142-28 RUN DATE AHD TIME: 14SEP87:13:28 VALVE=-.---.--I-.VALVE POSITION-I--
~CM=306-   O=GA =-18.
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)
                  .         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
TYPE.COORDI OPER FUHCT ,ICL-=-==REQUIRED.PERFORMED MODE 2-SI-142" L3 0 CK 1.5 SA C/2 C 0 1 A C CF-1 CF-2 R YES1 NOTE 6~~42=L4 0=CK M.5==SA.=C/1 C.0 1=A=C CF-1 CF-2 R YES>NOTE 6 2"SV-96 0 REL 0.75 SA J/8 C 0 2 A C TF-1 TF-1.R HO 2-SV-97 0 REL 0.75 SA J/4 C 0 2 A C TF"1 TF-1 R HO 2"SV-98-N 0 REL 0.75 SA C/9 C 0 2 A C TF-1 TF-1 HO~VM8-S 0.--REL=0.75 SA-E/8 C=-0==-2 A C-TF-1 TF-L=R NO DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SV>SORY SHEET-UNIT 2 SYSTEN-NAHE:=EHERGENCY-CORE COOLING-=SZS-=-FLON DZAGSN:=2-5142=28.=.
                                                                                  .. fF-1 EF=5 ET-148 P
RUiN DATE AND TZHiE: 14SEP87:13:28 PEEVE=----l SAEVA POSITIiil I---.---ASEENESTIii.XI I I NASSER REV TYPE SIZE ACT F~D I POHER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)
P NO HO ttO~ NOTE 3
TYPE=COORD I OPER-RLCT I CL--.REQUIRED-..PERFORHED NODE 2-IRV-252 0 GL 1 A J/5 0 3 A B EF-1 EF"1 EF-5 EF-5 EF-7 EF-7 ET=.005---.ET-005 P P NO NO NO NO 2-IRV-255 0 GL 1 A H/6 0 2 A B EF1 EF-1---EF-5--=-=--EF--5-EF-7 EF-7 ET-004 ET"004 P NO W-P NO P NO 2-SZ-101 0 CK 8 SA H/8 C 0 2 A C CF-1 CF-3 R YESE NOTE 5 2-S1-104-N=O~K=-0..75=SA
-E/9--=C--=---0--.--2-=A=C--CF-1=--=--.CF-1-=.---P.N)-2-SZ-104-S 0 CK 0.75 SA J/9 C 0 2 A C CF-1 CF-1 P NO 2-SI-110-N 0 CK SA E/9 C 0 2 A C CF-1 CF-2 R YESP NOTE 5 2-SI-110-S 0 CK SA H/9 C 0 2 A C CF-1 CF-2 R YESS NOTE 5 2=S~26-----0=-CK==~--SA-H/6=0-C 2 A-C=-CF=i===CF-1=P NO 2-SI-142-L1 0 CK 1.5 SA C/1 C 0 1 A C CF-1 CF-2 R YES>N)TE 6 2-SI-142-L2 0 CK 1.5 SA C/2 C 0 1 A C CF-1 CF-2 R YES>NOTE 6


DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUY!CRY SHEET" UiHIT 2 SYSTEM=NAME
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--
=-EMERGENCY-CORE=-COOLING-SIS--=-=-
I                     I
-FLOH-DIAGRAM:=-2-5142-28----
                                                                                          =ASMEMECTION XZ HUM8ER    REV   TYPE SIZE ACT F.D. I POHER        SAFETY ICD A/P   CAT   PRIM TEST       TEST       TEST RELIEF REQUEST(S)
RUH DATE AHD TIME: 14SEP87:13:28 VALVE===---==---I=VALVE POSITXON I-I I AStiE-SECTION-XZ NUiiBER REV TYPE SIZE ACT F.D.I POWDER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE. 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
--TYPE-COORD I-OPER.FUii'CT--ICL--=------REQUIRED PERFORMED..-MODE 2-IMO-262 0 GL M0 L/8 0 0/C 2 A B EF-1 EF-5 ET-012 EF-2 Ef-5 ET-012 YES>NOTE 4 NO NO 2-ZMiO-263 0 GL 2 MO L/8 0 0/C 2 A B EF-1 EF-5=ET-012 EF-2 EF-5 ET-012-C YESp NOTE 4 NO C-NO 2-ZMiO-270 0 GA 4 MO E/9 0 0/C 2 A B EF"1 EF-1 P NO EF"5 EF-5=..-=-HO ET-024 ET-024 P HO 2=Z)0=275=0-GA-4.-----MiO-.E/8 0--=-0/C---2-A--B--=EF-1-----EF-5 ET-020 Ef-1 EF-5 ET-020 NO HO NO 2-ZMO-361 0 GA 4 MO G/9 C C/0 2 A EF-1 EF-5 ET"009 EF-1 EF-5 ET-009 2-ZMO-362 0 GA 4N)G/9 C C/0 2 A B EF-1 EF-5-.---ET-009 EF-)EF-5 ET-009.=NO NO-NO 2-IRV-251 0 GL 1 A H/5 0 2 A EF-1 EF-5--=---EF-7 ET-004 EF-1 P-EF-5---------EF-7 P ET-004 P
~~42=L4        0= CK M.5==      SA.=  C/1    C    . 0         1= A= C     CF-1         CF-2           R    YES> NOTE 6 2"SV-96        0   REL  0.75  SA    J/8    C         0          2 A C    TF-1         TF-1         .R    HO 2-SV-97        0   REL  0.75  SA    J/4    C          0         2 A C    TF"1         TF-1           R    HO 2"SV-98-N      0   REL  0.75  SA    C/9   C         0         2 A C    TF-1         TF-1                 HO
~VM8-S        0. -REL  =0.75  SA  E/8    C       =- 0 ==      2 A C    TF-1         TF-L      =   R    NO


DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE StRQARY SHEET-UNIT 2 SYSTEM-NAME:=EMERGEHCY-CORE--COOLING=-SZS--
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.=.
---FLON-DZAGRAM:
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)
2-5142-28=.RUN DATE AHD TIME: 14SEP87:13:28 VALVE I--VALVE-POSITION-I-=----------=-=--A%1E SECTION XZ-I I HOSER REV TYPE SIZE ACT F AD.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE=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
--TYPE-COORDI-OPER
                                                                                  -- -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
----FUui:T
--ICL------REQUIRED.
-PERFORMED..
MODE 2-ICM-250 0 GA H/2 C 0/C 2 A A EF-1 EF-5 ET-012 SLT-1=.EF-2 EF-5 ET-012 SLT-2 C C R YESp NOTE NO NO-YES>=NOTE 2-ZCM"251 0 GA MO H/3 C 0/C 2 A A EF-1 EF-2 C YES>NOTE 1 EF-5-.-==---EF-5----==-.-=-=-=-NO ET-012 ET-012 C HO SLT-1 SLT-2 R YES@NOTE 2"ZCM-260 0 GA 4 MO C/9 0 0/C 2 A A EF-1 EF-5 ET-012 SLT-l...EF-1 EF-5 ET-012.SLT-2 P HO NO P HO R--YES>NOTE 2 2-ICM"265 0 GA MO C/8 0 0/C 2 A A EF-1-EF=5-----ET-012 SLT"1 EF-1 E F--5-=----ET-012 SLT"2 P NO-=---HO=P NO R YES>NOTE 2 2-IMO-255 0 GA MO J/7 C 0 2 A 8 EF-1 EF-5 ET-015 EF-1 EF-5 ET-015 P NO HO P HO 2-IMO"256 0 GA 4 MO J/6 C 0 2 A B EF-1 EF-1 P HO EF-5 EF"5 HO ET-012-=-ET-012----==-=P=-NO-2-IMO-261 0 GA 8 MO M/8 0 0/C 2 A B EF-1 EF"2 C YES>HOTE 3 E F-5----=--E F-5-=-.------NO=--ET-015 ET-015 C HO e
~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUt%JARY SHEET-UtlIT 2 SYSTEH-NAHE:
-PAS-CONTAItCiEttT-.HYDROGEN--===
-----=--FLON DIAGRAH:--2-5141D-8
------RUiil DATE AND TIHiE: 14SEP87:1'5:28 VALVE-=--=-------I-VALVE-POSITION-I---..---------ASt4E-SECTION XI I I NJJEJER REV TYPE SIZE ACT F.D~I PONER SAFETY I CD A/P CAT PRItl TEST TEST TEST RELIE F REQUEST(S)
--TYPE-COORDI=OPER
--FUNCT-ICL-------REQUIRED=--PERFORHED HODE-2-ttS-283 2 CK 0.5 SA C/8 C 0/C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 2 R YES>NOTE 1 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUm)ARY SHEET-UNIT 2 SYSTEN-NAHE:
-PAS-CONTAI)RENT=HYDROGEN.-
---=-----F LON-DIAGRAH:
-2"5141D-8 RUH DATE AND TINE: 14SEP87:13:28-VALVE I=-VALVE-POSITION
-I----I I ASNE-SECTIOH XX--NU)SER REV TYPE SIZE ACT F~D I PONER SAFETY I CD A/P CAT PRIH TEST TEST TEST RELIEF REQUESTERS)
--TYPE-COORDI-OPER---
-FUHCT---ICL--:=-----REQUIRED----PERFORNED
--.-NODE 2-ECR-25 0 GL 0.5 A B/1 C 0/C 2 A A EF-1 EF-5 EF-7-ETF-002--SLT-1 EF-1 EF-5 EF-7 ETF-002.-SLT-2 P P-P R NO NO HO NO-----YES'OTE 1 2-ECR-26-=O=GL--0.5==-A----B/3-----C
=-----0/C-----2----.A--A
---EF-1=-----.--EF-1 EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT-1-==-=-=-SLT-2--P-=-HO NO P HO P HO-R--=-YES>NOTE 1--2"ECR"27 0 GL 0.5 A B/3 C 0/C 2 A EF-1-EF-5-EF-7 ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P HO NO P HO P HO R YES>NOTE 1 2-ECR-28 0 GL 0.5 A B/4 C 0/C 2 A EF-1 EF-5=EF-7----ETF-002 SLT-1.EF-1 EF-5 EF-7------ETF-002 SLT-2 P---P P R HO Na WO NO YES'OTE 1 2-ECR-29 0 GL 0.5 A B/4 C 0/C 2 A A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO-=ETF-002-=-.---ETF-002-------P-==HO SLT-1 SLT-2 R YESp NOTE 1 0~DOHALD C.CNK NUCLEAR PLANT SECOiND TEH YEAR INTERVAL VALVE SU2 fARY SHEET-U22)IT 2 SYSTEH-HA)fE:=-PAS-CONTAZtRENT HYDROGEN===FLOH DIAGRA)f: 2221410-8.=RUN DATE AND TINE: 14SEP87:13:28 VALVE=---===-I-VALVE-POSITION I-I I ASNE-SECTIOH XI-NU00BER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRZH TEST TEST TEST RELIEF RE@JEST(S).TYPE COORD I-OPER-=-FUAACT=ICL.REQUIRED PERFOR'fED JfODE-2-ECR-20 0 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ETF=002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P NO N)P NO P=tiO R YESB NOTE 1 2-000-21 0-Gl-0.0-.-2-.-0/2-C-..-.0/0-.A=-A EF-1 EF-5 EF-7 ETF-002-SI.T-1-EF-1 EF"5 EF-7 ETF-002 SLT-2 P---W-HO P NO P NO R YES>NOTE 1 2-ECR-22 0 GL 0.5 A B/2 C 0/C 2 A EF-1.-EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5-EF-7 ETF-002 SLT-2 P P R NO NO NO NO YES>NOTE 1 2-ECR-23 0 GL 0.5 A B/1 C 0/C 2 A EF-1 EF-5----=-EF-7-ETF-002 SLT-1 EF"1 EF-5 EF-7-ETF"002 SLT-2 P P R HO NO NO I)YESB NOTE 1 2-ECR-24 0 GL 0.5 A B/3 C 0/C 2 A EF-1 EF-5 EF-7 ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P P P R NO HO NO NO-YESB NOTE 1 0
0 0 DOHALD C.COOiti NUCLEAR PLANT SECOHD TEH YEAR INTERVAL VALVE SURSLRY SHEET-UHIT 2 SYSTEH-NAHE:
-PAS-CONTAICKNT=HYDROGEN--.-
=-=---FLOH-DZAGRAH:
..2=5141D-.8-RUH DATE AND TINE: 14SEP87:13:28 VALVE I-=VALVE-POSITION-I I l AS!%-SECTION-XL HOSER REV TYPE SIZE ACT F.D I PONER SAFETY ICD A/P CAT-TYPE-COORDI-OPER
---FUHCT--ICL--------=---PRIH TEST TEST TEST RELIEF REQUEST(S)
REQUIRED-.-PERFORHED--
-NODE.2"ECR-15 0 GL 0.5 A A/1 C 0/C 2 A A EF"1 EF-5 EF-7 ETF.=002 SLT-1 EF-1 EF-5 EF-7=.ETF.-002 SLT-2 P NO HO P HO P HO R YES>HOTE 1 2-ECR-16--0-GL-=0.5=----A---A/3==C--0/C-----2---A---A.----EF-1----EF-1 EF-5 EF-5 EF-7 EF"7 ETF-002 ETF-002 SLT-1.NLT=2-..-=-.--P----.-VQ HO P HO P HO R=-..YESp NOTE.3-=2-ECR-17 0 GL 0.5.A A/3 C 0/C 2 A A EF1 EF-.5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P P R NO HO HO HO YES>HOTE 1 2-ECR-18 0 GL 0.5 A A/4 C 0/C 2 A A EF-1 EF-5 EF-7=-ETF-002 SLT-1 EF-1 EF-5-=EF=?=ETF-002 SLT"2 P==P R HO HO HO-HO YES>NOTE 1 2-ECR-19 0 GL 0.5 A A/4 C 0/C 2 A A EF-1 EF-5 EF-7-ETF-002-SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P HO HO P HO P---..HO R YES'OTE 1 e'
0=D(NALD CD COOK NUCLEAR PLANE SECOND TEN YEAR IttTERVAL~VALVE SvtuQRY SHEET-UiiIT 2 SYSTEtl-NAttE:
-PAS-COttTAIt"tENT-HYDROGEN-=-
-==-=-FLON DIAGRAtt t--2-51410-8 RWi DATE AND TIHiE: 14SEP87:13:28
----VALVE---I-VALVE-POSITION-I-
----=--I.I--.ASHE SECTION Xl-tmiiSER REV TYPE SIZE ACT F~D.I POHER SAFETY ICD A/P CAT PRltt TEST TEST TEST RELIEF REQUEST(S)
=-.-TYPE-COORDt--OPER-==-FUMCT--ICL-----=-RE@JIRED--:
-PERFORHED HiODE-2-ECR-10 0 GL 0.5 A C/8 C 0/C 2 A A EF-1 EF-5 EF-7 ETF-002 SLT-1 EF-1 EF"5 EF-7 ETF-002 SLT-2 P P R HO HO HO HO YESp NOTE 1 2-ECR-ll-.-0-GL=0.5---A--==A/2=-C
--0/C--=2--A=-A-===-EF-1-----
----EF-1 EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT-1=-----.SLT-2-P--HO-NO P NO P HO R--=-YES'OTE 2-ECR-12 0 GL 0.5 A A/2 C 0/C 2 A A EF1--EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF"002 SLT-2 P P P R HO-HO---HO HO YES'OTE 1 2-ECR-13 0 GL 0.5 A A/1 C 0/C 2 A A EF-1 EF-5-EF-7---ETF-002 SLT-1 EF-1 EF-5 EF-7-ETF-002 SI.T-2 P P R tiO HO HO HO YESp NOTE 1 2-ECR-14 0 GL 0.5 A A/3 C 0/C 2 A A EF-1 EF-5 EF-7.ETF-002 SLT-1 EF-1 EF-5 EF-7-ETF-002 SLT-2 P-P-R NO NO NO NO YESp NOTE 1


SYSTEM-NAME-:
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----
-NUCLEAR-SAHPLING-DONALD C.COOK NUCLEAR PLANT SECOND TEll YEAR INTERVAL VALVE S~~RY SHEET-UNIT 2-F LON-DIAGRAH: 5141A-30 RUN DATE AND TIME 14SEP87:13:28-VALVE I VALVE-POSITION-I-=-------=----=--ASHE SECTION-XI--
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)
==--I I tiKRSER REV TYPE SIZE ACT F.D I PONER 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
TYPE=COORDI OPER--FUNCT ICL--REQUIRED-PERFORMED-HODE 2-MCR-253 0 GL 0.5 A B/1 0 2 A B EF-1 EF-5 EF-7 ETF-002-EF"1 EF-5 EF-7 ETF-002 P NO NO P NO--P NO 2-HCR-254 0 GL 0.5 A B/1 0 2 A B EF-1 EF-5--EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P NO NO P NO P NO
                                                                                    = 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


SYSTEH-NAHE:
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--  -
-NUCLEAR-SAttPLItiG DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SSDtARY SHEET-UNIT 2 FLOH=DZAGRAtt:.2-5141A-30 RUiH DATE AND TItlE: 14SE F87:13: 28-.-VALVE--------=---I-VALVF-POSITION-I I I h&#xc3;ltSER REV TYPE SIZE ACT F.D.I POHER SAFETY I CD A/P CAT TYPE COORDI-OPER
FLON-DZAGRAM: 2-5142-28 =.
--RPitCT--ICL ASHE-SECTION XZ PRIH TEST TEST TEST RELIEF REQUEST(S)
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
REQUZRED PERFORHED HODE-2-DCR-301 0 GL 0.5 A 8/2 0 C 2 A 8 EF-1 EF-5 EF-7 ET-003 EF-1 EF-5 EF-7 ET-003.P NO NO P HO P-NO--2-DCR-302 0 GL 0.5 A 8/3 0 C 2 A 8 EF"1 EF-5----EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P HO----=-t'O-=-P NO P NO 2-DCR"303 0 GL 0.5 A 8/3 0 A 8 EF-1 EF-5 EF-7 ETF-002-EF-1 EF-5 EF-7-ETF--002 P NO HO P NO P--=HO=--2-DCR"304 0 GL 0.5 A 8/3 0 C A 8 EF"1=-EF-5 EF-7 ETF-002 EF-1 EF-5--EF-7 ETF-002 P NO NO P NO P HO 2-MCR-251 0 GL 0.5 A 8/2 0 2 A 8 EF-1 EF-5 EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002 P NO HO P HO P NO 2-ttCR-252 0 GL 0.5 A 8/2 0 C 2 A 8 EF"1-EF-5 EF-7 ETF-002 EF-1-=-EF-5-EF-7 ETF-002 P NO HO-.P HO P NO C SYSTEtl-NAttE:
                                                                    --  -REQUIRED.
-NUCLEAR-SANP LING DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR IttfERVAL VALVE S4tt&RY SHEET-UNIT 2 FLON-.DIAGRAtt: 5141 ----RUiN DATE AHD TINE: 14SEP87t13:
TEST PERFORMED..
28 VALVE----I-VALVE-POSITION I I I ASNE-SECTION-XZ HlESER REV TYPE SZ2E ACT F.D.I PONER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)
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 ---==-
TYPE-COORDI-OPER-
                                                                                          =                      .   =-=-=-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
--FUNCT--ICL-=-----==--REQUIRED
                                                                            -EF=5 --     E F- =-         -=---   HO=
-=PERFORttED
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
----tlODE--2-HCR-108 0 GL 0.5 A 0/6 0 2 A A EF-1 EF-5 EF-7 ETF=002-.-SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P NO HO P NO...P--NO R YES'OTE 1 2-NCR-109-0-Gl 0.5-A-D/5--0--C---2---A--A==-EF-1--=-=---EF-1---=EF-5 EF-5 EF-7 EF-7 ETF-002 ETF-002 SLT"1----SLT-2-.P--HO-=NO P HO P NO-R--YES>NOTE 1 2-HCR-110 0 GL 0.5 A D/6 0 C 2 A A EF-1 EF=-5------EF-7 ETF-002 SLT-1 EF-1 EF-5--EF-7 ETF-002 SLT"2 P P P R NO-NO-NO HO YES>NOTE 1 0
                                                                                                                          =-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 -=   .
DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUMttARY SHEET-UNIT 2 SYSTEM-NAME:=NUCLEAR-SAMPLIHG
                                                                                                                  - -     NO= -
=--.------.-----=-FLON DIAGRAM:=2"5141-27=
ET-015          ET-015                C       HO
-.--RUH DATE AHD TIME: 14SEP87:13:28 VALVE I--VALVE-POSITION I I ASME-SECTION-XZ HKtDER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
---------TYPE COORDI-OPER----FLNCT--ICL---==REQUIRED-PERFORMED=*MODE 2-ICR-5 0 GL 0.5 A C/5 0 C 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF-5 EF"7 ETF-002 SLT-2 P HO NO P HO P NO R YES'OTE 1 2-ZCR-6-=0-Gl 0.5----A--D/5-=0-----C-2--A--=A-=-EF-1--" EF-5 EF-7 ETF-002 SLT-1=--EF-1-EF-5 EF-7 ETF-002 SLT-2 P=-HO NO P NO HO-:R-----YES'OTE 1 2-HCR-105 0 GL 0.5 A C/7 0 C 2 A EF-1-EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P P P R NO HO HO HO YES>NOTE 1 2-HCR"106 0 GL 0.5 A C/7 0 EF-1 EF-5 EF-7 ETF>>002 SLT-1 EF"1 EF-5-EF-7=-=-ETF-002 SLT-2=----P-P R HO NO.HO.-HO YES>HOTE 1 2-HCR-107 0 GL 0.5 A D/6 0 C 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF-5 EF-7 ETF-002 SLT-2 P-P R NO HO HO HO YESp HOTE 1 SYSTEtt=NANE:
-CONPONENT-COOLIHG
--DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR IHTERVAL VALVE SUtCtARY SHEET-UNIT 2 FLON-DIAGRAN:=-2"51358-14
---.==-=RUN DATE AND TlttE: 14SEP87: 13: 28 VALVE-=---------=I VALVE-POSITION I=-------I I ASttE=SECTION-XZ-HUttBER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)
----TYPE-COORD I OPER--FLRCT-ICL----------=REQUIRED-----PERFORttED
--l40DE=-2-CCI't-243-25 2 CK 1 SA C/5 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp NOTE 2 YESp NOTE 1 2-CCN-243-72 2 CK 1 SA C/5 0 2 A AC CF-1 SLT"1 CF-2 SLT"2 R R YESp NOTE 2 YESp NOTE 1 2-CCN-244-25 2 CK 1 SA C/6 0 2 A AC CF1 SLT-1 CF-2 SLT-2 R R YESp ttOTE 2 YESp NOTE 1 2-CCW-244-72 2 CK 1 SA C/6 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp HOTE 2 YESp NOTE 1 2-SV-122-258 0 REL 1.5 SA B/6 C 0 3 A C TF1 TF-1 R HO 2-SV-122-728
-0=-REL=1.5-.--SA=-B/6---C-.--0---=3--A---C-=-==TF-1=-----TF-1-R NO


SYSTEM-NAME:
e
-COMPONENT-COOLING DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE St&DARY SHEET-UtGT 2 FLOH DIAGRAM:-2-51358-14 RUH DATE AHD TIME: 14SEP87: 13: 28-VALVE-=---=----.-=I-VALVE-POSITION-I I I HUAABER REV TYPE SIZE ACT F.D.I POHER SAFETY!CD A/P CAT-TYPE COORDI OPER=--FACT-ICL ASME-SECTZOiN
                                                                                  ~
=Xl-=-----PRIM TEST TEST TEST RELIEF RE@JEST(S)
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:
REQUIRED PERFORMED.MODE 2-CCM-430 0 GL 1.5 MO D/6 C 0/C 2 A A EF-1 EF-5 ET-018---SLT=1 EF-1 EF-5 ET-018 SLT-2 P P R HO NO NO YES'OTE 1 2-CCM"431 0 GL 1.5 MO D/6 C 0/C 2 A'EF-1 EF-1-==---=--EF-5-.-=EF-5 ET-015 ET-015 SLT-1 SLT-2 P NO NO P HO R YES>HOTE 1 2-CCM&32 0 GL 1.5 MiO D/6 C 0/C 2 A A EF-1 EF-5 ET-018 SLT-1 EF-1 P NO EF-5 NO ET-018 P HO SLT-2-R YES HOTE 1 2-CCM-433 0 GL 1.5 MiO D/6 C 0/C 2 A A EF-1-=-EF-5 ET-019 SLT-1 EF"1 EF"5 ET-019 SLT-2~P P R NO NO HO YES>NOTE 1 2-CCR-440 0 GL 1.5 A D/6 0 A EF-1 EF-5 EF-7 ET-008 SLT-1 EF-1 EF"5 EF-7 ET-008 SLT-2 P P R NO NO NO HO YESR NOTE 1 5-CCR-441 0-51--1.5 A..5/6 0---2--A--A--EF-1----EF-5 EF-7 ET-005 SLT-1 EF-1 EF-.S EF"7 ET-005 SLT-2 P P P R HO NO HO NO YES>NOTE 1  
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


0 0 DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SmDQRY SHEET-UHZT 2 SYSTEM NAME-'COMPONENT.
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
COOLING FLOH DIAGRlL): 2"5135A"30 RUN DATE AND TIME: 14SEP87:13:28 VALVE-==-=.I..VALVE=POSITION I.-.-..---I I--ASME SECTION XZ-NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST.TYPE COORDI OPER-FACT ICL.REQUIRED TEST PERFORMED TEST RELIEF REQUEST(S)
                  -VALVE                 I =-VALVE-POSITION- I     -- -                             ASNE- SECTIOH  XX--
MODE 2-CYA)-416 0 BF 16 MO G/5 0 0/C 3 A B EF-1 EF-5 ET-103 EF-1 EF"5 ET"103 P NO HO P NOp NOTE 1 2-CYiO-419 0 BF 14 MO E/5 C 3 A B EF1 EF-1 P HO EF-5 EF-5 HO ET-053--ET"053--P NO-2-CMO-420 0 BF 16 ViO H/4 C/0 0 3 A B EF-1 EF-1 EF-5 EF-5 ET-066 ET-066 P HO HO P NO 2=CM0=429 0=BF==14 MO E/5 C 0 A B EF 1 EF-1 EF-5 Ef"5 ET-054 ET-054 P NO HO P HO 2-CRV-412 0 GL 4 A K/1 0 C A B EF"1 EF-5 EF-7-ET-019-EF-1 EF-5 EF-7 ET-019 P NO NO P NO-P-.-NO---2-SV-60 0 REL 3 SA L/1 C 0 3 A C TF1 TF-1 R HO 2-SV-72 0 REL 1 SA E/5 C 0 A C TF-1 TF-1  
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


SYSTEH-NAME:
0                                                DOHALD
-COMPOiNENT-COOLING
                                                                                    ~
---==---DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE  
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 h&#xc3;ltSER  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==
==SUMMARY==
SHEET-UNIT 2.=-====-=*-FLOH DIAGRAH: 2-5135A RUN DATE AND TIHE: 14SEP87:13:28-VALVE-------=-I--VALVE=POSITION I I I NUiSER REV TYPE SIZE ACT F.D I POHER SAFETY LCD A/P CAT PRIM TEST TYPE-COORDI OPER-=-FUNCT-ICL--.------REQUIRED ASHE-SECTION-XZ TEST TEST RELIEF REQUEST(S)
SHEET         - UNIT 2 SYSTEH-NAME:COMPOiNENT-COOLING--    ==
PERFORMED-MODE 2-CCN-176-E 0 CK 16 SA L/4 C/0 0 3 A C CF1 CF-1 HO 2=CCN=176=N=O CK=--16===SA-K/4 C/0.0==3=A C.--CF-l.CF"1 P.NO 2-CHO-410 0 BF 16HO H/4 C/0 0 A B EF"1 EF-l.P HO--=-=--EF=5-----EF-5---=-NO-ET-055 ET"055 P KO 8=888881i=0
                                        -      . =-====-= *-FLOH DIAGRAH:       2-5135A                 -VALVE             - =I--VALVE=POSITION I
-88~8==80=H/8--8.EF-1 EF-5 ET-053--P=---HO NO P NOp NOTE 1 2-CHiO"412 0 BF 16 HO L/3'0/C A B EF1 EF-5 ET-054 EF-1 EF-5 ET-054 NO NO NO>NOTE 1 2-CYA)-413 0 BF 18 HO L/5 0 0/C 3 A B EF-1 EF-1 EF-5 EF-5---=-ET-053--=--ET-053 P HO NO--=P-----NO 8 HOTE 1 2"CHO&14 0 BF 16 MO K/3 0 0/C 3 A B EF-1 EF"1 EF-5--EF-5 ET-054 ET-054 P NO NO P NOp NOTE 1 2=CH0=415 0 BF~6.-HO.H/5-0..0/C-.3-.A B.--EF.-1..--EF-5 ET-054 EF-1---P HO EF-5 NO ET-054 P NO>NOTE 1 SYSTEH-NAt%:
I I
-CC fPONENT-COOLING=
ASHE -SECTION-XZ NUiSER   REV TYPE   SIZE     ACT F.D     I POHER       SAFETY LCD   A/P   CAT PRIM TEST                   TEST            TEST      RELIEF REQUEST(S)
DONALD C.COOK NUCLEAR PLANT RUN DATE AND TINE: lOSEP87:13:28 SECOND TEN YEAR INTERVAL VALVE SlM1ARY SHEET-UNIT 2=FLOH.DIAGRAH: 2-5135-30.--VAlVE-=---------I-VALVE-POSITION I---l I ASHE SECTION XI NEVER REV TYPE SI2E ACT F.D.I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF RE(PEST(S)
TYPE-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
TYPE-.COORD)
                                                                              --=-   =-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
OPER-=-.FUINCT.ICL=..REQUIRED PERFORHED HODE 2-SV-68 0 REL 1 SA J/2 C 0 3 A C TF-1 TF-1 R NO E=RII.-.T1 0-REI 3-:--EA--..-LF3 C-0-3..A.-0..TF-3.TF-3 R RC  
                                                                                  ---= -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


SYSTEtt-NAME.CO'tPONEttT-COOLING
0                                                                        ~
~~DONi ALD C.COOK NUCLEAR PLAttT SECOitD TEtt YEAR INTERVAL VALVE SUGARY SHEET-UittIT 2 FLO)L DIAGRAM: 2-5135-34 RUN DATE AND TIME: 14SEP87:13:28-VALVE-.I VALVE.POSITION-I
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
.-ASME=SECTIOH
                    -VALVE--      -==-- I I
=XZ I I NUtiBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRZt1 TEST TEST TEST RELIEF REQUEST(S)
VALVE-POSITION-I I
TYPE COORDI.OPER FUNCT ICL REQUIRED PERFORMED MODE 0 2-CCH-135 0 CK 2.5 SA B/3 0 2 A AC CF1 SLT-1 CF"2 SLT-2 R YESp NOTE 4 R YESp NOTE 2 2-CRY-445 1 BL 6 A L/5 0 C/0 3 A B EF-1 EF-5 EF-7 ET-034 EF-1 EF-5 EF-7 ET-034-P P NO ttO NO HO 2-CRV-470 0 GL 6 A G/1 0 3 A B EF1 EF-7.ET-HA EF-1 P N)ttOTE 5-YESp HOTE 5 HOTE 5-YESp NOTE 5 2=CRY=485=
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)
0.BF 10--A B/7 0 A-B-EF I EF-5 EF-7 ET-018 EF-1 E F-5 EF-7 ET-018 P-HO HO P NO P HO 2"SV"122 0 REL 1 SA D/3 C 0 A C TF"1 TF-1 R NO 2-SV-62 0 REL 1 SA 0/3 C 0 A C TF-1 TF-1 R HO 2=SV"63--O==REL=1.=SA E/3.C*0 3 A C TF-1 TF-1 R HO 2-SV-64 0 REL 1 SA C/3 C 0 A C TF-1 TF-1 R HO 2-SV-65 0 REL 1 SA tt/I C 0 3 A C TF"1 TF-1 R NO
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
=0 DONALD C.COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SUt01ARY SHEET-UNIT 2 SYSTEN-NAt tE.:-CfRPONENT-COOLItiG
                                                                                -- 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)
--=----==-----FLOtL DIAGRAIH--2-5135-34
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
--=-=--RUN DATE AND TIttE: 14SEP87:13:28 VALVE---------------I-VALVE=POSITIOtt=l I I MEMBER REV TYPE SIZE ACT F.D I POttER SAFETY I CD A/P CAT TYPE-COOROI-OPER
                                                                                -= 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
-FWCT ICL=-----ASttE SECTION XZ-PRIH TEST TEST TEST RELIEF REQUEST(S)
REQUIRED----PERFORMED-
-.tlODE 2-CCR-455 0 GL 2 A 8/3 0 C A A EF-1 EF"5 EF-7 ET-005 SLT-1 EF-2 EF"5 EF-8 ET-005 SLT-2 C C C..R YESp ti'OTE 3 ttO HOp NOTE 3 HO YESp HOTE 2 2-CCR-456=0=GL- --=-A==D/4"--0 EF-5 EF-5 EF-7 EF-8 ET-005 ET-005-SLT-1---SLT" 2 C C R-2-==A---A=
-==EF-L--=--
==EF-2-=--------C--YESp HOTE 3--HO HOp NOTE 3 NO YESp NOTE 2 2-CCR-457 0 GL A D/4 0 C EF-1 EF-5-EF-7 ETF-005 SLT-1 EF-2-EF-5 EF-8 ETF-005 SLT-2 C C R YESp NOTE 3 NO HO NOTE 3 HO YESp NOTE 2 2-CCR-460 0 GL 3'C/4 0 C 2 A A EF-1 EF-5-EF-7--ET-010 SLT-1 EF-1 EF-5-----EF-7 ET-010 SLT-2 P-P P R HO NO-NO-=N)YESp NOTE 2 2-CCR-462 0 GL 3 A A/4 0 C 2 A A EF-1 EF-5 EF-7 ET-009---SLT-1 EF-1 EF-5 EF-7 ET-009-SLT-2 P P P R NO HO HO HO YESp HOTE 2


SYSTEM-NAHE-.-
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
COMPONENT-COOLING DOttALD C.COOK hRJCLEAR PLANT SECOND TEN YEAR ZttTERVAL VALVE SUtStARY SHEET-UttIT 2-FLON-DIAGRAH:-2-5135-34
                                                      =-. FLOW .DIAGRAM:-- 2-511%A-.27 UNIT 2 VALVE -=   ----     =-     -
-=-RUN DATE AND TIHE: 14SEP87:13:28 VALVE=-----l VALVE POSITION-I
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)
--I I ttUHBER REV TYPE SIZE ACT F.D.I POHER SAFETY!CD A/P CAT TYPE COORDI OPER---FUttCT--ICL
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
--ASHE SECTION XZ PRIH TEST TEST TEST RELIEF RWUEST(S)-REQUIRED-
                                                                        --- -------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
-==-PERFORMED-HODE 2"CCH"451 0 BF 8 HO E/4 0 C 2 A A EF-1 EF-5 ET-026-SLT-1-EF-2 EF-5 ET-026-SLT-2 C YES'OTE 1 NO C NO R-YES'OTE 2 2-CCH-452 0.BF HO E/5 0 C 2 A A EF-1 EF-5==------ET-023 SLT-1 EF-2 EF>>5 ET-023 SLT-2 C R YES'OTE 1-tiO-ttO YES>NOTE 2 2-CCH-453 0"GL 4 HO E/4 0 2 A A EF-1 EF-5 ET-030 SLT-1=----EF-2 EF-5 ET-030 SLT-2 C C R YES'OTE 1 NO NO YES>ttOTE 2-2-CCH-454 0 GL HO E/5 0 C 2 A A EF-1 EF-2 EF-5-===-=EF-5-ET-030 ET-030 SLT-1 SLT-2 C R YES>NOTE NO NO YES>NOTE 2-CCtf-458 0 BF 8 HiO A/2 0 2 A A EF-1 EF-5 ET-023 SLT-1 EF-2 EF-5 ET-023 SLT-2 C C R YES>NOTE NO NO---YES'OTE 2-CCH-459 0 BF 8 HO B/2 0 2 A EF-1 EF-2-EF-5-----EF-5 ET-024 ET-024 SLT-1 SLT-2 C YESi NOTE 1 NO-C NO R YES>NOTE
                                                                                - - ---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


DONALD C.COOi<NUCLEAR PLAtA'ECOND TEN YEAR INTERVAL VALVE SUl01ARY SHEET-UNIT 2 SYSTEM=NAME:
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
-CVCS-LETDOWN-8-CHARGING--
                                                                                            -- ASME SECTION XZ NUMBER     REV TYPE SIZE   ACT F.D. I POHER      SAFETY ICD    A/P   CAT   PRIM TEST       TEST       TEST RELZEF REQUEST(S)
--=-=-==--=-FLOW=DIAGRAM: 5129A-20--
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- =-
RUH DATE AND TIME: 14SEP87:13:28
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)
-VALVE-I VALVE-POSITION I I I ASME%ECTION-XI-NUMBER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
ET-006        -ET-006      -P-- -HO SLT-1          SLT-2         R    YES> HOTE 1
TYPE-COORDI-OPER
--FUiiiCT--ICL-=--------REQUIRED-
--=-PERFORMED-
--MODE.-2-QCM-250 0 GA MO C/8 0 2 A A EF-1 EF-2 E F-5 EF-5 ET-015 ET-015 SLT-1------SLT-2-C-R YES>NOTE 1 NO HO YES>NOTE 2 2-QCM-350 0 GA 4 MiO D/8 0 2 A A EF-1---EF-5 ET-009 SLT-1 EF-2---E F-5---ET-009 SLT-2 C R YES>NOTE 1 HO HO YES>NOTE 2 2-QMO-451 0 GA 4 MO J/5 0 2 A B EF"1 EF-5 ET-009 EF-2 EF-5 ET"009 C YES>HOTE 3 NO C HO 2-QMO-452 0 GA MO J/5 0 2 A B EF-1 EF-5-.-ET-006=-=-
EF-2 EF-5--ET-006 C YES>NOTE HO C-NO 2-QRV-400 0 GL 2 A K/4 C 0 2 A B EF-1 EF-1 P HO--EF-5-=-EF-5--------"=-=HO EF-7 EF"7 P HO ET-005 ET-005 P NO 2-SV-53 0 REL 3 SA M/2 C 0 2 A C TF-)TF-1 R-.SV-&i-.-0-REI~->A--E/4--C----.0----2 A---C---TF"1-=----TF-1 R--HO 4
~DOiRLD C.COOK NUCLEAR PLANT SECOND TEN YFAR INTERVAL VALVE SUED'RRY SHEET-UNIT 2 SYSTEH-NAHE:=-CVCS-LETDO'ruN-8-CHARGING-
---=-==-=-FLON-DZAGRAH:--2-5129"32-RUN DATE AND TINE: NSEP87: 13: 28-VALVE---I VALVE=POSITION I I I-ASHE-SECTION-XZ NLPiBER REV TYPE SIZE ACT F.D~(POHER SAFETY!CD A/P CAT PRZH TEST TEST TEST RELIEF REQUEST(S)-TYPE COORD I-OPER-FUNCT--ICL----REQUIRED-PERFORHED--HODE 2-SV-55 0 REL 0.75 SA K/7 C 0 2 A C TF-1 TF-1 R NO 2-SV-56=-=-0-REL==--0'5-SA--L/6 C-----0---2-A-C-TF-1----TF-1 R-NO 0-DOiiALD C.COOK NUCLEAR PLANT SECOiND TEN YEAR INTERVAL VALVE SUHHARY SHEET-UiNZT 2 SYSTEH=NAHE:
-CVCS.=-=LETDORI-S-CHARGING
-------==---FLOil-DZAGRAH:=-
2-5129 RUN DATE AND TINE: 14SEP87:13:28
-=VALVE I VALVE-POSITION I I I ASi lE=SECTION=XZ--HUl&ER REV TYPE SIZE ACT F.D.t POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
TYPE COORD)OPER--FUHCT ICL----REQUIRED..PERFORHED-HiODE 2-QHO-226 0 GA 2 Y>D G/7 0 0/C 2 A B EF-1 EF-5 ET-011 EF-1 EF-5 ET-Oll P NO NO P HO 2-QRV-200 1 GL 3 A H/3 0 0 A B EF-1 EF-3 EF-7 NOTE 8--ET-NA-----NOTE 8-P NO>HOTE 8 YES>NOTE 8-YES>NOTE 8-2-QRV-251 1 GL A H/5 0 0 2 A B EF1 EF-3 P HOp NOTE 9-EF-7-:----HOTE=9-------YESp NOTE 9 ET-NA NOTE 9 YES>NOTE 9 2-QRV-61---0=-GL-----3----A---C/2--C---0-----2 A--B--EF-1 EF-5 EF-7 ET-008 EF-1 EF-5 EF-7 ET-008 P-HO-NO P NO P HO 2-QRV"62 0 GL 3 A C/2 0/C 0 2 A B EF-1 EF-1 EF-5 EF-5 EF-7=-=---EF-7-=-ET-009 ET-009 NO NO HO-HO 2-SI-185---0--CK-.-.-8----SA K/5-C-0 2.--A--C--CF-1-Cf-2 R-YES'OTE 10 2"SV-51 0 REL 2 SA E/2 C 0 2 A C TF-1 TF"1 R HO 2-SV-52 0 REL 2 SA K/1 C 0 2 A C TF-1 TF-1 R HO 0~DONALD C.COOK NlCLEAR PLANT SECO'ND TEN YEAR INTERVAL VALVE SUYu'1ARY SHEET-UiHIT 2 SYSTEM-NAME:--CVCS--LETDOWN-8-CHARGING
---=----FLOH DIAGRAM:--2"5129-32 RUH DATE AND TIME: 14SEP87:13:28 VALVE-.-=-=-=--=.-.I VALVE POSITION I-I I----ASME SECTION Xl HUi'SER REV TYPE SIZE ACT F~D.I POHER SAFETY I CD A/P CAT-TYPE COORDI-OPER FUHCT ICL PRIM TEST REQJIRED TEST TEST RELIEF REQUEST(S)
PERFORMED MODE-2-IMO-910 0 GA 8 MO L/5 C 0 2 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P NO NO P NO 2-IMO-911 0 GA 8 MO L/6 C 2 A B EF-1 EF-5-ET-012 EF-1'F-5--ET-012 P NO HO P---HO 2-QCR-300 0 GL 2 A E/1 0 A A EF-1 EF-5 EF-7 ET"003 SLT-1 EF-2 EF-5 EF-8 ET-003 SLT-2 C YES>NOTE 6 HO C NO>NOTE 6 C NO R YES>HOTE 3 2-ACR-301 0 GL 2 A E/1 0 C 2 A A EF-1 EF-5 EF-7-,ET-005 SLT"1 EF-2 EF-5 EF-8 ET-005 SLT-2 C--C R YES>NOTE 6 NO NOp-NOTE 6 NO YES'OTE 3 2-QMO-200 0 GA 3 MO J/3 0 0/C 2 A B EF"1 EF-5 ET-012 EF-2 EF-5 ET-012 YES'OTE 7 NO NO 2-QMO-201 0 GA 3 MO J/3 0 0/C 2 A B EF-1 EF-5 ET-012 EF-2 EF-5-ET-012 YES>NOTE 7 NO HO-2-QMO"225 0 GA 2 MiO J/7 0 0/C 2 A B EF-1 EF"5 ET-012 EF-1 EF-5 ET-012 P NO--HO P NO


.~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUl~RRY SHEET" LAIT 2 SYSTEH-NAHE:=-CVCS==LETDOHN-8-CHARGING
0                                            DONALD C. COOK NUCLEAR PLANT                           RUN DATE AHD  TINE:    14SEP87:13:28 SECOND TEN YEAR ItfTERVAL
=-.FLON-DIAGRAll:.
                                                                              -  UHIT 2 SYSTEtt-HANE:=ttON-ESSEtlTZA~ERVZCE-HATER==-   -=   VALVE SLMKRY SHEET
2-5129"32 RUH DATE AND TINE 14SEP87:13:28 VALVF==----=-=----I=VALVE POSITION-I
                                                      -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)
--------=---=ASHE-SECTION-XZ-I I NURSER REV TYPE SIZE ACT F D I PONER SAFETY I CD A/P CAT PRZH TEST TEST TEST RELIEF RE@lEST(S)
TYPE COORDI OPER - -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  - - =-
---.TYPE-COORDI-OPER-
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---
-=-FUHCT--ICL---REQJIRED--PERFORHiED
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
---NODE 2-CS"292 0 CK 2 SA H/6 C 0/C 2 A C CF-1 CF-2 C YESp NOTE 1 2=CS-297-"E=O=-CK-----2--
                                                                              - 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
-==SA=-H/7 0/C-0--2 A=C-CF-1 CF"1 2-CS-297-H 0 CK 2 SA F/7 0/C 0 2 A C CF1 CF-1 2-CS-299-E 0 CK 4 SA H/7 0 0/C 2 A AC CF-1 SLT"1 CF-3 SLT-1 P YESp NOTE 2 R HOp NOTE 3 2-CS-299-H 0 CK SA F/7 0 0/C 2 A AC CF-1 SLT-1 CF-3 SLT-1 P YESp NOTE 2 R HOp NOTE 3 2-CS-321 0 CK 3 SA E/3 0 C/0 2 A AC CF-1 SLT-1 CF-2 SLT-2 YESp NOTE 4 R YESp NOTE 3 2-CS-328-L1 0 CK 3 SA 8/2 0/C 0 1 A C CF-1 CF-1 P NOp NOTE 5 2-CS-328-L4 0 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P NOp HOTE 5 2=CS=329=.L1=.0 CK D====SA.8/2.0/C 0 1.A C CF-1 CF-1 P NOp NOTE 5 2-CS"329" L4 0 CK 3 SA 8/3 C/0 0 1 A C CF-1 CF-1 P HOp NOTE 5 2-IHO-360 0 GA 4 HO J/6 C 0 2 A 8 EF-1 EF-5 ET-009 EF-1 EF-5 ET-009 P P NO NO NO SYSTEH-t4NEt=REACTOR-COOLANT-DONALD C.COOK NUCLEAR PLAtR SECOND TEN YEAR INTERVAL VALVE SUi~0'NRY StlEET-UNIT 2 F LOtt-DIAGRAH:-2-5128A-34 Rmt DATE AND TIHE: 14SEP87-.13:28-VALVE-=----------I.-VALVE POSITION I I I-ASHE SECTION XI----NUYBER REV TYPE SIZE ACT F.D.I PtNER SAFETY ICD A/P CAT PRItk TEST TEST TEST RELIEF REQUEST(S)
----TYPE COORD I-OPER-=FUitiCT=ICL REQUIRED PERFORHED.
HODE 2"SI"189 2 CK SA D/7 C 0/C 2 A AC CF-1 CF-2 SLT-1 SLT-2 R YES>NOTE 7 R YESs NOTE 2 2-SV-45A 0 REL 6 SA K/6 C 0 A C TF-1 TF-1 R NO R-SV.-468 0--RRI 6----SA.-J/6-C----..-0---6-A C-TF-1 TF-I R---=NO 2-SV-45C 0 REL 6 SA H/6 C 0 1 A C TF-1 TF-1 2-SV-50 0 REL 2 SA G/3 C 0 A C TF"1 TF-1 R NO I 0 ,
SYSTEN-HARE:
-REACTOR-COOLANT=
DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiQRY SHEET-UiiIT 2 FLOH DIAGRAH:-=.2=5128A-34..
RUN DATE AND TINE: 14SEP87:13:28 VALVF=--=--=-==-==-I--VALVE-POSITION-l
-------=l I NAKER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT-TYPE COORDI OPER---FUNCT-ICL-ASNE SECTION XZ-PRIN TEST TEST TEST RELIEF REQUEST(S)
REQUIRED PERFORNED MDE 2-NSO-062 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 6 NOp NOTE 6 R YESp HDTE 6 R YESp NOTE 6 2-NSO-063 2 GL 1 SO N/6 C 0/C EF-1--EF-5---EF"7 ETF-002 EF-2---EF-5------EF-8 ETF-002 R R YESp NOTE 6 HOp NOTE 6--YESp NOTE 6 YESp NOTE 6 2-NSO-064 2 GL 1 SO N/6 C 0/C 2 A B EF-1 EF-2 R EF-5 EF-5 EF-7 EF-8 R ETF-002 ETF-002---R YESp HOTE 6 HOp NOTE 6 YESp NOTE 6 YESp-NOTE 6 2-PN-275 2 CK SA B/9 0/C C 2 A AC CF-1 CF"2 SLT=1=-=-=-SLT-2 R YESp HOTE 4 R-YESp NOTE 2 2-RCR-100 0 GL 0.375 A B/7 0 C 2 A A EF-1---EF-5 EF-7 ETF-002 SLT-1 EF-1 EF-5-EF-7 ETF-002 SLT-2 P P P R HO HO NO NO YESp NOTE 2 2-RCR-101 0 GL 0.375 A B/7 0 C 2 A EF-1 EF-5-EF-7-ETF-002 SLT-1 EF"1 EF-5 EF-7 ETF-002 SLT-2 P P P R HO NO NO--NO YESp NOTE 2


SYSTEN-NAHC:
0                                                                          ~
-REACTOR-COOLANT DOHALD C.COOK NUCLEAR PLICA SECOND TEN YEAR INTERVAL VALVE SVi'DIARY SHEET-UNIT 2 FLON-DIAGRAN:-2"5128A-34 RUN DATE AND TINE: 14SEP87:13:28 VAI.VE=--=-I-VALVE=POSITION I I I ASYiE SECTIOiN XI HL~iER REV TYPE SIZE ACT F~D I PONER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)
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
---TYPE-COORD I-OPER--=-FUHCT-ICL--REQUIRED---PERFORHED NODE 2-NlO-152 0 GA HO K/7 0 C 1 A B EF-1 EF-5 ET-014 EF-1 EF-5 ET-014 2-h~iO-153 0 GA 3 NiO K/6 0 C 1 A B EF-1 EF<<1 EF-5 EF-5 ET-014---ET-014-=-P N)N)-P-NO 2-NPX-151 0 GL 0.5 N N/8 C C 2 P A SLT-1 SLT"2 YESp hN)TE 2 2-HRV-151 0 GL 3 A K/7 C C/0 1.A B EF-1 EF"4 EF-5 EF"5 Ef-7-=-==-EF-0=ET-008 ET"008 HOp NOTE 3 NO NOp NOTE 3 NO 2-NRV-152-
                                        ~                SAFETY I CD  A/P   CAT     PRIN TEST         TEST         TEST   RELIEF REQUEST(S)
=-;-O=GL~=.
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
=-=-A-K/7--C.----C/0-1-A-B-EF 1 EF-5 EF-7 ET"008 EF-4 EF-5 EF-8 ET-008 NOp NOTE HO HOp NOTE NO 2-HiRV-153 0 GL 3 A K/6 C C/0 1 A 8 EF1 EF-5 EF-7 ET-008 EF"4 EF-5 EF-8 ET-008 NOp NOTE NO NOp hOTE NO 2-NSO-061==2
                                                                                                                    -- P      NO HO EF-7            EF"7            P      NO ET"006          ET-006          P      HO
-Gl~SO--N/6---C------0/C=-2 A-B--EF-1-----=EF-2=-----EF-5 EF-5 EF-7 EF-8 ETF-002 ETF-002 R R R YESp h'OTE 6-=HOp NOTE 6 YESp HOTE 6 YESp NOTE 6
                                                                                      =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


SYSTEH-NAME:
O.
-REACTOR-COOLANT DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUHHARY SHEET-UNIT 2-FLOH=DIAGRAH:- 5128A RUN DATE AND TINE: 14SEP87:13:28
DOHALD C. COOK NUCLEAR PLANT                         RUN DATE AND    TIME:  14SEP87:15:28 SYSTEM NAME' NON=ESSENTIAL SERVICE HATER          =
-VALVE I VALVE-POSITION-I I ASHE SECTIOH=XZ-
SECOND TEN YEAR INTERVAL VALVE SlPiOARY SHEET     - UiHZT 2 FLOH DIAGRAM:.. 2".5114A-.27 VALVE   . =      ....      I I
----==-HUYBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT TYPE COORDI-OPER
                                                  .VALVE.POSITION   I I
--FUNCT.ICL PRZH TEST TEST TEST RELIEF REQUEST(S)
                                                                      ..                      ASME SECTION    XI NUMBER    REV TYPE SIZE       ACT F.D. I POHER        SAFETY ICD     A/P CAT     PRIM TEST       TEST         TEST   RELIEF REQUEST(S)
REQUIRED PERFORHED-NODE 2-CS-442-1 0 CK 2 SA B/4 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YESp NOTE 2 2-CS-442"2 0 CK 2 SA B/4 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES>NOTE 1 R YES>NOTE 2 2-CS-442-3 0 CK 2 SA B/4 0 C 2 A AC CF"1 SLT-1 CF-2 SLT-2 R R YES>NOTE 1 YES'OTE 2 2-CS-442-4 0 CK 2 SA B/4 0 C 2 A AC CF-1 SLT-1 CF-2 SLT-2 R R YESp NOTE 1 YES NOTE 2 2-GCR-301 0 DA 0.75 A B/8 0 2 A A EF-1 EF-5 EF-7-ETF-002 SLT-1 EF-1 EF"5 EF"7 ETF-002 SLT-2 P P P R HO NO HO HO YES'OTE 2 2-N-159=--2=-CK-=-0.75--SA-C/8-0/C---C----=2--A--AC---CF-1-------CF-2-SLT-1 SLT-2 R-=----YES>-HOTE=5 R YESp HOTE 2 2-HCR-252 0 GI A B/9 C C 2 P A EF-1 EF-5 EF-7 ET-004-.SLT-1.==EF-1 EF-5 EF-7 ET-004 SLT-2-P P P-R-HO HO NO HO YES>NOTE 2 2-QiO-151 0 GA 3 VO K/7 0 1 A B EF-1-EF"5 ET-015 EF-1 EF-5 ET-015 P NO HO P NO  
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


SYSTEM-NAME:
0 0                                            DONALD C. COOK NUCLEAR PLANT 0                            RUN DATE AND    TINE:  14SEP87:13:28
-REACTOR-COOLANT-
                                        ==.
~~DONALD C COOK NUCLEAR PLANT SECOHD TEN YEAR INTERVAL VALVE SU'i~RY SHEET-UihIT 2-FLOH-DIAGRAM:
SECOttD TEN YEAR INTERVAL VALVE SL.uSRY SHEET UittZT 2 SYSTEH-NAttE:=-ESSEttTXAL=SERVICE-HATER-     =-=          FLOH DIAGRAH: 5113=36 VALVE-==    =--- =I-VALVE-POSZTXON I
2-5128 RUH DATE AND TIME: 14SEP87:15:28
I I
--.VALVE=---==---==-I-VALVE POSITION-I---I I ASME-SECTION-XZ-tiIPiSER REV TYPE SZ2E ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD,I OPER=---FUNCT=-ICL--REQUIRED---PERFORMED
                                                                                                  = ASNE SECTXOtt XZ SI2E  ACT F.D. I POHER HURDLER  REV  TYPE
-MODE 2-HSO-021 2 GL 1 SO J/6 C 0/C 2 A B EF"1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 1 HOp NOTE 1 R YESp NOTE 1 R YES NOTE 1 2-NSO-022 2 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-2-EF-5------EF-5 EF-7 EF-8 ETF-002 ETF-002 R YESp NOTE 1 HOp HOTE 1--R YESp NOTE 1 R YESp NOTE 1 2-NSO-025 2 GL 1 SO J/6 C 0/C 2 A B EF-1 EF-5 EF-7 ETF-002 EF-2 EF-5 EF-8 ETF-002 R YESp NOTE 1 NOp NOTE 1 R YESp NOTE 1 R YESp NOTE 1 2-NSO-024 2 GL 1 SO J/6 C 0/C 2 A B EF1 EF-5-EF-7 ETF-002 EF-2 EF-5-EF-8 ETF-002 R R YESp HOTE 1--HOp NOTE--1=-===---
                          ==--                          SAFETY ICD TYPE COORDI- OPER. ---FUNCT- ICL     =
-=YESp NOTE 1 YESp NOTE 1 0.~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ZNTERVAL VALVE SUNDRY SHEET-UHIT 2 SYSTEM-NAME:=STATZOH-DRAINAGE,CONTAI%!ENT=-
A/P  CAT
-----FLON=DIAGRAM:-=2-5124-20 RUN DATE AND TIME: 14SEP87:13:28 VALVE---=---==-------I-VALVE-POSITION=
                                                                            =--
I=I I-ASME-SECTION-XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
PRItl TEST REQUIRED TEST PERFORHED--
TYPE-COORDI OPER--FWCT--ICL-----REQUIRED-PERFORMED MODE 2-DCR-600 0 DA 3 A N/6 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 f F"5 EF-7 ET-004 SLT-2 P P P R HO NO NO NO YESD NOTE 1 3-000-601= DA-3 A-N/6-0-0-3 A=-A----EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7 ET-004 SLT-2 P P R HO HO NO HO YES NOTE 1 2-NS-357 2 CK 0.5 SA K/9 C 0/C 2 A AC CF-1-SLT-1-CF-2 SLT-2 R YES>NOTE 2 R YESR N)TE 1 M 00
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


0DO?QLD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UiNIT 2 SYSTEM-NAME:--NON-ESSENTIAI SERVICE HATER..-..-=-FLON DIAGRAM:=2"5114A-27
                                                                                          . ~
..RUN DATE AND TIMiE: 14SEP87:13:28
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
--VALVE.-.-------=-I-VALVE=POSITION I I I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
                                                                              -- - --     --- ---       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 COORDl-OPER
                                    -TYPE-COORDI-OPER- -FLDtCT          ICL       -=  = -REQUIRED-          PERFORtlED    N)DE 2-&#xc3;~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
---FUNCT ICL---=-REQUIRED PERFORMED MODE 2-NCR-967-3 0 DA 2 A J/3 0 C 2 A A EF1 EF-5 EF-7.ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT"2 P P P R NO NO NO NO YES NOTE 1
                                                                                      =-==-- ET-024            ET-024 -=
~DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sinai'RORY SHEET-UNIT 2 SYSTEH-NAlK:
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=
-NOH-ESSENTIAL-SERVICE HATER---=.FLOH DIAGRAN:=2-.5114A-27 RUN DATE AND TINE: 14SEP87:13:28 VALVE---===--===-=
ET-026            ET-026          P     HO
---I VALVE POSITION=I--I I HRSER REV TYPE SIZE ACT F~D~I PONER SAFETY t CD A/P CAT TYPE-COORD I-OPER--FACT-=ICL ASHE=SECTION-XI==--=---PRIH TEST TEST TEST RELIEF REQUEST(S)
REQUIRED-PERFORNED NODE 2"NCR"962 0 DA 2 A J/3 0 2 A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P NO ET-004.ET-004=P HO SLT-1 SLT-2 R YES>NOTE 1 R-HCR=965 0-OA-2-.--A=J/3---0-=-C-.---2--A=A=-EF-1-EF-5 EF-7 ET-004 SLT-1 EF-1--EF-5 EF-7 ET-004 SLT-.2 P P R HO HO HO HO YES>NOTE 1--2-HCR-964-3 0 DA 2 A J/7 0 2 A EF-1 EF-5=EF-7 ET-005 SLT"1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO NO=P NO P NO R YES>NOTE 1 2-HCR-965-3 0 DA 2 A J/7 0 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5 EF-7-ET-005 SLT-2 P NO HO P---NO-P HO R YES'OTE 1 2-hCR-966-3 0 DA 2-A J/3 0 2 A A EF-1 EF-5 EF-7=-==ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO HO P NO P=--HO R YES>HOTE 1


.e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SU&lARY S)IEET-LPi)IT 2 SYSTEH-HA))Et=NON-ESSENTIAL-SERVICE-HATER-
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 = --
=---=--.-FLON-DIAGRAH: 5114A-.27 RUH DATE AND TINE: 14SEP87:13:28 VALVE)-VALVE POSITION-I..I I------=------ASNE-SECTION XI NU)GER REV TYPE SIZE ACT F,D.I PONER SAFETY ICD A/P CAT---TYPE=COORDI OPER-FUNCT-ICL-PRIH TEST TEST TEST RELIEF REQUEST(S)
I                  I
REQUIRED=.PERFORHED NODE 2-HCR-956-2 0 DA A J/3 0 C 2 A A EF-1 EF-5 EF-7.ET-004 SLT-1 EF-1 EF-5 EF-7-ET=004-SLT-2 P P P R HO NO HO HO YES'OTE 1 2-HCR-957-3= -DA=-3---A---J/3-=-0=-=--C--.---2--A EF-1----==EF-1=--
                                                                              -                   -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)
EF-5 EF-5 EF-7 EF"7 ET-003 ET-003 SI T-1 SLT-2-P P P R---HO NO NO NO YES>NOTE 1.2-HCR-958-4 0 DA 3 A J/3 0 C 2 A A EF-1-EF-5-=EF-7 ET-005 SLT-1 EF-1 EF=5=EF-7 ET-005 SLT-2 P P R HO HO HO HO YES'OTE 1 2-HCR-960 0 DA 2 A J/7 0 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5-EF-7 ET-005 SLT-2 P-P R NO NO NO NO YES>HOTE 1 2-HCR-961 0 DA 2 A J/7 0 C 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R HO HO HO-HO YES>NOTE 1
                            =------ 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


DONALD C.COOK HUCLEAR PLANT SECOND TEtt YEAR INTERVAL VALVE SmNARY SHEET-UthZT 2 SYSTEM-NAttE:
0' 0            .                                                                    ~
-NON=ESSENTIAL-SERVICE HATER-..FLOW DIAGRAM: 2=5114A=27
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                 = .
.RUN DATE AND TIME: 14SEP87:13:28
FLOH-DZAGRAtt: =2-5113-36
--VALVE-.-
                  -VALVE ==-          -- == -=I--VALVE-POSITION I
-=-=-=-=-----I-VALVE-POSZTZON-I I I HUYBER REV TYPE SIZE ACT f D I POWER SAFETY ICD A/P CAT TYPE-COORDI OPER FUNCT ICL ASME SECTION XZ PRIM TEST TEST TEST RELIEF REQUEST(S)
I I
REQUIRED PERFORMED MODE 2-WCR-951 0 DA 3 A K/6 0 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF"5 EF-7 ET-005 SLT-2 P NO NO P NO P.NO R YES'OTE 1 2=ttCR-452=2 DA-3=----A---.K/6=-" 0-==C EF-1------=EF-1 EF"5 EF"5 EF-7 EF-7 ET-004 ET-004 2 A-A.---SLT-1-=-SLT-2 P.--HO-NO P NO P NO R YES>NOTE 1 2-WCR-953-3 0 DA A K/6 0 2 A EF-1 EF-5--EF-7 ET-005 SLT"1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO-HO NO NO YES>NOTE 1 2-WCR-954-4 0 DA A K/6 0 C 2 A A EF-1 EF-5 EF.-7 ET-005 SLT-1 EF-1 EF-5.EF-7-=ET"005 SLT-2 P NO HO=P-=-HO-P NO R YES>NOTE 1 2-WCR-955 0 DA 3 A J/3 0 C 2 A A EF"1 EF"5 EF-7 ET-005-SLT-1 EF-1 EF-5 EF"7 ET-005 SLT-2 P NO NO P NO P-NO.R YES>NOTE 1
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 SECOND TEN YEAR INTERVAL VALVE QPiRKRY SHEET-UNIT 2 SYSTEM HAME-:-NON=ESSENTIAL SERVICE..HATER
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 -==
=FLON DIAGRAM:.2"5114A-27 RUN DATE AHD TIME: 14SEP87:13:28-VALVE----=-I VALVE-POSITION-I I I NUMBER REV TYPE SIZE ACT F~D.I POKER SAFETY I CD A/P CAT TYPE COORD I-OPER.=FUtKT I CL=ASME-SECTION-Xl PRlt1 TEST TEST TEST RELIEF REQUEST(S)
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)
REQUIRED.PERFORMED=MODE 2-NCR"944-4 0 DA 3 A J/6 0 C 2 A A EF-1 EF"5 EF-7 ET-004 SLT-1 EF-1 EF-5 EF-7.ET-004 SLT-2 P P R NO HO HO NO YESp NOTE 1 2=NClL945 0 DA==3=-=-A:=J/3 0-----C 2--A---A-EF.-)EF-5 EF-7 ET-005 SLT-1--EF-l.-EF"5 EF"7 ET"005 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2-NCR-946-2 0 DA A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-)EF-1 EF-5 EF-7 ET-004 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2"NCR-947-3 0 DA 3 A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO NO P NO P HO R YESp NOTE 1 2-NCR-948M 0 DA 3 A J/3 0 C 2 A A EF-1 EF-5 EF-7 ET"005.SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO t/0 P HO P NO-R YESp NOTE 1 0!1 I I
                            -TYPE -COORDI OPER -       -- FUNCT    = ICL- --=-   ----- REQUIRED --=-   PERFORMED-   --   MODE- ---
=0 e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE Sly IARY SHEET-UNIT 2 SYSTEN-NANE:
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-----
-NOH=ESSENTIAL-SERVICE-HATER-.
                              -                       -   0    - 3
-=---.=.FLOH DZAGRAH: 2-5114A-27 RUN DATE AND TINE: 14SEP87:13:28-VALVE I--VALVE POSITION-I I I ASNE SECTION XZ HU)0)ER REV TYPE SIZE ACT F D I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
                                                                  -           A C-===CF-1       = -- -CF          . P    NOp NOTE 1---
TYPE COORD I OPER FACT I CL REQUIRED PERFORNED tiODE 2"HCR-934 0 DA 3 A K/2 0 C 2 A A EF-1 EF-5 EF-7 ET=005 SLT-1 EF-1 EF-5 EF-7 ET=005 SLT-2 P HO NO P HO P NO R YES'OTE 1 2=HCR-$35==-0-DA-=-3--.=-A-=J/2--0-=----.C-.-----2--A EF-1-EF-5 EF-7 ET-005 SLT-1---EF-1 EF-5 EF-7 ET-005 SLT-2 P P R NO HO HO HO YESp HOTE 1 2"HCR" 941"1 0 DA A J/6 0 2 A A EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5-EF-7 ET-005 SLT-2 P P R NO HO HO HO YES>NOTE 1 2-HCR-942-2 0 DA A J/6 0 2 A A EF-1 E F-5 EF-7-ET-004 SLT-1 EF-1 Ef-5-EF"7 ET-004 SLT-2 P P P R NO hN)HO=HO YES>NOTE 2-HCR"943-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-5 EF-7--ET"004 SLT-1 EF-1 EF"5 EF"7 ET-004.SLT-2 P P P R HO HO NO NO YES>NOTE 1
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


0~DONALD C.COCC NUCLEAR PLAtti SECOND TEt(YEAR INTERVAL VALVE SC0)ARY SHEET-UNIT 2 SYSTEN-HAtfE:=-HON-ESSENTIAL=-
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--
SERVICE-HATER==-
                --VALVE--=   ==    =-=  -   = I=VALVE-POSITION I--                              -- ASME SECTION XZ--
==-=--'=--FLON-DZAGRAN) 5114A-27 RUN DATE AHD TINE: 14SEP87:13:28
I                I HU'SER    REV   TYPE   SIZE   ACT   F.D. I POHER  SAFETY ICD A/P       CAT     PRIt1 TEST         TEST       TEST  RELIEF REQUEST(S)
---VALVE-----==--I VALVE-POSITION-I I I ASt)E SECTION-XI-HETER REV TYPE SIZE ACT F AD I PONER SAFETY ICD A/P CAT PRZN TEST TEST TYPEiCOORDI OPER----FUHCT=ICL--REQUZRED-----PERFORMED TEST RELiEF REQUEST(S)
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--
ViODE 2-)')CR-929-3 0 DA 3 A K/6 0 C 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7--ET=005==-ET=005 SLT-1 SLT-2 P P R HO HO NO ti'0 YES>NOTE 1 2"NCR-930"3=0-=DA
--=3-=---=-A==-K/2-0-=-=C-----2.-A-A-EF-1-EF"5 EF-7 ET-004 SLT-1---=EF=1-EF-5 EF-7 ET-004.SLT-2 P P R-HO HO NO N)YES>NOTE 1 2"NCR-931-3 0 DA 3 A J/2 0 2 A A EF-1-=EF-5=--EF-7 ET-004 SLT-1 EF"1--EF-5 EF-7 ET-004 SLT"2 P P P R HO HO NO HO YESp NOTE 1 2-NCR-932-4 0 DA 3 A J/6 0 2 A A EF-1 EF-5 EF-7---.--ET-004 SLT-1 EF-1 EF-5--EF-7 ET-004 SLT-2 P P-P R NO HO HO HO YES>NOTE 1 2-HCR-933 0 DA A K/6 0 C 2 A A EF-1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-005-=---=ET-005 SLT-1 SLT-2 P P P R NO HO YES>NOTE 1 0 0 DOHALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE S!RCIARY SHEET-UNIT 2 SYSTEM=NAME:
-NN-ESSENTIAL-SERVICE-WATER-=--=-=-.FLOW.DIAGRAM:--
2-511%A-.27-RUH DATE AND TIME: lOSEP87:13:28 VALVE-=----=--I VALVE-POSITION-I-I I Nk)DER REV TYPE SIZE ACT F~D t POWER SAFETY I CD A/P CAT TYPE-COORDI OPER=-FLNCT ICL-=AQK SECTION-XZ PRIM TEST TEST REQUIRED PERFORMiED TEST RELIEF REQUEST(S)
MiODE 2-WCR-924-2 0 DA A J/6 0 2 A A EF-1 E F-5 EF-7----------ET-"005 SLT-1 EF"1 EF-5 EF-7 ET-005 SLT"2 P P P R NO NO HO NO YESp NOTE 2-WCR-925-2=-=0-
-DA---3---A--=K/6-=O.=--=--C--==---2.-A--A--EF-1=---EF-5 EF-7 ET-005 SLT-1-EF-1-EF-5 EF-7 ET-005 SLT-2 P NO HO P NO P NO R YES>NOTE 1 2-WCR;926-2 0 DA A K/2 0 C 2 A EF-1 EF-5--EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R NO HO HO HO YES'OTE 1 2-WCR-927-2 0 DA 3 A J/2 0 C 2 A EF-1 EF-5-----EF-7=ET-005 SLT-1 EF-1 EF-5 EF-7=-ET-005 SLT-2 P P R NO NO HO-NO YESp NOTE 1 2-WCR-928-3 0 DA 3 A J/6 0 C 2 A A EF-1 EF-5 EF-7*--ET-005-.SLT-1 EF-1 EF-5 EF-7--ET-005-SLT-2 P P R HO HO N)HO YESp NOTE 1


0 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtD!ARY SHEET-t)NZT 2 SYSTEM-NAME:
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)
-ttON-ESSENTZA~ERVZCE-HATER
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--
.--==------FLON DIAGRAM:-2-5114A-27 RUN DATE AND TIME: 14SEP87:13:28 VALVE-=-=----I-VALVE POSITION-I I I NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT TYPE=COORDI-OPER
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
-FUHCT---ICL=
---------ASME SECTION XZ PRIM TEST TEST TEST RELZEF REQUEST(S)
REQUIRED PERFORMED MODE 2-HCR-915-4 0 DA 6 A K/4 0 C 2 A A EF"1 EF-5 EF-7 ET-006 SLT-1 EF-1 EF-5 EF-7 ET-006 SLT"2 P P P R HO ltO NO NO YES>NOTE 1 2-HCR"=920-1==0
-DA=~=-A--J/6-0----C---=-2-==A=--EF-1 EF"5 EF-7 ET-005 SI.T.-1 EF-1 EF-5 EF-7 ET-005 SLT=2 P P R HO HO NO HO YESi HOTE 1-=-2-HCR-921-1 0 DA A K/6 0 2 A A'F-1 EF-5--EF-7 ET"005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P P R HO HO-HO NO YES>NOTE 1 2-NCR-922-1 0 DA 3 A K/2 0 C 2 A A EF-1 EF-5 EF-7-ET-005 SLT-1 EF"1 EF-5 EF-7=ET-005 SLT-2 P P P R HO NO NO-NO YES>HOTE 1 2-HCR-923-1 0 DA 3 A J/2 0 2 A A EF"1 EF-5 EF-7-ET-006 SLT-1 EF-1 EF-5 EF-7-ET-006-SLT-2 P ttO HO P th)-P---HO R YES>HOTE 1 0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR ItfTERVAL VALVE SLMKRY SHEET-UHIT 2 SYSTEtt-HANE:=ttON-ESSEtlTZA~ERVZCE-HATER==-
--=-FLOtl DZAGRAH:---
2-5114A-27 RUN DATE AHD TINE: 14SEP87:13:28 VALVE I VALVE POSITION I I I-ASNE-SECTION XZ-HUtlDER REV TYPE SIZE ACT F.D~I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)
-TYPE COORDI OPER---FUNCT=ICL--=----REQUIRED-
----PERFORHED
-MODE 2-HCR-910-3 0 DA 6 A J/4 0 C 2 A A EF-1 EF-5 EF"7 ET-006-SLT"1 EF-1 EF-5 EF"7 ET-006 SLT-2 a NO HO a NO P-NO-----=-R YES>HOTE 1 2-HCR-911-3 DA=--6--A---K/4-=0--=-C--=-=-2.-=--A=--A=-EF-1---EF-5 EF-7 ET-005 SLT-1-EF-1 EF-5 EF-7 ET-005 SLT-2 P--=NO HO P HO P NO R YES>HOTE 1 2-HCR-912-4 0 DA 6 A J/9 0 2 A A EF-1 EF-5 EF-7 ET-009 SLT-1 EF"1-EF"5-EF-7 ET-009 SLT-2 P P R NO HO-HO HO YES'OTE 1 2-lCR-913-4 0 DA 6 A K/9 0 2 A A EF-1 EF-5--EF-7-ET-008 SLT-1 EF-1 E F-5 EF-7-ET-008 SLT-2 P P P R HO HO HO HO YESp HOTE 1 2-HCR-914&
0 DA 6 A J/4 0 C 2 A A EF-1 EF-5 EF-7 ET-005----.SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P HO HO P NO P--=NO R YES>NOTE 1


0~DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtCtARY SHEET-UiiIT 2 SYSTEtt-HAttE:
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)
-NOH"ESSENTIA~ERVICE-HATER--
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.
--===--FLON DIAGRAH:-2=5114A RUN DATE AND TINE: 14SEP87:13:28 VALVE---------I-VALVE-POSITIOH I---=-I I HUiiSER REV TYPE SIZE ACT F~D.I POHER SAFETY I CD A/P CAT TYPE COORD i=OPER=-FUHCT
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.
--I CL---ASHE-SECTION-Xl PRIN TEST TEST TEST RELIEF REQUEST(S)
N)
REQUIRED PERFORNED NiODE 2-ItCR-905-2 0 DA 6 A K/9 0 C 2 A A EF-1 EF-5 EF-7 ET-006 SLT-1 EF-1 EF-5 EF-7 ET=006 SLT-2 P P R ttO NO ttO HO YESp NOTE 1 2-HCR-906-2 -DA-=-6----A.--J/4-0-==-=C=--=--2=--A-A.---EF-1-EF-5 EF-7 ET"006=SLT-1 EF-1-EF-5 EF"7 ET-006 SLT-2---P NO HO P NO P HO-R---YES>NOTE 1 2-HCR-907 0 DA 6 A K/4 0 C EF-1 EF-5 EF-7 ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P P R HO NO t<0 NO YES>NOTE 1 2-HCR-908-3 0 DA 6 A J/9 0 C 2 A EF-1 EF-5--EF-7----ET-008 SLT-1 EF-1 EF-5-.--EF"7==ET-008 SLT-2 P-=-P R t<0 HO NO HO YES>HOTE 1 2-HCR-909-3 0 DA 6 A K/9 0 C 2 A EF-1 EF-5 EF-7--ET-006-SLT-1 EF-1 EF-5 EF-7-ET-006 SLT-2 P P P R HO HO HO HO YES'OTE 1  
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


O.DOHALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SlPiOARY SHEET-UiHZT 2 SYSTEM NAME'NON=ESSENTIAL SERVICE HATER=-FLOH DIAGRAM:..2".5114A-.27 RUN DATE AND TIME: 14SEP87:15:28 VALVE.=....I.VALVE.POSITION I..I I ASME SECTION XI NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
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 - -    .           . - -
TYPE.COORDl-OPER
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)
=-FUHCT=ICL------=
                            -  - 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
----REQUIRED.PERFORMED HiODE 2-HCR-900-1 0 DA 6 A J/9 0 C 2 A A EF-1 EF-5 EF-7 8 ET 00 SLT-1 EF-1 EF-5 EF-7 ET-008 SLT-2 P P P R NO NO NO.NO.YES>NOTE 1 2=HCR"BOl"I=-
                                                                                =  ET.-031.             ET-031 2FH0221      0   GL    4          HO  C/5    0      0           3, A   B EF)
0-DA 6.-A.=-K/9-.-0 C 2 A A-=--EF"1.-
EF-.5 ET-021
----EF-5 EF-7 ET"008 SLT-1-EF"l.EF-5 EF"7 ET-008.SLT-2------P=HO NO P NO P NO R YES>.NOTE 2-HCR-902-1 0 DA 6.A J/4 0 C 2 A EF-1 EF-5 EF"7 ET-005 SLT-1 EF-1 EF,-5 EF-7 ET-005 SLT"2 P P P R HO HO HO NO YES>NOTE 1 2-HCR-905-1 0 DA 6 A K/4 0 2 A A EF-1 EF"5 EF=7-, ET"006 SLT-1 EF-1 EF-5 EF-7-ET-006 SLT-2 P P P R NO HO NO NO YESp NOTE 1 2-HCR-904-2 0 DA 6 A J/9 0 C 2 A A EF-1 EF-1 P EF-5 EF-5 EF"7 EF-7 P ET==008 ET.=008.P SLT-1 SLT-2 R NO HO NO NO=YES>NOTE 0
                                                                                                ..      EF-1 EF-5 ET-02)
0 0 DONALD C.COOK NUCLEAR PLANT SECOttD TEN YEAR INTERVAL VALVE SL.uSRY SHEET-UittZT 2 SYSTEH-NAttE:=-ESSEttTXAL=SERVICE-HATER-
P P
-=-===.-FLOH DIAGRAH:-2-5113=36 RUN DATE AND TINE: 14SEP87:13:28 VALVE--==-=----=I-VALVE-POSZTXON I I I=ASNE SECTXOtt XZ HURDLER REV TYPE SI2E ACT F.D.I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(S)
NO NO NO 2=FH0=222    0   GL    4  ..      HO  C/5    0      0           3..A = B  -    EF-1---
==--TYPE COORDI-OPER.---FUNCT-ICL==---REQUIRED PERFORHED--
EF-5         .
ttODE=2-l'tRV-722-CD 0 3H 4 A K/8 0 0 3 A B EF-1 EF-7 ET-NA NOTE EF-8 NOTE P R YESp NOTE 3 YESp NOTE 3 YESp NOTE 3 2-HRV-724-CD 0 3H A H/8 0 0 A B EF1 NOTE EF-7 EF-8--ET-NA=-=---NOTE P R 3-YESp NOTE 3 YESp NOTE 3=-=YESp NOTE-3-2-HRV-726-AB 0 3H 4 A K/8 0 0 3 A B EF-1 NOTE 3 EF=7=-EF-8 ET-NA NOTE 3 P YESp NOTE 3 R YESp NOTE 3 YESp NOTE 3 2=WRY=.728"AB 0=MH=4=A H/8-0=-0..3-A--B-EF-1---NOTE 3 P.YESp NOTE3 EF-7 EF-8 R YESp NOTE 3 ET-ttA NOTE 1 YESp NOTE 3
                                                                                                    --   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 CD COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiARY SllEET" UiNIT 2 SYSTEN-NAHE:
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- =-
-ESSENTXA~ERVICF=-ttATER
I I
-----==--=--FLON DIAGRAM:--2=5113-36 RUiN DATE AND TINE: 14SEP87t13:28 VALVE--------I-VALVE-POSITION-I----------------ASttE-SECTION XI-I I NUBBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRItl TEST TEST-TYPE-COORDI-OPER-
VALVE-POSITIOtt I I
--FLDtCT ICL--==-REQUIRED-
                                                                      -- . - - 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)
--PERFORtlED 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
N)DE 2-&#xc3;~iO-726 0 BF 6 HO K/6 C 0 3 A B EF1 EF-5 ET-023 EF-1 EF-5 ET"023 P HO NO P NO 2-HMO-728 0 BF 6 HO L/6 C 3 A B EF1 EF-5=-==--ET-024-EF-1 EF-5 ET-024-=-2-Htl0-734 0 BF 16 HO H/3 0/C 0 3 A B EF-1 EF-1 EF"5=EF-5 ET-054 ET-054 P HO HO P NO 2=)D'i0=738
---0---BF--.16----N)-K/3--0/C-0--3 A-B-EF-1-EF"5 ET-055 EF-1 EF-5 ET-055 P-HO-HO P HO 2-RtO"744 0 BF 4 HO J/6 C 0 A B EF-1 EF-5 ET-036 EF-1 EF-5 ET-036 P HO HO P NO 2-IC iO-753 0 BF 6 HO H/5 C 0 3 A B EF-1 EF"5 ET-024.EF-1 EF-5 ET-024 P NO NO P.HO 2-Ht40-754 0 BF 4 HO K/6 C 0 3 A B EF-1 EF-1--EF-5-----EF-5-ET-026 ET-026 P HO tlO=P HO  


DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAiR INTERVAL VALVE SU)IIRRY SHEET-UiNIT 2 SYSTEN=NANE:=.ESSENTIAI SERVICE-HATER=-=
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-- =  ---==-. -=- = -
--.=--FLOH-DIAGRAlf: 5113-36 RUN DATE AND TINE: 14SEP87:13:28 VALVE--===----t VALVE POSITION=I
I 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)
VALVE-POSITION=-I-I
=------TYPE-COORDI OPER--FUHICT-ICI.------REQUIRED PERFORHED---HiODE-2-H)lO-704-2H 0 BF 20 HO H/8 C 0 3 A B EF1 EF-1 EF-5 EF-5 ET-054 ET-054 P P 2-)040-706 0 BF 20 HO e/8 0 0/C 3 a e EF-1 EF-5 ET-056--EF-1 P NO EF-5 HO--ET-056----P HO 2-HNIO-708 0 BF 20 HO 6/6 0 0/C 3 A B EF-1 EF-1.EF-5-EF-5 ET-055 ET-055 P HO HO P NO 2-IOIO-215 BF-12-MO--M/5.C.-0-3--A-B=-EF-1 EF-5 ET-034 EF-1-EF-5 ET-034 P-N)NO P HO 2-hYiO-718 0 BF 12 HO N/5 C 0 A B EF-1 EF-5 ET-036 EF-1 EF-5 ET"036 P N)NO P HO 2-NlO-722 0 BF 6 HO H/6 C 0 3 A B EF-1 EF-1 P NO EF-5 EF-5 NO---ET-023-ET-023---.P-NO 2-h~O-724 0 BF 6 HO N/6 C 0 3 A B EF-1-EF"5-ET-020 EF-1 P EF-5------=------ET-020 P HO NO HO 0'
                                                                                                  --ASME SECTION     XI NUHBER    REV TYPE   SIZE   ACT F D. I POHER          SAFETY LCD A/P     CAT     PRIH TEST         TEST           TEST   RELIEF REQUEST(S)
0.~DONALD C.COOK NUCLEAR PLANT SECOttD TEN YEAR INTERVAL VALVE SLPi~tARY SHEET-UiNZT 2 SYSTEH-NANE:
                              - 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.
-ESSENTIAL-SERVICE-HATER
EF-5
---=-.--FLOH-DZAGRAtt:
                                                                                                  -- EF=2-EF"5
-=2-5113-36 RUiN DATE AND TZttEt 14SEP87:13:28-VALVE==----==--=I--VALVE-POSITION I I I-ASttE.=SECTION-XX NUiiBER REV TYPE SIZE ACT F.D.I POWER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD I OPER=FUiN'CT-ICL--=REQUIRED-PERFORttED
                                                                                                            - ==-             YESi NOTE HO 1--
--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
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 BF-D tt-.-F/<-C-0-=--.3=-A=B.EF-1 EF-1 P=NO 2-ESH-171"S 0 BF 3 H F/1 C 0 3 A B EF"1 EF-1 P NO 2-ESH-240 0 BF 6 H H/5 C 0 3 A B EF1 EF-2 R YES'OTE 2 2-ESH-243 0 BF 4 H J/7 C 0 A B EF"1 EF-2 R YES>NOTE 2 2=SV.-14-2E
-.---0=-REL--1-----SA---L/1-C---=-0=-3-=A C--TF-1---TF-1 2-SV-14"2H 0 REL 1 SA lVl C 0 3 A C TF-1 TF-1 2-SV-15-2E 0 REL 0.75 SA G/3 C 0 3 A C TF-1 TF-1 2-SV-15-2H 0 RE L 0.75 SA J/4 C 0 3 A C TF"1 TF-1~V=16=AB 0 REL D~A=L/8..C-0.3 A C TF=1 TF-1 2-SV-16-CD 0 REL 1 SA L/8 C 0 A C 7 F1 TF-1 NO 2-hYiO-703-2E 0 BF 20 NO N/8 C 0 A B EF1 EF-5 ET-053 EF"1 EF-5 ET-053 NO NO HO  


0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUi81ARY SHEET-UNIT 2 SYSTEM-NAME:
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
-ESSENTIAL-SERVICE-HATER
                = VALVF                  I -VALVE-POSITION= I                         ASME= SECTION XZ.
-=-=-=-.--=FLOW-DIAGRAM: 5113 -==RUN DATE AND TIME: 14SEP87:13:28 VALVE-I VALVE POSITION I---------AQ)F=SECTZON-XZ-I I NLRGER REV TYPE SIZE ACT F.D~I POWER SAFETY (CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
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---FUNCT=ICL---=------REQUIRED--=-PERFORMED-
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
--MODE------2-ESW-102-2E 0 CK 20 SA H/8 C 0 3 A C CF-1 CF-1 P HO 2-EN(-102-2W=-0=-CK= =-SA H/8 C===.0-3-A-.C-CF-L CF-1 P NO 2-ESH-141 0 CK 6 SA K/6 C 0 A C CF1 CF"1 P NO>NOTE 1 2-ESH-142 0 CK 6 SA L/6 C 0 3 A C CF1 CF-1 P NO)HOTE 1 2-ESH-143 0 CK 6 SA M/6 C 0 3 A C CF-1 CF-1 P NO>NOTE 1 2=ESW-144=0=CF~6
-----SA--H/6----C-----
--0----3-A-C-===CF-1-=---CF-1--.P NOp NOTE 1---2"ESW-145 0 BF 4 M J/6 C 0 3 A B EF-1 EF-2 R YES>NOTE 2 2-ESW-168-N 0 BF 3 M H/1 C 0 3 A B EF-1 EF-1 P NO 2-ESW"168-S 0 BF M H/1 C 0 3 A B EF1 EF-1 P HO 2-ESW-169-N -BF=3=--H=-=-G/1-=0 C-----3-A-B----EF.-l-EF-1---=--P-NO 2-ESW-169-S 0 BF 3 M G/1 0 A B EF1 EF-1 2"ESW-170-N 0 BF 3 M F/1 0 C 3 A B EF-1 EF-1 P HO SYSTEN-NANE:=FEEDHATER DOiNALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUiiHARY SHEET-i%IT 2=FLON-DZAGRAH:=--2-5106A-41--
RUN DATE AHD TINE: 14SEP87:13:28
----VALVE--=
-==-=-=-=I=VALVE-POSITION I--I I--ASME SECTION XZ--HU'SER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIt1 TEST TEST TEST RELIEF REQUEST(S)
-TYPE COORD I OPER--FUHCT-I CL---.--REQUIRED-PERFORNED-NiODE 2-FN"160 2 CK 1 SA N/9 C 0/C 3 A C CF 1 CF-1 P NO>NOTE 5 2-FN-161-=0
--CK--8-----SA-J/7 C-.0---3--A--C---.CF-1-CF-1 P HO 2-SV-160-I 0 REL 0.75 SA E/1 C 0 3 A C TF-1 TF-1 R HO 2"SV-140-2 0 REL 0.75 SA D/I C 0 3 A C TF-1 TF-1 2-SV-169-A 0 REL 0.75 SA K/9 C 0 3 A C TF-1 TF-1 R N)2-SV-169-8--
--0--=-REL-=0.75 SA G/9--C 0----3 A C TF-I-=TF-1 R HO--
SYSTEM-NAMF:.--FEE DNATE R DOiNALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUttttARY SHEET" UiNIT 2--=FLOM.DIAGRAM:-
.2=5106A>>41 RUN DATE AND TZtfE)14SEP87:13)28
-VALVE-----------=-=I-=VALVE POSITION-I-I I AstlE SECTION XZ NUMBER REV TYPE SZ2E ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE-COORDI-OPER
-=-FUiiCT ICL=----REQUIRED PERFORMED-
----MODE 2-FN-132-3 2, CK SA D/5 C 0/C 2 A C CF-1 NOTE 1 YES>NOTE 1 2-FH"132 =2=CK=~---SA C/4.C--0/C-2.A=..C----CF.-1-.-NOTE 1=---=---YES>NOTE 1 2" FH-134 0 CK 10 SA B/9 C 0 3 A C CF1 CF-1 P NO>NOTE 2 2-FN-135 0 CK 8 SA E/8 C 0 A C CF1 CF-1 P NO>NOTE 2 2-FM-138-1 2 CK 4 SA C/4 C 0/C 2 A C CF1 NOTE 3 YESp NOTE 3 2-FH-138-2
-2=CK--4:-.--=SA=D/5-C=-0/C---2--A C----CF-1-ROTE 3--=--=-YES>HOTE 3--2-FH"138-3 2 CK SA D/5 C 0/C 2 A C CF-1 NOTE 3 YES>N)TE 3 2-FW-138-4 2 CK 4 SA C/4 C 0/C 2 A C CF-1 HOTE 3 YES>NOTE 3 2-FH-149 0 CK 0.75 SA D/2 C 0 3 A C CF1 CF-1 P hN)p NOTE 4 2"FN"150=-
=-0-CK--0.75---SA=-D/3 C-0 3 A C---CF-1-CF-1 P NO>HOTE 4 2-FH-153 2 CK 1 SA tt/9 C 0/C 3 A C CF-1 CF-1 P HOp NOTE 5 2-FH-159 0 CK 6 SA L/7 C 0 3 A C CF1 CF-1 P HO 4
SYSTEM NAME:=FEEDHATER DOiiALD C.COOK NUCLEAR PL)80'ECOiHD TEN YEAR INTERVAL VALVE SUi'IMARY SHEET-UNIT 2 FLOH DIAGRAM: 2&106A=41 RUH DATE AHD TIME: 14SEP87:13:28 VALVE--=--..---I-VALVE-POSITION-I---.-.---.----.--.-----ASME=SECTIOH-XI I I NUMBER REV TYPE SIZE ACT F~D.I PONER SAFETY I CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE COORDI OPER--FUHCT-ICL----REQUIRED
=PERFORMED.MODE 2"FMiO-242 0 GL 4 MO B/4 0 0 3 A B EF-1 EF-1 EF-5 EF-5 ET"030 ET-030 NO NO NO 2-FRV-247 0 GL 1 A M/9 C C/0 3 A B EF-1 EF-5 EF=7==-ET-008 EF-1 EF-5 EF=7=ET-008-P P HO NO.NO 2=F.RV=257 0-G~A H/9 C C/0 3 A B.EF-1 EF"5 EF-7 ET-005 EF-1 EF-5 EF-7 ET-005 P P P HO.N)HO NO 2-FRV"258 0 GL 1 A E/9 C C/0 3 A B EF-1 EF-5 EF=-7==ET-005 EF-1 EF-5 EF-7 ET-005 P P P NO HO NO HO 2"FHD24 0 CK-8---=SA.F/7-C--0-3-=A-C=CF-1-------CF"1-----P.-HO 2"FN-128 0 CK 6 SA H/7 C 0 3 A C CF-1 CF-1 P HO 2-FH-132-1 2 CK 4 SA C/4 C 0/C 2 A C CF-1 NOTE 1 YESp NOTE 1 2-FH-132-2 2 CK SA D/5 C 0/C 2 A C CF-1 II',OTE 1 YES>NOTE 1  


SYSTEM-NAME:
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    =-- === ---
-FEEDNATER DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUGARY SHEET UiiIT 2 FLON DIAGRAH: 2-5106A"41 RUN DATE AND TIHE: 14SEP87:13:28 VALVE----I-VALVE-POSITION=I
                                          =    = -           FLOH -DIAGRAM: =2-51059-2 VALVE  ==-==                  .
--.----.---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)
I VALVE POSITIOH I                                -ASME SECTIOH  Xl=--
---TYPE COORDI.-OPER
I                     I NUMBER    REV TYPE   SIZE     ACT F.D.
=--FUNCT=-ICL=-
                        =------- TYPE-COORDII POHER OPER- =
--------REQUIRED---PERFORMED-HODE-2" FHO-211 0 GL 4 ViO B/4 0 0 3 A B EF)EF-5 ET-025 EF-1 EF-5 ET-025 P NO NO P NO 2-FHO" 212 0 GL HO B/4 0 0 A B EF1 EF-1 EF-5 EF-5=ET.-031.-ET-031 2FH0221 0 GL 4 HO C/5 0 0 3, A B EF)EF-1.EF-.5..EF-5 ET-021 ET-02)P NO NO P NO 2=FH0=222 0 GL 4..HO C/5 0 0 3..A=B--EF-1-----EF-1 P NO EF-5.EF-5 NO ET-036 ET-036 P NO 2" FHi 0"23)0 GL 4 HO C/5 0 0 A B EF-1 EF-5 ET-026 EF-)EF-5 ET-026 P NO NO P NO 2-FHO-232 0 GL 4 HO C/5 0 0 3 A B EF-)EF-1 EF-5 EF-5 ET-034=-=ET=034.=P NO NO P NO 2-FHiO-241 0 GL 4 HO B/4 0 0 3 A B EF-1-EF"5.ET-024 EF-1-EF-5 ET"024 P NO NO P NO
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


SYSTE!1-NAttEt
l 0
-FEEDHATER-DONALD C.COOK NUCLEAR PLAttT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UNIT 2 FLON DZAGRAtt:--2-5106 "34-RUN DATE AHD TIttE: 14SEP87:13:28 VALVE---=--I VALVE-POSITIOtt I------.-------ASttE SECTION XZ I I tlUt%ER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRItt TEST TEST TEST RELIEF REQUEST(S)
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          =-
-TYPE COORDI OPER--FUNCT--ICL---.---REQUIRED----PERFORttED
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)
-ttODE 2-FRV-240 0 AG 14 A H/5 0 2 A B EF-1 EF-5 EF-7 ET"005 EF-2 EF-5 EF-8 ET-005=-C YES7 NOTE 1 ,NO C ttO)NOTE 1 C-HO 0
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 -=--
SYSTEH-NAHE:=
                                                                                          .      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-= =--
FEEDklATER--
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
DOiNALD C.COOK NP'LEAR PLANT SECOND TEH YEAR INTERVAL VALVE SVC%RY SHEET-UNIT 2-.-FLOH.DIAGRAH:=-2-.5106.-34 RUN DATE AND TINE: 14SEP87:13:28 VALVE---=----==-.-=-=-I VALVE-POSITION=-I-I I NUHBER REV TYPE SIZE ACT F D.I POHER SAFETY LCD A/P CAT-TYPE-COORDI OPER-FUNCT.--ICL-
-==--ASME SECTION XI PRIH TEST TEST TEST RELIEF REQUEST(S)
REQUIRED.-==-PERFORHED--NODE 2-FHO-201 0 GA 14 HiO G/5-0 C 2 A EF-1 EF-5 ET-020 EF-2 EF-5 ET-020 YESp NOTE 1 HO NO 2-FN)-202 0 GA 14 HO E/9 0 2 A B , EF-1 EF"5 ET-018==EF-2 EF-5=--ET-018=--YES>NOTE 1 NO-.HO 2-FHO"203 0 GA 14 HO F/9 0 C 2 A B EF-1--EF"5 ET-019 Ef-2 EF-5 ET-019 C YES>NOTE 1 HO C HO 2-FHO-204-=0-GA~4=---N)=-H/5--0---C=-2=-A-B-EF-l.-EF-5 ET-019--EF=2----==-EF"5 ET-019 YESi NOTE 1--HO NO 2-FRV-210 0 AG 14 A G/5 0 EF-1 EF-5 EF-7 ET-005--EF-2 EF-5 EF-8-ET-005 C YES>HOTE 1 NO C NOi HOTE 1 C--NO-2-FRV-220 0 AG 14 A E/9 0 C 2 A 8 EF-1 EF-5 EF-7 ET-005 f F-2 EF-5 EF-8 ET-005 C YES>HOTE 1 NO C HOp HOTE 1 C NO 2-FRV-230 0 AG 14 A F/9 0 2 A B EF-1 EF-5 EF-7 ET-005 EF-2 EF-5 EF-8 ET-005 C C C YES>NOTE 1 NO HOp NOTE 1 HO 0 DONALD C.COOY.NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SALARY SHEET-UNIT 2 SYSTEM-NAllE:~TEAM GEHERATIHG.SYSTEM-
-.-..-=.=-.=FLOH DZAGRJQJ: 2=5105D=2 RUN DATE AND TZME: 10SEP87:13:28
-=VALVF-I-VALVE-POSITION
=I I I ASME=SECTION XZ.NUMBER REV TYPE SIZE ACT F.D.l POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
TYPE=COORDI OPER---FUHCT.-ICL REQJZRED PERFORMED MODE 2-SV-3-1 0 REL 6 SA B/5 C 0 2 A C TF-1 TF-1 2=SV."3=2 0-REL.6==SA==M/5=C.
=0=..2=A C TF-1.TF-1 R HO 2-SV-3-3 0 REL 6 SA M/1 C 0 2 A C TF-1 TF-1 R HO 2-SV-3W 0 REL 6 SA B/1 C 0 2 A C TF-1 TF-1  


DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UI'lIT 2 SYSTEM-NAMEMTEAM
DONALD C. COOK NUCLEAR PLANT                             RUN DATE AND  IIHE: 14SEP87:13:28 SECOND TEN YEAR INTERVAL SYSTEM-NAME:=-STEAH-GENERATING=SYSTEM--=---       -=-=- =
=GENE RATING-SYSTEM-==--=-===----FLOH-DIAGRAM:=2-51059-2 RUN DATE AHD TIME: 14SEP87:13:28 VALVE-==-==I.VALVE POSITIOH I I I-ASME SECTIOH Xl=--NUMBER REV TYPE SIZE ACT F.D.I POHER SAFETY)CD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
VALVE SUPssQRY SHEET FLON-DIAGRAM:-=2"51050                                                                                          UNIT 2
-=-------TYPE-COORDI OPER-=FULNCT=-ICL-
                ---- 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)
---=--REQUIRED--PERFORMED--MODE 2-SV-18-1 0 REL 6 SA 8/5 C 0 2 A C TF-1 TF-1 2-SV-18-2-=-0=-REL--6----SA---L/5---C--0-----=2--A--C-TF-1-TF-1 R NO 2-SV-18-3 0 RE L 6 SA L/1 C 0 2 A C TF-1 TF-1 R NO 2-SV-18-4 0 REL 6 SA 8/1 C 0 2 A C TF-1 TF-1 2"SV-2A-1 0 RE L 6 SA 8/5 C 0 2 A C TF-1 TF-1 2-SV.-RA-2=.0
                              ===-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
-.REL-6..-.--SA-.-L/5.C--0.---2-A 0-TF-2 TF-1-R HO 2-SV-2A-3 0 REL 6 SA L/1 C 0 2 A C TF-1 TF"1 R HO 2-SV"2A-4 0 REL 6 SA 8/1 C 0 2 A C TF-1 TF-1 2-SV-28-1 0 REL 6 SA 8/5 C 2 A C TF1 TF-1 2-SV-25-2-0-REI-6---.SA-: L/5.0-0 2 A C TF-1---TF-1 2-SV"28-3 0 REL 6 SA L/1 C 0 2 A C TF1 TF-1 2-SV-28&0 REL 6 SA 8/1 C 0 A C TF-1 TF-1 R HO l
                                                                              =- ET.-005 ET-005          C     NO 2-HRV-221      0     AG    2       A     H/5     C       0 EF-1 EF                                                                                        EF-7 EF-1
SYSTEtt-NAttE:=STEAtt-GENERATING-SYSTEtt
                                                                                                    -EF-5 EF-7 P
---0 DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVF SUi'tttARY SHEET-UNIT 2--==FLON-DIAGRAtt:=-2-51050 2-=-RUN DATE AHD TINE: 14SEP87:13:28 VALVE-I-VALVE-POSITION-I I I AStfE-SECTION-XL-HUiitER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRZtt TEST TEST TEST RELIEF REQUEST(S)
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
TYPE-COORDI-OPER==FUHCT=ICL=-""--" REQUIRED PERFORHED-NODE 2-tkRV-240 1 GA 28 PO B/3 0 2 A B EF-1 EF-3 EF-5 EF-5 EF-7 EF-8 ET" 005-.-=----ET-005 C C-HOp NOTE NO t<0>HOTE 2 NO 2-HRV-241 0 AG 2 A A/1 C 0 2 A B EF-1 EF-5-EF"7 ETF-002 EF-1 EF-5-=EF-7 ETF"002 P HO-==-=HO P HO P HO 2-ttRV-242 0 AG 2 A A/1 C 0 B EF-1 EF-5 EF-7 ETF-002---
                                                                                    -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-1 EF-5 EF-7 ETF"002-P HO HO P ttO P--HO 2-NS-108-2 2 CK SA K/4 C 0/C 3 A C CF"1 CF-2 R YES'OTE 3 2" HS" 108-3 2 CK 4 SA K/4 C 0/C 3 A C CF-1 CF-2 R YES>HOTE 3 2-SV-ZA-1 0 REL 6 SA C/5 C 0 2 A C TF-1 TF"1 2-SV-1A-2-0-RE L-6-SA=-K/5--C---==0--.2-A=C TF-1 TF-1 R-HO-=-=----2-SV-1A-3 0 REL 6 SA K/1 C 0 2 A C T F1 TF-1 R NO 2-SV-1A-4 0 RE L 6 SA C/1 C 0 2 A C TF 1 TF-1 R HO
                                                                                  =-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 NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUPssQRY SHEET UNIT 2 SYSTEM-NAME:=-STEAH-GENERATING=SYSTEM--=---
        ~                                                                    ~
---=-=-=FLON-DIAGRAM:-=
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)
2"51050 RUN DATE AND IIHE: 14SEP87:13:28
                              -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
----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)
                                                                              -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--
===--TYPE-COORDI
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
-OPER-=-FUiNCT
-ICL------REQUIRED PERFORMED=MODE 2-HRV-220 0 GA 28 PO L/7 0 2 A EF-1 EF-5 EF-7=---ET.-005 EF-3 EF-5 EF-8 ET-005 P C C NOp NOTE 2 NO NOp NOTE 2-NO 2-HRV-221 0 AG 2 A H/5 C 0 EF-1--EF-5-EF-7 ET-003 EF-1--EF-5-EF-7 ET-003 P NO NO P NO P NO 2-HRV-222 0 AG 2 A H/5 C 0 EF-1 EF-5 EF-7-.--ET-003 EF-1 EF-5 EF-7 ET-003 P NO NO P NO-P NO 2"HRV"230 0 GA 28 PO H/3 0 C EF-1--=-EF-5 EF-7 ET-005 EF"3 EF-5 EF-8 ET-005 P NO NOTE 2 NO C NOp NOTE 2 C NO 2-HRV-231 0 AG 2 A H/1 C 0 2 A B EF-1 EF-5 EF-7 ETF-002 EF-1 EF-5 EF-7 ETF-002=P P-P-NO NO NO=NO 2-HRV-232 0 AG 2 A H/1 C 0 2 A B EF 1=-EF-5-EF-7 ET-003 EF-1 EF-5--EF"7 ET-003 P P P NO NO---NO NO  


~~DONALD C.COOK tRCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUtDIARY SHEET UNIT 2 SYSTEM-NAME:
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  
-STEAN.GENERATING SYSTEM-=-.----:--FLON DIAGRAM:-..2-.5105D=2 RUN DATE AND TIME: 14SEP87:13:28
                    -YAivE-           I YALYE.POszTIO>l   -I                         -
-VALVE I-VALVE=POSITION-I I I AStK SECTION-XZ tmHBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT-TYPE-COORDI-OPER
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)
-FUNCT-ICL PRIM 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
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=-
                                                                                - 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
CK==14-SA K/8.-0=..C=.2-.A-C.-.CF-1 CF-2 R.YES>NOTE=1 2-FH-118-3 0 CK 14 SA J/3 0 C 2 A C CF-1 CF"2 R YES>NOTE 1 2-FW-118-4 0 CK 14 SA C/3 0 C 2 A C CF"1 CF-2 R YES>HOTE 1 2-MCH-221 0 GL 4 HO K/4 0 0/C 2 A B EF-1 EF-5 ET"049 EF-1 EF.-5 ET-049 P HO NO P NO 2-HCH-231 0 GL 4 HO K/4 0 0/C 2 A B EF-1 EF-5 ET-050 EF-1 EF-5 ET-050 P NO HO P HO 2-HRV-210 0 GA 28 PO 8/7 0 C 2 A B EF-1 EF-3-EF"5---==EF-5---EF-7 EF-8 ET-005 ET-005 C C HOi NOTE 2 NO-HOW HOTE 2 NO 2-MRV-211 0 AG 2 A A/5 C 2 A B EF-1 EF-5 EF-7 ET-003=EF-1 EF-5 EF-7 ET-003 P P--2-HRV-212 0 AG 2 A A/5 C 0 2 A B EF"1 EF-1 EF-5 EF-5 EF-7 EF-7 ET-004 ET-004 P NO HO P HO P NO SYSTEtt-NANE:
-tQIN-STEAN DONALD C.COOK tRCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SViNARY SHEET" UNIT 2---FLOH DIAGRAN: 2-51058 --RUiN DATE AND TINE: lOSEP87tl3:28
--YAivE------I YALYE.POszTIO>l-I I I-ASNE SECTION Xl HUNBER REV TYPE SIZE ACT F.D.I POHER SAFETY (CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)
=TYPE=COORDI OPER-FLIiCT=ICL------REQUIRED--PERFORNED NODE 2-DCR-310 2 GL 2 A B/3 0 C 2 A B EF-1 EF-5 EF-7 ET-006-EF-1 EF-5 EF-7 ET-006 P ttO NO P HO P NO 2-DCR-320 2 GL 2 A B/2 0 C 2 A B EF-1-EF=5=--=EF-7 ET-006 EF-1 P EF-5-EF-7 P ET-006 P HO-HO--HO HO 2-DCR-330 2 GL 2 A B/1 0 C A B EF"1 EF-5 EF-7 ET-008--EF-1 EF-5 EF-7 ET-008 P HO HO P NO-P NO 2-DCR-300 2 GL 2 A B/2 0 2 A B EF-1 EF-5=-EF-7 ET-009 EF"1 EF-5 EF-7 ET-009 P NO-HO-P HO P NO 2-QT-506 0 GL HO A/8 C 0 3 A B EF1 EF-5 ET-023 EF-1 EF-5 ET"023 P HO NO P HO  


~e DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE Sly~>ARY SHEET-UNIT 2 SYSTEM=SQ1E:
        ~                                                                   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 -
-PAL-SAMPLING=S--INST-.
                  -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)
=PAHELS=U-2=--FLIN-DIAGRAM:-.--12-5141F-6
                                -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
-----RUH DATE AHD TIME: 14SEP87:13:28
---VALVE---I=VALVE-POSITION I I I--ASME SECTION XI--NUMBER REV TYPE SIZE ACT F.D.t POHER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORDI-OPER
-=FUHCT-.--lCL--=-
-----REQUIRED PERFORMED-MODE-2-SM-I 0 CK 1 SA A/3 0 2 A AC CF-1 SLT-1 CF-2 SLT-2 R YES'OTE 3 R YES>NOTE 2  


DONALD C.COOK NlCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SlMCARY SHEET-UNIT 2 SYSTEN-HANE:
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== =----
-PAI NlNPLZHG-8=INST.-
I                    I HUYBER   REV TYPE
PANELS==U-2=FLON-DZAGRAN:.
                      = SIZE     ACT   F.D. I PONER
~2-5141F-6 RUH DATE AND TINE: 14SEP87:13:28 VALVE I VALVE.POSITION.I I I ASNE=SECTIOH-XZ==
                          - == TYPE-COORDI=OPER--=-
=----HUYBER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)
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
=--==TYPE-COORDI=OPER--=-
                                                                                =-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
-FACT-ICL-------REQUIRED PERFORMED-NEODE 2-ECR-31 2 GL 1 A B/3 0 2 A A EF-1 EF-5 EF-7-=-ET-005 SLT-1 EF-1 EF-5 EF-7 ET-005 SLT-2 P NO HO P HO P NO R YES>NOTE 2 2-ECR-.32-2-GL-5.-2-B/5--5----2-=2-=A=-=-A===EF-1 EF-5 EF-7 ET-005-----SLT-1--EF-1-EF-5 EF-7 ET-005-SLT" 2 P P P R NO HO HO HO YES>HOTE 2 2"ECR-33 2 GL 0.75 A B/2 0 C A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-1 EF-5-EF-7 ET-004 SLT-2 P P R HO HO-NO HO YES>NOTE 2 2-ECR-35 2 GL 1 A B/2 0 C 2 A A EF-1 EF-5 EF=-7-ET-004 SLT-1 EF-1 EF-5-----EF-7 ET-004 SLT-2 P R HO HO NO NO YES>NOTE 2 2-ECR-36 2 GL 1 A B/3 0 C 2 A A EF-1 EF-5 EF-7 ET-004 SLT-1 EF-2 EF-5 EF-8 ET-004 SLT-2 C C R YES'OTE 1 HO NOR NOTE 1 YESR NOTE 1.YES'OTE 2 0 f 0 o DONALD C.COOK HUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNDRY SHEET-UNIT 2 SYSTEH-NANE:
                                                                              - -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.
-PAS-LIQUID 2-GAS==UNIT=2
SLT-1         SLT-2         R       YES'OTE    2
==-=.FLON DIAGRAN:...
12=5141C-.8
.RUH DATE AHD TINE: 14SEP87:13:28 VALVF----t--VALVE-POSITION I I ASME..SECTION.
XZ NEER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIN TEST TEST--TYPF COORD I-OPER=.-.FACT ICL-=-.--REGUIRED PERFORNED TEST RELIEF RE@JEST(S)
NODE 2-ECR-536 0 GL 0.5 A L/2 C A EF-1 EF-5 EF-7 ET-003..SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P P R HO HO HO HO YES>HOTE 1 0
0.DONALD C.COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE SUtaaARY StlEET-UNIT 2 SYSTEH-NAHE-:=-PAS-LIQUID GAS-UNIT-2----------FLON.DZAGRAH 5141C-8
=RUN DATE AND TINE: 14SEP87:13:28-VALVE---=----I VALVE POSITION=-I
-=--=I I ASttE SECTXON XL--h REER REV TYPE SZZE ACT F AD I PONER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
TYPE-COORDI-OPER
-FUNCT---ICL---==--=-=----REQUIRED---PERFORHED-
-tlODE 2-ECR-416 0 GL 0.5 A H/6 C 2 P A EF-1 EF-5 EF-7 ETF-002 SLT"1 EF-1 EF-5'EF-7 ETF-002-SLT"2 P P R HO t<0 HO NO YES'OTE 1 2-ECR-417--0-GL--0.5--A---H/6--C.=-------C
---2----P=-A--EF-1==-==-=-EF-5 EF-7 ETF-002 SLT-1 EF-1====-==-=-=P---HO-EF-5 NO EF"7 P NO FTF"002 P NO SLT-2 R YES>NOTE 1 2-ECR-496 0 GL 0.5 A H/8 C 2 P EF-1-EF-5 EF-7 ETF-002 SLT-1 Ef-1=-=-EF-5=EF-7 ETF-002 SLT-2 P P R NO-HO NO HO YESp NOTE 2-ECR-497 0 GL 0.5 A H/8 C C 2 P EF-1 EF-5-EF-7-=ETF-002 SLT-1 EF"1 EF"5=EF-7-ETF-002 SLT-2 P P P R tm tlO NO ND YES>NOTE 2-ECR-535 0 GL.0.5 A H/2 C C 2 P A EF-1 EF-5 EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P R NO NO HO ttO--YESp NOTE
'
DONALD C.COOK NUCLEAR PLANT SECOiND TEN YEAR INTERVAL VALVE SUEEENRY SHEET-UiNIT 2 SYSTEH-NAME:
=HDS<<VENTS-2i-DRAINS
--FLON-DIAGRAH:=12-5137A RUN DATE AND TIHE: 14SEP87:13:28 VALVE-I VALVE-POSITION I I I=-ASHE=SECTION
=Xl-AMBER REV TYPE SIZE ACT F.D.I POHER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
--TYPE-COORDI-OPER==-
FUNCT--ICL
--------REQUIRED-.
-.--PERFORHED
---HiODE---2" DCR-621 0 DA 1 A N/9 0 2 A A EF-1 EF"1 EF"5 EF-5 EF-7 EF"7-ET-005=---
--ET-005-SLT-1 SLT-2 P=P R NO NO NO NO YESp NOTE 1 2-N-160-O=CK=l==SA=
--F/4-0--==-C--=2=-A--AC-:-CF ---=----CF-2---=-SLT-1 SLT-2--.-2-..TER.MOTE 2 R YESp NOTE 1 2-SF-159=-==--=0 DA-3=----H---'/5--C----
==---C----.-
=2---P--A--SLT-1--..-.-SLT-2---.---.--R----YESp-NOTE 1 2-SF-160 0 DA 3 H F/5 C 2 P A SLT-1 SLT 2 R YESp NOTE 1 0 IP SYSTEN-NANE:-HDS-VEttTS-tt-DRAINS DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE RPittARY SHEET-UHIT 2 F LOlt-DIAGRAtt:-=%2-5137A-2l=-
RUH DATE AND TINE: 14SEP87:13:28
-VALVE-=-----l VALVE-POSITIOiN j I I ASttE SECTION XI ttUtSER REV TYPE SIZE ACT F.D.I POWER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)
=--=TYPE-COORD I=-OPER:---FUitCT I CL--------REQJIRED-=--PERFORYiED
.ttODE 2-DCR-206 0 GL A E/8 0/C 2 A A EF-1 EF-5 EF-7 ET=-005--SLT-1 EF-1 EF-5 EF-7-ET-005 SLT-2 P P P R NO HO NO NO-YESp NOTE 1 2-DCR-207-O=DA---I--=A---F/4--0---=-C==-=--2-A--A-=---EF-1-EF-5 EF-7 ETF-002 SLT-1-EF-1-EF-5 EF-7 ETF-002 SLT-2 P P P R HO=HO N)NO YES'OTE=1 2-DCR-610 0 DA 2.5 A M/9 0 2 A A EF1--=EF=S=EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7 ET-003 SLT-2 P P R NO HO t<O NO YESp NOTE 1 2-DCR-611 0 DA 2.5 A N/9 0 2 A A EF-1 EF-5 EF-7---ET-004 SLT-1 EF-1 EF"5 EF"7 ET-004 SLT-2 P-P P R NO NO NO-NO YESp NOTE 1 2-DCR-620 0 DA 1 A tt/9 0 2 A A EF-1 EF-5 EF"7-ET-004-=-SLT-1 EF"1 EF-5 EF-7 ET-004 SLT-2 P P P R HO NO NO t,'0 YESp NOTE


SYSTEM-NAME:=NDS-VENTS-8-DRAINS DOHALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUta>ARY SHEET-UNIT 2 FLON.DIAGRAM:
0 f
.-12-5137A-21
==RUN DATE AND TIME: 14SEP87:13:28 VALVE I-VALVE POSITXOAN-I-I I-ASME SECTION XZ NlRSER REV TYPE SIZE ACT F~D.I PWER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)-TYPE-COORD I=OPER=-=--
FUNCT=-I CL-----REQUIRED--PERFORMED--MODE 2-DCR-201 0 DA 1 A E/4 C 2 P A EF-1 EF-5 EF-7 ETF=002 SLT-1 EF-1 EF-5 EF"7 ETF-002 SLT-2 P P P R HO HO NO HO YES>NOTE 1 2-000-202 0-02-.0..75--2--0/5 0-A=A--EF=l EF-5 EF-7 ETF-002.SLT-1.-EF-1=--=-EF-5 EF-7 ETF-002 SLT-2 P P R.NO--NO HO NO YES>NOTE 1 2"DCR-203 0 DA 1 A F/4 C 2 P EF-1 EF-5-EF-7 ETF-002 SLT-1 EF-1 EF"5 EF-7 ETF-002 SLT"2 P HO NO P HO P NO R YES>NOTE 1 2-DCR-204 0 DA 0.75 A F/5 0 C 2 A EF-1 EF-5 EF-7 ET-003 SLT-1 EF-1 EF-5 EF-7-ET-003 SLT-2 P NO NO P---HO P HO R YES>HOTE 1 2-DCR-205 0 GL 4 A E/7 0/C C 2 A EF-1 EF-5 EF-7 ET-005--SLT"1 EF-1 EF-5 EF"7 ET-005 SLT-2 P==P-R HO HO NO HO-YES>NOTE 1


0DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SLMSRY SHEET-LAIT 2 SYSTEN-NANE:
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 .
-SPENT-FUEL-PIT-COOLING-8-CLEAN/P-U2
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)
-=-FLSI-DIAGRAN:=-12-5136 -=RUN DATE AND TINE: 14SEP87:13:28 VALVE---=------I VALVE-POSITION I I I AWE SECTION XX NUNBER REV TYPE SIZE ACT F.D.I PFIZER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)-TYPE.COORDI OPER---=FUNCT--ICL------REQUIRED PERFORMED NiODE 2-SF-152 0 DA 2.5 N K/9 C 2 P A SLT-1 SLT-2 R YESp NOTE 1 2-SF--154--0=-GL-2.5=-=N--K/9 C-C-2-P=-A---SLT-1--SLT-2-R YES'OTE 1  
                            - -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 o DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SCARY SHEET-UNIT 2 SYSTEM-NAME.=CVCS--.-.BORON-MAKE-UP==UHITS
0 0                                        .
~8 2=.FLON DIAGRAM:~2.-.5131=19 RUN DATE AND TIME: 14SEP87:13:28 VALV VALVE-POSITION I I I ASME SECTION XI HRKER REV TYPE SIZE ACT F.D.I PONER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUEST(S)
DONALD C. COOK NUCLEAR PLANT                                 RUN DATE AND      TINE:  14SEP87:13:28 SECOND TEH YEAR INTERVAL SYSTEH-NAHE-:=-PAS-LIQUID2-GAS  UNIT-2 -- -- --   -
TYPE-COORD I=OPER-=--FUHCT
VALVE SUtaaARY StlEET FLON.DZAGRAH    -
=I CL=-=.==REQUIRED.PERFORMED-MODE 2-CS-415-3 1 CK 2 SA K/6 0/C 0 A C CF-1 CF-1 P HO R=CG-413%~K
UNIT 2 12-5141C-8  =
-2.GA L/6--0/C.-.-0-.-E,--A..2.-CF-1-CF-1...P BO 2-CS-026-S 1 CK 1 SA M/6 0/C 0 A C CF-1 CF-1 P NO 2-CS-027-S 1 CK 2 SA M/5 C 0-3 A C CF1 CF-2 C YESP NOTE 1 2-QMO-420 1 GA 2 MO L/5 C 0 3 A B EF-1 EF-5 ET-012 EF-1 EF-5 ET-012 P HO HO P NO 2-QRV-421 1 GL 2 A M/6 0/C 0 3 A B~EF-1 EF-5-EF-7-ET-006 EF-1 EF-5 EF-7 ET-006 P HO NO P HO P HO 2-ERG-422-~GL-
                  -VALVE       =-
-.2.----A.=-0/2--0..--0.--3-A-0---EF=1.-----EF-1-.EF-5 EF-5 EF-7 EF-7 ET-005 ET-005-==.=P=--=-=HO HO HO HO
                                      - -- 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


0=e DONALD C.COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUE)ARY SllEET-UNIT 2 SYSTEN HANE'=CO)PRESSED~RMYSTEN UNIT 2-==.FLON DIAGRAM:=12"51208=22 RUN DATE AHD TINE: 14SEP87:13:28 VALV
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                   
Vt(OCWttsfec~)
Vt(OCWttsfec~)
FOR ICEVIS>QN OKSCICPTICN SCE SEPARATE/ttvtstQN RECC/O fOR IleS ORAWJIC i K iSI CL)tt4Rt/.51'r FC CKOSSR>t TO AVCI r ROM UiilrlrOR COMC 51 f PVIG I.Q>OGA.M/9 CPX 2$)~6 FRQN KSSKVTLLL 2 SERVICE WATER/r PUMPS.SCC CWe Att 2'5 IO il/6 WNQ 75)erc>Scf CSW 210 4<N)TKX weii CS)ttefi)/CS.V440 I TCST 3>14.ii.5.a'wvc I FL'Ok TURB.QRIVKN CPF)c>KC Vttf KR.SCC~SKETCH 0 t.CCA 4 1s t~lcr fW.O)-/V/O4 ric 14$I I PP-4.6 c rpt 5 Stt.CT DUPLC K 5'TR*ttlf IK O PUIAP 9/)PJ GP>4 2114 ifc TQK 4)'0 2>54 900 tcp kcr.QSCIL Pt!SS:-1443 4$1$SCI.(Orct 53 I TURBINE-()DIV N AUXI IARY FRV.Z$8 (KNKRCKN T LcAK orf YALvg)FFX f 2>t.2$6 It(sf YA'Y lt.C f 110 Wlesltlf QRIVKN CQQUtre W41CR.SKE SKKICH'02>i i Uti."5 Set ORTAIC Ci/5F/FD>c CPX 24$
(t(Kff,                                                                                                  FV/4)6 rK424            rrfsr CCKN J                                              rw.Its                                                                                                                                  IW 166                              FW.I$ 8 4      FRCM    t)sc IT~X                                                                                                                                                  (rDRMII)
ALLSIKTIOM 4 DISCHARGE                                                                                                                                                    SCRVICC VIATKR PIPIIIG FOR A JXILIARY 7'EED                                                                                                                                              pgt/p SLE          prs
                                    .Pukps      TO  SERG)        I                                                                                                                                            Z-sil).K/6                                                6 CP                                                  IW 128                                                                                                                                                                                                                    FOR ICEVIS>QN OKSCICPTICN SCE PJ/f)$                                                                                                                                                                                                                                                                              FW455 SEPARATE /ttvtstQN RECC/O FPX CC                                                                                                                                                                                                                                                                                        fOR IleS ORAWJIC 2$ /
mo        vve)v~vee>ececee acctvc ceece He>tee ceep. w 5 tvw                              V CPX 2$ )
rpt                                                                CDX                                            Pl                                  Set ORTAIC Ci/5F/                            CPX                                                            rpi                            l.Sff.                                                          ~ t>e  ev\ev >w e v w ie v wwvv
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  ~ e >>tee      v wv ee v >vc ee VV pv t>e Pew>ice ie w iv veev ee i
2 6 FRQN      KSSKVTLLL
                                                                                            ~                                  5                                                                254                                          ts4                                                                                24$
CETAIL 6'5      tt/5-                          ww
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  ~ etta eww ei ee el ~ ecetttcc cev ee                                i ric  14$  I                                                                                                    Isl                                                  FD>c SERVICE WATER                                                                                                                                    SV. I 69C I/5'5                                                                                                                      SV                ttrCI              1$ 1                                                                                                                            ee w Iwve eevwta ie >ve <<ve>5
                                      /r 2'5 IO PUMPS. SCC CWe            Att    I FL'Ok TURB.          I                                                                                                    IHJGQ                  CL)                                                  147                                            >cesar>C sef 0 Ho rstc                  I                                                                                                                                    w e ie H >ct>we eeevvev
                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                  ~                                                                      1.
FRV.Z$ 8 I'fieetso il/6 WNQ 75) erc>
QRIVKN CPF)c>KC VttfKR. SCC t.
(KNKRCKN T LcAK orf YALvg)                                                        p    gg,i                                                    f FRY 2$ 7 I NKRGKNCY)
Se  etc                                              dv FRY-247 (EMERGENCY                                          pe>IA>>A ~ eicHIOAH cecil>tie cch                                  r iSI CL)            CSW 210                4<
                                                                      ~  SKETCH 0                                                                                                                  I re7                                                                          LKAKOffVALVE)
I CAP R
                                                                                                                                                                                                                                                                                                                                                                                  'e 5
LEAKnrr VALVE),
ffresp                                              . DONALD C. COOK 221 l
Scf                                                                                                                                                                                                                                                                                                                                                                                                                                                                                    IIUCLEAR PLA/IT tt4Rt/.51  N)TKX    weii                                        CCA Stt.
FFX rfx                                                                                                                                                                                                                                                  c
                                            /
                                                                                                                                                                                              <DC                                                                                                                                                                                                                                                                                                ~ 4>044>K CS) ttefi)        CS.V440                4          1s t~                                                                        f2>t. 2$ 6 It(sf YA'Y                        1$                                  TO                                        FV/ IS'                                                                                                                                            IW. 60                    4 FFX
                  'r                          I TCST 3>14.
ii .5. a'wvc          lcr                          .6 c PP-4 lt                  r                        8 FLR.
                                                                                                                                                                                                                                    .6 PP-58 4,      6 FW. I)$
4 FW 1
I)4, 244 FLOW DIAGRAM FC.                                                                                                                                      SZ  ~
Fv                                                                                                                                              tts Y                                                                                                                        AUX: Fe.ED(AIC,TER FC                            fW.O)      -/V/ O4                                                                                                    .C                            5                  CADc f  -r                                                                            e)t 4                          cccee Cctv  >      ~>        WCST UNIT 2 CKOSSR>t TO AVCI r ROM                                                                                  TURBINE-()DIV N AUXI IARY                                      f                                  CTX                                LlR(VC'N AUk(L)ARY                        fRV.2$ $
t                          DUPLCK STRA>>eea                            LIOTOR.DRIVEN AUXI(IARY                                                  rev MIQS&dl 1'1OTOR 110 Wlesltlf UiilrlrOR COMC 51  f CT O PUIAP                              QRIVKN CQQUtre                                                              r EEO PU)JF>
(T ST,VAL'/i)                                    SZW                  i                    Ute            PUUP                                          VALVf) tcs'TCST PVIG I.Q>OGA.M/9 9/)PJ GP>4          2114 ifc TQK                  W41CR. SKE SKKICH'02
                                                                                                                                                                                    )'CPLRk                      410GDM 2)tcrCTQH 340ORDM ~HP
                                                                                                                                                                                                                                                      )                                                LSI 4$ 0 GP>L,Z)M FT. TCH 5600 RPN 500 HP                                                                                                        VC DUPLC K      5'TR*ttlfIK            4)'0    2>54        900 tcp                                                        'tRA>MCR NAX 01SCH PRESS isfQ P51G'c)                                                                                      ~                MAX. DOCH Peers. 1$ $ 0 PSIG SCJ.                                                                                                                C kcr. QSCIL Pt!SS:- 1443          4$ 1$                                              Ocet 328 (Orct 53 I                                                                                                                                                                                                                                                                                                                                                                                                                                                    Ce SCI.
                                                                                                                                                              >i Uti. "5 i                                                                                                                                                                                                                                                                                It                                                              ~.
i ISI CLS                                                                          lit                                                                                                            II 0                (                  C                                                                                                                                                                                        H                                                                                                                                                                              M                I            ~ N                                  O                                  t>
SY101302                                              ls-0$
 
e It '
S 1  '~~A S S
I
 
A tel)5.Z, I
N)H.NO I  ~        c          '
sff FROM AIR HLHDLINC UNIT.
t DNC. 5149,5/SsH/3 illa lit.sl G
l)'o MR Nawo($
sti  DN(.Z
                                                                                                                                                                                                                                  )
Sll'I 14 FISH/5 ESYPFCS.S f SYI I cd u Vsot.
WFI 744.5 vef I )4)at I
4    Vtwt~
K      ''      f
                                                                                                                                                                                                                                                                                                                                                                              ~tswtu CSWtu M saw tlw ud.
                                                                                                                                                                                                                                                                                                                                                                                                  ~ L~  ~
c te pv
                                                                                                                                                                                                                                                                                                                                                                                                                      ~ Las fff)on I
SOC Etefe((7(Hfdf SPRAY HEAT EX HAN(cRS
                                                                                                                                                                                                                                                                                                                                                                                                                                                          .      M r
Oo.daw CSW 141 GENERAL '))OTES LEGENO SUPPLY PIPING 2 10 JUIIB(NE                                                              5 ttST Coaat(ttn)                            asR    YCNtvaLYC I'(LTq                                    Wtl                        Ott Dar      t 5)49 IILPT/S                                                          WFI 5001 Hoou suatra 5fE p a.        IS.LA 5
                                                                                                                                                                                                                                                                                                                                                                                                                      ~
r>>i aw r'Ll ~
Fsfaac,serai)sot)sr (SU                                      N SY          Hsf                                          R=TURN PIPING S (C Da)C      t 3)41  C.K/3                                        1                OLLV DISCI). TO FLDOZ                                                                                                              AVX. PIPING g- g/                                                                          TD u
IPitt

Latest revision as of 00:47, 4 February 2020

Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML17334B150
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/05/1987
From:
INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17326B298 List:
References
AEP:NRC:0969H, AEP:NRC:969H, PROC-871005-01, NUDOCS 8710130278
Download: ML17334B150 (317)
v • d • e


Text

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

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

SUMMARY

SHEETS

7. FLOW DIAGRAMS

~ l01,30278. 87l005~

PDR .- ADOCN,'05000315 P PDR~

Page 1 of 7p

ASME SECTION XI VALVE TEST PR 2ND TEN YEAR INSPECTION INTERVAL FOR THE D. C. COOK NUCLEAR PONER STATION UNIT NO. 2 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power.

3 ~ Completion of all valve testing is not a prerequisite to return to power. Any testing not completed during one cold shutdown should be performed during any subsequent cold shutdowns starting from the last test performed at the previous cold shutdown.

I

4. For planned cold shutdowns, where ample time is available and testing all the valves identified for the cold shutdown test frequency in the IST Program will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> commencement of testing is allowed.

G. The following criteria have been used in developing limiting values of full-stroke time for the power operated valves:

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs performed each refueling outage. The valves will be "fail-safe" tested during refueling outages. The valves cannot be stroke timed because they are thermostatic valves whose position is controlled by process fluid temperature. There is no external control available.

Page 19 of 70

DONALD C. COOK NUCLEAR PLA VALVE TEST PROGRAM RELIEF REQUEST NOTES Plow Diagram No: 2-5114A-27 Revision No: 2 Date: 8-31-87 NOTE 1: See <<Attachment-A<< for permissible seat leakage values.

Page 20 of 70

DONALD C. COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5124-20 Revision No: 2 Date: 8-31-87 NOTE 1: See "Attachment-A" for permissible seat leakage values.

NOTE-2: NS-357: This check valve is located on the return line of the post accident sampling system inside the containment. Since the line is open-ended inside the containment and the check valve is not equipped with the position indication, the valve will be full stroke exercised in the open position by performing a flow test quarterly and will be confirmed closed during refueling outages.

Page 21 of 70

e DONALD C. COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128-19 Revision No: 2 Date: 8-31-87 NOTE 1: NSO-021 -022 -023 & -024: These four one-inch solenoid operated isolation valves are installed (two in each leg in series) in the reactor head vent. These valves cannot be tested during power operation, hot standby, or hot shutdown because the valve design is such that testing of either valve can cause "burping" (momentary opening) of the second valve, resulting in the release of radioactive fluid and create an airborne situation in containment.

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

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

Page 22 of 70

DONALD C. COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5128A-34 Revision No: 2 Date: 8-31-87 NOTE 1: 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

>OA0H 0 N

8 q5

~ H SA Q8 8

~

A8

+

8 0 ~ 0 8

& g0

~ N Ql 0 8't5 t0 ld>>g& Nnl& A NOg SgO M Q 8 8 'tH g 0 ~

0 SW 5 WWNnI

~ rl A Stdgh tPWROHOQ 4N QW M CA OPcP~N ldQSMN ONA g>SAHg 4 0 AN W f4 5 't5 X tP Sld nI 0 Ql 't5 0 nI NN Hww NN N 4 td td% td-H 0 g ~ Q&

Q~XA$ r4 85 SAW NNtdgO&5 N 8-a~nI N 4A 0 ARK&0 N 8

~

O 'tI N 8 A nI N 8 N 0 NQAAP RAeg

~

'550 ~ . Q 0 0 0 A 't5 8 8 0 5 &I 'd 0 N5&SWtd&g g4td 8 egg ~ 4 gA 0 ON A Q 0 8 4'tI 8 ~0.84 Ql 54 Q N 8 .rl Ul

~ 8

~ AsM M leos Ql g ~ 0 N.R 54 f4%

I Ql 0

-8 g g4-rt Id NgNNO 8 0 f40&

f4Q 5'tfOA~Q 0& 4 5 8 td&

A ON 4 g 8 ~ A5 nI 8 k.R f4& 0 N f4 td~& I4$

nI-H rd 8 0 M H 'd 0 g f40440>

nI Q0 54 R.H N

g 8 '5 td

&SN'5 5 8 0 0'tI gN 8 54 tP 0 Ul I4 A t0 8 M 8 g g N 0 g OA &

4J 0.8.8 g td &

N'5 I4$ bigH 'tI I4A .rl 0

+ 0

~ P I4 0& f44 0 8 nI.R tp 0 g g

H 40 N H4 R nI 0 rl OQAWtd ~n$ +4 8 8 .00tde08

~ ~

0 f4 5 N I4 't5 8 4 't5 ~

gQOH ~nI 0 8 8 8 gA 4 4 8 WN SQQ~g tPI4&H 8 P-H 4 SAWQOI4 8 g 4& 8 Q M M SN N<H OSMIUM g4M 5 M'5 8 &N 0 0 OMS 4 & nI td w 0 Q 0

~00 0 Ql

~ M ealHMnlale 4A 5 8 0 ~ M 8 Sdgee Q g 0 nI SAS

'tf N A 8 N r I f45 H M 4 0 f44 I4< 0

.R~ SA8 A 8

.R <H 0 nl 84% 4A N .RN 8

~

WN gNP SW 55M>&

nI I4 N g W 5 Ql 8 pl N

A Idee 0 A 4 I.RWOSX N 0 & WA~ > g 8 td N g nI N~R g 0 td-rl-rl P&.rl.H 4%4-H4 Q g 0 0 0 tP I4W tP Ql g rl H<H 5 0A 8 ~ IPI 0

Vl OI

~ HeÃe td 4888 8 0 f4 4 't5 8 A 0 A td A.+55td '5 8 0 %OMAN 8 A A 0 tPQl > 8 H 'd 0 8 g > N 4l N 0 nI 4 0 0

~ W 4

M~ g 8 N AO ANN&8 >0+OnINS> Ql nI 8 MA SA 8 4 5O'A

~

ON A 4,H W

848 0 N 0 0 8 4 8 ow H 08>0 areal 8 0 A NNNN A Ql> 0 N 0 W QA 4 X 0 tP 8 A&040 08&&0 0 4 'tI + A.R 0 04&&

8 nI 't5&

nI 8 & td 8 8 8<H 0&A 4S-R.H Mw OgNS O ~NMI4 8 8 0 ~ 4 't5 A n5~

AAwse~o&P 8 nI 5

'dN 0 td 54 &0 0 0 <H A I Ul 08~ Sgq5 I NN

.rl N N g 0 NA & nI I4 4 8 g 0 HQ 0 0 SNI4 Ql g 0 Ol rd4N SA

.rl nI 4 ~ $ 5 Qg>8 F4 I4 8 A&84rd 8

~ g 8 ~ b 8 8 0W't5 % I W Q

~ rE Q A N NO A 0

SWN'R nI Ql OH% N4A gN > 8 N W 0~

N nI 0~

N N NW A 0 nIA NW g& W nlgnI SAM Ul 8 W 8 nl NgNN 5 AQ 8 N

~ RH884 N 4

~~

0 0540

-8 0 g R.R 0 'tH 0 0 A~ 4 A 0 g ep spA AeeM AenIEC Ql CV 44$ 8'tI4g

~

4genINOSAWAA OAA 8 A.rl > 0-8 n$ N 0 0 4 4 Old M nial W 8 A

SNOenI 8 Q

nI

~~

0 g)

I 0 nI

>H OVA08 8 nI I pl 0 co ~0 ~0 A ~ 8 N 0~

~ g Ql 8 nI C4 A

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

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

. SLT-1. SLT-2 R YES> NOTE 1 2"DCR-203 0 DA 1 A F/4 C 2 P EF-1 EF-1 P HO EF EF"5 NO EF-7 EF-7 P HO ETF-002 ETF-002 P NO SLT-1 SLT"2 R YES> NOTE 1 2-DCR-204 0 DA 0.75 A F/5 0 C 2 A EF-1 EF-1 P NO EF-5 EF-5 NO EF-7 EF-7 P - - HO ET-003 ET-003 P HO SLT-1 SLT-2 R YES> HOTE 1 2-DCR-205 0 GL 4 A E/7 0/C C 2 A EF-1 EF-1 HO EF-5 EF-5 HO EF-7 EF"7 P NO ET-005-- ET-005 == P- HO-SLT"1 SLT-2 R YES> NOTE 1

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 -

VALVE =-----

I VALVE-POSITION I AWE SECTION XX I I NUNBER REV TYPE SIZE ACT F.D. I PFIZER SAFETY I CD A/P CAT PRIN TEST TEST TEST RELIEF REQUEST(S)

-TYPE.COORDI OPER -=FUNCT- ICL

- --REQUIRED PERFORMED NiODE 2-SF-152 0 DA 2.5 N K/9 C 2 P A SLT-1 SLT-2 R YESp NOTE 1 2-SF--154 0=-GL 2.5=- =N K/9 C C 2 P= A--- SLT-1 SLT-2 R YES'OTE 1

0 o DONALD C. COOK NUCLEAR PLANT 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)

TYPE-COORD I=OPER-=--FUHCT = I CL = =. = = REQUIRED . PERFORMED MODE 2-CS-415-3 1 CK 2 SA K/6 0/C 0 A C CF-1 CF-1 P HO R=CG-413%~K 2. GA L/6 0/C. . 0 . E,--A .. 2 . CF CF-1 ... P BO 2-CS-026-S 1 CK 1 SA M/6 0/C 0 A C CF-1 CF-1 P NO 2-CS-027-S 1 CK 2 SA M/5 C 0- 3 A C CF1 CF-2 C YESP NOTE 1 2-QMO-420 1 GA 2 MO L/5 C 0 3 A B EF-1 EF-1 P HO EF-5 EF-5 HO ET-012 ET-012 P NO 2-QRV-421 1 GL 2 A M/6 0/C 0 3 A B ~ EF-1 EF-1 P HO EF-5 EF-5 NO

- EF-7 EF-7 P HO ET-006 ET-006 P HO 2-ERG-422-~GL- .2. -A.= 0/2-0.. -0 . --3 A0---EF=1.

EF-5

-- -EF-1 EF-5

. ==.=P=-- =-=HO HO EF-7 EF-7 HO ET-005 ET-005 HO

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)

-TYPE COORD I OPER -- -FUHCT -- ICL- -- REQUIRED - PERFORHED NODE 2-PA-342 2 CK 2 SA K/7 0/C C 2 A AC CF-1 CF-2 R YES> NOTE 1 SLT-1 SLT-2 R YES> NOTE 2 2"PCR-40 2 GA 2 A H/7 0/C C 2 A A EF-1 EF-1 P HO EF-5 EF-5 HO EF-7 EF-7 P HO ET-003 .ET=003 P NO-SLT-1 SLT"2 R YES> NOTE 2 2=XCR"100== 0 GL. =..1 ., A ..L/3 0. = C== ==- 2 ==A A EF-1 EF"5 EF"2 EF-5 C YES> NOTE 3 HO EF"7 EF-8 C NOp NOTE 3 ET-004 ET-OOI+ C NO SLT-1 SLT-2 R YES> NOTE 2 2-XCR-101 0 GL 1 A L/3 0 C 2 A A EF-1 EF-2 C YES> NOTE 3 EF-.5 EF-5 HO EF-7 EF-8 C HOp NOTE 3 ET-005 ET-005 C HO SLT-1 SLT-2 R YES NOTE 2 2-XCR-102 0 GL 1 A L/2 0 C 2 A EF-1 EF-2 C YES> HOTE 3 EF"5 EF-5 HO

. EF-7 EF.-8 C . HOp NOTE 3 ET-004 ET-004 C HO SLT-1 SLT-2 R YES'OTE 2 2-XCR-103 0 GL 1 A L/2 0 C 2 A A EF-1 EF-2 C YES'OTE 3 EF-5 EF-5 HO EF-7 EF-8 C NO> NOTE 3 ET-004 ET-004 C HO SLT-1 SLT-2 R YES> HOTE 2

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:

5115A-41= =

VAlVE I -VAlVE-.POSITION - I- ASHE-SECTZOtt-XZ I I t'UtSER REV TYPE SI2E ACT

-- TYPE F.D. I PONE R COORD I -OPER-SAFETY ICD A/P

-FUNCT=--lCL =- --

CAT PRIM TEST REQUIRED TEST PERFOR!tED TEST NODE RELIEF REQUEST(S) 2-QCR-919 0 DA 2 A D/7 0/C C 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 YESR NOTE 1 2=002&20 0 OA 2 A=O/7 0/C C 2 2- A EF"1 EF-5 EF-2 EF-5 P NO NO EF"7 EF-7 P NO ET-004 ET-004 P t<O SLT-1 SLT-2 R YESO NOTE 1

e A 14 BSOIS Z'ON 1<0 80 149 <'RAIN Tcsc<ADDR MOISTURE GENERAL NOTcs OMS~ILABSEPARATOR Ver% 'TO ATF105. t.EGKND RC, ~ Iei ici (ill)

IVSIDC CDF<IAINCAKVT(

CDN18 BLCPFL<D<MN FR<F4 G acrOR PCACC5 SOS DWG.

ATDR ryw 4 5' 12 IG Ej DRAIN FILOPI UNIT tr I ~4' AS )JOT FOR VALVE IN STRUM I N T>>

E.O R))D 2.54050. SALAPL<NC, PIP/. MATE<IIAL CD -) Vr.~02-3 .

R00R K(.705-0 2'.c 2'3)

AND 0/NKR SYMDDLS NO'r 1 SLOWDOWN EXP<A<NEO O'N TNIS DVCM,~ APD

'UF~AK 4 Sac'0<f8 <.51050 L/2 Sl)rjW6 CDR MARK NU<FA<K<k COOFS,

>/5 DEMINKRALIZKRS QRI/ 322 ~ +DRY))I fL.CLC)3 D. SEE Dr<65. 12.5K)3 4 <2 5<f14

<fo 5 R(X)P EL E300 Kl YKNT 10 AT<409. <0)S CONN. (tIP) ", ~I)0<2AM CC.

OCR)ro dvu a~).t ~4/9tjs DAVCCRY Rn 3O RKSU) FILL(TYP) BY WESTINGNOUSE 8 ef)trdK . OW CYC IIVASI< 5CR 8 rio SV145 SKK CFWG St)0,)C/8 QDDIOR-t > DWG I/ r85509 DD Scl C Z,5PSIG.

I/t 00<24IA 61 BY INGERSOLL RAND C. I<0 2+ Spar r t 3 SD<30 \

CFN)f EISW454 ~

ptcstv I I NOTE A eDK)) 4 %0 228W ~

SUFF<OENT RDOLI FROY<D:-0 4p~393 FD CD<DCI<stR 4 I ATDSX 30(, 302M<v SCS FOR DRV312 4 <O

.DFAD<r~).c/A A 8.3 GRAIL &LMPLES Dta f(ryp) Cccvcfr D 80 155 ~TC svrsw sccp ~ rFfcsd4 IVI SY~sccrt8 UNE 3

Clos DM4 ra DL D 56FT 56F'TS ALL EQU)F)4EIIT SC El PC CD<)CO fDR coNT DSX EX,-EPT AS l/OTED NSW393 36 RESI N BKD RESIN SKD C'TLL'1ALS Ant 55 c<AT: 35)xA FesfR ZOrt) C" DRV8< 1 ICLMFCMM \ I Mo.l

~ L 80<02-<

+OOOO I~Ra 41 P/CF4 NC<f<<AL 5TEAM jGKNKRAT0/L CROSS-T<K TO UNIT 0 I D

3

)

(OC-)DS)f) (OC X)SCI)

DDI Rr~v 8/D (DC'O)E) foc. Cca)t Z

~ MD Yoccd Lccds Tac

\t Pi<AC<a<4 TICt occrtujtrvr Ls<tl CFOcP<DRY kit CYICVD) lli SK<l'eart pot cc4sf t ytvr c Dsua doujcsrv CATDrrF J AF<s <MC<arMR< Tjije Pftff

)4 coiw tet tn lo vilplxrn BL'ONPDI/O due 0<A,XT 0 Srff

~ANK Nal SEE DWC 1.5ICSC SK J 5 80125 Ow Pw 00120 ~ CF \444<AY C,VPF)D YLAYD~

STL FOC< NI'INOGINsfjc<X<ac)

Da SCCA'0 ccu Ctscor<WLT (TK 9)) 2 ~80<ZSK <Nca l

Lav vp ccnDCctiDI<s 801st

~80 1St I 801'I / 14<4 SVFCDOL P<DKATrs (trP.4 Ckaces)

)'CROM NON KSSD<f)AL eo lts Dl FLOOR IL.CFI CF 004) 14

$ 01)

DN544W 3

80IZSM ffffSca St ~ )/j(IRAN 2 Ar CLC ICSSLCT DN rj4% oafccsva, viifjcac rat

.IMDIcarrs rae vaLvc l)D Fea.

I'Alr CICCL8 I 3 VICP<N IKE CDFFOL, (rt. )< FCVD IS SKRWC'K WATER. SKK du I sl 3 0( f ICCA )DIFPSEN<t)L

~ I ed<)ref DN Tcc. YFLLY% LIST, S~Z'LDW 80<29 6 CCWN a SD119 '80<2<

DIALS)I4A,M/9~ NSW542 Sf/Cf<CE Vj<ATCR SEE. PAR<

TREATMENT I 584A,MJ 9.N/9 D<r)44 E 80122

<)FMILLAD<CNAN8 5 To)0<SALL~It< I 80<23 I FRDV< NUCLCAA Gfs<r RCIOZ ILDNDDrjN 3'RK)IU 4 ZNSVC)55 SCLNIONVCC SISCLCA RNlIL/26/ITffcCAGCf I 5CK ON53 5tfIA8' I I OUTLET

'<YF) a)f LF 'Nsv/849 333 f)f/545' I SDV)4'M SD I <F2 FOR COLIT, rf VCU. FAR cafj/EÃ SDS ~

'.J S

r- DSX I+)4 DRAIN Sf 6 TAIS DAG. NCZ<

LLC/2 DSX C/Ca Dr)fj)LWAFFCR 5/K)K<IT TIK UN<r FP0)c DUDco<a~s I DO<fr

) L SKK DW&2.6<)54'G/7 A ate/zg J a. ffu KACN CCWt<DNCNT <Of Nr<F<

,S<2 CIWQ.

0

'LCIf1 jr L.GIZMO)

Ca)ION <as<Of R 1) a<aft<CISE <4)ICD t'. U<RRss 350 ~WCNIAMDCFAP. 'c SrARr UP 5/K<F/ GENERA/DR '

RD cs "4 '4 CDlt0 55<

t)0<<2 5'ILL FLANGE J 5 CF 2

4 80.148>

~ 3 ID SPRIT RESIN STORAGE TANK SLOV/fcr<N FLASK TANK 450 DCIIU I 4 SEE, KAVG.5138 A, KLS)lV) CuO D/AXE) STR SI(.-2)/

LTYM 45) 3 bD-I Cg /'- eciod CL 55 FCS"L BCA<IICG Dj<A)N TQ DASLPLATf, Spa~ t2 CAD<V4 DCVU<f

~CL 4 4 cfc SLSKFLATK DRAW LEGEND 4

~~

sff DWDFtjs<ae ci4 'O'D<46 Tj/K<ATLIE)AT OLOWOOWMF OCMFFCO T'll'CM"MTljFFC 6' LOWDOWN so ac ~a Ow IU)AP SEED ~ vt Nt AND FLICK FLUscap<D<c<c 1,'<0Y/CCVA)

TD TURB<NK ROOM SLRAD 5<25.C/5 StLHP . II~I f)K /DP)NG. FDR.'SITA/I

'RIMAPY WA'TKR L DVLY'Llacat Yai.yc

'fui)

Mfuef DCLAWHC. St ih DN CFS'PPCAR OYER/LOVE '1 (K OarMS<fce)f!7 2 FROM BLI)WDOyVN +=BY PASS LINE ALL PIPING.TCFBE GKKIR/)WOOTSY/f 004)OIKICALIKAT)0N . RESIN SLIIIC<NG P<PINGC SOPARACC YALVC iufut<faatKH DK)AIICRALIKKR03'fLET CtSR CDIJ: SCB CFO C<PM ITS TT I/OWD 0 SY5TE M AUX. PIPING U)r foj< ccJ<VAL0cc p&<CN SK'E IS M/5 Ttc<5 DWG G/8, ~ (TIP~) 'SttSCC/<o IuCR I NVuef S. R DWC t'ra" <af efas <CO<sf<CD

'VAC)18 vkracasNFD'aws,CDIL w ACC

.f C r uscjp Ai CRDIA IAA<N STEACA LEA'D Of STEAM FLOW RcCUIRKMKNTS

/F225~5/c<R PER STARi'-UD KC/ECTDR

%25 LSS//IR I'KR STEAM CIKT AIR Zj/KCTDR AUYISDC Eff/.Fl+

SP 4O stX

'ST)t T)~ c<D 5 PA qt<

AUl l)fA PX 51K ADXfst 5)si.l)-2 LESE<MD OOFMN Aa(

StKIjrf PCPIVCF

'DRAMINO appcaas as: Nsw0)w AH)fi<aufur CIODC VAIVC uaaK

~ 2 N)44YKD

~

ps4to sreAM cKNecarots Nf 1 4 3 etff/)/8 A<<XI164 AW'155 Nvs NDC sjcuwN Dy cRAMFHc(sec

~ 1< SCC DN' S<DSDCCitS YALYC. <DCN'fir<cat<OP USTI CCRIC<D er ADD<Wc ro 2 sr <NRPCC<<DV lb CL 1 888 g."~~:/-/C(;W~')OSFS<

C'DRIP j<//X584 )tiff ~SIC~ SCU07 3 8 CROPFI AUX VIFTCAPt N CA DC<I HSCRltutur NltuefR CDR SIN AC PFPVLSCW rl stflf ItS r\I

)ODKP 4)SORFs< mr) 6KE DWG CDFL <xxtk C pjrRILDCY<

LCak OFF IDD MO 11DDRPM 8 5<26, I/9 Vffc<NNTIC ID MINOR 8'ED/AUST T) Ai)AC6 JCLVX < OD<) AUX< ILUlc< ll hf (S<DPB TD AVOID V<ATCR, TD ROCF IIXLffsff Oc t ) if.ff /4/P 0 <

~

Nerf.

(CLT SDT)

A/F

~

POCKETS IQ Cl<PLUST S<t DM6 sra CR<$

~ Ut I <GC /fit1158 2 XII5 A FAUX I IS OFN

/YPP JCAC 4 too cr 5 STN I/7 STNASC 5<N.17-4 Gtuuf I CDR RCY<)con ccscfuptccf Tc 4<S

~ RDX 511 scf 4)$ SPC St)C Sf<RLRatK RLV<S<DN RCCDRD fot)OCL srx AUX585 430 AUX577 AUX.S)3

~

8 ASD 4R 1<OS DRAPANc TD P<ARP 3'lfNCO tf)5 SCCDO SIN) C f)CCXSR ALO f

f

    r 4 (TIPKAL ~ RACCS) %4 4 +4 WMP pea ppaco w rc ue'Au (I SIAFRE) CCFCPC FOPO Mpjc Ce . Cw p CWFOC PW ~ oppao CMW p ~ w oo jp FppMMRW oo C<AS 39 Z tvr. (8 p<ACKs') P MP Mt ~~4 CWWL OPCC /f)X'f/t OO 4 Vr A<it L OOMPP ie rggar '9 M I ASC . AUK IASC. 145 'f" Xt)X jt/)<C. <CefL>> ~ w ppju <<PMO w ac pa uc fweE TO C FCCOW ACF rjpcr CF \c rcp I/sfvp(e p<AcE5) r FOR FOR 5 ~ 'r ci <2/R 4-sp)ctswr t AlÃSec JCKXZIZ'<AC tc r Aax-s)4 plapc ow lo u poo ocprc CONDENSER CONDENSER apse'ss'r INDIANA4 MICNICAN <1ACC<VC Cta <~os~) C 8 S/4'Leave DONALD C. COOK SLA< OPACV I'CILA)ID LEAXC)CT TO START UP ~ N /FO<t Ur 58) A<9(585 AUX575 << UCLKAR PLANf . 5Y ld" 8'UX579 EdK,CTDRS CONDEF/SKIA A ld SCAT DAAIN t/4 CA)I<KSDRA)N /(SlfHL/)<Oft I/<PSEAM RISK) DRA/N ALII FLOW 0/AGRA'M set Wr O.DILa'4 541'u'ya 'KE //IA)N. STEAA( )jc Sayf RNDR. 'VALYR STR<f'EAK DCF SFKtCN'B-g Stk <MJA) SiesjRCVI Avc 543 4 FALSI STAGE 0PIE- 125O4 (FDCR C'.DNDEA<SCR. Ib 3<R <NLK? ri<OFM f25=I< F/SP COO<DC NSCCC'7 .. ~ Id'iKID~'9 0</ILK T OCEEV25 Z SHEET UNIT ¹2 3OF3 EJ ECT OR (1YR CDNDZN5~56E (FDR Coa/DENSECZ'A) (FDIC F P. T. Cf)NDENSK/<5) 9 ~ 4 PIP<NC AT AUX FK'KD PUMP TURBINE. EL.C Dg'w 0 P<MACN5) CY<5 'WDSKFtit EL,CD)'VO DR.~=5//)SB-. SEISMIC CLASS I 42 (4) STEAM 1)ET AIR KUE.CTORS ~ Pu ~ (3)START UP 122 <) ~T Ec A<UL<22 M SF ETCN 'N 8 FCR< af<RAF<60JEN I'F CDCLING WATEfl FOR TUR/af<C 0<f4 COOLER ECTDRS'0/V) (C<r<E-<Zcn) E. IRAN) AU)LIZZ5 DRAI<f PIPING Ar St'EAM 4)KT h<R KLIKCTORS 4 START Ufs KI/KCTORS P+ rva %'.gvPjfWJLILRF ~A<LAL g+IJY,x. NOTKI FOR ORIKN'fATIDNDF KC)UIPMKNt sKK K'KY PLAN ON DWCO.Z 5<09A 8/1 AF<D 60JKRLKXL S<C.VE SEE SIC D 2 DVVG. 2- S<0/FA A D I D (CP46.1245) C 5~M~.Z'Dcf 72//K: FSCTTXKL~OERF AT'S~ACS f///G 1 51094 AuvccAR epocDMAC a<clice rocai Naccx cojr LLY rove Z I K I L I ~ n ~ I CD Mal ULTÃiIt III'KHI:ILE IVIIII'8 Also Available Oa Aperture Card 4 QVl0130278 Ql 'V I 4 t I V I ~ ( 1 +p I . C i'."-~ A I 8 I C I Es ' C F c N J I I I I K ~ I I M N OI<<0)v-2 SV(8'4 SYS'4 AIM05pw(ac L v>>N '<<c C e-l Le) t~e ~ C VENTS To ATMOSPIKRE SVZA 4 sva. ~ C'WAM 10 ($ )vkv(L t)- CAPP(0 tA$ 4t1.4 Msl(C 3 CAPPED Msatl 3 olo lo e ~SLTA.S vENTS TO ATMCSPHKPE~ Sv(8'3g SY>>3.3 6 7 )~rSYZOS s 5 0') ( o'30 ~ SV3.3 C' E I Is)lNLV($ 5tt VENTS ATMSSHERE G=N-RAI. N)TES LEGE)w) F(((tlat ER PEA Ta\ <00(A>>IT SCE CHART ~<<Z v Msl(L 4 t PI AUIL tftt>>5 A tent,M/1 LI 30 ZLDJ>>DOWN JH A7 t VX st'0 0 11$ tKLL I ~ !It URV ZCI~ EO 5(>>P)4( (1 )(4 4$ 1 )15) Z'L'I 1 5+1 ~ Ol FJL .0 M LCRIAZ31 lg FOR VALVE PISTRUM(NKSJJ>>ftt>>6 CLZ ""K 31 0 D.I.Z$ ROM. V>>ALL WALE gv( MRV Z3Z tcf MAI(>>4k A>>Ks 0(HER 5YLL4d.s ()O QV <<Z( NOT ( jPLAPKO ON TH5 OWG A>>PJ FOR MAAR NIP<<tech foots SIC 1 tr. Foh(33> VENT To Cg ItlaCS(IS ATMOSPHERE Msvsl ~ M jlos ' a>>sos 3 )I< ItNT To OHG R SOSJOa ~1 SEEK(I Ivsa I'OR Ca(T OC fdh (0>>IT OC LGRW 3 ATMOSNCRC Cia I>>PI ( ~ 1 5L'I'4 l04 Nlsl $ ff t SHIA,S/l OV Ya Ms'I 5(( owG Z 5>>4IA 8/I (PK(R ll>> WAc(4 ROJEF W,(<<RH I SL'3 3 IS((v la H J H O'H SLthtvt $ (C IO(( S(tH(VZ >>PI ~ t<<1 FOR I I SLPI)WZ 5(t No(C C PSS 41 4 I I as MRR Sihtlcll Siwp(YZ C roR ~ MRA R 14 I est H FOR MAP( h ap(Nvt 17 CJ 8;, STEAM 5 I SPA L ~ PA ) I(. HSCSI.S 5(E Owa H>> CC. PL ZL g. t sestls W V I I>>0 I Sit>>OW, I tao 8 H tl I3 00 I 8(fuah e I --T-- 'MfCHIC I CYCHOVC -I FOR MAD( STEAM $ 151(M SCf. DHCL aJ \ SLP(31sT L t SOS.L/I ~ ~ I OLD+IT HSHOC3 tLOOJY CPN $ pCFN.A ALL EOUPMENY SC. 1 fxfttf AS NO I LO. so'aaxl'~7 STEAM 6(NKRA108 STDP YALYE (5C'1) IOIIS I )I .14 ~a c H')TTAU 5'TEAM 6(KRATOA 59iXJC M>>IV 140 A R a I OR STOP VKV((SC I) foR cooE ELAs5 2 t(STRLS>>ENYI NQ4 SPARE roti CACH 0TH(R hlas MRY. 30f SAMPLE CaPKEnwS TK Gl NQ3 3 L($ 1( O)JE.3.4 IIT H0 CI HI IS>> ~I OME-3 3 4 St J H 151 t7 SCCPOARY ERT Eacs Yo AMS YKLLO(s TK Fast lOOT YALVL V ~CLZ j NOTE rAo>>J I((0>>AX+(4 Gt tl PAOIARTY To Pff ~ vt t4 os a 5>>c Msi)$ 3 C'TECTOR 5TST(M 5(f ~ <<C tsaa JUC Sff I>>of PHYSKALLT A(TJUKaroR I (wo Z $ OC,K/f DETAL 5fC OWt. 2-$ faaf 1 ION RK f((D lotoIos.sa rROM PCEDWATEA 5vSTEM Diva t SYJC,(/4 8(3 HOVI I SLT I SOW ~ .t PIPJP 5 ISTLM c<<c tsol,va SKC FPOM AYLfEED PIPICP $ 15TEM (FIZS F----~ - +gael Pftf0 Zg IJ>>JV t SEC DHa 1 seCat C/5 at(aa(7 SA'6.8.'Hvo SEE DWat SYJCAJO/4 f((0 5(f I "-I"I a) ~ TO 1 r avAUL PIAaO TLRSAC owa t sesS Atr(ssoool Is/<<R 5R. VENTS F pav4 CHKCL SIST(M SEE fCfD To ZLDHDOHN $ 15TEM5CE Z.sosal>>t I I I ILHHJ I a ~ HI F>>DEIL I I I I $ VA ~c SKacztl EIZ 1(1>> M5100'Z AT I(SO tsi.(OOO LSS/RR AT KS tsl) ~RAT v ALII TO ATMOSPI>>KRE OWPA I rt JKT(R(OOLACTI (Rat( 5151(M Stl ~vsf alo~woE SVZS'1 DW5, Z.SR() J,f/5 I I I  ! SYS IKM SEE ../ DHra Z $ 1(8 I K 5 FROM CH(atf((0 SENTS Ta ATMOSPHERE l (SLY'Uteif VI(<<K IAA>>5(05 I t! I Svto Z~ SVZA.Z ($)VKY($ 5tK Atw(AR OV 1>>$ (Raw>>K $ (K Z $ (ratalt vaLYK I SYSTEM SEE CE>>lf e e t t Se(IJ/3 CHAILRPPA/3 KATE<>ERE+ Z LGI fal ahfuRKVT (CSCN IVERI MALKIIS, TAC MAIS(PS VSOCIEl FOR CRJ>>WVO USE AS fOLLOwS: t Lia Na vsw HOS-w SV(AJ~ e M54(L.( MS ~ 15 ~a CAP(to DVYS.Z.SDSS(A Altf ats 4 5 VS<<OS<< ra Fa MAV ZIZ C JH 1$ 1 43>> (Sl VALVES SCC hP M/1 CM>>lt Mills I~ t 3t 00. Lts ADILWALL MSC(T 1 (0 c St>>SYRCACNT 8001 HS5 NOT 5>>SAN CN vkvt NARC (Wa<<IKIS(E \RLVC U(VlfeaTON LG(l CL SZ aa Lt5'>>>>OIL!IALL LVRvas 8>> Ja>>IG 10 ~ V 5 S>>(SAZt( VGTRUICNT ICMXRI MMO Z>>0 Ml 'I a)$ 05 2 IOR($ ) Ci YEW SJKC CPIASCI VI l(NT '10 FOR CONE Of MSPSC Z L FOR CONT. OC F OR DaAKE IJPILLc I aw (Its IR(AIo IJtl faa($ ) AIMSSISCIC MS( SEE.DHP<< MSX 5(C Y(NT To VZIOOWus IR ta ZIZ SLKIKKR Z SH(AJ8/t Z $ >>4>>A>>SR tot A1NPSPH(AK 4 SL 34 H J.H OSI I 8(rRIYZ g~ I SLPI(IVZ SL'3 t 8 H Sf/ fORNSTK 8LPYLVZ I ,'awztv) STYJJC CCV(RARH slop vaa<<c IM Ll C taaa I 'SEC tel E >>cw 110 RIDRAYLIC K CLSCW SLPROVZ I 1(LPKO>>) K'(OIHM 5>>RJSS (R WIIR ~ II ~ (IYZlvaLvC5) col APL K ~ ltV'Ics I ltA t>>T (ACAL ~ Isa<<I (1ft 4 VALYCS) <<l<<II<< MINK J Yl 4 5(CA<<I PI510N t<<ls I F.C <>CMZ S4IS 1'RIV( ~ LLPRM I H 44 VL(WWH (IIP 4 YALY($) Loot>>C(L) Wttt Nrftvl I I (LPK(vl H54$ <<Z NOTES: (lit 4 VALV(L) HCLK C(N $ Tot >>IATDR vkvC SHELL DE SGN 1 H( VMT ta(f Il 0(LKVAICIN foR (KR Ul PLIK6(0 DRAPI (IC'1) ataw(O CtN t tttssvaf I >>CPN.3 ~ SYOI 1 COMPOIENT UCNYIPKATKNIal (1 YPKAL lots ts(6 C IS't:(04.ESS OTHKRVHSC NO(Ca (Tt456,3) I 4 YALY(5)g FOll MAN I.. 7raa(l NOIR IVA(L ~SA SPARK (DR CACR OTRKR I tI tl \ t>>ll C~RA ~TLIE I al 3000(lhlk WKL ( ZJ-Ff 5 'I (AN (TT I(M NQ I L'H '7 Dalf l-SEE Dv<<L OMF:3 I I 11 Itl NO 2 t SIOS,JK Ms>>3$ I ~ lo I(0 II OM"--3 2 J.H J. fER P(vtseV OCSOIPIOV Sff J 3>> RI r~ $ (PARATK R(vee R(Cae Pl>> T>>st oat<<to R). JJN) TI ~)SZ I 10>>SOS MS(3E I CLZ I I i t(RFORAT(0 'I! I I ST(R(W( r-- I ttefoRAI(0 ttf Hl. ta I s'LTUOVl. 5 ApEII), UIIIE f tw w w A At w<<w v w avI<<oI ~ IIICIACtttl~ He<<a COV W A a<<W W>>W<<>>WJWA>>>>>>>>Wc>><< atcwa>> <<<<W <<<<<<V>> t<< %<<<<<<W W>>t Cwt IcW>> V tv>> ~ a<< t<<t>><<At W tl ~ tlt<<CI Clat Aa ~ CS(st I Rl IK 1 IW F fROM Jotft(D ~svs (va c.scaRN = CARD ctW>>>>W>>AA <<AW <<IIWI, ~ '<<W lt >>>>ttW<< W <<<>6. 2 SIOSI vt>>6 I >>5 ~ I( O >>8 vva Ii'DEIL( 8 Jva tt I E J L 1 SIXAJE/5 CM ~t~ PROM F(KOWATER +vs(EM 5(f /7 INDIANA~ tt>>CHIOJN LLCOYR>>0 CCL DOKALD C. COOK III IH( Ital a ( ~ I SHELL) V w>> OSWIPJOW )CRAZI< I 7 I )at>> NUCLEAR PLANT I FZACTOR CO(LANT 5G1(N 5CE I I I I R(ACT(R COOL>>>>(( I I AlSO AVaBable OET. ~ R>>00vav VIORCM ~ I SYSTEM SEE O'a I OWC t'SI(8,0/7 fAOM CHEM Ap&iCI.'6 CBx'8. FLOW O(AGRAM J I 0<<Z FEED 5YSTCM ) SYSTCM SCC OWG. t.s>>04,f/4 J Ol Pa Ps IIP I I I I Z'H ES OUTSOE R(ACTOR CONTAPIMEN1 S(C DWY, t.5IOC A/3 STEAM GEFEI(ATOR A(ETY VALVE CATA STEAM GENERATE(G UIIT NQ 2 SYSTEM ~ VKVC 5(T tAt55 SIZE Err(LSS/HL) Dv>>5 )l l4 Q>> L TO SLOWDOWN STSTEM 5(E ttl SWJA CC'Catcoaa SVIA MARV NL It 3 ~ P SIC ~ KKS CLIO t(R YJ 8S ISO LOCAIKN DKMR 2 (050.2 14'7 DWG. Z'5IOSS, CJS SV>>a. Lt I ~ cae 8514 T>>$ L>>l LA SA LC(ahal PLAN SVZA 1 141 Ul LAST IAoal Aill.f(ED PUMP~ To Sl.owoawV SV(S II Lal LIT 5 IO I5 cle s>>S SY$ 1CM $ (C Owva Kfhavl CH(CL CECO 8$ CXI I>>SLI IPL 1 $ >>ala,a>>4 S'YSTKM SEE Dvtva SYSTEM SCC OHYA t SV>>saCI( 5vl I '3 41 ~ '1 Clto es 2'I l << P Z SOC,A/1 s satits roa lafk 5 I It Iso IS$ /IH (<<0 Ix) Cat>>I LEAD . >>5~')9(:/ Zovkats POR TOTAL (IGES00(85/ICL(esf)t(AJI (EPOS ~ I AIIa<<CAR a(CT PIE IOVIR HRYICC (CHIP D I I 5 I c I I J I K I I 1 I l ~ 9" ~ 4 f 4 p H CS A Vtt FLEX. HVSC. Ot 170(ttt) ExtSI>t>O totrKCCT>0>) GENERAL lloTGS j t00>5 CC >3> ) \HC >txkttvrrtE th0020) LEGEND CF>50 I f FEEOWATER / I I I .t AUX. PIP>HEI I'VENT CHEM. FEED: I VENT rw ZZZ. SWZSO PIPING cw tt9~ rwtto I'w'tZS] 4 J CW> I 0 fOR VA'LYE, 1HSTRU>4CNTy I 54.'I'>PUNG PIPE VATCRIALr 18 ANP OTI>ER 5'A>)tctLS NEST Zpj 18 20j( EXPLAINSP ON THIS OWC ANO FOR >httRK NUMbtR (I tttC11 rt rw>09 445 ~>W>05 45 CODESt SE(t DKAUtl(5E>3(>241(rh I 2$ 3'CH(IC tt IHt Cps 6 55 2 >8'~ cl(INDCC ccr'>L Id ~5 CHEM.CLEAN>NG CONN. SQZE:. ALL E(ZU>PICENT SE)S)C>C C 2 -t P>pax)70 86 GLA55EP t ~ 24h P3 EXCEPT AS 'C.ASS L1CSALSSNOIEP g l L FPX NOTED /'1-10 r~ Ct>4>H F 155 I 10 Ctt(M>CAL FT 'l5 Qzt 0UANTIT)ES PER G.E. CO. rEED FVMI 5 SEE 257 SCCICH 6 1 HCTE 0 Atd HEATER HEAT.ER HEAT BALANCE 37>H813( VWO REVIS'ED 3.2.5.4 d CHEMKAI ADD>twc L>HC f>0M CCEDWACCtt SYSIC>t (/EGA) (REKI 5) 8 8.B.CO. NEAT F Px HI>) ID CHEMtCI>. CECD tVMt5 DATED It-11 Cd 26'tx BALANCE'10240/0 750 AT MAX. REACTOR POWSR ftx fPA l 3 25>>> tf ZSS 251 '257 ELEV 43350 , H/5 G/5 CHEIIKILCCEANtKIC3>HECT>CN5 PZOVCOED FDE CONDENSATE VS> FTR, FEEPf/ATE>Z SYSTEM ELEC>ICAL p20 2 ELEC S. Ftl CPS SCE DtvS. C SK/>S ffhxtSC.CKtrCC 'lt0 2>0 FPI Ct 12 H>A>(AS ttt YCH>S 04Kr>L Sr'0 50 AP T I rtx 240 I t II 240 5V-I) I F'f 'TO 5TEAVI GENE)CATC)R NC I 5'ET 0544 2.5>OSP,)5/9~ 14 240 24> trCHS>C CLEANISS Cc>K>t 54F HV>t W 0'54DINr I'5 SET AT 450 PSI ~ea ~ g 14 2 9>K)tL EST Scx I)) /0>5CIVUCGE TO FLOOR DRAIN t0'c ccOE ELAss'2 t>rtxv 90'APART I f ZOO CPttt>CCY>DHS,TNC ISI 00VHDIVt ~ r STEAM CENERATOR CXYEN DS TO AND >HCLVDCS Ilt C I FILL LINE ~ tt>ST ROOT VALVE J T>9 STEAVS <<0 N'ERCAO N w 4, SEC ! ACa / tt rrc >Fc. Ht i lrC
    2. 5105'Ot C/5 4 I >0 t4 I I~t 240 V(HI I VENT C 253 2> I d.
    (4/ 20~ ~hYDRO TEST p F WEED Vh .WC gPSS 2 Dhh:Es src I'sl >50>404thr / hTHTS PHD rw\Is~ CONN 4 $ / 7.337000 CBVNR r FROM'EED PUMP HW 44>CHDS 70 pt>0 0KIVD(5 IVC f titxf HVXIIP4IC C>PS(9 VILVL r r F.Cq CWI >44 CRY 740 ~ w -J. 2'DRI>N (to FIR Ct f>40 252 Dtc CMI ttLtf>x CCStCSNDH 104 Ctpt w FW>OCR cwtrkxt ID>H trxp>xr Hs.a E 25> Isttss 0>rlxthst tctcp N'>Rh251 FRV 2>O CWI>4v> Ff FIVID41V t4 FMO tot m CDX >W>154 CtH 25 rw>05K I'ID F(00'R H CW > IIW tw>OSW CWSS9C tWHD r WI40tt f rwloDw DRAIN L ttt<<24 f rtKS204 CWI 4l E. 4000GPN EVER/,LEAKED)tf l0 CDD 70> (C05207 W) 'DRA>tt HCDRATNE C I I'VENT To AIH>vd. CWI>7 I 2(f I fvprL rtth>t>>l Lrw>>sv 20 SCE00555IOC,A,SK/G 3 tsf w, C.U, ~twt>SSW rtr IO COND 8 (CONF. A'FRD>4 V>EST PULIP) SEE SIC>02 HIHV Vt RACED YALYE IVENC>f>CAC>OH ttVHXCRS r FWI> C Attw>DN! ADDCIIO>4 'IC. h-hdCE I DW. 6000LY I 20 '207 7.$ 37.000 LSSIRKL. C tfT E j LDNLY'VH>CVC VALVC HVMFE>tS m>tf 0 th/5 4 tox IfeYENT t tvv Attcxh VN THIS Dxxw>HC. SEE r px ro 24 t SCtARAIC VALVE >0(HI>CKAI>VN 247 f.0 LIST FOR EOV>VALE/>I DES>CN CVSCWg I'P '~ EIEV. CI2'-Dg 251 Zog 424. CZDGtC >C. r ~ .~tt (VCR) HVHpfRS. NGG-202 IS 1 t, IAC HVMSERS VGO>rl(0 COR HCCIWLIRV ZS DRxwttC VSE AS DLUhrj; f TAC Nt'.hsw.v>09 w Tx 204 TCS STEAM TO STEAK GENERATCtR Nt t trCD GENERATDR Nx 3, SEE PICG HEATE,R HEATER CPX I APPEARS AS; HSW>VSW CA>10>>C NR.2,M.G PICG '55>05P 54$ >3 4 'PA 202'vr to> 0> At>SI>>VMEHI RVVY VALVE NARK fDtt-0 'N'i cHCZI rtl FP1.2Vr>W/t HVI St>CWH otl ~ f tx h-Cr> ~ 5 2-SICKSP FI/>5 ~t (HE 54 rtx (Nf, 58) rwtcvw 4,4 NCS DRIWt>CCSEC FIX X Co) 202sr C 140 VAI.VC IDE>lttr>CA'I>ON UST) I I Ct>59 CCI>ZE Cf>4>WQ rrlttw 5'HEM. CCEXNIHC 254 IK 54 255 I ~ rl DCR>YED DY.ADD>HC TO X>SIRVMENI >h>MDER: CONNECTION fCR SINGLE pwhISEVI Ct:>40 CKtr4 Vg ~ ~ I tith FVR DolXE PxhISCVKCPSIREXM> Cr)4 I 14 24 ~20 4 tv >>44 fwtxs- rwttr47 tt tw>DO I CI I ~ FTx I'cvtts 07$ $ fPx-ZC>tw ZCI CSSI FOKC HOSE 0 22> I'xxtwt tEED rxEDWK>YER 4'attr CEEDWATER ELEV. 409to Cch>t(5. To CHC>h.tECD 'IANK~crt>52 ACC 201 C H CM. TANK >Cfxtxx'I t>H CONK Pt.tt, tt.>W 2 tj-$ 7 34 >IKDK(AT>NE 4 ~ 0 FIX AN>SON) A (Ik KI44) ttkhf4t) t fhEt253 -(2 TD FLOOR DRAD( ~ (2) fEED PU>IPS r PR>>>45. 200 GAL. too GR Z5> H.TS($ GPM 2>50 FT TOH toit REY>S>ON DESUCPIXXI SCE CDA.ZOZ W ftx KXFAPIRI S.ZZO RPM 9343 HP SEFKV>IIE REV>S >DN. RECORD tE' DW Uxt 210 FPI 210 r)4 FPI 230 FP 730 259 4'W>07.5tA CMD>254 + fWIO7.5D 2 Tb L>ISC. DRNN C2656 . C25 CDh crc .cFc.zoZ hfdf Z FROM HEATER N24. SEE EN/042.510')AJ/vr.. ~ )DR 'IIRS DRIWKNC r r tw rtvtrt r rr trtvlttr Vknav n>DN CtatS fVtt CCHIL or CH tth Cnk2 CC >ICE It Cn>CW >NW 8 ,FWIOG>> DA 4 ID FLCOR DRAIN > SE-b9 TAHE TENT STSEE SEE'>0>CI 2-5>038.' '20 I 70 I 255 G tttcTvtc ttvtr Hrrtl 40vt, ~ 4 tr>> ~ ~ tt r Ht tt H owned ~~~rt DW450 >VVENT trv tr 400>ITVE tJHCS NIDFL r 4S VERT, rtvvh Hptvr~ttatrvr,vt rrrt 04 Sf, 1 D .6NDWH IM dt>CYCH rct02 n ffc To M>5C.P>CAIN TA.NK CYP CIX vttet vt<<rratrwtratrw << t 'C.t Y WS 'lo 0>sett. 30'~ '4 .VENT STAOCSEE OVKG 224 ~ to CC >Vt40SPAK ~ tP $ 'Zt Ct f XE 'HD>E~ Ct 1>SW dtc NOIC ~ IC ffc ICL ttt ttt ( 2~ 251098;SK 4 5 CTX.ZS9 W cts 24. 'N'D>CAIN - ~ ~ tv rv rv 4 tt H t tt rvv rvrwI i >>SE - 220 27 A/0 QND HN. htw r)~~- Kv Cf >>SW 29 CHEMICAL CLE'ANHCG CONN. C 940H ttCHAHA 0 MtCH>GAH IIXC>R>C 00 p'etr CCIZCC rCCNSw Lt FX 4 4>C)-- SEE)KrtE AtCV3 CPK>CL.2.5117A. C 940 5 DONALD C. COPE FRV-Z20 ~<at> E Ct>ICWI l4' CF X.ZDthr/ ROC(EAR FIANT 6>> IKLEEJ)JBL5L4 tt Crr. I (-Krt5 l ft4tv I tt rxts tpl 250 (KF 0 (.'ZC. ~ R>DCHIt> '>0>>444 >HYLCRALIICL>tt W'>CH YALY SET Q I>FOCS> Pt4tC ~ I ( I I 1 Ill 0 I1 1 F.C tfVP 102 FW>14 2 CRV Ac@ j 14'E )4 CW I I '4 ELEV. 5'l 5 Sttptttotftrt>CCD ctx ,. Fl.OW O(AGEAQ-Cf VSCS I I Cn>sw 4 FW>42 1, "FE E DWATEE> 4. "-'. 4'gJ ~ 1 >11 H 224 Ct'00E cf>t pttt I 1 tt ktl API XPI KPI I I -, Yg I II I I FW>l'I 2 fPX fW I IV 3 lAIlII VH>IIKXIC- ~ 0 Stxtt >CW 2 I ~ Z3 ZZ If>a II II 5>57'3 Z04 ZCI Et Lr t'0 t>000 V LC>XVGO L05/itt+ c - 2-5')0()-34 I (II ) ) I 70 SIE A>4 rt 3 I ~ I f Px 22 04HH r>x t) FP 4,9504>00 >.05/44 FROM HEATER DRAIN 14C ptv 2 St050 0th wf - -j -- 4. J I I rwHS 2 rcrctttctL 4001>It t>HC TO fwt>5 S -A;tso AvaBEEble 0> Put>PS. SEE OW4 ~ 25>OT 3/9 EL5974f cwt44th rc>0 rttrtt I 04 me Card ~ Ctrtt, Itt Sh &'I Crts Ottth, Itt>XKIII>LCC>xk IVW>X5>H>KCC 40>W. ~ETCH >5& t 4404>lt>II 'D> Ipxx FEEDKNATER C>EAICALFBD SYPH A 0 I C 0 I E F I 0 I H I J l I I. 14 1 N . ~ I -. C3 .I'..~, ~v 3 l 1 ll' II 4 Ll 'I/90IS-Z wm C ( GI6 Otttp>C 0 cu LN H II ( Tttc t>>tv FAcr 5 Dec>aviv>OM PDK fice ccteeevcvv >Qcvvtetcc Te)ti VUVSSR 1$ 't'CCL\56 OTALR>ASX COULD N ~ GENERAL NOT=S 0 - AVX.FtrJIATE2 eteCKGC MCY LCAtc r $ >QG L/6 51st w -COOJNC lKATER I fw l411 fw 145 rpx 2)zw t'PX 2 Qlv /PX rcl -Al/X PIPING ~ lcc ta /vs ttl 269 /$ 140 K ,QBGH 'rst.>04W ~ e TFST LINE 241 rt>210 tst c.! rD SV)4+2' y".t Scf Tye' .2- 3 , Zr IAVI>KF.K rtP VfNT )HIS PKG HADE VICIOUE J'4 219 fOR UNILZ FRON DWC rrs 75 254 VA!.VfTO Hctf' Piu ec0 ~ ( GP/f2 VCR TC FttC PU14PW 2 It SIOGA REV,25. ') ~ STOP TO 1 CRQJ TURDINE laccoDLCA fSf f / RAVEL JDW 10 fir>I <<fev 259.. 74 Lsk CON M. 0 2/Et/ CL/U/i=" D'e/M>> 0:5 Jtcefc Be/AK FL>(ffr) I Res IS 7$ PSIG fLDW (1414.) FRV ZCOW 4 /R)M COVQ. rJ. -WP>K 4 ScltPIK HAIPJI fOR VALVf..INSTRUNfNT,SAIIP FRV.)el. 800)TER Puctp I. FtcsftNG REAL sf IJNG. PIPE MATERUILC OTHER VZHTHIS KV/e. Tttes U fRV.2685/ I' DOCH SKK CWC i ---n-2-----~- SYMBOIS NQT CXPLAINED ON ffs ffs OCL CCOC Oc FDX ~ r>M 5 THIS Pt/G F FOR NARK N'JNSER '. 2 5 1st. 4/4 TIZO~9'/ERFLQW 251 t 14 165 243 Li IJ V U CODES Sf f. DWG lt QKts(tt SKX( rpc FPX 264W SCAL 1 is rp>>tww'SI'ICS FSI corp I/St'lotrf /II5 Q-LWE (DENT(FICAT)OLl ~ SI.IQGvr P 266 i ( CIXNDEHSATC STORALK TANIC 5Ytt DOLS FOR CCMT. SEE E/9 $ 1'4 014 31:sirkt H THIS CWL RN i>> KNO FRO>4 MA>M rKKO NOTE A* OETA(L B.2 Sr)ION. Sf E ~ )/4 r r 3 2 vfttf TQ ATL10 .ITVP) PUMP 5CIL WATCR PU'its. SKK L/5 ~ VALVES ALSO SHOWN (AVQ RUMSDKRCD) OM DWG 5IO NQT TO BC QUPLtvtfCD. AND +RC THIS DWG. tLKETCH 0.2 I Bl NORMALLY CLOSGD; C~>AIL Of TURS>NG DRIVRN Attic. PESO C>I)MID ~NQT TuREDNE COCLUJG WAYSR fsl lcr f Fst 103( 5'ts) 6 FRO14 Lltsc. DaUN TAIIK Fsi. IC r)t iosw VSCD. FOR HEATING SYSTEM OPERATION DURRIGe CotISTRUCT-1st I Is; FTC.255W 2 r)C FTC'264W N AK4 f/if ~ 4 .21 C-261 I lt IOM AND ON OCCA51QNS 1KHCN BOTH UN175 ARE IN OPERATION 151 C's FNC ell CD it VCAT~ TKACwC, I CLS 5t ('Qf t fw.tsr I5 I fw.t)t.t TQ ~JN SKSKRATQR h71 secAK FI.Gs t s 'C'OVIPN CMT sf tSN IC CLASS:ttCA Sfi Cr/5 ~ 57SD t' ttPTr io TIO'M AS Ie)tiD/ FW 1st 45 r, ) FW4324 34 '41 TQ sicvL>4 Q'4QJ,GR N>4 ~OVCIVOVS 4 TANK 0 tee r I. FOR OQQE Ctt455 2(5 Wfttu NKNT CONNECTLQtcs VTHC tSI 5>r DV/5 2 SIOSP.C/e> ~ e OC" I C 265 I/rVfMT I'k(RCKNCY SOUNDARY. CXTEND5 To ANQ " '-' e ~'~~'~~" 'SKETCH Ct-S 4mSff 05VG 5259 VARQ 0 RAINAPCC L'KAKOIF I INCLUQES THF. FIRST ROOT rv oi.i ( rMot.i $4~5>055,C DrstLS orssiN rKCQ PJ/cpih/fcftQN wsrfe XJ 75 t VALVE 4 fo D>P IUVNCL~t LT ~CSX I Z.FOR COQE CLASS 24 5 VENTS iK Ca V~IDO 110 I 1 113 4 DRAINS,THE 1st DOUNOARY /V/ 1)IUI. FWA)te 6 >IAKKUP TC CCNCKNSKRS cft L CXTCNDS TO AND Ihv~>Pg. 4 ~tst 1$ 1 C txea) re:r SCC 2 3107,g/4, rC SttMACC Hi + CLR >4c '4' I I THc ITRfr NORMALLYc(0)CD I 3(44 FW.i)7 ) I W'135') TQ SiEAII CKNKZATCA )Ie) SKC QtfS. FCR FNQ Ztt FOR FNO ZQ) 3 FROM M>SC ORAI tAMK Stet OWC>. tr f I NOTS'8 CLI 110 LOCATTO 14'TOAFP'ROOHL /4 F'A'l)7 2 I i"W OS 6 Z. S IOSPMl5 TQ STEAM GEM KRATQR FOR 1TS +ff) rot r f'5 Te i rs 2 FEED PVMP SEAL WATER ~ SKC SIX tJI G.s Jl) Ties Dwc 2 S>OSOP >1/0 + ~ Occt) 1 CI ) I I ( tr>rr'p ~~AFP'SITA>e SKE OWG. 2:5K)$ 8,A/9. SUPPLY Q NDZ SCC DWS 2 $ 1050.+0 SEE H/Q. 2$ Zec CCNT S. N/8. 'twis P//G. '14 144 fst 114 rj I rw.ot.) THIS CWG. I FRZRI.RIG YttcttR SUPPLY Tf) 4 FSI 10) I AUK.Fcto pi>>ID scARecG'KA >aaws ocociMOWLl L PctG 2 Stt/e " FOR FNQ M>~ ~ fOR F)10.242 I ZKC)CCUIATICM Utcf FSI lot FSI U)- C-eteeece/t 4 I FJ/o lwozz 70 CCNQKKSKR 3 SEE ic'4 I 2 D~te 1.5, I 0%'G '2.5107, C/5 t/ (. RG49 r FSI.IIS CPX 267 5 ALT(Ruff SUCTION )CD)IF FRCN HCTWKLL C/3 LN acts I I t U~>V i ~CO t i itic PUkP CO>PL HCACKR. I 1st ~ rlAI fss(NTJI' I CtKISSTRP 5>CD FKQVu wtste fw i6$ CLS 4 Y/AfcR pvlpp 5(i r Z.stt)a/7 RVICC CPC 245 CKE ct>o t.'tcr E/8 I L ONLY1/Ntouf YALI/cNUNS)(IS APPCAR OM 'TH15 DWG. SCC Dwe DCI063>G/7 (rv(NT) 'cGSW- 85o I 5EPARATC VALVC IQENTIFICAT>OM /6 (I(1 VihT) >4C WNQ,744 fst'101 FSI-Ilt I fW'126 I IJ$ T F02 EOVIVALCN'fDESIGIP I I (4ICR) NUNCKR5 /6 fw. 166 ititti i 100 GPN cD pUtip >~PL wa~ 700 /T TQH. iip I I I I 2.TA>> h7/MSCRS MQQIIICD I'QR DWG IME As FOLLIFKS I . I TAc Ne. 2 115M vtosew CR/tsscit TQ AND rcc)M V V.NT) 5600 RPN 75 HP I UHITV scf owo 'I slo64 . 015ck. pRcss. Srs.p5>c ( APPCARS AS N WIQSW iw.ts)(IVOIT) Wtttc ORCAIC FLG S.INSTR)lMCNT ROOT VALVC (TfR) 144RK N)S NOT SHOWN Ctt UWG, Ctc fVALVEIQVITIFICATIQti DERIVED SY ADDING TP '.tST) SEC NOTE A>> a>e WNO 754 cefr.lcc rw 162 iw-1st INSTRVMEIIT IU)MBER rw.i65(rr EN)) QA 8 t et 1/W I)0 6 fOR SINCIEJNPVL5ftvl FOR DODS' IMPVLSCI Vl 0/P)TRCAM) Vt(OCWttsfec~) (t(Kff, FV/4)6 rK424 rrfsr CCKN J rw.Its IW 166 FW.I$ 8 4 FRCM t)sc IT~X (rDRMII) ALLSIKTIOM 4 DISCHARGE SCRVICC VIATKR PIPIIIG FOR A JXILIARY 7'EED pgt/p SLE prs .Pukps TO SERG) I Z-sil).K/6 6 CP IW 128 FOR ICEVIS>QN OKSCICPTICN SCE PJ/f)$ FW455 SEPARATE /ttvtstQN RECC/O FPX CC fOR IleS ORAWJIC 2$ / mo vve)v~vee>ececee acctvc ceece He>tee ceep. w 5 tvw V CPX 2$ ) rpt CDX Pl Set ORTAIC Ci/5F/ CPX rpi l.Sff. ~ t>e ev\ev >w e v w ie v wwvv ~ e >>tee v wv ee v >vc ee VV pv t>e Pew>ice ie w iv veev ee i 2 6 FRQN KSSKVTLLL ~ 5 254 ts4 24$ CETAIL 6'5 tt/5- ww ~ etta eww ei ee el ~ ecetttcc cev ee i ric 14$ I Isl FD>c SERVICE WATER SV. I 69C I/5'5 SV ttrCI 1$ 1 ee w Iwve eevwta ie >ve <<ve>5 /r 2'5 IO PUMPS. SCC CWe Att I FL'Ok TURB. I IHJGQ CL) 147 >cesar>C sef 0 Ho rstc I w e ie H >ct>we eeevvev ~ 1. FRV.Z$ 8 I'fieetso il/6 WNQ 75) erc> QRIVKN CPF)c>KC VttfKR. SCC t. (KNKRCKN T LcAK orf YALvg) p gg,i f FRY 2$ 7 I NKRGKNCY) Se etc dv FRY-247 (EMERGENCY pe>IA>>A ~ eicHIOAH cecil>tie cch r iSI CL) CSW 210 4< ~ SKETCH 0 I re7 LKAKOffVALVE) I CAP R 'e 5 LEAKnrr VALVE), ffresp . DONALD C. COOK 221 l Scf IIUCLEAR PLA/IT tt4Rt/.51 N)TKX weii CCA Stt. FFX rfx c / <DC ~ 4>044>K CS) ttefi) CS.V440 4 1s t~ f2>t. 2$ 6 It(sf YA'Y 1$ TO FV/ IS' IW. 60 4 FFX 'r I TCST 3>14. ii .5. a'wvc lcr .6 c PP-4 lt r 8 FLR. .6 PP-58 4, 6 FW. I)$ 4 FW 1 I)4, 244 FLOW DIAGRAM FC. SZ ~ Fv tts Y AUX: Fe.ED(AIC,TER FC fW.O) -/V/ O4 .C 5 CADc f -r e)t 4 cccee Cctv > ~> WCST UNIT 2 CKOSSR>t TO AVCI r ROM TURBINE-()DIV N AUXI IARY f CTX LlR(VC'N AUk(L)ARY fRV.2$ $ t DUPLCK STRA>>eea LIOTOR.DRIVEN AUXI(IARY rev MIQS&dl 1'1OTOR 110 Wlesltlf UiilrlrOR COMC 51 f CT O PUIAP QRIVKN CQQUtre r EEO PU)JF> (T ST,VAL'/i) SZW i Ute PUUP VALVf) tcs'TCST PVIG I.Q>OGA.M/9 9/)PJ GP>4 2114 ifc TQK W41CR. SKE SKKICH'02 )'CPLRk 410GDM 2)tcrCTQH 340ORDM ~HP ) LSI 4$ 0 GP>L,Z)M FT. TCH 5600 RPN 500 HP VC DUPLC K 5'TR*ttlfIK 4)'0 2>54 900 tcp 'tRA>MCR NAX 01SCH PRESS isfQ P51G'c) ~ MAX. DOCH Peers. 1$ $ 0 PSIG SCJ. C kcr. QSCIL Pt!SS:- 1443 4$ 1$ Ocet 328 (Orct 53 I Ce SCI. >i Uti. "5 i It ~. i ISI CLS lit II 0 ( C H M I ~ N O t> SY101302 ls-0$ e It ' S 1 '~~A S S I A tel)5.Z, I N)H.NO I ~ c ' sff FROM AIR HLHDLINC UNIT. t DNC. 5149,5/SsH/3 illa lit.sl G l)'o MR Nawo($ sti DN(.Z ) Sll'I 14 FISH/5 ESYPFCS.S f SYI I cd u Vsot. WFI 744.5 vef I )4)at I 4 Vtwt~ K f ~tswtu CSWtu M saw tlw ud. ~ L~ ~ c te pv ~ Las fff)on I SOC Etefe((7(Hfdf SPRAY HEAT EX HAN(cRS . M r Oo.daw CSW 141 GENERAL '))OTES LEGENO SUPPLY PIPING 2 10 JUIIB(NE 5 ttST Coaat(ttn) asR YCNtvaLYC I'(LTq Wtl Ott Dar t 5)49 IILPT/S WFI 5001 Hoou suatra 5fE p a. IS.LA 5 ~ r>>i aw r'Ll ~ Fsfaac,serai)sot)sr (SU N SY Hsf R=TURN PIPING S (C Da)C t 3)41 C.K/3 1 OLLV DISCI). TO FLDOZ AVX. PIPING g- g/ TD u IPitt LCZ CDtGROL ROOM, VrI f58(f jJ)ZA()l.(TTP) ~ v / '2 AIR CONDITIONING ) CDrtDENSE R.SEE naw ALL PIPING CLASS A IZ Ill5 (07 F fataae ppERTUBE Wta 1 Hv'aco't fl C50$ 0 M lte lt GPM SK.'G.Z'300 fmmttf)i~ COLTI(CION ~ 1 lt 1 /(SVISI I'/s'v(esl (5V le! +7 ~ UNLESS NOTED All EGIRPNIPIT sflslltC CLASS I. @ABB l 1 C '1 w 1 So V caw)ra 5 = 12)CDIIIRDL Root( MR CONDI(IDNINC FOR DSTAILS SEE DWC 2 3)a> D.l/3 i CSW IG9'N (50 CPM ~ g lstl EXCEPT AS NDefD. FOR VALV(,1115'IRVM(NT, 3AMOLsvc ~ nsot atll(RIAL AvD COHDENSLRL SCI)I Cslas 149 5 )6'if ~ ICt Fvtwt 806 P)4 OtutR 371450(5 Not ES P(AIR(0 ON THIS DW(e > AND FOR )4LRK 3'(TVRH.S(t THtsi NVMS(R COD($ 1 Sttoaraltdo)C '0 2'. Z SUPPLY Stt Ill CL 5 SZ.S)04. THIS 0114, LI5 st(f TCH (wc 'n "/2 wepMA wta S'f7v((5m. Adse Available Oa Tt PICAL f A'RRLNC MENT OF CONTROL Aoo)4 AVL (DHDITIDSCNC CDSIDENSERS PIPILC AT 1 ~tsarl 10 WMO.') IZ 7 3,500GOL( 11' H (SY VI(SNTS(t)fsTCSP4 fvtat 1D UHIT N)Z Aperture Card WSX
    7) '~
    tsu (st /It AIR ~)FV/a < $ 500 COM ( 20 fytNT 104 1)2 rfott 7)C CONDITIONING YVMD73+, 73(5 eo PSO wt gj f ID FROM COMPONENT 2'RAM CONDENSE FLSE SIC'G-Z f HAVE INTERMEDIATE LIMIT )ta)07 2 101 CDIXSC $ 15)EM. SEE Dte(w ltvl10 SWITCH TD OMIT Floyl DN tswstl I) ~ Dtd) ~ rf Ir Yttie I sat)to Eaa135)SWSLJI4 t5rets SAFETY n()ECTION SIGNA. Na erst str )SOPH (T r)~ ar ~ IDI 1st LPA 7 2 '4 ($ 1) ts Vl llwsss VENT Woo 750 '4 4)IS Nt 1I 2 CHE SIIC(L CLEARING CDHNEC)10N ~ CMCFAKAL~ CLC ~ cow 0 COHH, (1st C5SI)CO N~r:)I/5 RETURN PIPLNr CHANGES I FROM CLASS fAUX.8LDG) lk I6 7(l Tt . 7)4 P 110 P TD CLASS IB (TUR(L RDDM) MNT 'C': V/S.H/d, 7 I8 i! .," I Z ENORCLED LETTERS ARE SHOWN FOR DRIFNTATIDN DF )K )SC IL IC Y, Is/ p 41 i! Su tst c ' laws Id ~as OQ wf (5u t$1 u 15'er a/MO 1)C (saw 1 4 I -. I.-r g-" J 1 I (Swtr (T e .,-,I $1 f ew 5 0 VALVE IN PIPING,'THfsf LETTERS REF(.ECT SIMILAR MARKINGS ON VALVE 800V afcocAAI teuaacD =. I 4/4 CHAIV)OLL)cdto h ~N ~~ K T<<i&Sr era DCULIL7C IOR La)W ftj COHPONttlf CODLIHC /f aeo OV t'AOULStgNSWP Htal CXUIau4(RS 10 E FRCM CONTAINMENT zo'j a~ g 4 Mi3t 0 Stela(5 ZC 5 ILHTR SPRAY SYSTEM SEE p 'aswaaae/s(IIp)-. / WHO 1)O 1twO asasCCIASMG,SAC Isl ootrfoacf (Stcwos toaaiO(etCLLOCS rac FIR)t coot trave I( wca FS)tttt f MPM e II IPI LIPIPLL ~ I OLDINI 7r "'~ ~pt ROOM AIR COND(II(RIING IDR coco(a)at($ vcefsatosww CDNDENstcs. sf 6 sr.'G-z'~-, >> WIX S'IL -Yaatt51H j 0 .PL I Daeaoa 'S tattrt Dtatoco DIG re 2 41 SIDCH Act Cat)to VAIVC . ~IOS . OEIR4H td FL(DR@ ti I. ~ (swNS ~tt<<esa (DNLG~ ec VALVts PA(CD Ioretu fata) FROM 2N COND.~'f)OVI'85 COND. ~If*raswlol I'YENIS Ntt Oct(CO) DV Drtr 510wa t l'L loa 0 M ..)6w IGi 'THC lVHST OR(fit'DC5)CNAYtON foRAIN FDR tacw cow)OH RT HCN)srscaveow ~. M)et-r. NVM$CA IS '2 VHLCSS t4'EP 10 C )sr sa)TCC Otvcw ~ Ost so w)f fl\0 tvwt sct ancrl5) I (Setsow otwtorssc sate)re(a 511)d>4k t )oat 144 4 fofcwoac 11 4 110 11 10 taeww tft ftcorvv tlro toe)1k s CJ 20) Hawo ot(R t(D val 511)S (s/9 " 511)0 C/I 5(1)S.F/5 (\WI4$ <8+Vrt / tst cc..s sa I lo(wtsf scat)UN NVMS(NS VH tod area YSI ears lot taweat 1 fTELLTPLC+ iL tsw lao*, I. OSLLY ttttOVC VILLVC NV M 5 RS attc4R DH THts DRawwc. t W40705~ IIILIILP e a eo W)t )P VALVE ID(wtsf)cats(fe 5(l'(taRATC I (Swst) lest F0R covsvAt.cell'csscw 0 tJ 54$ (g 7 hatt r (Sw)41 > gtu CLS t .()SCRI NVMS(RS, TAC'NUMSCRS )KOIA(0 Coo DRAW)VC VSC AS FDLLDNS: Csv er) ' >>wr)trad~ 'fad st ~ ' tesw YD5 w (Swstt aces u)W re) 1 ~ taco 14 ~ tsf CLA 6) I APPEARS AS: Nswsosw 'l,l lo ctosa co 1st w ea 0 toc 4'teofapcf OL)ecv To ~ Of HWOO Orate <<N FOD ~ALT. FEED C' iCIDGOM cl ~ tsc ttNCa 3.)wstRUMcwt Roof YALYc 44RK Tcwoc 10 rter scc I saaaaac DOt NFS Nof Sssoww DN owawvec(5(c Orea 1' el),4et 2 Dtta)N cI rr gZ(f (SWH4 ) vALvc socN11rsc41NNs U5TI D(RSVCD St ADOSNC TO ~ tstttvM(wr pevMs(R; 20 SIGPM~ CSutdd~ ZD.J C 10 f FRDM HtAI EICHANCERS )DR ~ 1st Cus ftft st)PCLC NPUUXSII COI (ttcat aatASCÃt)PSIWC Lvle ..i 'CD'tufttGCff( tttSEL EHCIHE YZNow t5) CL.S e tsw STCo 6q ~ ~ 4 treat-aa ~ ~ ~ fwo 4 I)IIJet)AL wtl 722%0 l)rra'as'. Tr tas cswsacKO feet. VPSF. ~~ . 14. I f. SCOFKC rt.ta tve 7)G 70( w ul sctttw Ydrl'1 . tar )area t ) [vs)e Yco ctrfsccw)7 I lo'W o(SI ~ st THIS TAC rwe wtt to Yo csueet)AL to tsstutsal ~ pe 1'e aw FM) ~ re sat / Df Twteta'H ar 2 2.5 3g ')04 'lsa $ (once wal(A SSR'INCR Walt CR tyt( [ Clwtld H(4)tR,SCC YH)5 wav )cd~ wav 7)d~ HRLDSR. scc TNTS ~ re'Parr ) 2 w Ml DMISL H/7 tsws)a DW4 Hll IP I') I tet'Va ~ rtf ro) ur le Ta fOR Rtyss)ON DCSC)ttttt)N SCC ree ll w )OS lot ~s M TCtr 4)aa 4 tpaetta Stffdtalf lttyts)DH Rlcoao MOl eros sf w Amz rf a\Cata F0R T)4$ DRawtwo 704 7'1st 4 weao "104 70) ~erato 101 ar-aseeaa atas 1 ~ Ase C(XSLERS Atz AF1oz COOLERS ~ taa at tsspa Aa 1st ~ aat4 '0 N 4 M Mere ar M awtwtaa 015 'srav 775 lr rg. ~ aaawasw T IS)'2 NORYN 500TH ttctl. 70 'Q ~ ~ wa wea c~ ucswc Porta seaewc co>>. Me 4 4 w et H twwreea aa aa r Ma ~ 4 aa et i)4'0 ss (Swsotw tswlOZE Mwwt M saw w M rarwa\ Mewa we>> ap wr ~ Nteett cow'a ~ ~7ZZYD w>> Mw ~ wl ~1 ta'g 20'e at WIZV w M <<Mw awwwa ea rwa werwe. W H \ HMMWt Zaj .WRV IZD Pigegj W catt(de j Moroo otta cwot) a e- to (DVMJtta aftlw tswenaW DRAIN 70 fI 704 DVOLCY STRAIN(45 ayfo da(arasw 40ICC CiTE (dY (LL)CT ) DOC R Dtt.stt - I (Dvaut(R ae 1 )0 OVFL(t 51aa eta'5 'Wslw AUTO dacAWA'sw f to fi 01 tsl ccs l ) CSNH) CD tselKI'ad+ 4 4 VENT Jatatr QSC)L70 fl ctoato DCSDI MCTta wer) ovrtco 4 6~ - W(X CD )5 C 152 IR WFI.TZC TYIF l~ IPRHAHA ~ a)004)taa MKH)ol'NttaclltIC CO, DONALD C. COOK NUCLEAR PLANT Nooseclsa t. ~ Oaaos ($ WIOOIV IO(f AT) Fg rCS CSwlodfi (4 O'VENT fCLKC4 ttaatwr lt) I O)Alr A)A 59110'ta7( j ¹ CSWIOCW d E( leaf ewa arwaa gacecr llatcc Fstaro ESSENf)AE Ca Sde" +see wd 1 1 ~ es f sas Clef F15~ I fROV.'w DUO(Et ., I tsws4$ (0 CM ca ,3/4 015AD( 0 <<4 scc cafe. c.s ssd (/TC>>1 4 (PSISID) f/rfCO) IL I 1 ) I SERVICE U)Z)rs V/ATER CSSCHYIAL 5(RTK( wattR ~ Vwt atooootea s4$ FT Tow 445 Rare 450HO 'to Taaswtwoovae ~ raV 744 Wtlta Ltf(L VL. ~ rovv1143 11 'TO ~ atewase ovtL(7 H(LO(R stt'twesow4 sard f SCEN'flAL SERVICE IIA)ER PUMP )0.000 CP)l l45ffI 2'44'Rlo. TO 'TRAStl TRDLK)t WRV 7 / wcl'1)3 V IZ ~IZ 'fo 57RasHCIL(A ZAGcwaSH DU)LET f ZAtfl)HG SCZEEN TFASH TZDUCH. VeAIER g ~~ ~ ~ rtar MM ww tetra. ~ww ctcaasecttsftt)tatr 0(ss Dcs(L 0)case ~ WFX 122 Wfi 720 . ~~ ~+ CD L)d I 2-5 I )3-3(0 ~ eat. (wsctt ORcls (MLN 'SSSerst 450HP eat aer to t)eo tt tlSaer) St E.SARGE N f 4 LUH()V TD teeluf sf C r ~ 44140ISCH PRESS 120 PSI 0 . 0ts4.1 5114 f.51SIC, 2.3151 a) Dasoe 'R:'oc <<MM~ J aa 1 0 544 0 (L.Salas I TvtKLL $ 4(tcw d. ~ aoa'ct or tetewo AT U)cereal scavKc walla tvw t. wt)r I EL.5464)'L ( MIN IIATER LF VE+ LL.SCS'-ll ~EL S47' Sgf /GH IYPIGAL AZR'G'f Of PI>>PIG AT EAST ESScNIIAL SfRVICf. TIATf.R. PUMP F.e) 1 n~ ts c,scc ~---'~ J LWa'accwarca v 441 S2.5ww ~ L /1 SU)(G'sera f)RC nVMO 5(C Drd ~ M(ae ar ILL(51tK roe 4 (OTK( ftwr I 12 4152* ~ Hrd l ~ Itoaowtt " sar loac I G I O, f 8 I I . c f ~ ~ w p "re q ~rc'.L.s r.ay r OP P P PI I c I D I- < I F g I ~ H I ~ ~ 3 I IC I Ll " ' H I - 0 ~ INSID( RELCTOZ'CONTA5Nl4ENT OUTSIDE REACTOR CONTAIiiuitu'T G'ENERAL NOTES I CONTAN4MENT 4 rh ~ tew '1 (4)I.OWfR YfNT COPCTAIMN(MT VNCTS NIDSILE DAMPRIERP ECAccsz couTAIMMEMT AIMMEICV AUK.CHARCOAL ALTER SYSTEM, (LEAM.vp HV CST I Cr)veseNLJ vePN VSUpee44 4Mov1'V-CVV 4 rsvi55 h usel5$ 5 tsriss 'I ill~ 1$ $ NOW 1 44 ~ I et~ PTA'5SC ~ I 3 0 usr see 15' 1'Sr llt 5 154111 4 ~ teN 1 1 $1 ~ 1 YlfA.93l~ 3 WFA 927.2 wfa, 923-t ~~ LEG'EHD septet R>>TURN PIPING Pll SUI p p P 4 (Cl ZEAC OZ COOLANT PIPIPS 4 (5.C.Id) re 1 5 et 51 8 ~ MOTOR AIR COOLER'5 CPM ~ '2C CN05) Vtu t el ~ I WT) lls I elite $1 4 rsr 555. t FOR YALYOvlNSTRUMONT, I ~)Is'2 CPI4- TT (Nl'I) v Pst 4 VIT) 527 2 Q C 4 Q il~ (2) NSTZVIVCN'OOM Plvtsl , WPK 111515 I SAIAPLING, PIPE MATERIAL VENT UNITse I COH DS<NIS) et tSHI Vcr l Wlt "5'5 I 3 AllP OTHER SYMBOLS NOT 0 lesvrss 2 1$ vlss 5 Vsvtss-a~ 3 I 'Nc ~ 150 5 er O.etc. 15 415 5 YEN( OXPLAINFP ON 'THIS OWG.S ~~~ ~ Ct 1$ ~ . I DZAIM.TO FLOOR. rslttsa I vlvi5i-I AND SOZ MARI( HUMVJER Vivtsi t ~K ~3/ I ~~~~~ ~PLer. CODE SISEE Dwfl.il5054595M ~~ ~~~ 1501$ PZ . vsvtsNS <<ivcsi.s etsvts< 4 vivcsa-4 LIOT08 e 1$ 41st'3 rgere errata ae4pe 1 p4p OOee VAL A'J EOJPI ~ uf DEISSIPC <<svtle.t E<' cLAss tt Rtec40T As aaoTRDL tsvll4'I ~ N 1W ~ 4 )ZPCVGGtOTCSTCDMM.(rrp) C' cLFotc coDC chA6$ 2'laiST ldl 0 ~ 4 SQee ag-4 TISA. ISS (M14) CcspaaNL Tete CvsvvDARY ~v M) UPP(z coNTAlM'icfNT CPH 04(H14) wfrt.957 cNI3) ~ EKTcaecps vcs 4 cefcLvocB 'VENT UNITS ( ADPyt Q CPN'05(NCS) vrve.vorfarr IICW Oit 2 Mala ~ tl 3 Wfk')sb(NIZ) C TNM eeeRST RCI37 vhi.v'C, SIR CODS CLASS '2 VCefl5 4 I CAP IIS Itt vtesvrrotervs 151 550.$ MISSILE ()AZZIER) I 0 5 YFNT CrN 11 (Hez) CPN 'ZCP 5 Gsi Wr(')5C(NIZ) 1552 9'51(N15) 9$ 5 - 1545494 Dttheeid Tete ldl cvc4eacpd To 4 IuchaK5457544 plRsc aastehaaAY ctcsdCP 5 9')5(N'4) pf TENT o ~l' ~ OI5 itswslf-4 15 vtsr.terbr al yhh'vc" 1$PSCIPS 1 rwrrt ~ ~ IV'r NTAIMMENTAUK.CSIARCDAL 15%Isis 'I watt 4 0 V ~~ ~ l51514 I '51LTER EPVTOTEM.CLEAN. UP HV CFT 2 t pePla IPsea ~aap
    r. 44 (S.C3)2) IPCatel 1 1
    ~ IGy426 Wf. cesv414-2 <<wv.>> ~ e'etre ~ tvvw rre 0 L 2 PLUGGED LOCATiOH PLA.N $ 14' ~~ iCAP etc 4 NSw426 ovhv i awa'aa)etp p~ ~ cpas I r ZIS r '4 SSSV rev $ 144 II PLUGGED aoc eoeclc ~ eve'1) WFS$ 90).t TEST CcsNN. SICR 5LO 3 4 ~ tivcsi 4 VTYF$ 'Wf5 Wls-555 5 PSV4ci ~ 4 vseisl 3 Wf Wls-s($ .4 - 294 ~ CPH.14(ull) ftsyhtl 3 WCI 957 5 '%3 957 seepaour IDI '5 6$ CFH-75(NO5) 0'lrA.003 eaer aoee 1 Cut 5 (PM 15(N 5) 1$ 4400 5 11' 400% VS(I 90)'t 'wrA scr.s " WFA sll 5 CPH'22 r G\I ISC Vllt )H 3 1 ~ vcscc 001 PCreets.a Veftt ~ tls 4 VST) 040 Va A P fVENT Ogl4 907 VCP tel'5 6 5 O'RATH VCA vl rt Ilsvtle 1$ 1QI 4 l vsrssr.t 1$ 4$ $ 1 5 .0 Vsvlsli usta stat vsvtesm r vsv csr 2 ~tee . 040aavi Lt lr t Orf 5 rsvceps 4) 3 i J rsvturl 151515 I C 'tcp' laser~ 'l/~ / SS1515.1 151 515.$ O t CFN"10 (Mll) CPH 27(NOZ) )c Vz'PLUGG(0 Tfsf cONIL(tyr) I IvCSC ~ i 5 451515< WFA 922 I 'IVCSC Z)2' CPH 8'5(iie)) VSvtst 0 ccacecov 5UppLY CPH.84 W VISA-'51C 2 REA(70Z (00(ANT fVENT WEIDYirfttrCM CSSTSOFPERCDVT 0 i ~4 WRV 9$ 4 95 F WFA 45)O'5 I VENT PVMP 5 MOTOR. ADCvtuf N0$ 4 ~ rwwvtp t- WRV.9$0-3 vsrMS I CI ~ SUTC I AIR COOLERS Me I Nt 3,0il'Y I TK lieut PC (2) DER MOTOR i al Sll 1 4-usrladw rsrlas 5 Vlvtat.t vlcc DC gechTKSSs rvsc ctK44 ccarecrpyr IDfufr rechrrsea aAatlccC 13 2+ CHART TD COOZDINA'TE-SUPPLY AND RETURN (S.C.TL) C LIM'ES TP E UIPM'EMT NOT SHOWH ulrlao I Iatace cstccrpos aa3ecch ~ 711 ic'PLUCCVD TEST COMM gcC, IC rivc51-4 eivt50.4 SIAVD 00ERATCD vALVE <<svcso.i 00 GPNn 2)~ STMDOL EQUIPMENT Si )3. 15vlsi-I M TO AHO FROM VENTILATCPM UNITS. vsvtes I ~2 TDOIARCOLLSRTER5 VDR ARE PROTECTION sccDwG.lc sist(t)rs) ell tsvcsr vlvtli 4~+ '5 4Gvg'-=11: 1$ VI$I 1 Ieseiss 2 aleiii 'I fYE lesvNO.4 15VC40 rsvtad.t )8 locttceslchreoie
    l. DMI.T 'VMIOVC VALVE Cai THIS DRAWUIC. 5EE etvetucus MVMSERS'PPEAR
    ~ Lowfz coNTA.'IHMENT. rseces 2 'PM.ZC Pe/CDZAIMTOFLOO~RPtCDGPH 1$ 414$ ~ I Ilsvlel 5 SEPARATE YALYC IOEMTIFICArrrl Clsf FOR EDIRVALEMT DESIGN 'TP AIID SROM, YfNTILATION Vli 5 1 R M el sl CON, 1501454 (2) VSNTlLATIONUNITS Nr 4)04P~ earl le F4 i ~w(41551(Mat) Lelsrsda I 1$ 15$ 4't Vrrvr CaaCR) MVVSERS TAC'Mueadfts IKOIFIC0 FOR svpplv lpvcsmLATeou wiTrp 9 etsr Isa 5 ~ DRAWOrt VSE AS 151554~ Nt; z.leswaaccvw FOLLOWS'Ac vppER coNTAIMsaEMT CHARCOAL 1NSTAVVIEMTATION ROCI( r)LTTRsrDR FIRE PRdfccnou AMD RDVRMFROMYENTRATNal,VNITB HV CIR 4 t acocrsc r FA)$2(NI tt Arrfttis AS'ISWIOOW Ne <<ve rer en.c 953(N13) c'FA 50tsruutaf Mf ROOT VALVE MARIC VPPCR CDMTAIMMEMT TP AIIP FROM VEHTILATIOMUulrft ccpp est vtsurAINMEMT' KftcrAXZ CDNTAcMSIENT YollllATIOHVMrrs Zip ~ ll'svt55:,4 usrcss'5 0 CPH 754 .cvvp$ f WFA Ssl(ral) A ~15'vlss'4 154551 5 M<5 HOT SIIOIIM DM DRAWIMCCSCE VALVE IDCMrifICATIOMUSrl DCRIVEO ST ADDVIC TO HK MO. I Ate K MD.1 DAM K MO.$ t ~ esffivtafvf NvsesfRl . SUPPLY 1D VENT)LAT)QH UNITS TNSO VM STMSOC 5THRVL vvle LZ F:0$ ISO CPM(NLx) 1) 1 ftst 5 IIPC44 040CLCW 3)PPER COMTAIMMEstrt CNA'RCOAI N)VZI)2 NSS'ZC 2 NS'W ZIS.Z Ltf2'-wRV-SSZ fOR DCKCLC 04PIAsc VVIPScRSAMI VDEACNPTO f(OCRNV XlLTER FDRSTRE PRO'f ECTIOH tMP IQVtc) I MSW Zie.l MSW ZIO I 0 RETURM SROM YEMT)(AT(0M UNITS SIPPER COMTAIMMENT Qi N)lizi)'5 IQMti) 4 NSN Zirs Q? NSW Zl5-3 t MSWVVaV WRV 9CCPSV A ~ 0 + fre='7.$ Nt-t<C,V Haiue te:. ."DfctrvSDOC. '.cl NSN ZC 4 N5W 'USL4 $ TO AMP FROM RESCTOR CSXXAMT tiSW41l tasw41i'3 WFA.946.5 4 Nit H$ RZH 2 NSWZS7 2 HSW 223.2 ic.s PUMPSS )40TDR AIR C(0(ER N)Nzll MSW ZIT.I MSW 2204 HSW475'4 ~ tpw ~ 14 4 NPW 4PP h ~ SS 7 02 1 HSW')57 3 Qe iisec 'f'tO 3 Zsc (TVP) Ic utdavrt vpeaA'cc Nf 0 tof I CJ,.'M Date a IQlizi4.l Nswcc>4 HSW ZZO4 rsv. 84NC cuoi Sard-t<o-3 F0R RfviscsN Des(surf ON sEE vrhvcd Nectc clod 114 4 wrs NSNZIS 2 NSW lid't NSW ZZI'Z NV CCV? "Is ICR $ 1)a 0IVA 'hOt P SCPILRAfE REVISION RECORD z'6 ~ lQWZIS I NSW ZI81 IisW Zzi- I 0 Olt OIA iS I1 IU Cruvd 1DS 151$ WSC IDR 11VS DRAwIMC 1 L ueA ROC.C Hse)zls 3 5QM zl s-l NSWZIDS MS'W zi04 MSW ZZI ) HNi ttl'4 s 7 '6 OS gQ3 2 CPN lr(MO Cl'Nl'5 CNI 5) Ii MFA 4110 3 ,LPA 4114'4 vitNO.I 150 $50. 5 ew 4 ~ 4 er lt 44 areavaa cop'r 4 p p ~~ Ie904201 ceecepc tepee etarea 8 ~A Nwrw Nr 1 4 pf p p pwpreee BYMBoL TP cooRDtklATE SUPPLY 'AND RETURN LtMES TO EQUcPMEMT IQrztcat iQN ltd I HSW NS'4 tt$ 1 tzs.l MSW NSW Ztt 2 ZZCI h (4)VEtm- 9 Ltreoutuut Cr $520(NO 4$ I I NSW 4 15'3 ~ wRsatarc 555CV 902.5 C ~ tee N 4 Na acre PN Nr % N Ne rwa prep M 8 Hor BNOWN. rQvztds lQ'V 2234 tQv Zcaz Mrw 2153 CC)tf 115-1 .I)scy 224.2 H5W 2225 Hsytzz54 MSW 223'2 I cacAIM(TYP)g ~ 1 Aite.v tM rtN 911 f 1$ vtita usvllt 5 ulrllt I VtP icsw 4 cah WRf 9ras WIN.9i~ 4 tsvrOLI SVCO05 evvco04 8 I I- ~ ~ N pp ewer pNprr 'p 44t w 1 p p prwe pN ~ ertrt err el v 44 4 1 1 leap(a OUle .HSV?Crt Qc Mesc 23) 5 Ql Ms(V? 2$ -) 2 ZS'2 4e tl wc5 64 C' ~ 3 C Iesv coat. C cttseaeeA ~ eelceeecaM cttcrwic co, MSV ZZPS )ISW 2203 MSW 2230 pry p) eesr 412 I I ~ FC. .~ DONALD C. COOK SQVZZ94 MSW 2?Ces NSW ZZ34 ~ ts W41$ 2 ZI NSN ~ Ic 3 reeve s 1 NvclEAR rcAME iQM25O t tQW 2252 MBV 114 2 ELG52 O 59 ~w 472 4~ ~ L 15W IOI EL Ctz'Kr C 1 CeSV250 I )tSN 2271 Nsrl 22t) I HSMZSDS MSlf 2253 tisW ZZ4.S 5'2) cDMctocsv:ur srcdaaAEE f t/2 PEACH TO FLOOR-l vrsvtlo'2 >>V>>s'.I VSVZOS FI.OW DIAGRAM HSV2)34 N5'll ZZ7. Itsw Zhrs Vh'5 FOZ FR(. COICCCSON SEL Saxi ls blttteh>f 4lfft NIV114 5 I rsvt ss NON-ESSENTIAL 0 INLET I@tests 2 'MW $ 44 t IMi.ET Nstv sir 1 Zl leivt Isa 9OO 1 Ce SERVICE WATER NSW 54CV Qs H Sr Sup') NSW S4GS HSM 5454 Nw 5495 HOVE: S TO ANO FRO4l sLOWDOWN HEAT EIGJctsQER 0 I'DRAIN UNIT NQ 27 Nfii544'4 FOR UuldUE VALVE HUrIDERS SEE DRGZ 5IOSEhflc(cjf4 CR Acct tQVSas4 DVAIV StSN Sl14 AT LowER cats TAluasEMT vsc(T I 35 GPN (ICAK) 2-S 114 A-27 IQVSSSZ DllILS f CVTLEr MSW 544 1 ILATIGN UiMTS. SEE CHART Dl(3 3'O 5'fART.UP 51l( rcEPL S(OI( DOWN 4 ~ t(F Also Available On HSV 541 I iQV545) o 5'9M 545 IQW 54>S C frvtl R HSM $ 44 I Nsef 544 5 FLASH TANK.SEE DIYG Z-scos(5 A/4 l I ~ j DRAIN SQVSCZ+ IN reset SC54 DRAIN MSW S44.1 X.rp Aperture. Card 4'P I 194 IPVDppi Dfsc. GfvCCATCat Ceasricceeei ~ ew,VV 7 4 V 5444044 Odte6J$ <<&Y CVCP4444GCtteattg C)6 freer 1 DNCI. 2 4tt its ~ 5K'K.GL C 5'J4P V NGP4 JC, CCR tCVAlTilRMISCAD(il.s(t aritKatt cccccttc covet icteect cuar rs/ Ovc 2'Diet, Cvtr 0IIG 1.5II4 jts l oa04CIIOT Vcr $ 0M /g'r A c 0 - 'I iH ',, ~,I / ~ r' I I I E F Q . I 3 I . K L ~ I I I . M I . H - I 0 8,71018 02 78 -.08 4 1 f ( '1 l~ ~ ~ V ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ' ~ I ~ ~ ~ 0 ~ ~ Nl ~~ t~ . ~ ~ r J ag J a~ ~ ~ ~ IMI ~>> J ~W j ~R P ~ I I I NTTkRI @ N JjLI 0 % amimma ~ ,8 REIWHN I~~S ~a s~. ri. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~w ~gg dh a~dKs m ~ /pe ~ ~ I ~ ~ ~ ~ ~ ' ~ ~ I 4 n 'lf lw II 1, p 'f~< C gb ~ ~ ~ ~ ~ ~ ~ ~ T ~ ~ ~ m C~g T ~ ~ ~ ~ o ~ o gb Ch 5 ~ ~ ~ 4 I ~ ~ ~ ~ ~ ~ 4 ~' I ~ 'I . TI ~ ~ I ~ ~ ~ %J ~ ~ ~ ~ ~ ~ ~ ~ ~ e~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~- ~ ~ ~ ~ ~ ~ I~ ~ ~ ~ ~ ~ ~ hmua ~ ' ~ ~ ~ ~ ~ ~ ~ ~~ ~ 0 ~ 1 ~ 4 I ~ ' 'T ~, e A ' ' 3 I ' I D I R F I C I H I L I M.. <l I 0 ='(f tc)8IC Rt AGTotl cooLANTQ DLa 10 ptl<p <N 1 uw'f < ~. ~<~to v a 3.1 avs v a.lst /also ofv ~ 1< Ts Ll'c~<cuss lllswN<rtcvff<4q>> HCTKS STEAM 5)AND fife QLA sat<are 413 al, ~ I,lll <f1,tll litt Deva<a a<45<15 IN Oak<elf 1 Tarte'< Ires tv<aero<a TK'(0 Dtfg<i, as<<et 10 CSOCt.sa PLA 40fuur N<4 GKN'ERATDR Nt5 <<LVLV,SD Olt S te S v a vea.<4 Sear<44 ef l <<'trl l<</C. L =GKMO t KHOI(),00 1$ TNTS as<<et 40 C54 3 40 CS4v'3 30 /YE I .resS a<D <3 <<v<41'$ Leo<a<su IV l<<vh L <<a foe<a<la I rc fs 44$ cavvc JMUI cf lrlcvss tpa<<taco<<<as fea ~ C5443 10 Cea 1<cavo voc aif ctouu <<L/col i<led< REACTOR 2 sv/a <<'VD veh lf etl 2 <M 2 ~CLCSS)$4 lu 0' C5443 <0 2< F3<VS 0'La 3< fvvP 4<5 QLA 4$ PWIP Nc4 N12 Mmm'mE u<<LVS S<VSO'<$ e<OLNTCD 04 Caak 5 10 <rlua ttr>CS <S aes ie AV/D feasu<S RA<44 ulaa 4 voav alt c<<$ <P erlrc $ << 4 cwc cu << 1 < t 1 tf 1 ~ 4 o o<<ter tea 1st uvvpa<f a<If<oat<ates Ieckrtcs fel. Io<f ep< a<<ca<vora<ra COOLANT, PIPING BY (T/) AUX. PIPING Y I ttu D' euo. s ~EL GXAP CAB& 9 )NSTR. PIP)NG BY WESTINGHOUSE .ov I +4 I V(NI /I'O<VLLN C5 4 43 C5443'11 N I $3RS55uR<ZKR ALL VALVKS AND INSTRU. LV t() 4$ G5 451 ~ 5443 SI PRIMARY WATER ELEV GSZ TV M'(NTATION BY (6) 0 I as<et tl CS443 41 I MAKE.UPI seE <<cut cela<I<<at out<3. <<<<fa<<wtef a%441 St ~ rcts< COR YALVF.< lNSTRUM'(NTT ~ crt<I t QRv - I JMD SKETCH G 9'<C/6 Prtft ~ I 21 MO.2 tltK MATKRILI O Puff< 1 tfl'3 't<<as< <PITS 1 fret<<< 011 11 QRV 31 POMO MO.S ~PLI ~ SSMPLIHG, AND DTN<R GY$<SDLS NOT ~ u) <N Pte ftren-4 QRV ~ 41 PUMP H0.4 5/4 to PRESS4RIZER ps<at <N Cru.>4 sel 'ltlcrel"1< fl<L<uffl EXPLAIN<a ON THIS DWGV TO REACTOR EOOLAIOT DRAIN TAN)( OUTLET SEE DWG. 51374gjG cl<IM Cll$ 1't f1<51 I FROM PUMP NO.3 CSHI I clast 1 'l<5< Cl<l<.~ ca<5< ~ cs<5< 1 C5<$ < I DeafN /eau KXCK55 4 t. Kl(R5(( St(sap/8 RELIEF TA))K l scc uols ~ 0 I,/< III(4< I) ~ 5< t)$ <APS) JNCAlffl AND FOR MARK NUMBER CODES,SKE DWG5.16510>; SL)4. 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 ~ $ < I Clif< I LC <sat<'1 f54<V) R yrt<< et<et Jhhleeel t-Ro tost Dft'40 tv<it N<4 NO.'2 -/3 LP (L.59813> 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 <I 141<TK<al 0)I -4/ 1,600FI 146SPSI C60F or<Lees) I 51 ~ 55 <SI 15 I5 I tt v <<Tet< e v toe< ~ evvev <v<< <Tee. v 4 <<e ee rr /<<v ee~ <<neo/k MAI(f Ut Uu(5 N(.P<5211< <pve ~ ~ <<ewe<N~ <<<<ca <>>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
    • I e I C I o. I 6 I r
    '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 (st< I CCWssc. 5 Cwl )).5. It 5 Ooit g ccwl)t 2 ccwt)o.t COMPONENT tt! 5 t(W"astra ccwt)c ccw )rw twt)). CCW)1).4 CCH)t(..I Cc<<N(,.t CCWNC'5 CCISSX) CC1)2)O 5 CCWNO2 Ctertte.~l ftt.dsi LNe I) Lfwtt >L. "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 -. I ~ I ffx fssssae rAH swsee CAs. aw p aHIP Iee ewwaA eaw w ~ <<r 1\ H Hsweesav ea
    • L ssawsc SHVes H AAt A <<PL A eaa Ae I 8- . C'I Px sKAT crcwvacr.r . R$
    ~ ~ ~ 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
    t. Cavia>> I D
    ' ct 4 TO I ,o CAR K(DOO GALS (AtfXOL SSO GCLffT.) CZ'O'OD. Ile(f HK'TM FOR VALVE, INSTRUMENT SAMPLIMQ DIDO MATfRIAL AMD OTHER SYMBOLS MOT Cew ccv Dsa EXPLAltlfo OM THIS DWG.I C(vteeA ((evtet I aOal CCW Iltl fvaar Staff foctet ROM CCW PVMP Iw FC(vtcd AMD FOR MARK NUMBER Ya 1 Dree SSC\SA (ft I ill DWG I 5IDSA f/1 C(wted~ C(Y:N 1~~. CFI I ((riel COOKS, SEE DWGS.IZ Seo)(5104 f DRAIN ffc CICKSDI IICEJ Dff SIDS.Fr( . Dtul 0;/ t'I ID BY WES)let HOUSE 2'1 Ccw(59 2 DRAIN OW tRDCICCW PUMP IE Vwff I $ 1( DWi I'SCSSA (A C)t Df Vaeraaeetta Watt R, 5(I Dwf TCDTCSA Jfs fSPE ESP + Csx csx (O'c~ CCw1 to EL(GCSO' OVIPNENT SVPPLIKD SY W 4.$ NO'tKD .,i~
    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
    'aw avaw ~ Av e(rata ND CMD-4 4 429 TO NAVE DITKRHKDIAtf.usvt srdtcR l~ ro COMleO)SENT CCXXMGw3(tfft5JKJZUMP .(SRAal)4')P))JG 15(e lto 410 C! CNO 414 GNOHgtt C(wetf C7 IC LIIIIT (Loll 0N SAFKTf PNVSICALLV CDCATKO IH VHITvf 410 IG Fooea srawv VAN INJECTION SIGNAL 65233CPfc) 3)23IS,P/D ~ Vre ~ (S aw\D)DC% ~ Coa CF(- D 'IA fo 425 (ves '420(tll PS 4to / C(rfllee 19 DRAIN JJ I(W(ld OCNT'0'ld 1I CatC ~ SCDCA eeald ~MO: It'tcasccatf twftfc WC lit tteaaoaaf aefeeef P CP IC) eav I Iaactf fratwlf )tvt eae W C TXMZB(W I CTA CP CPÃ428(NI I a~ Ctx-4)S(w)~ 14' CTX 415 IG't ~ fR(af ESSENTIAL + (4'~ / i. PX CZI ~ 10 4 ID cta ~ CD CPA iaa 14 va 1 atoe f faaff I a ft(C Ca allo vcrea w Dca vS fat 15ltcavtaav at taeea to WD Wfeaatf ~ Tt 1 R(71 aeoctaaaf (Cava o ccwl ~ ew/ CCWI ~ I( 410 Cfd 14 UNIT C(vf tdtSC Nt't SfofILV~ SERVICE WATER. SKE Otto S43,0/4, f/4,+4,Xt4 ICB TAIe(. 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 . I c(oaatal lo eaooaa 'C CCw COMI)F Ccwaet CCrt otfs aettvr HIS'SCO+13 lv( fires tllce'I ((ie vatow fel(acr ~(a . CACWAOVCV a (2) RESIDVAL tr FR(ca Rfeaferac 'tcwvelcll ~ ae 'we seaaaec lcaN I NMT EXCHANGERS ~O,SRdseoataa.eadAT C ~C.~S, v (aattal V CC Oataa Crt carter(NI lccvffcafcDN I vrt(C Is 1 ovl(55 Cta(trail NDIFD )4 CMO' a Ccae 4tt IS ~ca OIAW ((WCC HAND DPECIATCD Val vf 3~ NJ 16 ID(wtefacATCON NvaedERS D tlArl / SCC2 Se-Stt(S LoeelY VTCOVE VALVE NVVOERS I aaeccracwt ZS APtfAR Oel THIS DRAWCNC. 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....... N l e ~ ' 4 8 'P ll ), ~ ) t-=>>" p" m4 I I\ I Ig . L 41 I, h I'ETAIL'lA-I I H A Ih'E ~ rxlh Sv-m DETAIL'M 1) XC SV 150 SCXAT 1501st %E DEfAIL'M GENERAL MOTES INSIDE CONTAINMENT OIITSIDE COMTAIHMEHT $ (f Af ISO PSI PX, CPX I'VTIC INSIDE OUTSIDE IHSTPUM'EMTATION Af COHTAO414ENT DEMKTRATH)NS LEGEHO t COITAIHSC(MT COHTAINNENT REOUNUMG COMPOHE! r CDOUHG WATER DSCSIALiE 1) RCOR(ITP) CCV 1 SC4 COMPONKNT IHLET OUl'LKT ~ CCVT ISO ccvtssn $ (r. owG t ELEV. 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. M.l SS'I 'SS'9 560 Irrw cOTLETOCCEss 4 g q Msvw. r r Dx Cox Ctrtshs cclc41C 11 T-$335$ COB'-0'05 561 563 564 )Aia&PWP rx1 Sv-ltt CCW 440 I Ctwtll-5 CPX Px 0'0 56'I 560 COOUHG COLS SLT Al 450 PSS COCIIS 5 5'10 '511 515 ~ .V W XSOtlh)E TO RC(R (TYK) CCEE ISNS PASS ~ Ar CCW Xtht SEE DETAIL'M I SKETCH 'J PASS'A GIVE ~ awvss awrrrt I'Y(Ml' AT CONTA114MEMT PENETRATION COOLING WATER t'OMPONENT HO65 M INseK ovtteK ccr INSIDE ' c cc OUTS!(E E E c I'Xl 3 Sv SEK DETAIL EM.I CCVCtSO 5 CHC EIIC rrrll E C I xt)F sv.t22 EEE ccrc@ SK DETAIL'M I CPH.5(EAST SIDE)LE4 4 ccw t son I I CPH.3 (IIKST SIOK)SICFC CCVtll 5 cctc lrhl CPT CPx CCW I SO.S kl CP CPX Ccr tean Ccwttl.5 CCW 50.4 CCWTS040 SCW 154 51 CPx CPx CCWI I'I 1 CCWIE5.4 CCw 2 44'n I . Vi PASS E4 avllse awlsho Sew 1 scale CCV I SCS 44 CCW144 14 h CCWQI.S F5$$ '5 ~wt5CS47 CC'vtss f S(C DLTCTL 'll CCWHI TT . I e FPDM PEHKTRATIOH I'o I Y(Hf f IQ ~ COOLING SVPPI.Y HEADERS PASS A I I'CH511 14 $ (E TRIS DWG Cld, Gld OSOutcf TO ftOOR CCWSSI 15 r MAIM S'f(AM LrrCUIIC COIL avwhs CCTC141 1 DASS'tr awtls.c I I PEHETRATIOM at tw44 CCW141.4 CCW'Ic1 "5 CCWOS lt Tla Ixxr FRCPTEC DC5CAtaxtost CCW %41 CCWISS 11 fccx DEECH cctswtsllaatf XD 14ca COT 14'S. W a Tts.>> Irtcwt r V(HT awtch 4 4$ EKI'VIPERS CTIHCZSIIDC UFTC) 4 l 4'VTO Tt SEE, MOTE 'A'K ccvlcs.lc as tahh 11 alctls'Ts r TOIT lo AIID Stole PEHETRATIOH IIOTG n CCHSSS.T ccscrcc *>> cva COOLING COILS I'WACH CCV144 ccvtch ts CCw114 tl, CCHN!01t 514ECIEW ccwtct CCH 141.11 54 lt CPCS 11 CIDLDIO SIPPLY IEIANX 54( txtt TM)4 Dwca HAD& UI4IOUE fOR UNIT K AHD SVP 125t CCW444 14 ccwtcces '&dllakc C4 HIT@ lh' NOTE'A'e )5 ( ISIH FIN(t taDOI OCX 11 awttch OEEC tvtEVKXIS Ctrtlt.c DCD Caaati.l C 5135 13 RP/.7 CIVIC t CO/<M GEIVEEC DPTIT Nto(tS, Cert Sh'll WA VA 3(E IXS OVC.S.+CIIL PASS Et'q CCHIST 11 I ttctc/ICA Krc NUVSCRS OSC54 ~ 8m+ lo AHD fdbal PEHKTRATKSI KId,ot NIRNIKud COOLING CODE Ctrtst Ctrlct 14 ON.Y ISWOLC VALVC NUHSCTIS C f II) CCCCiW CODLING 5VTPLY HKIDO(LS(E CPH (IYPICAL) Pal\ E4 V~V (TYPICA;) f 14 C SFTCAN ON TH15 OICWSCC. 5EC SCTARATK VALVt'NTSClAICA tWS OVG SIKO44LFIILHIS CPH X Ih'S.KD5 tfe'I)K~K)FVXR(TVP)~ . - ~f Sl ccvcTE-~s Ctralc Tj CCEESTC IS ~TDC cttaEY. DCC. TNID Dstci ethel (stoa WEOEE catv) Ir U51 FOR EOUCVlLENT CC51CH (TSCRI NUICOER5. 2 TACV NVS44ETC5 ICCOFICO FOR l Iha5$ SKTAT ISOPIC INdgcbcStct15~~>C msr 45 sGAST Sco(S rrr 'A Ctrlcl '1 Pass'A CCV151 C DRawscc vsc As follows t ccr 519-25 ccL CCR ~ 4 IWTSY SEC() ccwssP11 CCW 144 1 CCV TSC ~ \1 YAC lect t.wswrrrthw rxi@'Ov-tcc. t awlla 11 avt444 CCP141-4 APPEARS 45: NSWTOSW Sa I tott CCECSI'4 Tt h CCM~)O((4$T DO() ~ ~ cpx cpx Ctwlct.t CCVTQ 11 ~sec rect Coocsw ccrcr lcc CCM 432(wist $ 104) CF 1-433 (HEST SIDE) l awtcho CCS141.0 CPT. CPT ccwtcl ~ 14 5. 445TRIWCCNY Hoor vasK NARr 3N Ltcc SIZE AT as 4th Ec Ccr tel ~ TS Nrs Nor SHoww ow otawscc CPN Ks(EAST SIDE) 4 ocacw r awt44 4 vALvc ICENTSFIOATKEN Lht1 CPH:Q(W(ST SIDE) f CCSW)I GAST 110K) CCVSES SC 451 S K ETCH CFSNK(LSEO FUNK SIK AT axles at tchh 14 Ctt SCS N CCW th DCWIVEO er ADOCWC TO AER ttocclwtocEHcrcwFM NV CKO-I EADT(SC>> j ccM 453(N(sTSIDK) CCW 5 cs Tc COOUNG WATER 'D.4'(XAPOMKNT AT COH'TAIMM'KNT PEN\TRA'flONS CPH KEE34,4T SKE'fCH 'H 5 SKETCH SFE DETAIL'M I ~ TllUSCCNY NUSCOCR 5INEXC WCIXSCVI FOR TXXSLC WCCSASC 'OI CCV525.25 0 CI&tf (PEHC.T RATION Mt 5 5 6 5 EAST SIDE AS SHOWN) COMPONENT COOLING WATER COOLING WATEIL 'M.S'OMPONENT CCWSts TC (NV~O.S) )VEST AT COHTAIHMEMT PKMf TRATIOHS Mt 'L 6, D,K516,34,47 (PENETRATION th'5 5 C 4 WEST 'SIDE SIMILIAR) AT CONTAIHMENT PENETRATIOHS HTC.3X'l+T(L19 5'K t 141 OCIIOTTSH Statvs stf fxlh'nf.ttc.c Ilt'O e 45014 CPH C 5 THRU CFN.TS 114'O 6 FSDII ASC RECIECpl ~ SKIMNIER FCAN Toe FROM CFN 3 e 4 TKPII CPH.YK 0)'10 6 fSDMAQ. RKGIRC/Hs SKIMNER F1EE54 eeeXF aCOO i-.,r Ore. AT EAST SIDE or COHTAINMKNT 'SEE SKKTOI '0-4 ~ ($ .6))IXIXI CPH-1$ COHTAIXNKNT SEE AT EAST SIDE OF SK'D 4 SEE SKETCH 'D-4'~o AT WEST SIDE Cr CONTAINMEMT . Oct~ CPTI-Tt Al SKE SKETCH '0-4 WKU SIDE or COHTAIHMKNT CPM 5 SEE SK'Dvr CPM.1 tll IK'W C PH.S SKIS CPN.15 4'$ K SK'H.S ~ CK SK'(hc'h14K SX'H-5 CS'HK CPM-9 SKK SK CPH-5 04 CPH 5K Sr.'H-5 6 Ctti 1$ SK sx'M S CPH-Tl S(K SK'M 5 SKE CPH:5 cx NI.S SE'K CP'H 4 SK'NS CPM-3) SK SK'4-$ 'KECPH.41 SK 'N-O'(K SK 'N'5'PH-CC S(E CK'HC'(K SK'J-) 5-CS' I FDR RCVISSSN CKDOCPTXSI SCK 'I 5OWISTK IKVI5ION RECORD fOI 2145 DRCWTNC lhg lh'g t I,. .I fg
    I rg l t l HEH wccvc ~ sw rwMT w sw acrEM CECcrv EvM SErvs CME M 0 arM vw
    ~ cvrvs wv w ~ M % w Mvrcw 44 r ~ r rwc % EvCC ~ ~ ~ Mvrv scavrsas Ts M cvcw HEEM Ih', I I I I ss svEEV <<sr ao svEvc cav L ,. M Erraw arMHE\ Ts srv M 0 w w wlmw vsa wsM I 23 colotc/rear L 4 I I I I. .ITWTIAHA~ SOCHNIAH SMOTTWCOX Cc ~ ,I I I .I- l I CMSEECW (IHAU) C. COOK IIVCtEAR FIANT Ssssace TI-'-, l l I I L. 4 C~2 c I I s~l coFE(poNENF UNIT NQ I coollNG AM APZRYURE +~ ~ ~ KL, CIEL0 l CARDc TANK A'REA PIP'E TUNNEL IM Ih'l' CWC tcCC 2-51358-14 QSE err racer r 3J TO e CROM PKHKTRATeM c sr kvaHab1e Og) 4 4 CXLWIG SVPPLY NEAOKR SK OWG 5155,AI6 ELSSI 0 tttcttoc lowtw NÃcrx wtoacwar " ~ HN TCWW lhpeeaze C~g I O 180278-I I T 4 t l p I l 'I ~ V fC ~ I Q v' err L I C I D R . j F I 0 I 8 I " J I K= I l I )4 ( MY ttcre erat re Vtlrr \ ~ SOHP~ F crore )pat 2 vocrrac PRSN 645 DC CAY eAF'ICS Sauotc GENERAL NCQES II Ic .3 cturcoL eaeec viue ~4~>>t~~ .Osi Cdutaoc YA'eu Vcut 554 Cxrf Dred.t Site)4 ~ C/t HCASCR scc De/ce et Sess,evs 4 r LfGE)4D FROM LETfr))IH LINK l Ea f ROM PRESSURIZER STEAM AT BEAVH. INL(T SLE r) RSO SOO/ ir tro)de SF ')D scute CA Erc rr o 4 MAIMPCOW SPACE .BLE DWG 512SA,KIT. 0 45 ofc Av I)IG. Z-S)294 ICJ t er)oee crete ¹ tav45 vtirr cf. OttceaOFSSF)QOFS OCC 'SOS DID 20) SOI 302 nC; 3 3 <<CN 304 SCI 30 VNI 345 Oy.) 307 Cll 303 fatera ( o g 42 N D \ ee AU)C FLOW CDR VALVE, IHS RUMC)47, saeaPLSNG 4 P)PL MAT'I'RIAL, t aors CD)rt I tt "47 \' r ~ 7 AND OTHER SYMC)OL5 I'ST DSX 7 Tcern crrrtrtccxctoe<OOL r FRDM PRESSURIZER A YOC OOLANT DSI ~ta~vturdcct 4 ~ o 6 XPLAINED 0)4 1)4)5 DV/G.) UOUID SPACE SEZ D7IG 5)2'LA,J/te). j 500 DFFA el YA 5ltorr4 r/7. ill\cur rdsrsN. ~ tu509gl HSOSC I't 5IS)A ~ T/5 I-Hs 20 oo.- V er AND 50+ MA'IN, HV)aaJER 14RV 104 ~ RC)NSS)vut I f RCTS Ue)ITirt PRCSSLRFZEFC ~ r. n 4 re' 4 4 4 er CODES. SE'I DWG5.12 5K)3 C I pRcssvtrtcrt reit) 't*ua 1/cr rf IZ 504) HSX RCS)CC CAFA44Oil RCLett 5etdA A/r. VfNT SEC Oac) fte)547 h,g O era~ 3'.4 4 N r re 5YtdBOLS sec leo e dirae, Ol C g 8 5 2 2 ~ 104 Cc )4 GC tcfr4 te dorv CO)deegS e)OSOaivr FRC 1 4 NC'iree ACiD)'VAP
    h. 51 DFL rfr ce Q OVICK D)5COI)MSCT SC-. -rc. 1. t CDVPUN(t C.
    NRV JPZ io CVADVCFl'7 703) '3'7)t~ SEE CF/r4 rt'elstct Ve 2 FROM H01 LEG NSX ~ /C. 5 esse al/4 ~ ~ICOSCS70 etu)Stot 4 70- )e OAIFISRAYFCFF) c 45 veer 7 llrK el 7 it.ctor 5 ~ )4OOD i LOOP 3. Sf.E 102 FC Set~ FROrt re CVCS 5'CVCS HOLDUP TAF)FC Svsttea OCO lt Hs'toO ltresldd Cf > l n f)FVG.5)ZD, )Ul HS DECAY COIL HOLD VP TAS)FC YCNTS'CE Deice rt 3)ste)C/3 DFF4 rdsraoitvd 4 r. ai Iv OW 8Y WESTINGHNJSE NRV 103, vcuYSOC DNG IlrseSt.evd 1PJ b+O.Six) 4 rauttvtur to t r 1 2 'SX FCOF4 \ttut RCSFH veal OQTIIe dr l A7 5rotaoc tav)4 3 as I SC)s CVC5 )FOLD Vee 'CANxvcuT SEO Dwo rc 454332 4'ROFS'4 ALL PIPIHG TO BE= ~ FIX)M HOT LEG" 103 vCut CCE Owd lt sisde Ce/7 1 It Sr32ef/C) ~etus e'r'3 EXCEPT As i)OTCD LOOP 1. SEE . NR(:IO (fritALLLeuc sites) 3 (rYR) lterstld~ ~rsusst7 ALL RQVIPMEHT SXL XI f3WG. 5128, E/5 t)5X CAPPED~ ))FFROST l45,5ff t)resorexyd e SVS tlt Sl'C erat 101 FC I/redeeeedd ct c) OJ lrr THE(9)IT PRECIXDESIGHATION SA FOR 8 ACH Core)tear)eedt tc rt)lsd oo~ )t 7 tl7 LOOP IDCttt)FeCAT)0HrrVNSISEIC IS ACCUMVLATOR SAMPLES, AIL SOS VASKO
    • cxdoL 445'rcs 45'AC t agtc Or
    '7 VUNLESS CST)IEIC err)5>> 44OTTF 0 BCE. PWG. 514S, P/4 dYQvi rl Fere CAPPE 0 'Yrxt SCC Yrcd CFF44 Ark )i tourt liat treed 5 rte\Nvee ar. C reed Care C! } e>tue.e/4 ~ Isx ISX 1st )SX t lt'5432 4 4'I)'SPAt) Ceas CO)INECTIO)4~ AU'f0MAT)C vdl 3 tfetut to eaeastel e. ~ 1 2 4 V4'PLANT AIR st E DWG IZ 5IZOSCtr 7 AG ANALYZER r 'til"r)led OCC D45eroud)DD,X /C. 2'DRAFF4 5 5C V. 477 DWG.I slal FL/3 1'H)TROFFCH(ZERO CAS) (IC)DROof rr 4 Drtfe 1 H CP)1 81 CR044 LITDPWH Ate FCR Aru,SCS d SIC Dree.s))4)CLCIS Pert csee Le)4 F.C. FA . LINE AT D'IMD1. "pw rent.e45 7 Fi . 4445 FL. B.IV 53750 Secret ev DNS k'cata OUTLET.SEC DHCL FL fL. 587" 0 e 4/7 c/dCCrd I 5 2 rt)CSAFLJO It-NSI)7 KVRTI et'll 4 EL. 6)2'4 ()RV ~ 2 L L)RY 3 'IRT 9 'f t Tlat edavroee rs eocuf icA L Yo Sactcu 144 ev oua rsidl var Ytd *Rc ere eaa 7 ~ vasa F 51st, r FC' 1 -5437, J/Es /OL)TOE)A e~Ztr 7(IKLYZEQ. 1 TO%.LJICTTS t44 NOTE)t)I)5 'PORT)GROT I)V/G 4)ID)Cat ES \ CF Q CNCLO'bED SAMPLE SIA)4 )Z; OC 82) CALI. VALVRa csY J)rv. LIAHVCActuef I) L ~ CKFCA tell Ccnreo NS S)f 30l
    s. NS l47
    ~ I SHC REE) E44VIP LCFM AL). SOLQIDID VALV4.5 5'f (r~ fo )HUH)T 1 Ngtel 7HIS PORTIOHOF E))VG 4NDICATES SHARED EOUIP.LOCATET) )34UN)t I reteoc tec)crf veaLVK ccned zvwtrto rc s "~eve cccc vvec'ee\ rx .TO Sa)APLIMG s)HK. 4 FFCPJeroaecv'octcaeao v ~CA/FPEf) 4 0 )C ' 04 I J SERT)))SCROG SK'Idc DD 4 eacearoca Yeea Pere~ rc)eeaeaaa)C cxr)Next SFA4vc /lsx.303.3041Nsx )01.)03 /Osr-300 v vlu\ ic ald CSSX M)) I IZ r e OFC'/ Fg C~ / )4 N ra\ NNa ~ 4 ~ 4 ta Nsf ~ IOZ~ e/Zto VOLUME COHTCOL NSS) C fCDH VOIUHI CDHTXD1. TANK Sf f. DWG.Z SI29,)'I/4 isr-I TANK Gas SPACE SCC ~ 43 Q)N4. 5)39 A, H/3 ISC ~ 2 Hauo or Rat 0 va v ~4 /4 Drrr/OC Saeeett Roeee I)X 3 (Dcutrtlcatrou NDNOXRS I IV TT) BLD& EXHAIJST ~ radc OANFFsc at /- )c )sr< fg' O'Rv sod VCHTSYSTE)FUSEE~ DWEASICB.C/8 ~ f. irx, ~ IOVCerf ~.SCC LDNLY lxwovc YALE ta/VSCRS APPCAR Ou THIS DRAW)NC. SCE scpARATE vatvc IDENT)FIOAT)ON Htx l IICR 10 4 t 6 Cr)ro I X)0 t45.I 53 Lettt NS)dt~ Ivr) 5rdtaeea'5 idvuiti Dtc ~e~lgfg LIST FOR EOVIYALCHT DCSICN lHCR) NVHOCRS. 2, tAO rarudcas LoctficD FDR rOS NPx rod Nsrt)< Drraweeo vsc As FDLLows tac N 4: 2 Nsw.veos"w IVER 105 107 I I FI OFI Ai'PEARS AS. NSWOSW IOS 3 0 SrestRVHCNT ROOf VALVE HARK I teVS NO'f SHOWN OH DFIAW)NCISCC ', v'tvtoo- Ust) 'EEVER-RESIDUAL g . ' 'E TO FA)).ED FUEL NSrtt IOO NSFI') uclrd vALVE IOCNtefrcatroN DERrvco ot ADD)uc 'to 5 WDETECTOR SCE DAG Nllll REKXEHKiEL . 4~aeter araotv't ctree 8NB, N/2 tit SCS2 reSTRveecHT tarudcR: fOR srrctl ~ pv)3cvt roe $ $ NSIN fc)4 ocxrxc d/pvcsc:vx)p5!local)4 u le dc fNQSO 7 t/4 OOTOS)96 i' IOC llKCClllllSIAIVS SCL cosctoctvf cocuv6 )FF Icv)sscu Rccrxeo foR ttcs leer>> Isx IRV-303 C.CI ~ lr /',, WATIC(TYP) Sff 9HG. 5) 35, )I) I eg ulr)4 ulr'll itrf R) 4 I 55 36 at)49)rr \ CP / 7 9 de rc 7 ac Jracr Fera 4 Freorcd I FRON I".R-"SfDU/rrl- FF4 'I tl e r/Fr)I )A Cor ED ~ersrd) FOR RCVIS)OH DCSC)crtr)H SCI F.C HEAT g~cgQI'F//5(. HEAT EXCflANGER. SEE DWG.E- $ )4 J, P)/5 I IRV 304 .reaeiuSrSO IZt~ 4 p4PNL ~l q e SS.TVSIHCV I I 1 I I )NSTALLCD Wliul 'tarVNO scitvratc Rcvlsrou RCCORD IOR t)CS DRAW)HO ( I ef ee Net ;sex CIC-SCX )4 I FA ~ 4 I I I ~tsctY. 4rtaccs3 CSCOK FOKS 4 eu Nree e ar 4 reK44 Heter eter, M 4 eeve 4NNAWAN eeue Neet ~ ~ ee eee ~e ~ ~NS)50 10 ~N)rit I I cr cL PC(5UCJ2CI I I ~4 erat elr ~ N Nrt. 44 ee>> N ~ ~ 4 41 I/ 3 I Cx Llaui0 'I 1 1 va aaie 44 I 2 NP I VI I 1 D. IIPI sa)IIXE TfSsfl I I , raver~ NNFN v av ~ NNN erNN lr\Aeeirt crit ee Nee eeaeee ~ I I I 3 3 4 Z I NSrdd et etu NNverNNKW t HCI .NSZ I (aP.W) I ~ ui L e Z I r SV ICD er I 'I I)'4 D.D. TvsiNC Ccx/IPOHIHT CCOLI)rc tt I t IS <~ti T 6 ISPSXL INDIANA4 eeecH)OAH cxxctxrc cxx Z 'Z )CATER.SIC DNC SISS.F/9 I Vt YOLVVE l ~FFSFSI DONALD C. COOK t- I 2 Z Z ) tg 1 I e eer OC r 0 SAMPLE trfssCL ~ crocuac NVCCIAR FIANT 3 I+ AMFLE HEAT (QP.1 3 SFKNcac 49 I cc 1 I EXCNANSCR /Nr)r)d F LOW IA RAM I (COIL TYPE) NUCLEAR SAMPLING ~ I I I 1 TYPICAL) ac 501 II )Ytos Derarv eeaueccr) Dias. SFAI.I/scItrrf4 I ) UNIT NR Z XC)r r QFS D TI Eg YUEE eer = I CC ar
Retrieved from "https://kanterella.com/w/index.php?title=ML17334B150&oldid=2425052"