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Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2
	ML20055E810
Person / Time
Site:	Quad Cities
Issue date:	07/01/1990
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20055E807	List: ML20055E810;
References
	PROC-900701, NUDOCS 9007120354
	Download: ML20055E810 (369)
	v • d • e

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,# a lh-f"c Revision 3 A l July 1,:1990

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1 1-te j i-t PUNP AND VALVE

= INSERVICE TESTING PLAN FOR Quad Cities Nuclear Power Station, Unit 1-Cornnercial Service Date ~ Pebruary 18, 1973 Quad Cities Nuclear Power Station, Unit 2,

. Commercial 8ervice Dates March 10, 1973

' P . O ~. Box 216 Cordova, IL 61242 COMMONWEALTH EDISON COMPANY

.P. O. Box 767 Chicago, Illinois 60690

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Quid Citics Nue1Cor P:wcr Stcticn, Unito 1 cnd 2 l TNSERVICE TESTTNG PLAN INFoitMATION COMMON TO PUMPS AND VALVES a i l'__ D i. SEYISION

SUMMARY

SIERT l

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I Effective Page(s) Rev.

l INFOR2!ATICW COMMON TO 4-PUNPS AND VALVES i to V 3 1-1 to 1-2 3 2-1 to 2-12 3 s PUMPS

1-1 to 1-15 3 2-1 to 2-3 3 >

3-1 to 3-15 3

.{ ) 4-1 to 4-2 3 5-1 to 5-2 3 VALVER l

1-1 to 1-62 3 l

2-1 to 2-16 3 i

3-1 to 3-6 3 l

4-1 to 4-223 3 ;

5-1 to 5-2 3 6-1 to 6-2 3 l

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ii Qund CitiO3 Nucicor Ptwor' Station, Unito 1 cnd 2

, , INSERVICE TESTING PLAN ljfF',RMATION COMMON TO PUMPS AND VALVES

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\ TABLE OF CONTENTS ,

Section' Descriotion Pace IMPORMATION COMMON TO PUMPS AND VALVES 1.0 Introduction and Plan Description 1-1 2.0 Piping and Instrumentation Diagrams 2-1 PUMPS l 1.0 Relief Requests 1-1 2.0 Technical Approach and Positions 2-1 {

3.0 Program Listing 3-1 i I

4.0 Augmented Inservice Testing Requirendets 4-1 5.0 References 5-1 YALVES

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-() 1.0 Relief Requests 1-1 2.0 Cold Shutdown Justifications 2-1 '

3.0- Technical Approach and Positions 3-1 4.0 Program Listing 4-1 i

5.0 Augmented Inservice Testing Requirements 5-1 L 6.0 References 6-1 i

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Qutd CitiC3 Nuc1Cor P wsr StStion, Unito 1 cnd 2 INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES p)

(j LIST OF TABLES (Sheet 1 of Pl Table Descriotion Pace COMMON INFORMATION TO PUMPS AND VALVES 2.0-1 List of Unit 1 Piping and Instrumentation 2-3 Diagrams (P& ids, sorted by System name) 2.0-2 List of Unit 2 Piping and Instrumentation 2-5 Diagrams (P& ids, sorted by System name) !

2.0-3 List of Unit 1 Piping and Instrumentation 2-7 Diagrams (P& ids, sorted by P&ID number) i i

2.0-4 List of Unit 2 Piping and Instrumentation 2-10 Diagrams (P& ids, sorted by P&ID number)

PUMPS

() 1.0-1 2.0-1 Relief Request Summaries Technical Approach and Position Summaries 1-4 2 3.0-1 Unit 1 Pump Listing 3-4 3.0-2 Unit 2 Pump Listing. 3-10 i

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-Qund Citico Nucloor P:wcr Station, Unito 1 cnd 2 ,

INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES

) LIST OF TABLIS (Sheet 2 of 2)

Table Descrietion Page VALVES 1.0-1 Relief Request Summaries 1-4 ,

1 2.0-1 Cold Shutdown Justification Summaries 2-4 3.0-1 Technical Approach and Position Summaries 3-3 4.0-1 Unit i Valve Listing (sorted by P&ID) 4-6 4.0-2 Unit 2 Valve Listing (sorted by P&ID) 4-92 4.1-1 Unit i Valve Listing (sorted by <alve number) 4-175 4.1-2 Unit 2 Valve Listing (sorted by valve number) 4-190 4.2-1 ACTUATOR Abbreviation Listing 4-205 (the type of actuator used to operate the valve, e.g., MO: motor operated) 4.2-2 BODY STYLE Abbreviation Listing 4-207 *

(the type of valve body, e.g., GAT:

gate valve) 4.2-3 FUNCTION CATEGORY Abbreviation Listing 4-211 (the category corresponding to the function the valve must fulfill, see IWV-2200) 4.2-4 NORMAL POSITION Abbreviation Listing 4-213 (the position of the valve during normal plant operation. For safety systems, the valve position will frequently be different during system operation) 4.2-5 TEST FREQUENCY Abbreviation Listing 4-216 (the test frequency, e.g.,

quarterly is abbreviated M3: once every three (3) months.)

4.2-6 TEST TYPE Abbreviation Listing 4-223 (the type of test to be performed, e.g., AT-01: Category & Iest number

-21, or a containment isolation

\- valve seat leakage test)

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l Qund Citico Nucloor Powar Staticn, Unito 1 and 2 INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES

'l I!!TRODUCTION AND PLAN DESCRIPTION D

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1 Qur.d citico NucicCr P wbr Stction, Unito 1 cnd 2 INSERVICE TESTING PLAN l INFORMATION COMMON TO PUMPS AND VALVES

1.0 INTRODUCTION

AND PLAN DESCRIPTION l

This Inservice Testing Plan for ISI Class 1, 1 3, and NC pumps and valves was developed in accordance with the inservice testing requirements ASME Section XI,

, Subsections IWP and IWV. Where hese requirements are determined to be impractical, specific relief is requested. 1 All references to the " Code" in this Plan are taken from the i ACME' Boiler and Pressure Vessel Code,Section XI, Division I, " Rules for Inservice Inspection of Nuclear Power Plant

Components", 1980 Edition through and including the Winter 1980 Addenda. 3 This Inservice Testing Program will be effective from July -

1, 1990 through and including o Unit 1 - February 17, 1993, and o Unit 2 - March 9, 1993. !

This Plan is one of two Plans that cover Inservice Inspection and Inservice Testing at Quad Cities Nuclear Power Station. The other Plan covers: ,

o Inservice Inspection (Non-Destructive Examination) '

The key features of this Plan are; Relief Requests, Cold

Shutdown Justifications,. Technical Approach and Positions, '

i and the Pump and Valve Listings that define the scope of the I

Inservice Testing Program. Administration, implementation procedures, and other details of the Inservice Testing Program are addressed in documents available at Quad Cities. ,

Administrative procedures, surveillance testing procedures, l reference value test results, and other records required to .

i define and execute the Inservice Testing Program are all retained at Quad Cities.

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INSERVICE TESTING PLAN j INFORMATION COMMON TO PUMPS AND VALVES l 2.0 PIPING AND INSTRUMENTATION DIAGRAMS-The Quad Cities Nuclear Power Station Piping and )

Instrumentation Diagrams (P& ids) clearly define the scope of the ISI Class 1, 2, 3, and NC Inservice Testing Program.

Systems or portions of systems subject to the requirements of ASME Section XI have been identified on the P& ids. ,

The Legend and Symbols drawings (P&ID M-12 Sheets 1 and 2) '

provided with the P& ids explains the ISI Class.ifications.

Lists of P& ids for Quad Cities Nuclear Power Station, Unit 1 have been included in Table 2.0-1 (sorted by System name) and Table 2.0-3 (sorted by P&ID number) . Lists of P& ids for Quad Cities Nuclear Power Station, Unit 2 have been included in Table 2.0-2 (sorted by System name) and Table 2.0-4 (sorted by P&ID number). ,

The ISI boundaries on the P& ids are limited to safety related systems which contain water, steam, or radioactive materials in accordance with Regulatory Guide 1.26.

The P& ids submitted with this Inservice Testing Plan are For Information only. A controlled set of P& ids will be maintained at Quad Cities. The controlled set of P& ids are as-built P& ids to ensure that all system additions and

! modifications are properly addressed by the IST Program.

Some pumps and valves that perform a safety function are not ,

included in the ISI class 1, 2, or 3 boundaries marked on 4 the P& ids (e.g., diesel fuel oil systems). These pumps and valves have been included in the IST Program in recognition of their importance to safety. These pumps and valves are noted as ISI Class "NC", meaning not classified ISI class 1, 2, or 3, but safety related.

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j QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 !

INSERVICE TESTING PIAN !

{ INFORMATION COMMON TO PUMPS AND VALVES i i

Table 2.0-1 LIST OF UNIT 1 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by System name) t I

P&ID System Name Number ATMOSPHERIC CONTAINMENT ATMOSP9ERE DILUTION SYSTEM M-0642-1 CLEAN AND CONTAMINATED CONDENSATE M-0058-3 CONTAINMENT AIR SAMPLING M-1057.

CONTAINMENT ATMOSPHERE MONITOR SYSTEM M-0641-1 CONTROL ROD DRIVE HYDRAULIC M-0041-1 CONTROL ROOM HVAC M-1551 CORE SPRAY M-0036 HIGH PRESSURE COOLANT INJECTION M-0046 I

' INSTRUMENT AIR PIPING M-0024-2 L. P. SERVICE WATER PIPING M-0022-1 LIQUID SAMPLING M-1056-1 MAIN STEAM PIPING M-0013-1 M-0013-2 OFF GAS M-0042-1

,i PRESSURE SUPPRESSION M-0034-1 REACTOR BUILDING CI4 SED COOLING WATER M-0033 REACTOR BUILDING EQUIPMENT DRAINS (INCLS. 1/2 DG START AIR) M-0043 REACTOR CORE ISOLATION COOLING M-0050 REACTOR FEED P! PING M-0015 Revision 3 PUMPS AND VALVES 2-3

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LIST OF UNIT 1 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids) '

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n9 P&ID '

jl-.. , System Name Number i

I f REACTOR REC'.RCULATION PIPING M-0035-1 4 [g M-0035-2 ,

REACTOR FATER CLEAN-UP e M-0047

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RESIDU'.L HEAT REMOVAL, PUMP DISCHARGE JD HEAT EXCHANGER M-0037 t i

' RESIDUAL HEAT REMOVAL, RHRSW PUMPS AND RHR HEAT EXCHANGER M-0039-2 i ' RESIDUAL HEAT REMOVAL; SUCTION, CONTAINMENT SPRAY, AND LPCI M-0039-1

. SERVICE.> AIR PIPING (INCLUDES DIESEL GENERATOR STARTING AIR) M-0025 '

f M-0044 t- . STANDBY GAS TREATMENT

,j STANDBY LIQUID CONTROL M-0040 .,

TURBINE AND DIESEL OIL PIPING M-0029 ,

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (v' INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES ,

Table 2.0-2 j LIST OF UNIT 2 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by system name) l P&ID System Name Number q l

.M-0029 ATMOSPHERE CONTAINMENT ATMOSPHERE DILUTION M-0642-2 CLEAN & CONTAMINATED CONDENSATE PIPING M-0058-3 CONTAINMENT AIR SAMPLING SYSTEM M-1062 CONTAINMENT' ATMOSPHERE MONITOR M-0641-2 CONTROL ROD DRIVE HYDRAULIC M-0083-1 I'

CONTROL ROOM HVAC .M-1551 CORE SPRAY M-0078 HPCI (HIGH PRESSURE COOLANT INJECTION) M-0087 INSTRUMENT AIR PIPING M-0071-2 LIQUID SAMPLING SYSTEM M-1061-1 MAIN STEAM M-0060-1 '

M-0060-2 NUCLEAR BOILER & REAdroR RECIRCULATION M-0077-1 M-0077-2 OFFGAS PIPNG M-0084-1 PRESSURE SUPPRESSION M-0076 RCIC PIPING-(REACTOR CORE ISOLATION COOLING) M-0089 REACTOR BUILDING' COOLING WATER M-0075

! REACTOR BUILDING EQUIPMENT DRAINS M-0085 Revision 3 PUMPS AND VALVES 2-5 l

'f QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2-

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INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES Table 2.0-2 l

LIST OF UNIT 2 INSERVICE INSPECTION l

l. PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by System name)

P&ID System Name Number REACTOR FEED PIPING M-0062 REACTOR WATER CLEANiP M-0088 RHRS PIPING (RESIDUiL HEAT REMOVAL SYSTEM) M-0079 '

M-0081-1 ,

M-0081-2 ;

i. SERVICE AIR PIPING (AND DIESEL STARTING AIR) M-0072 SERVICE WATER M-0069-1 i L

STANDBY GAS TREATMENT M-0044 ;

STANDBY LIQUID CONTROL M-0082 1

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' QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

's INFORMATION COMMON TO PUMPS AND VALVES l Table 2.0-3 LIST OF UNIT 1 INSERVICE INSPECTION '

l- PIPING AND INSTRUMENTATION-DIAGRAMS (P& ids)

(sorted by P&ID Number)

P&ID Number System Name M-0013-1 MAIN STEAM PIPING

'Rev : AF M-0013-2 MAIN STEAM PIPING Rev : MN M-0015 REACTOR TEED PIPING Rsv : AH' M-0022-1 L. P. SERVICE WATER PIPING Rev : BF

\ M-0024-2 INSYRUMENT AIR PIPING k Rev : AH .,

M-0025' SERVICE AIR PIPING (INCLUDES DIESEL GENERATOR STARTING AIR) :>

Rev : RR M-0029 TURBINE AND DIESEL OIL PIPING '

Rev : AD M-0033 REACTOR BUILDING CLOSED COOLING WATER Rev : U M-0034-1 PRESSURE SUPPRESSION Rev : AH '

M-0035-1 REACTOR R2CIRCUIATION PIPING Rev : AE M-0035-2 REACTOR RECIRCULATION PIPING ;

Rev : W M-0036 CORE SPRAY Rev : AG O

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

..( INSERVICE TESTING PIAN N INFORMATION COMMON '"O PUMPS AND VALVES ,

Table 2.0-3 .

LIST OF UNIT 1 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by P&ID Number) r P&ID Number System Name M-0037 RESIDUAT, HEAT REMOVAL, PUMP DISCHARGE AND HEAT EXCHANGER Rev : AC-M-0039-1 RESIDUAL HEAT REMOVAL; SUCTION, CONTAINMENT SPRAY, AND LPCI Rev : AN M-0039-2 RESIDUAL HEAT REMOVAL, RHRSW PUMPS AND RHR HEAT EXCHANGER Rev : AK M-0040 STANDB'l LIQUID CONTROL Rev : AF '

O M-0041-1 CONTROL ROD DRIVE HYDRAULIC Rev : AK M-0042-1 OFF GAS Rev : AE M-0043 REACTOR BUILDING EQUIPMENT DRAINS (INCLS. 1/2 DG START AIR)

Rev i AK M-0044 STANDBY GAS TREATMENT Rev : Z M-0046 HIGH PRESSURE COOLANT INJECTION Rev : AR M-0047 REACTOR WATER CLEAN-UP Rev : AG M-0050 REACTOR CORE ISOLATION COOLING Rev : AG M-0058-3 CLEAN AND CONTAMINATED CONDENSATE Rev : AB

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

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'/3 INFORMATION COMMON TO PUMPS AND VALVES Table 2.0-3 LIST OF UNIT 1 INSERVICE TNSPECTION '

PIPING AND INSTRUMENTATION DITSRAMS (P& ids)

(sorted by P&ID Ntunber) ;

i

.l P&ID i Number System Name' j 1

l M-0641-1 CONTAINMENT ATMOSPHERE MONITOR SYSTEM Rev U l M-0642-1 ATMOSPHERIC CONTAINMENT ATMOSPHERE DILUTION SYSTEM

-Rev : T M-1056-1 LIQUID SAMPLING '

Rev : 8 M-1057 CONTAINMENT AIR SAMPLING

, Rev : 4 M-1551 CONTROL ROOM HVAC

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i o QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN l

<O INFORMATION COMMON TO PUMPS AND VALVES C Table 2.0-4 LIST OF UNIT 2 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

O' (sorted by P&ID Number)

P&ID Number System Name o

I M-0029 7 Rev : AD M-0044 STANDBY GAS TREATMENT '

Rev : Z l g M-0058-3 CLEAN & CONTAMINATED CONDENSATE PIPING ;

'Rev : AB ;

M-0060-1 MAIN STEAM !

Rev : AF t :

M-0060-2 MAIN STEAM Rev : MN M-0062 REACTOR FEED PIPING Rev : AH M-0069-1 SERVICE WATER

.g Rev : AZ L' SERVICE WATER ,

L Rev : BF j L

i M-0071-2 INSTRUMENT AIR PIPING L Rev : AH l:

M-0072 SERVICE AIR PIPING (AND DIESEL F'.ARTING AIR)

Rev : RR M-0075 REACTOR BUILDING COOLING WATER Rev : U M-0076-l' PRESSURE SUPPRESSION l Rev :.AH M-0077-1 NUCLEAR BOILER & REACTOR RECIRCULATION l l

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 O INSERVICE TESTING PLAN INFORMATION COMMON TO PUMPS AND VALVES L't) '

l Table 2.0-4 i LIST OF UNIT 2 INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by P&ID Number)

P&ID

. Number System Name Rev : AE -

M-0077-2 NUCLEAR BOILER & REACTOR RECIRCULATION Rev : W M-0078' CORE SPRAY Rev : AG M-0079 RHRS PIPING (RESIDUAL HEAT REMOVAL SYSTEM)

Rev : AC M-0081-1 RHRS PIPING (RESIDUAL HEAT REMOVAL SYSTEM)

'( Rev : AN M-0081-2 .RHRS PIPING (RESIDUAL HEAT REMOVAL SYSTEM) ;

Rev : AK M-0082 STANDBY LIQUID CONTROL Rev : AF M-0083-1 CONTROL ROD DRIVE HYDRAULIC Rev : AK

'M-0084-1 OFFGAS PIPNG Rev : AE M-0085 REACTOR BUILDING EQUIPMENT DRAINS Rev : AK M-0087 HPCI (HIGH PRESSURE COOLANT INJECTION)

Rev : AN HPCI (HIGH PRESSURE COOLANT INJECTION)

Rev : AR M-0088 REACTOR WATER CLEANUP Rev : AG

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 O INSERVICE TESTING PLAN LI INFORMATION COMMON To PUMPS AND VALVES Table 2.0-4 -

LIST OF UNIT 2-INSERVICE INSPECTION PIPING AND INSTRUMENTATION DIAGRAMS (P& ids)

(sorted by P&ID Number)

P&ID ,

Number System Name M-0089 RCIC PIPING (REACTOR CORE ISOLATION COOLING) .:

Rev : AG '

M-0641-2 CONTAINMENT ATMOSPNERE MONITOR Rev U M-0642-2 ATMOSPHERE CONTAINMENT ATMOSPHERE DILUTION Rev :,T l M-1061-1 LIQUID SAMPLING SYSTEM !

Rev : 8 V M-1062' CONTAINMENT AIR SAMPLING SYSTEM -

Rev : 4 M-1551 -CONTROL ROOM HVAC !

Rev : 7 '

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INSERVICE TESTING PLAN - PUMPS

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PUMP RELIEF REQUESTS 1'

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Qutd Cition Nuclcor P wor Station, Unito 1 & 2 INSERVICE TESTING PLAN - PUMPS

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N]J 1.0 RELIEF REQUESTS Pursuant to 10CFR50.55a (g) (5) (iv), Relief Requests have been included when specific requirements in the Code are considered impractical. The enclosed Relief Requests are subject to change throughout the inspection interval. If testing requirements are determined to be impractical during 1 the course of the interval, additional or modified. Relief Requests will be submitted in accordance with 10CFR50.55a (g) (4) (iv) and NRC Gensric Letter 89-04. y i

J Relief Request numbers are in RP-NNA format, where; RP Relief Request for Pump Inservice Testing (RV - Valve Inservice Testing)

NN: 00 for general issues I The first two characters of the Equipment Piece Number (system identifier) is used for system -

dependent Relief Requests.

o l 10 Residual Heat Removal i 11 Standby Liquid Control l

O 13 14 Reactor Core Isolation Cooling Core Spray 23 High Pressure Coolant Injection 39 Service Water 52 Diesel Oil A: A unique, sequential, alphabetical character (e.g., RP-00A would address pump vibration velocity, RP-11A would address Standby Liquid ,

control pump differential pressure) '

A summary of Relief Requests is provided in Table 1.0-1.

Each summary includes:

1. TYPE : 1 Pre-approved per Generic Letter 89-04, Attachment 1, Positions 2 Alternate approach to Generic Letter 89-04, Attachment 1, Positions (with maintenance, etc.

background information to substantiate our position) 3 Relief Requests that were docketed prior to April 3, 1989 (that do not

/' conflict with a Generic Letter 89-( 04, Attachment 1, Position)

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. cued Citico Nucloor P0 wor Station, Unito 1 & 2 INSERVICE TESTING PLAN - PUMPS

}N 4 Relief Requests requiring approval

' l\ ,) (ASME Class 1, 2, and 3 components) 5 Relief Requests for non-ASME Class 1, 2, or 3 components (that have been provided for information only)

2. POSITION: The applicable position from Generic Letter 89-04, Attachment l'

3. CODE : The impractical Code requirement (s)

ARTICLE 4.-

SUMMARY

A brief summary of-the Relief Request Grandfathered Relief Resuests New Humber Pg. No. Old Number Pg. No.

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I QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 q INSERVICE TESTING PLAN - PUMPS Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST

SUMMARY

RP-00A TYPE 4, Tables IWP-3100-1 and -2, IWP-4510 Vibration velocity will be used to assess pump mechanical degradation in lieu of vibration amplitude. Vibration velocity is more sensitive than vibration amplitude to all modes of pump degradation. >

RP-00B TYPE 4, IWP-3100, Table IWP-3100-1 Bearing temperature is not a particularly useful test. Pump j bearing vibration tests will detect mechanical problems well before bearing temperature begins to increase. ;

.I

RP-00C TYPE 4, IWP-3230(c)

, A new reference value test will not necessarily be l established atter an operability evaluation. Better t trending can be performed by retaining the original reference value test.

RP-11A TYPE 4, IWP-3100, Table IWP-3100-1, IWP-3110 :

Differntial pressure and suction pressure cannot'be measured for the Standby Liquid Control pumps. All evaluations of pump performance will be based on discharge pressure.- Since these pumps are positive displacement pumps, discharge pressure is just as sensitive to change as differsitial pressure.

RP-52A TYPE 5, IWP-3100, Table IWP-3100-1, IWP-3110 -

Differntial pressure and suction pressure cannot be measured for the Diesel Fttel Oil Transfer pumps. All evaluations of pump performance will be based on discharge pressure. Since-these pumps are positive displacerent pumps, discharge pressure is just as sensitive to change as differential pressure.

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i Qund Citico Nucloor Pow 0r Station, Unito 1 & 2 INSERVICE TESTING PLAN - PUMPS

/~N - RELIEF REODEST NUMBERt RP-001 (Sheet 1 of 2)

.b COMPONENT IDENTIFICATION CODE PUMP NUMBER CIARE DRAWING NUMBER COORDINATE

<All pumps > 1, 2,

&3 FUNCTION (8) *

'All. pumps in the IST Plan are affected. These pumps are required to perform a specific function in shutting down the reactor or mitigating the consequences of an accident and are provided with an emergency power source.

r CODE REOUIREMENT Table IWP-3100-1, " Inservice Test Quantities," Vibration amplitude (V)

Table IWP-3100-2, " Allowable Ranges of Test Quantities,"

Acceptable, Alert Range, and Required Action g- Range for vibration amplitude i

s' Article IWP-4510, " Vibration Amplitude," The Code requires vibration measurements to be recorded and analyzed based on displacement in mils (thousandths of an inch).

BASIS FOR RELIEF ;

Low amplitude, high frequency vibration due to misalignment, imbalance, or bearing wear is difficult to detect via vibration !

l amplitude measurements when pump speed is grmater than or equal ;

p to 600 RPM.

Vibration velocity measurements are much more sansitive to small changes that art indicative of developing mechanical problems.

Vibration velocity is a far more informative reading because it ;

accounts for both displacement and frequency range. A vibration '

monitoring program based on. velocity is more comprehensive than i L that required by the code.

The specific limits assigned to the HPCI and RHRSW pumps are based on extensive experience with these pumps and the inherent '

high vibration levels associated with pumps of this design. The HPCI pump impellers have been modified to reduce vibration levels I

(~50%) yet absolute levels remain high. The elimination of I absolute Alert Range (0.325 ips) and Required Action Range (0.700 O ips) will be compensated'for by reducing the multiplier for the Required Action Range from 6 to 2.5.

Revision 3 PUMPS 1-6 l

Qund Citio3 Nucloor Pow 3r Station, Units 1 & 2 ,

INSERVICE TESTING PLAN - PUMPS l RELIEF REOUEST NRKBER: RP-001 (Sheet 2 of 21 J

PROPOSED ALTERNATE TESTING i

Pump vibration measurements will be taken in vibration velocity (inches per second) if the pump speed is greater than or equal to 600 RPM. The allowable ranges of vibration-velocity will be based on Table 1. ,

Table 1 ,

ALLOWABLE RANGE 8 OF VIBRATION VELOCITY Acceptable Required ,

Pump Type Range Alert Range Action Range Centrifugal with 5 2 . 5 V, > 2.5 V

$ 6. 0 V, and > 6.0 V, speed 2 600 RPM (except HPCI and but not, but not RHRSW) > 0.325 ips > 0.700 ips Centrifugal with 5 1. 5 V, > 1. 5 V, and > 2.5 V, speed 2 600 RPM $ 2.5 V, (HPCI and RHRSW) __

( Reciprocating 5 2. 5 V, > 2. 5 V, and > 6.0 V, 5 6. 0 V, Gear 5 2.5 V, > 2. 5 V, and > 6.0 V,

$ 6. 0 V, V,: vibration reference value ips: inches per second mils: thousandths of an inch (applies to low speed pumps only)

NOTE: There are no safety related centrifugal pumps that operate at speeds < 600 RPM at Quad Cities. There are no safety related vertical line shaft pumps at Quad Cities.

APPLICABLE TIME PERIOD Rslief is requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 4 Relief Request (requires NRC approval).

O Revision 3 PUMPS 1-7

V Qutd citico Nuclcor P wor Station, Units 1 & 2

. INSERVICE TESTING PLAN - PUMPS RELIEF REOUEST NUMBERI RP-005 (Sheet 1 of 2) !

l-COMPONENT IDENTIFICATION 1

L CODE PUMP NUMBER CLASS DRAWING NUMBER COORDINATE !

<All pumps > 1, '

2, j

&3 l l

FUNCTION (S) i K All pumps in the IST Plan are affected. These pumps are required I to perform a specific function in shutting down the reactor or mitigating the consequences of an accident and are provided with an emergency power source.

CODE REOUIREMENT IWP-3100, " Inservice Test Procedure," The test quantities shown in Table IWP-3100-1 shall be measured or observed and recorded. j i'

Table IWP-3100-1, " Inservice Test Quantities," Bearing -

Temperature (T 3 ) shall be measured.

BASIS FOR RELIEF !

Pump bearing vibration monitoring can be used to detect: worn bearings, misalignment of bearings, a change in the balance of

' rotating parts, a change in hydraulic forces, and general pump integrity. Quarterly pump bearing vibration measurements, (

. combined with an observation of lubricant level / pressure,-are i mere sensitive than bearing temperature measurements to the' types of problems that may be exhibited by increased bearing ,

-temperature. Since bearing vibration monitoring is more sensitive and is performed more frequently, there is no need to meas:2re bearing temperature. ;

Revision 3 PUMPS 1-8 i

. Quad Citico Nucicar Powcr, Station, Unito 1 & 2 I INSERVICE TESTING PLAN - PUMPS

/^ RELIEF REQUEST NUMBERt RP-005 (Sh9 et 2 of 2)

' (s BASIS FOR RELIEF (Continued) ,

Given controlled environmental conditions, bearing temperature measurements may be capable of detecting pump degradation, but theLfollowing problems exist in a power plant setting:

1. Many bearings are lubricated by the pumped fluid; and '

the temperature of the pumped fluid will change depending on the season.

'2. 'Long run times to stabilize bearing temperature are not practical for the HPCI pump'(during.the summer, the Suppression Pool temperature may approach the 95 'F ,

limit because the HPCI turbine exhaust is directed to

.the Suppression Pool). j~

L L These environmental condition variables make it extremely difficult, if not impossible, to evaluate bearing temperature test results.

Bearing temperature measurements could potentially L'e misinterpreted and they-do not provide any additicnal information

()

concerning the pump's condition. This inservice test quantity is impractical to measure and evaluate.

PROPOSED ALTERNATE TESTING In comparison to the other tests used to detect mechanical and hydraulic change, a bearing temperature test does not provide additional, meaningful information. Vitration velocity I measurements are much more sensitive t pump degradation. No p alternate testing is appropriate.

l-l APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

l RELIEF REQUEST TYPE

[

This is a Type 4 Relief Request (requires NRC approval).

Revision 3 PUMPS 1-9

=

a Quad Citioc Nucitar Pawar Station, Unito 1 & 2

/ INSERVICE TESTING PLAN - PUMPS RELIEF REQUEST MUMEERt RP-00C (Sheet 1 of 2) 00MPGNENT IDENTIFIchTION 4 a

CODE PUMP NUMBER CLASS DB& WING RUMBER COORDINATE

<All pumps > 1, 2,

&3 FUNCTION (S)

All pumps in the IST Plan are affected. These pumps are required to perform a specific function in shutting down the reactor or mitigating the consequences of an accident and are provided with an emergency power source.

CODE REQUIREMENT IWP-3230(c), " Corrective Action," Corrective action may be .

an analysis to demonstrate that the condition !

does not impair pump operability and that the pump will fulfill its function. After such analysis is performed, a new set of reference values shall be established.

BASIS FOR RELIEF The Code requirement to establish a new reference value based on a test result that is in the Alert Range or Required Action Range is not a good testing practice. With a new reference value based on a test result that represents degraded performance, additional degradation may take place before meaningful corrective action is instituted.

Acceptance criteria based on the initial reference value, with owner-specified limits substantiated by an operability analysis, provides better test control because the initial reference test remains part of the test record ahd trend. Any additional degradation (and total degradation) will be easier to identify if the initial reference value is. retained.. .(i.e., If the ranges in Table IWP-3100-2 cannot be met, IWP-3210 allows the owner to establish appropriate limits in lieu of the standard Code ranges.

The option to establish new limits, substantiated by an operability analysis, is available to the Station. In this situation, establishing new reference values would not be

. prudent.).

Revision 3 PUMPS 1-10

Quzd Citico' Nuclear Pow r Station, Unita 1 & 2

. INSERVICE TESTING PLAN - PUMEE l l-p RELIEF REODEST NUMBERt RP-00C (Sheet 2 of 2)

G/ ^

PROPOSED ALTERNATE TESTING L 1

As described in the Basis for Relief, the original reference o value may be retained. A pump operability analysis will be performed to substantiate any owner specified limits.- The test l frequency will be doubled in accordance with.IWP-3230(a), until i

three (3) additional test show no further evidence of degradation. If three (3) additional' tests show no further I evidence of degradation, the test frequency will be returned to l quarterly. The rate of degradation will be watched carefully to ensure that the pump'will remain operable. Replacement or repair,-per IWP-3111,'will be performed, as necessary.

APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.-

RELIEF REQUEST TYPE l

This is a Type 4 Relief Request (requires NRC approval).

Revision 3 PUMPS 1-11

p +

l

' ' l Quad Citios Nucloar:Powcr Station, Units 1 &2 .

INSERVICE TESTING PLAN - PUMPS l y RELIEF REQUEST NUMBERS RP-111'(Sheet 1 of 2) 1 l

f l COMPCNENT IDENTIFICATIOli l CODE l PUMP NUMBER CLASS DRAWING NU)iBIB COORDINATE Unit 1' 1102A 2 M-0040 D-7. -1 1102B 2 M-0040 E-7 i Unit 2 1102A 2 M-0082 D-7 i

.1102B 2 M-0082 E-7 )

FUNCTION (8) 7 The Standby Liquid Control (SBLC) pumps are used to inject poison (sodium pentaborate) into the reactor vessel, if the Control Rod Drive Hydraulic system fails. The' poison injected by the'SBLC system'will absorb neutrons and control reactivity.

(

CODE REQUIREMERf '

IWP-3100, " Inservice Test Procedure," The test quantities shown in Table IWP-3100-1 shall be measured or observed and recorded.

Table IWP-3100-1, " Inservice Test Quantities," Inlet Pressure ,

(P and,) during the test.shall.be measured before Differential pump startup pressure *

(dP) shall be measured. ,

IWP-3110, " Reference. Values," Differential' Pressure-will be duplicated during subsequent inservice testing.

BASIS FOR RELIEF i<

The SBLC inservice test is conducted using the SBLC Test Tank (1104 0 B-7), rather than the Standby Liquid Control Tank (1103 0 i

A-10). The Test Tank is filled at the start of the test (minimum- I water level 16"), and the Test Tank level remains virtually !

constant throughout the inservice test. !

i Inlet pressure instrumentation was not installed for the.SBLC pumps. Inlet pressure before the test (P ib) could be calculated i based on Test Tank level, but this calculated hydrostatic I pressure is meaningless once the pump starts. I Revision 3 PUMPS 1-12

l Qutd Citico Nucloor Powcr Station,-Unito 1 & 2.

INSERVICE TESTING PLAN - PUMPS RELIEF REODEST NUMBERI RP-111 (Sheet 2 of 2)

BASIS FOR RELIEP (cont'd)

L The SBLC pumps are positive displacement pumps. The performance of the'SBLC: pumps is not sensitive to changes in pump inlet pressure.. SBIC discharge pressure can be substituted for differential pressure, and the ability to detect changes in i hydraulic performance _.will'not be.affected. -;

PROPOSED ALTERNATE TESTING f Discharge pressure will be substituted for differential pressure in any test requirements or acceptance criteria for the SBLC pumps, ll APPLTCABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIEP REQUEST TYPE

) This'is a Type 4 Relief Request (requires NRC approval). ,

i i

i O t Revision 3 PUMPS 1-13

Quad Cities Nuclear Power Station, Unita 1 & 2 INSERVICE TESTING PLAN - PUMPS RELIEF REOUEST NUMBER: RP-521 (Sheet 1 of 2)-

COMPONENT IDENTIFICATION CODE PUMP NUMBER CLASS DRAWING NUMBER COORPINATE Unit 1 5203 NC M-0029 F-3 Unit 1/2 5203-1/2 NC M-0029 F-3 Unit 2 5203 NC M-0029 F-3 FUNCTION (B)

The Diesel Fuel Oil Transfer pumps are used to keep the Diesel Fuel Oil Day Tank (5202) full while the diesel generator is required to generate emergency power.

CODE REOUIREMENT IWP-3100, " Inservice Test Procedure," The test quantities shown in Table'IWP-3100-1 shall be measured or observed and recorded.

.l

, -Table IWP-3100-1, " Inservice Test Quantities," Inlet Pressure (Pi ) shall be measured before pump startup and during the test. Differential pressure (dP) shall be measured.

IWP-3110, " Reference Values," Differential Pressure will be duplicated during subsequent s inservice testing.

~

BASIS FOR RELIEF Inlet pressure instrumentation was not installed for the Diesel Fuel Oil Transfer pumps. The Diesel Fuel Oil Storage Tanks (5201) are located below the Diesel ~ Fuel Oil Transfer pumps.

Therefore, the suction pressure will be negative, and the suction pressure before the test will vary from test-to-test depending on the tank level. Positive displacement, gear. pumps are used in this application because they do not require positive suction head for proper operation. Diesel Fuel 011 Transfer pump discharge pressure can be substituted for differential presnure,

-and the ability to detect cha:.ges in hydraulic performance will not be affected.

Revision 3 PUMPS j 1-14 l

^^

Quad cities NuclGar Powar Station,.Unita 1 &-2 INSERVICE TESTING PLAN - PUMPS

[ A. RELIEF REOUEST NUMBER: RP-521 (Sheet 2 of 2) )

,Q. .

PROPOSED ALTERNATE TESTING j i

! Discharge pressure will be substituted for differential pressure .l l

in'any test requirements or acceptance criteria for the Diesel '

Fuel'011 Transfer pumps. l l

l APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIEF REOUEST TYPE This is a-Type 5 Relief Request.

O .I

.i L

I t

l~

L O

Revision 3 PUMPS l 1-15 l.... . . . . .

L, ,

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'1 . ,,

J

l Quad lCitic3 Nuclear Powcr Station,lJnits'1:and 2 1

INSERVICE' TESTING PLAN - P3MPS: ,

t

' ! :' . (

if i ., . 'x. 1- ,

L ,,

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f PUMP TECHNICAL APPRonCH ANDLPOSITIONS

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i i

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.l q.

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d Revision 3 PUMPS 2-1

m -

ik m,'

w Quad cition Nucloer Power Station, Unita 1 and 2

fpo ,

M ERVICE TESTING PIAN - PUMPS

_, ti- '

2.0- TECHNICAL APPROACH AND POSITIQN ghi When the requirements of the Code-are not easily Pl 'ly interpreted, Quad, Cities has reviewed g>neral licensing and ti o regulatory requirements, and industry practice to determine a practical method of implementing each Code requirement.

3;s . The. Technical Approach and Position documents in this

~1 section of the Plan have been provided to clarify Quad cities' implementation of the Code.

,w -A summary of Technical Approach and-Positions is provided f ,

6 Table 2. ~ -1.

3v.

l

',Q a 1

1 i z _1 n

+

O Revision 3 PUMPS 2-2

)

f -

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Quad: Citioo'Nucloar'Pov0rl Station, Unita 1 and.2 INSERVICE TESTING PLAN - PUMPS

(~' 4 Table 2.0-1 l D TECEMICAL APPROACH AND POSITION SUMMARIES i

, j

, ' TECHNICAL 'l r APPROACH l; -AND

'l POSITION NUMBER GENERAL DEOCRIPTION

]

TP-00A . Lubrication levels will be observed during each )

inservice test for pumps that are designed such- 1 y that levels can be verified. The core spray (14 01)l, RHR (1002), and the D/G fuel oil transfer (5203)? pumps are lubricated by pump flowage and,'

l thus, lubricant level or pressure measurements.are not relevant.

l' 9

C I

i j;',

A _.

J 6

O Revision 3 PUMPS 2-3

.Qund'Citios Nuclea'r Pow 3r Station,. Units 1 and 2

' INSERVICE' TESTING PLAN - PUMPS ,

k

.p , . ?

l,

.i PUMP PROGRAM LISTING l 'R i

L i

i i

Revision 3 PUMPS 3-1

l 1

, , -t i

. Quad'Citioc Nuclear Powsr Station, Units 1 cnd 2 INSERVICE TESTING PLAN - PUMPS' 3' O _ PROGRAM LISTING ,

!- Table 3.0-1, " Pump Listing"-lists all pumps included in the t i Quad Cities Nuclear Power. Station,' Unit-1 IST Program.

r L Table 3.0-2,>" Pump Listing" lists all pumps included in the b Quad. Cities Nuclear Power Station, Unit 2 IST. Program..

L.

.The data contained in this Table identifies all pumps subject to inservice testing,.the inservice test quantities,- -i i .the inservice testing frequency, and any applicable remarks.

The column. headings in the Table are listed and explained :

below: J j o Pump Number The unique number that identifies the pump. The Pump ;

J

~

Listing is sorted by Pump Number.

l r ,

o Pump Name a I

The common name for the pump.

o IST Class ;

' The ISI' classification as.shown on the Piping and' i Instrumentation Diagram (P&ID)..

O- o P&ID Number '

The P&ID number. If.the F-4p appears on multiple P& ids,'the' primary P&ID will be listed.

o. Dwg Coor The coordinate location (e.g., D-5) on the P&ID where' the pump. appears.

+- o Test Type Test type is an abbreviation for the Inservice Test

. Quantities listed in Table IWP-3100-1, a

o Relief Request If a Relief Request is included in Section 1.0, the Relief Request number will appear.

Revision 3 PUMPS 3 -> 2 l

_i_ o_ _ _ _ _ ._ _ . - -

' , 1

., \

" ~

LQuadcCitico Nuclcar/ Pow 3r-Station, Units 1 and 2 LINSERVICE TESTING PLAN ~~ PLM :

li '

' ' },

,; ;k_ o . Test Freq' i a ~

' .The test frequency associated with each test type will-be.specified, o Technica1' Approach ar.G Position i

When appropriate,, clarifying remarks concerning Quad ,

Cities' technical approach and position have been- !

'A included in Section 2.0. ;

i r

Q -

i e

- Revision 3 PUMPS 3-3 A -.y___m_ = ___._-a -

a__- -.___g g n - - - -m- --e- y --

ry 7!; , , t >

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Qund Citico Nucioar Pow *.,r Station, Unita 1 and 2 ,

[', l7NSERVICE TESTING PLAN - PUMPS j On Table-3.0-1L (s~ 1 -

UNIT 1. PUMP LISTIMG q

i l ... - PUMP. P&ID DWG IST TEST TEST RELIEF TECHNICAL y '" - NUMBER. NUMBER COORD CLASS' TYPE FREQ. REQUEST . POSITION g . ______ ______ _____ _____ ____ . __ _______ _________

E '

U <

3903 M-0022 A-10 3 . INLET QTLY '

' PRESSURE g,. .-m DIFFERNTL

.i PRESSURE-FLOW RATE I' VIBRATION RP-00A BEARING RP-00B.

TEMPERATURE FUNCTION: ' DIESEL' GENERATOR COOLING WATER 1/ - 403 .M-0022 A-10 2 INLET QTLY PRESSURE-DIFFERNTL 'I PRESSURE FLOW.

E . RATE j i

VIBRATION RP-00A

' i

BEARING RP-00B TEMPERATURE e FUNCTION: ' DIESEL GENERATOR.' COOLING WATER l 5203 'M-0029 F-3 NC INLET QTLY RP-52A PRESSURE i DIFFERNTL. RP-52A PRESSURE l FLOW l, RATE VIBRATION RP-00A l BEARING RP-00B l TEMPERATURE FUNCTION: DIESEL GENERATOR FUEL OIL TRANSFER Revision 3 PUMPS 3-4

+

y i

- . 2 ,

1; !.

l

, :. n i

,i :

P!l. a 'Qutd Cities Nuclear Powar Stationf.Unito l'and 2 ,

j g INSERVICE TESTING PLAN - PUMPS- .

y...

< 1 .

s [, Table 3~0-1 .

(< - ; - '

UNIT 1 PUNP LISTING

' TEST RELIEF - TECHNICAL

?l-

' PUMP' P&ID DWG IST TEST

' NUMBER NUMBER COORD CLASS TYPE FREQ' REQUEST POSITION y" , -1/2-5203 M-0029 F-3 NC INLET QTLY RP-52A-PRESSURE ,

DIFFERNTL- RP-52A PRESSURE e i

FLOW. !

RATE

" VIBPATION RP-00A

, BEARING -RP-005 TEMPERATURE .

. FUNC7 ION: DIESEL GENERATOR' FUEL ~ OIL. TRANSFER-L :______________.._________________________________________________

1A-1401 M-0036-E-9 2 INLET- -QTLY PRESSURE DIFFERNTL PRESSURE

- ((

FLOW ._

L <

RATE VIBRATION RP-00A 'l

(; BEARING RP-00B .

TEMPERATURE FUNCTION: CORE SPRAY. PUMP 1A 1B-1401 M-0036 E-6 2 INLET QTLY PRESSURE DIFFERNTL PRESSURE ll FLOW RATE VIBRATION RP-00A BEARING RP-00B 1

TEMPERATURE FUNCTION: CORE SPRAY PUMP 1B

.o '

Revision 3 PUMPS 3-5 -

4

.------.--A-.-._----------------

, , - - - + ,e,-,. ,-v-r w s-- ,

my , , y ~ y:u - -- -- ' ~

---7 - - ~ ~ - -- - - - ^ ' -

y;;, ;; m; mi +.. !H ,

?iM ;,. -

i Qutd Citioc Nucicar-.Powar Station, Units 1 and 2'

' INSERVICE TESTING ' PLAN - PUMPS . -1 N, :. '

Table 3.0-1, i

[L-(

L UNIT 1 PUMP LISTING o . PUMP . P&ID DWG. IST TEST TEST- RELIEF TECHNICAL-

"", NUMBER: NUMBER COORD CLASS TYPE 1FREQ REQUEST POSITION ,

p o .____. _ _ _ _ _ . . ___ __... .... ___. .. ____ ...._____

l 1A-1001~ M-0037L B-4 -2' . INLET QTLY PRESSURE .F lc DIFFERNTL i a '

PRESSURE a.

o FLOW

. RATE .,

t J VIBRATION RP-00A, m,

p, BEARING 'RP-00B- ,i ,

j/' TEMPERATURE

/. FUNCTION:- RHR PUMP 1A 1B-1001' M-0037 E-4 2 INLET QTLY' l ,'

3 PRESSURE t

4 g >

DIFFERNTL i5 PRESSURE- -i l

FLOW RATE i i y _

. VIBRATION RP-00A 7

h BEARING = RP-00B u TEMPERATURE- '!

L

-FUNCTION: RHR PUMP 1B Gs

~

L , t

1C-1001 M-0037 B-8 2 INLET QTLY PRESSURE DIFFERNTL r ir: +- PRESSURE FLOW RATE 40 i B~' VIBRATION RP-00A

$ u'J >

RP-00B BEARING .i TEMPERATURE :

J! FUNCTION: RHR PUMP 1C o

u. ,

L Revision 3 PUMPS

t. 3 3-6 L: g .

o .i-l>

1 3-1-

io- --- - . - - , - . _ ..__-_ _ - - - _ _ _ _ _ - - - - _ - _ . _

.o gj.3. r q._ ,

1 rg

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l f Quad: Citici Nuclear Pow 3r Station; Unito 1 and 2.. q k,k.ai;' ' INSERVICE TESTING' PLAN - PUMPS '! 1

, 1

,Jn.m.,Y L;I'~ Table ~3.0-1 =l A.,/c. .

UNIT 1 PUMP LISTING 'l

, . PUMP P&ID DWG IST TEST TEST.: RELIEF TECHNICAL -l

,FREQ:' REQUEST POSITION'

-NUMBER- NUMBER COORD . CLASS TYPE-.

1D-1001- M-0037- E-8 2 INLET- 'QTLY- f

~

n PRESSURE e

'g'*' +

DIFFERNTL f

-PRESSURE N FLOW-RATE 7 p.<

VIBRATION RP-00A 1 s

BEARING- RP-00B TEMPERATURE FUNCTION: RHR PUMP 1D

'1' __ _____________________________________________________________ 3 '

, 1001-65A M-0039 F 3 INLET . QTLY-PRESSURE

\. '

s S ; DIFFERNTL LI i.-.. .

PRESSURE- ,

t 7

< at s FLOW RATE ,

a ;

VIBRATION RP 2 00A BEARING RP-00B TEMPERATURE q RHR SERVICE WATER A PUMP' FUNCTION:

. g" 1001-65B M-0039 F -4 3 INLET QTLY t'

PRESSURE DIFFERNTL

' PRESSURE -

FLOW

> RATE li- 1 l' VIBRATION RP-00A

, BEARING RP-00B L,,, TEMPERATURE IL J FUNCTION: RHR SERVICE WATER B PUMP l'

i

( - Revision 3 PUMPS l' 3-7 I

i

+, d . .,4 . _ . . . , , _ . . - . ,.

(.!pt ' .!

pg)

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&' E :Qund Citica' Nuclear. Power Station, Unito 1 and 2 a RfC ' # d ,

INSERVICE TESTING' PLAN - PUMPS.

I h

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'M Table 13.0-1:

g; QJ e UNIT 1 PUMP LISTING 1

w PUMP. P&ID DWG IST TEST TEST RELIEF -TECHNICAL .

o

. NUMBER -NUMBER ~ COORD: CLASS TYPE FREQ: REQUEST: POSITION g b -. , ' y ,

opp '

1001-65C M-0039 F-7 3 INLET QTLY 6- ! PRESSURE.

DIFFERNTL~

-5' PRESSURE' r

u- , ;

l FLOW

"' RATE.

3, VIBRATION RP-00A

F 4 1 ' e RP-00B BEARING TEMPERATURE FUNCTION: . RHR SERVICE WATER C PUMP ;

t '/l)I 1001-65D M-0039. F-4 3 INLET QTLY ;

m/ W PRESSURE-a A' [' i DIFFERNTL l

... sh PRESSURE H FI4W -

RATE-VIBRATION- 'RP-00A.

.s

$' BEARING. RP-00B TEMPERATURE

. FUNCTION: RHR SERVICE WATER D PUMP

. 1A-1102. M-0040- D-7 2 INLET . QTLY RP-11A' l'i PRESSURE-DIFFERNTL RP-11A 'l PRESSURE l 7

'.. FI4W

'

RATE i l

VIBRATION RP-11B- -

1 BEARING RP-00B TEMPERATURE

. FUNCTION: STANDBY LIQUID CONTROL PUMP 1A l N.. _____ ____ __ . ________ _____ ___ . ___ _____________ ___

1-p Revision 3 PUMPS l

, 3-8 ,

l 9

l r 4

f. i i

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, - 1 ;

Qutd Citico Nucicar Pow 3r StatiCn,'Unito 1 and'2 '

i INSERVICE TESTING PLAN PUMPS-I

.t r pp '

4_ m Table 3.0-1 i .

, UNIT 1 PUMP LISTING

.' PUMP! P&ID DWG IST TEST TEST RELIEF TECHNICAL l s

, NUMBER NUMBER COORD- CLASS TYPE FREQ REQUEST ~ POSITION

1B-1102 M-0040 E-7 2 INLET QTLY RP-11A -

4 g , ,

PRESSURE DIFFERNTL RP-11A. _,

. PRESSURE i

_. U.

FLOW RATE ,

v. >

VIBRATION RP-11B i BEARING RP-00B TEMPERATURE FUNCTION: STANDBY LIQUID.. CONTROL PUMP 1B y 2302 M-0046 A-4 2 SPEED QTLY' INLET. i PRESSURE (

t.

. .DIFFERNTL l

b. - PRESSURE; 1.

l> FLOW <

RATE i

-1 VIBRATION RP-00A-l BEARING RP-00B TEMPERATURE FUNCTION: HIGH PRESSURE' COOLANT INJECTION ' -

1 1-1302 M-0050 A-4 2 SPEED QTLY I

INLET ;

l PRESSURE

DIFFERNTL L PRESSURE 1 FIDH RATE VIBRATION RP-00A BEARING RP-00B' L

u TEMPERATURE FUNCTION: REACTOR CORE ISOLATION COOLING PUMP Revision 3 PUMPS 3

,, 3-9 r i e

I - '

, +. . - . . . ..- . . .. .

' h'.g._-.-

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i

p. ,

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<Qutd citioc Nuclear Powar< Station, Unito'1 and 2 j -; ,

,n , ' INSERVICE TESTING PLAN - PUMPS p -

Tabl'e 3.0 /.fN, s

/ W UNIT 2 PUMP LISTING l~ .

'; PUMP .,_LP&ID . DWG IST TEST . TEST RELIEF TECHNICAIi o NUMBER" NUMBER COORD CLASS TYPE. FREQ' REQUEST POSITION ;

L"s i .i 2-5203' M-0029. F-3 NC-INLET.

QTLY RP-52A' s I

, PRESSURE- ,

j DIFFERNTL' 'RP-52A PRESSURE-l;

, t' !

L '

' FLOW 4 ,

f RATE VIBRATION RP-00A i BEARING RP-00B !

TEMPERATURE -i

' FUNCTION: -DIESEL GENERATOR FUEL OIL TRANSFER L'il 2-3903 M-0069 A-10 3 INLET QTLY l

PRESSURE <

q DIFFERNTL 3 PRESSURE .J 3

c plow- Ji

(, , RATE.' i VIBRATION RP-00A BEARING RP-00B~

i' TEMPERATURE G' ' FUNCTION: DIESEL GENERATOR COOLING WATER it j F INLET

. 2A-1401- M-0078 E-9 2 QTLY

," PRESSURE m DIFFERNTL PRESSURE ,

9;d FLOW

RATE i

VIBRATION RP-00A y ;

BEARING RP-00B TEMPERATURE gs - FUNCTION: CORE SPRAY PUMP'2A Revision 3 PUMPS

.3. _

3-10

7 _.

1 ti t ' o

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. + t Qutd Citios' Nuclear Pow 3r' Station, Unito 1.and 2 ]'

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NUMBER - NUMBER COORD CLASS TYPE FREQ REQUEST POSITION

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2B-1401 M-0078; E-6 2 INLET QTLY PRESSURE DIFFERNTL !

PRESSURE

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. TEMPERATURE CORE SPRAY PUMPc2B.

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i' 2A-1001 M-0079 B-4 2 INLET QTLY PRESSURE l.

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PRESSURE. i FLOW RATE VIBRATION RP-00A .'

'llEARING RP-00B

'rEMPERATURE FUNCTION: RHR PUMP 20 Revision 3 PUMPS 3-11

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______ ,---___ _____ _ ___ -___ ___. --____. -________ y 2A-1102 M-0082 D-7 2. INLET QTLY RP-11A. .. i PRESSURE:

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2-1302 ,M-0069 A-4; 2 SPEED QTLY .., .

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FUNCTION: REACTOR CORE ISOLATION COOLING. PUMP'_____,_

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The following' augmented inservice testing requirements are '

being implemented at Quad. Cities Nuclear Power Station:

a '. . Diesel Generator Fuel' Oil Transfer does not perform a safety function. The Diesel Fuel 011' Transfer pump has.been included in the IST Plan at' the NRC's request. .

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b. Reactor Core Isolation Cooling (RCIC).does not 1 perform a safety function, and no credit'is taken for the RCIC system in any UFSAR accident >

analyses. The RCIC pump has been included in the-IST Plan at the NRC's request.

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EThe references used to develop this~ Inservice Testing i

' Program for pumps include: ,

a. ASME. Boiler and Pressure Vessel Code,Section XI, Division I, " Inservice Inspection of Nuclear 1 , Power Plant Components", the 1980 Edition through1 .

Y and-including the Winter'.1980 Addenda, i L .- .

b. .:ASME/ ANSI OM, " Operation and: Maintenance of if Nuclear Power' Plants", including the 1990 Addenda. f u

I Part 6 ' " Inservice Testing'of Pumps in' Light-Water Reactor Power Plants" c.- Final Safety Analysis Report, Update 8, Quad Cities Nuclear Power. Station, Units 1 and 2 *

, d. Technical Specifications, Amendment 119, Quad- !

Cities Nuclear Power Station, Units 1 and 2 I '

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/' 1.0 RELIEF._REQUTATS b] Pursuant to 13CFR50.55a (g) (5) (iv), Relief Requests have been included when specific requirements in the code are i considered impractical. The enclosed Relief Requests are subject to change thr69ghout the inspection interval. If testing requirements are determined to be impractical during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10CFR50.55a (g) (4) (iv) and NRC Generic Letter 89-04. '

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Relief Request numbers are in RV-NNA format, where; RV Relie0 Request for Valve Inservice Testing (RP - Pump Inservice Testing)

NN: 00 for general issues

---.......................--..........--.......-- l The first two characters of the Equipment Piece .

Nuaber:(system identifier} is used for system dependent Relief Requests.

02 Reactor Recirculation and Nuclear Boiler l 03 Control Rod Drive f 07 Traversing In-Core Probe ,

N-s 10 Residual Heat Removal ,

11 Standby Liquid Control ,

12 Reactor Water Cleanup 13 Reactor Core Isolation Cooling 14 Core Spray 16 Containment and Pressure Suppression 19 Puel Pool Cooling and Cleanup 20 Radwaste (Drywell Sump) 23 High Pressure Coolant Injection 24 Containment Atmosphere Monitor 25 Atmosphdric Containment Atmosphere Dilution 30 Main Steam 32 Reactor Feedwater 33 Condensate (Clean and Contaminated) 37 Reactor Building Closed Cooling Water 39 Service Water 41 Fire Protection (Turbine snd Diesel Oil) 46 Service Air 47 Instrument Air I 48 Reactor Building Equipment Drains i 49 Turbine Building Equipment Drains ,

52 Diesel Oil l 54 Off Gas 57 Heating and Ventilating (Reactor Building Ventilation)

( 75 89 Standby Gas Treatment High Radiation Sampling System Revision 3 VALVES 1-2 l 1

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( ,f A A unique, sequential, alphabetical character (e.g., RV-00A would address Primary Containment Isolation Valves, RV-00D would address the '

reference value stroke time concept, and RV-14A would address the Core Spray check valves inside ,

containment) l A summary of Relief Requests is provided in Table 1.0-1.

Each summary includes )

1. TYPE : 1 Pre-approved per Generic Letter 89- )

04, Attachment 1, Positions 2 Alternate approach to Generic-Letter 89-04, Attachment 1, Positions (with maintenance, etc.

background information to substantiate our position)

G Relief Requests that were docketed prior to April 3, 1989 (that do not conflict with a Generic Letter 89-04, Attachment 1, Position) ,

i 4 Relief Requests requiring approval O (ASME Class 1, 2, and 3 components) 5 Relief Requests for non-ASME Class 1, 2, or 3 components (that have j been provided for information only)

2. POSITION: The applicable position from Generic '

Letter 89-04, Attachment 1

?. CODE : The impractical Code requirement (s)

ARTICLE

4.

SUMMARY

A brief summary of the Relief Request

" Grandfathered" Relief Recuegig

/~x Revision 3 VALVES 1-3

j, QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST

SUMMARY

I RV-00A TYPE 1, POSITION 10, IWV-3421 through 3425, and 3427(b) i Primary containment Isolation Valve Local Leak Rate Tests Will Be Conducted in Accordance With 10CFR50, Appendix J i

- 1 RV-00B TYPE 4, , IWV-3521 !

Excess Flow Check Valve Exercise Test Frequency - These valves cannot be exercised during n7rmal operation or Cold Shutdown since safety related instri.ments would be taken out ,

of service. These valves will be tasted in accordance with j Technical Specification 4.7.D (pagte 3.7/4.7-32) and Updated l Final Safety Analysis Report Sectjon 5.2.2 (page 28) i RV-00C TYPE 1, POSITION 6 , IWV-3 417 (r.) !

Fast Acting Valves (Maximum Scroke. Time = 2.000 Seconds)

Will Not Be Subject to More Frequent Testing When The Stroke Time Changes By More Than 50% - These valves will be declared inoperable if the measured stroke time exceeds 2.000 seconds.

l j RV-00D TYPE 4, , IWV-3417(a)

Reference Value Stroke Time vs. Previous Stroke Time -

Rather than using the results of the previous test to

establish more frequent testing limits for the next test, a l

reference value stroke time concept will be implemented.

RV-00E TYPE 1, POSITION 2 , IWV-3521 and IWV-3522 check Valve Disassembly - If a valve cannot be exercised with system flow, disassembly to verify that the valve will stroke open is a last resort. A sample plan (as outlined in the' Relief Request) will be used to perform disassembly tests. Partial stroke open testing of the valve will be performed if possible.

Revision 3 VALVES 1-4

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 g x INSERVICE TESTING PLAN - VALVES

'~) Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF-REQUEST

SUMMARY

RV-00F TYPE 4, , IWV-3521 and IWV-3522 ;

Check Valve Disassgmbly - If a valve cannot be excercised with system flow, disassembly to verify that the valve will ,

stroke closed is a last resort. A sample plan (as outlined ;

in the relief request) will be used to perform disassembly tests. ,

RV-00G TYPE 4, , IWV-3417(b) and IWV-3523 Corrective Actions Will Be Governed By Technical Specification LCos vs.Section XI - Especially for Cold Shutdown testing, corrective actions will be performed in accordance with the Limiting conditions for operation. A test f ailure will not necessarily require repair /replacelaent prior to startup/ continued operation.

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\_/ RV-03A TYPE 1, POSITION 7 , IWV-3411, 3417(a), and 3521' '

Control Rod Drive Scram Inlet and outlet Valve Exercise Test Frequency - These valves cannot be tested during normal operation because a CRD would be inserted. Cold Shutdown testing would result in more frequent testing than required.

These valves will be tested in accordance with Technical Specification 3/4.3.C RV-07A TYPE 4 , IWV-3521 Traversing In-Core Probe Purge Check Valve Exercise Test '

Frequency - This Primary Containment Isolation Valve cannot be isolated during normal operation or Cold Shutdown because '

continuous purge flow is required.

l RV-11A TYPE 4, , ..WV-3521 Standby Liquid Control Primary containment Isolation Check I

Valve Exercise Test Frequency - These valves cannot be exercis6d during normal operation because the SBLC poison must be separated from reactor coolant. The test performed during. cold Shutdown will only partial stroke the valves.

Revision 3 VALVES 1-5 l

< l QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PIAN - VALVES

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Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST

SUMMARY

l RV-13A TYPE 5, , IWV-3521 .

RCIC Turbine Exhaust and RCIC Vacuum Pump i Check Valve Exercise Test Frequency - There is no I means to confirm that these valves closed following system operation, although there are indicators that the valves closed. The PCIV leak test at reactor refueling will be l

used to confira valve closure. .

RV-23A TYPE 4, , IWV-3521 h HPCI Turbine Exhaust and HPCI . _

Drain Pot check Valve Exercise Test Frequency - There is no i means to confirm that these valves closed following system -

operation, although there are indicators that the valves closed. The PCIV leak test at reactor refueling will be

- used to confirm valve closure. [

RV-24A TYPE 5, , IWV-3521 ,

Containment Atmosphere Monitor (CAM) H2/02 Analyzer Discharge Check Valve Exercise Test - This simple check i valve (without position indication) is impractical to test _ i during normal operation or Cold Shutdown. !

I L

RV-25A TYPE 5, , IWV-3521 Atmospheric Containment Atmosphere Dilution (ACAD) PCIV/

Discharge check Valve Exercise Test Frequency - These simple :

check valves (without position indication) are impractical !

test during normal operation and Cold Shutdown.

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RV-30A TYPE 4, POSITION 6 , IWV-3411, IWV-3417(a) '

Main Steam Target Rock and Electromatic Relief Valve ,

i Exercise Test Frequency and No Position Indication -' Proper response by the discharge line temperature and acoustic l monitors, and the Turbine Bypass valve will be used to j confirm valve operability.

l iO Revision 3 VALVES 1-6 P

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 1.0-1 RELIEF REQUEST SUMMARIES R2 LIEF F.EQUEST

SUMMARY

RV-30B TYPE 4, , IWV-3513 Main Steam Safety Valve Setpoint Testing, Additional Testing Requirements - Based on the special maintenance schedule applied to these valves (cleaned and re-built every other ,

refueling outage),.there is no need to perform additional ,

testing of these valves. See Technical Specification 4.6.E.

r RV-30C TYPE 4, , IWV-3521 Main Steam Safety / Relief Valve Discharge Line Vacuum Breaker Exercise Test Frequency - These simple check valves inside containment probably work properly after each SRV actuation, but there is no means of confirming their operability. A manual exercise test will be performed during Reactor Refueling to confirm their operability.

t RV-30D . TYPE 5, , IWV-3411 Main Steam Isolation Valve AC, DC, and 2-Way Air Pilot Actuated Solenoid Exercise Test Frequency - Due the special tests that are performed (pulling fuses and simulating a loss-of-air test) these valves cannot be tested during normal operation or at Cold Shutdown. >

IWV-3521 RV-32A TYPE 4, ,

Feedwater Primary Containment Isolation Check Valves Exercise Test Frequency - The feedwater check valves cannot be closed during normal operation or the unit will scram on

! low water level. During Cold Shutdown, LWCU is required to prevent thermal stratification in the reactor vessel i and to maintain reactor water quality.

RV-37A TYPE 5, , IWV-3521 Reactor Building Closed Cooling Water (RBCCW) Supply to the Drywell Check Valve, Exercise Test Frequency. This valve l cannot be closed during normal operation or Cold Shutdown because the Reactor Recirculation pump and motor bearing coolers, and the drywell coolers would be isolated.

O Revision 3 VALVES 1-7 l

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_ QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

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Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST

SUMMARY

RV-43A TYPE 5, , IWV-3521 Clean Condensate supply to the Drywell, Check Valve Exercise Test - This simple check valve (without' position indication) is inaccessible during normal operation and Cold Shutdown.

Since it is normally isolated by two closed valves,'it will be tested closed during the 10CFR50, Appendix J seat leak test.

RV-46A TYPE 5, , IWV-3 417 (a)

Diesel Generator Starting Air Solenoid Valves Do Not Have Position Indication; Therefore, No Maximum Stroke Time, No Criteria for More Frequent Testing - Operability of the subject valves will be determined by the Diesel Engine start time test.

L RV-46B TYPE 5, , IWV-3521

', Service Air to the Drywell Isolation Valve Exercise Test Frequency - Since the valve is a simple check valve without L, position indication, a reverse flow / leak test must be L performed. This is impractical to do at any time other than rwactor refueling.

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RV-47A TPYE 5, , IWV-3521 Main Steam Isolation Valve and Target Rock Safety / Relief Valve Air Actuator Accumulator check Valve. Exercise Test Frequency - These simple check valves inside containment cannot be exercised during normal operation or Cold Shutdown because they are not accessible. These valves will be exercised during the accumulator check leak test (AT-06)

RV-47B TYPE 5, , IWV-3521 '

Instrument Air Primary Containment Isolation Valve Exercice Test Frequency - The air supply to the MSIV, SRV, and Torus /

Drywell vacuum breaker air actuators is required to prevent MSIV closure and other plant transients. It is impractical to test these simple check valves (without position indication) at any time other than Reactor Refueling.

L l

Revision 3 VALVES 1-8

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 7

INSERVICE TESTING PLAN - VALVES Table 1.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST

SUMMARY

RV-52A TYPE 5, , IWV-3417(a) and IWV-3417(b)

Diesel Generator Fuel Oil Transfer Pump Discharge Line Solenoid Valves Do Not Have Position Indication; Therefore, No Maximum Stroke Time, No Criteria for More Frequent-Testing 1

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l Revision 3 VALVES 1- 9

Quad Cition Nucloor Pow 3r Statien, Unito 1 & 2 INSERVICE TESTING PROGRAM ~ VALVES RELIEF REQUEST N M ERt RV-001 (Sheet 1 of 2)

COMPONENT _ IDENTIFICATION IW-2200 CODE DWG

_ VALVE NUMBER CATEGORY CIJdia DRAWING NUMBER CQQE All Primary Containment Isolation Valves (PCIVs) i FUNCTIOMfS)

Not Applicable.

CODE REQUIREMENT Article IW-3421, " Scope" l Article IW-3422, " Frequency" Article IW-3423, " Differential Test Pressure" Article IW-3424, " Seat Leakage Measurement"

, Article IW-3425, " Test Medium" l Article IW-3427 (b) " Corrective Action for valves 6 inch y nominal pipe size and larger" BASIS FOR RELIEF The intent of Articles IW-3421 through IW-3425 is met by a primary containment isolation valve surveillance program that complies with the requirements of 10CFR50, Appendix J for Type C Local Leak Rate Testing. NRC Generic Letter 89-04, Attachment i 1, ' Position 10 states that the usefulness of IW-3427(b) does not l justify the burden of complying with the requirement.

l PROPOSED ALTERNATE TESTING l Primary containment isolation valve seat leak rate testing will l be performed in accordance with the requirements of 10CFR50, ;

! Appendix J for Type C testing. !

I O I Revision 3 VALVES L 1-10 l

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Quad Citico'NuclGor P war Statien, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REODEST NUMBERt RV-001 (Sheet 2 of 2)

The results of primary containment isolation valve seat leak rate testing will be analyzed in accordance with the requirements of:

o 10CFR50, Appendix J for Type C leak rate tests, and o Technical Specification Section 3.7 l Corrective actions will be taken in accordance with Technical Specification Section 3.7.

[ (* kPPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

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RELIEF REQUEST TYPE This is a Type 1 Relief Request complying with NRC Generic Letter .

89-04, Attachment 1, Position 10.

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COMPONENT IDENTIFICATION )

l IWV-2200 CODE DWG !

VALVE NUMBER CATEGORY C.LMil DRAWING NUMBER S.QQE All Excess Flow Check Valves FUNCTION (8)

An excess flow check valve limits flow (leakage) from a failed instrument line comiected to the Reactor Coolant Pressure Boundary (RCPB) . If an instrument line fails outside primary containment, downstream of the excess flow check valve, the amount of reactor coolant discharged into secondary containment will be minimized.

CODE REQUIREMENT -

Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

BASIS FOR RELIEF These valves are tested in accordance with the Technical Specifications and Updated Final Safety Analysis Roport. It is impractical to perform a stroke test during normal operation or Cold Shutdown because safety related instrument channel (s) would have to be taken out-of-service to perform the test.

PROPOSED ALTERNATE TESTING Excess flow check valves will be exercised closed with the

' reactor vessel at normal operating pressure (1000 psi) at the end of each reactor refueling outage, in accordance with-Technical Specification 4.7.D (page 3.7/4.7-32, the last paragraph) and Updated Final Safety Analysis Report Section 5.2'2 (page 28).

APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIEF REOUEST TYPE This is a Type 4 Relief Request (requiring NRC approval)

Revision 3 VALVES 1-12

Qu2d citico Nuclocr Psw0r Station, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOURST NUMBERt RV-00C (Sheet 1 of 3)

COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CIASS DRAWING NUMBER COOR i

All Category A and B valves with a maximum stroke time of 2.000 seconds (i.e., fast acting valves). Note that there are no valves in the program with a maximum stroke time less than 2.000 ;

seconds.

Unit 1 0203-003A B/C 1 M-0013-1 F-7 0203-003B B 1 M-0013-1 E-6 .

0203-003C B 1 M-0013-1 C-8 I 0203-003D B 1 M-0013-1 B-8 1 0203-003E B 1 M-0013-1 E-8 l 0302-181A B NC M-0041-1 D-8 i 0302-181B B NC M-0041-1 D-8 '

0302-182A B NC M-0041-1 F-8

, 0302-182B B NC M-0041-1 F-8 l 0305-120 -FCV B 1 M-0041-1 C-10 1

0305-121 -SO B 1 m-0041-1 C-9

/-wg 0305-122 -SO B 1 M-0041-1 C-9

-( j 0305-123 -FCV B 1 M-0041-1 C-10

-0305-126 -CV B 1 M-0041-1 D-10 0305-127 -CV B 1 M-0041-1 D-9 2499-001A-SO B NC M-0641-1 D-6 ;

2499-001B-SO B NC M-0641-1 D-3 2499-002A-SO A NC M-0641-1 D-6 2499-002B-SO A NC M-0641-1 D-3 i 2499-003A-SO B NC M-0641-1 B-7 2499-003B-SO B NC M-0641-1 B-2 2499-004A-SO A NC M-0641-1 B-6 L

2499-004B-SO A NC M-0641-1 B-3 L 4699-226 B NC M-0025 Z-99 L 5201- -SO B NS M-0029 D-4 ,

1 I

Unit 1/2

( 4699-226 - -1/2 B NC M-0043 C-7 5201- -50 -1/2 B NS M-0029 F-6

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Unit 2 ,

0203-003A B/C 1 M-0060-1 F-7 1 0203-003B 'B~ 1 M-0060-1 E-6 I 0203-003C B 1 M-0060-1 C-8 0203-003D i B 1 M-0060-1 B-8 :

0203-003E B 1 M-0060-1 E-8 0302-181A B NC M-0081-1 D-8 !

(' 0302-181B B NC M-0081-1 D-8 0302-182A B NC M-0081-1 F-8 i 0302-182B B NC M-0081-1 F-8 l Revision 3 VALVES 1-13 ;

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Qusd Citica Nucloor Powsr StGticn, Unito 1 & 2 !

INSERVICE TESTING PROGRAM - VAL \T4 g RELIEF REQUEST NUMBERt RV-00C (Sheet 2 of 3)

Unit 2 (Con't.)

0305-120 -FCV B 1 M-0081-1 C-10 '

0305-121 -SO B 1 M-0081-1 C-9 0305-122 -SO B 1 M-0081-1 C-9 0305-123 -FCV B 1 M-0081-1 C-10 0305-126 -CV B NC M-0081-1 D-10 0305-127 -CV B NC M-0081-1 D-9 2499-001A-SO B NC M-0641-2 D-6 2499-001B-50 B NC M-0641-2 D-3 2499-002A-SO A NC M-0641-2 D-6 ,

2499-002B-SO A NC M-0641-2 D-3 2499-003A-SO B NC .M-0641-2 8-7 ,

2499-003B-SO B NC M-0641-2 B-2 2499-004A-SO A NC M-0641-2 B-6 2499-004B-SO A NC M-0641-2 B-3 ,

FUNCTION (S)

Not Applicable.

CODE REOUIREMENT

()

V Article IWV-3417(a), " Corrective Action," Power operated valves that normally exercise in less than or equal to 10 seconds require more frequent testing if the comparison between the previous test and the current test indicates that the stroke time has increased by 50% or more.

BASIS FOR RELIEF For valves with a maximum stroke time of 2.000 seconds, operator and timing device inconsistency is the most significant contributor to the difference in stroke time from one test to the next. Given the' problems with obtaining an accurate test mearurement, it is impractical to compare the results of the current and previous test, and determine whether more frequent (monthly) testing is required, t In accordance with IWV-3417(b), the valve will be declared inoperable and appropriate corrective action will be taken if the test result exceeds the limiting value of full-stroke time, bv Revision 3 VALVES 1-14

Quod citico Nucloor P3 var StGtion; Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBER: RV-00C (Sheet 3 of 31 )

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1 jw-) " J PROPOSED ALTERNAfE TESTING !

t Since test results for power operated valves with a maximum '

stroke-time of 2.000 seconds are impractical to trend, no

alternate test is available. ,

i APPLICABLE TIME PERIOD :

Relief is requested for the 2nd ten (10). year interval.

RELIEF REQUEST TYPE ,

This is a Type 1 Relief Request. complying with~NRC Generic Letter 89-04, Attachment 1, Position 6. j i

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t Revision 3 VALVES 1-15

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. Qu0d CitioO Nuc1 Car P w0r Station, Unito 1 & 2 INSERVICE TESTING PROGRAM _- VALVES e RELIEF REQUEST NUMBERt RV-00D (Sheet 1 of 3)

COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR All Category A and B power operated valves, this Relief Request deals with general requirements.

, 7 FUNCTION (5) ,

Not Applicable.

GODE REQUIREMENT Article IWV-3417(a), " corrective Action," Power operated valves that normally exercise in less ,

! than or equal to 10 seconds require more l frequent testing if the comparison between the previous test and the current test indicates that the stroke O- time has increased by 50% or more.

Power operated valves that normally exercise in more than 10 seconds require ,

more frequent testing if,the comparison between the previous test and the current test indicates that the stroke time has increased by 25% or more.

4 BASIS FOR RELIEF The Code requirement for more frequent testing is based on a i comparison between the current stroke time and the previous stroke time. This approach allows the threshold for more frequent testing to slowly creep up over' time, if there are small-l- changes between the current stroke time and the previous stroke ;

~

time. A variable limit based on the previous stroke time is difficult to administer because the limit is not a permanent entry in.the test procedure.

Conversely, a fixed limit based on a reference value stroke time j will yield a tighter band of acceptable stroke times and is easy to administer. 1 i

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4 Revision 3 VALVES 1-16 l 1

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Qu;d Citics Muc1Cor Pow 3r StOtiCn, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES i- RELIEF REOURST MUMBERt RY-00D (Sheet 2 of 3)

PROP 085D ALTERNATE TESTING Quad Cities Station will establish a reference value stroke time when the valve is known to oe operating acceptably. When a reference value may have been affected by repair or routine servicing of the valve, a new reference value will be determined or the previous reference value will be reconfirmed.

The following terms have been defined:

T, : Reference value stroke time T,, : Full stroke _ time as measured during the exercise test T, : Mhximum stroke time (limiting value for full- -

stroke)

The test f requency will be increased to monthly if T 'eisif in the Alert Range, andthevalvewillbedeclaredinoperabk T,, is in the Required Action Range in accordance with Table 1 Table 1

( POWER OPERATED VALVE

- STROKE TIME LIMITS A Ref.

c Stroke Acceptable Alert Reg'd t Time Range Range Action u (secs) (seconds) (seconds) Range L

a (seconds) t o

r SO T ,= 2 T,,5 2 . 0 Not defined, see T,,> 2 . 0 Relief Request l' RV-00C MO T,510 0. ST,,T,,51. ST, T,,< 0. ST, T,,> 2 . OT, o r >T, i

1. 5T,<Tus2. 0T.

MO T, > 10 0. 7 5T,5T,,51. 2 5T, T,,< 0. 7 5T, T,,>1. 7 5T, or >T,

1. 2 5T.<Tu < 1. 7 5T, j 1

i l

AO any 0. 5T.5T,,51. ST, T,,< 0. ST, T,,> 2 . OT, o r >T, i HC 1. ST.<Tus 2 . OT. l I

lMSIV any 3.057 ,55.0 Not Defined To>5.0 l

l Revision 3 VALVES 1-17

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' Qutd Citico Nucloor Pow 0r station, Unito 1 F 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOURST NUMEREt RT-00D fEheet 3 of 31 .

&RELICARLE_11FM JERIOD Relief is regtyT?FJ for the 2nd ten (10) year interval.

RELIEF REQUEST. TYPE ,

i This'is a Type 4 Relief Request (requires NRC approval). See the r October 25, 1989, Minutes of Public Meetings on Generic Letter j 89-04, response to Question 40, page 26.

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!; Revisior. ? VALVES 1-1E

I Qund Citico NuclO3r Pow 3r StOtien, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REODERT MUMBER RY-00E (Sheet 1 of 3)

COMPONENT IDENTIFICATION f

IWV-2200 CODE DWG VALVE NUMBER CATEGORY CIASS DRAWING NUMBER COOR Unit 1 2301-034 A/C 2 M-0046 C-8 2301-039 C- 2 M-0046 E-8 2301-050 C 2 M-0046 C-5 2301-071 A/C 2 M-0046 D8 2301-075 C 2 M-0046 B-4 2399-005 C NC M-0046 D-8 2399-006 C NC M-0046 D-8 24 994-022 A A/C NC M-0641-1 C-7 2499-022B A/C NC M-0641-1 C-2 5299-003 C NC M-0029 'F-4 Unit 1/2 5299-003 - -1/2 C NC M-0029 F-4 Unit 2 2301-034 A/C 2 M-0087 C-8 2301-039 C 2 M-0087 E-8 >

f 2301-050 C 2 M-0087 M-0087 C-5 D-8

'2301-071 A/C 2 2301-075 C 2 M-0087 B-4 2399-005 C NC M-0087 D-8 2399-006 C NC M-0087 D-8 2499-022A A/C NC M-0641-2 C-7 2499-022B A/C NC M-0641-2 C-2 5299-003 C NC 'M-0029 F-4 FUNCTION (8)

These check valves must open and pass the maximum required accident flow.

l O l Revision 3 VALVES p 1-19 l l

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'Qund Citics Nuclocr Power Station, Unito 1 & 2 l INSERVICE TESTING PROGRAM - VALVES RELIEF REQUEST NUMBERt RV-00E (Sheet 2 of 3)

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CODE REQUIREMENT Article IWV-3521, " Test Frequency ~," Check valves shall be I exercised at least once every 3 months, except as provided by IWV-3522.

l Article IWV-3522, " Exercising Procedure," Check valves shall )

be exercised to the position required to fulfill their safety function.

Confirmation shall be obtained by visual observation, position indication, 1 appropriate pressure or flow indications, 1 or other positive (quantitative) means. I BASIS FOR RELIEF Quad Cities has conducted a detailed evaluation of the testability of each of the subject valves. We have concluded that there is no cuantitative means of verifying that the subject check valves have been exercised to the open position by passing )

the maximum required accident flow through the valve. )

PROPOSED ALTERNATE TESTING The operability of the subject check valves will be verified by disassembly. Due to the scope of this testing (specifically, the personnel hazards involved and system operating restrictions),

disassembly and inspection will be performed during reactor refueling outages. Since it would be burdensome to disassemble and inspect all of the subject check valves during each refueling outage, a sample disassembly and inspection plan for groups of identical valves in similar applications will be employed.

Check valves will be disassembled to the extent necessary to' assess the condition of the valve and to allow manual exercising of the disk. During the visual examination, full stroke capability will be verified. Any loose or corroded parts will be evaluated and appropriate corrective action will be taken, if-required.

If a partial stroke exercise with flow can be performed, a partial stroke test will be performed after disassembly and inspection. If system conditions during Cold Shutdown or Reactor Refueling permit, the partial stroke exercise will be performed before returning the' valve to service. Additionally, each check valve will be part stroke exercised open quarterly when system conditions permit.

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Revision 3 VALVES 1-20

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1 Qund Citico Nucloor P:w0r Staticn, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES l 1

4 RELIEF REQUEST NUMBER MV-00E (Sheet 3 of 3) )

The population of check valves listed in this Relief Request has been broken down into sample groups that contain no more than four (4) valves. All of the valves in a given sample group are of identical design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation.

7 APPLIchBLE TIME PERIOD l

I Relief. is requested for the 2nd ten (10) year interval.

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RELIEF REQUEST TYPE i

This is a Type 1 Relief Request complying with NRC Generic Letter 89-04, Attachment 1, Position 2. See the October 25, 1989, Minutes of Public Meetings on Generic Letter 89-04,. responses to questions concerning Position 2, Questions 9 through 20, pages 11 L through 20.

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O Revision 3 VALVES 1-21

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-Qund Citica Nuclocr Powar Station, Unito 1 & 2 i INSERVICE TESTING PROGRAM - VALVES l l

RELIEF REOUEST NUMBERt RV-00F (Sheet 1 of 3)

(c) v =

COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER ED.QB Unit i 1001-131 C 2 M-0039-1 B-7 1001-136A C 2 M-0039-1 D-8 1001-136B C 2 M-0039-1 E-2 1402-071 C 2 M-0036 D-7

? 2301-020 C 2 M-0046 E-1 2301-051 C 2 M-0046 C-5 2301-076 C 2 M-0046 E-4 l 2301-108 C 2 M-0046 C-1 2399-005 C NC M-0046 D-8 2399-006 C NC M-0046 D-8 2901-010 C 2 M-0046 D-7 3999-085 C 3 M-0022-1 E-2 3999-088 C 3 M-0022-1 E-2 5199-158 C NC M-0029 C-6 Unit 1/2 5199-158 - -1/2 C NC M-0029 C-6 Unit 2 1001-131 C 2 M-0081-1 B-2 1001-136A C 2 M-0081-1 D-8

! 1001-136B C 2 M-0081-1 E-2 1402-070 C 2 M-0078 E-7 2301-020 C 2 M-0087 E-1 l- 2301-051 C 2 M-0087 C-5 l 2301-076 C 2 M-0087 E !

'2301-108 C 2 M-0087 C-1 2399-005 C 2 M-0087 D-8 l 2399-006 C 2 M-0087 D-8 2901-010 C 2 M-0087 D-7 3999-088 C 3 M-0069-1 B-9 5199-158 C NC M-0029 C-6 FUNCTION (S) t These check valves must close.

Revision 3 VALVES 1-22

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d Qund Citico Nuclear Powar' Station, Unito 1 & 2 )

INSERVICE TESTING PROGRAM - VALVES KELIEF REQUEST NUMBER RV-00F (Sheet 2 of 3)

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\ 1 CODE REOUIREMENT l Article IWV-3521, " Test Frequency," Check valves shall be exercised at.least once every 3-months, i except as provided by IWV-3522.

Article IWV-3522, " Exercising Procedure," Check valves shall be exercised to the position required to fulfill their safety function. Confirmation shall be obtained by visual observation, position indication, appropriate pressure or flow indications, or other positive (quantitative) means.

BASIS FOR RELIEF Quad Cities has conducted a detailed evaluation of the ,

testability of each of the subject valves. We have concluded that there is no auantitative metns of verifying that the subject check valves have been exercised to the closed position by either a reverse flow or " seat leakage" type teut. A variety of 4 pressure tests, vacuum tests, special system alignments, etc.

were evaluated, and no conclusive test is possible.

PROPOSED ALTERNATE TESTIN2 The operability of the subject check valves will be verified by i disassembly. Due to the scope of this testing (specifically, the personnel hazards involved and system operating restrictions), 4; disassembly and inspection will be performed during reactor refueling outages. Since it would be burdensome to disassemble and' inspect all of the subject check valves during each refueling

" outage, a sample disassembly and inspection plan for groups of identical valves in similar applications will be employed.' t Check valves will be disassembled to the extent necessary to assess the condition of the valve and to allow manual exercising of the disk. During the visual examination, full stroke capacility will be verified. Any loose ot corroded parts will be evaluated and appropriate corrective action will be taken, if required.

-The population of check valves listed in this Relief Request has been broken down into sample groups that contain no more than four (4) valves. All of the valves in a given sample group are of' identical design (manufacturer,-size, model number, and materials of construction) and have the same service conditions l

( including valve orientation.

Revision 3 VALVES 1-23 ,

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1 Quad citics NuclGar Pow 0r Station, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REQUEST NUM2ERt RV _00F (Sheet 3 of 3)

O APPLICABLE TIME PERIOQ Relief is requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 4 Relief Request (requiring NRC approval). See the October 25, 1989, Minutes of Public Meetings on Generic Letter 89-04, response to Question 17, page 15.

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! J Quad Citioc Nucloor Pcwor Station, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES L g-( RELIEF REOUEST NUMBER: RV-00G (Sheet 1 of 2) l V'

COMPONENT IDENTIFICATION IWV-2200 CODE DWG l VALVE NUMBER CATEGORY CLASS DRAWING NUMBER CO2E ;

I All valves, this Relief Request deals with general requirements. I FUNCTION (S) ;

Not Applicable.

CODE REOUIREMENT l

Article IWV-3417(b), " Corrective Action," shall be initiated t

/ immediately if a valve fails to exhibit ;

the required change in~ valve stem or disk position or exceeds its limiting value of full-stroke time. 'When corrective action is required as a ,

result of tests made during Cold h, Shutdown, the condition shall be

\~/

corrected before startue. '

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Article IWV-3523, " Corrective Action," shall be initiated immediately if a valve fails to exhibit the required change of disk position.

When corrective' actions required as a result of tests made during cold Shutdown, the condition shall be corrected before startue.

BASIS FOR RELIEF

.The Technical Specifications provide Limiting conditions for Operation-(LCOs)'which state the miniana conditions necessary for safe' operation of the plant. The fr.ilure of a particular valve may not necessarily need to be corrected immediately, and may not prevent plant startup.

PROPOSED ALTERNATE TESTING j- ' Quad cities will evaluate the condition of each valve with respect to its safety function (s) and take appropriate corrective action as stated-in the applicable Technical Specification LCo.

l Revit!.on 3 VALVES 1-25 l

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' !' Qu0d Citico Nucloor Pcw3r Station, Unito 1 & 2 g, INSERVICE TESTING PROGRAM - VALVES

, =r , RELIEF REQUEST NUMBER: RV-00G (Sheet 2 of 2) l 1

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, M CAELE TIME PERIOD Relief is requested for the 2nd ten-(10) year interval.

RELIEF REQUEST TYPE This is a Type 4 Relief Request (requires NRC approval).

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Revision 3 VALVES

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Quad Citico Nucloar Powcr Station, Unito 1 & 2 I INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBER: RY-03A (Sheet 1 of 3)

COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1 0305-114 C 2 M-0041-1 E-9

.0305-126 -CV B 'l M-0041-1 D-10 03 0.5-127 -CV B 1 M-0041-1 D-9 Unit 2 .

0305-114 C 2 M-0083-1 E-9 1 0305-126 -CV B 1 M-0083-1 D-10 0305-127 -CV B 1 M-0083-1 D-9 FUNCTION (8)

The scram discharge check valve (0305-114) opens to discharge reactor coolant from the control Rod Drive (CRD) above-piston area to the Scram Discharge Volume (SDV). The scram inlet valve 0305-126-CV' opens to discharge the CRD Hydraulic Control Unit (HCU) accumulator into the CRD below-piston area. The scram

(" outlet valve. 0305-127-CV opens to vent the CRD above-piston area

( and discharge reactor coolant to the SDV.

A CRD is inserted by creating a dP across the CRD piston with "high" pressure in the below-piston volume and " low" pressure in the above-piston-volume. At low reactor pressure (5 600 psig),

the CRD HCU accumulator is required to insert a CRD within safety '

analysis time limits.

1 CODE REOUIREMENT Article IWV-3411, " Frequency," Category B valves shall be exercised at least once every 3 months, except as provided by IWV-3412(a), IWV- 1 3415, and IWV-3416.

Article IWV-3417(a), " Corrective Action," Power operated valves that normally exercise in less than or equal to 10 seconds require more

!, frequent testing if the comparison between the previous test and the current test indicates that the stroke j time has increased by 50% or more.

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Qund Citics Nucionr Pow 3r Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES e

e SE4IEF REODEST NUMBER RV-031 (Sheet 2 of 3)

CODE REQUIREMENT (cont'd)

Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

Bh5IS FOR RELIEF j As noted in TV-03A, the valve listed in the IST Plan is typical '

of 177 valves, i.e., one for each of the Control Rod Drives. The scram inlet and outlet valves are power operated valves that full stroke in milliseconds. These valves are not equipped with close and open position indicators.

Quarterly exercising of the subject valves would result in the rapid insertion of one or more Control Rod Drives. Quarterly testing would result in more frequent testing than is required to verify operability. Proper operation of each of these valves (3 x 177) is demonstrated during Technical Specification 3.3.C scram testing. The acceptance criteria for these tests is based on each CRD's scram insertion time. If the CRD is inserted within the time limits in Technical Specification 3.3.C.1, these valves are functioning properly.

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.Q. Trending the stroke times of the scram inlet and outlet valves is (s / impractical and unnecessary because these valves are indirectly 7 stroke timed and'no meaningful correlation between.the scram insertion time and the stroke time can be obtained. Based on the conservative limits established-for CRD scram insertion times, it is unnecessary to trend the stroke times.

PROPOSED ALTERNATE TESTING The operability of the subject valves will be verified by an indirect test. If the CRD scram insertion time is less than the limits in Technical Specifications 3.3.C.1 and 3.3.C.2, then the associated scram inlet and outlet valves are operable.

The test frequency for the subject valves will be based on the frequency of scram insertion time testing, as specified in Technical Specifications 4.3.C.1 and 4.3.C.2:

i Revision 3 VALVES 1-28 l

i Qund Citico Nucloor Powcr Station, Unita 1 & 2 INSERVICE TESTIN'_ PROGRAM - VALVES RELImr amoansT wumammt av-031 (Sheet 3 of 3)

PRQPOSED hLTERNATE TESTING (cont'd)

a. All control rod drives shall be tested after each )

refueling outage prior to operation above 30% power I with the reactor pressure above 800 psig, ,

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b. All control rod drives shall be tested annually, and j 1

c. 50% of the control rod drives in each quadrant of cne reactor sha?.1 be tested at an interval no more frequently than 16 weeks nor less frequently than 32 weeks.

l Relief Request RV-00E contains additional Alternate Testing H information for valves 0305-126-CV and 0305-127-CV. l APPLICABLE TIME PERIOD :

1 Relief is requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 1 Relief Request complying with NRC Generic Letter 89-04, Attachment 1, Position 7.

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mL' -Qutd CitiOD Nucloer Powor: Station, Unita 1 E 2 y,' , INSERVICE TESTING PROGRAM - VALVES r b ,

/ RELIEF REQUEST NUMBER: RV-07A

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COMPONENT IDENTIFICATION !

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IWV-2200 CODE .DWG r VALVE NUMBER CATEGORY CLASS H

DRAWING NUMBER COOR

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Unit 1 0743' A/C NC - M-0024-2 B-7 Unit 2-0743 A/C .NC M-0071 B-7

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FONCTION(8) l y This valve is the Primary Conteinment Isolation Valve (PCIV) for the -Traversing In-Core Probe (TIP) system nitrogen purge line, i

CODE REOUIREMENT l

i Article IWV-3521, " Frequency," Check valves shall.be exercised at least once every 3 months, H

except as provided byJIWV-3522. '

BP.878 FOR RELIEF This. valve cannot be. tested. during normal (power) operation because the TIP system must;be purged continuously.

This-valve cannot be tested during Cold' Shutdown because there

. are nod external: means of determining disk position and there are no test connections available to pressurize the. valve in the. :i reverse direction. The system must be:taken out-of-service and tubing joints must be= disconnected to perform-a close exercise l' test.-

w The subject valve will be erarcised closed during each reactor

' refueling outage.

APPLICABLE ~ TIME PERIOD Relief is requested f(r the 2nd ten (10) year interval.

RFLIEF REQUEST TYPE This'is a. Type 5 Relief Request. ,

' Revision'3 VALVES 1-30

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I Quad Citics Nuclocr Powar Station, Unito 1 ' 2' INSERVICE TESTING PROGRAM - VALVES

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scs v RELIEF REOUEST NUMBERt RV-111 (Sheet 1 of 21 J j-SQMEAMENT_IDEETIZICATISM IWV-2200 CODE .DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1 1101-015 A/C 1 M-0040 C-3 1101-016 A/C 1 M-0040 C-3 Unit 2 1101-015 A/C 1 M-0082 C-3 I 1101-016 A/C 1 M-0082- C-4 l FUNCTION (8) l These valves are Primary Containment Isolation Valves (PCIVs).for the Standby Liquid Control (SBLC) system. These ve'ves must open for the SBLC pumps to inject poison (sodium pentaborate) into the' j raactor. The SBLC system is a backup to the Control Rod Drive, hydraulic system. The SBLC system uses a poison (neutron absorber) to control reactivity. l

,' CODE REQUIREMENT Article IWV-3521, " Frequency," Check' valves shall be exercised'at least once every 3 months, except as.provided by o IWV-3522. 1 l

BASIS FOR RELIEF

-Any. exercise test of these valves is complicated because they are- '

isolated from the main part of the SBLC system by explosive actuated valves (1106A and 1106B). The' explosive actuated: valves.

maintain a leak tight physical barrier between the poison in:the-SBLC' system and reactor water.

An exercise test to the open position (using demineralized water) cannot be performed during normal operation because the resulting ;

cold water, injection would produce undesirable thermal stresses-l in the complex SBLC piping inside the' reactor vessel. The test connection downstream of the explosive actuated valves can be used~during Cold Shutdown to part stroke open the subject valves.

The test connection is not large enough for a. full flow test; a ,

full stroke test can only be performed during Reactor Refueling l f using .the SBLC pumps.

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5 T.evision 3 VALVES 1-31 . ,

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Quad Cities Nuclear Power Station, Units 1 & 2 INSERVICE TESTING PROGRAM'- VALVES E "

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RELIEP REQUEST NUMBER: RV-11A (Sheet 2 of 2) s r 1

-These simple check valves do not have position indication, and '

valve 1101-015 is inside the drywell so it is norma 1.ly inaccessible' . These valves cannot be tested tc cue close position-without performing some type of reverse-flow / leak test, which is impractical to perform during noraal operation or Cold

' Shutdown.

I PROPOSED ALTERNATE TESTING These valves will be exercised partially open during Cold l uk Shutdown. -l l

These valves will be full stroke exercised closed and open during Reactor Refueling.

1 These valves will be exercised open during the SBLC reactor.

vessel injection surveillance. After the explosive actuated m : valves are detonated, the SBLC pumps will be aligned to pump

[r demineralized water from the SBLC Teet Tank to the reactor vessel. The flowrate during this special test will exceed 40

gpm, the maximum required accident flowrate.

APPLICABLE TIME PERIOD

=r Relief'is requested for the 2nd ten (10) year interval.

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BELIE.F REQUEST TYPE This is a Type 4 Relief Request (requires NRC approval).

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Quad Citico Nuclcar Pow 0r Station, Units 1 &.2 INSERVICE' TESTING PROGRAM - VALVES

.' RELIEF REOUEST NUMBER: RY-13A (Sheet 1 of 2)

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COMPCNENT IDENTIFICATION IWV-2200 CODE DWG l VALVE NUMBER CATEGORY CLASS DRAWING NUMBER faQE ,

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1301-040 A/C NC M-0050. D-2 1301-041 A/C NC M-0050 D-2 1301-055 A/C NC M-0050 D-2 1301-064 A/C NC M-0050 D-2 Unit 2 .

1301-040 A/C NC M-0089 D-3 Y

. 1301-041 A/C NC M-0089 D-2 1 1301-055 A/C NC M-0089 D-3 1301-064 A/C NC M-0089 D-2 FUNCTION (8) l Valves 1301-040 and 1301-055 are Primary. containment Isolation valves (PCIVs) on the RCIC vacuum pump discharge line to the l

Suppression Pool-(Torus).

j Valves 1301-041 and 1301-064 are Primary Containment Isolation l Valves (PCIVs) on the RCIC turbine (1303) exhaust line to the .

I Torus.

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CODE REOUIREMENT ]

Article IWV-3521, " Frequency," Check valves _shall be exercised at least once every-3 months, except as provided by. l IWV-3522. I BASIS FOR RELIEF It would be impractical to unlock and close stop check valves 1301-055 and-1301-064 for the purpose of pressurizing the volume

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l between the.stop check valves and the subject check valves.to ]

verify valv ' closure. If this test were performed during normal j plant operation, the system would have to be declared inoperable q for the sole purpose of confirming a valve position. It is impractical'to perform such complicated tests during Cold l Shutdown.

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, l Quid Cition NuclGar Powsr Station, Unita 1 & 2

,INSERVl'CE TESTING PROGRAM - VALVES RELIEF REQUEST NUMBERt RY-131 (Sheet 2 of 2) 'I

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'c PROPOSED ALTERNATE TESTINQ The subject check valves will be exercised closed during each reactor refueling' outage'. H APPLICABLE TIME PERIOD ,

Relief is requested for the 2nd ten (10) year interval.

AELIEF REQUEST TYPE This is a Type 5 Relief Request.

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-Quad Citios Nuclocr Powar Station, Unitd 1 & 2 L INSERVICE TESTING PROGRAM - VALVES ,

. _ RELIEF REOUEST NUMBER RV-2'A 3 (Sheet 1 of 2)

L COMPQNENT. IDENTIFICATION ,

IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1 2301-034 A/C 2 M-0046 D-7 2301-045 A/C 2_ M-0046 B-8 2301-071 A/C 2 M-0046 D-8 l 2301-074- A/C 2 M-0046 C-8 Unit 2 2301-034 A/C. 2 M-0087 C-8 2301-045 A/C 2 M-0087 B-8 2301-071 A/C 2 M-0087 D-8 :

2301-074 A/C 2 M-0087 C-8 FUNCTION (8)

Valves 2301-034 and 2301-071 are Primary Containment Isolation Valves (PCIVs) on the HPCI drain pot (2301-97) discharge line to the Suppression Pool (Torus). These valves must open to f( '. discharge. condensate from'the drain pot, and ensure-that

\ - condensate does not back-up into the steam lines or turbine.

Valves 2301-045 and 2301-074 are Primary Containment Isolation

' Valves (PCIVs) on the HPCI turbine (2303) exhaust line to the Torus. These valves must open.to exhaust " low" pressure steam, and ensure that the HPCI turbine does not trip _on excessive

. backpressure. If the.HPCI system trips, the steam in the exhaust line will start'to condense and create a vacuum. These valves must close to prevent Torus water from entering the discharge line/ turbine, while the vacuum breakers relieve the vacuum. If-Torus water enters the exhaust line/ turbine, the system may be damaged when_the operator resets the trip and attempts to re-start the system.

CODE REQUIREMENT Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, 3 except as provided by IWV-3522.

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-i Quad Citico. Nuclear Powar Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBER: RV-23A (Sheet 2 of 2)

BASIS FOR RELIEF The HPCI valves will be exercised open' quarterly during the HPCI system pump tast. There are no position indicators on these-valves and there is no conclusive, indirect means of determining- ,

that these: valves were exercised closed during the quarterly pump J test. These valves have probably closed since-the discharge-line pressure returns to atmospheric pressure at the conclusion of the: '

test. An elevated pressure would indicate that the line was flooded when the vacuum created by condensing steam sucked Torus ,

water into the line (which is at a lower elevation than the connection to the Torus).

?It would be impractical to unlock and close stop check valves 2301-071'and 2301-074 for the purpose of pressurizing the volume j' between the stop check valves.and the subject check valves to verify valve closure. If this test were performed during normal plant operation, the system would have to be declared-inoperable for the sole purpose of confirming a valve position. 'It is impractical to perform such complicated tests during Cold Shutdown..

PROPOSED ALTERNATE TESTING ,

The subject check valves will be exercised closed during each reactor refueling outage.

APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

i RELIEF REOUEST TYPE This is a Type 4. Relief Request (requires NRC approval).

Revision 3 VALVES 1-36

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Quad citiso-Nuclocr-Powcr Station, Unitsi1 & 2 i D' '

INSERVICE TESTING PROGRAM - VALVES a

.M RELIEF REOUEST NUMBERt RV-241 COMPONENT IDENTIFICATION 1.

IWV-2200 CODE DWG VALVE NUMBER CATEGORY ,C.MSE DRAWING NUMBER COOR ^

Unit 1 a 2499-022A A/C NC M-0641-1 C-7 2499-022B A/C NC M-0641-1 C-2 Unit 2 ,

2499-022A A/C NC M-0641-2 C-7 ,

2499-022B A/C NC 'M-0641-2 C-2 FUNCTION (8) 4 i

The subject valves areLin the return lines from the Containment Atmosphere Monitoring system 2H/02 analyzer to the drywell.

'These valves are Primary Containment Isolation Valves (PCIVs) outside containment. They. must open for the H2 /02. analyzer to function properly..

l O CODE REOUIREMENT O. :

Article-IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

BASIS FOR RELIEF Since the subject valves are simple check valves with no position indication, they cannot be tested without performing some type of.

reverse: flow / leak test. This type of test is impractical to perform during normal operation and Cold Shutdown.

PROPOSED ALTERNATE TESTING The subject valves will be exercised closed during each reactor refueling outage, i

APPLICF.BLE TIME PERIOD o

Relief is requested for the 2nd ten (10) year interval. .

l RELIEF REOUEST TYPE This is a Type 5 Relief Request. l 1

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Quad' Citiac Nuclear Pow 3r Station, Units 1- & 2 INSERVICE TESTING PROGRAM - VALVES 1 RELIEF REOUEST NUMBER RV-251 ll I

COMPONENT IDENTIFICATION i IWV-2200 CODE DWG i VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1- _

2599-023A A/C NC M-0692- C-3 :

2599-023B A/C NC M-0642-1 ~C-6 k 2599-024A A/C NC M-0642-1 C-3' .

2599-024B- A/C NC M-0642-1 C-6 .!

l Unit 2 2599-023A A/C NC M-0642-2 C-6 ,

2599-023B A/C NC M-0642-2 C-3

'2599-024A A/C NC M-0642-2 C-6 ,

2599-024B A/C NC M-0642-2 C-3 '

FUNCTION (8)

Valves-2599-023A and 2599-023B are Primary Contairaent Isolation ;

Valves (PCIVs) on the Atmospheric Conthinment Atmosphere Dilution-( ACAD) - supply to the drywell. Valves 2599-024A and 2599-024B are-PCIVs on the ACAD supply to the Suppression Pool (Torus). If the ;

1 . containment atmosphere contains excess hydrogen, these valves open to supply dilution air.

CODE REQUIREMENT Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3-months, except as provided by IWV-3522.

BASIS FOR RELIEF Since the subject valves are simple check valves with no position indic3 tion, they cannot be tested without performing some type of reve r" . flow / leak test. -This type of-test is-impractical to pertere during normal operation or Cold Shutdown.

PROPOSED ALTERNATE TESTING The subject valves will be exercised closed during each reactor refueling outage.

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.Qutd Citics Nuclear Powar' Station, Units 1 &.2

' INSERVICE TESTING PROGRAM'- VALVE- .

h I RELIEF REQUEST NUMBER: RV-25A (cont'd) l ' '%)

APPLICABLE TIME PERIOD

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.-Relief is requested for the 2nd ten'(10) year interval'.

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RELIEF REOUEST TYPE '

1 This-is a Type '51 Relief Request. ;

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l Quad Citiec Nuclear Powar Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBERt RV-30A (Sheet 1 of 3)

COMPONENT IDENTIFICATION I

IWV-2200 CODE DWG VALVE' NUMBER CATEGGHy CLASS- DRAWING NUMBER COOR Unit 1 l 0203-003A B/C 1 M-0013-1 F-7 0203-003A-SO: B NC M-C013-1 F-7 M-0024-2 B-2 0203-003B. B 1 M-0013-1. D-6 0203-003C B 1 M-0313-1 C-7 0203-003D B 1 M-0013-1 B-7 0203-003E B 1 M-00'3-1 D-8 1

Unit'2

'0203-003A B/C 1 M-0060-1 F-7 0203-003A-SO. B ;NC .M-0060-1 F-7 l 0203-003B B 1 M-0060-1 D-6 1 0203-003C B 1 M-0060-1 C-8 0203-003D B 1- M-0060-1 B-8 0203-003E B 1 M-0060-1 D-8 FUNCTION (8)

, Valve 0203-003A is.a dual function Safety / Relief valve j; manufactured by Target Rock. Valve 0203-003A-SO is.the solenoid E

valve thatLcontrols the air supply to the Target Rock valve's diaphragm operator. Valves. 0203-003B-through E are Electromatic Relief. valves manufactured by Dresser.

l The Target Rock and Electromatic relief valves open upon receipt- l of an Automatic Depressurization System (ADS) signal to reduce l reactor pressure. Target Rock valve (0203-003A) also functions )

as-a safety valve which actuates on high system pressure.

CODE REOUIREMENT Article IWV-3411, " Frequency," Category B valves-shall be exercised at least once every 3 months, .l except as provided by IWV-3412(a), IWV- '

3415, and IWV-3416.

Article IWV-3417(a), " Corrective Action," Power operated valves that normally exercise in less than or equal to 10 seconds require more frequent testing if the comparison between the previous test and the q current test indicates that the stroke

d. time has increased by 50% or more.

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b' Quad Citics Nuclear Pow 3r Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES p,1 RELIEF REOUEST NUMBERt RV-301 (Sheet 2 of 3) (

j BASIS FOR RELIEF -

These. valves can only be tested at very low reactor power levels with primary system pressure greater than 150 psig. The test- -,

sequence requires an Operator to: !

a. Open at least one turbine bypass valve and discharge I main steam directly to the condenser, r

b. Actuate the relief valve and observe the corresponding; closure of the turbine bypass valve (pressure control ,

on the turbine. bypass valve is fairly quick to respond,- 1

~1 seconds), ;

c. Close the relief valve and observe the corresponding =?

opening'of the turbine bypass valve. -

Each relief valve actuation prcduces hydrodynamic loads which are-transmitted to the. Suppression Pool (Torus). The Quad Cities ,

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Mark I Containment, Plant Unique Analysis' Report (PUAR) fatigue l : evaluation is based on 300 relief valve actuations with nornal

! operating conditions (i.e., 300 actuations for testing purposes).

Quarterly testing of the subject valves would result in 4 e

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, (quarters) x 40_ (years). x 5 (valves) = 800 test actuations, which V would exceed the approved design basis.-

Finally, the failure of any relief valve to close would;cause an uncontrolled rapid depressurization of the primary system (stuck !

open relief. valve transient). The resulting severe-thermal.

gradients in the reactor vessel are not desirable, and should be I L minimized.

These valves-cannot be tested at cold Shutdown or Reactor i

.. Refueling since the primary system pressure must be greater than

150 psig to actuate these valves.

l- The' subject valves are fast acting valves (normally exercise in less than 2 seconds) and they do not.have stem / disk position indicators. Stroke timing of these valves is performed .

,- indirectly via turbine bypass valve position and relief valve L discharge-line temperature and acoustic alarms.

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1 Quad Cities Nucloor Pow 3r Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBERt RY-301 (Sheet 3 of 3)

PROPOSED ALTERNATE TESTING -)

The subjtet valves will be exercised once every six-(6) months during plant: operation. Relief Request RV-00F contains additional Alternate Testing information for 0203-003A-SO.

. Relief Request RV-00C contains additional Alternate Testing information for 0203-003A through E. l Stroke times will not be measured, and increased tast frequency l based on change in stroke time will not be implemented. As described in the Basis for Relief, Quad Cities will verify the l

. operability of the subject valves. I APPLICABLE TIME PERIOD Relief -is requested for the 2nd ten (10) year interval. f i

RELIEF REQUEST TYPE This is a Type 4-Relief Request (requires NRC approval). The.

fast acting valve discussion complies with NRC Generic Letter 89-04, Attachment 1,-Position 6.

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Quad Citico Nuclonr Powsr Station, Unito 1 &'2 INSERVICE TESTING PROGRAM - VALVES-

-(^g RELIEF REOUEST' NUMBER RV-30B (Sheet 1 of 2)

COMPONENT IDENTIFICATION IWV-2200- CODE ~DWG- '

VALVE NUMBER CATEGORY CLASS DBAEING NUMBER. SQQB Unit 1 i 0203-003A. B/C 1 M-0013-1 F-7 0203-004A- C 1 ~M-0013-1 7-8 0203-004B C 1 M-0013-1 D-5 0203-004C C 1 M-0013-1 C 0203-004D. C 1 M-0013 B-5 0203-004E C 1 M-0013-1 F-8 0203-004F C 1 M-0013-1 D-5 ;

0203-004G C 1 M-0013-1 C-5 0203-004H C 1 M-0013-1 B-5 Unit 2 0203-003A 1 M-0060-1. f B/C F-7 0203-004A C 1 M-0060-1 F-8 -;

-0203-004B C 1 M-0060-1 E-5 02Cc 004C C 1 M-0060-1 C-5 0203 004D C 1 M-0060-1 -B-8 '

, 0203-004E C 1 M-0060-1 F-8 j]

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-0203-004F C 1 M-0060-1 E-5 0203-004G C 1 M-0060-1 C-5 0203-004H C~ 1 M-0060-1 B-8 FUNCTION (8)

. Valve 0203-003A is a dual function Safety / Relief valve-manufactured.by Target Rock. The remaining valves are simple safety valves. These Main Steam Safety Valves are used to terminate an abnormal pressure incre se in the Reactor Vessel and

.the Reactor Coolant Pressure Boundary (i.e., they provide overpressure protection).

CODE REOUIREMENT Article IWV-3513, " Additional Tests," When any valve in the system fails to function properly during a regular test, additional valves in the system shall be tested.

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Quad.Citics Nucloar Powar Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REOUEST NUMBER: RV-30B'(Sheet 2 of 2)

BASIS FOR RELIEF In accordance with Technical Specification 4.6.E, at least half of the nine (9) safety valves are rebuilt during each refueling outage. This accelerated maintenance schedule provides adequate assurance <that these safety valves will perform thei'r safety function. i Quad Cities does not have the facilities required to perform setpoint tests on large relief and safety. valves. These valves are unbolted from their mounting flanger,, decontaminated,-and I shipped to-a' test facility. Since the valve has been decontaminated and. transported, the setpoint' initially measured 1 at the test facility is not necessarily representative;of the valve's. condition when it was installed in the plant. The test i facility cleans and rebuilds the valve, and adjusts the valve's setpoint in accordance with Technical Specification'4.6.E, and ships the valve back to Quad Cities.

Additional setpoint testing:is not appropriate for these valves.

The frequent maintenance performed on these valves should preclude any problem with valve setpoints. -

i PROPOSED ALTERNATE TESTING '

u At least half of the nine-(9) safety valves will be rebuilt and reset in accordance with Technical Specification 4.6.E during each reactor refueling outage.

1 APELEABLE_ TIME _ PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIET' REQUEST TYPE l l

This is a Type 4 Relief Request (requires NRC approval).

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Quad Citios Nuclcar Powcr. Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES ,

?' RELIXF_REOUEST NUMBER: RV-30C'(Sheet 1 of 2)

O L COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE' NUMBER CATECQX CLASS DRAWING NUMBER COOR Unit ~1 0220-081A. C NC M-0034-1 E-4 ;

-0220-081B' C NC M-0034-1 E-4 0220-081C C NC M-0034-1 E-4 0220-081D C NC M-0034-1 E-5 0220-081E C NC M-0034-1 E-5 ;

0220-105A C NC M-0034-1 D-4 0220-105B C NC M-0034-1 E 0220-105C- C NC M-0034-1 D-5 0220-105D C NC M-0034-1 D-5 0220-105E C NC M-0034-1 E-5 ,

Unit 2 0220-081A C NC M-0076-1 E-4 0220-081B C NC M-0076-1 E-4 0220-081C C NC M-0076-1 E-4 0220-081D C NC M-0076-1 E-6 0220-081E C NC M-0076-1 E-6 ,

e 0220-105A C NC M-0076-1 D-4 '

5 0220-105B C NC M-0076-1 E-4 0220-105C C NC M-0076-1 E-5 0220-105D C NC M-0076-1 D-5 0220-105E C NC M-0076-1 E-5 FUNCTION (8) j These Main Steam Safety / Relief Valve Discharge Line (MS S/RVDL) vacuum l breakers must'open to admit drywell atmosphere into the MS S/RVDLa. : Suppression Pool (Torus)-water would be sucked into the MS S/RVDL after a relief valve' actuation (as the steam in the line condenses) if these valves do not open. A subsequent relief valve actuation with an elevated water leg in the MS S/RVDL would s result'in large water clearing ~ transient loads that could damage the SIS S/RVDIA.- These valves are required to open for the

. Automatic Depressurization System (ADS) to perform its safety function.

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CODE REQUIREMENT !

. Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

0 Revision 3 VALVES 1-45

i Qutd Citis3' Nuclear Powar Station, Unito 1;& 2 l INSERVICE TESTING PROGRT_M - VALVES- )

l RELIEF REQUEST NUMBER: RV-30C (Sheet 2 of 2)'

BASIS FOR RELIEF

.These vacuum breakers (si mple check valves)_do not have remote position indication so there is no means available to verify that I these valves are normally closed, and then open following a relief valve actuation. Since these valves are located inside the drywell, they are only accessible when the containment is deinerted during a Cold Shutdown or Reactor Refueling.

.l 4 PROPOSED. ALTERNATE. TESTING l i

I These check valves areJat the end of the vacuum breaker line, and the disc is readily accessible for examination / testing. These check valves will fut exercised _open during reactor refueling: )

-outages by manually pushing the disk away from its' seat using a ,

-small diameter rod. After exercising the valve open, a visual i examination will be performed to verify that the disc returns to l 4

the closed position. These valves are also subject to a j preventive maintenance program which includes disassembly, ,

refurbishment, adjustments and force measurements prior to their I return to service. 1 APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIEF REOUEST TYPE This is a Type 4 Relief Request (requires NRC approval).

Revision 3 VALVES 1-46

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l Quad Citics Nuclocr Powsr Station, Unito 1 &2 l IHfERVICE TESTING PROGRAM - VALVES j g-

,( s "tELIEF 3EOUEST NUMBER RV-30D (Sheet 1 of 3)

'~# COMPONENT IDENTIFICATTON j IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS D_RAWING NUMBER pj2QB -

Unit 1 0203-001A-SO2 B NC M-0013-2. F-7

-0203-001B-SO2 B NC M-0013-2 F-7 0203-001C-SO2 B NC M-0013-2 F-7 0203-001D-SO2 B NC M-0013-2 F-7 i 0203-001A-SOAC B NC M-0013-2 ~ F-7 1 0203-001B-SOAC B NC M-0013-2 F-7 0203-001C-SOAC B NC M-0013-2 F-7 0203-001D-SOAC B NC M-0013-2 F-7 0203-001A-SODC B NC M-0013-2 F-7 1 0203-001B-SODC B NC M-0013-2 F-7 )

0203-001C-SODC B NC M-0013-2 F-7 0203-001D-SODC B NC M-0013-2 F-7

'i 0203-002A-SO2 B NC M-0013-1 F-4

0203-002B-SO2 B NC M-0013-1 F-4 l 0203-002C-SO2 B NC M-0013-1 F-4 0203-002D-SO2 B NC M-0013-1 F-4 1 0203-002A-SOAC B NC M-0013-1 F-4 l l['T!

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0203-002B-SOAC 0203-002C-SOAC B

B NC NC M-0013-1 M-0013-1 F-4 F-4 l

0203-002D-SOAC B NC M-0013-1 F-4 0203-002A-SODC B NC M-0013-1 F-4 L 0203-002B-SODC B NC M-0013 F-4 ?

0203-002C-SODC B NC M-0013-1 F-4 1 0203-002D-SODC B NC M-0013-1 F-4 1

l Unit 2 0203-001A-AP2 B NC M-0060-1 F-4 0203-001A-SOAC B NC M-0060-1 .F-4 0203-001A-S6DC B NC M-0060-1 F-4 l 0203-001B-All B NC M-0060-1 F-4 0203-001B-COk2 B NC M-0060-1 F-4 0203-001B-SODC B NC M-0060-1 F-4 :

0203-001C-AP2 B NC M-0060-1 F-4 1 0203-001C-SOAC B NC M-0060-1 F-4 l 0203-001C-SODC B NC M-0060-1 F-4 l 0203-001D-AP2 B NC M-0060-1~ F-4 l 0203-001D-SOAC B NC M-0060-1 F-4 .

0203-001D-SODC B NC M-0060-1 F-4 I i

0203-002A-AP2 B NC M-0060-2 F-7 0203-002A-AP4 B NC M-0060-2 F-7 I l

0203-002A-SOAC B NC M-0060-2 F-7 l

( 0203-002A-SODC B NC M-0060-2 F-7 0203-002B-AP2 B NC M-0060-2 F-7 ,

0203-002B-SOAC B NC M-0060-2 F-7

' Revision 3 -

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1 Qrem S;to3 Nucloer Powcr Station,.Unito 1 & 2

)) SERVICE TESTING PROGRAM - VALVES

[f . RELIEF REOUEST NUMBER RV-30D (Sheet 2 of 3)

L/di Unit 2 (cont'd)-

>< 0203-002B-SODC B NC M-0060-2 F-7 0203-002C-AP2 B NC M-0060-2 F-7 0203-002C-SOAC B- NC M-0060-2 F-7 0203-002C-SODC B NC - M-0060-2 F-7 0203-002D-AP2 B NC M-0060 F-7 0203-002D-SOAC B NC M-0060-2 F-7 0203-002D-SODC B NC M-0060-2 F-7 l

FUNCTIONIS) !

Valves in the 0203-001_-S02 and 0203-002_-S02 series are 2-Way-Valves with air pilot operators that gust open during a loss-of-instrument air event.- When these valves open, the Main Steam Isolation valve will close.

Valves-in the 0203-001 -SODC and 0203-002 -SODC series are the DC solenoids. .The DC solenoids must exercise to the de-energized position to close the Main Steam. Isolation Valves.

ValvesLin'the 0203-001 -SOAC and 0203-002 -SOAC series are the AC solenoids adjacent to the DC solenoids (not to be confused with.

the AC test solenoids). The AC solenoids must exercise to the '

r~T de-energized position to close the Main Steam Isolation valves.

ig CODE REOUIREMENT Article IWV-3411, " Frequency," Category B. valves shall be exercised.at least onca every 3 months, ;

except as provided by IWV-3412(a), IWV-3415, and. IWV-3416. v BASIS FOR RELIEF The 2-Way valves with air pilot operators are probably. exercised each time the associated Main Steam Isolation Valve (MSIV) is closed. Since these valves provide a second vent path independent of the 4-Way solenoid, it is extremely difficult to i determine whether the.MSIV closed via both the 4-Way solenoid and '

the subject 2-Way solenoid, or the 4-Way solenoid alone. A loss- l of-instrument air event must be simulated via a special test to provide conclusive evidence that the subject valve was exercised j open.- It is impractical to simulate a loss-of-instrument air i test during' normal operation or Cold Shutdown. l l

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-Quad Citics Nuclear Powar Station, Units 1.& 2' g INSERVICE TESTING PROGRAM - VALVES 7-RELIEF REOUEST'NUMBERt RV-30D'(Sheet 3 of 3)

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-The AC and DC solenoids are probably exercised each time the l associated MSIV is closed. Since the MSIV can be opened with one i of these two valves in the de-energized position, a routine- '

exercise of the MSIV will not confirm that both of these valves were exercised from the energized to the de-energized position.

Closure of the MSIV does confirm that both valves were either exercised from energized to de-energized, or that the solenoid remained in the fail safe (de-energized) position. A conclusive 1 test of these solenoid valves can be performed by alternately, I pulling the fuses for the AC and DC power supplies to these solenoids. Since this is a comp *icated test and MSIV position indication is temporarily lost when the DC power supply fuse is pulled,-it is impractical to perform this test during either normal operation or Cold Shutdown.

PROPOSED ALTERNATE TESTING The subject valves will be exercised during each reactor

. refueling outage. See Relief Requests RV-00E and RV-00F for additional information on Alternate Testing.

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\ APPLICABLE TIME PERIOD 1

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Relief is requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 5, Relief Request.

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l QuadTCitioc Nuclear < Pow 3r Station, Unito 1 & 2 l INSERVICE TESTING PROGRAM - VALVES !

RELIEF REQUEST NUMBERt RV-32A (Sheet 1-of 2)

O COMPONENT IDENTIFICATION-IWV-2200 CODE DWG i i1 - VALVE NUMBER CATEGORY CLASS DRAWING NUMBER .qqQB Unit 1- I

.0220-058A 0220-058B A/C 1 M-0015 E-3 j A/C M-0015 "

1 F-3 0220-059B C 1 M-0015 F-3 -)

0220-062A A/C 1 M-0015 E-3 1

'0220-062B A/C 1 M-0015 F-3 j Unit 2 _

l 0220-058A A/C M-0062

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1 E-2 0220-058B- A/C 1 M-0062 F-3 0220-059B. A 1 M-0062 F-3 0220-062A A/C 1 M-0062 E-2 0220-062B A/C 1 M-0062 F-3 rumptionist 1

Valves 0220-058A, 0220-058B, 0220-062A, and'0220-062B are Primary -!

' Containment Isolation Valves (PCIVs) for the Reactor.Feedwater.

system.

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Valves 0220-058B and 0220-062B must open, and valve 0220-059B must close, when High Pressure Coolant Injection (HPCI) performs 1 its safety function.

CODE REQUIREMENT Article IWV-3521, " Frequency," Check valves shall'be

exercised at least once every 3 months, )

except as provided by IWV-3522.

BASIS FOR RELIEF These valves cannot be tested closed during normal (power) operation because the Feedwater system is required to maintain reactor vessel / primary coolant level. A scram on low water level would occur if one of the subject valves was closed to perform an exercise test.

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Quad Citica Nuclear Powor Station, Units 1 & 2 l

INSERVICE' TESTING PROGRAM - VALVES l RELIEF REOUEST NUMBER RV-321 (Sheet 2 of 2)

BASIS FOR RELIEF (cont'd) l Valves 0220-058Aland 0220-062A cannot be tested closed during J Cold-Shutdown because the Reactor Water Clean-Up-(RWCU) system.is l required to be operable during Cold Shutdown to maintain reactor water chemistry and minimize thermal stratification in the '

reactor vessel. 'All.of these valves would be extremely difficult to , test during Cold Shutdown (even if RWCU was isolated)..

Domineralized~ water service connections are not available in the X-Area,,which is a special extension of Secondary Containment. ..

Domineralized water would be required to perform some type of I

reverse' flow- test' while the rest of the feedwater ~ header was i drained.- ~It is-impractical =to perform such complicated tests I during Cold Shutdown. H I

PROPOSED ALTERNATE TESTING The subject valves willibe exercised closed during each reactor refueling outage.

APPLICABLE TIME PERIOD rh 1 j). Rellef is requested for the 2nd ten (10) year interval.

l RELIEF REOUEST TYPE

.This'is a Type 4 Relief Request (requires NRC approval). , ,

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Qutd Cities Nuclear' Power Station, Units 1 & 2 g INSERVICE TESTING PROGRAM - VALVES n ;

SELIEF REOUEST NUMBER: RV-37A l COMPONENT IDFETIFICATION ]

IWV-2200 CODE 4 DWG VALVE NUMBER- CATEGORY CLASS DRAWING NUMBER C,QQR Unit 1

3799-031 A/C NC M-0033 B-3

. Unit 2

'3799-031 A/C NC M-0075 B-3 FUNCTIONfB)

The~ subject valve 11s in.the. Reactor Building Closed Cooling Water ;

(PBCCW) supply line to the drywell. It is the Primary l Containment Isolation Valve (PCIV) inside containment. !.

CODE REQUIREMENT

..p Article IWV-3521,- " Frequency," Check valves shall be exercised at least once every 3 months, BASIB FOR RELIEF

'The~ subject" valves cannot be closed during normal operation because.the:RBCCW system supplies cooling water to the Reactor xRecirculation pump and motor bearings, and the drywell-coolers.

'The-Reactor Recirculation pump and motor bearings would be L 1

damaged, and drywell temperature would increase if the subject check' valve was closed.

Since the subject valve is a simple clieck. valve with no position indication,'it cannot be tested without performing some type of reverse flow / leak test. This type of test is impractical to '

s perform during-Cold shutdown.

PROPOSED ALTERNATE TESTING The subject valves will be exercised closed durir7 each reactor ;

refueling' outage. ;

AEELLc4BLE TIME PERIOD LRelief is requested for the 'nd i ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 5-Relief Request.

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Qund Citico Nuclcar Powar Station, Unita:1'& 2 L

. INSERVICE TESTING PROGRAM - VALVES RELIEF REQUEST NUMBER: RV-434 COMPONENT. IDENTIFICATION IWV-2200 CODE DWG 1 VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR '

Unit 1 4399-046 A/C NC M-0058-3 D-5 Unit 2- 4 4399-046 A NC-' M-0058-3 A-4 -.

FUNCTION (8)

The subject valve is in-the clean Condensate supply line to the i drywell. -It is the Primary Containment Isolation Valve (FCIV) i outside containment.

.I CODE REQUIREMENT Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, r- except as provided by IWV-3522. ;

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BASIS FOR RELIEF Since the subject valve is a simple check valve with no position indication, it cannot be tested without performing some type of reverse flow / leak test. .This type of test is. impractical.to perform.during normal. operation and Cold Shutdown. ,

3 PROPOSED ALTERNATE TESTING The subject valve will be exercised closed during each reactor refueling outage.

APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE ; 1 This is a Type 5 Relief Request. ,

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QuQd CitiOO Nuclomr Powar-Station, Units 1 & 2' INSERVICE TESTING PROGRAM - VALVES.

RELIEF = REQUEST NUMBER: RV-461 (Sheet 1 of 2)

, ,O f COMPONENT IDBMTIFICATION IWV-2200- CODE .DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit-l' 4699-226 B NC M-0025 D-8 Unit 1/2 4699-226 -' -1/2 B NC M-0043 D-8 Unit 2 4699-226 B NC M-0072 D-9 FUNCTION (S)

These solenoid valves must cpen for the diepel starting air motors to engage with the diesel engine flywheel, and then air is admitted to the diesel starting air motors. The diesel starting air motors crank the-diesel:to starting-speed.- Once the diesel speed reaches 200 rpm, these solenoid valves close to disengage the starting air motors (and stop the-starting air motors).

CODE REOUIREMENT Article IWV-3417(a), " Corrective Action," Power!. operated valves that normally exercise in less than or equal to 10 seconds require more frequent testing if the comparison between the previous test and'the current test indicates that the stroke time has increased by 50% or:more.

BASIS FOR RELIEF The diesel generator start solenoid valves. full stroke in milliseconds. These valve are not equipped with close and open position indicators.

The acceptance criteria for these tests is based on'each diesel's start time. If the diesel starts within-ten (10) seconds in accordance with UFSAR Section 8.2.3.1, these valves are functioning properly.

Trending the stroke times of the diesel start solenoids is unnecessary because these valves are indirectly stroke timed and no meaningful correlation between the diesel start time and the stroke time can be obtained. Based on the conservative limits established for diesel start time, it is unnecessary to trend the O stroke times.

Revision 3 VALVES 1-54

Qugd Cities Nuclcar Powsr Station, Units 1 & 2 INSERVICE TESTING PROGRAM - VALVES

,. RELIEF REQUEST NUMBERt RV-461 (Sheet 2 of 2)

PROPOSED ALTERNATE TESTING Stroke times will not be measured, and increased test frequency based on change in' stroke time will not be implemented. As described in the Basis for Relief, Quad Cities will verify that

-the subject valves are operable by verifying that the associated diesel meets the starting time limits in UFSAR Section 8.2.3.1.

APPLICABLE TIME PERIOD 1

Relief is requested for the 2nd ten (10) year interval. l RELIEF REOUEST TYPE This is a Type 5 Relief Request.

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Qutd Citics Nuclcar Powar-Station, Unita 1 & 2 INSERVICE TESTING PROGRAM - VALVES jx RELIEF REOUEST NUMBER: RY-46B COMPONENT IDENTIFICATION IWV-2200 CODE DWG ,

. VALVE NUMBER C&TEGORY CLASS DRAWING NUMBER GQQE Unit 1 4699-047- A/C NC M-0025 .E-3 4

Unit'2 4699-047 A/C NC M-0072 E-6 FUNCTION (8)

The subject valve is in the Service Air supply line to the .i drywell. It is the Primary Containment Isolation Valve (PCIV) outside containment.

I CODE REOUIREMENT Article IWV-3521, " Frequency," Check valvan shall be exercised at least oncu every 3 months, '

except as provided by IWV-3522.

l. A d BASIS FOR RELIEF Since the subject valve is a simple check valve with no position indication, it cannot be tested without performing some type of l reverse flow / leak test. This type of test.is impractical to .I perform.during normal operation and cold-shutdown. l l

l PROPOSED ALTERNATE TESTING The subject valve will be exercised closed during each reactor refueling outage.

APPLICABLE TIME PERIOD Relief is' requested for the 2nd ten (10) year interval.

RELIEF REOUEST TYPE )

This is a Type 5 Relief Request.

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. Quad Citics NuclGar Powsr Station, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES RELIEF REODEST NUMBERt RV-47A (Sheet 1 of 2) l, f) :

COMPONENT IDENTIFICATION IWV-2200 CODE DWG -

VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR ;

Unit 1 0220-084A A/C NC M-0013-1 F-3 0220-084B A/C NC M-0013-1 F-3 0220-084C A/C NC M-0013-1 F-3 0220-084D A/C NC M-0013-1 F-3 0220-085A A/C NC M-0013-2 F-7. q 0220-085B A/C_ NC M-0013-2 F-7 i 0220-085C ' '

A/C NC M-0013-2 F-7 0220-085D A/C NC M-0013-2 F-7 i

.4799-281A A/C NC M-0024-2 P-2 ;

Unit 2 0220-084A A/C NC M-0060-1 F-3 0220-084B A/C NC M-0060-1 F-3 3 0220-084C A/C NC M-0060-1 F-3 0220-084D- A/C NC M-0060-1 F-3 ~;

0220-085A A/C_ NC M-0060-1 F-7 )

0220-085B A/C NC M-0060-1 F-7 0220-085C A/C NC M-0060-1 F-7 ;

0220-085D A/C NC M-0060-1 F-7 L (' ) - 4799-281A A/C NC M-0071-2 B-2 FUNCTION (S)

, These check valves are installed on che Main Steam Isolation Valve (MSIV) air actuator accumulators (0220-084A to D) and the Target Rock Safety / Relief Valve (SRV) air actuator accumulator (4799-281A). Since the Instrument Air system is not safety related, these check valves must close to retain compressed nitrogen in the local accumulator, and preserve sufficient

" power" to actuate the MSIV or SRV.

CODE REOUIREMENT l Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

Revision 3 VALVES 1-57

Qutd Citica Nuclocr Psw0r. Station, Unito 1 & 2 i INSERVICE TESTING PROGRAM - VALVES

. - RELIEF REOUR8T NUMBER: RV-47A (Sheet 2 of 2)

BA818 FOR RELIEF These check valves do not have remote position-indication and there is no. indirect means of determining that these check valves are closed. Since these valves are located inside the drywell, they are only accessible when the containment is de-inerted during Cold Shutdown or Reactor Refueling.

PROPOSED ALTERNATE TESTING These valves will be verified closed during the special accumulator check valve leak-test (AT-06) that is performed during each reactor refueling outage.

APPLICABLE TIME PERIOD Relief is requested for the 2nd ten (10) year interval.

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RELIEF REOUEST TYPE This is a Type 5 Relief Request.

i Revision 3 VALVES 1-58

Qund CitiG0' Nuclear Powsr Station, Units 1 &'2 ,

INSERVICE TESTING' PROGRAM - VALVES RELIEF REOUEST NUMBERt RY-47B (Sheet 1 of 2)

COMPQNENT IDENTIFICATION IWV-2200 CODE DWG.

VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1 4799-155 A/C NC M-0024-2 E-2 4799-156 A/C NC M-0024-2 E-3 4799-158 A/C NC M-0024-2 F-4 4799-159 A/C NC M-0024-2 F-4 Unit 2 4799-155 A/C NC M-0071-2 E-2 4799-156 A/C NC M-0071-2 E-3 4799-158 A/C NC M-0071-2 F-4 4799-159 A/C NC M-0071-2 F-4 FUNCTION (8)

. Valves 4799-155 and 4799-156 are Primary Containment Isolation l

Valves (PCIVs). on the Instrument Air supply to the drywell. The Main Steam Isolation Valve (MSIV) and Target Rock Safety / Relief g Valve (SRV) receive their air supply via this line.

Valves 4799-158 and 4799-159 are PCIVs on the Instrument Air supply to the Suppression Pool (Torus). The Torus /Drywell vacuum breakers receive their air supply via this line.

CODE REQUIREMENT Article IWV-3521, " Frequency," Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522.

, BASIS FOR RELIEF The drywell air supply check valves (4799-155 and 4799-156)

.cannot be~ closed during normal operatior. '.1ecause the MSIVs might i.

close when Instrument Air is isolated. 61nce-all of these valves

[ .are simple check valves with no position indication, they cannot l be. tested without performing some type of reverse flow / leak test.

l This type of test is impractical to perform during normal

-operation or Cold shutdown.

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Revision 3 VALVES 1-59

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Quad Citico Nuclear Powar Station, Unito 1 & 2 IESERVICE TESTING PROGRAM - VALVES

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' RELIEF REQUEST NUMBERt RV-47B (Sheet 2 of 2)

PRQPOSED ALTERNATE TESTING The subject valves will be exercised closed during each reactor refueling outage.

APPLICABLE TIME PERIOD Relief is. requested for the 2nd ten (10) year interval.

RELIEF REQUEST TYPE This is a Type 5 Relief Request.

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Quid CitiGD Nuclear Powar. Station, Unito 1 & 2 INSERVICE TESTING PROGRAM - VALVES' 7 RELIEF REOUEST NUMBER: RV-521 (Sheet 1 of 2)

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COMPONENT IDENTIFICATION IWV-2200 CODE DWG.

VALVE NUMBER CATEGORY CLASS DRAWING NUMBER QQQB Unit 1 5201- -SO B NC M-0029 D-4 Unit-1/2 5201- -SO -1/2 B NC M-0029- F-6 Unit 2 5201- -SO B NS M-0029 D-4 FUNCTIONfS) 1 These solenoid valves must open for the Diesel Fuel Oil Transfer '

Pumps (5203) to replenish the fuel' oil supply in the Diesel 011 Day Tank (5202).

CODE REOUIREMENT Article IWV-3417(a), " Corrective Action," Power operated valves that normally exercise in less

( than or equal to 10 seconds require.more frequent testing.if the comparison between-the' previous test and the current test indicates that the stroke time has increased by'50%<or more.

Article IWV-3417(b), " Corrective Action," Power operated-valve limiting value of_ full stroke l time.

l-l BASIS FOR RELIEF ,

The diesel fuel oil transfer-pump discharge solenoid valves full stroke _in milliseconds. These valves are not' equipped with close-and open position indicators.

PROPOSED ALTERNATE TESTING

! Stroke times will not be measured, and increased test frequency l

based on change in' stroke time will not be implemented. Quad cities will verify that the subject valves are open by verifying that the associated Diesel Puel 011 Day Tank can be re-filled following a diesel operability test.

Revision 3 VALVES 1-61

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Qund Citico Nuclear Powor Station, Units 1 & 2.

INSERVICE TESTING PROJRAM - VALVES

. 4 RELIEF REQUEST NUMBER: RV-521-(Sheet 2 of 2) .

APPLICABLE TIME PERIOD .

Relief is requested for the 2nd ten (10)-year. interval.

RELIEP REOUEST TYPE This is a Type 5 Relief-Request.

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VALVE

-COLD SHUTDOWN JUSTIFICATIONS l

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' Quad Citics Nuclear'Powar Station, Units l'and 2 '

INSERVICE TESTING PLAN - VALVES '

x m 2.0 COLD SHUTDOWN JUSTIFICATIONS m f-s :

k ,) .' In accordance with Article IWV-3412 or IWV-3522 of the Code,

' Quad-Cities will full. stroke exercise certain valves during '

Cold Shutdown if the valve cannot be exercised during. Normal Operation. The technical justification for exercising a r valve-during(Cold Shutdown rather than Normal Operation is provided in a' Cold Shutdown Justification.

2.1 Cold Shutdown Test Frecuency l

. Inservice valve testing at cold shutdown is valve testing which commences within two hours after the plant reaches a q cold shutdown condition but in no case later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months I after cold shutdown is reached. This testing continues until all valves are tested or the unit is ready for start-up. Completion of all testing is not a prerequisite to plant start-up Valve testing which is not completed during a cold shutdown shall be completed during subsequent cold shutdowns that may occur before refueling to neet the Code specified testing frequency. In the case of frequent cold shutdowns, valve testing need not be performed more often than once every three months.

.In the case of longer planned cold shutdowns, the testing i - gsc need not be started within the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months limitation. However,

'3 ) in these instances, all valve testing must be completed prior to startup. ;

NOTE It is expected that the required testing will normally be completed in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months following cold shutdown. However, ,

completion of all valve testing during cold shutdown is not j required if plant operating conditions will not permit the testing of specific valves. ,

2.2 Cold Shutdown Justification (s)

=A summary of Cold shutdown Justifications is provided in Table 2.0-1.

Cold Shutdown Justification numbers are in CS-NNA format, p where; ;

CS: Cold Shutdown Justification for Valve Inservice Testing l

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' Quad'Citics Nuclear Power Station, Unito 1 and 2

' INSERVICE TESTING PLAN ' VALVES NN:: 00 for general issues R

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The first two characters of the Equipment-Piece Number (system identifier) is used for system dependent cold Shutdown Justifications. ,

02 Reactor Recirculation and Nuclear Boiler-03 Control Rod Drive 4 07 Traversing In-Core Probe 10 Residual Heat Removal i

11 Standby Liquid Control 12 Reactor Water Cleanup (

13 Reactor Core Isolation Cooling *

.14 Core Spray 16 Containment-and Pressure Suppression 19 Fuel Pool Cooling and Cleanup 20 Radwaste (Drywell Sump) l 23 High Pressure Coolant Injection L 24 Containment Atmosphere Monitor 25 Atmospheric Containment Atmosphere' Dilution-30 Main Steam 32 Reactor Feedwater 33 Condensate (Clean and Contaminated) 37 Reactor Building Closed Cooling Water

(,r s) 39 Service Water 41 Fire Protection (Turbine and Diesel 011)~ ,

46 -Service Air !

47 Instrument' Air 48 Reactor Building Equipment Drains 49 Turbine Building Equipment Drains 52 Diesel Oil 54 Off Gas

57 Heating and Ventilating (Reactor Building Ventilation) ,

75 Standby Gas Treatment-89 High Radiation Sampling System A: A unique, sequential alphabetical character (e.g.,

CS-02A would address the Reactor Recirculation pump isolation valves).

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L Revision 3 VALVES 2-2 l

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i QUAD. CITIES NUCLEAR-POWER STATION, UNITS 1 AND 2

,, INSERVICS TESTING PLAN - VALVES -

I v_-) Table;2.0-1 I

COLD SHUTDOWN JUSTIFICATION SUMMARIES l COLD SHUTDOWN- l JUSTI-CATION

SUMMARY

CS-00A ,

These valves cannot be excercised during normal operation because of differential pressure against their valve seat, because they perform-a pressure isolation safety function, and because of reactor thermal shock considerations. They will be stroked at cold shutdown.

CS-02A These valves cannot"be stroked during power operation because to do so would require the isolation of one reactor.

recirculation loop, which is to be avoided because of potential neutron flux oscillation considerations. They.

/ will be stroked at cold shutdown.

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CS-02B This valve cannot be stroked during power operation because it is interlocked with the 0220-052 valve. Stroking the i valve at power induces a high differential pressure across the inner reactor head seal. Any leaks or imperfections in the seal would be compounded by the differential pressure causing a more severe leak or seal damage. [

CS-03A These valves cannot be tested during normal operation :

because the testing procedure requires the securing of the CRD pumps. This would result in the interuption of cooling water to the CRD seals,.which could damage them. They will be tested at cold shutdown.

CS-03B Control. Rod Drive ARI and Scram Dump Valves Exercise Test Frequency - These valves cannot be tested during normal operation because all CRDs would be inserted.

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

( Table 2.0-1 COLD SHUTDOWN JUSTIFICATION SUMMARIES COLD SHUTDOWN JUSTI-CATION SUMKARY CS-10A These valves cannot be stroked during operation because they isolate high pressure piping from low pressure-piping. They will be stroked at cold shutdown.

CS-10B These valves cannot be stroked during normal operation because they are required to remain open to link the two divisions of the RHR system for maximum core cooling flow.

They will be stroked at cold shutdown.

O CS-16A The valves cannot be tested during normal operation because a seat leakage / pressure. decay test is the only practical means of testing them. This is practical to perform only at cold shutdown. They will be tested at cold shutdown.

CS-23A These valves cannot be tested during normal operation-because they must remain open for the HPCI system to remain operable. They will be stroked at cold shutdown.

CS-37A These valves cannot be tested to the closed position during normal operation as they isolate water to the equipment in the drywell. Equipment affected by the stroking of these valves.must be secured prior to testing, which could result in damage to pump bearings, etc. They will be tested at cold shutdown.

Revision 3 VALVES 2-4

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Qusd Citloc Nuclear Powar Station, Units l'and 2-INSERVICE TESTING PLAN - VALVES COLD SHUTDOWN JUSTIFICATION I' h NUMBER CS-00A (Sheet 1 of 2)

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COMPONENT _ IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR ;

Unit 1 1001-068A-AO A/C 1 M-0039-1 E-5 1001-068B-AO A/C 1 M-0039-1 .E-4*

1402-009A-AO A/C 1 M-0036 -C-3 ,

1402-009B-AO A/C 1 M-0036 C-4 i

'2301-007 -AO C 2 M-0046 D-6 l Unit 2 1001-068A-AO A/C 1 M-0081-1 E-5 1001-068B-AO A/C 1 M-0081-1 E-4 1402-009A-AO A/C 1 M-0078 C-3 1402-009B-AO A/C 1 M-0078 C-4

~2301-007 -AO C 2 M-0087 E-6 PUNCTION(8) tN 7 Valves-1001-068A, 1001-068B, 1402-009A, and 1402-009B must close

(,,/' to isolate the Reactor Coolant Pressure Boundary. All of the subject valves must open when the associated Emergency Core Cooling System (ECCS) is required to inject water into the L reactor vessel. The ECCS number prefixes are 1001 - Residual Heat Removal (RHR), 1402 - Core Spray (CS), and 2301 - High Pressure Coolant Injection (HPCI).

JUSTIFICATION These check valves cannot be opened during normal operation using the air actuator because there is a 1000 psi differential pressure across the valve disk. The air operators on these valves cannot overcome a differential pressure of 1000 psi. The i air operators are capable of exercising the check valve when the i

differential pressure across the disk'is < 5 psi.- Since these valves are located in the drywell (CS and RHR) and the X-Area or D MSIV Room-(HPCI), it is impractical to enter these areas during H normal operation to equalize the pressure across the valve 1 obturator. Exercising these valves during normal operation would expose personnel to the following hazards: the drywell is inerted during normal' operation, the ambient temperature near these valves is between 120 and 140' F, and an accumulated radiation dose of '1.5 man-Rem.

O Revision 3 VALVES 2-5

-Quad Citioc Nuclear Powar Station, Units 1 and 2 INSERVICE TESTING PLAN - VALVER These check valves cannot be exercised during normal operation.

/O via a-full = flow test because the resulting cold water. injection 3s would produce reactivity excursions that would be extremely difficult-to control. The thermal shock to various1 Class 1 piping systems, reactor vessel nozzles, and. reactor vessel 1

internals would also be unacceptable. Finally,'the CS pump j discharge pressure (*350 psig) and RHR pump. discharge pressure

('400 psig) are too low to overcome normal reactor pressure and open the respective _ injection check valves.

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l Quad Citioc Nuclear Powsr' Station, Unita 1 and 2' JNSERVICE TESTING PLAN - VALVES COLD 8HUTDOWN JUSTIFICATION j-4 NUMBER: C8-02A v

COMPQNENT IDENTIFIQATIOF

-IWV-2200 CODE DWG l VALVE NUMBER CATEGORY CLASS DRAWING NUMBER- ,Q.Q.QB j

. Unit 1 0202-005A-MO B 'l M-0035-2 D-6 0202-005B-MO B 1 M-0035-2 D-3 Unit 2 0202-005A-MO B 1 M-0077-2 D-6

'0202-005B-MO B 1 .M-0077-2 D-3 FUNCTION (8) j Valves 0202-005A and 0202-005B are the RR pump discharge isolation valves. The RR pump suction and discharge isolation '

valves must close if there is a leak between the RR pump suction

.and discharge isolation valves. The RR pump discharge isolation valve must close upon receipt of a. Low Pressure Coolant Injection (LPCI) mode,, Residual Heat Removal LPCI Loop Selection logic signal.- Closure of.the RR pump discharge isolation valve ensures that LPCI flow is directed to the reactor core, rather than being l

diverted out a RR. system line break.

i JUSTIFICATION These valves cannot be closed during normal operation because one loop ~of the Reactor Recirculation system would have to be secured prior to performing the test. Single' loop operation is limited-by Technical Specifications and should-be avoided because coolant flow imbalances will lead to neutron flux oscillations. In addition, it.is impractical to reduce power as required for single loop operation for the sole purpose of performing an exercise test.

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Revision 3 VALVES 2-7

Quad' Cities Nuclear Powar Station, Unito 1 and 2 INSERVICE TESTING PLAN - VALVES, COLD SHUTDOWN JUSTIFICATION j p.; NUMBER C8-02B

,%I COMPONENT IDENTIFICATION IWV-2200 CODE DWG L VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR 4

Unit 1 0220-051 B 1 M-0035-1 E-5 Unit 2 0220-051 B 1 M-0077-1 E-5 FUNCTION (8)

Valve 0220-051 is the Reactor Head Flange Leak detector outboard ;

isolation valve. This valve must remain closed to isolate any leakage from the inner head seal. This valve is interlocked with the 0220-052 valve such that one valve is always closed.

JUSTIFICATIQE This valve cannot be stroked during normal operation because-of the anterlock with the inboard isolation valve. If these valves l: fs were stroked during power operation, a high differential pressure j'} .would be induced across the reactor inner head seal during the

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period that both valves were open. The resulting high' ;

differential pressure would cause additional damage to the inner '

head seal if a small leak-or any imperfection existed on the seal prior to the test.

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O Revision 3 VALVES 2-8

. Quad Citica Nucloer Powsr Station, Units 1-and 2

INSERVICE TESTING PLAN - VALVES QOLD SRUTDOWN JUSTIFICATION

() NUMBER C8-03A COMPONENT.. IDENTIFICATION IWV-2200 CODE . DWG .)

VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1- p 0305-115 C 1 M-0041-1 E-10 1

Unit 2 0305-115 C 1 M-0083-1 E-10 FUNCTION (8)

The Control Rod Drive,(CRD) charging water header check valves .

(typical of 177) must close when each CRD scram inlet valve (0305-126 -FCV)' opens and discharges the CRD Hydraulic Control Unit (HCU) accumulator into the CRD under-piston area to insert a control rod. If this CRD charging water header check 1 valve does not close, CRD:HCU scram drive flow may be diverted to the charging water header.

JUSTIFICATION These valves cannot be closed during normal operation because the CRD pumps would have to be secured, and accumulator. pressure

L monitored,:to verify valve closure. If the CRD pumps are L secured, cooling water to the-CRD seals would be interrupted and L the seals may be damaged.

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Revision 3 VALVES 2-9

I Quad Citico Nuclear Powar Station, Unito'1 and 2 INSERVICE TESTING PLAN - VALVES

,- :. COLD 8HUTDOWN JUSTIFICATION i NUMBER: C8-038 !

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COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER .QATEGORY CLASS DRAWING NUMBER COOR Unit 1 0302-020A B NC M-0041-1 E-8 0302-020B B NC M-0041-1 E-8 [

0302-025A B NC M-0041-1 E-7 0302-025B B NC M-0041-1 E-7 l 0302-181A- B NC M-0041-1. E-8 0302-181B B NC M-0041-1 E-8 0302-182A B NC M-0041-1 F-8 L 0302-182B B NC M-0041-1 F-8 Unit 2 0302-020A B NC M-0083-1 E-8 0302-020B B NC M-0083-1 E-8 0302-025A B NC M-0083-1 E-7 0302-025B B NC M-0083-1 E-7 0302-181A B NC M-0083-1 E-8 0302-181B B NC M-0083-1 E-8 IN '0302-182A B NC M-0083-1 F-8

\ss 0302-182B B NC M-0083-1 F-8 FUNCTION (8)

The Control Rod Drive Scram Air Header has multiple-vent paths to ensure reliability in case scram action is necessary. The 0302-020A and 0302-020B valves are the Scram Dump Valves. The remaining valves (030R-125A, 0302-25B, 0302-181A, 0302-181B, i

0302-182A and 0302-182B) are vent valves for the Anticipated Transient Without Scram / Alternate Rod Injection (ATWS/ARI) system. These valves must energized to provide a vent path to depressurize the Scram Air Header.

I JUSTIFICATION These valves cannot be exercised during normal operation because their actuation could lead to an unplanned rapid insertion of all control rods and the. closure'of the scram discharge volume vent and' drain valves. Because the 0302-020A and 0302-020B valves are in series and do not have individual position indication, the only positive method of determining that these valves open is to actuate both the A and B scram logic. The actuation of a single ARI/ATWS valve would result in the depressurization of the entire scram air header.

Revision 3 VALVES 2-10

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'Qutd-Cxties Nuclear Powor Station,-Units.1 and 2 INSERVICE TESTING PLAN - VALVES s

QOLD SHUTDOWN JUSTIFICATION L

'(; j -<[ NUMBERt C8-10A s-;

COMPONENT IDENTIFICATION o IWV-2200 CODE DWG L VALVE NUMBER . CATEGORY CLASS DRAWING NUMBER COOR Unit 1-1001-047 -MO A 1 M-0039-1 C-4 L 1001-050 -MO A 1 -M-0039-1 D-4 i Unit 2 1001-047-MO A 1 M-0081-1 C-4 1001-050-MO A 1 M-0081-1 D-4 FUNCTION (8) l These valves are Primary Containment Isolation Valves-(PCIVs) and Pressure Isolation Valves (PIVs) for the Residual Heat Removal l

(RHR) Shutdown Cooling mode suction line. Since Shutdown Cooling l- mode is not a safety related mode of RHR, the only safety <

function.these valve perform is closure for containment and pressure isolation. .

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l JUSTIFICATION l

1. These valves cannot.be opened and exercised closed during normal I operation. These valves isolate the-low-pressure design RHR Shutdown Cooling suction piping from_the reactor coolant pressure l boundary. The RHR Shutdown Cooling suction piping-is protected i by an interlock that ensures that these valves cannot be opened when' reactor pressure is greater than 100~psig.

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l Revision 3 VALVES 2-11

Quad Citiso' Nuclear Powor Station, Unito 1 and 2 INSERVICE TESTING PLAN - VALVES 1 COLD SHUTDOWN JU8TIFICATION

-y NUMBER C8-10B COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBETt CATEGORY CLASS DRAWING NUMBER COOR Unit 1 't 1001-019A-MO A 1 H-0039-1 B-8 1001-019B-MO A 1 M-0039-l' B-2 Unit 2' B-8

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-1001-019A-MO B 2 M-0081-1 1001-019B-MO B 2 M-0081-1 B-2 FUNCTIONtS)

.These valves'are located on the cross-tie between the "A" and "B" loops of the Residual Heat Removal (RHR) system. These valves must be-open when RHR is aligned in.LPCI mode and maximum core 1 cooling:( 15,000 gpm) is required. One of these valves must l close if RHR has to be aligned with one division in LPCI mode and ;

the other division in Containment cooling mode. . l JUSTIFICATION -l

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These valves should remain in the open position to ensure that the cross-tie line is available to link both divisions of RHR for maximum core cooling flow. Closing these valves during normal operation places the. system in an uncertain situation. q l

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l Revision 3 VALVES 2-12 L

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Qund Citico Nucisar Powar Station, Units 1 and 2 INSERVICE TESTING PLAN - VALVES

,_s COLD SHUTDOWN JUSTIFICATION l Y NUMBER: C8-16A a/

COMPONENT.. IDENTIFICATION IWV-2200 CODE DWG' VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR Unit 1 1601-020A-CK1 C NC M-0034-1 A-2 1601-020A-CK2 C NC M-0034-1 A-2 1601-020B-CK1 C NC M-0034-1 A-2' 1601-020B-CK2 C NC M-0034-1 A-2 1601-021 -CK1 C NC M-0034-1 A-2 1601-021 -CK2 C NC M-0034-1 A-2 1601-022 -CK1 C NC M-0034-1 A-2' ;

1601-022 -CK2 C NC M-0034-1 A 1601-023 -CK1 C NC M-0034-1 A-2 1601-023 -CK2 C NC M-0034-1 A-2 1601-024 -CK1 C NC M-0034-1 A-2 1601-024 -CK2 C NC M-0034-1 A-2 1601-056 -CK1 C NC M-0034-1 A-2 1601-056 -CK2 C NC M-0034-1 A-2 1601-060'-CK1 C NC M-0034-1 A-2 1601-060 -CK2 C NC M-0034-1 A-2 1601-063 -CK1 C NC M-0034-1 A-2

("'))

(_ 1601-063 -CK2 C NC M-0034-1 A-2 Unit 2 M-0076-1 1601-020A-CK1 C NC A-8 1601-020A-CK2 C NC M-0076-1 A-8 1601-020B-CK1 C NC M-0076-1 A-8 1601-020B-CK2 C NC M-0076-1 A-8 1601-021 -CK1 C NC M-0076-1 A 1601-021 -CK2 C NC M-0076-1 A-8 1601-022 -CK1 C NC M-0076-1 A-8 1601-022 -CK2 C NC M-0076-1 A-8 1601-023 -CK1 C NC M-0076-1 A-8 1601-023 -CK2 C NC M-0076 A-8 1601-024--CK1 C NC M-0076-1 A-8 i 1601-024 -CK2 C NC M-0076 A-8 1601-056 -CK1 C NC M-0076-1 A-8 1601-056 -CK2 C NC M-0076-1 A-8 ,

1601-060 -CK1 C NC M-0076-1 A-8 1601-060 -CK2 C NC M-0076-1 A-8 E 1601-063 -CK1 C NC M-0076-1 A-8 l 1601-063 -CK2 C NC M-0076-1 A-8 L

O Revision 3 VALVES 2-13

Quad Cities Nuclear Power Station, Unito 1 and 2 INSERVICE TESTING PLAN - VALVES f

COLD 8HUTDOWN USTIFICATION i NUMBERt C8-16h (cont'd)

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FUNCTION (8) ,

These check valves are installed on the fail safe air actuator- ;

accumulators in the Pressure Suppression system. 'Since the Instrument Air system is not safety related, these check valvos ;

must close to retain compressed nitrogen in the local accumulator, and preserve sufficient " power" to actuate the

" main" valve.

JUSTIFICATION These check valves do not have remote position indication and there is no indirect means of determining that these check valves are closed. The instrument air supply to these valves must be- ;

isolated, and a seat leakage / pressure decay test must be ;

Complicated-performed to verify-that these valves have closed.

testing of this nature is impractical to perform during normal operation.

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Revision 3 VALVES 2-14

'l Quad Citieo Nuclear Powsr-Station,-Units 1 and 2

~

~ INSERVICE TESTING' PLAN - VALVES

. COLD SHUTDOWN JUSTIFICATION }

h' NUMBER C8-23A tN-); ,

i COMPONRNT IDENTIFICATION IWV-22OO CODE DWG '

~ VALVE NUMBER CATEGORY CLASS DRAWING NUMBEB' COOR 6 nit' 1 2301-004 -MO A 1 M-0046 C-9 ,.

2301-005 -MO A 1 M-0046- B-10 t

. Unit 2 2301-004 -MO A 1 M-0087 C-9

-2301-005 -MO A 1 M-0087- B-10 i FUNCTION (8) i i These valves are Primary Containment Isolation Valves (PCIVs) on 1 the High Pressure' Coolant Injection (HPCI) steam supply line from !

l Lthe reactor vessel-to the HPCI turbine. These valves must open L (remain open) to-supply steam to the HPCI turbine. These valves ,

I are normally open so reactor steam will pre-heat the HPCI steam i line and ensure'that HPCI can start-up quickly.

I s JUSTIFICATION These valves should remain in the-open position to ensure that L steam will be supplied to the HPCI turbine, which drives the HPCI t i

l booster and main pumps. Closing these valves during normal l operation places the system in an uncertain situation. If either j

of the subject valves were to fall closed during the test, the ;

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HPCI-system would have to be declared inoperable. t f

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Revision 3 VALVES 2-15 L'

l Quad Citios Nuclear Powar Station, Unite'l-and 2 I INSERVICE TESTING PLAN - VALVES COLD SHUTDOWN JUSTIFICATION

(~'y NUMBER C8-37A bu I l 1

COMPONENT IDENTIFICATION IWV-2200 CODE DWG VALVE NUMBER CATEGORY CLASS DRAWING NUMBER COOR l I

Unit 1 3702- -MO A NC M-0033 B-3 '

3703- -MO A NC M-0033 B-1 l 3706- -MO: A NC M-0033 B-1~ i Unit 2 3702- -MO A NC M-0075 B-3 3703- -MO A NC. M-0075 B-1 3706- -MO A NC M-0075 -B-1 FUNCTION (8)

These valves are Primary Containment Isolation Valves.(PCIVs) on the Reactor Building Closed Cooling Water (RBCCW) supply and return lines to the drywell.

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( JUSTIFICATION 4

l These valves cannot be closed during normal operation because the-RBCCW system supplies cooling water to the Reactor Recirculation .

(RR) pump and motor bearing coolers and the drywell air coolers.

Interrupting the cooling water supply to the RR pump or motor bearings for even a short time could result in damage to the pump bearings.

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Revision 3 VALVES 2-16

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_ Quad Cition Nuclear. Power Station, Unito 1 and.2 INSERVICE TESTING PROGRAM - VALVES ,

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f VALVE TECHNICAL APPROACE AND' POSITIONS i

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i Revision 3 VALVES 3-1 j ._

Quad Cities Nuclear Powsr Station,'Unita 1 and 2 INSERVICE TESTING PROGRAM - VALVES h 1

/~'T ' 'J . 0 TECHNICAL APPROACH AND POSITION 1

}~ )' 1 When.the requirements of the Code are not easily l interpreted,. Quad Cities has reviewed general. -l licensing / regulatory requirements and industry practice to determine a practical method of implementing each Code requirement. The Technical Approach and' Position documents in this-section of the Plan have been.provided to clarify Quad Cities' implementation of the Code.

a summary of Technical Approach and Positions is provided in Table 3.0-1. j i

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Revision 3 VALVES 3-2

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QUAD C??IES NUCLEAR POWER STATION, UNITS 1 AND 2

(~T) INSERVICE TESTING PLAN - VALVES ,

t

'~ Table 3.0-1 i

TECHNICAL APPROACH AND POSITION SUMMARIES l

TECHNICAL APPROACH AND POSITION

SUMMARY

TV-00A Maximum stroke times are established using multipliers and the reference stroke time value. For SOVs with Tr <For2s, MOVs Tmax = 2s. For MOVs with Tr < los, Tmax = 2.0Tr.

with Tr > los, Tmax = 1.75Tmax. For AOVs/HOVs, Tmax = 2.0Tr. In all cases,.if the Tech. Spec. maximum stroke time is less than that calculated using the multipliers, the Tech. Spec stroke time will apply.

TV-00B The 10CFR50, Appendix J, Type C Local Leak Rate Test (LLRT) of this valve is performed in the reverse direction.

Testing in the reverse direction is justified in the Appendix J Program.

f N).)

TV-00C The 10CFR50, Appendix J, Type C Local Leak Rate Tests (LLRT) <

of these valves do not yield valve specific seat leakage measurements (i.e., the valves are tested as a group). The leakage limit assigned to these valves is the limit for the entire group of valves-at the penetration. This test method is justified in the Appendix J Program.

TV-00D Stroke times for power operated valves will be measured as the time interval between placing the valve control switch in the open, close, etc. position and an indication (usually a light) that the valve has reached the intended position.

TV-00E Air Pilot and Solenoid Valves that Control a " Main" Valve Do Not Have Position Indication; Therefore, No Maximum Stroke Time and No Criteria for More Frequent Testing - The operability of air pilot and solenoid control valves will be based on the performance of the " main" valve.

Revision 3 VALVES 3-3 i

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

[

INSERVICE TESTING PLAN - VALVES Table 3.0-1 TECHNICAL APPROACH AND POSITION SUMMARIES f

TECHNICAL APPROACH AND POSITION

SUMMARY

i TV-00F For safety and relief valves, only the operational readiness test of PTC 25.2-1976 will be performed.

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TV-00G During valve position indication testing, only the remote position indicator used during ASME Section XI valve excercising and stroke timing will be verified to be operable.

TV-00H This pressure isolation valve is not leak tested with water.

Rather, the water leakage is determined using mathematical correlation to the LLRT test results.

j TV-00I Technical Approach for Fail Safe Testing 2-way, 3-way, or 4-way Air Pilot and Electric Solenoid Valves - Most air pilot and electric solenoid valves do not require any additional fail safe testing. In most cases, a stroke excercise test and a fail safe test are equivalent.

l TV-03A There are 177 CRD Hydraulic Control Units (CRD HCOs). Each CRD HCU contains one of these valves. The valve-number listed in Table 4.0-1, " Valve Listing" is typical of 177.

All 177 valves will be tested as specified for the typical valve.

b Revision 3 VALVES 3-4

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QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 O INSERVICE TESTING PLAN - VALVES t '"j Table 3.0-1 l

l TECHNICAL APPROACH AND POSITION SUMMARIES TECHNICAL APPROACH AND POSITION

SUMMARY

TV-03B Rupture Diaphragms tagged with this technical approach and position are not of a testable design. Therefore in accordance with IWV-3620, these rupture diaphragms will not be tested. (TV-03A also applies.)

I TV-07A The TIP shear valves cannot be seat leak tested due to !

their design / operating characteristics. The assembly would have to be replaced if the TIP shear valve explosive actuator was detonated to crush the TIP guide tube and 1 perform a seat leak test. This position is justified in the

(} Appendix J Program.

l \/ 1 TV-16A Individual leak rates for the drywell/wetwell vacuum breakers cannot be measured. Therefore, a " decay rate less I than a one inch orifice" acceptance criteria is applieu l collectively to all twelve vacuum breakers. ;

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Reference:

Technical Specification 4.7.A.4.b.4 l

TV-23A Rupture Diaphragms tagged with this technical approach I and position are not of a testable design. Therefore in accordance with IWV-3620, these rupture diaphragms will not be tested.

TV-30A Rupture Diaphragms tagged with this technical approach I and position are not of a testable design. Therefore in I accordance with IWV-3620, these rupture diaphragms will I not be tested.

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Revision 3 VALVES 3-5

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 3.0-1 TECHNICAL APPROACH AND POSITION SUMMARIES TECHNICAL APPROACH AND POSITION

SUMMARY

TV-30B Main Steam Electromatic Relief Valves - The pressure switches will be calibrated to verify setpoints and an excercise test will verify valve operability. The requirement to verify relief and safety valve setpoints in accordance with PTC-25.2-1976 is not applicable to these valves.

TV-30C The preferred stroke times for the main steam isolation valves are as follows:

3.75 to 5.00 secs. - Hot Stand-by with no Steam Flow 3.50 to 5.00 secs. - 200 MWe or greater 3.00 to 5.00 secs. - 500 MWe or greater

Reference:

QOS 0250-S02, page 1 O The Technical Specification limit is 35t<5.

O Revicion 3 VALVES 3-6

.. . _ . . - _ - . - . _ _ . - - - . . . . - . . . . . . . . - . - - . - - - . ~ . - - . - .- - . . -- . . . . . -

Quad Citioc Nucicor Pow 3r Station, Unita 1 and 2 INSERVICE TESTING PROGRAM - VALVES VALVE PROGRAN LISTING .

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l l' Revision 3 VALVES l- 4-1 L

Y Qund Citio3 Nuclear Pow 0r Statien, Unito 1 and 2 INSERVICE TESTING PROGRAM - VALVES 4.0 PROGRAM LISTING Table 4.0-1, " Valve Listing" lists all valves included in the Quad cities Nuclear Power Station, Unit 1 IST Program.

Table 4.0-2, " Valve Listing" lists all valves included in the Quad Cities Nuclear Power Station, Unit 2 IST Program.

The data contained in this Table identifies all valves subject to inservice testing, the type of inservice test, the inservice testing frequency for each inservice-test, and any applicable remarks.

The headina on each page includes the following information:

o P&ID Number The Piping and Instrumentation Diagram number. If the valve appears on multiple P& ids, the primary P&ID will be listed. The primary sort for the Valve Listing is P&ID Number.

o Drawing Title (System Name)

The drawing title, as it appears in the lower right corner of the P&ID.

O The column headinas in the Table are listed and explained i below: l o Valve Number l

l The unique number that identifies the valve will be !

listed. The secohdary sort for the Valve Listing is i Valve Number. l o Dwg Coor The coordinate location (e.g., D-5) on the P&ID where the valve appears, o IST Class The ISI classification as shown on the P&ID. ,

o Function Category A: Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function i O B: Valves for which seat leak &ge in the closed position is inconsequential for fulfillment of their function Revision 3 VALVES l 4-2 )

i

r-Qutd Citico Nucloor Pow 3r Station, Unito 1 and 2 INSERVICE TESTING PROGRAM - VALVES f C: Valves which are self-actuating in response to

\ some system characteristic, such as pressure-1 (relief valves) or flow direction (check valves) l D: Valves which are actuated by an energy source L capable of only one operation, such as rupture L disks or explosive-actuated valves (See Table 4.2-3) o eine (Inch)

The nominal pipe size of the valve, in inches. If the valve size is listed as ".001," the valve diameter is smaller than 1.000".

o Body style The valve's body style (e.g., "BTF" for a butterfly valve), per Table 4.2-2 o Actuator The type of actuator provided with the valve body 1 (e.g., "MO" for a motor operated valve or "SA" for a '

self-actuated valve such as a check valve), per Table !

( 4.2-1 o Normal Position L The valve's position during normal plant operation, per l Table 4.2-4. NOTE: If the subject system does not

! operate during normal (power production) operation, the l l valve's normal position is the position of the valve l when the system is not in operation.

o Test Type (and Stroke Direction)

The test type is an abbreviation for the typa of test to be performed and the direction the test will be performed, per Table 4.2-6. !

For a seat leakage test, the abbreviation will define the type of leak test (e.g., a 10CFR50, Appendix J, Type C local leak rate test of a containment isolation valve or a pressure isolation valve seat leak test).

For an exercise test, the abbreviation will define the type of exercise test and the stroke direction associated with the test (e.g. a check valve stroke test to the closed position).

O Revision 3 VALVES 4-3

Qutd citico Nucloor Powor Station, Unito 1 and 2 INSERVICE TESTING PROGRAM - VALVES o Test Freq The test frequency associated with each test type will be specified, per Table 4.2-5.

o Relief Request If a Relief Request is included in Section 1.0, the Relief Request number will appear.

o cold shutdown Justification If a Cold Shutdown Justification is included in Section 2.0, the Cold Shutdown Justification number will appear.

o Technical Approach and Position When appropriate, clarifying remarks concerning Quad Cities' technical approach and position have been included in Section 3.0.

The footina after each valve includes the following informations

() o Alternate Valve Number (Optional)

The Nuclear Steam Supply System vendor's valve number.

o Description The function performed bf the valve will be described.

O Revision 3 VALVES 4-4

Qu2d Citio3 Nuclocr Powor Staticn, Unito 1 cnd 2 INSERVICE TESTING PROGRAM - VALVES l

4.1 Valve Listina (sorted by Valve Number)

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A Unit i Valve listing sorted by valve number is included in Table 4.1-1. A Unit 2 Valve listing sorted by valve number is included in Table 4.1-2. These listings will help the person who does not know the correct P&ID number find the valve in Tables 4.0-1 and 4.0-2, " Valve Listing".

4.2 Abbreviations Abbreviations that appear in the Valve Listing are included in the following Tables:

Table Abbreviation Listina 4.2-1 ACTUATOR 4.2-2 BODY STYLE 4.2-3 FUNCTION CATEGORY 4.2-4 NORMAL POSITION 4.2-5 TEST FREQUENCY f) 4.2-6 TEST TYPE O

Revision 3 VALVES 4-5

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING M 0013 1 DRAWING TITLE t MAIN STEAM PIPING RELIEF NORMAL RE0VE ST DWG IST FUNCT10N SIZE BODY ACTU- POSl* TEST TEST OR COLD TECNNICAL VALVE NUMBER COOR' CLASS CATE GORY (INCN) STYLE ATOR T10N TYPE FREO $NUTDOWN PDSITION 0203 001A A0 F.4 1 A 20.000 GL ho 0/FC AT 01 RR STC M3 Tv 30C FST M3 PIT Y2 FUNCTION MAIN STEAM ISOLATION VALVE 0203 001A AP2 F.4 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 30D FUNCTION t MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 001A 50AC F4 NC B .001 503 So E BTD RR tv 300 FST kt Rv 300 FUNCTION t MAIN STEAM ISOLAfl0N VALVE ACT. 3 WAY AC CONTROL SOLEW010 0203 001A 500C F4 NC B .001 S03 B0 E BTD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL SOLEN 010 0203 0018 A0 D4 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 Tv 30C FST M3 PIT Y2 FUNCTION t MAIN STEAM ISOLAfl0N VALVE 0203 0018 AP2 F*4 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 300 FUNCTION t MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 0018 AP4 F4 NC B .001 804 50 E BTD M3 FST M3 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAT AIR PILOT VALVE n

0203 0018 50AC F4 NC B .001 $03 50 E BTD RR RV 300 FST RR RV 300 FUNCT!DN t MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL $0LENotD 0203 0018 $00C F4 NC B .001 S03 50 E BTD RR tv 300 Revision 3 VALVES 46

BUAD CITIES MUCLEAR POWER STAfl0N, UNITS 1 AND 2 r

O INSERVICE TESTING PLAN VALVES Table 4.01 UNIT 1 VAtVE LISTING DRAWING t M 0013 1 DRAWING TITLE I MAIN STEAM P! PING RELIEF WORMAL REQUEST DWG IST FUNCil0N SIZE BODY ACTU* POSI- TEST TEST OR COLD TECHNICAL VALVE NUMSER COOR CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FRED SMUIDOWN POSITION 0203 0018 $0DC F4 NC B .001 S03 to E FST RR FUNCTION I MAIN STEAM ISOLAfl0N VALVE ACT. 3 WAY DC CONTROL SOLENCID 0203 001C A0 C4 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV 30C FST M3 PIT Y2 FUNCTION MAIN STEAM ISOLATIDW VALVE 0203 001C AP2 F4 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 30D I FUNCTION I MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 001C AP4 F4 NC B .001 $04 to E BTO M3 FST M3 l FUNCTION MAIN STEAM !$0LATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE l

0203 001C SOAC F4 NC B .001 303 50 E BTD RR RV 300 FST RR RV 30D FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3 WAY ; CONTROL SOLENCID 0203 001C SODC F4 NC B .001 303 So E BTD RR RV 300 FST RR RV 300

I FUNCTION MAIN STEAM ISOLAfl0N VALVE ACT. 3 WAY DC CONTROL SOLEN 0ID 0203 0010 A0 B4 i A 20.000 CL A0 0/FC AT 01 RR STC M3 Tv 30C FST M3 Pli Y2 FUNCTION : MAIN STEAM ISOLATION VALVE 0203 0010 AP2 F-4 NC B .001 PLT A0 E BTD RR RV 300 1

FST RR Rv-300 l FUNCTION MAIN STEAM !$0LAfl0N VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 001D AP4 F4 NC B .001 $04 S0 E BTD M3

[_ FST M3 i (

Revision 3 VALVES 47

ouAD CITIES WUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UWlf 1 VALVE LISTING DRAWING t M 0013 1 DRAWING TITLE MAlW STEAM P! PING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Poll

TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREO SNUTDOWN Postfl0N FUNCTION : MAIN STEAM ISOLAfl0W VALVE ACTUATOR 4 WAT AIR PILOT VALVE 0203 0010 80AC F4 NC B .001 S03 80 E BTD RR 'RV 30D FST RR RV 30D FUNCTION 4 MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL SOLENCID 0203 0010 SODC F4 NC B .001 S03 So E BTD RR RV 30D FST RR RV 30D FUNCTION 3 MAIN STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL $0LEN010 0203 002A AP4 F4 NC B .001 804 So E BTD M3 FST M3 FUNCTION 3 MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILDT VALVE 0203 003A F7 1 B/C 6.625 Say SAP C BTC M6 RV 30A TV 30R BT0 M6 RV 30A TV 308 CT SP Y5 Rv 303 Plf Y2 FUNCTION t MAIN STEAM - SAFETY / RELIEF VALVE (TARGET ROCK) 0203 003A 80 F7 NC B .001 S03 30 D BTD M6 RV 30A BTE M6 av 30A FUNCTION t MAIN STEAM - SAFETY /P.ELIEF VALVE (TARGET ROCK) SOLEN 010 0203 003B E6 1 5 6.000 RV SO C BTC M6 RV 30A BTO M6 RV 30A Pli Y2 FUNCTION 3 MAIN STEAM ELECTROMATIC REllEF VALVE 0203 003C C8 1 B 6.000 RV 20 C BTC M6 RV 30A BTO M6 RV 30A PIT Y2 FUNCTION t MAIN STEAM ELECTROHATIC RELIEF VALVE 0203 0030 B8 1 B 6.000 RV $0 C BTC M6 RV 30A BTD M6 RV 30A PIT Y2 Revision 3 VALVES 48

GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0013 1 DRAWING TITLE : MAIN STEAM PIPING

! RELIEF NORMAL REQUE$T DWG IST FUNCTION SIZE 80DY ACTU- Post- TES? TEST OR COLD TECHNICAL VALVE NLAstER C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION FUNCTION : MAIN STEAM

ELECTROMATIC RELIEF VALVE 0203 003E E8 1 3 6.000 RV So C BTC M6 RV 30A Bio M6 RV<30A Plf Y2 FUNCTION : MAIN STEAM ELECTROMATIC RELIEF VALVE 02C3 004A F8 1 C 6.000 SV SA C CT SP Y5 RV 30s PIT Y2 FUNCTION : MAIN STEAM SAFETY VALVE 0203 004A RPD F8 NS 0 8.000 RPO SA C DT M NT TV 30A FUNCTION : MAIN STEAM + SAFETY VALVE DISCNARGE RUPTURE DI APNRAGM 0203 0048 E5 1 C 6.000 SV SA C CT SP Y5 RV 30s PIT Y2 FUNCTION MAIN STEAM

SAFETY VALVE 0203 0048 RP0 D5 Na D 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAlW STEAM . SAFETY VALVE D!nCNARGE RUPTURE DIAPNRAGM 0203 004C C5 1 C 6.000 SV SA C CT SP Y5 RV 30s Plf Y2 FUNCTION : MAIN STEAM SAFETY VALVE 0203 004C RP0 C5 NS 0 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPNRAGM 0203 004D t5 1 C 6.000 SV SA C CT SP Y5 RV 30s Plf Y2 FUNCTION : MAIN STEAM SAFETY VALVE 0203 0040 RP0 B5 NS 0 8.000 RPO SA C DT M NT Iv 30A FUNCTION : MAIN STEAM SAFETY VA6VE DISCNARGE RUPTURE DIAPHRAGM 0203 004E F8 1 C 6.000 SV SA C CT SP V5 RV 30s Plf Y2 Revision 3 VALVES 49 l

1 l

I 1

OuAD CITIES WUCLEAR POWER STAfl0W, UNITS 1 AND 2 1 INSERVICE TESTING PLAN VALVES 1

Q Table 4.0 1 UNIT 1 VALVE LISTING DRAWING: M 0013 1 DRAWING TITLE : MAIN STEM PIPING RELIEF j NORMAL REQUEST DWG IST FUNCTION SIZE toDY ACTU- P051- TEST . TEST OR COLD TECHNICAL C00R CLAll CATEGORY (INCN) STYLE ATOR T10N TYPE FRE0 SHUTDOWN Postfl0N VALVE NUMBER

)

FUNCTION MAIN STEAM SAFETY VALVE 0203 004E RP0 F8 NS 0 8.000 RPD SA C DT M NT TV 30A q FUNCTION MAIN STEAN SAFETY VALVE DISCNARGE RUPTURE DIAPMRAGM 0203 004F E5 1 C 6.000 SV SA C CT SP Y5 RV 30s PIT Y2 ,

FUNCTION : MAIN STEAM SAFETY VALVE 0203 0047 RPD D.5 NS D 8.000 RPD SA C DT M NT TV 30A I

j e- FUNCTION MAIN STEAM SAFETY VALVE DISCNARGE RUPTURE DIAPNRAGM k

0203 004G C5 1 C 6.000 SV SA C CT SP Y5 RV 30s Plf Y2 FUNCT!0N MAIN STEAM SAFETT VALVE i 0203 004G RPD C5 NS- D 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPNRAGM ;

0203 004H 85 1 C 6.000 SV SA C CT SP Y5 RV 30s PIT Y2

! FUNCTION : MAIN STEAM SAFETY VALVE 0203 004N RPD S5 NS D 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPNRAGM 0220 001 M0 E4 1 A 3.000 GA M0 C AT 01 RR BTC M3 PIT Y2 FUNCTION : MAIN STEAM LINE DRAIN ISOLAfl0N VALVE 0220 084A F3 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV-47A l '

FUNCTION : MAIN STEAM ISOLATION VALVE ACCLBULATOR CHECK VALVE 0220 0848 F3 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV 47A 1

Revision 3 VALVES 4 10

auAD CITIES NUCLEAR P0hiER STATION, Ut'ITS i AND 2 INSERVICE TESTING PLAN

VALVES

~b Table 4.0 1 UNIT 1 VALVE LISTING s

DRAWING : M 0013 1 DRAWING TITLE : MAIN STEAM P! PING RELIEF NORMAL REcutST DWG IST FUNCTION SIZE 80DY ACTU- PO$la TEST TEST OR COLD TECHNICAL VALVE NLMBER C00R CLASS CATE00RY (INCN) STYLE ATOR T10N TYPE FREG SNUTDOWN POSITION FUNCTION : MAIN STEAM ISOLAfl0N VALVE ACCUEJLATOR CHECK VALVE l

0220 084C F3 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV 47A FUNCTION : MAIN STEAM ISOLATION VALVE ACCUNULATOR CHECK VALVE 0220 084D F3 NC C 1.000 CK SA STS AT 06 T2 CTC RR RV 47A FUNCTION : MAIN STEAM ISOLAfl0N VALVE ACCUNULATOR CHECK VALVE l

I -

n-l l'

l l

l O

Revision 3 VALVES i 4 11

BuAD CITIES NUCLEAR POWER STAT!0N,t* NITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0-1 UNIT 1 VALVE LISTING DRAWING 14 0013 2 DRAWING TITLE : MAIN STEM PIPING RELIEF NORMAL REGUEST DWG IST FUNCTION SIZE 900T ACTU. Post. TEST TEST OR COLD TECHNICAL VALVE NUI4BER C00R CLASS CATE00RT (INCN) STTLE ATOR TION TTPE FREQ SMUTDOWN Pollfl0N

.................. .... ..... ........ ...... ..... ..... ...... ..... .... .....e.. ........-

0203 001A AP4 F7 NC B .001 804 80 E STD I43 FST M3 FUNCTl0N t 14AIN STEAM ISOLAfl0N VALVE ACTUATOR 4*WAT AIR PILOT VALVE 0203 002A.A0 F.7 1 A 20.000 GL A0 0/FC AT.01 RR BTC st3 TV 30C FST IG Plf T2 FUNCitou MAIN STEAM ISOLAftou VALVE 0203 002A AP2 F.7 NC 8 .001 PLT A0 E STD RR RV 300 FST RR RV.33 FUNCTION IIAIN STEAM ISOLAfl0N VALVE ACTUATOR 2 WAT Alk PILOT VALVE 0203 002A 80AC F.7 NC B .001 803 to E BTD RR RV 30D FST RR RV 30D FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3 WAT AC CONTROL 50LEN010 0203 002A.80DC F7 NC B .001 803 30 E STD RR RV 300 FST RR RV 300 -

FUNCTION : MAIN STEAM ISOLAfl0N VALVE ACT. 3 WAT DC CONTROL SOLENCID 0203 0028 A0 E.7 1 A 20.000 GL A0 0/FC AT 01 RR STC M3 TV 30C FST M3 PIT T2 FUNCTIDW 9tAIN STEAM ISOLATION VALVE 0203 0028 AP2 F7 NC e .001 PLT A0 E STD RR RV 30D FST RR RV 300 FUNCTION MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAT AIR PILOT VALVE 0203 0028 AP4 F7 NC t .001 SO4 30 E BTD M3 FST M3 FUNCTION : MAIN STEAM ISOLAfl0N VALVE ACTUATOR 4 WAT AIR PILOT VALVE 0203 0028 SQAC F7 NC 8 .001 303 80 E BTD RR RV 300 Revision 3 VALVES 4 12

GuAD CITIE$ NUCLEAR POWER STAT!Du, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES J Table 4.0 1 ,

UNIT 1 VALVE LitTING i DRAWING : M 0013 2 DRAWING TITLE : MIN STEAM PIPING RELIEF NORMAL REQUEST DWG !$T FUNCTION $12E BODY ACTU- Post- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLA$$ CATEGORY (INCN) $TYLE ATOR T10N TYPE FREO $NUTDOWN POSITION' 0203 0028 90AC F7 NC 8 .001 303 to E FST RR RV 30D FUNCTION : MAIN STEAM l$0LAfl0W VALVE ACT 3 WAY AC CONTROL SOLEN 0ID I I

0203 0020 80DC F7 NC 8 .001 303 to E BTD RR RV 300 l FST RR RV 300 FUNCTION : MAIN STEAM !$0LAfl0N VALVE ACT. 3 WAY DC CONTROL SOLEN 0ID l

0203 002C A0 07 1 A 20.000 GL A0 0/FC AT 01 RR l ITC M3 TV 30C l

F$f M3 I Plf Y2 I I-(

FUNCil0N : MAIN STEAM ISOLAfl0N VALVE l

i 1

0203 002C AP2 F7 NC B .001 PLT A0 E BTD RR RV 300 j FST RR RV 30D FUNCil0N MAIN STEAM l$0LAfl0N VALVE ACTUATOR 2 WAT AIR PILOT VALVE l

0203 002C AP4 F7 NC B .001 304 80 E STD M3 )

FST M3 j FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE I

l l 0203 002C $0AC F7 NC B .001 303 to E BTD RR RV 300 l

FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL 80LEWotD 0203 002C 300C F.7 NC 8 .001 803 so E BTD RR RV 300 FET RR RV 300 FUNCTION : MAIN $ TEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL $0LEW010 0203 002D A0 B7 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 Tv 30C FST M3 PIT Y2 FUNCTION : MAIN STEAM is0LATION VALVE 'l l

0203 002D AP2 F7 NC B .001 PLT A0 E BTO RR RV 300 FST RR RV 300 l

Revision 3 VALVES 4 13

. - = - . - --

euAD CITIES NUCLEAR POWER STAtl0N, UNITS 1 AND 2 INSERVICE TESTINC PLAN VALVES Table 4.0 1 UWlf 1 VALVE LISTING DRAWING : M 0013 2 DRAWING TITLE : MIN STEAM PIPING REllEF NOREL REQUE$T DWG IST FUNCTION SIZE b@T ACTU+ POSI- TEST TEST OR COLD TECHNICAL VALVE NUNSER C00R CLASS CATEGORY (INCN) STYLE ATOR 710W TYPE FREO SNUTDOWN Postfl0N FUNCTION MAIN STEAM ISOLAfl0N VALVE ACTUATOR 2 WAT AIR PILOT VALVE 0203 002D AP4 F7 NC 0 .001 806 80 E STD M3 FST M3 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAT AIR PILCT VALVE l l

l 0203 002D 80AC F7 NC B .001 803- 80 E BTD RR RV 30D FST RR RV 300 FUNCT!W e MAIN *t' ,' R Afl0N VALVE ACT. 3 WAT AC CONTROL SOLEN 0ID 0203 002D*SODC F7 NC 3 .001 9U3 to E BTD RR RV 300

( FST RR RV 30D l

FUNCTION : MAIN STEAM 100LAfl0N VALVE ACT. 3 WAT DC CONTROL 80LEN010 1 l

0220 002 M0 E*7 1 A 3.000 GA M0 C AT 01 RR ITC M3 '

PIT Y2 l FUNCTION : MAIN STEAM LINE DRAIN ISOLATION VALVE i 1

0220 017A E8 1 A/C 1.000 XFC SA STS AT 02 RR CTC RR FUNCTION : 1A MAIN STM INST LINE EXCESS FLOW CK VLV t

0220 0175 D*8 1 A/C 1.000 XFC M STS AT*02 RR CTC RR FUNCTION : 18 MAIN STM INST LINE EXCESS FLOW CK VLV l

0220 017C C8 1 A/C 1.000 XFC SA STS AT*02 RR I

CTC RR FUNCTION : 1C MAIN STM INST LINE EXCESS FLOW CK VLV I l

l 0220 017D B8 1 A/C 1.000 XFC SA STS AT 02 RR I. CTC RR FUNCil0N : 1D MAIN STM INST LINE EXCESS FLOW CK VLV 0220 018A E*8 1 A/C 1.000 XFC SA STS AT 02 RR I CTC RR l 0 Revision 3 VALVES '

4a14 l-t .

QUAD Clitts NUCLEAR POWER $1Afl0N, UN!!$ i AND 2 IN$ttVict itst!NG PLAN

VALVl$

fable 4.0 1 UNIT 1 VALVE LittlNC DRAWING : M 0013 2 DRAWING fifLE : MAIN $1EAM P!P!NG ttLitF WatMAL tt0VElf DWG ist FUNCfl0N $12t BODY ACTU- PO$1+ filf it$1 OR COLD ftCHNICAL VALVE NJM8tt COOR CLA$$ CAftGORY (INCM) $ffLE ATOR 110N ffPt FRio ,$HUfDOWN POSl110N FUNC110N : 1A Math STM IN$f LINE EXCE$$ FLOW CK VLV 0220 0184 D8 1 A/C 1.000 KFC SA SY$ AT 02 at CTC tt FUNCil0N : il MAIN $1M IN$1 LINE EXCt$$ FLOW CK VLY 0220 016C C8 1 -A/C 1.000 XFC SA SYS AT 02- At CTC Rt FUNCfl0N : 1C MAIN $1M IN$1 LINE (ICESS FLOW CK VLV 0220 0100 t8 1 A/C 1.000 XFC SA SYS AT 02 tt CTC RR FUNCil0N : 10 MAIN $fM IkST LINE EXCis$ FLOW CK VLV 0220 085A F7 NC C 1.000 CK SA SYS At 06 Y2 CTC at RV 47A FUNCTION : MAIN $1 TAM ISOLAtl0N VALVE ACCultiLATOR CHECK VALVE 0220 0858 F7 NC C 1.000 CK SA SY$ AT 06 Y2 CTC te kV 47A FUNC110N : MAIN SitAM ISOLAft0N VALVE ACCUMULATOR CHECK VALVE 0220 085C F7 NC C 1.000 CK SA SYS AT 06 Y2 CTC Rt RV 47A FUNCil0N : MAIN $1 TAM ISOLA 110N VALVE ACCUMULATOR CHECK VALVE 0220 0850 F*7 NC C 1.000 CK SA SYS Af*06 Y2 CTC tt RV 47A FUNCil0N : MAIN $1 TAM 1SOLAil0N VALVE ACCUMULATOR CHECK VALVE tevision 3 VALVi$

4 15

l 1

l GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

-(7%) INSERVICE TESTING PLAN . VALVES

.\ )

Table 4.0 1 )

UNIT 1 VALVE LisilWC I l

DRAWING : M 0015 j DRAWING TITLE : REACTOR FEED PIPING RELIEF NORMAL REQUEST l

~

DWG IST FUNCTION $12E BODY ACTU- Post- TEST TEST OR COLD TECHNICAL VALVE NUNRER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FRE0 SMUTDOWN PO$lfl0N

0220 058A E2 1 A/C 18.000 CK SA STS AT.01 RR ,

CTC RR RV 32A I

FUNCTION : REACTOR FEED CNECK VALVE IN$10E CONTAINMENT 0220 0588 F2 i A/C 18.000 CK SA STS AT 01 RR CTC RR RV 32A CTO M3 f FUNCTION : REACTOR FEED CNECK VALVE INSIDE CONTAlWufNT l

0220 0598 F2 2 C 18.000 CK SA SYS CTC RR RV 32A f^g FUNCTION : REACTOR FEED

SECOND VALVE OUTSIDE CONTAINMENT

.i 0220 062A E2 1 A/C 18.000 CK SA SYS AT 01 RR CTC RR RV 32A FUNCTION : REACTOR FEED FIRST CNECK VALVE OUTEIDE CCWTAINMENT 0220 0628 F2 1 A/C 18.000 CK SA STS AT 01 RR CTC RR RV 32A CTO M3

(

FUNCil0N : REACTOR FEED + FIRST CNECK VALVE QUTSIDE CONTAINMENT l

l l

(

Revision 3 VALVES l 4 16 l

l I GunD CITIES E LEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.01 UNIT 1 VAL)I LISTING DRAWING : M 0022 1 DRAWING TITLE : L. P. SERVICE W TER P! PING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE B007 ACTU. P0ll* TEST TEST OR COLD TECHNICAL VALVE N'JMSER Cook CLASS CATEGORY (INCM) STYLE ATOR T10N TYPE FRE0 SMUTDOWN POSITION 3999 085 E.2 3 C 8.000 CK SA STS CTC St RV.00F CTO M3 FUNCTION : LPSW . DG COOLING WATER PUMP DISCHARGE CHECK VALVE 3999-086 E2 3 C 8.000 CK- SA STS CTC SR RV.00F CTO M3 FUNCTION : LPSW . DG COOLING WATER PUMP DISCHARGE CNECK VALVE 3999 088 E.2 3 C 6.000 CK SA STS CTO M3 FUNCTION tPSW

DG COOLING WATER PUMP DISC. CROSS flE CHECK VALVE 3999 560 C4 3 C 2.500 CK SA STS CTC M3 FUNCTION LPSW

SERvlCE WATER To NPCI ROOM COOLER CHECK VALVE 3999 561 C.4 3 C 4.000 CK SA STS CTO M3 FUNCTION : LPSW . SERVICE WATER TO VITAL COMPONENTS CNECK VALVE Revision 3 VALVES 4 17

r GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

,,q

/ INSERVICE TESTING PLAN . VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0024 2 DRAWING TITLE : INSTRUMENT AIR P! PING RELIEF NORMAL REQUEST DWG IST FUNCTION 512E 80DY ACTU- P081 TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR T10W TYPE FREO SHUTDOWN POSITION 0737 001A F7 NC A .375 BAL 80 C/FC AT 01 RR STC M3 FST M3 Pli Y2 FUNCTION TRAVERSING IN CORE PROSE BALL VALVE, PCiv 0737 0018 F7 NC A .375 BAL 80 C/FC AT 01 RR j BTC M3 l FST M3 l Plf Y2 !

FUNCTION : TRAVER$1NG IN CORE PROBE SALL VALVE, PCIV i

0737 001C F7 NC A .375 BAL so C/FC AT 01 RR BTC M3 l

FST M3 i Pli Y2 I FUNCTION : TRAVER$1NG IN CORE PROBE SALL VALVE, PCIV j

.\.

0737'0010 F*7 NC A .375 BAL So C/FC AT 01 RR BTC M3 ;

FST M3 f

PIT Y2 :

i FUNCTION : TRt.VER$1NG IN CORE PROSE SALL VALVE, PCIV 0737 001E F7 NC A .375 BAL 80 C/FC AT 01 RR BTC M3 FST M3 -

PIT Y2 FUNCTION : TRAVEPSING IN CORE PROBE SALL VALVE, PCIV 0737 002A F7 NC A .375 SMR EXP O/KL AT 01 RR TV 07A DT E $2 !

FUNCTION : TRAVER$1NG IN CORE PROBE $NEAR VALVE, PCIV 0737 0028 F7 NC A .375 SNR EXP O/KL AT 01 RR TV 07A DT E S2

\

Revision 3 VALVES 4 18

}_

b g . QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES

. {V Table 4.0 1 UNIT 1 VALVE LISTING DRAWING t N 0024 2 DRAWING TITLE t INSTRUMENT AIR PIPING RELIEF NORMAL REQUEST DWG !$f FUNCTION SIZE BODY ACTU- P061- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREO SNUTDOWN Postfl0N -[

FUNCTION TRAVER$1NG IN CORE PROSE $NEAR VALVE, PCIV

0737 002C F7 NC A .375 SNR EMP 0/KL AT 01 RR TV 07A ,

DT E $2 FUNCTION : TRAVERSING IN CORE PROBE $NEAR VALVE, PCIV 0737 002D F 7 NC A .375 SNR EMP 0/KL AT 01 RR TV 07A DT E $2 FUNCTION : TRAVERSING IN CORE PROBE $NEAR VALVE, PCIV O 0737 002E F7 NC A .375 SMR EMP 0/KL AT 01 RR TV 07A DT*E $2 FUNCTION : TRAVER$1NG IN CORE PROSE $NEAR VALVE, PCIV 0743 B7 NC A/C .375 CK SA SYS AT 01 RR CTC RR RV 07A FUNCTION TRAVER$1NG IN CORE PROSE CHECK VALVE, PCIV l

4720 03 NC A 1.000 DIA A0 0/FC AT 01 RR STC M3 FST M3 Plf Y2 FUNCTION t INSTR. Alt

PCIV, AIR SUCTION FOR INSTR. AIR FROM DRYWELL 4721 D3 NC A 1.000 DIA A0 0/FC AT 01 RR STC M3 FST M3 l

l Pli Y2 l- FUNCTION INSTR. Alt - PCIV, Alt SUCTION FOR INSTR. Alt FROM DRYWELL 4799 155 E2 NC A/C 2.000 CK SA SYS AT 01 RR CTC RR RV 475 FUNCTION : INSTR. AIR PCIV, INSTR. AIR GIPPLY TO DRYWELL ,

4799 156 E3 NC A/C 2.000 CK SA STS AT 01 RR CTC RR RV 475 Revision 3 VALVES 4 19

l

.,,_ GUAD CITIES WUCLEAR POW R STATION, UNITS 1 AND 2 )

[ INSERVICE TESTING PLAN . VALVES l

. %/

Table 4.0 1 ;

UNIT 1 VALVE LISTING DRAWING N 0024 2 DRAWING TITLE : INSTRLMENT AIR PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER. COOR CLASS CATEGORY (INCM) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION FUNCTION : INSTR. AIR PCIV, INSTR. AIR SUPPLY TO DRYWELL 4799 158 F4 NC A/C .500 CK SA SYS AT.01' RR CTC RR RV 47B l

FUNCTION INSTR. AIR PCIV, INSTR. AIR SUPPLT TO TORUS i

4799 159 F4 NC A/C .500 CK SA STS AT.01 RR CTC RR RV 47B FUNCT!DN INSTR. AIR . PCIV, INSTR. AIR SUPPLY TO TORUS 4799-281A B2 NC C .500 CK SA STS AT 06 Y2 I RR RV 47A CTC FUNCTION : INSTR. AIR TARGET ROCK ACCLMJLATOR CHECK VALVE 4799 485- D3 NC 8 .001 803 80 E STD M3 i FST M3 l FUNCTION : INSTR. AIR

PCIV (A!R SUCTION FROM DAYWELL) SOLENCID VALVE 4799 486 D3 NC D .001 803 to E BTD M3 FST M3 FUNCTION : INSTR. AIR PCIV (AIR SUCTION FROM DRYWELL) SOLEN 0ID VALVE t

l l

/*h Revision 3 VALVES 4 20 r -

l 4

t Ou4D CITIES NUCLEAR POWER STAfl0N, WITS 1 AND 2

,O INSERVICE TESTING PLAN VALVES

4

' N, '

Table 4.0 1 l UNIT 1 VALVE LISTlWG DRAWING : M 0025 DRAWING TITLE : SERVICE AIR PIPING (INCLWES DIESEL GENERATOR STARTING Alt)

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECNNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREO $NUTDOWN Postfl0N -

4699 046 E3 NC A 1.000 GL M C AT 01 RR FUNCY10N : SERVICE AIR - PRIMARY CONTAlWMENT ISOLATION VALVE-4699-047 E3 NC A/C 1.000 CK SA SYS AT 01 RR CTC RR RV 464 I FUNCTION : SERVICE AIR PRIMARY CONTAINMENT ISOLAfl0N VALVE -l l l 4699 123 D9 NC C 1.500 CK SA SYS CTO M3 l

FUNCTION : SERVICE AIR * (DIESEL) RECEIVER TANK SACKFLOW PROTECTION 4699 196 D9 NC C 1.500 CK SA SYS CTO M3 J FUNCTION : SERVICE AIR - (DIESEL) RECEIVER TANK BACKFLOW PROTECTION l

l 4699 226 2 99 NC 8 1.500 DIA A0 C BTC M3 RV 46A STD M3 RV 46A FUNCTION : SERVICE Alt - (DIESEL) AIR START RELAY VALVE 4699 306A 2 99 NC C .750 RV SA C CT SP V5 FUNCTION : SERVICE AIR - (DIESEL) RECEIVER TANK SAFETY VALVE

]

2 99 NC l 4699 3068. C .750 RV SA C C1 SP V5 FUNCTION : SERVICE AIR * (DIESEL) RECEIVER TANK SAFETY VALVE 4699 306C Z 99 NC C .750 RV SA C CT SP Y5 FUNCTION : SERVICE AIR - (DIESEL) RECEIVER TANK SAFETY VALVE 4699 306D 2 99 NC C .750 RV SA C CT SP Y5 FUNCil0N : SERVICE AIR - (DIESEL) RECEIVER TANK SAFETY VALVE l- 4699 307A 2 99 NC C .500 CK SA SYS AT 06 Y2 CTC M3 FUNCil0N : SERVICE Alt - (DIESEL) COMPRESSOR BACKFLOW PROTECTION 4699 307B Z 99 NC C .500 CK SA SYS AT 06 Y2 CTC M3 FUNCil0N : SERVICE AIR * (DIESEL) COMPRESSOR BACKFLOW PROTECTION Revision 3 VALVES 4 21

OUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 l INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 V.%VE LISTING DRAWING : W 0025 DRAWING TITLE : SERVICE AIR P! PING (INCLLDES DIESEL GENERATOR STARTlWG AIR)

. RELIEF NORMAL REQUE$T DWG !$f FUNCTION $12E 80DY ACYU- PoS!* TEST TEST OR COLD TECNNICAL VALVE NUMSER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION 4699 309 Z 99 NC C 1.500 CK SA SYS CTC M3 CTO M3 FUNCTION : SERVICE AIR * (OlESEL) AIR START RELAY VALVE DPNRGM. CK VLV.

4699 310 2 99 NC $ .250 S03 to D STD M3 STE M3 FUNCTION : SERVICE AIR - (DIESEL) START SOLEN 0ID i h V

i' l

l' l

l O

Revision 3 VALVEt 4 22

GuAD CITIES WUCLEAR POWER STAfl0N, UNIIS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING .

DRAWINC : M 0029 DRAWING TITLE : Tutt!NE AND DIESEL Cll PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION $1ZE BODY ACTU- P081* TEST TEST OR COLD TECNNICAL VALVE NUMBER C00R CLASS CATEGORT (INCN) STYLE ATOR T10N TYPE FRE0 SNUTDOWN Postil0N 5199 157 C6 NC C 1.000 CK SA SYS CTC M3 CTO M3 FUNCTION : DIESEL Ott . PRINING PUMP DISCHARGE BACKFLOW PROTECTION 5199 157 - 1/2 C6 NC C 1.000 CK SA SYS CTC M3 CTO M3 FUNCTs0N : DIESEL Olt PRIMING PUMP DISCHARGE BACKFLOW PROTECTION

$199 158 C6 NC C .750 CK SA SYS LTC SS RV.007 CTO M3 FUFCTION : DIESEL DIL . EXCESS FUEL RETURN BACKFLOW PROTECTION 5199 158 - 1/2 C6 NC C .750 CK SA SYS CTC ST RV 00F CTO M3 FUNCTION DIESEL O' . EXCESS FUEL RETURN BAr:KFLOW PROTECTION 5201- .RV E4 NS C 1.500 RV SA, C CT SP Y5 FUNCTION : DIESEL DIL . TRANSFER PUMP DISCHARGE RELIEF VALVE 5201 RV 1/2 E4 NS C 1.500 RV SA C CT SP V5 FUNCTION : DIESEL clL . TRANSFER PUMP DISCHARGE RELIEF VALVE

$201 80 04 WS B 1.000 $02 $0 0 sto M3 RV 52A FUNCTION : DIESEL CIL TRANSFER PUMP TO DAY TANK CONTROL VALVE

$201 .S0 1/2 F.6 NS B 1.000 502 So C eio M3 RV 52A FUNCT10N : DIESEL clL . TRANSFER PLD P TO DAY TANK CONTROL VALVE 5299 003 F.4 NS C 1.500 CK SA STS CTO SX RV 00E FUNCTION : DIESEL DIL . TRANSFER Ptp P DISCHARGE BACKFLOW PROTECTION

$299 003 1/2 F.4 NS C 1.500 CK SA SYS CTO SY RV.00E FUNCTION : DIESEL OIL . TRANSFER PUMP DISCNARGE SACKFLfAI PROTECTION

$299 005 F4 NS C 1.500 CK SA SYS CTC M3 CTO M3 Revision 3 VALVES 4 23

GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0029 DRAWING TITLE : TURSINE AND DIESEL CIL PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DY ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREO SNUTDOWN Postfl0N FUNCTION : DIESEL 0!L . TRANSFER PUNP DISCHARGE BACKFLOW PROTECTION 5299 005 *1/2 F4 NS C 1.500 CK SA SYS CTO M3 FUNCTION : DIESEL CIL TRANSFER PUNP DISCHARGE SACKFLOW PROTECTION Revision 3 VALVES 4 24

.. - .- .~ - . , . . _ __ - -.- , . - .

I

., QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

/ INSERVICE TESTING PLAN

VALVES

}

ll Table 4.01 l- UNIT 1 VALVE LISTING DRAWING.: M 0033 DRAWING TITLE : REACTOR BUILDING CLOSED COOLING WATER-6 RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BCDY ACTU- Post- TEST TEST OR COLD TECHNICAL' y VALVE NUMBER = C00R CLASS CATEGORY. (INCH) STYLE ATOR TION TYPE FRE0 SNUTDOWN POSITION !

3702- M0 B3 NC ' A 8.000 GA NO O AT 01 RR BTC CS CS 37A PIT Y2 l . FUNCTION : RBCCW = PRIMARY CONTAINMENT ISOLATION VALVE 3703- M0 31 NC A 8.000 GA MO 0 AT 01 RR BTC CS CS 37A Plf Y2 FUNCTION RBCCW

PRIMARY Cot:TAINNENT ISOLATION VALVE I

3706- No B1 NC A 3.000 OA N0 6 AT*01 RR s BTC CS CS 37A PIT Y2 FUNCYl0N : L CONTAINMENT ISOLATION VALVE .

3799 031 -B3 NC Vt 8.000 CK SA SYS 1T 01 RR CTC . RR RV 37A FUNCTION : .V.N PRI C . TINMENT ISOLATION VALVE l

i f

l l'

11-r ~ {'

\

Revision 3 VALVES 4 25 l

l-L

1 i

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 '

i

-) INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING

l. DRAWING : M 0034 1 ,

f. d DRAWING ?J'), t F2tsSURE SUPPRES$10N [

l. RELIEF went REQUEST !

Out IST FUNCTION SIZE BG)Y ACTU- POSI- Ittt TEST OR COLD TECHNICAL !

VALVE NUM6ER C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FRED SHUTD(WN POSITION

..........u...... !

0220 081A E4 NC C 1.000 CK SA SYS CTOME CS RV 30C FUNCTION PRES. SUPPR. SAFETY VALVE DISCHARGE VACUUM BREAKERS !

h 0220 0818 E4 NC C 1.000 CK SA SYS CTOME CS RV 30C :

-FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS l

0220 081C E NC C .1.000 CK SA SYS CTOME CS RV 30C FUNCTION PRES. SUPPR. SAFETY VALVE DISCHARGE VACUUM BREAKERS 0220-081D E-6 NC C 1.000 CK SA SYS CTOME CS RV 30C D FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACWM BREAKERS !

.( '

0220 081E E6 NC C 1.000 CK SA SYS CTOME CS . RV 30C ;

FUNCTION : PRES. SUPPR. SAFETY VALVE DISCHARGE VACWM BREAKERS l_q 0220 105A D4 NC C 8.000 CK SA SYS CTOME CS RV 30C hJ FUNCTION : PRES. SUPPR. SAFETY VALVE DISCHARGE VACLAM BREAKERS '

0220 1058 E4 NC C 8.000 CK SA SYS CTOME CS RV 30C FUNCTION : PRES. SUPPR. SAFETY VALVE DISCHARGE VACUUM SAEAKERS 0220 105C D5 NC C 8.000 CK SA SYS CTOME CS RV 30C :

FUNCTION : PRES. SUPPR. SAFETY VALVE DISCHARGE VACWM BREAKERS 0220 1050 05 NC C 8.000 CK SA SYS CTOME CS RV-30C FUNCTION PRES. SUPPR. SAFETY VALVE DISCWARGE VACWM BREAKERS b

l' 0220 10$E E5 NC C 8.000 CK ' SA SYS CTOME CS RV 30C 4 FUNCT10N : PRES. SUPPR. SAFETY VALVE DISCHARGE VACUUM BREAKERS u!

! 1601 020A A0 09 NC A 20.000 BTF A0 C/F0 AT 01 RR STC M3 BTO M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR.

PRIMARY / SECONDARY CONTAINMENT VACUUM SREAKERS Revision 3 VALVES 4 26 e

I T

l

~- QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

{V INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING e

DRAWING : M 0034 1 !

DRAWING TITLE : PRES $URE SUPPRESSION RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU* Post. TEST TEST OR COLD TECHNICAL VALVE NUM6ER COOR CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION 1601 020A AP A2 NC 4 .001 PLT A0 D BTD M3 FST M3 FUNCTION : PRES. SUPPR.

VACUUM BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 020A CK1 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION : PRES. SUPPR. VACULM SREAKER/PCIV ACCUMULATOR CHECK 1601 020A CK2 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 1M FUNCTION : PRES. SUPPR. VACWM BREAKER /PCIV ACCtmulATOR CHECK i 1601 0208 A0 E9 NC A 20.000 BTF A0 C/F0 AT 01 RR BTC M3 y

)

BT0 M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR. PRIMARY / SECONDARY CONTAINMENT VACWM BREAKERS

'1601 0208 AP A2 NC B .001 PLT A0 D BTD M3 FST M3 FUNCTION : PRES. SUPPR.

VACWM BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 0208 CK1 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR. VACUUM BREAKER /PCIV ACCUMULATOR CHECK 160107)B CK2 A2 NC C .001 CK SA STS AT 06 Y2 CTC- CS CS 16A FUNCTION PRES. SUPPR. VACUUM BREAKER /PCIV ACCUMULATOR CHECK 1601 U21 A0 C6 NC A 18.000 BTF A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL INERT & PURGE O

Revision 3 VALVES 4 27

~

eunD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTlWG' DRAWING : N 0034 1 DRAWING TITLE : PRESSURE SUPPRESS 10N RELIEF NORMAL REQUEST

'DWG IST FUNCTION $12E d@Y ACTU- Post- TEST TEST OR COLD TECmilCAL VALVE NUNSER COOR CLASS CATEGORT (INCN) STYLE ATOR TION TYPE FREQ SMUTDCMN POSITION 1601 021 AP A2 NC B .001 PLT AD D BTD M3 FST M3 FUNCil0N : PRES. SUPPR. VAC M BREAKER /PCIV ACCUNULATOR AIR PIL0T 1601 021 CK1 A-2 NC C .001 CK SA STS AT 06 Y2 CTC CS CS 16A FUNCTIGN PRES. SUPPR.'a CHECK VALVE 1601 021 CK2 A2 NC C .001 CK SA STS AT 06 Y2 CTC CS CS*16A FUNCTION : PRES. SUPPR.

CHECK VALVE 1601 022 A0 C6 NC A 18.000 STF A0 C/FC AT 01 RR STC M3 -

FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL INERT & PURGE 1601 022 AP A2 NC s .001 PLT A0 D BTD M3 FST M3 FUNCTION : PRES. SUPPR. VACUUM BREAKER /PCIV ACCUNULATOR AIR PILOT 1601 022 CK1 'A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION : PRES. SUPPR. CHECK VALVE 1601 022 CK2 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A F.4NCT10N : PRES. 3UPPR. - CNECK VALVE 1601 023 A0 B3 NC A 18.000 STF A0 C/FC AT 01 RR STC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR. - DRYWELL VENT 1601 023 AP A2 NC B .001 PLT A0 D ETD M3 Revision 3 VALVES 4 28

i GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES

-Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0034 1 DRAWING TITLE PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION $12E SQDT ACTU- POSI- TEST' TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (lWCM) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION 1601 023 .AP A2 NC S .001 PLT AD. D FST' M3 FUNCil0N : PRES. SUPPR. 4ACUUM BREAKER /PCIV ACCUMULATOR AIR PILOT

'1601 023 CK1 A2 NC C .001 CK SA SYS AT 06 T2 CTC CS CS 16A FUNCTION : PRES. SUPPR. - CHECK VALVE 1601 023 CK2 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR. CHECK VALVE 1601 024 A0 B2 NC A 18.000 BTF A0 C/FC AT.01 IR BTC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR. DRYWELL AND SUPPR. CHAMBER VENT TO RK BLDG.

1601 024 -AP A2 NC B .3U1 *LT A0 0 BTD M3 FST M3 FUNCTION : PRES. SUPPA. - VActAM BREAKER /PCIV ACCUBRJLATOR AIR PILOT 1601 024 CK1 A 2_ NC C .001 CK SA SYS AT*06 Y2 CTC CS CS 16A FUNCTION PRft. TJrPR. CHECK VALVE 1601 024 CK2 n-2 NC C .001 CK SA STS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPP9. . CNECK VALVE 1601 031A D*9 NC A/C 20.000 CK SA SYS AT 01 RR CTC M3 CTOME M3 FUNCTION PRES. SUPPR. - PRIMARY / SECONDARY CONTAINMENT VACUUM BREAKERS 1601 031B E9 NC A/C 20.000 CK SA SYS AT 01 RR CTC M3 CTOME M3 Revision 3 VALVES i 4 29

i

' QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

'O" INSERVICE TESTINC PLAN - VALVES !

Table 4.0 1 1 UNIT 1 VALVE LISTING e

DRAWING : M 0034 1-DRAWING TITLE : PRESSURE SUPPRESS 10N

(. i j RELIEF NORMAL REQUEST I. DWG IST FUNCTION SIZE BODY ACTU- POS!* TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR- CLASS CATEGORY (INCN) STYLE ATOR. T10N TYPE. FREQ ~SNUTDOWN. POSITION FUNCTION : PRES. SUPPR. PRIMARY / SECONDARY CONTAINMENT VACUUN BREAKERS l

l _.. 1601 032A E2 NC A .001. CK SA SYS AT 05 RR TV 16A l CTC M3 CTO M3 P!T Y2 -

FUNCTION PRES. SUPPR.

DRYWELL/SUPPRES$10N CNAMBER VAculat BREAKERS 1601 0328 E2 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 l

PIT Y2 N FUNCTION : PRES. SUPPR. - DRYWELL/SUPPRES$10N CHAMBER VACUUM BREAKERS 1601 032C E2 NC A .001 CK SA SYS AT 05 RR TV 16A u

CTC M3 CTO M3 i

Pli Y2 FUNCTION : PRES. SUPPR.

DRYWELL/ SUPPRESSION CNAMBER VActAJM BREAKERS -

1601 032D E2 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 PIT Y2 FUNCTION : PRES. SUPPR.

DRYWELL/SUPPRES$10N CHAMBER VACUUM BREAKERS 1601 032E E2 NC A .001 CK SA SYS AT 05 RR TV 16A i CTC M3 CTO M3 l

P!T Y2 FUNCTION PRES. SUPPR.

DRYWELL/SUPPRES$10N CHAMBER VACUUM BREAKERS 1601 032F F2 NC A .001 CK SA SYS AT 05 RR Tv 16A CTC M3 CTO M3 Pli Y2 l d.

Revision 3 VALVES 4 30

i GUA0 CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.0 '

UNIT 1 VALVE LISTING l

DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRESSION RELIEF NORMAL' REQUEST DWG IST FUNCTION SIZE BODY ACTU* Post- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCM) STYLE ATOR flou FREQ SMUTDOWN POSITION

.................. .... ..... ........ ...... ..... ..... ......' TYPE ..... .... ........ .........

FUNCTION PRES. SUPPR. DR M LL/SUPPRES$10N CHAMBER VACUUM BREAKERS 1601 033A E7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 Plf Y2 FUNCTION PRES. SUPPR. DRYWELL/SUPPRES$10N CHAMBER VACLAM BREAKERS 1601 0338 E7 NC A .001 CK SA SYS AT 05 RR Tv 16A

'> CTC' M3 CTO M3 PIT Y2

, FUNCTION PRES. SUPPR. DAYWELL/ SUPPRESSION CHAMBER VACUUM SREAKERS 1601 033C E7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3

Plf Y2

! FUNCTION PRES. SUPPR. DRYWELL/ SUPPRESSION CNAMBER VACUUM BREAKERS

1601 0330 E7 NC A .001 CK SA . SYS AT 05 RR Tv 16A CTC M3 7 CTO M3 PIT Y2 FUNCTION PRES. SUPPR.

DRYWELL/ SUPPRESSION CHAPSER VACULM BREAKERS

_ 1601 033E E7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL/SUPPRES$10N CHAMSER VACUUM BREAKERS 1601 033F E7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3

CTO M3 PIT Y2

.N Revision 3 VALVES 4 31 af.

1 4

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 1.'

UNIT 1 VALVE LISTlWG DEAWING M 0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POST. TEST TEST OR COLD TECHNICAL VALVE NWSER C00R CLASS CATEGORT (INCH) STYLE ATOR TION TYPE FREQ SMUTDOWN P081 TION FUNCTION PRES. SUPPR. . DAYWELL/SUPPRES$10N CHAMBER VACULB4 BREAKERS 1601 050A 50 09 NC B .001 $04 50 E BTD M3 BTE M3 FST M3 FUNCTION : PRES. SUPPR.

VACUUM BREAKER /PCIV CONTROL SOLENCID 1601 0500-50 E9 NC B .001 504 S0 E BTD - M3 BTE - M3 FST M3

FUNCTION : PRES. SUPPR.

VACUUM BREAKER /PCIV CONTROL SOLENCID 1601 051A 50 C6 NC B .001 504 to D BTD M3 FST M3 FUNCTION : PRES. SUPPR. . MISC. PCIV AIR OPERATOR CONTROL $0LEW010 1601 0518 50- C7 NC B .001 $04 So D BTD M3

'FST M3 FUNCTION : PRES. SUPPR. . MISC. PCIV AIR OPERATOR CONTROL SOLEN 0ID 1601 052A So C2 NC B .001. $04 SO D OTD- M3 FST M3 FUNCTION : PRES. SUPPR. MISC. PCIV AIR OPERATOR CONTROL SOLEN 0ID 1601 0528 50 C2 NC B .001 504 So D BTD M3 FST M3 FUNCTION : PRES. SUPPR. - MISC. PCIV AIR OPERATOR CONTROL $0LEM010 1601 055 A6 NC A 4.000 GA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. NITROGEN MAKE*UP/PUMPBACK SUCTION 1601 055 50 A6 NC B .001 303 S0 E BTD M3 FST M3 O

Revision 3 VALVES 4 32

QUA0 CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 ;

,.Cy INSERVICE TESTING PLAN - VALVES jj~'

fable 4.0-1 UNIT;1 VALVE LISTING -

1 DRAWING : M 0034 1 ORAWING TITLE.: PRESSURE SUPPRESSION >

RELIEF }

NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORY ~ (INCN) STYLE ATOR TION TYPE FREQ SMUTDOWN POSIT 10N FUNCil0N : PRES. SUPPR. NITROGEN INERTION ISOLATION CONTROL $0LEN010 1601 056 A0 D6 NC A 18.000 BTF A0 0/FC AT 01 RR STC M3 FST M3 -

(: PIT Y2 FUNCTION : PRES. SUPPR.

CONTAINMENT INERTING/PUMPSACK SUCil0N l

1601 056 AP A2 NC ' 5 .001 PLT A0- D BTD M3 FST M3 FUNCTION PRES. SUPPR. VACUUM BREAKER /PCIV ACCUIRJLATOR AIR PILOT t 1

.} l 1601 056 CK1 A2 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION : PRES. SUPPR. CHECK VALVE 1601 056 CK2 A2, NC C .001 CK _ SA SYS' AT 06 Y2 CTC CS CS 16A FUNCTION : PRES. SUPPR. - CHECK VALVE 1601 057 D8 NC- A 1.000 GL MO O AT 01 RR STC M3 PIT Y2 FUNCTION : PRES. SUPPR. NITROGEN MAKE UP/PtMPSACK OlSCNARGE PATH 1601 058 A0 D7 NC A 1.000 CL A0 C/FC AT 01 RR STC M3 FST - M3 Pli Y2 FUNCTION : PRES. SUPPR. NITROGEN MAKE UP/PUMPBACK ISOL. FROM TORUS 1601 059 A0 07 NC A 1.000 GL A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR. NITROGEN MAKE-UP/ PUMP 9ACK DISCHARGE PATH Revision 3 VALVES A 33

i QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE tlEY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUNBER Coot CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FREQ SMUTDOWN POSITION 1601 060 .A0 E1 NC A 18.000 BTF A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. . SUPPRES$10N CHAMBER VENT 1601 060 .AP A2 NC B .001 PLT A0 0 BTD M3 FST M3 FUNCTION : PRES. SUPPR. VACUUM BREAKER /PCIV ACCURlLATOR AIR PILOT 1601 060 .CK1 A2 NC C .001 CK SA STS AT.06 Y2 CTC CS CS 16A FUNCTION : PRES. SUFPR. . CNECK VALVE 1601 060 *CK2 A2 NC C .001 CK SA SYS AT.06 Y2 CTC CS 'CS 16A-FUNCTION : PRES. SUPPR. . CHECK VALVE 1601 061 .A0 F.1 NC A 2.000 GL A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. . SUPPR. CHAMBER VENT BYPAS$ AND SBGT SUCTION 1601 062 .A0 B3 NC A 2.000 GL A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. . DRYWELL VENT Bypass & STANDBY GAS TR. SUCT10N 1601 063 .A0 A2 NC A 6.000 BTF A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPP. . STANDBY GAS TREAT. CONNECTION TO PRINARY CONT.

1601 063 AP A2 NC B .001 PLT A0 0 BTD N3 i

Revision 3 VALVES 4 34

1 l

l l

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 '

/N INSERVICE TESTING PLAN VALVES c :p) .

Table 4.0 1 UNIT 1 VALVE LISTING 'l l

DRAWING M 0034 1 I

DRAWING TITLE : PRESSURE SUPPRESSION l

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL I VALVE NUMRER C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE. FREQ $NUTDOWN. POSITION.

1601 063 .AP_ A2 NC . B .001 PLT A0 0 FST M3 FUNCTION : PRES. SUPPR. VACULM BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 063 CK1 .A 2 NC ' -C .001 CK SA SYS AT 06 Y2 Y CTC CS CS 16A FUNCTION PRES. SUPPR. - CHECK VALVE ;

1601 063- CK2 A2 NC C .001 CK SA SYS AT 06. Y2 CTC CS CS 16A

'- FUNCTION : PRES. SUPPR. CHECK VALVE l(

.1601 065 80 'D 7 NC B .001 SO4 So E' BTD M3 FST M3 l '

l FUNCil0N PRES. SUPPR. MISC. PCIV AIR OPERATOR CONTROL SOLEN 010 1601 066 80 07- NC B .001 503 50 D BTD M3 FST M3 FUNCTION PRES. SUPPR.

AIR OPERATED GLOSE VALVE S0LEN010 ,

1601 067 50 D 6' NC B .001 $03 So E- BTD M3 FST M3 1 1

FUNCTION : PRES. SUPPR. - AIR OPERATED GLOSE ;ALVE $0LENotD 1601 068 S0 F1 NC B .001 804 to D BTD M3 FST M3 4

FUNCTION PRES. SUPPR. MISC. PCIV AIR OPERATOR CONTROL SOLENotD 1601 069 80 F1 NC' B .001 503 $0 D BTD M3 FST M3 FUNCTION PRES. SUPPR.

AIR OPERATED GLOBE VALVE SOLENOIDS 1601 070 So B3 NC B .001 803 So D BTD M3 FST M3 FUNCTION : PRES. SUPPR. AIR OPERATED GLOSE VALVE SOLEN 0 IDS 1601 071 So A3 NC B .001 804 So D BTD M3 FST M3 o

Revision 3 VALVES 4 35

l QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0-1'

- UNIT 1 VALVE LISTING DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRESSION RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU. Post. TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SMUTDOWN POSITION FUNCT10N PRES. SUPPR. . M14C. PCiv AIR OPERATOR CONTROL SOLEN 0!D

'q. 4711 .RV D8 NC~ A/C 1.500 av SA C AT 01 -RR CT.SP T5 FUNCTION PRES. SUPPR. . NITROGEN MAKE.UP OVERPRESSURE PROTECTION 8801 A FCV C3 NC A .500 DIA A0 0/FC AT.01 RR BTC M3-1 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. . DRYWELL AIR SAMPLE 4

8801 A 50 C3 NC B .001 C03 $0 E STD M3 FST M3 FUNCil0N : PRES. SUPPR. . DIAPNRAGM VALVE S0LEN0 IDS 8801 B FCV D.3 NC A .500 DIA A0 0/FC AT.01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8801 B SO D3 NC B .001 503 50 E BTD M3 FST M3 FUNCTION : PRES. SUPPR. DIAPMRAGM VALVE SOLEN 0lDS 8801 C FCV D.3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8801 C So D3 NC B .001 $03 So E STD M3 ,

FST M3 FUNCTION : PRES. SUPPR. . DIAPMAAGM VALVE SOLENCIDS 8801- D.FCV E3 NC A .500 DIA A0 0/FC AT 01 RR Revision 3 VALVES 4 36

f QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

. INSERVICE TESTING PLAN

VALVES Table 4.0 1 a

UNIT 1 VALVE LISTING DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRESSION RELIEF NORMAL REQUEST-DWG !$T FUNCTION $12E BODY ACTU- POSI- TEST TEST CA COLD TECHNICAL VALVE NLMBER COOR CLASS CATEGORY (INCN) !TTLC AT3 TION TYPE FREQ $NUTDOWN POSITION 8801- D FCV E3 NC A .500 DIA A0 0/FC BTC M3 FST M3 -

Pli Y2 FUNCTION PRES. SUPPR. SUPPRES$10N CHAMBER AIR SAMPLE 8801- D 80 D3 NC B .001 803 to E BTD M3 -

FST M3 FUNCTION PRES. SUDPR. DIAPHRAGM VALVE SOLENCIDS 8802 A FCV C3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8802* A 50 'C-3 NC B .001 303- 80 E BTD M3 FST M3 FUNCTION PRES. SUPPR. DIAPNRAGM VALVE S0LENCIDS 8802* B FCV D3 NC A .500 DIA A0 0/FC AT 01 RR STC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8802- B 30 D3 NC B .001 $03 to E BTD M3 FST M3 FUNCTION : PRES. SUPPR. - DIAPHRAGM VALVE 80LEN01DS 8802- C FCV D3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8802- C 30 D3 NC B .001 S03 So E BTD M3 FST M3 Revisto 3 VALVES 4 37 l l

4 GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING.

DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION S!ZE 8@T ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SMUTDOWN POSITION FUNCTION PRES. SUPPR. DIAPNRAG4 VALVE S0LEN0 IDS 8802- D FCV' E3 ' NC - A .500 DIA A0 ' 0/FC AT 01 RR STC M3 FST M3 Pli Y2 FUNCTION- PRES. SUPPR

SUPPRES$10N CHAMBER AIR SAMPLE 8802- D 50 E3 NC B .001 $03 So E BTD M3 FST M3 FUNCTION : PRES. SUPPR.

DIAPMRAGM VALVE SOLEW0lDS 8803 C6 NC A .500 GL A0 0/FC AT 01 RR BTC M3 -

FST M3 PIT 'Y2 FUNCTION : PRES. SUPPR.

DR M LL AIR SAMPLE 8803* -50 C6 NC B .001 503 So E BTD M3 FST M3 FUNCTION : PRES. SUPPR. AIR OPERATED GLOBE VALVE $0LEN01DS 8803* 10 03 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL AIR SAMPLE 8803 -1E D3 NC A .500 GA N C AT 01 RR FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 1F 03 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL AIR SAMPLE 8803- 10 03 NC A .500. GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL AIR SAMPLE 8803- 1H D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SMPLE O

Revision 3 VALVES A 38

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2.

INSERVICE TESTING PLAN - VALVES w-Table 4.0 1 UNIT 1 VALVE LISTING DRAWING M*0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUE$T.

DWG IST FUNCT10N SIZE BODY ACTU- POSl* TEST. TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION 8803- 11 D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8803- IJ D-3 NC A .500 GA M C AT 01 RR -

FUNCTION PRES. SUPPR. - DAYWELL AIR SAMPLE 8803- 1K D3 NC. A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DRYWELL Alt SAMPLE 8803- il 03 NC A .500 GA -M C AT 01 RR FUNCTION : PRES. SUPPR. - DRYWELL' AIR SAMPLE

'8803- 1M D3 NC .500 GA -M AT 01 RR A C FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE- .-

8803- 1N 03 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. - DRYWELL AIR SAMPLE 8803- 10 D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. - DRYWELL AIR SAMPLE 8803- 1P D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR.

DRYWELL AIR SAMPLE-8803- 10 0 3 - NC A- .500 GA M C AT 01 RR FUNCTION PRES. SUPPR.

DRYWELL AIR SAMPLE 8803- 1R D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 15 D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. - DRYWELL AIR SAMPLE 8803- if D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL Alt SAMPLE 8803- 1U D3 NC A .500 GA M C AT 01 RR Revision 3 VALVES 4 39

i GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES fable 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL -

VALVE NUMBER C00R CLASS CATEGORY _(lWCN) STYLE ATOR TION TYPE- FREQ SNUTDOWN POSITION FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 1V D3 NC A .500 GA M C AT*01 RR FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE.

8803- 1W D3 NC A .500 GA M C AT.01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE

'8803- 1X D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 1Y 03 NC A .500 GA N C AT 01 RR FUNCTION-1 PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 2D D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 2E D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. - DR M LL AIR SAMPLE 8803- 2F D3 NC A .500 GA M C AT 01 RR FUNCil0N PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2G D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2N 03 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL AIR SAMPLE 8803- 21 03 NC A .500 GA M C AT 71 RR FUNCTION : PRES. SUPPR. - DRYWELL AIR SAMPLE 8803- 2J D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2K D3 NC A .500 GA M C AT 01 RR Revision 3 VALVES 4 40

- QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTINC PLAN

VALVES W.. Table 4.0 1 UNIT 1 VALVE LISTING DRAWING M 0034 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUE ST DWG IST FUNCTION SIZE 80DY ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY .(INCM) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2L D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803 2M D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR.' DRYWELL AIR SAMPLE 8803- 2N 03 NC A .500 GA M C AT 01 RR FUNCT10N PRES. SUPPR.' DR M LL AIR SAMPLE 8803- 20 D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2P D*3 NC A .500 GA N C Af 01 RR FUNCTION PRES. SUPPR. DR M LL AIR SAMPLE 8803- 20 D3 NC A .500 GA N C AT 01 RR FUNCTION t PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2R D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. - DR M LL AIR SAMPLE 8803- 2S D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. - DRYWELL AIR SAMPLE 8803- 2T D3 NC A .500 GA M C AT 01 RR FUNCTION t PRES. SUPPR. - DR M LL AIR SAMPLE 8803- 2U 03 NC A .500 GA N C AT 01 RR FUNCT10N PRES. SUPPR. DR M LL AIR SAMPLE 8803- 2V D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DA M LL AIR SAMPLE 8803- 2W D*3 NC A .500 GA M C AT 01 RR e l Revision 3 VALVES 4 41

s QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 ;

, INSERVICE TESTING PLAN . VALVES O

ia )--

Table 4.0 1 .!

UNIT 1 VALVE LISTING {

p DRAWING : M 0034 1 DRAWING TITLE : PRESSURE SUPPRESSION RELIEF NORMAL REQUEST DWG IST FUNCTION- SIZE' 00DT ACTU. POSla TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORT (INCN) STTLE ATOR .T10N TTPE FREQ SNUTDOWN POSITION PRES. SUPPR. . DRYWELL AIR SAMPLE ;

FUNCTION 8803 . 2X D3- NC A .500 GA M C AT 01 RR FUhCTION PRES. SUPPR.

DRYWELL AIR SAMPLE 1

8803* 2T D.3 NC A .500 GA M C AT 01 RR !

FUNCTION : PRJS. SUPPR. . DRTW LL AIR SAMPLE l

8804 06 NC A .500 GL- A0 0/FC AT.01 RR BTC M3 l l

FST M3 P!T Y2 ;

FUNCTION PRES. s tJPPR. . DRYWELL AIR SAMPLE '!

! 8804 50 D6 NC B ,001 803 So E BTD M3 l- FST M3 FUNCTION PRES. SUPPR. . AIR OPERATED GLOSE VALVE SOLENCIDS

(

l l

).

%/

l Revision 3 VALVES 4 42 1

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES

.o :

Table 4.01 UNIT 1 VALVE LisilWG Y

DRAWING M 0035 1 DRAWING TITLE : REACfDR RECIRCULATION PIPING RELIEF NORNAL REQUEST DWG IST FUNCTION . SIZE BODY ACTU- Posl* TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ' SMUTDOWN POSIT 10N 0220 051 E5 1 a .500 DIA A0 C/FC FST_ CS CS 02B PIT Y2 FUNCTION : REACTOR REClRCULATION

FLANGE LEAK DETECTOR DRAIN LINE 0220 051 -$0 E5 NC B .999 $03 So D FST CS CS 028 FUNCTION : REACTOR RECIRC

FLANGE LEAK CETECTOR DRAIN LINE SOLENotD 0220 054 E6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX PS-1 261 20 & PI 1 261 21 EXCESS FLOW CK VLV E6 1 1.000 XFC St AT.02 RR O 0263 2 011 ' A/C SYS CTC RR FUNCTION : RX LT 1 263 61 HI SIDE EXCESS FLO2 CK VLV 0263 2 013A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1 263 57 HI SIDE EF". DSS FLOW CK VLV 0263 2 0138. D3 1 A/C 1.000 X'c SA STS AT 02 RR CTC RR FUNCTION : RX LT 1263 56 HI $1DE EXCESS FLOW CK VLV 0263 2 015A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT.1 263 57 LO SIDE EXCESS FLOW CK VLV 0263 2 015B 'D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1 263 58 L0 SIDE EXCESS FLOW CK VLV 0263 2 017A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT*1646A & LT 1263 23A to SIDE EXCESS FLOW CK VLV 0263 2 017B 03 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR 9 Revision 3 VALVE!

4 43

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

.,FV INSERVICE TESTING PLAN - VALVES-t Table 4.0 1 UNIT 1 VALVE LISTING i

DRAWING : M 0035 1 l

DRAWING TITLE : REACTOR RECIRCULATION PIPING RELIEF f NORMAL REQUEST -'

DWG IST FUNCTION SIZE t(BY ACTU- POSI- TEST TEST OR COLD TECHNICAL' VALVE NUMBER C00R CLASS CA1EGORY (INCN) STYLE ATOR TION TYP! FREQ' SNUTDOWN POSITION-0263 2 0175 D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR I

FUNCil0N : RX LT 1 M68 & LT 1263 238 L0 SIDE EXCESS FLOW CK VLV 0263 2 019A C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1 646A & PT 1 647A MI SIDE EXCESS FLOW CK VLV l

0263 2 019e C3 1 A/C 1.000 XFC SA SYS AT 02 RR I CTC RR l

FUNCTION : RX LT 1 6465 & PI 1 6473 HI SIDE EXCESS FLOW CK VLV i 0263 2 020A 86 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 1 FT 1 263 63A MI SIDE EXCESS FLOW CK VLV 0263 2 0200 B6 1 A/C 1.000 XFC SA AT 02 RR SYS .

CTC RR IJWCTION : JET PMP 6 FT 1 263 638 NI SIDE EXCESS FLOW CK VLV '

0263 2 020C B3 1 A/C 1.000 XFC - SA SYS AT 02 RR CTC RR -

FUNCTION : JET PMP 11 FT 1 263-63C NI SIDE EXCESS FLOW CK VLV 0263 2 0200 83 1 A/C -1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 16 FT 1 263*630 MI SIDE EXCESS FLOW CK VLV 0263 2 023A C6 1 A/C 1.000 XFC SA SYS AT 0C RR CTC RR FUNCTION : JET PNP 1 FT 1263 63A L0 SIDE EXCESS FLOW CK Vtv 0263 2 0238 C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 6 FT 1263 636 LO $1DE EXCESS FLOW CK VLV 0263 2 023C B3 1 A/C 1.000 XFC SA SYS AT 02 RR Revision 3 VALVES 4 44

GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTlWG PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING N 0035 1 DRAWING TITLE : REACTOR REClRCULATION PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI. TEST TEST OR COLD- TECHNICAL VALVE NUNBER COOR CLASS CATEGORY (INCN) STYLE ATOR TION- TYPE FREQ SMUTDOWN POSITION 0263 2 023C B3 1 A/C 1.000 XFC SA STS CTC RR

, FUNCTION : JET PMP 11 FT 1 263 63C LO $1DE EXCESS FLOW CK VLV 0263 2 0230 s3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 16 F1 1 263 630 LO SIDE EXCESS FLOW CK VLV 0263 2 025 86 1 ' A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX CORE PLATE DPT 1 263 62 to $1DE EXCESS FLOW CK VLV 0263 2 027 A6 1 A/C 1.000 XFC SA SYS AT-02 RR CTC RR FUNCTION : RX CORE PLATE DPT 1 263 62 NI SIDE EXCESS FLOW CK VLV 0263 2 0318- C6 1 A/C 1.000- XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 2 FT 1 263 648 L0 SIDE EXCESS FLOW CK VLV 0263 2 031C C6 1 A/C 1.000 XFC SA SYS AT*02 RR CTC RR FUNCTION : JET PMP 3 FT 1 263 64C Lo $1DE EXCESS FLOW CK VLV 0263 2 031D C6 1 A/C 1.000 XFC SA -SYS AT 02 RR-CTC RR FUNCTION : JET PMP 4 FT 1 263 64D Lo SIDE EXCESS FLOW CK VLV 0263 2 031E C6 i A/C 1.000 XFC SA SYS AT.02 RR CTC RR -

FUNCTIOk JET PMP 5 FT 1 263 64E L0 SIDE EXCESS FLOW CK VLV 0263 2 031G C6 1 A/C 1.000 XFC SA SYS AT.02 RR CTC RR FUNCTION : JET PMP 7 FT 1 263 640 L0 SIDE EXCESS FLOW CK VLV 0263 2 031H C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR Revision 3 VALVES 4 45

a l

1 QUAD CITIES NUCLEAR POWER STAfl0N, TWITS 1 AND 2 S INSERVICE TESTING PLAN VALVES

$qd ) Table 4.0 1 UNIT 1 VALVE LISTING !

l DRAWING : M 0035 1 j DRAWING TITLE : REACTOR RECIRCULATION P! PING i l

i RELIEF l NORMAL REQUEST l

DWG IST FUNCTION $1ZE RODY ACTU- POSI- TEST TEST OR COLD TECNNICAL {

VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ $NUTDOWN POSITION l I

FUNCTION : JET PMP 8 FT 1 263 64N LO SIDE EXCESS FLOW CK VLV 0263 2 031J C6 1 A/C 1.000 XFC SA SYS AT 02 RR ;

1 CTC RR FUNCTION : JET PMP 9 FT 1 263 64J L0 SIDE EXCESS FLOW CK VLV l l 0263-2 031K C6 1 A/C 1.000 XFC SA SYS AT 02 RR' CTC RR 1 FUNCTION : JET PMP 10 FT 1 263 64K Lo SIDE EXCESS FLOW CK YLV 0263 2 031M C3 1 A/C 1.000 XFC SA SYS AT 02 RR C) CTC RR FUNCTION : JET PMP 13 FT 1 263 64M LO SIDE EXCESS FLOW CK VLV 0263 2 031N- C*3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 13 FT 1 263 64N L0 SIDE EXCESS FLOW CK YLV 0263 2 031P C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JEP PMP 14 FT 1 264 64P LO $1DE EXCESS FLOW CK VLV l

0263 2 031R C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JEP PMP 15 FT 1 263 64R LO $1DE EXCESS FLOW CK VLV i 0263 2 031T C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR l FUNCTION : JET PMP 17 FT 1 263 64T LO $10E EXCESS FLOW CK VLV 0263 2 031U C3 1 A/C 1.000 XFC SA SYS 'AT 02 RR CTC RR FUNCTION : JET PMP 18 FT 1 263 64U LO $!DE SNUT0FF VLV 0263 2 031V C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR Revision 3 VALVES 4 46 1

i

k' i

n QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 r INSERVICE TESTING PLAN VALVES

r. - s-:

Table 4.0 1' UNIT 1 VALVE LISTING-l-

i, DRAWING M 0035 1 -!

DRAWING TITLE : REACTOR RECIRCULAfl0N PIPING RELIEF NORMAL- REQUEST f

l DWG IST FUNCTION SIZE BODY ACTU- POSI . TEST TEST OR COLD. TECHNICAL .

VALVE NUMBER ' C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SMUTDOWN POSITION ';

FUNCTION JET PMP 19 FT 1 263 64V Lo SIDE EXCESS FLOW CK VLV-0263 2 031W C3 1 A/C 1.000 XFC SA SYS AT 02 RR I CTC RR FUNCTION : JET PMP 20 FT 1 263 64W Lo $10E EXCESS FLOW CK VLV 0263 2 033 B3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR i FUNCil0N RECIRC LOOP JET PMP FT Lo $10E EXCESS FLOW CK VLV ,,

. 0263 2 042A C6 1 A/C 1.000 XFC SA SYS AT 02 RR

't '

-CTC RR FUNCTION RX LT 1 263 73A HI SIDE EXCESS FLOW CK VLV 0263 2 042B C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT-1 263 738 NI SIDE EXCESS FLOW CK VLV :I I

h i

L l

1 i

i l'

I' I-l.

I.

l' 3,

l l

o Revision 3 VALVCS 4 47

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2,

[ INSERVICE TESTING PLAN

VALVES g' V}

Table 4.0 1 .

.- t

(' UNIT 1 VALVE LISTING DRAWINC : M 0035 2 DRAWING TITLE : REACTOR RECIRCULAfl0N P! PING s

RELIEF NORMAL REQUEST ,

DWG IST FUNCTION $12E BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL'

(

VALVE NUMBER COOR class CATEGORY. (INCN) STYLE ATOR TION TYPE FRE0 $NUTDOWN POSITION 0202-005A M0 D-6 1 B 28.000 GA No 0 STC CS CS 02A PIT Y2

{- FUNCT!DN : REACTOR RECIRCULATION

RECIRC. PUMP DISCHARGE VALVE

1 0202 0058 M0 03- 1 B 28.G00 GA No o BTC CS CS 02A Pli Y2 FUNCTION : REACTOR RECIRCULATION

RECIRC. PUMP DISCLANGE VALVE 0220 019A B6 1 A/C 1.000 XFC SA SYS AT 02 RR 4 CTC' RR p FUNCTION : RECIRC PMP DPT 1 261 5A LO SIDE EXCESS FLOW CK VLV I' 0220 0190 83 1 A/C 1.000 XFC SA SYS AT 02 RR

[ CTC RR l FUNCTION : RECIRC PMP DPT 1 261 58 LO SIDE EXCESS FLOW CK VLV l

!J 0220 020A B6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR ,

l FUNCTION : RECIRC PMP DPT 1 261 5A H! SIDE EXCESS, FLOW CK VLV I

0220 0208 83 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP DPT 1 261 54 HI SIDE EXCESS FLOW CK VLV 0220 021A' D8 1 A/C 1.000 XFC SA - SYS AT 02 RR j CTC RR FUNCTION : RECIRC PMP FT 1 261 6A Lo SIDE EXCESS FLOW CK VLV -

0220 0219 D1 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR l FUNCTION : REClRC PMP FT 1 261 6C LO SIDE EXCESS FLOW CK VLV 0220 022A D8 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP FT 1 261 6A H! SIDE EXCESS FLOW CK VLV

[ 0220 022e 01 1 A/C 1.000 XFC SA SYS AT 02 RR

'(

Revision 3 VALVES i 4 48 l

f f) 4 QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0035 2 DRAWING TITLE REACTOR RECIRCULATION PIPING '(

i' RELIEF i NORMAL REQUEST i DWG- IST FUNCTION SIZE ' BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL .!

VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SNUTDOWN POSITION !

0220 022B' D1 1 A/C- 1.000 XFC SA SYS CTC RR-FUNCTION : RECIRC PMP FT 1 261 6C M1 $1DE EXCESS FLOW CK VLV P

0220 044 E2 1 A .750 GL AO' 0/FC AT 01 RR BTC M3 /j FST .M3 PIT Y2 FUNCTION : REACTOR RECIRCULATION

REACTOR WATER SAMPLE LINE ISOLATION 0220 044 SO E2 NC B .001 503 30 E ' BTD M3 !

l p FST M3

- t, FUNCTION : REACTOR RECIRCULATION . CONTROL SOLEN 0ID 0220 045 E1- 1 A .750 GL A0 0/FC' -AT 01 RR l BTC M3 l

FST M3 PIT Y2 e FUNCTION : REACTOR RECIRCULAfl0N. REACTOR WATER SAMPLE LINE ISOLATION 0220-045 So E1 NC B .001. 303 50 E STO M3 FST M3 FUNCTION : REACTOR RECIRCULAfl0N CONTROL SOLENOID 0220 067A E6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC LOOP DPIS 1 261 34A A EXCESS FLOW CK VLV-0220 0675 F6 1 A/C 1.000 XFC SA STS AT*02 RR CTC RR FUNCTION : RECIRC LOOF DP!S*1 261*34A B EXCESS FLOW CK VLV 0220 067C E6 1 A/C 1.000 XFC SA STS AT 02 RR CTC RR FUNCTION : RECIRC LOOP DPIS 1 261 34C A EXCESS FLOW CK VLV 0220 067D F6 1 A/C 1.000 XFC SA SYS AT 02 RR U CTC RR Revision 3 VALVES 4 49

i l

.. QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES V

Table 4.0 1 j UNIT 1 VALVE LISTING ;

DRAWING : M 0035 2 DRAWING TITLE : REACTOR RECIRCULATION PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION . SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUNSER C00R CLASS CATEGORY (INCH) STYLE ATOR TION TYPE FREQ SMUTDOWN POSITION FUNCTION : RECIRC LOOP DPIS 126134C B EXCESS FLOW CK VLV 0220 067E 'E6 1 A/C 1.000'XFC SA SYS AT*02 RR CTC RR FUNCTION : RECIRC LOOP DPIS 1 261 348 A EXCESS FLOW CK VLV 0220 067F F6 1 A/C 1.000 XFC SA . SYS AT 02 RR CTC RR i FUNCTION : RECIRC LOOP DP!S 1 261 348 8 EXCESS FLOW CK YLV 0220 067G E6 1 A/C 1.000 XFC AT 02 RR (c

i SA SYS .

CTC RR FUNCTION : RECIRC LOOP DPIS 1 261 340 A EXCESS FLOW CK VLV i

~;

, 0220 067H F6 1 A/C' 1.000 XFC SA SYS AT 02- RR '

I CTC RR FUNCTION : RECIRC LOOP 0P15 1 261 340 8 EXCESS FLOW CK VLV 0220 089A- E1 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP SUCT PS 1 261 23A EXCESS FLOW CK VLV 0220 0898 E1 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR I FUNCTION : REClRC PMP SUCT PS 1 261 238 EXCESS FLOW CK VLV 0262 2 005A B7 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP SEAL CAVITY 2 Pl/PT EXCESS FLOW CK VLV 0262 2 0050 B2 1 A/C 1.000 XFC SA STS AT 02 RR CTC RR FUNCTION : RECIRC PMP SEAL CAvlTY 2 Pl/PT EXCESS FLOW CK VLV 0262 2 006A B7 1' A/C 1.000 XFC SA SYS AT 02 RR CTC RR i r '

t Revistori 3 VALVES 4 50 l-1

.As eUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE ' TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING h DRAWING : M 0035 2 I DRAWING TITLE : REACTOR RECIRCULATION PIPING

?

1. RELIEF IIORMAL REQUEST

[

DWG IST- FUNCTION SIZE teY ~ ACTU* P061- TEST TEST -OR COLD TECHNICAL C00R CLASS CATEGORY (INCN), STYLE ATOR T10N TYPE FREQ SNUTDOWN. POSITION g VALVE NUNBER FUNCTION : RECIRC PMP SEAL CAVITY 1 Pl/PT EXCESS FLOW CK VLY 1 0262 2 0064 B2- 1 A/C 1.000 XFC SA SYS AT 02 RR

[ CTC RR FUNCTION : RECIRC PMP SEAL CAVITY 1 PI/PT EXCESS FLOW CK VLV m-e e,

r Revision 3 VALVES 4 51

. _ . = . . _ _

i QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES (O[' Table 4.0 1 ;

UNIT 1 VALVE LISTING DRAWING : M 0036 i DRAWING TITLE : CORE SPRAY RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE B(mY ACTU- POSI- TEST TEST. OR COLD TECNNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR T!0N . TYPE. FREQ SNUTDOWN POSITION 1402 003A M0 F7 2 B 18.000 GA MO 0 0f0 M3 Pli Y2 FUNCTION : CORE SPRAY SUPPRES$10N POOL SUCTION LINE ISOLATION I l

1402 0038 M0~ F5 2 8 18.000 GA MO 0 BTO M3 PIT Y2 l FUNCTION : CORE SPRAY SUPPRES$10N POOL SUCTION LINE ISOLATION 1402 004A M0 B8 2 8 8.000 GL Mo C .BTC M3

~

PIT Y2 l

FUNCTION : CORE SPRAY FULL FLOW TEST RETURh 10 TNE SUPPRESSION POOL 1

.{'

1402 0044 M0 C8 2 8 8.000 GL M0 C BTC M3 l Pli Y2 .'l FUNCTION CORE SPRAY FULL FLOW TEST RETURN TO THE SUPPRESSION POOL 1402 008A E9 2 C 12.000 SCK .SA C/LO CTO M3 FUNCTION : CORE SPRAY - PWP DISCNARGE BACKFLOW PREVENTION '

1402 0088 E6 2 c. 12.000 SCK SA C/Lo CTO M3 FUNCTION : CORE SPRAY PWP DISCNARGE BACKFLOW PREVENTION 1402 009A A0 C3 1 A/C 10.000 CK , A0 SYS CTC CS CS 00A CTO CS CS 00A PIT Y2 FUNCTION : CORE SPRAY REACTOR VESSEL INJECTION CNECK VALVE 1

1402 0099 A0 C*3 1 A/C 10.000 CK A0 SYS CTC CS CS 00A CTO CS CS-00A PIT Y2 FUNCTION : CORE SPRAY REACTOR VESSEL INJECTION CNECK VALVE 1402 0134 E9 2 C 1.500 SCK SA C/LO CTO M3 FUNCTION : CORE SPRAY MINIMUM FLOW RECIR. LINE BACKFLOW PREVENTION 1402 0138 E6 2 c 1.500 SCK SA C/LO CTO M3 k

Revision 3 VALVES l 4 52 L __ _ _ ___ _ __ _ _ _ _________

eunD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES fable 4.0 1 UNIT 1 VALVE LISTINO -

DRAWING : h 0036 -.-

DRAWING TITLE CORE SPRAY -.

RELIEF NonetAL REGL.tST -

DWG iST FUICluN SIZE BODY ACTU+ POEl* T;1T TEST OR COLD TECNNICAL VI.LVE NUNDER C00R CLASS CATE00RY (INCN) STY'.E ATOR TIC % TYPE FREO SNUTDrwN P051T10W _

SUNCT!DW 1 CORE SPRAY

klkil8JM FLN REClR. LINE SACKfLN PREVENTION c 1402 024A esc t2 2 A 10.000 GA too 0 AT 01 at BTC **s BT0 tI3 PIT ft 7WCT10N CORE SPRAT

INJECTION LlP.E ISOLAfl0N VALVE 1402 0248 mo B5 2 A 10.000 GA no o AT 01 RR .

BTC M3 STO M3 -

Plf Y2 FullCil0N CORE SPRAY INJECTION LINE ISOLATION VALVE ,

1402 025A le0 C2 1 A 10.000 GA MO C AT 01 RR AT 03 RR TV 00N STC N3 _

BTO M3 Plf Y2 .

FUNCTION t CORE SPRAY

REACTOR VESSEL INJECT!001 It0 TOR OPERATED VALVE 1402 0250 180 C5 1 A 10.000 GA teo C AT 01 RR AT-03 RR BTC 63 ST0 K3 PIT Y2 FUNCTION t CnRE SPRAY a REACTOR VESSEL INJECTION It0 TOR OPERATED VALVE 1402 028A RV C9 2 C 2.000 RV SA C CT*SP V5 ,

FUNCTION : CORE SPRAY

CLASS 2 OISCNARGE LlelE OVERPRESSURE PROTECTION 1402 0288 RV 06 2 C 2.000 RV SA C CT*SP Y5 FUNCT1011 : CORE SPRAY

CLASS 2 OlSCNARGE LINE OVERPRESSURE PROTECTION 1402 031A 03 1 A/C .750 XFC SA SYS AT 02 RR .

CTC RR Revision 3 VALVES 4 53

i euAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 h^

INSERv!CE TESTINC PLAN

VALvit

\

Table 4.0 1 Wif 1 VALVE Ll8 TING DRAW!NG : N 0036 DRAWING TITLt CORE SPRAY RELIEF WORMAL REGLEST DWG !$f FUNCTION 812E BODY ACTU. POsl* TEST TEST OR COLD TECHNICAL VALVE NUNDER C00R CLAS$ 1. ATE 00RY (INCN) STYLE ATOR T10N TYPE FREQ $ HUT 00W:4 +051T10N FUNCTION CORE $ PRAY PMP D*!$*1'1459A L0 SIDE EXCESS FLOW CK Vtv 1402 0318 D4 1 A/C .75 0 KFC 5A SYS AT*02 RR 4 CTC RR ,

FUNCTION : CORE SPRAY PMP DPIS 1*14598 LO $1DE EXCESS FLOW CK YLV 1402-034A M0 E8 2 0 1.500 GA MO C BTC M3 Bio M3 Plf Y2 FUNCTION : CORE SPRAY

MikIIRJN FLOW REclRCULAfl0N LINE 180LATION 1402 0380 M0 E*7 2 3 1.500 GA MO C BTC M3 BTO M3 Plf Y2 FUNCTION : CORE SPRAY

MINilRM FLOW RECIRCULAfl0N llNE ISOLATION 1402 071 D*7 2 C 1.500 CK SA SYS CTC SM RV 00F FUNCTION : CORE SPRAY

CONDENSATE MAKE UP TRANSFER LINE ISOLATION k

Revision 3 VALVES 4 54

1 r ,

I t

GUAD CIT!ES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 CN INSERVICE TESTlWG PLAN . VALVES l

.f Table 4.0 1 l UNIT 1 VAlvt LISTING i

DRAWING : N 0037 4 DRAWING TITLE e RESIDUAL WEAT REMOVAL, PtteP DISCHARGE AND NEAT EXCNANGER l

i I

l RELIEF !

NORMAL REeutST DWG lsT FUNCTION SIZE b@Y ACTU- POSI. TEST TEST OR COLD TECHNICAL !

YALVE WVNSER C00R CLASS CATCCORY (INCN) STYLE ATOR T10N TYPE FREC SNUT00hti PollT10N

.1001 00?A esc 36 2 B 14.C30 GA loo 0/KL IT0 N3 PIT Y2 FUNCTION RNR SUPPRESSION POOL SUCil0N LINE ISOLATION l

1001 0073 No E6 2 8 14.000 GA No 0/KL ST0 N3 1 Pli Y2 l FUNCTION 1 RNR . SUPPRES$10N POOL SUCTION LINE ISOLATION l

1001 007C MO 36 2 0 14.000 GA 01 0 0/KL BT0 N3 <

l PIT Y2 l l

FUNCTION : RNR

SUPPRES$10N POOL SUCTION LINE It0LAfl0N l

V 1001 007D N0 E6 2 8 14.000 GA N0 0/KL STO se3 i

l PIT Y2 FUNCTION : RNE

SUPPRESSION POOL SUCTION LINE ISOLATION 1001 043A-M0 04 2 0 14.000 GA 11 0 C/KL BTC N3 l

Plf Y2 j FUNCTION : RNR . $NUTDOWN LdOLING BUCTION 190LAfloet 1001 0438 M0 E4 2 8 14.000 GA MO C/KL STC M3 ;

Plf Y2 FUNCTION : RNR * $NUTDOWN COOLING SUCT10ef 190LATicet 1001 043C se0 B8 2 B 14.000 GA too C/KL STC M3 Plf Y2 FUNCTION : RNR

SNUTD0 bad COOLING SUCTION ISOLAT10el 1001 0430 M0 D8 2 8 14.000 GA MO C/KL BTC M3 PIT Y2 FUNCTION : RNR

SMUTDOWel COOLING BUCTI0li 190LAfl0N 1001 067A B3 2 C 12.000 CK SA SYS CTC N3 CTO M3 FUNCT10ef a RNR

PtteP DISCNARGE SACKFLOW PREVENil0N O E 3.

V 1001 0675 2 C 12.000 CK SA SYS CTC N3 Revision 3 VALVES 4 55

I QUAD CITIES NUCLEAR POWER STAT!DN, UNITS 1 AND 2 !

INSERVICE TESTING PLA!!

VALVES O)

\

L I Table 4.0 1 :

UNIT 1 VALVE LISTING l

DRAWING : M 0037 DRAWING TITLE : RESIDUAL NEAT REMOVAL, PUMP Dl%CNARGE AND NEAT EXCHANGER I

REllEF j NORMAL REQUEST l DWG ist FUNCTION SIZE B@Y ACTU* Pott- TEST TEST OR COLO TECHNICAL VALVE NUMBER C00R CLAtt CATEGORY (INCN) STYLE ATOR T10N TYPE FREO $NUTDOWN PUSITION 1001 067B E3 2 C 12.000 CK SA SYS 470 M3 FUNCTION : RNR PWP DISCNARGE BACKFLOW FREVENTION 1001 06?C 09 2 C 12.000 CK SA SYS Cic N3

! CTO M3 l

FUNCTION : RNR + PUMP DISCHARGE BACKFLOW PREVEhfl0N 1001 067D E9 2 C 12.000 CK SA SYS CTC M3 CTO M3 FUNCTION 3 RNR . PUMP DISCNARGE BACKFLOW PREVENTION 0 1001 125A RV B5 2 C 1.000 RV SA C CT SP Y5 1

FUNCTION : RNR

PWP SUCTION OVERPRES$URE PROTECTION 1001 1258 RV E5 2 C 1.000 RV SA C CT SP Y5 FUNCTION : RNR

PLMP SUCTION OVERPRESSURE PROTECTION 1001 125C RV t7 2 C 1.000 RV SA C CT*SP V5 FUNCTION : RNR PUMP SUCTION OVERPRESSURE PROTECTION 1001 125D RV E7 2 C 1.000 RV SA C CT SP Y5 .

FUNCTION : RNR

PWP SUCTION OVERPRESSURE PROTECil0N 1001 142A B3 2 C 2.000 CK SA SYS CTC M3 CTO M3 FUNCTION : RNR MINI M FLOW RECIRCULAfl0N LINE BACKFLOW PREVENTION 1001 1428 03 2 C 2.000 CK SA SYS CTC M3 CTO M3 FUNCTl0N RNR

MINI M FLOW RECIRCULATION LINE BACKFLOW PREVENTION 1001 142C 89 2 C 2.000 CK SA SYS CTC M3 CTO M3 FUNCTION : RNA MININLM FLOW RECIRCULATION LINE BACKFLOW PREVENTION 1001 142D E9 2 C 2.000 CK SA SYS CTC M3 CTO M3 R wiston 3 VALVES 4 56

00AD CITIES NUCLEAR POWER $f Afl0N, UNITS 1 AND 2

/'7 INSERVICE TESTING PLAN

VALVES b Table 4.0 1 <

I UNIT 1 VALVE LISTING DRAWING : N 0037 DRAWING TITLE : REllDUAL NEAT REMOVAL, PtmP DISCNARGE AND NEAT EMCHANGER I

RELIEF NORMAL REQUEST DWG !$7 FUNCTION SIZE BODY ACTU- PNI . TEST TEST OR Crx.D TECHNICAL VALVE NUMBER COOR CLAlt CATEGORY (INCH STTLE ATOR T10N TYPE FREG SNUTDOWN POSITION FUNCTION : RNR

MlWI WA 2L(W RECIRCULAfl0W LINE BACKFLOW PREVENTION l l

1001 165A RV A2 3 C 4.000 RV SA C CT*s> T5 l

FUNCTION 3 RNA NEAT EXCHANGER THERMAL RELIEF VALVES l 1001 1658 RV A 10 3 C 4.000 RV $A C CT4P T5 FUNCTION : RNR

NEAf EXCHANGER TMLRMAL RELIEF VALW5

~ """*

i 1001 166A RV A2 2 C 1.000 RV SA C CT SP T5 !

I FLNICTION : kNF

WEAT EXCNANGER THERMAL RELIEF VALVES l

(R 1001*1668 RV A*10 2 C 1.000 RV SA C CT SP Y5 l FUNCTION : RNR NEAT EMCNANGER THERMAL RELIEF VALVES l

(

Revision 3 VALVES 4 57

BUAD CITIES NMEAR POWER STAfl0N, UNITS 1 AND 2 INSERVILE TESTING PLAN . VALVES Table 4.0 1 Wif 1 VALVE LISTINC DRAWING : M 0039 1 DRAWING TITLE : REllDUAL NEAT REMOVALI SUCTION, CONTAINMENT SPRAY, AND LPCI RCLIEF

stMAL REBUEST DWG IST FUNCTION SIZE BODY ACTU- P0Bl. TEST TEST OR Cott 'ECHNICAL VALVE IRMBER C00R CLASS'CATEGORT (INCN) STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION

.................. .... ..... ........ ...... ..... ..... ...... ..... .... . . . . . . . . ~........

1001 016A M0 A7 2 8 18.000 GL MD 0 BTC M3 BTO N3 P!T Y2 FUNCTION : RNR HEAT EXCHANGER BYPASS LINE ISOLAfl0N 1001 0168 M0 A2 2 B 18.000 GL M0 O BTC 4 BTO M3 Plf Y2 FUNCTION : RNR HEAT EXCHANGER BYPASS LINE IB0LATION 1001 01BA 000 C6 2 8 3.000 GA MD C BTC M3 BTD M3 PIT Y2 FUNCTION : RNR

MININUM FLOW RECIRCULATION RETURN LINE ISOLAtl0N 1001 01BB M0 C3 2 B 3.000 GA Mo C BTC M3 BT0 M3 PIT Y2 FUNCTION : RNR

MINIIRm FLOW REclRCULAfl0N RETURN LINE ISOLAfl0N 1001019A 180 BB 2 B 18.000 GA MO 0/KL STC CS CS 100 STO CS CS 108 PIT Y2 FUNCTION : RNR . CROSS TIE LillE ISOLAfl0N 1001 0198 M0 B2 2 B 18.000 GA MO 0/KL BTC CS CS.100 BTO CS CS*108 Plf Y2 FUNCTION t RNA . CROSS Tit LINE ISOLAfl0N 1001 020 .M0 B3 2 B 3.000 GA 10 0 C BTC M3 BTO M3 Plf Y2 FUNCTION : RNR . TRANSFER LINE TO RADWASTE ISOLATION 1001 021 M0 B3 NC B 3.000 GA MD C BTC M3 BTO M3 Revisten 3 VALVES 4 58

GUAD CITIES NUCLEAR PWER STAfl0N, UNITS 1 AND 2 f' INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING 1

DRAWING : N 0039 1 ;

DRAWING TITLE REllDUAL NEAT REMOVAL; SUCTION, CONTAINMENT SPRAY, AND LPCI RELIEF NOR8tAL REQUEST DWG IST FUNCil0N Sitt BODY AC7U- P081* TEST TEST ON COLD TECHN!u.L VALVE Ntar,Ek 000R CLASS CAfl00RY (INCN) STYLE ATOR T10N TTPE - FRE0 SNUT30WW *>0$l

t:W

..............a... .... ..... ........ ...... ..... ..... ...... ..... .... ........ .........

1001 021 ago B3 NC 3 3.000 GA Mo C PIT Y2 FUNCTION : R E

TRANSFER !!NE TO RAD W STE ISOLAfl0N 1001 022A AV E8 2 C 1.000 tv SA C CT.SP Y$

FUNCTION kMt

R4 PL84P DISCNARCI OVERPRE79URE PROTECil0N

, .-. -. l l 1001 0228 RV E*2 2 C 1.000 kV SA C CT+SP Y$

FUNCil"W 3 RNR

RNR PL44P DISCNARGE OVERPRES$URf PROTECTION ]

1 - 1 1001 023A M0 E6 2 8 10.000 GA MD C OTC M3 Plf Y2 i FUNCTION : RNR

DRYWELL SPRAY MOTOR OPERATED ISOLATION VALVE 1001 0238 M0 E3 2 B 10.000 QA No C BTC N3 1 Plf Y2 l FUNCTION : RNR

DRYWELL SPRAT MOTOR OPERATED 190LAfl0N VALVE l

l 1001 026A M0 E5 2 s 10.000 GA No C BTC M3 PIT Y2 FUNCTION : RNR

DRYWELL SPRAY MOTOR OPERATED ISOLATION VALVE 1001 0268 M0 E4 2 B 10.000 GA MO C BTC M3 Plf Y2 FUNCil0N : RNR

DRYW LL SPRAY MOTOR OPERATED ISOLAfl0N VALVE 1001 028A M0 E*6 2 B 16.000 GL M0 O OTC CS CS 10C STO CS CS 10C i PIT Y2 FUNCTION : RNR REACTOR VESSEL INJECTION MOTOR OPERATED VALVE l

1001-0288 M0 E3 2 B 16.000 GL M0 O BTC CS CS 10C BT0 CS CS 10C I Plf Y2 l FUNCTION : RNR

REACTOR VESSEL INJECTION MOTOR OPERATED VALVE l

1001 029A M0 E*6 1 A 16.000 GA MD C AT 03 RR TV 00H BTC CS CS 10C Revision 3 VALVES

l. 4 $9 l

[

i

eunD CITIES W CLEAR POWER STATION, UNITS 1 Am 2 D

INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE L18 TING DRAWING t N 0039 1 DRAWING TITLE I REllDUAL teEAT REMOVAL; SUCTION, CONTAINNENT SPRAY, AND LPCI RELIEF NORMAL REeu!$T DWG IST FUNC110N $12E 80DY ACTU- POSl* TEST TEST OR COLD T!CNNICAL-VALVE trJeER C002 CLAtt CATEGORY (INCN) STYLE ATOR T10N TYPE FREG $NUTDOWN PO$1710N

........ 4........ .... ..... ........ ...... ..s.. ..... ...... ..... .... ........ .........

1001 029A M0 E6 1 A 16.000 GA No C BTO CS CS 10C PIT Y2 MCT!0d t RNR

REACTOR YESSEL INJECTION NOTOR OPERATED VALVE 1

1001 0298 No E3 1 A 16.000 GA NO C AT-03 RR TV 00N BTC CS CS 10C I BTO CS C$ 10C l Pli Y2 ')

FUNCil0N 8 RNR . kEACTOR VEltEL INJECT 10N MOTOR OPERATED VALVE

{

1001 034A M0 E7 2 B 16.000 GA No C BTC M3 J

t BTO M3 Pli Y2 l

FUNCT10N 3 kNR * $UPPRES$10N POOL COOLING AS SPRAY ISOLATION VALVE l l

l' 1001 0348 M0 E3 2 B 16.000 GA No C BTC M3 i

BT0 M3 Plf Y2 FUNCTION RNR SUPPRES$10N POOL COOLING AND SPRAY ISOLAfl0N VALVE 1001 036A M0 E7 2 B 14.000 GL MO C BTC M3 BT0 N3 i PIT Y2 FUNCil0N t RNR

SUPPRES$10N POOL COOLING N0 TOR OPERATED ISOLATION VLV.

1001 0368 M0 D3 2 8 14.000 GL No C BTC M3 BT0 M3 PIT Y2 FUNCTION 1 RNR SUPPRESSION POOL COOLING MOTOR OPERATED 180LAT!0N VLV.

1001 037A M0 E7 2 B 6.000 GL No C BTC M3 PIT Y2 FUNCTION I RNR SUPPRES$10N POOL SPRAY MOTOR OPERATED ISOLAfl0N VALVE 1001 0375 N0 D3 2 B 6.000 GL no C BTC M3 PIT Y2 i

Reviston 3 VALVES l 4 60 I

auAD CITIES NUCLEAR POWER STATION, UNIT $ 1 AND 2

/]

s /

INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0039 1 DRAWING TITLE : REllDUAL NEAT RE100 VAL; SUCTIQi, CONTAllINENT SPRAY, AND LPCl RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU- PO$la TEST TEST OR COL 0 TECNhlCAL ]

VALVE M mBF4 Cout class CATEG3RY (INCM) STYLE ATOR ficN TYPE FREO $NUTDOWN POSITION ,

. FUNCTION t ant . irJPPRESS10W P;tA SPAAY 40 Tut OPERATED !$0LAfl0N VALYC ,

i 1001 047 M0 C4 1 A 20.000 CA 14 0 C At 01 RR I AT 03 RR TV 00N STC CS CS 10A PIT Y2 FUNCTION : RNR * $NUTDOWN COOLING MOTOR OPERATED 180LAfl0N VALVE 1001 050 M0 D4 1 A 70.000 GA 10 0 C AT 01 RR Af*03 RR TV DON (s

t ITC Plf CS Y2 CS 10A i

\

FUNCT!0N : RNR . $NUTDOWN COOLING MOTOR OPERATED ISOLATION VALVE i 1001 059 F3 2 C 1.000 RV SA C CT SP Y5 FUNCTION : RNR . RNR DISCNARGE PIPlhG OVERPRESSURE PROTECTION 1001 068A A0 E5 1 A/C 16.000 CK A0 SYS CTC CS CS 004 CTO CS CS 00A Plf Y2 FUNCTION RNR REACTOR VESSEL INJECTION CHECK VALVE 1001 0688 A0 E4 1 A/C 16.000 CK A0 SYS CTC CS Cs 00A CTO Cs CS 00A Pli Y2 FUNCTION : RNR

REACTOR VESSEL INJECTION CNECK VALVE 1001 131 07 2 C 3.000 CK SA SYs CTC SK RV 00F FUNCTION 8 RNR CONDENSATE MAKE UP TRANSFER LINE 180LAT10N 1001 136A D8 2 C 3.000 CK SA SYs CTC so RV 00F FUCCTION : RNA CONDENSATE NAKE*UP TRANSFER LINE ISOLAfloti 1001*1368 E2 2 C 3.000 CK SA STS CTC SD RV 00F FUNCTION : RNR CONDENSATE MAKE UP TRANSFER LINE ISOLAfloof a

Revision 3 VALVES 4 61

i I

GuAD CITIES NUCLEAR POWER STAfl0Ni UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES

['

U fable 4.0 1 UNIT 1 VALVE LISTING DRAWING t M 0039 2 DRAWING TITLE : DEllDUAL MAT REMOVAL, RNR9W PWPS AND RNR NEAT EXCNANGER RELIEF !

NORMAL REQUEST DWG IST FUNCTION SIZE BCDY ACTU- Poll- TEST TEST OR COLD TECHNICAL VALVE NW8ER COOR CLAS$ CATEGotY (INCN) STYLE ATOR fl0N TYPE FRED $NUTDOWN P0$lfl0N 1001 002A C7 3 C' 12.000 cK sA STS CTC M3 CTO M3 FUNCTION kNR($V)

PWP DISCHARGE CNECK VALVE 1001 0028 B7 3 C 12.000 CK SA SYS CTC M3 CTO M3 FUNCTION 1 RNR($W)

P W P DISCNARGE CNECK VALVE l

1001 002C 02 3 C 12.000 CK SA SYS CTC M3 i CTO M3 l FUNCTION RNR($W)

P WP DISCNARGE CHECK VALVE .

.j t l 1001 002D S2 3 C 12.000 CK SA SYS CTC ' M3 l CTO M3 FUNCTION 4 RNR($W)

PWP DISCNARGE CNECK VALVE l

l 1

l l

l N.

Revision 3 VALVES 4 62 l l

l

I SUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 Am 2

(' INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0040 DRAWING TITLE : STAND 8T L18UID CONTROL RELIEF NORMAL REaufST DWG IST FUNCTION SIZE SCET ACTU- P081- TEST TFST OR COLD TECHNICAL VALM #JMBER C00R CLASS CATC00RT (!NCh) STTLE ATOR TION TYPE FREQ SNUTDOWN P051T10N it)1-C15 C3 1 A/C 1.500 CK SA STs AT 01 RR CTC RR RY 11A CTO RR RV 11A i CIOP CS RV 11A FUNC1100 : SSLC

INJECTION LINE CHCCK VALVE 1101 016 C3 1 A/C 1.500 CK SA STS AT 01 RR CTC RR av 11A l CTO RR RV 11A CTOP CS RV 11A l

. FUNCTION t SSLC a PRIMART CONTAINNENT ISOLATION (CNECK) VALVE !

' l 1101 043A D6 2 8 1.500 CK SA STS CTC m3 I CTO M3 FUNCTION : SSLC PUMP DISCHARGE CNECK VALVE 1101 0438 D6 2 8 1.500 CK SA STS CTC N3 CTO M3 j FUNCTION : SSLC PUMP DISCHARGE CNECK VALVE l l

1105- A RV C7 2 C 1.500 RV SA C CT SP T5 FUNCTION : SSLC RELIEF VALVE FOR OVERPRESSURIZAfl0N PROTECTION j 1105- B RV E6 2 C 1.500 RV SA C CT SP T5 FUNCTION : SSLC RELIEF VALVE FOR OVERPRESSURIZATION PROTECTION 1106- A C4 2 0 1.500 SMR EMP C/KL DT E SM FUNCTION : SSLC EMPLD51VE ACTUATED ($QUIS) VALVE 1

1106- O D4 2 0 1.500 SNR EXP C/KL DT E SN FUNCTION : SSLC EMPLoslVE ACTUATED (SOUIS) VALVE l

Revision 3 VALVES 4 63

ouAD CITIES WUCLEAR POWER STAfl0N, UNITS i AND 2

[T INSERVICC TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : 84 0041 1 DRAWING TITLE : CONTROL R(E DRIVE NYDRAULIC RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DY ACTU- Post- TEST TEST OR COLD TECHNICAL VALVE NUMptR COOR CLASS CATEGORT (INCN) STTLE ATOR TION TTPE FREQ SNUTDOWN POSIT!0N 0302 020A E6 NC B .500 803 to E BTD CS CS 03s FST CS CS C38 FUNCTION : CR0 SCRAM DUMP ($0LEN010) VALVES

~

0302 020s 't8 h; .500 $03 S0 I B E STD CS CS 03e FST Ct CS 038 i l

FUNCTION 1 CR0 SCRAM DUMP (SOLENCID) VALVES !

i 0302 021A E6 2 8 1.000 DIA A0 C/FC BTC M3 j FST M3 l

( FUNCTION CRD SCRAM DISCHARGE VOLletE VENT (SDV)

)

0302 0218 E6 NC B 1.000 DIA A0 C/FC STC M3 FST M3 PIT T2 FUNCil0N : CRD SCRAM DISCHARGE VOLUME VENT (BDV) 0302 021C F1 2 8 1.000 DIA A0 C/FC BTC M3 FST M3 Plf T2 FUNCTION CRD SCRAM DISCHARGE VOLLstE VENT (SDV) 0302-0210 F1 NC B 1.000 DIA A0 C/FC BTC M3 FST M3 PIT T2 FUNCTION : CR0 SCRAM DISCNARGE VOLUME VENT (SDV) 0302 022A F5 2 8 2.000 CIA A0 C/FC BTC M3 FST M3 Plf T2 FUNCTION CRD SCRAM DISCNARGE V0ttME (SDV) DRAIN 0302 022B F5 NC B 2.000 DIA A0 C/FC BTC M3 FST M3 P!T T2 Revision 3 YALVES 4 64

l l

GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

( INSERVICI TESTING PLAN . VALVES

(

Table 4.0 1 UNIT 1 VALvt Ll5 TING DRAWING : M 0041 1 DRAWING TITLE : CONTROL ROD DRIVE NYDRAULIC RELIEF NORMAL REQUEST DWG !$f FUNCTION SIZE BODY ACTU- P081* TEST TEST OR COLD TECNNICAl.

VALVE NuuSER C00R CLASS CATEGORY (!N'H) STTLE ATOR TION TYPE FREC $NUTDOWN POSITION FUNCil0N : CR0 $ DAM P!$ CHARGE VOLUME (SDV) DRAIN 0302 022C F3 2 s 2.000 DIA Ao C/FC s1C M3 FST M3 j Pli Y2 FUNCTION : CRD SCRAM DISCHARGE VOLLME (SDD DRA!N 4302 022D F2 NC C 2.000 DIA A0 C/FC BTC M3 FST M3 Plf Y2 7 FUNCTION : CRD SCRM DISCHARGE veLLM (SDV) DEAIN 0302 025A C.7 NC B 1.000 803 So D STE CS CS 038 FUNCTION : CRD ALTERNATE RCD INJECTION SCRM (SOLENotD) VALVES 0302 0250 E7 NC 8 1.000 803 80 D BTE CS CS 038 FUNCTION : CRD ALTERNATE ROD INJECTION SCRM (SOLENotD) VALVES (

0302 181A D8 NC 5 1.000 802 30 C/F0 STO CS CS 038 FST CS CS 038 FUNCTION : CR0 ALTERNATE ROD INJECTION SCRAM (80LEN0!D) VALVES 0302 1818 D8 NC B 1.000 S02 So C/70 BTO CS CS 038 FST CS CS 038 FUNCTION : CR0 ALTERNATE RCD INJECTION SCRM (80LENotD) VALVES -

0302 182A F.8 NC 9 1.000 802 30 C/F0 BTO CS CS 038 FST CS CS 038 FUNCTION : CRD ALTERNATE ROD INJECTION SCRM (SOLEN 0ID) VALVES 0302 1828 F8 NC B 1.000 802 80 C/F0 BTO CS CS 038 FST CS CS 038 FUNCTION CRD ALTERNATE RCD INJECTION SCRAM (80LEN0!D) VALVES 0305 000 RPD E.10 1 0 .250 RPD SA C DT M WT TV 038 FUNCTION : CRD ACCUMULATOR RUPTURE DISK (TYPICAL OF 177)

(

Revision 3 VALVES 4 65 i

I

b GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

( 'N INSERv!CE TESTING PLAN . VALVES i .

Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0041 1 DRAWING TITLE : CONTROL RCD DRIVE HYDRAULIC i RELIEF NORMAL REQUEST DWG lti FUNCil0N SIZE 80DY ACTU- POSI - TEST TEST OR COLD TECHNICAL VALVE immtER C00R CLAts CATEGORY (INCM) STYLE ATOR T10N TYPE FRE0 $NUTDOWN P0$1710N 0305 114 E9 2 C .50 CK SA SYS CTC RR RV 03A TV 03A CTO RF, tv 03A FUNCil0N : CR0 NCU BACKFLOW PROTECfok (TYP. OF i n) r DNS 115 E 10 1 C .500 CK SA CYS AT 06 Y2 CTC CS CS 03A TV 03A f

FUNCTION : CRD ACCLMULATOR DiSCMARGE SACKFLW PROTECTON (TYP. OF 1U) l 0305 1 9 E9 NC B .35 803 30 L $70 RR RV 03A TV 03A FST RR RV 03A FUNCTION : SCRAN PILDT SOLENOID VALVES (TYP. OF i n)

\

\ 03Ci 118 E9 NC 8 .35 303 30 E BTD RR RV 03A TV 03A FST RR RV 03A FUNCTION : SCRAN PILOT SOLEN 0ID VALVES O YP. OF 1 U) ,

0305 120 FCV C 10 1 B 1.000 302 to C/FC BTC N3 TV 03A FST N3 FUNCTION CRD NCU DIRECTIONAL (WITMDRAW) CONTROL VALVE (TYP. OF 1 U )

0305 121 so C9 i B .50 802 to C/FC BTC N3 TV 03A FST M3 FUNCTION : CRD NCU DIRECTIONAL (INSERT) CONTROL VALVE (TYP. OF i n )

0305 122 80 C9 1 B .50 302 to C/FC BTC N3 TV 03A FST N3 FUNCTION : CR0 NCU DIRECTIONAL (WITMDRAW) CONTROL VALVE (TYP. OF in) 0305 123 FCV C 10 1 B 1.000 802 30 C/FC BTC M3 TV 03A FST M3 FUNCTION : CRD NCU DIRECTIONAL (INtERT) CONTROL VALVE (TYP. OF in) 0305 126 *CV D 10 1 B 1.000 DIA A0 C/F0 BTO RR RV 03A TV 03A FST RR PIT Y2 FUNCTION : CRD ACCUN. DISCMC 1 TO $ PEED SCRAN INSERTION (TTP. OF 1U)

A Revision 3 VALVES 4M

. _ ~ _ - . - . . . - . - _ - - . - - . - . . . - - . - . _ . - . . _ . -

SuAD CITIES NUCLEAR POWER $1 Afl0N, UNITS 1 AND 2 f INSERVICE TESTING PLAN

VALVES

( Table 4.0 1 UNIT 1 VALVE LISTING DRAWING N 0041 1 DRAWING TITLE : CONTROL ROD DRIVE NYORAULIC RELIEF NONNAL REQUEST DWG IST FUNCTION SIZE GCSY ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATE00RY (INCN) STYLE ATOR T10N TYPE FREG SNUTDOWN Pollfl0N 0305 127 *CV D9 1 0 .750 OIA A0 C/F0 BT0 RR RV 03A TV 03A FST RR Plf Y2 FUNCTION : DISCHARM CRD NCb TO THE SCRAN DISCHARGE VOL.(TTP. OF 177) 0305 138 C 10 1 C .500 CK SA SYS CTC N3 TV 03A FL'NCTION : CRD TAtivE WATER BACKFLol PQTECTON (TYP. OF 177)

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i kevision 3 VALVES 4 67 i

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1

oua0 CITIES NUCLEAR POWER STAT 10N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES

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V Table 4.0 1 UNIT 1 VALVE LISTING i

DRAWING : N 0042 1 DRAWING TITLE : 0FF GAS RELIEF ;

l le0RMAL REQUEST DWC IST FUNCTION SIZE 8(ET ACTU- P081- TEST TEST OR COLD TECHNICAL VALVE trJNBER COOR CLA$$ CATEGORY (INCN) STY 5E ATOR TION TYPE FRE0 $NUTDOWN POSITION 5401- A A0 E8 NC 8 18.000 BTF A0 0/FC BTC M3 FST M3 Plf Y2 FUNCTioW 0FF GAS CONDEN$ER !$0LATION VALVE 5401- A CK 1 99 NC C .001 CK $A SYS AT 06 Y2 )

CTC RR l FUNCTION : OFF GAS CONDENf!R ISOLATICel VALVE ACCUN. CHECK VALVES 5401- A $0 E */ NC 8 .001 804 $0 E STD M3 y FST M3 L FUNCTION : NF GAS CONDENSER ISOLAfl0N $0LEN010 5401- B A0 E8 hc 5 18.000 BTF A0 0/FC BTC M3 FST M3 j PIT Y2 FUNCTION : OFF GAS CONDENSER ISOLAfl0N VALVE

$401- B CK 2 99 NC C .001 CK SA SYS AT 06 Y2 CTC RR l

FUNCTION : 0FF GA$

CONDENSER 180LAT10N VALVE ACCW. CHECK VALVES 5401- B 50 E7 NC B .001 806 30 E STD M3 1 FST M3 FUNCTION : 0FF GAS CONDENSER It0LAtl0N BOLEN010 5402- A A0 03 NC 8 18.000 GA A0 0/FC BTC K3 FST M3 Plf Y2 FUNCTION OFF GAS

CONDEN$ER ISOLAfl0N VALVE i

5402- A CK 2 99 NC C .001 CK SA STS AT 06 Y2 CTC RR FUNCTION : OFF GAS CONDEN$ER 180LAT!ON VALVE ACCLM. CHECK VALVES 5402- A 50 D2 NC B .001 $04 $0 E STD M3 FST M3

%d .

kevision 3 VALVES 4 68

GUAD ClflES WUCLEAR POWER $1Afl0N, UWlf$ 1 AND 2 lasERVICE Test!NG PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LllflNG DRAWING : N 0042 1 DRAWING fifLE : OFF GAS RELIEF NORMAL REQUEST DWG IST FUNCTION 812E 80DT ACTU- P0Gl* TEST Test OR COLD TECHNICAL VALVE NWSER C00R CLASS CAff00RT (INCN) STYLE ATOR T10N TYPE PRE 0 SNUTDOWN Pottil0N FUNCTION : OFF GAS . CONDENBER 190LAfl0N SOLENOID

$402- B Ac D3 NC 8 18.000 GA A0 0/?C BTc e FST 90 P1f Y2 FUNCt10N : OFF GAS CONDENSER ISOLAfl0N VALVE 5402- B CK Z 99 NC C .001 CK SA SYS AT 06 Y2 ift RR FUNCTION : OFF GAS CONDENSER ISOLA 110N VALWi! ACCW. 4 HECK VALWS 5402- 8 $0 D2 NC $ .001 804 80 E BTD R3 FST IG FUNCTION : OFF GAS

CONDENBER ISOLAfl0N SOLEN 0ID Revision 3 VALVES 4 69 l

i

GUAD CITIES WUCLEAR POWER STAfl0N, UNITS 1 Am 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE L18TlWG DRAWING : M 0043 DRAWING TITLE : REACTOR SUILDlWG EQUIPMENT DRAlWS (INCLt.1/2 DG START AIR)

RELIEF NORMAL REQUEST DWG' IST FUNCTION $12E 80DT ACTU- Poll

TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLAS$ CATEGORY (INCN) $ffLE ATOR T10N TYPE FRE0 $NUTDOWN Postfl0W 2001 003 A0 F.7 2 A 3.000 GA A0 C/FC AT 01 RR STC M3 FST M3 PIT Y2 FUNCTION RX SLDG EQUIP DRNS.

PRIMARY CONTAINMENT ISOLAfl0N VALVE 2001 003 80 F7 NC 3 .001 Sc3 $0 0 BTD M3 Ftf M3 FUNCT!nN : RX SLDG 200!P DANS.

DRIMARY CONT. ISOLATION VALVE SOLEN 0ID 2001 004 *A0 F47 3 A 3.000 GA A0 C/FC AT 01 pt BTC M3 FST M3 Plf Y2 . . _

FUNCTION RX SLDG EQUIP DRNS.

PRIMARY CONTAINMENT ISOLAfl0N VALVE 2001 004 80 F7 NC B .001 303 80 D BTD M3 FST M3 FUNCTION : RX BLDG EQUIP DANS.

PRIMARY CONT. 190LAfl0N VALVE $0LEW010 2001 015 A0 E4 2 A 3.000 GA A0 C/FC AT 01 RR BTC M3 FST M3 Plf Y2 FUNCTION : RX BLDG EQUIP DANS. PRIMARY CONTAINMENT ISOLAfl0N VALVE 2001 015 80 E4 NC 5 .001 803 30 D BTD M3 FST M3 FUNCTION RX SLDG EQUIP DRNS.

PRIMARY CONT. ISOLAtl0N VALVE SOLEW0!D 2001 016 A0 E3 2 A 3.000 GA A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : RX BLDG EQUIP DRNS.

PRIMARY CONTAlWMENT ISOLATION VALVE 2001 016 80 E3 NC B .001 303 80 0 BTD M3 Revision 3 VALVES 4 70

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QUAD CITIES NUCLEAR POW R STAfl0N, UNITS i AND 2

. f INSERVICE TESTING PLAN

VALVES

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Table 4.0 1 UNIT 1 VALVE LISTING DRAWING N 0043 DRAWING TITLE : REACTOR SUILDING EQUIPMENT DRAINS (INCLS.1/2 DG START AIR) ,

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE Nef ACTU+ P081* TEST TEST OR COLD TECNNICAL VALVE IMeetER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FRES SNUTDOWN Postfl0N I 2001 016 50 E.3 NC S .001 803 So D FST M3 FUNCTION : RX SLDC EQUIP DANS.

PRIMARY CONT. ISOLAfl0N VALVE 80LEN010 f

4 99 048 - 1/2 C9 NC C 1.500 CK SA SYS CTO M3 FUNCTION : SERVICE AIR * (DIESEL) RECElVER TANK btCKFLOW PROTECTION ;

499 196 * *1/2 C'9 NC t 1.500 CK SA STC CTO M3 FUNCTION : SERV)CE AIR - (DICSEL) EECEIVER TANK SAJFLOW PROTECTION 4 99 226 - 1/7 C7 NC S .001 CL A0 C STf; M3 RV 46A p ST0 M3 RV 4A t FUNCTION : SERVICE AIR - (DIESEL) AIR START RELAY VALVE 499 306A* 1/2 2 99 NC C .001 RV SA C CT SP Y$

FUNCTlou SERVICE AIR * (DIESEL) RECEIVER TANK SAFETY VALVE i Wrv-3060 1/2 2*99 NC C .001 RV SA C CT SP Y5 FUNCTION : SERVICE AIR * (DIESEL) RECEIVER TANK SAFETY VALVE 499 306C- *1/2 2 99 NC C .001 RV SA C CT SP Y5 FUNCTION : SERVICE AIR * (DIESEL) RECEIVER TANK SAFETY VALVE 4699 3060* *1/2 2 99 NC C .001 RV SA C CT SP V5 FUNCTION : SERVICE AIR - (DIESEL) RECE!VER TANK SAFETY VALVE 4699 307A. 1/2 2 99 NC C .500 CK SA SYS AT 06 Y2

,CTC M3 FUNCTIDM SERV!CE AIR * (DIESEL) CONPRESSOR SACKFLOW PROTECTION 4 99 3078- 1/2 2 99 NC C .500 CK SA SYS AT 06 Y2 CTC M3 FUNCTION : SERVICE AIR * (DIESEL) COMPRESSOR SACKFLOW PROTECTION 4699 309 - 1/2 2 99 NC C .001 CK SA SYS CTC M3 CTO M3 FUNCTION : SERVICE AIR - (DIESEL) AIR START RELAY VALVE DPNROM. CK VLY.

l k Revision 3 VALVES 4 71

1 GunD CITIES NUCLEAR POWER STAft0W, UNITS 1 AND 2 f] IN$ERVICE TESTING PLAN

VALVES

\j Table L.0 1 UNIT i VALVE LISTING DRAWING : N 0043 DRAWING TITLE : REACTOR SUILDING E0VIPMENT DRAINS (INCLS.1/2 DG BTART AIR)

]

kELitF WORetAL REGUEsT DWG 15T FUNCil0N $12E 80DY ' ACTU- P061* TEST TEST OR COLD TECHNICAL :

VALVE NUMBER C00R CLAls CATEGORT (INCN) STYLE ATOR T10N TTPE FREC SNUTDOWN POSITION 4699 310 - 1/2 2 99 NC B .001 803 R0 0 STD M3 BTE N3 FUNCTION : SERVICE AIR - (DIESEL) START $0LEW0iD 1

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Revision 3 VALVES

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i BUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVE 8 Table 4.0 1 UNif 1 VALVE LISTING -

DRAWING : N 0044 DRAWING TITLE : STANDBf GA$ TREATMENT ,

1 l

RELIEF NORMAL REBUEST l

DWG !$f FUNCTION $1ZE BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR TIDW TYPE FRES $NUTDOWN P0$lfl0N '

.................. .... ..... ........ ...... ..... ..... ...... ..... .... ........ ......... l 7503- -

M0 b2 NC B 18.000 BTF M0 O BTC M3 BTO M3 PIT - T2 FUNCTION : $8GT . TRAIN INLET !$0LAfl0N VALVE l I

7504- A M0 1/2 03 NC B 6.000 BTF M0 O BTC M3 l BT0 M3 I Plf Y2 FUNCTION : $5GT

COOLING AIR INLET 7504- B M0 1/2 A3 NC B 6.000 BTF M0 O BTC M3 j BTO M3 Plf Y2 l FUNCil0N : 800T

COOLING AIR INLET l

'l 7505* A MO 1/2 03 NC -B 24.000 BTF N0 C BTC M3 BTC M3 l

Plf Y2

]

FUNCTION : $5GT . TRAIN $ ELECT AND INLET ISOLAfl0N VALVE 7505- B Mo 1/2 B3 NC B 24.000 BTF M0 C BTC M3 BT0 M3 Plf Y2 j FUNCTION : $3GT TRAlW SELECT AND INLET ISOLAfl0N VALVE ;

7507- A M0 1/2 D*9 NC B 24.000 BTF Mo C BTC M3 BT0 M3 PIT Y2 l FUNCTION : $5GT

TRAIN $ ELECTION AND OUTLET IB0LAT10N VALVE I l

7507 B M0 1/2 B9 NC B 24.000 BTF N0 C BTC M3 BT0 M3 Pli T2 I FUNCT10N : $5GT = TRAIN $ ELECTION AND OUTLET IBOLATION VALVE O !

Revision 3 VALVES u

4 73 :

l

GunD CITIES WUCLEAR POWER STAfl0N, UNITS 1 AND 2 thSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWIN3 : M 0046 DRAWING TITLE : HIGN PRESSURE COOLANT INJECTION RELIEF NORMAL REQUEST DWG IST FUNCTION 812E BODY ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NWBER C00R CLASS CATEGORY (INCN) STTLE ATOR T10N TYPE FREG SenJTDOWN POSITION 2301- *SV A7 2 8 24.000 PLC Ho C STC M3 STO M3 PIT Y2 FUNCTION : HPCI Tutt!NE STOP VALVE 2301 003 No A7 2 B 10.000 GA Mo C ST0 M3 Pif Y2 FUNCTION n NPCI STEAM SUPPLY /SLOCKING VALVE, PRE NEATS THE SUPPLY LlWE 1301 004 *MO C9 i A 10.000 GA MD 0 AT 01 RR STC CS CS 23A ST0 CS CS 23A Plf Y2 FUNCTION : HPCI STEAM SUPPLY FRON INE REACTOR VESSEL TO THE TURBINE 2301 005 M0 3 10 1 A 10.000 GA M0 O AT 01 RR BTC CS CS 23A STO CS CS 23A Plf Y2 FUNCTION : HPCI STEAM SUPPLY FROM TMS REACTOR VESSEL TO TWE TURBlWE 2301 007 AD E6 2 C 14.000 CK A0 SYS CTO CS CS 00A Plf Y2 FUNCTION : HPCI INJECTION LINE TO FEEDWATER SACKFLOW PREVENil0N 2301 008 No E6 2 8 14.000 GA No C BTC M3 PIT Y2 FUNCTION : HPCI INJECTION LINE TO FEEDWATER ISOLATION 2301009 -No E5 2 8 14.000 GA No o sfo M3 PIT Y2 FUNCTION : NPCI !NJECTION LINE TO FEEDWATER ISOLAtl0N 2301 010 MO E5 2 8 6.000 GL MD C STC M3 PIT Y2 FUNCTION : MPCI FULL FLOW TEST RETURN TO CONDENSATE STORAGE TANK d

Revision 3 VALVES 4 74

OuAD CITIES WUCLEAR POWER STAfl0N, UNITS 1 AS 2 ;

I O INSERVICE TESTlWG PLAN . VALVES ;

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V-Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0066 DRAWING TITLE : NIGN PRESSURE COOLANT INJECTION I

RELIEF NORMAL A10UEST DWG IST FUNCTION SIZE tef ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLAll CATEGORY (lNCN) STTLE ATOR T10N TYPE FRE0 SNUTDOWN Postfl0N 2301 014 M0 C6 2 8 4.000 GL N0 C BTC M3 2 ST0 M3 J

PIT Y2 l FUNCTION : NPCI MINIMUM FLOW RECIRCULATION LlWE ISOLATION 1 2301 020 E1 2 C 16.000 CK SA SYS CTC SE RV 00F !

FUNCTION : HPCI TO CONDENSATE STORAGE TANK BACKFLOW PREVENTION 2301 C23 RV B3 2 C 1.500 RV SA C CT SP Y5 FUNCTION : HPCI BCESTER SUCTION LINE 'JVERPRESSURE PROTECTION

( .

2301 026 D 10 1 t./t 1.000 NFC SA $13 AT 02 RR l

i CTC RR FUNCTION : MAIN STM TO NPCI DP/P WI $1DE CXCESS FLOW CK VLV 2301 027 D 10 1 A/C 1.000 NFC SA SYS AT 02 RR j' CTC RR FUNCTION : MAIN STM TO NOCl DP/P L0 $1DE EXCESS FLOW CK VLV l:

2301 028 89 2 0 1.000 GL A0 C/F0 BTO M3 p FST M3

! PIT Y2 l FUNCTION : HPCI STEAM LINE DRAIN POT DISCNARGE TO SUPPRESSION CHAMBEk

l 2301 028 50 B9 NC B .001 303 SO D STD M3 ,

FST M3 '

FUNCTION : HPCI STEAM LINE DRAlW POT DISCHARGE TO TORUS SOLEN 010 2301 029 B 10 2 0 1.000 GL A0 0/FC BTC M3 FST . M3 Pli Y2 FUNCTION : NPCI STEAM LINE DRAIN PCT DISCNARGE TO TNE MAIN CONDENSER l'

2301 029 80 B-10 NC B .001 303 to D STD M3 FST M3 FUNCTJON : HPCI STEAM LINE DRAIN POT DISCHARGE TO CONDENSER SOLEWOID l

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kevision 3 VALVES A 75 i

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euAD CITIES WUCLEAR POWER STAtl0N, UNITS 1 AND 2

- [D INSERVICE TESTING PLAN VALVES V Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0066 DRAWING TITLE : NIGH PRESSURE COOLANT !NJECTION RELIEF NORMAL REQUEST DWG IST FUNCTION Sl2E 80DY ACTU- P081* TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FRE0 SMUTDOWN P0$lfl0N

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2301 030 B*10 NC B 1.000 GL A0 0/FC BTC M3 FST M3 ,

PIT Y2 FUNCTION : HPCI STEAM LINE DRAIN POT DISCHARGE TO THE MAIN CONDENSER j 2301 030 80 3 10 NC 8 .001 803 80 D' BTD M3 l

FST M3 FUNCTION : HPCI STEAM LINE DRAIN PCT DISCNARGE TO CONDENSER 30LEN010 l

2301 032 50 C7 2 8 1.000 GL So C/FC BTC M3 L

FUNCTION : HPCl DRAIN POT TO GLAND SEAL CJMDENSER i l

.J 2301 034 C8 2 A/C 2.000 CK SA SYS AT 01 RR j CTC SL RV 23A i CTO SL RV 00E j FUNCT!DN : HPCl, ALL DRAIN POTS, DISCNARGE TO SUPPRES$10N CHAMBER )

1 2301 035 M0 ET 2 8 16.000 GA Mc C Bio . M3 DIT Y2 <-

FUNCTION : NPCI SUPPRES$10N CHAMBER SUCTION LINE ISOLAT10N

. h 2301 036 M0 E9 2 B 16.000 GA MO C BTC M3 ST0 M3 Plf Y2 l FUNCTION : HPCl SUPPRES$10N CHAMBER SUCTION LINE ISOLAfl0N l

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2301 039 E8 2 C 16.000 CK SA SYS CTO SE RV 00E CTOP- M3 RV 00E FUNCTION : HPCI SUPPRES$10N CHAMBER SUCT10N BACKFLOW PREVENTION 2301 040 D7 2 C 4.000 CK SA SYS CTO M3 FUNCTION : MPCI MIN 11RM FLOW RECIRCULAfl0N LINE BACKFLOW PREVENTION 2301 045 B8 2 A/C 24.000 CK SA SYS AT 01 RR I CTC RR RV 23A

\

Reviston 3 VALVES 4 76

k

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LilflWG DRAWING : M 0046 DRAWING TITLE : NIGN PRESSURE COOLANT INJECTION RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE SCET ACTU* Pc61 TEST TEST OR COLD TE CHN ICA'.

VALVE NUNDER C00R CLAtt CATEGORY (INCH) STTLE ATOR TION TYPE FRED SMUTDOWN POSITION 2301 045 e8 2 A/C 24.000 CK SA SYs CTO M3 FUNCTION : HPCI TURtlNE EXNAUST SACKFLOW PREVENTION 2301 048 .M0 34 2 B 4.000 GA MO 0 ST0 M3 Plf Y2 FUNCTION : HPCI LUBE CIL AND GLAND SEAL COOLING WATER RETURN ISOLATION 2301 049 M0 E.4 2 B 4.000 GA MD C STC M3 Pli Y2 FUNCTION : NPCI Ltts' Olt AND GLAND BEAL CD.%ING WATER RETURN ll0LATION 2301 050 C5 2 C 4.000 CK SA STs CTO Sc RV 00E CTOP M3 RV 00E FUNCTION : HPCI LUBE CIL COOLER AND GLAND SEAL CQtIDENSR TO 800$fEp PtRep 2301 051 C5 2 C 4.000 CK SA SYS CTC SM RV 00F rTCP M3 RV 00F IUNCTION : HPCI GLAND SEAL.' LUBE DIi CCOLING PUNP BACKFLN PREVENTION 2301 053 *RV C4 2 'C 4.000 RV SA C CT*SP T5 FUNCTI0li : MPC! GLAND SEAL /Lutt CIL OVERPRESSURE NtofECTION 2301 064 A7 2 8 1.000 GL A0 0/FC STC M3 FST M3 Plf Y2 FUNCTION : HPCI TURBINE STOP VALVE A80VE SEAT DRAIN DISCHARGE 2301*064 80 A6 NC B .001 803 So D STE M3 FST M3 FUNCTION : HPCI TUR0lNE STOP VALVE ABOVE SEAT DRAIN DISCHARGE $0LEN010 2301 065 A8 WC B 1.000 GL A0 0/FC BTC M3 FST M3 Plf Y2 FUNCTION : MPCI TURBINE STOP VALVE ABOVE SEAT DAAlW DISCHARGE 2301 065 80 A7 NC B .001 303 so D BTE M3 Revision 3 VALVES 4 77

1

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OuAD CITIES NUCLEAR POWER STAfl0W UNITS 1 AND 2

~

INSERVICE TESTING PLAN . VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : N 0046 DRAWING TITLE : MIGN PRESSURE COOLANT INJECTION -

6 RELIEF

, NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- P081 TEST TEST OR COLD TECHNICAL VALVE NUMBER C00d CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREO SNUTDOWN P0$lTION 2301 065 *SO A*7 NC B .001 803 80 0 FST m3 FUNCTION : HPCI TURtlNE STOP VALVE ABOVE SEAT DRAIN DISCNARGE $0LEWO10 2301 068 A6 2 0 16.000 RPD SA C DT M NT TV 23A FUNCTl0N : HPCI TURBINE EXNAUST LINE RUPTURE DIAPMRAGM 2301 069 A6 2 0 16.000 RPD SA C DT M NT TV 23A FUNCTION : HPCI TURBINE EMNAUST LINE RUPTURE DIAPMRAGM 2301 071 D8 2 A/C 2.000 SCK SA ' C/LO AT 01 RR CTC RR RV 23A g CTO St RV 00E L FUNCTION : NPCl, ALL DRAIN POTS, DISCNARGE TO SUPPdES$10N CHAMBER 2301 074 C8 2 A/C 12.000 SCK SA C/LO AT 01 R4 CTC RR RV 23A CTO M3 ,

FUNCTION : HPCI TURetNE EXNAUST SACKFLOW PREVENilfM 2301 075 B4 2 C 4.000 Ct: SA CYS CTO SU RV 00E ;

CTOP N3 RV M ;

FUNCTION : HPCI LCET TO C' AND

. TEAL / LUBE OIL COOLER BACKFLOW PREVENTt0N 2301 076 E4 2 C 2.000 CK SA SYS CTC SN RV 00F CTCP N3 RV 00F FUNCTION : HPCI GLAND SEAL CONDENSER RETURN PUMP SACKFLOW PREVENTION 2301 108 C1 2- C .750 CK SA SYS CTC SO RV 00F L FUNCTION : HPCI ECCS FILL SYSTEM TO NPCI SACKFLOW PROTECTION l

l 2399 005 D8 2 C 2.000 CK SA SYS CTC SZ RV 00F

=

CTO SZ RV 00E FUNCTION : HPCI TURBlNE EXNAUST Vacuum BREAKER 2399 006 D8 2 C 2.000 CK SA SYS CTC 90 RV 00F CTO SQ RV 00E f

k Revision 3 VALVES 4 78 l

auAD CITIES NUCLEAR POWER ETAflau, UNITS 1 AND 2 l

INSERVICE TECTING PLAN = VALVES Table 4.0=1 UNIT 1 VALVE ?1 STING .

DRAWING : W 0066 DitAWING TITLE : NIGN PRESSURE COOLANT INJECTION REllEF NORMAL REeutlT DWG IST FUNCTION $1ZE 90DY ACTU- PO$la TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R class CATEGORY (INCM) STTLE ATOR T10N TYPE FREG $NUTDOWN PO$lTION FUNCil0N : HPCI TURBINE EMMAUST VACust BREAKER 2901*010 D7 2 C 4.000 CK SA STS CTC SJ RV 00F FUNCTION : HPCI SAFE 5NUTDOWN MAKE*UP 70 HPCI BACKFLOW PROTECT!DN Revleton 3 VALVES 4 79

ouAD CITIES NUCLEAR POWER $TAfl0N, UNITS 1 AND 2 INSERVICE TESTlWG PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LitTING DRAWING : M DM7 DRAWING TITLE : REACTOR WATER CLEAN UP REllEF NonsuL - REQUEST DWG IST FUNCTION SIZE BODT ACTU- P061 TEST TEST OR COLD ' TECHNICAL VALVE IOIBER C00R CLA$$ CATE00RT (INCN) STYLE ATOR T10N TTPE FRE0 SNUTDJWN POSITION

.................. .... ..... ........ ...... ..... ..... ...... ..... .... ........ ......m..

1201 002 M0 06 1 A 6.000 CA No 0 AT 01 tR STC M3 PIT Y2 FUNCTION RWCU

PRIMARY CONTAINMENT ll0LATION VALVE 1201 005 840 BT 1 A 6.000 GA No 0 AT 01 RR BTC M3 PIT Y2 FUNCTION : RWCU . PRIMARY CONTAINMENT ISOL ATION VALVE i

Revision 3 VALVES 4 80

s GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES

,, Table 4.01 UNIT 1 VALVE LISTING DRAWING : M 0050 DRAWING TITLE : REACTOR CORE ISOLATION COOLING RELIEF NORNAL REQUEST

@5 - DWG IST FUNCil0N S!ZE BODY ACTU- POSI- TEST -TEST OR COLD TECHNICAL VALVE NUNSER COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREG SMUTDOWN POSITION 1301 015A A2 1 A .001 XFC SA SYS AT 02 RR CTC = RR FUNCTION 1301 0158 B2 1 A .001 XFC SA SYS AT*02 RR CTC RR FUNCTION :

1301 016 No 32 1 A 3.000 GA Mo o AT 01 RR STC M3 Plf Y2 FUNCT10N : RCIC a TURBINE STEAM FEED ISolAfl0N VALVE 1301 017 M0 53 1 A 3.000 GA No 0 AT 01 RR --

sTC M3 Pli Y2 FUNCTION : RCIC TURt!NE' STEAM FEED ISOLATION VALVE-1301 040 04 NC A/C 2.000 CK SA SYS AT 01 RR CTC RR RV*13A FUNCTION : RCIC TURBINE DISCHARGE ISOLATION VALVE, PClV 1301 041 02 NC A/C 8.000 CK SA SYS- AT 01 RR CTC RR RV 13A FUNCTION : RCIC TUROINE DISCHARGE ISOLATION VALVE, PCIV 1301 055 D3 NC A/C 2.000 SCK SA C/LO AT 01 RR CTC RR RV 13A FUNCTION : RCic TuttlNE DISCHARGE ISOLATION VALVE, PCiv 1301 064 02 NC A/C 8.000 SCK SA C/LO AT 01 RR CTC RR RV 13A FUNCTION RCIC

ftP U E DISCHARGE ISOLATION VALVE, PCIV O

Revision 3 VALVES 4 81

GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

~ INSERVICE TESTING PLAN . VALVES Table 4.0 1.

I UNIT 1 VALVE LISTING ,

DRAWING : M 0058 3 DRAWING TITLE : CLEAN AND CONTAMihATED CONDENSATE RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Post. TEST TEST OR COLD TECHNICAL VALVE NUMBER- COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREO $NUTDOWN POSITION.

4399 045 D5 NC A 3.000 GA M C AT.01 RR FUNCT10N C & C CONDENSATE . PRIMARY CONTAIMMENT ISOLAfl0N VALVE 4399 046 D5 NC A 3.000 CK SA STS AT 01 RR -

CTC RR RV.43A FUNCTION C & C CONDENSATE . PRIMARY CONTAINMENT ISOLATION VALVE O

Revision 3 VALVES 4 82

t GUAD CITIES NUCLEAR POWER STAfl0N, UNITS i AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 1 UNIT 1 VALVE LISTING-DRAWING : M 0641 1 DRAWING TITLE : CONTAINMENT ATMORPMERE MONITOR SYSTEM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Post

TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION 2499 001A So D6 NC B .500 S02 30 C/FC BTD M3- RV 00C FST M3 FIT Y2 FUNCTION : CAM DRYWELL SAMPLE PATM SELECTION VALVE 2499 0018 80 03 NC B .500 S02 50 C/FC BTO M3 RV 00C FST M3 PIT Y2 FUNCTION 1 CAM DRYWELL SAMPLE PATH SELECTION VALVE 2499 002A 50 'D6 NC A .500 $02 So C/FC AT 01 RR BTC hl RV 00C BT0 M3 RV 00C FST M3=

PIT , Y2 FUNCTION : CAM DRYWELL SAMPLE PATH SEti;fl0N VALVE 2499 0028 80 'D3 NC A .500 502 50 C/FC' AT 01 RR STC M3 RV 00C BT0 M3 Rv 00C FST M3 PIT Y2 FUNCTION t CAM

DRYWELL SAMPLE PATH SELECTION VALVE 2499 003A 50 B7- NC B .500 502 50 C/FC Bio M3 RV 00C FST M3 PIT Y2 FUNCTION 1 CAM

SUPPRES$10N CHAMBER SAMPLE PATH SELECTION VALVE 2499 0038 80 32 NC B .500 502 $0 C/FC BT0 M3 RV 00C FST M3 Plf Y2 FUNCTION 3 CAM SUPPRES$10N CHAMBER SAMPLE PATH SELECTION VALVE 2499 004A 50 B6 NC A .500 $02 So C/FC AT 01 RR BTC M3 RV 90C Bio M3 RV 00C Revision 3 VALVES 4 83

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

. INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTlWG -

DRAWING M 0641 1 DRAWING TITLE : CONTAINMENT ATNOSPNERE MONITOR SYSTEM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU* P061 TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREC $NUTDOWN Postfl0N

'2499 004A So B6 NC A .500 802 S0 C/FC FST M3 PIT ' Y2 FUNCT10N CAM SUPPRES$10N CHAMSER SAMPLE PATH SELECTION VALVE-2499 0048 50 B3 NC A .500 802 53 C/FC AT 01 RR STC M3 Rv 00C OTO M3 RV 00C FST M3 PIT Y2 FUNCTION : CAM SUPPRESSION CHAMBER SAMPLE PATH SELECTION VALVE

(, y 2499 022A C7 NC A/C .500 CK SA SYS- AT*01 RR F CTC RR RV 24A CTO SV .RV 00E CTOP M3 RV 00E FUNCil0N CAM

ATMOSPMERE SAMPLE RETURN CNECK VALVE 2499 0228 C2 ' NC A/C .500 CK SA SYS AT*01 RR CTC SW RV 24A CTO SW RV 00E CTOP M3 RV 00E FUNCTION CAM ATMOSPNERE SAMPLE RETURN CHECK VALVE Revision 3 VALVES 4 84

t GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES

' Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0642 1 DRAWING TITLE : ATMOSPHERIC CONTAINMENT ATNOSPNERE DILUTION SYSTEN RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU* Pos!* TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORY- (INCH) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION 2599 002A A0 C4 NC A 1.500 GL A0 C/FC AT 01 RR (

BTC M3 I BT0 M3 (

FST M3 Plf Y2 FUNCTION : ACAD AIR INJECTION INTO THE DRYWELL SELECTON VALVE j 1

2599 002A*SO D3 NC B 1.000 $03 80 0 BTD M3 '

BTE M3 j FST M3 FUNCil0N : ACAD - AIR INJECil0N INTO THE DRTWELL SELECTION VALVE SOLEN.

.O 2599 002B A0 C5 NC A 1.500 GL Ao C/FC AT 01 RR BTC M3 Bio M3 FST M3 PIT Y2 FUNCTION : ACAD

AIR INJECTION INTO THE DRYE LL SELECTON VALVE <

2599 002B 50 06 NC B 1.000 $03 $0 0 BTD M3 l' BTE M3 FST M3 FUNCTION : ACAD Alt INJECTION INTO THE DRYWLL SELECTION VALVE SOLEN.

2599 003A A0 C3 NC A 1.000 CL A0 C/FC AT 01 RR BTC M3 BT0 M3 FST M3 Plf Y2 FUNCTION : ACAD AIR INJECTION INTO THE SUPPR. CNAMBER SELECTION VLV.

2599 003A 50 C2 NC B 1.000 $03 50 D BTD M3 BTE M3 FST M3 FUNCTION : ACAD AIR INJ. INTO ~3E SUPPR. CHAB. SELECTION VALVE SOLEN.

9 2599 003B A0 C6 NC A 1.000 GL A0 C/FC AT 01 RR 1

Revision 3 VALVES 4*85

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES.

Table 4.0 1 UNif 1 VALVE LISTING DRAWING M 0642 1 DRAWING TITLE : ATMOSPHERIC CONTAINMENT ATMOSPHERE DILUTION SYSTEM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS . CATEGORY (INCH)' STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION 2599 0038 A0 C6 NC A 1.000 GL Ao C/FC BTC M3 BTO M3 FST M3 Plf Y2 FUNCTION ACAD

AIR INJECTION INTO THE SUPPR. CHAMBER SELECTION VLV.

2599 0030 30 C.7 NC B 1.000 503 So D BTD M3 BTE M3 FST M3 FUNCTION : ACAD AIR INJ. INTO THE SUPPR. CHAB. SELECTION VALVE SOLEN.

2599 004A A0 F.3 NC A 1.000 GL A0 C/FC AT 01 RR BTC M3 Bio M3 FST M3 Plf Y2 FUNCTION t ACAD PRESSURE BLEED 0FF ISOL ATION VALVE 2599 004A 50' F3 NC B 1.000 803 So D BTD M3 BTE M3 FST Y2 FUNCTION ACAD

BLEED OFF ISOLATION VALVE SOLENCID 2599 0045 A0 E3 NC A 1.000 GL Ao C/FC AT 01 RR BTC M3 Bio M3 FST M3 Pli Y2 FUNCTION : ACAD . PRESSURE BLEED OFF ISOLATION VALVE 2599 0040 50 E3 NC B 1.000 503 to D BTD M3 BTE M3 FST Y2 FUNCTION ACAD

BLEED OFF ISOLATION VALVE SOLEN 010 2599 005A FCV F5 NC A 1.000 DIA A0 C/FC AT 01 RR 9 FST M3 Revision 3 VALVES 4 06

i

.] ;

eUAD ClTIES WUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING M 0642 1 DRAWING TITLE : ATMOSPMrslC CONTAINMENT ATMOSPMERE DILUTION SYSTEM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU* Post. TEST TEST OR COLD TECH 'AL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION 2599 005A FCV F5 NC A 1.000 DIA A0 C/FC PIT Y2 FUNCTION : ACAD . PRESSURE BLEED OFF ISOLATION AND THR0TTLING/FCV VALVE 2599 005A 50- F5 NC 8 1.000 $03 SO O FST M3 FUNCTION : ACAD . BLEED OFF ISOLAfl0N AND FCV VALVE SOLEN 010 2597 005B FCV E5 NC A 1.000 DIA A0 C/FC AT 01 RR FST M3 i PIT Y2 FUNCTION : ACAD

PRESSURE BLEED.0FF ISOLAtl0N AND THROTTLING /FCV VALVE 2599 0058 50 E5 NC B 1.000 $03 50 D FST M3 FUNCTION : ACAD . BLEED OFF ISOLAfl0N AND tCV VALVE $0LENCID 2599 008 F8 NC C 1.000 CK SA SYS CTO M3 FUNCTION : ACAD BLEED OFF BACKFLOW CHECK VALVE 2599 022 A7 NC C 1.500 CK SA SYS CT0 M3 FUNCTION : ACAD . AIR COMPRESSOR BACKFLOW PROTECTION CHECK VALVE 2599 023A C3 NC A/C 1.500 CK SA SYS AT 01 RR CTC RR RV 25A CTO M3 FUNCTION : ACAD .. AIR INJECTION INTO THE DRYWELL CHECK VALVE 2599 0238 C.6 NC A/C 1.500 CK SA SYS AT.01 RR CTC RR RV 25A CTO M3 FUNCTION : ACAD AIR INJECTION INTO THE DRYWELL CHECK VALVE 2599 024A C3 NC A/C 1.000 CK SA SYS AT 01 RR CTC RR Rv 25A CTO M3 FUNCTION : ACAD . AIR INJECTION INTO THE SUPPR. CHAMBER CHECK VALVE 2599 0248 C6 NC A/C 1.000 CK SA SYS AT 01 RR CTC RR Rv 25A Revision 3 VALVES 4-87

I ouAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 0642 1 DRAWING TITLE : ATMo$PHERIC CONTAINMENT ATMOSPNERE DILUTION STSTEM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- : POSl* TEST TEST OR COLD TECHNICAL VALVE NUMSER COOR CLASS CATEGORT.(INCN) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION 2599 0248 C6 NC A/C 1.000 CK SA SYS CTO M3 FUNCTION : ACAD AIR INJECTION INTO THE SUPPR. CHAMBER CHECK VALVE 2599 996 RV A5 NC. -C .001 RV SA C CT SP V5 FUNCTION : ACAD AIR COMPRESSOR SAFETY VALVE 2599 999 A6 NC C 1.250 CK SA SYS CTO M3 FUNCTION : ACAD AIR COMPRESSOR BACKFLOW PROTECTION CHECK VALVE Revision 3 VALVES 4 88

. , , , . . . . - . _ , , _ _ m,

<;\ h OUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 1056 1 DRAWING TITLE : LIQUID SAMPLING RELIEF 7 NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- P061- TEST TEST OR COLD TECluMCAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION 8941 705 XCV C6 2 B .500 DIA A0 C/FC BTC M3 FST M3 Plf Y2 FUNCTION : CORE SPRAY - SAMPLING SELECT VALVE h

8941 705 XSV C7 NC B .001 803 $0 0 BTD M3 FST M3 FUNCTION : CORE SPRAY SAMPLING SELECT VALVE SOLEN 0ID 8941 709 XCV E5 2 8 1.000 DIA A0 C/FC BTC M3 FST M3 PIT Y2 FulsCTION : RNR - SAMPLING SELECT VALVE 8941 709 *XSV E5 NC B .001 303 30 0 BTD M3 FST M3 FUNCTION : RHR - SAMPLING SELECT VALV2 S0LEN010 8941 710 *XCV D5 2 8 1.000 DIA A0 C/FC STC M3 FST M3 PIT Y2 FUNCTION : RHR SAMPLING SELECT VALVE 8941 710 XSV D5 NC B .001 803 30 D BTD M3 FST M3 FUNCTION : RHR SAMPLING SELECT VALVE 80LEN010 0

Revision 3 VALVES 4 89

_ _ .. __ . . _ ~ . . _ .

OUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 lNSERVICE TESTING PLAN . VALVES

/]l G Table 4.0 1 UNIT 1 VALVE LISTING DRAWING M 1057 DRAWING flTLE t CONTAINMENT AIR SAMPLING

-1 RELIEF- !

NORMAL. REQUEST DWG isi FUNCTION SIZE BODY ACTU- P081- TEST . TEST OR COLD TECNNICAL VALVE NUMBER. C00R CLASS CATEGORY (INCN) STTLE ATOR TION TYPE FAEG SNUTDOWN PO$lil0N 8941 101 XCV C6 NC B .500 DIA A0 C/FC BTC M3 FST M3 PIT Y2 l FUNCil0N : 58GT/CAS a SAMPLING [ SOLATION VALVE (FOR ACAD & DRTW. PURGE) la 8941 101 XSV C-6 NC e .001 $03 So D sTD M3 FST M3 I

' FUNCTION : SSGT/CAS.- SAMPLING ISOLATION VALVE SOLEMOID l

I

!h l D/

l l'

1 1

l l

l i

I l

t l'

i l Revision 3 VALVES 4 90

D- ,

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 1 UNIT 1 VALVE LISTING DRAWING : M 1551 DRAWING TITLE : CONTROL ROOM MVAC RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE toDY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATECORY (INCH) STYLE .ATOR T10N TYPE FREQ SHUTDOWN POSITION 5741 306 xCV D 7. NC 3 1.000 DIA A0 C/FC BTC M3 FST M3 PIT Y2 FUNCTION : CONTR. RM. MVAC

AFU FIRE PROTECTION SPARGER ISOLAfl0N VLV.

5741 306 xsV 07 NC- B .001 $03 $0 0- BTD M3 FST M3 FUNCTION : CONTR. RN. HVAC AFU FIRE PROT. SPARGER ISOLATION VLV. SOL.

5741 3198- -1/2 C.2 3 s 3.000 DIA A0 C/FC FST M3 FUNCTION : CONTR RM. HVAC

SERVICE WATER FLOW CONTROL VALVE 5741 3198 X$V 1/2 C2 NC s .001 $03 So D FST M3 FUNCTION : CONTR. RM. WVAC

SERVICE WATER FLOW CONTROL VALVE SOLENCID 5741 345 PSV 1/2 33 3 C 2.000 RV SA C CT SP V5 FUNCTION : CONTR. RM. HVAC RNRSW RELIEF VALVE, OVERPRESSURE PROT.

5799 386 C2 3 C 2.500 CK SA SYS CTC M3 FUNCTION : CONTR.' RM. HVAC RHR$W BACKFLOW PROTECTION CHECK VALVE ,

Revision 3 VALVES 4 91

QUAD CITIES NUCLEAR POWER STAT 10N, UNITS i AND 2 INSERVICE TESTING PLAN

VALVES Tabte 4.0 2 UNIT 2 VALVE LISilWG DRAWING : W 0029 DRAWING TITLE : TURBINE AND DIESEL Qil PIPING RELIEF NORMAL REQUEST

-DWG IST FUNCTION SIZE BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR 110N TYPE FREQ SHUTDOWN POSITION

$g99 157 C6 NC C 1.000 CK SA SYS CTC M3 CTO M3 FUNCTION : DIESEL Oil PRIMING PUMP DISCHARGE BACKFLOW PROTECTION C6 NC C .750 CK SA SYS CTC - RR RV 00F 5199 158 CTO M3 FUNCil0N : DIESEL Olt EXCESS FUEL RETURN BACKFLOW PROTECTION E4 NS C 1.500 RV SA C CT SP T5

$201- RV FUNCTION : DIESEL oil TRANS,FER PUMP DISCHARGE. RELIEF VALVE D4 NS 'B 1.000 S02 S0 -0 810 M3 RV 52A 5201- SO FUNCTION : DIESEL OIL TRANSFER PUMP 10 DAY TANK CONTROL VALVE F4 NS C 1.500 CK SA SYS CTO RR RV 00E 5299 003 FUNCil0N : DIESEL OIL

TRANSFER PUMP DISCHARGE BACKFLOW PROTECTION 5299 005 F4 NS C 1.500 CK SA SYS CTC M3 CTO M3 FUNCTION : DIESEL OIL TRANSFER PtNP DISCHARGE BACKFLOW PROTECTION Revision 3 VALVES 4 92

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0044-DRAWING TITLE : STANDIY GAS TREATMENT RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BCDY ACTU. POSI- TEST TEST OR COLD TECNNICAL VALVE NUMBER C00R CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FRE0 SNUTDOWN POSITION 7503- Mo 02 NC B 18.000 STF M0 O -

STC M3 BTO M3 PIT Y2 FUNCTION : SaGT TRAIN INLET ISOLATION VALVE Revision 3 VALVES 4 93

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0058 3 DRAWING TITLE : CLEAN & CONTAMINATED CONDENSATE PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORT. (INCH) STYLE ATOR TION. TYPE FREQ SNUTDOWN POSITION 4399 045 A*4 NC A 3.000 GA M C AT 01 RR FUNCTION : C & C CONDENSATE PRIMARY CONTAINMENT ISOLAfl0N VALVE rd 4399-046 A4 NC A 3.000 CK SA SYS AT*01 RR CTC RR RV.43A FUNCTION

C & C CONDENSATE PRIMART CONTAINMENT ISOLATION VALVE Revidor) 3 VALVES 4 94

QUAD CITIES NUCLEAR POWER 51ATION, UNITS 1 AND 2 W- INSERVICE TESTlWG PLAN VALVES "s

Table 4.0 2 UNIT 2 VALVE LISTING

+ DRAWING : M 0060 1 DRAWING TITLE : MAIN STEAM RELIEF WORMAL REQUEST DWG IST FUNCil0N SIZE BODY ACTU- Post. TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STTLE ATOR' TION TYPE FREQ SNUTDOWN POSITION 0203 001A A0 F4- 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV 30C FST M3 PIT Y2 l~

I' FUNCTION MAIN STEAM ISOLATION VALVE 0203 001A AP2 F-4 NC B' .001 PLT A0 E STD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISCLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 001A APA F4 NC B .001 $06 So E BTD M3

(

FST M3 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE 0203 001A 50AC - F4 NC 'B .001 503' $0 'E BTD RR RV 300 l

FST RR RV 300 FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL SOLEN 01D-0203 001A SODC F4 NC B .001 $03 50 E STD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL $0LEN0!D 0203*0018 A0 D4 1 A 20.000 GL A0 0/FC AT 01 RR

'BTC M3 Tv 30C ;

FST M3 PIT Y2 FUNCTION : MAIN STEAM ISOLATION VALVE 0203 001B AP2 F4 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 0018 AP4 F4 NC B .001 504 50 E BTD M3 FST M3 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE 0203 001B 30AC F4 NC B .001 503 SO E STD RR RV-300 Revision 3 VALVES 4 95

QUAD CITIES NUCLEAR POWER STATIJN, UNITS 1 AND 2-INSERylCE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING t M 0060 1 DRAWING TITLE : MAIN STEAM RELIEF NORMAL REQUEST DWC IST FUNCTION SIZE BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMBER' -C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SNUTDOWN POSITION 0203 0010 SOAC F4 ' NC B .001 307 to E FST RR RV 300 FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL SOLEN 0ID 0203 0018 500C F4 NC B .001 $03 So E BTD RR RV 300 FST. RR RV 300, FUNCTION MAIN STEAM !$0LAil0N VALVE ACT. 3 WAY DC CONTROL SOLEN 010 0203 001C A0 C4 1 .A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV 30C FST M3 PIT Y2 FUNCTION MAIN STEAM ISOLATION VALYE 0203 001C AP2 F4 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 300 ~

FUNCTION MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY A!R PILOT' VALVE 0203 001C AP4 F.4 NC B .001 SO4 - 80 E BTD M3 FST M3 FUNCTION MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE 0203 001C SOAC F.4 NC B .001 $03. So E BTD RR RV-30D FST RR RV 300 FUNCTION MAIN STEAM If0LATION VALVE ACT. 3 WAY AC CONTROL $0LEh0!D 0203 001C 80DC F4 NC B .001 $03 So E STD RR RV 30D FST RR RV 300 FUNCT!0N MAIN STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL SOLENCID 0203 0010 A0 B4 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV-30C FST M3 PIT Y2 FUNCTION : MAIN STEAM ISOLATION VALVE 0203 0010 AP2 F4 NC B .001 PLT A0 E BTD RR Rv 300 FST RR RV 300 Revision 3 VALVES 4%

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 F INSERVICE TESTING PLAN VALVES

~

Table 4.0 2 UNIT 2 VALVE LISTING ORAWING : M 0060 1 DRAWING TITLE : MAIN STEAM RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODT

~

ACTU- P081- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STTLE ATOR T10N TYPE FREQ SMUTDOWN POSITION

.................. .... ..... ........ ...... ..... ..... ....... ..... ...e ........ .........

FUNCTIDW MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 001D AP4 F4 NC B .001 SO4 $0 E STD M3 FST M3 FUNCTION I MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE 0203 001D $0AC F4 NC 9 .001 $03 So E STD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAT AC CONTROL $0LEN0!D-0203 0010 $00C F 4' NC e .001 $03 So E BTD RR RV 300 FST RR RV 300-FUNCTION MAIN STEAM !$0LAfl0N VALVE ACT. 3 WAT DC CONTROL SOLENotD 0203 003A F7 1 ~8/C- 6.625 SRV SAP C BTC M6 RV 30A TV 308 STO M6 *V 30A TV 308 CT SP- Y5 RV 308 Pli Y2 FUNCTION MAIN STEAM - SAFETY / RELIEF VALVE (TARGET ROCK) 0203 003A SO F7 NC' B .001 503 to D BTD M6 RV 30A STE M6 RV 30A FUNCTION : hAIN STEAM SAFETY / RELIEF VALVE (TARGET ROCK) SOLENOID 0203 0038 D6 1 3 6.000 RV So C BTC M6 RV 30A STO M6 RV 30A Pli Y2 FUNCTION : MAIN STEAM - ELECTROMATIC RELIEF VALVE 0203 003C C8 1 8 6.000 RV So C BTC M6 RV 30A BT0 M6 RV-30A PIT Y2 FUNCTION : MAIN STEAM ELECTROMATIC RELIEF VALVE 0203 0030 B3 1 B 6.000 RV $0 C BTC M6 Rv 30A BTO M6 RV 30A PIT Y2 Revision 3 VnLVES 4 97

4 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0060 1 DRAWING TITLE : MAlu STEAM RELIEF WORMAL REQUEST DWG IST FUNCTION $12E ' BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR TION TYPE- FRE0 SMUTDOWN POSITION FUNCTION : MAIN STEAM ELECTROMATIC RELIEF VALVE-0203 003E D8 1 B 6.000 RV So C STC M6 RV 30A BT0 M6 RV 30A PIT T2 FUNCTION : MAIN STEAM ELECTROMATIC RELIEF VALVE 0203 004A F8 1 C 6.000 SV SA C CT SP Y5 RV 300 PIT Y2 FUNCTION : MAIN STEAM - SAFETY VALVE 0203 004A RPD F8 NS D 8.000 RPD SA C .

DT M NT TV 30A FUNCTION : MAIN STEAM . SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM 0203 004B 'E 5 - 1 C 6.000 SV SA C CT SP V5 - RV 30s PIT Y2 FUNCTION : MAIN STEAM SAFETY VALVE 0203 004B RPD D5 NS D 8.000 RPD SA C DT*M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM 0203 004C C5 1 C 6.000 SV SA C CT SP. Y5 RV 308 PIT Y2 FUNCTION.: MAIN STEAM

SAFETY VALVE 0203 004C RPD C5 NS 0 8.000 RPD SA C DT M NT TV 30A FUNCTION.: MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPMRAGM 0203 0040 88 1 C 6.000 SV SA C CT SP Y5 RV 30s PIT Y2 FUNCTION : MAIN STEAM SAFETY VALVE 0203 004D RPD B8 NS D 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM

. 0203 004E F8 1 C. 6.000 SV SA C CT SP Y5 RV 30s PIT Y2 Revision 3 VALVES 4 98 r.

ni missss----n- i- -

I QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

.['" INSERVICE TESTING PLAN

VALVES i -

1 Table 4.0 2 UNIT 2 VALVE LIsilWG DRAWING : M 0060 1 DRAWING TITLE : MAIN STEAM

RELIEF NORMAL REQUEST F- DWG ' IST FUNCTION $12E BODY ACTU- P051- TEST TEST OR COLD TECHNICAL VALYC NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREO SHUTDOWN POSITION, FUNCTION t MAIN STEAM SAFETY VALVE 0203 004E RPD F8 NS 0 8.000 RPD SA C DT M NT TV 30A FUNCTION : MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM 0203 004F E5 1 C 8.000 SV SA C CT SP Y5 RV 30s PIT Y2 l

FUNCTION : MAIN STEAM SAFETY VALVE i

0203 004F RP0 -D 5 NS D 8.000 RPD SA C DT M NT TV 30A FUNCTION t MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM

^

\Y)M 0203 004G C5 1 C 6.000 SV SA C CT SP V5 RV 308 Plf Y2 FUNCTION MAIN STEAM - SAFETY VALW l

0203 0040 RP0 C5 NS D 8.000 RPD SA C DT M NT Tv 30A FUNCTION t MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM 0203 004H 88 1 C 6.000 SV SA C CT SP Y5 RV 30s '

Pli Y2 FUNCTION 1 MAIN STEAM SAFETY VALVE 0203 004H RPD B+8 NS ' D 8.000 RPD SA C DT*M NT TV 30A FUNCTION t MAIN STEAM SAFETY VALVE DISCHARGE RUPTURE DIAPHRAGM 0220 001 MO E4 1 A 3.000 GA M0 C AT 01 RR BTC M3 PIT Y2 FUNCTION : MAIN STEAM LINE DRAlW ISOLATION VALVE 0220 084A F3 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV 47A FUNCTION MAIN STEAM ISOLATION VALVE ACCUMULATOR CHECK VALVE 0220 0848- F3 NC C 1.000 CK SA SYS AT 06 Y2 a

CTC RR RV 47A j-

%d Revision 3 VALVES 4 99

rm . . .

I--

1J GUAD CITIES NUCLEAR POWER STAT!DN, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING 4 DRAWING M 0060 1 DRAWING TITLE : MAlu STEM RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL YALVE NLMBER COOR CLASS CATEGORY-(INCH) STYLE ATOR T10N TYPE FREO SMUTDOWN POSITION FUNCTION : MAIN STEAM ISOLATION VALVE ACCum>LATOR CNECK VALVE 0220 084C' F3 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV 47A FUNCTION : MAIN STEAM ISOLATION VALVE ACCUMULATOR CNECK VALVE 0220 0840 F3 NC C 1.000 CK SA SYG AT 06 Y2 CTC' RR RV 47A FUNCTION 1 MAIN STEAM ISOLAfl0N VALVE ACCLMULATOR CNECK VALVE Revision 3 VALVES 4 100

7 f

QUAD CITIES NUCLEAR POWER STAil0N, UNITS 1 AND 2

,Q _ ' INSERVICE TESTING PLAN

VALVES , ;

Table 4.0 2' UNIT 2 VALVE LISTING-DRAWING M 0060 2 e DRAWING TITLE : MAIN STEAM RELIEF NORMAL = REQUEST DWG IST FUNCTION- $12E BG)Y ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NtsISER COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ $NUTDOWN POSITION 0203 002A A0 F.7 1 A 20.000 GL A0 0/FC AT*01 RR STC M3 TV 30i; FST M3 h

PIT Y2 FUNCTION MAIN STEAM ISOLATION VALVE i 0203 002A AP2 F7 NC 8 .001 PLT A0 E BTD RR RV 300 l FST RR RV.300 i: FUNCTION s' MAIN STEAM ISCLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE l

l 0203 002A AP4 F7 NC 5 .301 $04 to E STD M3 RV 300 (V FST FUNCTION MAIN STEAM !$0LATION VALVE ACTUATOR 4 WAY AIR ?! LOT VALVE M3 l 0203 002A*SOAC F7 NC B .001 503 So E BTD RR RV 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL S0LENCID 0203 002A SCDC F7 NC B .001.503 So E STD RR RV 300 FST at .RV 300 l FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL S0LENCID 0203 0028 A0 E1 1 A 20.000 GL A0 0/FC AT 01 RR I

STC M3 Tv 30C l FST M3 PIT Y2 FUNCT!DN MAIN STEAM ISOLAfl0N VALVE l' 0203 0028.AP2 F7 NC 5 .001 PLT A0 E STD RR RV 300 l

FST RR RV 300 FUNCTION MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 0025 AP4 F7 NC B .001 SO4 S0 E BTD M3 FST M3 FUNCT!DN MAIN STEAM ISOLATION VALVE ACTUATOR 4-WAY AIR PILOT VALVE t 0203 0028 504C F7 NC 8 .001 S03 So E BTD RR RV.300 v

Revision 3 VALVES 4 101

euAD CITIES NUCLEAR POWER STAtl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0060 2 DRAWING TITLE : MAIN STEAM RELIEF WORMAL REQUEST DWG !$T FUNCTION' SIZE BCDY ACTU- POB1- TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORY' (INCH) STYLE ATOR TION TYPE FRE0 SNUTDOWN POSITION

.e................ .... ..... ........ ...... ..... ..... ...... ..... .... ........ .........

"0203 0028 50AC F7 NC B .001 $03 So E FST RR RV 300 FUNCTION MAIN STEAM !$0LAT10N VALVE ACT. 3 WAY AC CONTROL SOLINCID

' 0203 0028 800C F7 NC B .001 $03 50 E BTD RR RV 30D FST RR RV 300 FUNCTION : MAIN STEAM ISOLAfl0N VALVE ACT. 3 WAY DC CONTROL SOLEN 0!D 0203 002C A0 07 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV 30C FST - M3 FUNCTION t MAIN STEAM ISOLATION VALVE 0203 002C AP2 F7 NC B .001 PLT A0 E BTD RR RV 300 FST. RR RV 300 FUNCTION MAIN STEAM ISOLATION VALVE ACTUATOR 2*WAY AIR PILOT VALVE 0203 002C AP4 F7 NC B .001 504 50 E BTD M3 FST M3 FUNCTION : MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE 0203 002C SCAC F7 NC B .001 $03 $0 E BTD RR - Rv 300 FST RR RV 300 FUNCTION : MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL SOLENCID 0203 002C-$0DC F7 NC B .001 $03 So E STD RR RV 300 FST RR RV 300 FUNCTION MA]W STEAM ISOLATION VALVE ACT. 3 WAY DC CONTROL SOLEN 0!D

'0203 0020 A0 C7 1 A 20.000 GL A0 0/FC AT 01 RR BTC M3 TV 30C FST M3 Plf Y2 FUNCTION : MAIN STEAM ISOLATION VALVE

, 0203 002D d2 F7 NC B .001 PLT A0 E BTD RR RV 300 FST RR RV 300 i

Revision 3 VALVES 4 102

i

,oVAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 ,

/N- INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M*0060 2 DRAWING TITLE t MAIN STEAM RELIEF WORMAL . REQUEST DWG 'IST FUNCTION $12E BODY ACTU- PCBI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FRE4 SNUTDOWN R$1 TION l

FUNCTION 1 MAIN STEAM ISOLATION VALVE ACTUATOR 2 WAY AIR PILOT VALVE 0203 002D AP4 F7 NC B- .001 SO4 50 E BTD M3 FST M3 FUNCTION 1 MAIN STEAM ISOLATION VALVE ACTUATOR 4 WAY AIR PILOT VALVE. 1 1

0203 002D 50AC F7 NC B .001 $03 So E BTD RR RY 300 FST. RR RV 300 FUNCTION t MAIN STEAM ISOLATION VALVE ACT. 3 WAY AC CONTROL 'OLENotD 0203 002D 80DC F7 NC B .001 S03- So 'E BTD RR RV 300 FST RR RV 300 l(N FUNCTION MAIN STEAM ISOLATION VALVE ACT. 3*WAY DC CONTROL SOLENCID 0220 002 M0 E7 1 A 3.000 GA M0 C AT 01 RR I BTC M3 l

PIT Y2 FUNCTION t MAIN STEAM LINE DRAIN ISOLATION VALVE 0220 017A' E8 1 A/C 1.000 XFC SA SYS AT 02 RR 1 CTC RR l FUNCTION 1A MAIN STM INST LINE EXCESS FLOW CK VLV l 0220 017B D8 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR I FUNCTION I 1B MAIN STM INST LINE EXCESS FLOW CK VLY l

0220 017C C8- 1 A/C 1.000 XFC SA SYS AT 02 RR )

CTC RR l FUNCTION 1C MAIN STM INST LINE EXCESS FLOW CK VLV 0220 017D B8 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR ,

l FUNCTION t 1D MAIN STM INST LINE EXCESS FLOW CK VLV 0220 018A E8 1 A/C 1.000 XFC SA SYS AT 02 RR I f

s CTC RR Revision 3 VALVES 4 103

i QUA0 CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 l- ,

INSERVICE TESTING PLAN . VALVES

, ; q~\

Table 4.0 2 i

UN!T 2 VALVE LISTING-L DRAWING t N 0060 2 j,_ DRAWING TITLE MAIN STEAM l

l l

REllEF NORMAL REQUEST L DWG IST FUNCil0N SIZE- 800Y ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUM8ER C001 CLASS CATEGORY (INCN) STYLE AYOR TION TYPE FRE0 SNUT00WN POSITION j

.................. .... ... . ........ ...... ..... ..... ...... ..... .... ........ ......... ]

FUNCTION : 1A MAIN STM INST LINE EXCESS FLOW CK VLV i 1

lL 0220 0188 08 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION t IB MAIN STM INST LINE EXCESS FLOW CK YLV ,

0220 018C C8 1 A/C 1.000 XFC SA SYS AT 02 RR l l CTC RR l

! l l: FUNCTION : 1C MAIN STM INST LINE EXCESS FLOW CK VLV l

0220 0180 B8 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR f FUNCil0N : 10 MAIN STM INST LINE EXCESS FLOW CK VLV 0220 085A F7 NC C 1.000 CK SA - SYS AT 06 Y2 CTC RR RV 47A FUNCTION ? MAIN STEAM ISOLAfl0N VALVE ACCUMULATOR CHECK VALVE l

' 0220 0858 F7 NC C 1.000 CK SA SYS AT 06 Y2 CTC RR RV 47A l FUNCil0N MAIN STEAM ISOLATION VALVE ACCUMULATOR CHECK VALVE 0220 085C F7 NC C 1.000 CK SA SYS AT 06 Y2 '

CTC RR Rv 47A FUNCTION MAIN STEAM ISOLATION VALVE ACCUMULATOR CHECK VALVE 0220 0850 F7 NC C 1.000 CK SA SYS AT 06 Y2

. CTC RR RV 47A FUNCTION : MAIN STEAM ISOLATION VALVE ACCUMULATOR CHECK VALVE

/

?

L Revision 3 VALVES 4 104

s QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 j'^ ' INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0062 ORAWING TITLE : REACTOR FEED PIPING i

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE B007 ACTU- Pos!* TEST YEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION 0220 058A' E2 1 A/C 18.000 CK SA SYS AT 01 RR CTC RR RV 32A ;

FUNCTION : REACTOR FEED CHECK VALVE INSIDE CONTAINMENT 0220 0588 F2 '1 A/C- 18.000 CK SA SYS AT 01 RR I

CTC RR RV 32A l CTO M3 l= FUNCTION : REACTOR FEED CHECK VALVE INSIDE CONTAINMENT 0220 0599' F2 2 C 18.000 CK SA SYS CTC RR RV 32A ' ,

I q FUNCTION : REACTOR FEED = SECOND VALVE QUTSIDE CONTAINMENT 0220 062A E2 1 A/C 18.000 CK SA SYS AT 01 RR CTC RR 9V 32A FUNCTION : REACTOR FEED FIRST CHECK VALVE QUTSIDE CONTAINMENT j

~

0220 0628 F2 1 A/C 18.000 CK SA SYS AT 01 RR CTC RR RV 32A CTO M3 FUNCTION REACTOR FEED FIRST CNECK VALVE QUTSIDE CONTAINMENT

' ^

r t' Revision 3 VALVES

! 4 105

- . - .- ~.

..?

.s.

eUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

[~ ._ INSERVICE TESTING PLAN VALVES l%) i

~

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING.: M*0069 1 DRAWING TITLE : SERVICE WATER RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE. 80DY ACTU- Pos!* TEST TEST OR COLD TECHNICAL VALVE NLMBER COOR CLASS CATEGORY (INCH) STYLE ATOR TION TYPE FREO SMUTDOWN POSITION

.................. .... ..... ........ ...... ..... ..... ...... ..... .... ........ ......... . 1 3999 086 A 10 3 C 8.000 CK SA SYS CTO M3 ;

FUNCTION : LPSW . DG COOLING WATER PLMP DISCHARGE CHECK VALVE l

- 3999 088 S9 3 C 6.000 CK SA SYS CTC SS RV 00F CTO M3 FUNCTION : LPSW - DG COOLING WATER PUNP DISC. CROSS TIE CHECK VALVE

- j 3999 139 0 99 3 C 6.000 CK - CA SYS CTO M3 FUNCTION : LPSW 1/2-3903 TO 2 3903 PUMP SACK FLOW PROTECTION g 3999 560 D7 3 C. .2.500 CK SA SYS CTC M3 j FUNCTION : LPSW SERVICE WATER TO NPCI ROOM COOLER CHECK VALVE-3999 561 07 3 C 4.000 CK SA SYS- CTO M3 FUNCTION LPSW SERVICE WATER TO VITAL COMPONENTS CHECK VALVE l

t i

O i

Revision 3 VALVES l 4 136

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 2 L' NIT 2 VALVE LISTING DRAWING : M 0071 2 DRAWING TITLE : INSTRUMENT AIR PIPING RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION 0737 001A F.7 NC A .375 BAL so C/FC AT.01 RR BTC M3 FST M3-PIT Y2 FUNCTION TRAVER$1NG IN CORE PROSE BALL VALVE, PCIV 0737 001B F7 NC A .375 BAL $0 C/FC AT 01 RR BTC M3 FST M3 PIT - Y2 FUNCTION : TRAVER$1NG IN CORE PROSE BALL VALVE, PCIV rO 0737 001C F.7 NC A .375 BAL SC C/FC 'AT.01 RR STC - M3 FST M3 PIT Y2 FUNCTION TRAVER$1NG IN CORE PROBE BALL VALVE, PCIV 0737 001D F.7 NC A .375 BAL So C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION TRAVER$1NG IN. CORE PROSE BALL VALVE, PCIV 0737 001E F.7 NC A .375 BAL So C/FC AT 01 RR STC M3 FST M3 Pli Y2 FUNCTION : TRAVER$1NG IN CORE PROSE SALL VALVE, PCIV 0737 002A F.7 NC A .375 SMR EXP 0/KL AT 01 RR TV 07A DT E S2 FUNCTION : TRAVERSING IN* CORE PROBE SHEAR VALVE, PCIV 0737 0028 F7 NC A .375 SMR EXP 0/KL AT 01 RR TV 07A DT E S2 O

Revision 3 VALVES 4 107

_ _ ____ _ ._____. .. i _

GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

~ ~-

lNSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0071 2 DRAWING TITLE : INSTRLMENT AIR PIPING RELIEF

. NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (SNCH) STYLE ATOR T10N TYPE FREQ SMUTDOWN POSITION FUNCTION TRAVERSING IN-CORE PROSE SHEAR VALVE, PCIV 0737 002C F7 NC A .375 SMR EXP 0/KL AT 01 RR. TV 07A DT-t 52 FUNCTION : TRAVERSING IN CORE prose SHEAR VALVE, PCIV 0737 002D F7 NC A .375 SMR EXP 0/KL AT 01 RR TV 07A DT E $2 FUNCTION : TRAVER$1NG IN* CORE PROSE SMEAR VALVE, PCIV 0737 002E F7 NC A .375 SHR EXP 0/KL= AT 01 2R TV 07A DT E S2

. FUNCTION : TRAVERS!NG IN CORE PROSE $NEAR VALVE, PCIV 4720 D3 NC A. 1.000 DIA A0 0/FC- AT 01 RR STC M3 FST M3 Plf Y2 FUNCTION : INSTR. AIR . PCIV, AIR SUCTION FOR INSTR. AIR FROM DRYWELL 4721 03 NC A 1.000 DIA A0 0/FC AT 01 RR-BTC M3

-FST M3 PIT Y2 FUNCTION : INSTR. AIR PCIV, AIR SUCTION FOR INSTR. AIR FROM DRYWELL 4799 155 E2 NC J/C 2.000 CK SA SYS .AT.01 RR CTC RR RV 47B FUNCTION INSTR. AIR . PCIV, INSTR. AIR SUPPLY TO DRYWELL 4799 156 E*3 NC A/C 2.000 CK SA SYS AT 01- RR CTC RR RV 478 FUNCTION. INSTR. AIR . PCIV, INSTR. AIR SUPPLY TO DRYWELL 4799 158 F4 NC A/C .500 CK SA SYS AT 01 RR CTC RR RV 47B O

Revision 3 VALVES 4 106 ii i i i i ..ii

I l

l RuAD CITit$ NUCLEAR POWER STATION, UNITS 1 AND 2

~A IN$tRVICE f t$ TING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LitTING j l

DRAWING : M 0071 2 DRAWING TITLE t INSTRUMENT AIR PIPING l

I RELlff WORMAL RtGUE$T .

DWG l$f FUNCTION $!!! $0DT ACTU- Post

ftST ftST OR COLD TECHNICAL VALVE NUM8tR C00R CLAll CAft00RT (INCM) STTLE ATOR TION TYPE FREQ $NUTDOWN PO$1T10N FUNCTION : INSTR. AIR a PCIV, INSTR. AIR SUPPLY TO TORUS 4799 159 F4 NC A/C- .500 CK SA SYS AT 01 RR '

l CTC RR RV 475 (UNCTION i INSTR. AIR

PClV, INSTR. AIR SUPPLY TO TORUS i

4790 281A t2 NC C. .500 CK SA SYS AT 06 Y2 l CTC RR RV 47A FUNCil0N 8 INFVR. Alt

TARGET ROCK ACCLsAILATOR CHECK VALVE i

I g 4799 482 D3 *C B .001 303 so t sto M3

( isi M3 FUNCTION INSTR. Alk

PCIV (Alt SUCTION FROM DRYWELL) $0LEN010 VALVE 4799 483 D3 NC 8 .001 303 to E ITD M3 FST M3 FUNCil0N INSTR. Alt PCIV (AIR SUCTION FROM DRTWELL) SOLEN 0ID VALVE 743 07 NC A/C .375 CK $A STS AT"J1 RR CTC RR RV 07A FUNCil0N : TRAVER$1NG IN CORE PROSE CHECK VALVE, PCIV

. i Revision 3 VALVES 4 109 l

QUAD CITIES WUCLEAR PodER STATION, UNITS 1 AND 2

/~ INSERVICE TESTING PLAN

VALVES

\

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : N 0072 i DRAWING TITLE $ERVICE AIR PIP!NG (AND DIESEL STARTlWG AIR) !

RELIEF NORMAL REQUEST DWG !$f FUNCTION SIZE 80DY ACTU* P081 TEST TEST OR COLD TECHNICAL j VALVE NUMBER COOR CLA$$ CATEGORY (INCN) $TYLE ATOR T10N TYPE FRED $NUTDOWN POSifl0N I 4699 046 E*6 NC A 1.000 GL M C Af*01 RR FUNCil0N : $ERVICE Alt

PRIMARY CONTAINMENT ISOLATION VALVE 4699 047 E*6 NC A/C 1.000 CK SA SYS AT 01 RR l

CTC RR RV 468 l

FUNCTION : SERVICE Alt * *RIMARY CONTAINMENT ISOLATION VALVE J

l 4699 123 D 10 NC C 1.500 CK SA SYS CTO M3 FUNCTION : SERVICE AIR * (DIESEL) RECEIVER TANK BACKFLOW PROTECTION 1

4699 196 0 19 NC C 1.500 CK SA SYS CTO M3 I FUNCTION : SERVICE AIR * (DIESEL) kECEIVER TANK SACKFLOW PROTECTION 4699 226 D9 NC B 1.500 DI A A0 C STC M3 RV 46A BT0 M3 RV 46A I FUNCTION : SERVICE AIR * (DIESEL) AIR START RELAY VALVE 4699 306A 2 99 NC C .750 RV SA C CT SP V5 ,

FUNCil0N : SERVICE AIR * (DIESEL) RECEIVER TANK SAFETY VALVE l 4699 3068 Z 99 NC C .750 RV SA C CT*$P Y5 FUNCTION : SERVICE AIR * (DIESEL) RfCEIVER TANK SAFETY VALVE 4699 306C 2*99 NC C .750 tV SA C CT*SP Y5 FUNCil0N : SERVICE AIR * (DIESEL) RECElvtR TANK SAFETY VALVE 4699 3060 2 99 NC C .750 RV SA C CT SP Y5 FUNCTION : SERVICE Alt * (DIESEL) RECEIVER TANK SAFETY VALVE 4699 307A Z 99 NC C .500 CK SA SY$ AT*06 Y2 CTC M3 FUNCTION : SERVICE AIR * (DIESEL) COMPRESSOR BACKFLOW PROTECT!DN 4699 3078 Z 99 NC C .500 CK SA SYS

.J M Y2 CTC M3 FUNCT104 1ERVICE AIR * (DIESEL) COMPRESSOR BACKFLOW PROTECT 10N r

i Revision 3 VALVES 4 110 1

I ,

l GUAD CITIES NUCLEAR POWER STaf t0N, UNITS 1 AND 2 1 INSERVICE TESTlWG PLAN

VALVES G Table 4.0 2 UNIT 2 VALVE Ll8 TING DRAWING : M 0072 DRAWING TITLE : $ERVICE Alt PIPlWG (AND DIESEL STARTING Alt) l RELIEF WORMAL REQUEST DWG !$T FUNCTION SIZE D@T ACTU- Poll- TEST TEST OR COLD TECHNICAL l VALVE NUMBER C00R CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FREO $NUTDOWN POSITION 4699 309 Z 99 NC C 1.500 CK SA sYs CTC M3 l C10 M3 FUNCTION : SERVICE AIR * (DIESEL) Alt START RELAY VALVE DPHRGM. CK VLV.

4699 310 2 99 NC B .250 803 so D eTD M3 BTE M3 J FUNCTION : SERVICE Alt - (DIESEL) START $0LEWotD ]

l

)

I gs l

l Revisiert 3 VALVES 4 111

GuAD CITIES WUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTlWG PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTlWG DRAWING M 0075 DRAWING TITLE : REACTOR tulLDING COOLING WATER RELIEF NORMAL REQUEST DWG lli FUNCTION $12E 80DY ACTU. P081 TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR fl0N TYPE FRE0 SNUTDOWN P0$1110N 3)12 *sso t.3 NC A B.000 GA Mo 0 AT.01 RR BTC CS CS.37A Plf Y2 FUNCTION RSCCW . PRIMART CONTAINMENT ISOLAfl0N VALVE 3703- .M0 B1 NC A 8.000 GA MD 0 AT.01 RR BTC CS Ct.37A Plf Y2 FUNCil0N : RBCCW . PRIMART CONTAINMENT ISOLAfl0N VALVE 3706 .M0 B.1 NC A 8.0C0 GA 80 0 0 AT.01 RR BTC CS C$.37A PIT Y2 FUNCil0N t RBCCW . PRIMARY CONTAINMENT ISOLAtl0N VALVE 3799 031 B.3 NC A/C 8.000 CK SA STS AT 01 RR CTC RR RV.37A FUNCil0N RBCCW

PRIMARY CONTAINMENT ISOLATION VALVE Revision 3 VALVES 4 112

GUAD CITIES WUCLEAR POWER STATION, UNITS 1 AND 2

/ ' INSERVICE TESTING PLAN

VALVES

\

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0076 1 ,

DRAWING TITLE t PRESSURE SUPPRES$1GN RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- P0$i+ TEST TEST OR COLD TECHNICAL VALyt utMBER COOR CLAS$ CATEGORY (INCN) $TYLE ATOR T10N TYPE FRED $NUTDOWN POSITION 0220 081A E4 NC C 1.000 CK SA SYS CTOME CS RV 30C FUNCil0N : PRES. SUPPR. . $4FETY VALVE DISCHARGE VACUUM BREAKER $

0220 0816 E4 NC C 1.000 CK SA SYS CTOME C$ RV 30C FUNCTION : PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKER $

i 0220 081C E*4 NC C 1.000 CK SA SYS CTOME CS RV 30C I FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS 0220 0810 E6 NC C 1.000 CK SA $YS CTOME C$ RV 30C p FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS

\

0220 081E E6 NC C 1.000 CK SA SYS CTOME CS RV 30C FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS 0220 105A D4 NC C 8.000 CK SA SYS CTOME CS RV 30C FUNCTION PRES. $UPPR.

SAFETY VALVE Di$ CHARGE VACUUM BREAKERS 0220 105B E*4 NC C 8.000 CK SA SYS CTOME CS RV 30C FUNCTION : PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS 0220 105C E5 NC C 8.000 CK SA SYS CTOME C$ RV 30C FUNCTION PRES. SUPPR.

SAFETY VALVE DISCHARGE VACUUM BREAKERS 0220 105D D5 NC C 8.000 CK SA SYS CTOME CS RV 30C l FUNCTION : PRES. SUPPR. SAFETY VALVE DISCHARGE VACUUM BREAKER $

0220 105E E5 NC C 8.000 CK SA SYS CTOME CS RV 30C FUNCTION PRES. SUPPR. SAFETY VALVE DISCNARGE VACUUM BREAKER $

1601 020A A0 09 NE A 20.000 BTF A0 C/F0 AT*01 RR STC M3 i

STO M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR.

PRIMARY / SECONDARY CONTAINMENT VACUUM BREAKERS O

b Revision 3 VALVES 6 113 l

_...s. _ . . . . . . . , . . .. ,,

m OUAD CITIES NUCLEAR POWER STAtl0N, UNITS 1 AND 2 INSERVICE TElflNG PLAN - VALVES Table 4.0 2 UNIT 2 VALVE LISTING ,

DRAWING : N 0076 1 _

DRAWING TITLE PRESSURE SUPPRES$1UN e

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DY ACTU- Poll. TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FRE0 SNLITDOWN POSITION 1601 020A AP A9 NC 8 .001 PLT A0 D BTD M3 FST M3 FUNCTION PRES. SUPPR.

VACUUM BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 020A CK1 A8 NC C .001 CK SA 'TS

, AT 06 T2 .

CTC CS CS*16A FUNCTION : PRES. SUPPR.

VACULM SREAKER/PCIV ACCUMULATOR CHECK 1601 020A CK2 A8 WC C .001 CK SA SYS AT 06 Y2 C1C CS CS*16A i FUNCTION : PREt. SUPPR.

VACLAM BREAKER /PCIV ACCLMJLATOR CNECK 1601 0200 A0 E9 NC A 20.000 BTF A0 C/F0 AT 01 RR ,

I BTC M3 .-

870 M3 FST M3 Plf Y2 FUNCTION t PRES. SUPPR. PRIMARY /SECONDART CONTAINMENT VACLAJM DREAKERS 1601 0200 AP A9 NC B .001 PLT A0 0 BTD M3 ;

FST M3 FUNCTION t PRES. SUPPR.

VACUUM SREAKER/PClv ACCUWLATOR AIR PILOT 1601 0208 CK1 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION t PRES. SUPPR. VACULM BREAKER /PCIV ACCUMULATOR CHECK 1601 0208 CK2 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION t PRES. SUPPR.

VACUUM BREALER/PCIV ACCLMJLATOR CHECK 1601 021 *AO C6 NC A 18.000 STF A0 t/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION t PRES. SUPPR. DRYWELL INERT & PURGE O

Revision 3 VALVES 4 114

1 i

aunD CITIES NUCLEAR POWEP STATION, UNITS 1 AND 2 i

[' IkSERVICE TESTIN0 PLAN

VALVES i k

I Table 4.0 2 l UNIT 2 VALVE LISTING I

DRAWING : N 0076 1 DRAW;NG TITLE : PRESSURE SUPPRES$10N ]

I i

RELIEF NORMAL REQUEST j DWG IST FUNCTION Sitt Bef ACTU- POSI- TEST TEST OR COLD TECHNICAL j VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SMUTDOWN Postfl0h j 1601 021 AP A9 NC 8 .001 PLT A0 0 BTD N3 i FST N3 l FUNCTION PRES. SUPPR. VACULM SREAKER/PCIV ACCUNULATOR AIR PILOT l l

1601 021 *CK1 A8 NC C .001 CK SA SYS AT 06 Y2 l CTC CS CS*16A FUNCTION : PRES. SUPPR. CHECK VALVE 1601*021 *CK2 A8 WC C .001 CK SA SYS AT*06 Y2 CTC CS CS 16A I

% FUNCTION PRES. SUPPR.

CNECK VALVE f

', l 1601 022 A0 C6 NC A 15.000 BTF A0 C/FC AT*01 RR l STC N3 FST N3 Plf Y2 FUNCTION PRES. SUPPR. DRYWELL INERT S PURGE 1601 022 AP A*9 NC 8 .001 PLT A0 D BTD N3 FST N3 FUNCTION PRES. SUPPR. VACLAM BREAKER /PCIV ACCUNULATOR AIR PILOT 1601 022 *CC1 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR

CNECK VALVE -

1601 022 *CK2 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR. CHECK VALVE 1601 023 A0 03 ;;" A 16.000 BTF A0 C/FC AT 01 RR STC M3 FST N3 PIT Y2 FUNCTION : PRES. SUPPR.

DRYW LL VENT

, is 'l 023 AP A9 NC B .001 PLT A0 0 BTD N3 l \

l

( Revision 3 VALVES l' 4 115 l

l l

euAD CITIES NUCLEAR POWER STAfl0N, UNITE 1 AND 2

(] INSERVICE TESTING PLAN

VALVES Tehle 4.0-2 UNIT 2 VALVE LISTING l

DRAWING M 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION $12E 80DY ACTU* Post. TEST TEST (dt COLD TECHNICAL VALVE W WRER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FRE0 SNUTDOWN P0$lfl0N 1601 023 .AP A9 NC 0 .001 PL1 A0 D FET M3 FUNCTION PRES. SUPPR. . VACUUM DREAKER/PCIV ACCUMULATOR AIR PILOT 1601 023 *CK1 A8 NC C .001 CK SA SYS AT.06 Y2 CTC CS CS*16A FUNCil0N : PRES. SUPPR. CHECK VALVE 1601 023 .CK2 A8 NC C .001 CK SA SYS AT.06 Y2 CTC CS C$*16A FUNCil0N PRES. SUPPR. . CNECK VALVE 1601 024 .A0 8*2 NC A 18.000 BTF A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION PRES, SUPPR. . DRYWELL AND SUPPR. CHAMBER YENT TO RK BLDG.

1601 024 .AP A*9 NC 8 .001 PLT A0 D OTD M3 FST M3 FUNCTION PRES. SUPPR. VACUL81 BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 024 .CK1 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION : PRES. SUPPR. . CNECK VALVE 1601 024 CK2 A8 NC C .001 CK SA SYS AT*06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR.

CHECK VALVE 1601 031A D9 NC A/C 20.000 CK SA SYS AT.01 RR CTC M3 CTOME M3 FUNCTION PRES. SUPPR. . PRIMARY / SECONDARY CONTAINMENT VACULM BREAKERS 1601 0318 E.9 NC A/C 20.000 CK SA SYS AT 01 RR CTC M3

' - CTOME M3 4

! \

l Revision 3 VALVES 4 116

k GUAD CITIES NUCLEAR POWER STAtl0N, UNITS 1 AND 2

[' INSERVICE TERTING PLAN . VALVES I kv I Table 4.0 2 UNIT 2 VALVE LitTING' DRAWING : M 0076 1 DRAWING TITLE : PRE $$URE SUPPRES$10N RELIEF NORMAL REQUE$T DWG !$f FUNCT!DN $12E toDT ACTU- Post. TEST TEST OR COLD TECHNICAL '

VALVE NLMBER C00R CLA$$ CATEGORY (INCM) STYLE ATOR TION TYPE FREO $NOTDOWN Pollfl0N FUNCTION : PRES. SUPPR. . PRIMARY / SECONDARY CONTAINMENT VACLAM BREAKER $

1601 032A E2 NC A .001 CK 3A SYS AT.05 RR Tv 16A CTC M3 CTO M3 PIT Y2 FUNCTION : PRES. SUPPR. DRYWELL/$UPPRES$10N CHAMBFR VACUW BREAKER $

1601 032B- E2 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 ,

CTO M3 g PIT Y2 FUNCTION PRES. SUPPR. . DRYWELL/$UPPRE$$10N CHAMBER VACLAM SREAKER$

1601 032C E2 NC A .001 CK SA SYS AT 05 RR Tv 16A CTC M3 CTO M3 Plf Y2 FUNCTION PRES. SUPPR.

DRYWELL/$UPPRE$$l0W CHAMBER VACULM BREAKER $

1601 032D E2 NC A .001 CK SA STS AT 05 RR TV 16A CTC M3 CTO M3 Plf Y2 FUNCTION : PRES. SUPPR.

DRYWLL/$UPPREf310N CHAMBER VACLAM BREAKERS 1601 032E E2 NC A .001 CK SA $YS AT*05 mR TV 16A

(- CTC M3 CTO M3 PIT Y2 l FUNCTION PRES. SUPPR.

DRYWELL/$UPPRESSION CHAMSER VACUUM BREAKER $

1 1601 032F E3 NC A .001 CK SA $YS AT 05 RR TV 16A CTC M3 CTO M3 Pli T2 Revision 3- VALVES 4 117

i Gu4D CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

/ INSERVICE TESTING PLAN . VALVES

\ Table 4.0 2 UNIT 2 VALVE LISTING DRAWING t N 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION Sitt BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE WUMBER C00R CLASS CafEGORY (INCN) STYLE ATOR T10N TYPE FREO SHUTDOWN POSITION FUNCTION : PRES. SUPPR. . DRYWLL/ SUPPRESS 10k CHAMBER VACLAM BREAKERS 1601 033A E.7 NC A .001 CK SA STS AT.05 RR TV 16A CTC M3 CTO M3 Plf Y2 FUNCTION t PRES. SUPPR.

DRYWELL/SUPPRES$10W chi #.4ER VACLAM SREAKERS 1601 0338 E.7 NC A .001 CK SA SYS AT.05 RR Tv 16A CTC M3 CTO M3 )

f Plf Y2 FUNCTION PRES. SUPPR. . DRYWELL/SUPPRES$10N CHAMBER VACULM BREAKERS 1601 033C E.7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 PIT Y2 FUNCTION PRES. SUPPR. . DRYWELL/SUPPRES'10N CHAMBER VACUUM BREAKERS 1601 0330 E.7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 PIT Y2 FUNCTION PRES. SUPPR. . DRYWELL/ SUPPRESSION CHAMBER VACUUM BREAKERS 1601 033E E*7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 Plf Y2 FUNCTION t PRES. SUPPR. . DRYWELL/SUPPRES$10N CHANGER VACUUM BREAKERS 1601 033F E7 NC A .001 CK SA SYS AT 05 RR TV 16A CTC M3 CTO M3 PIT Y2 t Revision 3 VALVES 4 118

GunD CITIES WUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 ?

UNIT 2 VALVE LISTING l DRAWING : M 0076 1 l DRAWING TITLE : PRESSURE SUPPRESSION i 1 i RELIEF NQdtMAL REQUEST i DWG IST FUNCil0N $12% B@Y ACTU- i981- TEST TEST OR COLD TECMNICAL ] VALVE NLMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TTPE FREQ SMUTDOWN P0stil0N ' FUNCTION : PRES. SUPPR. DRYWELL/SUPPRES$10N CHAMBER VActAM BREAKERS 1601 050A 50 09- NC 8 .001 804 30 E STD M3 l BTE M3 l M3 I FST FUNCTION PRES. SUPPR. VACUUN BREAKER /PCIV CONTROL SOLEN 0ID 1601 0508 80 E9 NC 0 .001 504 So E BTD M3 STE M3 FST M3 FUNCil0N : PRES. SUPPR.

VACULM BREAKER /PCIV CONTROL SOLEN 0!D l

1601 051A So C6 NC B .001 804 80 D STD M3 l FST M3 l

 .                                          FUNCTION     PRES. SUPPR.

M!$C. PCIV Alt OPERATOR CONTROL SOLEN 010 1601 0518 $0 C7 NC 8 .001 804 $0 D BTD M3 FST M3 FUNCil0N PRES. SUPPR. MISC. PCiv AIR OPERATOR CONTROL 50LENotD 1601 052A So C2 NC 8 .001 SO4 So D BTD M3 FST M3 FUNCTIDW PRES. SUPPR.
MISC. PCIV AIR OPERATOR CONTROL SOLENCID 1601 0528 30 C3 NC B .001 SO4 So D BTD M3 FST M3 FUNCil0N : PRES. SUPPR.
MISC. PCIV AIR OPERATOR CONTROL 80LE.40!D 1601 055 A6 NC A 4.000 GA A0 0/FC AT 01 RR BTC M3 FST M3 Plf T2 FUNCTION : PRES. SUPPR.
NITROGEN MAKE UP/PLMPSACK SUCil0N I

1601 055 so A6 NC e .001 SO3 to E BTD M3 FST M3 Revision 3 VALVES 4 119

i cuAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 ~

/]

Q,) INSERVICE TESTING PLAN - VALVES Table 4.0 2 UNIT 2 VALVE LISTlWG DRAWING : M 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N l RELIEF WORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL , VALVE NUM4ER COOR CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FRE0 SHUTDOWN POSITION t ( FUNCTION PRES. SUPPR.

NITkOGEN INERTION ISOLATION CONTROL SOLEN 0ID 16010% A0 06 NC A 18.000 BTF A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR.
CONTAINMENT INERTING/PUNPSACK SUCTION 16010% AP A9 NC B .001 PLT A0 0 810 M3 l

, FST M3 FUNCTION PRES. SUPPR.

VACWM BREAKER /PCIV ACCUMULATOR Alt PILOT l

\'

1601 056 CK1 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A i , FUNCTION : PRES. SUPPR.

CHECK VALVE I i l l

1601 056 tK2 A8 NC C .001 CK SA STS AT 06 Y2 l CTC CS CS 16A FUNCTION : PRES. SUPPR. . CHECK VALVE i l 1601 057 D8 NC A 1.000 GL M0 O AT 01 RR I BTC M3 1 PIT Y2 FUNCTION : PRES. SUPPR.

NITROGEN MAKE UP/PLMPSACK DISCHARGE PATH

! i 1601 058 A0 07 NC A 1.000 GL A0 C/FC AT 01 RR I I BTC M3 FST M3 ! I PIT Y2 FUNCTION PRES. SUPPR.

NITROGEN MAKE UP/PLMPSACK ISOL. 4M TORUS I I

1601 059 A0 D7 NC A 1.000 GL A0 0/FC AT 01 RR BTC M3

FST M3 l PIT Y2 l FUNCTION PRES. SUPPR. NITROGEN MAKE.UP/P(MPBACK DISCHARGE PATM ) Revision 3 VALVES 4 120 , I l \___--._._.___.._--_______

           .                                                      ~    . .               -. __-            .-. . . . . _

QUAD CITIES WUCLEAR POWER STATION, UNITS 1 AND 2 i INSERVICE TESTING PLAN

VALVES Table 4.0 2 i UNIT 2 VALVE LISTING-DRAWING : N 0076 1 DRAWING TITLE : PRESSURE SUPPRESSION t

RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE SQDY ACTU- Post. TEST TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SMUTDOWN Postil0N 1601*060 no E*1 NC A 18.000 BTF A0 C/FC AT*01 RR STC M3 FST M3 l- Plf Y2 l FUNCTION : lites. SUPPR. . SUPPRESSION CHAMBER VENT 1601*060 *AP A9 NC B .001 PLT A0 0 STD M3 FST M3 , FUNCTION t PRES. SUPPR.

VACULM BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 060 CK1 A8 NC C .001 CK SA SYS AT 06 Y2

( CTC CS CS*16A FUNCTION PRES. SUPPR.

CNECK VALVE
1601 060 *CK2 A8 NC C .001 CK SA SYS AT 06 T2 l CTC CS CS 16A l FUNCTION PRES. SUPPR.
CNECK VALVE 16016061 *A0 F1 NC A 2.000 GL A0 C/FC AT 01 Rt

! BTC C f FST M3 Pli T2 FUNCTION PRES. SUPPR.

SUPPR. CHAMBER VENT SYPASS AND SSGT SUCTION 1601 062 *A0 03 NC A 2.000 GL A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR.
DRYWELL VENT SYPASS & STAND 8Y GAS TR. SUCTION 1601 063 *A0 A2 NC A 6.000 BTF A0 C/FC AT*01 RR STC M3 FST M3 Plf Y2 FUNCTION : PRES. SUPP.
STANDBY GAS TREAT. CONNECTION TO PRIMARY CONT.

1601-063 *AP A9 NC B .001 PLT A0 0 STD M3 Revision 3 VALVES l L 4*121

QUAD CITIES MUCLEAR POWER STAfl0N, UNIIS 1 AND 2 [D INSERVICE TESTING PLAN VALVES Tebla 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0076 1 DRAWING TITLE : PRESSURE S'JPPRESSION RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU* POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR TION TYPE FRE0 SNUTDWN POSITION 1601 063 AP A9 NC a .001 PLT A0 0 FST M3 FUNCTION PRES. SUPPR.

VACU W BREAKER /PCIV ACCUMULATOR AIR PILOT 1601 063 tK1 A8 NC C .001 CK SA SYS AT 06 Y2 CTC CS CS 16A FUNCTION PRES. SUPPR. CHECK VALVE ,

l 1601 063 CK2 AB NC C .001 CK SA SYS AT 06 Y2 ) CTC CS CS 16A l FUNCTION PRES. SUPPR. CHECK VALVE l l ( 1601 065 80 D7 NC B .001 804 80 BTD M3 E l FST M3 l FUNCTION : PRES. SUPPR. MISC. PCIV AIR OPERATOR CONTROL SOLENDID j 1601 066 80 D7 NC B .001 803 to D BTD M3 l FST M3

FUNCTION : PRES. SUPPR. AIR OPERATED GLOBE VALVE 80LEW0!D 1601 067 *C0 06 NC B .001 803 So E BTD M3 I FST M3

-)

FUNCTION PRES. SUPPR. - AIR OPERATED GLOBE VALVE 80LEN010 1601 068 80 F1 NC B .001 SO4 So D BTD M3 FST M3 FUNCTION : PRES. SUPPR. MISC. PCIV AIR OPERATOR CONTROL SOLENOID 1601 069 50 F1 NC B .001 803 30 0 BTD M3 FST M3 FUNCTION PRES. SUPPR. AIR OPERATED GLOBE VALVE SOLEN 0 IDS 1601 070 80 B3 NC B .001 803 80 D STD M3 FST M3 FUNCTION : F-RES. SUPPR.

AIR OPERATED GLOSE VALVE SOLEN 0 IDS 1601 071 So A3 NC B .001 804 50 D BTD M3 FST M3 Revision 3 VALVES 4 122

                    .        .    ..                                                - _ _ -. -        --  .~. - __

GUAD CITIES NUCLEAR POWER STAfl0W, UNITS 1 AND 2

  -']                                INSERVICE TESTING PLAN . VALVES
\

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING N 0076 1 DRAWING TITLC PRESSURE SUPPRES$10N RELIEF NORMAL RF00EST DWG IST FUNCTION 812E B@Y ACTU- P061- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FRE0 SNUTDOWN POSITION FUNCTION PRES. SUPPR.

MISC. PCIV AIR OPERATOR CONTROL S0t.EN01D 4711* RV D8 NC A/C 1.500 RV SA C AT 01 RR Ci SP Y5 FUNCTION : PRES. SUPPR. NITROGEN MAKE UP OVERPRESSURE PROTECTION 8801 A FCV C3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 l

FUNCil0N : PRES. SU*PR.

DRYWELL AIR SAMPLE l 8801 A 80 C3 NC B .001 303 to E BTD M3 FST M3 FUNCTION : PRES. SUPPR. DI APHRAGM VALVE SOLEN 0 IDS 8801* B FCV - D3 NC A .500 DIA A0 0/FC AT.01 RR BTC M3 FST M3 PIT Y2 FUNCTION : PRES. SUPPR.
DRYW LL AIR SAMPLE l l

8801 B 80 D3 NC B .001 803 30 E BTD M3 ) FST M3 l FUNCTION : PRES. SUPPR.

DIAPHRAGM VALVE SOLEN 0lDS j 1

8801 C FCV D3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION PRES. SUPPR.

DRYWELL AIR SAMPLE 8801- C 30 D3 NC B .001 303 $0 E BTD M3 FST M3 FUNCil0N : PRES. SUPPR. DIAPHRAGM VALVE SOLEN 0lDS f 8801- D FCV E3 NC A .500 DIA A0 0/FC AT 01 RR Revision 3 VALVES 4 123

l OUAD CITIES NUCLEAR POWER STAfl0N, 74ITS 1 AND 2 C

INSERVICE TESTING PLAN . Vat d s

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG IST FUNCTION &l2E D@Y ACTU- P0$1+ TEST TEST OR COLD TECHNICAL VALVE WLRIBER C00R CLAll CATEGORY (INCN) STYLE ATOR TION TYPE FREO SMUTDOWN Postfl0N l 8801- D FCV E3 NC A .500 DIA A0 0/FC BTC M3 FST M3 PIT Y2 FUNCT10N t PRES. SUPPR. = SUPPR W SION CHAMSER Alt SAMPLE 8801- D 80 E3 NC B .001 903 So E BTD M3 FST M3 FUNCTION PRES. SUPPR.

DIAPNRAGM VALVE 80LEW0lDS 8802- A FCV C3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 i

Plf Y2 FUNCTION PRES. SUPPR.

DRYWELL AIR SAMPLE 8802- A 50 C3 NC B .001 $03 S0 E BTD M3 FST M3 FUNCTION PRES. SUPPR. . OlAPWRAGM VALVE SOLENOIDS 8802- B FCV D3 NC A .500 DIA A0 0/FC AT 01 RR BTC M3 FST M3 Plf Y2 FUNCTION PRES. SUPPR.
DRYWELL AIR SAMPLE 8802- B 50 D3 NC B .001 S03 $0 E BTD M3 FST M3 FUNCTION : PRES. SUPPR. DIAPNRAGM VALVE SOLEmotDS i 8802- C FCV D3 NC A .500 DIA A0 0/FC Al 01 RR BTC M3 FST M3 Plf Y2 FUNCT10N PRES. SUPPR. DRYWELL AIR SAMPLE 8802- C B0 D3 NC B .001 303 S0 E BTD M3 FST M3 !

t l l l Revision 3 VALVES 4 124 L

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 I INSERv!CE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N REllEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Post. TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR TION TYPE FREQ SNUTDOWN P0$lfl0N FUNCTION PRES. SUPPR.

DIAPNRAGM VALVE SOLEN 0 IDS 8802 D FCV E3 NC A .500 DIA A0 0/FC AT 01 RR STC M3 FS' M3 Pli Y2 FUNCTION 3 PRES. SUPPR . SUPPRES$10N CHAMBER AIR SAMPLE 8802* D 80 E3 NC 8 .001 $03 So E SYD M3 FST M3 FUNCil0N PRES. SUPPR. . DI APMRAGM VALVE S0LENOIDS 8803 06 NC A .500 GL A0 0/FC AT 01 RR BTC M3 FST M3 Plf Y2 FUNCTION PRES. SUPPR. . DRYWELL Alt SAMPLE G803- *So C6 NC S .001 S03 $0 E BTD M3 FST M3 FUNCTION PRES. SUPPR.
AIR OPERATED GLOSE VALVE SOLEN 0 IDS 8803- 1D D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 1E D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 1F D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 1G D3 NC A .500 GA M C AT 01 RR FUNCTION t PRES. SUPPR. DRYWELL Alt SAMPLE 8803* 1H D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. . DRYWELL Alt SAMPLE Revision 3 VALVES 4 125

GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

    ,Q                                    INSERVICE TESTING PLAN VALVES
    \. )

Table 4.0 2 UNIT 2 VALVE LISTlhG DRAWING : M 0076 1 DRAWING TITLE : PRESSURE SUPPRE1810N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BG)Y ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NUNRER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FMG SNUTDOWN POSITION 8803- 11 03 NC A .500 GA M C AT 01 RR' FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 1J D3 NC A .500 GA h C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803- it D3 NC A .500 GA N C AT 01 RR FUNCitoW PRES. SUPPR. DRYWELL AIR SAMPLE 8803- il D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 1M D3 NC A .500 GA N C AT 01 RR FUNCil0N 3 PRES. SUPPR.

DRYWELL AIR SAMPLE 8803* 1N D3 NC A .500 GA M C AT 01 RR

                            ,    FUNCTION    PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 10             D3 NC          A            .500 GA        M     C        AT 01 RR FUNCil0N    PRES. SUPPR. DRYWELL AIR SAMPLE 8803- iP             D3 NC          A            .500 t%        M     C        AT 01 RR FUNCTION    PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 10             D*3    NC      A            .500 GA        M     C        AT 01 RR FUNCTION    PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 1R             D3 NC          A            .500 GA        M     C        AT-01 RR FUNCil0N : PRES. SUPPR.

DRYWELL AIR SAMPLE 8803- 15 D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR.
DRYWELL AIR SAMPLE 8803- 1T D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 1U D3 NC A .500 GA M C AT 01 RR

( Revision 3 VALVES 4 126 t, L

GUAD CITIES WUCLEAR POWER STAfl0N, UtlTS 1 AND 2 INSERVICE TESTING PLAN

VALVE $

Table 4.0 2 UNIT 2 VALVE LitTING DRAWING t M 0076 1 DRAWING TITLE : PRES $URE $UPPRES$10N RELIEF NORMAL REQUEST DWG IST FudCTION $12E 80DY ACTU- POS!* TEST TEST OR COLD TECHWlCAL VALVE NUMBER C00R CLAS$ CATE00RY (INCN) STYLE ATOR 110N TYPE FRED $NUTDOWN Postil0N FUNCTION t PRES. SUPPR. . DRYWELL Alt SAMPLE 8803- tv D3 bc A .500 GA N C AT 01 RR FUNCTION t PRES. SUPPR. . DRYWELL Alt SAMPLE 8803* 1W 03 NC A .500 GA M C AT 01 RR FUNCTION 3 PRES. SUPPR. . DRYWELL Alt SAMPLE 8803- 1x D3 NC A .500 GA N C AT 01 RR FUNCil0N PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 1Y D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. $UPPR. . DRYWELL AIR SAMPLE 8803- 2D D3 ht A .500 GA M C AT 01 RR FUNCTION t PRES. SUPPR. . DRYWELL Alt $ AMPLE 8803- 2E D3 NC A .500 GA N C AT 01 RR FUNCil0N PRES. SUPPR. . DRYWELL AIR SAMPLE 88ti32 2F D3 NC A .500 GA M C AT.01 RR FUNCTION PRES. SUPPR. . DRYWELL Alt $ AMPLE 8803- 2G D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 2M D3 NC A .500 GA M C AT 01 RR FUNCTION t PRES. SUPPR. DRYWELL AIR SAMPLE 8803* 21 03 NC A .500 GA M C AT*01 RR FUNCTION t PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 2J 03 NC A .500 GA M C AT 01 RR FUNCT104 : PRES. SUPPR. . DRYWELL AIR SAMPLE 8803- 2K D3 NC A .500 GA M C AT 01 RR Revision 3 VALVES , 4 127

l GUAD CITIES MUCLEAR POWER STAfl0N, UhITS 1 AND 2 , O) (J INSERVICE TESTING PLAN

VALVES l Table 4.0 2 ;

UNIT 2 VALVE LISTING l DRAWING M 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N l l RELIEF , WORMAL REQUEST ; ( DWG l$T FUNCTION SIZE 80DY ACTU- P0$l+ TEST TEST OR COLD TECHNICAL l VALVE WW8ER C00R CLAS$ CATEGORY (INCN) $TYLE ATOR T10N TYPE FRE0 $NL'TDOWN Postfl0N 1 FUNCTION t PRES. $UPPR.

DR M LL AIR $ AMPLE j 8803- 2L D3 NC A .500 GA M C AT 01 RR FUNCTION PRIS. SUPPR.
DR M LL Alk $4MPLE i 1

8803- 2M D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR.

DR M LL Alt SAMPLE 8803- 2N 03 NC A .500 GA N C AT 01 RR l FUNCTION : PRES. SUPPR.
DRYWELL AIR $ AMPLE 8803- 20 D3 NC A .500 GA M C AT 01 RR I FUNCTION : PRES. SUPPR. DRYWELL AIR $ AMPLE l l 8803- 2P D*3 WC A .500 GA N C AT 01 RR !

FUNCTION I PRES. SUPPR. DR M LL AIR SAMPLE 8803 20 D3 NC A .500 GA N C AT 01 RR FUNCTION PRES. SUPPR. DR M LL AIR $4MPLE l , 1 8803- 2R D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DR M LL AIR $ AMPLE l L 8803- 28 D3 NC A .500 GA M C AT 01 RR ( FUNCTION PRES. SUPPR. DR M LL Alt SAMPLE l 8803- 2T D3 NC A .500 GA M C AT 01 RR FUNCTION : PRES. SUPPR. DR M LL Alt SAMPLE 8803- 2U D3 NC A .500 GA M C AT 01 RR FUNCTION PRES. SUPPR. DRYWELL AIR SAMPLE 8803- 2V D3 NC A .500 GA M C AT 01 RR FUNCTiou a PRES. SUPPR.

DR M LL AIR SAMPLE 8803- 2W D3 NC A .500 GA M C AT 01 RR J

l Revision 3 VALVES 4 128 i

i i suAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 ( INSERvlCE TESTING PLAN . VALVES i N' fable 4.0 2 UNIT 2 VALVE L1$ TING i DRAWING N 0076 1 DRAWING TITLE : PRESSURE SUPPRES$10N RELIEF NORMAL REQUEST DWG 15T FUNCTION SIZE DODY ACTU- Post. TEST TEST OR COLD TECHNICAL VALVE NLDISER C00R class CATEGORY (INCM) STYLE ATOR TION TYPE FRE0 SMUTDOWN POSlf!ON FUNCTION : PRES. SUPPR. . DRYWELL Alt SAMPLE 8803 2x D3 NC A .500 GA M C AT.01 RR FUNCTION PRES. SUPPR. . DRYWELL AIR $ AMPLE 8803 2Y 03 NC A .500 GA M C AT.01 RR l FUNCTION : PRES. SUPPR. . DRYWELL AIR SAMPLE j l 8804 C6 NC A . 00 GL A0 0/FC AT.01 RR BTC M3 ! FST M3 I

                  ;                                                                                                                                           PIT    Y2                     j
                   \                                                                                                                                                                         '

FUNCTION PRES. SUPPR. . DRTWELL AIR SAMPLE l 8804 30 D6 NC 5 .001 803 to E BTD M3 I FST M3 FUNCTI0tt : PRES. SUPPR. . AIR OPERATED GLOBE VALVE SOLENotDS l l l l , i i i l-4 l h),)

                   '%                                                                                                                                                                       j Revision 3                                                                            VALVES 4 129 1

l-QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNif 2 VALVE LISTING DRAWING : N 0077 1 DRAWING TITLE : WUCLEAR BOILER & REACTOR RECIRCULAil0N REllEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUNBER COOR CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SHUTDOWN P051 T10N 0220 051 E5 1 B .500 DIA Ao C/FC FST CS CS 020 PIT Y2 FUNCTIDN : REACTOR REclRCULATION

FLANGE LEAK DETECTOR DRAIN LINE 0220-051 50 E-5 NC B .999 $03 So D FST CS CS 028 FUNCTION : REACTOR kECIRC FLANGE LEAK DETECIOR DRAIN L!NE SOLENOID 0220 054 E6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCT10N : RX PS*1*261*20 & PI 1 261 21 EXCESS FLOW CK VLV 0263 2 011 E6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC DR FUNCTION : RX LI*1 263 61 HI stDE EXCESS FLOW CK VLV 0263-2*013A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCil0N : RX LT 1 263 57 HI $1DE EXCESS FLOW CK VLV 0263 2 013B D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RK LT 1 263 58 NI SIDE EXCESS FLOW CK VLV 0263 2 015A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1263 57 Lo SIDE EXCESS FLOW CK VLV 0263 2 015B D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1 263 58 L0 SIDE EXCESS FLOW CK VLV 0263 2 017A D6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC ' RR FUNCTION : RX LT 1646A & LT 1263 23A to $10E EXCESS FLOW CK VLV 0263 2 017B D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR Revision 3 VALVES 4 130 I

l

4 _ ._ . _, QUAD CITIES WUCLEAR POWER STAfl0N, UNITS 1 AND 2 INbERVICE TESTING P6AN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0077 1 DRAWING TITLE : NUCLEAR TOILER & REACTOR RECIRCULAfl0N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE toDY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUNSER C00R CLASS CATEGORT (INCN) STYLE ATOR T10N TYPE FRE0 SHUTDOWN Postfl0N 0263 2 0175 D3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RX LT 1 6468 & Lt.1 263 238 L0 $1DE EXCESS FLOW CK VLV

 -0263 2 019A       C6 1           A/C                   1.000 XFC          SA          SYS     AT 02 RR CTC     RR
                       ?UNCY10N : RX LT 1646A & PT 1647A N1 $1DE EXCESS FLW CK VLV 0263 2 0198        C3 1          A/C                   1.000 XFC           SA          SYS    AT 02 RR CTC     RR FUNCTION : RX LT 16468 8 PI 1647B NI SIDE EXCESS FLOW CK VLV 0263 2 020A       B6 1          A/C                    1.000 XFC           SA         SYS    AT-02 RR CTC    RR . _ .

FUNCTION : JET PNP 1 FT 1263-63A HI SIDE EXCESS FLOW CK VLV 0263 2 020s a6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PNP 6 FT 1 263 634 NI SIDE EXCESS FLOW CK VLV 0263 2 020C B3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 11 FT 1263 63C N1 $1DE EXCESS FLOW CK VLY 0263 2 020D 83 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 16 FT 1 263 630 MI SIDE EXCESS FLOW CK VLV 0263 2 023A C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 1 FT 1 263 63A LO SIDE EXCESS FLOW CK VLV 0263 2 0238 C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 6 FT 1 263 638 LO SIDE EXCESS FLOW CK VLV 0263 2 023C t3 1 1.000 XFC AT 02 RR O A/C SA SYS Revision 3 VALVES 4 131

QUAD CITIES NUCLEAR POWER STAtl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES

 '   t Table 4.0 2 UNIT 2 VALVE LISTING DRAWING N 00TT 1 DRAWING TITLE : NUCLEAR BCILER & REACTOR REclktulATION RELIEF NORMAL                    REQUEST DWG     IST    FUNCf'M           SIZE BODY        ACTU-      Post. TEST TEST OR COLD TECNNICAL VALVE NUMBER   C00R CLASS CATEGORY (INCN) STYLE ATOR                        TION TYPE     FREO SNUTDOWN Postfl0N 0263 2 023C       03 1           A/C                1.000 XFC       SA        SYS     CTC ' RR FUNCT!0N : JET PMP 11 FT 1 263 63C LO SIDE EXCESS FLOW CK VLY 0263 2 0230       B3    1        A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION JET PMP 16 FT 1 263 630 LO $10E EXCESS FLOW CK YLV 0263 2 025        B6 1           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION : RX CORE PLATE DPT 1 263 62 LO $1DE EXCESS FLOW CK VLV O'    0263 2 027        A6 1           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION : RX CORE PLATE DPT 1263 62 NI $1DE EXCESS FLOW CK VLV 0263 2 0318       C6 i           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION : JET PMP 2 FT 1263 648 LO $1DE EXCESS FLOW CK VLV 0263 2-031C       C6 1           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION : JET PMP 3 FT 1 263 64C L0 SIDE EXCESS FLOW CK VLV 0263 2*0310       C6 1           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCil0N : JET PMP 4 FT 1263 640 LO $10E EXCESS FLOW CK VLV 0263 2 031E       C6 1           A/C                1.000 XFC       SA        SYS     AT 02 RR CTC    RR FUNCTION : JET PMP 5 FT 1 263 64E LO $1DE EXCESS FLOW CK VLV 0263 2 031G       C6 1           A/C               1.000 XFC        SA        SYS . AT 02 RR CTC    RR FUNCTION : JET PMP 7 FT 1 263 64G L0 SIDE EXCESS FLOW CK VLV 0263 2 031H       C6 1           A/C               1.000 XFC        SA        SYS     AT 02 RR CTC    RR v

Revision 3 VALVES 4 132

l

l I GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 [ INSERVICE TESTING PLAN

VALVES

( v fable 4.0 2 ; UNIT 2 VALVE LISTING DRAWING : N 00TT 1 , DRAWING TITLE : NUCLEAR A0!LER 8 REACTOR RECIRCULAfl0N RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE AGDY ACTU- Pos!* TEST TEST OR COLD TECHNICAL

VALVE NLMRER COOR CLASS CATEGORY (INCW) STYLE ATOR T10N TYPE FRES $NUTDOWN P081T10N FUNCTION : JET PMP 8 FT 1 263 64W LO $1DE EXCESS FLOW CK VLV 0263 2 031J C6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR l FUNCTION : JET PMP 9 FT 1 263 64J LO $1DE EXCESS FLOW CK VLV l

0263 2 031K C6 1 A/C 1.000 XFC SA SYS AT 02 RR l CTC RR i FUNCTION : JET PMP 10 FT 1 263 64K LO SIDE EXCESS FLOW CK YLV ' ~ 0263 2 031M C*3 1 A/C 1.000 XFC SA SYS AT 02 RR t CTC RR FUNCTION : JET PMP 13 FT 1 263 64M Lo $1DE EXCESS FLOW CK VLV 0263 2 031N C3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : JET PMP 13 FT 1 263 64N Lo SIDE EXCESS FLOW CK VLV I l 0263 2 031P C3 1 A/C 1.000 XFC SA SYS AT 02 RR

  ,                                                                                                                                                                                                 CTC-                      RR FUNCTinu JEP PMP 14 FT*1264 64P L0 SIDE EXCESS FLOW CK VLV 0263 2 031?                                                                     C3 1            A/C          1.000 XFC     SA    SYS      AT 02 RR CTC                       RR FUNCTION : JEP PMP 15 FT*1 263 64R L0 SIDE EXCESS FLOW CK VLV 0263 2 031T                                                                     C3 1            A/C          1.000 XFC     SA    SYS      AT 02 RR CTC                       RR FUNCTION : JET PMP 17 FT 1263 64T Lo $1DE EXCESS FLOW CK VLV 0263 2 0310                                                                     C3 1            A/C          1.000 XFC     SA    SYS      AT 02 RR CTC                       RR FUNCTION : JET PMP 18 FT 1263 64U LO $10E SHUT 0FF VLV 0263 2 031V                                                                     C3 1            A/C          1.000 XFC     SA    SYS      AT 02 RR l                                                                                                                                                                                                    CTC                       RR l     f"%
 ~

l Revision 3 VALVES 4 133 l l

euAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

           /~')                                                                                                                INSERVICE TESTING PLAN

VALVES L) Table 4.0 2 UNIT 2 VAL %I LISTING DRAWING : N 0077 1 DRAWING TITLE : NUCLEAR BolLER & REACTOR RECIRCULATION RELIEF NORi4AL REQUEST DWG IST FUNCTION SIZE 80DY ACTU- P081 TEST TEST OR COLD TECHNICAL bALVE NUNSER- C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ SHUTDOWN Po$lTION FUNCTION : JET PMP 19 FT 1263 64V LO $1DE EXCESS FLOW CK VLV l

0263 2 031W C3 1 A/C 1.000 XFC SA ST3 AT 02 RR CTC RR FUNCTION : JET PMP 20 FT 1 263 64W Lo SIDE EXCESS FLOW CK VLV 0263 2 033 B3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECitt LOOP JET PMP FT L0 $1DE EXCESS FLOW CK VLV 0263 2 042A C6 1 A/C 1.000 XFC SA SYS AT 02 RR

           ;                                                                                                                                                                                                                         CTC                    RR
             \                                                                                                        FUNCTION RX LT*1 263 73A HI SIDE EXCESS FLOW CK VLV 0263 2 0428                                                      C3 1          A/C          1.000 XFC                SA                           SYS                             AT 02 RR CTC                    RR FUNCTION : RX LT 1 263 738 HI $1DE EXCESS FLOW CK VLV
          /

Revision 3 VALVES 4 134

1 l i euAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

           /]                                                                                                                                INSERVICE TESTING PLAN

VALVES v Table 4.0 2 ;

i UNIT 2 VALVE LISTING l DRAWING : M 0077 2 DRAWING TITLE : WUCLEAR BolLER & REACTOR REclRCULATION 1 l l RELIEF l WORMAL REQUEST DWG IST FUNCTION S!!E 80DY ACTU- P081- TEST TEST OR d40 TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREO SHUTDOWN POSITION 0202 005A M0 06 i B 28.000 GA Mo 0 STC CS CS 02A l PIT Y2 I l FUNCTION : REACTOR RECIRCULATION RECIRC. PUMP DISCHARGE VALVE l ( 0202 0058 M0 D3 1 8 28.000 GA MO O STC CS CS 02A PIT Y2 l FUNCTION : REACTOR RECIRCULATION RECIRC. PLMP DISCHARGE VALVE l 0220 019A g*6 i A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP DPT 1 261 5A L0 SIDE EXCESS FLOW CK VLV 0220 0190 53 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP DPT 1*261 58 Lo SIDE EXCESS FLOW CK VLV 1-l 0220 020A B6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP DPT 1 261 5A HI SIDE EXCESS FLOW CK VLV l 0220 020e B3 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR l , FUNCTION : RECIRC PMP DPT 1 261 58 HI SIDE EXCESS FLOW CK VLV 1 0220 021A D8 i A/C 1.000 XFC SA SYS AT 02 RE CTC RR ( FUNCTION : RECIRC PMP FT*1 261 6A L0 SIDE EXCESS FL W CK VLV t 0220 0218 01 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP FT 1 261 6C LO $1DE EXCESS FLOW CK VLV ! 0220 022A D8 1 A/C 1.000 XFC SA SYS AT 02 RR (~ CTC RR FUNCTION : RECIRC PMP FT 1*261 6A HI SIDE EXCESS FLOW CK VLV

           /                                              0220 0228                                                      Di 1                   A/C          1.000 XFC   SA    SYS     AT 02 RR
           \

Revision 3 VALVES 4 135

GunD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTlWG DRAWING : M 0?TT 2 DRAWING TITLE : NUCLEAR toller & l'EACTOR RECIRCULAfl0N RELIEF WORMAL REQUEST DWG !$f FUNCTION SI2E 9@T ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STTLE ATOR TION TYPE FRE0 SNUTDOWN PostTION 0220 0228 D1 1 A/C 1.000 NFC SA SYS CTC RR FUNCTION : RECIRC PMP FT 12616C NI $10E EXCESS FLOW CK VLV 0220 044 E5 i A .750 GL A0 0/FC L 01 RR STC M3 FST M3 PIT Y2 FUNCTION : REACTOR RECIRCULAfl0N

REACTOR WATER SAMPLE LINE ISOLAfl0N 0220 044 80 E5 NC B .001 303 80 E STD K3 FST M3 FUNCil0N : REACTOR RECIRCULAT10W CONTROL SOLEW010 0220 045 E7 1 A .75 0 GL A0 0/FC AT 01 RR STC M3 FST M3 Plf Y2 FUNCTION : REACTOR REClRCULATION
REACTOR WATER SAMPLE LINE ISOLATION 0220 045 80 07 NC B .001 $03 to E STD M3 FST M3 FLA.UION : REACTOR RECIRCULAfl0N
CONTROL $0LEN0!D 0220 067A F6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC LOOP DPIS 1 261 34A A EXCESS FLOW CK VLV 0220 0678 F6 i A/C 1.000 XFC SA SYS AT.02 RR CTC RR FUk?Yl0N : RECIRC LOOP DPIS 1 261 34A B EXCESS FLOW CK VLV 0220 067C F6 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION : RECIRC LOOP DPil 1 261 34C A EXCESS FLOW CK YLV 0220 067D F6 i A/C 1.000 XFC SA SYS AT 02 RR CTC RR Revision 3 VALVES 4 136

s

 . P                            GUAD CITIES NUCLEAR POWER STAT 10N, UNITS 1 AND 2 p      .                                   INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING-DRAWING : M 0077 2 DRAWING TITLE : WUCLEAR toller & REACTOR RECIRCULAfl0N RELIEF-l(

NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMSER C00R CLASS CATEGORY (INCN) STYLE ATDR TION ' TYPE FREQ SNUTDOWN POSITION FUNCTION I REclRC LOOP DPIS 126134C B EXCESS FLOW CK VLV 0220 067E E6 1 A/C 1.000- XFC SA SYS- AT 02 RR CTC RR FUNCT10N : RECIRC LOOP DPIS 1 261 348 A EXCESS FLOW CK VLV

          .0220 067F           F6 1           A/C         1.000 XFC     SA     SYS       AT 02 RR CTC     RR FUNCTION REclRC LOOP DPll 1 261 344 8 EXCESS FLOW CK VtV 3

0220 067G E6 1 A/C 1.000' XFC SA ' SYS AT 02 RR CTC RR FUNCTION REC!RC LOOP DPIS 1 261 340 A EXCESS FLOW CK'VLV 0220 067H F6 5 1 A/C 1.000 XFC SA SYS. AT 02 RR CTC RR FUNCT!ON : RECIRC LO R p&lS 1 261 340 B EXCESS FLOW CK VLV 0220 089A E1 1 A/C 1.000 XFC SA SYS AT 02 RR CTC - RR FUNCTION : RECIRC PMP SUCT PS 1 261 23A EXCESS FLOW CK VLV 0220 0898 E1 1 A/C 1.000 XFC SA ' SYS AT 02 RR CTC RR FUNCTION : RECIRC PMP SUCT PS 1 261 238 EXCESS FLOW CK VLV

           -0262 2 005A         B7 1           A/C         1.000 XFC      SA :    SYS'    AT 02 RR CTC     RR FUNCTION : REclRC PMP SEAL CAVITY 2 Pl/PT EXCESS FLOW CK VLV 0262 2 0058       S2 1            A/C         1.000 XFC     SA      SYS      AT 02 RR CTC     RR FUNCTION t RECIRC PMP SEAL CAVITY 2 P!/PT EXCESS FLOW CK VLV
            -0262 2*006A        B7 1            A/C         1.000 XFC     SA      SYS      AT 02 RR CTC     RR Revision 3                                         VALVES 4 137

GUAD CITIES NUCLEAR POWER STAT!DN, UNITS 1 AND 2 1 - INSERVICE TESTING PLAN . VALVES

~~

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M*0077 2 DRAWING TITLE : NUCLEAR BOILER & REACTOR RECIRCULATION RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DT ACTU- Poll. TEST TEST OR CoiD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION FUNCTION : RECIRC PMP SEAL CAVITT 1 P!/PT EXCESS FLOW CK VLV 0262 2 0068 B2 1 A/C 1.000 -XFC SA STS AT.02 RR CTC RR FUNCTION : RECIRC PMP SEAL CAVITY 1 P!/PT EXCESS FLOW CK VLV I-- O Revision 3 VALVES 1 4 138

                                                                       .. r QUAD CITltS NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0078 DRAWING TITLE : CORE SPRAY
                                                                                                                                        . RELIEF NORMAL                REQUEST DWG             IST         FUNCTION SIZE BODY ACTU-                            POSI- TEST -TEST OR COLD TECHNICAL VALVE NUMBER     .C00R CLASS CATEGORY (INCN) STYLE ATOR                                            TION  TD4- FREQ SMUTDOWN POSlfl0N 1001 0188 M0           C-3          2             e             3.000 GA                        No   C       BTC    M3 Bio    M3 PIT    Y2 FUNCTION : RNR MINIMUM FLOW RECIRCULATION RETURN LINE ISOLATION 1402 003A M0           F7 2                        3           18.000 GA                        M0 ' 0       STO    M3 PIT    Y2 FUNCTION,a CORE SPRAY SUPPRESSION POOL SUCTION LINE ISOLATION 1402 0038 M0           F5 2                        8            18.000 GA                       M0    O      BT0    M3 PIT    Y2 FUNCTION : CORE SPRAY

SUPPRES$10N POOL SUCTION LINE ISOLATION 1402 004A M0 'B8 '2 8 8.000 GL MO C BTC M3 Pli Y2 FUNCTION : CORE SPRAY
FULL FLOW TEST RETURet TO THE SUPPRES$10N POOL 1402 0048 M0 C8 2 5 8.000 GL MD C BTC M3 PIT Y2 FUNCTION : CORE SPRAY FULL FLOW TEST RETURN TO THE SUPPRES$10N POOL 1402 008A E9 2 C 12.000 SCK SA C/LO CTO M3 FUNCTION : CORE SPRAY PUMP DISCHARGE BACKFLOW PREVENTION 1402 0088 E6 2 C 12.000 SCE SA C/t1 CTO M3 FUNCTION : CORE SP2AY - PUMP DISCHARGE BACKF'W PREVENTION 1402 009A A0 C3 1 A/C 10.000 CK A0 SYS CTC CS CS 00A CTO CS CS 004 PIT Y2 FUNCTION CORE SPRAY REACTOR VESSEL INJECTION CHECK VALVE 1402 0099 A0 C4 1 A/C 10.000 CK A0 SYS CTC CS CS 00A CTO CS CS 00A PIT T2 FUNCTION : CORE SPRAY REACTOR %ISSEL INJECTION CHECK VALVE Revision 3 VALVES 4 139

GUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERYlCE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING . DRAWING : M 0078 DRAWING TITLE : CORE SPRAY RELIEF WoitMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL-VALVE NLB BER COOR CLAls CATEGORY (INCN) STYLE ATOR T!ON TYPE FREQ SNUTDOWN POSITION 1402 013A E 10 2 C 1.500 SCK SA C/LO CTO M3 FUNCTION : CORE SPRAY MINIMUM FLOW RECIR. LINE BACKFLOW PREVENTION 1402 0138 E6 2 C- 1.500 SCK SA C/LO C10 M3 FUNCTION 3 CORE SPRAY MINIMUM FLOW RECIR. LINE BACKFLOW PREVENTION 1402 024A M0 32 2 A 10.000 GA MO O AT 01 RR' BTC M3 BTD M3 PIT Y2 FUNCTION : CORE SPRAY - INJECTION LINE ISOLATION VALVE 1402 0248 M0 B5 2 A 10.000 GA MO O AT 01 RR - STC M3 Bio' M3 PIT Y2 FUNCTION : CORE SPRAY INJECTION LINE ISOLA 110N VALVE 1402 025A M0 C2 1 A 10.000 GA MO C AT 01 RR . AT 03 RR TV 00H BTC M3 BT0 M3 PIT Y2 FUNCTION : CORE SPRAY - REACTOR VESSEL INJECTION MOTOR OPERATE 0 VALVE 1402 0258 HO C5 1 A- 10.000 GA M0 C AT 01 RR AT 03 RR TV 00H BTC M3 BT0 M3 PIT Y2 FUNCTION CORE SPRAY . REACTOR VESSEL INJECTION MOTOR OPERATED VALVE 1402 028A RV C9 2 C 2.000 RV SA C CT SP Y5 FUNCTION : CORE SPRAY - CLASS 2 OISCHARGE LINE OVERPRES$URE PROTECTION 1402 0288 RV D6 2 C 2.000 RV SA C CT SP V5 Revision 3 VALVES 4 140 l

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

    ,                                    INSERVICE TESTING PLAN VALVES Table 4.0 2                                                             j UNIT 2 VALVE LISTING                                                         l
                                                                                                                          -1 DRAWING M 007B DRAWING TITLE : CORE SPRAY RELIEF               -

NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- P081 TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORT (INCN) STYLE ATOR TION TYPE- FREQ $NUTDOWN PostTION , FUNCTION : CORE SPRAY CLASS 2 DISCHARGE LINE OVERPRESSURE PROTECT 10N 1402 031A D3 1 :A/C .750 XFC SA SYS AT 02 RR CTC R2

                                ~ WCTION CORE SPRAY PMP DPIS 1*1459A L0 SIDE EXCESS FLOW CK VLV 1402 031B.         D4     1      'A/C            .750 XFC        SA    SYS    AT 02 RR.

CTC RR l FUNCTION : CORE SPRAY PMP DPil 1+14598 LO $1DE EXCESS FLOW CK VLV 1402 038A M0 D8 2 8 1.500 GA M0 C BTC M3 BTO M3 PIT Y2 FUNCTION : CORE SPRAY MINIMLM FLOW RECIRCULAfl0N LINE ISOLAfl0N 1402 0388 M0- E 7' 2 B 1.500- GA No C STC M3-BTO M3 - PIT Y2 FUNCTION : CORE SPRAY MINIMUM FLOW RECIRCULATION LINE ISOLATION -

                                                                                                                         'I' 1402 070           E7 2             C           1.500 CK         SA    SYS    CTC    RR     RV 00F FUNCTION : CORE SPRAY CONDENSATE MAKE UP TRANSFER LINE !$0LAfl0N 4

r l 6 Revieion 3 VALVES 4 141

QUAD CITIES MUCLEAR POWER STATION WITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING t M 0(,79 DRAWING TITLE RNRS PIPING (RESIDUAL NEAT REMOVAL SYSTEM) m RELIEF NORMAL' REQUEST DWG IST FUNCTION SIZE BODY ACTU- Post- TEST TEST OR COLD' TECHNICAL VALVE NUMBER C00R CLASS . CATEGORY (INCM) STYLE ATOR TION TYPE FREQ SMUTDOWN POSITION 1001 007A M0 's 6 2 B 14.000 GA Mo 0/KL BTO M3 PIT Y2 FUNCTION RNR = SUPPNESSION POOL SUCTION LINE ISOLATION 1001 0078 M0 E6 2 B 14.000 GA MO 0/KL BT0 M3 PIT Y2 FUNCT!ON RNR
SUPPRESSION POOL SUCTION LINE ISOLATION 1001 007C M0 36 2 3 14.000 GA MD 0/KL BT0 M3

 "                                                                                               Plf    Y2 FUNCil0N RNR SUPPRESSION POOL SUCTION LINE ISOLATION 1001 007D M0        E6 2           B           14.000 GA       MO             0/KL    BTO    M3 Plf    Y2 --

FUNCTION RNA - SUPPRES$10N POOL SUCil0N LINE ISOLAfl0N 1001 043A M0 B4- 2 B 14.000 GA Mo C/KL BTC M3 - PIT Y2' FUNCTION : RNA SMUTDobal COOLING SUCTION ISOLATION 1001 0438 M0 E4 2 B 14.000 GA M0 C/KL BTC M3 PIT Y2 FUNCTION RNR

SNUTDOWN COOLING SUCTION ISOLATION 1001 043C M0 38 2 3 14.000 GA MO C/KL BTC M3 Plf Y2 FUNCTION RNR * $NUTDOWN COOLING SUCTION !$0LAfl0N 1001 0430 M0 D8 2 3 14.000 GA M0 C/KL BTC M3 Plf Y2 FUNCTION RNR
SMUTDOWN COOLING SUCTION !$0LAT10N 1001 067A B3 2 C 12.000 CK SA SYS CTC M3 CTO M3 FUNCTION RNR PUMP DISCMARGE BACKFLOW PREVENil0N 1001 067B E3 2 C 12.000 CK SA SYS CTC M3 I

Revision 3 VALVES 4 142

x QUA0 CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES v Table 4.0 2' ' UNIT 2 VALVE LISTING DRAWING : M 0079 DRAWING TITLE : RNRS PIPING (RESIDUAL NEAT REMOVAL SYSTEM) RELIEF NORMAL REQUEST DWG IST FUNCTION $12E BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FRE0 SHUTDOWN PostTION I- .................. .... ..... ........ ...... ..... ..... ...... .......... ........ ......... 1001 067B E3 2 C 12.000 CK SA SYS CTO M3 FUNCTION t RNR

PUMP DISCHARGE BACKFLOW PREVENTION j 1001 067C 89 2 C 12.000 CK SA SYS CTC M3 l' CTO M3 FUNCTION RNA PtSIP DISCHARGE BACKFLOW PREVENTION 1001 067D E9 2 C 12.000 CK SA' $YS CTC M3 CTO M3 FUNCTION .: RNR - PUMP DISCHARGE SACKFLOW PREVENTION L w l_ . 1001 125A RV 85 2 C 1.000 RV SA C CT SP Y5 FUNCTION I RNR
PUMP SUCTION OVERPRCSSURE PROTECTION i' -1001 1255 RV E5 2 C- 1.000 RV SA C~ CT SP Y5 L

FUNCTION : RNR PUMP SUCTION OVERPRESSURE PROTECTION - 1001 125C RV B7 2 C 1.000 RV SA C CT SP Y5 FUNCTION : RHR PLMP SUCTION OVERPRES$URE PROTECTION 1001 1250 RV E7 2 C 1.000 RV SA C CT SP Y5 FUNCTION t RNR PUMP $UCTION OVERPRESSURE PROTECTION 1001*142A B3 2 C' 2.000 CK SA SYS CTC M3 CTO M3 FUNCTION 3 RNA MINIMUM FLOW RECIRCULATION LINE BACKFLOW PREVENTION 1001 1428 E3 2 C 2.000 CK SA SYS CTC M3 CTO M3 ; FUNCTION RNR - MINIMUM FLOW RECIRCULAfl0N LINE SACKFLOW PREVENTION 1001 142C B9 2 C 2.000 CK SA SYS CTC M3 CTO M3 FUNCTION RNR MINIMUM FLOW RECIRCULATIOcl LINE BACKFLOW PREVENTION 1001 142D E9 2 C 2.000 CK SA SYS CTC M3 fy]/ CTO M3 Revision 3 VALVES 4 143

.re y . i QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M*0079 DRAWING TITLE : RNR$ PIPING (RESIDUAL MEAT REMOVAL STSTEM) RELIEF NORMAL REQUEST DWG IST FUNCTION $12E toDY ACTU- P061- TEST TEST OR COLD. TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION FUNCTION RHR NINIMLM FLOW RECIRCULATION LINE SACKFLOW PREVENTION 1001 165A RV A2 3 C 4.000 RV SA C CT SP Y5 FUNCil0N RNR

MEAT EXCHANGER THERMAL RELIEF VALVES 1001 165R RV A 10 3 C 4.000 RV SA C CT SP Y5 FUNCTION t RNR NEAT EXCNANGER THERMAL REll!F' VALVES.

1001 166A RW A2 2 C 1.000 RV SA C CT SP V5 FUNCTION RNR = HEAT EXCHANGER THERMAL RELIEF VALVES 1001 1668 RV A 10 2 C 1.000 RV SA C CT SP Y5 FUNCTION RHR

NEAT EXCHANGER THERNAL RELIEF VALVES

            . Revision 3                                         VALVES 4 144

                                                           ' OuaD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2
    'O'                                                               INSERVICE TESTING PLAN VALVES i.,          i Table 4.0 2 UNIT 2 VALVE LISTING i

DRAWING M 0061 1 DRAWING TITLE RNRS PIPING (RESIDUAL NEAT REMOVAL SYSTEM) p RELIEF i NORMAL REQUEST

                                                         'DWG      IST FUNCil0N $12E BODY ACTU- Post- TEST TEST. OR COLD TECHNICAL VALVE NUMBER      C00R CLASS CATEGORY' (INCN) STYLE ATOR           T10N TYPE          FREQ SNUTDOWN POSITION 1001*0164 M0           A7 2          8          18.000 GL     M0      O             BTC    M3 STO    M3                          -

PIT' Y2 FUNCTION : RNR NEAT EXCHANGER SYPASS LINE ISOLATION 1001 0168 M0 A2 2- B 18.000. GL Mo O BTC M3 ! 0T0 M3 Plf Y2 FUNCTION : RNR NEAT EXCHANGER OYPASS LINE ISOLATION l 1001 018A ho C6 2 B- .3.000 GA MO C STC M3 l STO M3

    '(                                                                                                                  P!T - Y2 FUNCTION : RNR

MINIMUM FLOW RECIRCULAfl0N RETURN LINE ISOLATION .i

1001 019A M0 E8 2 8 18.000 GA ' MO 0/KL 'BTC- CS - CS 108 BTO CS CS 100 PIT il FUNCT10N : RNA CROSS T!E LINE ISOLATION , 1001 0198 M0 B2 2- 8 18.000 GA MD 0/KL BTC ' CS - CS 100 ST0 CS CS 105 I Pif Y2 FUNCTION RNR- CROSS TIE LINE ISOLATION i 1001 020 MO B7 2 8 3.000 GA MD C BTC M3 BTO M3 Plf -Y2 lI FUNCTION : RNA TRANSFER LINE TO RADWASTE ISCLATION i 1001 021 M0 C7 NC B 3.000 GA MD C BTC M3 ITO M3 PIT Y2 l FUNCTION : RNR TRANSFER LINE TO RADWASTE ISOLAfl0N

,                                    1001 022A RV          E8 2           C           1.000 RV    SA       C            CT SP V5 l

Revision 3 VALVES 4 145 l L __1.__ _ . . _ _ _ _ __:____.___.___._

        . -                                            0U40 CITIES NUCLEAR POW R STAfl0N, UNITS 1 AND 2
     .O                                                                                                           INSERVICE TESTING PLAN VALVES-
     '\                                                                                                                                                                                            ;

Table 4.0 2 ; UNIT 2 VALVE LISTING DRAWING : M 0051 1 DRAWING TITLE t RNRS PIPING (RESIDUAL NEAT REMOVAL SYSTEM) i W lEF '[' NORMAL k6JUEST DWG IST- FUNCTION $!ZE BODY ACTU- POSI TEST TEST OR COLD TECHNICAL VALVE IRSIBER 'C00R CLASS CATEGORY (INCN) STYLE ATOR T10N TYPE FREQ SNUTDOWN POSITION FUNCTION RNR - RNR PLSIP D!$ CHARGE OVERPRESSURE PROTECTION 1001 0228 RV' ~E2 2 C 1.000 RV. SA C CT SP- T5 , FUNCTION 1 RNR - RNR PUMP DISCNARGE OVERPRES$URE PROTECTION 1001 023A M0 E6 2 B 10.000 GA Mo C BTC M3 , PIT Y2 FUNCTION RNR DR M LL SPRAY MOTOR OPERATED ISOLATION VALVE

              .1001 0238 MO-          E3 2                                                                            B         10.000 GA         MO    C       BTC            M3 p                                                                                                                                                         PIT            Y2 i                                                 FUNCTION RNR DRYWELL SPRAY MOTOR OPERATED ISOLATION VALVE 1

1001 026A M0. E5 2 8 10.000' GA MD- C .- BTC M3 PIT Y2 FUNCTION RNR DRYWELL SPRAY MOTOR OPERATED.! SOLATION VALVE l 1001 0265 M0 E4 2 B 10.000~ GA MO C BTL M3 PIT Y2 i FUNCTION RNR DRYWELL SPRAY MOTOR OPERATED ISCLATION VALVE

1001 028A M0 E6 2 5 16.000 GL MO 0 BTC CS CS 10C BTO CS CS 10C (- PIT Y2 .i ! FUNCTION RNR REACTOR VESSEL INJECTION MOTOR OPERATED b4LVE

1 1001 0288 M0 E3 2 B 16.000 GL M0 O BTC CS CS 10C ' BTO' CS CS 10C Plf Y2 I FUNCTION RNR REACTOR VESSEL INJECTION MOTOR OPERATED VALVE i 1801 029A M0 E6 1 A 16.000 GA. M0 C AT 03 RR TV 00N 1 BTC CS CS 10C CS 10C BTO CS P!T Y2

        ,                                              FUNCTION t RNR REACTOR VESSEL INJECTION MOTOR OPERATED VALVE Revision 3                                                                                                             VALVES                                                          ,

4 146 l

GUAD CITIES NUCLEAR POWER STAT 10N, UNITS i AND 2 ~ INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0081 1 DRAWING TITLE : RNRS PIPING (RESIDUAL HEAT REMOVAL STbfEM) RELIEF NORMAL REQUE$T DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) STTLE ATOR TION TYPE FREQ SMUTDOWN POSITION 1001 0298 M0 E3 1 A 16.000 GA NO C AT 03 RR TV 00H BTC CS CS 10C BTO CS CS 10C PIT Y2 FUNCTION : RHR REACTOR VESSEL INJECTION MOTOR OPERATED VALVE ;

i 1001 034A M0 E7 2 B 16.000 GA M0 C BTC M3 j I

BTO M3 PIT Y2 ! FUNCTION : RNR - SUPPRES$10N POOL COOLING AND SPRAY ISOLATION VALVE 1001 0348 M0 .E3 2 B 16.000 GA Mo C BTC M3 BTO M3 Pli Y2 FUNCTION : RNR

SUPPRES$10N POOL COOLING AND SPRAY ISOLATION VALVE 1001 036A M0 E7 2 B 14.000 GL Mo C -BTC M3 BT0 M3 PIT Y2 FUNCTION : RNR
SUPPRESSION POOL COOLING MOTOR OPERATED ISOLATION VLV. ;

1001 0368 M0 03 2 8 14.000 GL MD C BTC M3 sTO M3 Plf Y2 FUNCTION : RNR - SUPPRESSION POOL COOLING MOTOR OPERATED ISOLATION VLV. 1001 037A MO E7 2 8 6.000 GL M0 C BTC M3 PIT .Y2 FUNCTION : RNR

SUPPRESSION POOL SPRAY MOTOR OPERATED ISOLATION VALVE 1001 0378 MO D3 2 5 6.000 GL M0 C BTC M3 PIT Y2

                      .      FUNCTION RMR SUPPRESSION POOL SPRAY MOTOR QPERATED ISOLATION VALVE 1001 047 M0        C4      1       A           20.000 GA       M0               C                   AT 01 RR AT 03 RR                                      TV 00H BTC               CS               CS 10A Revision 3                                           VALVES 4 147 e                                                                                                                                                                    ,

x. OUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTlWG PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0081 1 DRAWING TITLE : RNRS PIPlWG (REllDUAL NEAT REMOVAL SYSTEM) RELIEF NORMAL. REQUEST DWG IST FUNCT!ON SIZE 80DT ACTU- P081 TEST TEST OR COLD TECHNICAL. VALVE NUMBER C00R CLASS CATEGORT (INCM) STYLE ATOR TION TYPE FREQ'SMUTDOWN POSITION 1001 047 .Mo C4 1 A 20.000 GA No C Pli Y2 FUNCTION : RNR . SMUTDOWN COOLING MOTOR OPERATED !$0LAT10N VALVE 1001 050 .Mo D4 1 A 20.000 GA Mo C AT 01 RR AT 03 RR TV 00H BTC CS CS 10A PIT Y2 FUNCTION RNR . SMUTDOWN COOLING MOTOR QPERATED ISOLATION VALVE 1001 059 F3 2 C 1.000 RV SA C CT*SP Y5 FUNCTION : RNR . RNR DISCHARGE PIPING OVERPRESSURE PROTECTION 1001 068A A0 E5 1~ A/C 16.000 CK A0 SYS CTC CS CS 00A CTO- CS CS 00A PIT T2 FUNCTION : RNR . REACTOR VESSEL INJECTION CMECK VALVE 1001 0688 A0 E4 1 A/C 16.000 CK A0 SYS CTC CS CS 00A CTO CS CS 00A-

                                                                                                    . Plf         Y2 FUNCTION : RNR . REACTOR VESSEL INJECTION CHECK VALVE 1001 131            62 2            C            3.000 CK       SA-      SYS                     CTC    SK   RV 00F-FUNCTION : RNR . CONDENSATE MAKE UP TRANSFER LINE ISOLATION 1001 136A          D*8     2       C             3.000 CK      SA       STS                     CTC    SD   RV 00F FUNCTION : RMR

CONDENSATE MAKE*UP TRANSFER LINE ISOLATION 1001 1368 E2 2 C 3.000 CK SA SYS CTC $0 RV 007 FUNCTION : RNR
CONDENSATE MAKE UP TRANSFER LINE ISOLATION O

Revision 3 VALVES 4 148

1 l l '. j QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0081 2 ,

DRAWING TITLE : RNRS PIPING (RESIOUAL. NEAT REMOVAL SYSTEM) f RELIEF .[ NORMAL- REQUE$T DWG IST -FUNCTION SIZE .SODY ACTU. Post- TEST TEST OR COLD TECHNICAL

VALVE NLRtSER C00R CLASS CATEGORY (INCN) STYLE. ATOR TION- TYPE FREQ SMUTDOWN POSITION 1001 002A C7 3 C 12.000 CK SA SYS CTC M3 CTO M3 FUNCTION RNR(SW)'*-' PLMP DISCNARGE CNECK VALVE l

1001 0028 87 3 C 12.000 CK SA ST$- CTC M3 ! CTO M3 FUNCTION RNR(SW) - PUMP OISCHARGE CNECK VALVE 1001 002C .D2 3 C 12.000 CK SA SYS . CTC M3 i CTO M3 n FUNCT!0N : RNR(SW) - PtRIP DISCHARGE CNECK VALVE f A 1001 002D 82 3 C 12.000 CK SA SYS CTC- M3-CTO M3 l FUNCTION : RNR(SW) - PLMP DISCHARGE CNECK VALVE I l t 1 P { ( Revisfon 3 VALVES 4 149

h 4 GUAD CITIES NUCLEAR POWER STATION, UNITS i AND 2 INSERVICE TESTING PLAN VALVES fable 4.0 2 UNIT 2 VALVE LISTING DRAWING t M 0082 DRAWING TITLE : STAND 8T LIQUID CONTROL RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Posta TEST -TEST OR COLD TECHNICAL VALVE NUNBER C00R CLASS CATEGORT (INCH) STYLE ATOR TION TYPE FREQ SNUTDOWN POSITION 1101 015 C3 1 A/C 1.500 CK SA SYS AT 01 RR CTC RR RV 11A CTO RR RV 11A CTOP CS RV 11A FUNCTION : SBLC INJECT 10W LINE CHECK VALVE 1101 016 C4 1. A/C 1.500 CK SA SYS AT 01 RR CTC RR RV 11A CTO RR RV 11A CTOP . CS RV 11A FUNCTION SSLC - PRIMARY CONTAINNENT ISOLATION (CHECK) VALVE 1101 043A D6 2 5 1.500 CK SA SYS CTC M3 CT0 M3 l A FUNCTION.t SSLC PUMP DISCHARGE CHECK VALVE 1101 0438 E6 2 B 1.500 CK SA SYS CTC M3 CTO M3 FUNCTION t SSLC PUMP DISCHARGE CHECK VALVE 1105- A RV C7 2 C 1.500 RV SA C CT SP V5 FUNCTION : SSLC. RELIEF VALVE FOR OVERPRESSURIZAfl0N PROTECTION 110$* B RV E6 2 C 1.500 RV SA C CT*SP Y5 FUNCTION : SSLC

RELIEF VALVE FOR OVERPRESSURIZATION PROTECTION 1106- A C4 2 0 1.500 DIA EXP C/KL DT E SM FUNCTION : SSLC EXPLOSIVE ACTUATED (SQUlB) VALVE 1106- B. D4 2 D- 1.500 DIA EXP C/KL DT E SM FUNCTION : SBLC EXPLOStVE ACTUATED ($0UlB) VALVE Revision 3 valve,$

4 150

euAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0063 1 DRAWING TITLE : CONTROL ROD DRIVE NYDRAULIC RELIEF NORMAL REQUEST DWG IST FUNCTIN SIZE B@Y ACTU- P081- TEST TEST OR COLD TECHNICAL VALVE MWBER C00R CLASS CATEGORY (INCN) STYLE ATOR TION TYPE FREQ SMUTDOWN POSITION 0302 020A 'Et NC 3 .500 S03 So E eTD CS CS 038 FST CS CS 038 FUNCTION : CR0 SCRAM DUNP (SOLEN 0ID) VALVES 0302 0208 E8 NC B .500 S03 50 E BTD CS CS 034 FST CS CS 038 FUNCTION : CRD SCRAM DUNP (SOLEN 010) VALVES

   -0302 021A          E6 2              5                   1.000 DIA      A0     C/FC                BTC     M3 -

FST M3 PIT Y2 FUNCT!0N : CRD SCRAM DISCMARGE VOLUME VENT (SDV). 0302 0218 E6 NC B 1.000 DIA A0 C/FC. BTC M3 FST M3 Pli Y2 FUNCIMN : CRD SCRAM DISCHARGE VOLUNE VENT (SDV) 0302 021C F1 2 8 1.000 DIA A0 C/FC STC M3 FST M3 Pli Y2 FUNCTION : CRD SCRAM DISCMARGE V0MME VENT (SDV) . 0302 0210 F1 NC B. 1.000 DIA A0 C/FC BTC M3 FST M3 PIT Y2 FUNCTION : CRD SCRAM DISCMARGE VOLLME VENT (SDV) 0302 022A F5 2 B 2.000 DIA A0 C/FC BTC M3 FST M3 P!T Y2

                         -FUNCTION : CRD SCRAM DISCHARGE VOLUNE (SDV) DRAIN 0302 0228         F5 NC               e                  2.000 DIA      A0     C/FC                  BTC    M3 FST    M3 PIT    Y2 O

Revision 3 VALVES 4 151

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES

Table 4.0 2 UNIT 2 VALVE LISTING DRAWING: M 0083 1 DRAWING TITLE : CONTROL RQD DRIVE NYDRAULIC RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DT ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUNSER- C00R CLASS CATEGORY (INCN) STTLE ATOR T10N TTPE FREQ SNUTDOWN POSITION FUNCTION : CAD SCRAM DISCHARGE VOLUME (SDV) DRAIN 0302 022C F3 2 5 2.000 DIA A0 C/FC BTC M3 FST M3 PIT \2 FUNCTION : CRD SCRAM DISCHARGE VOLUNE (SDV) DRAIN 0302 022D F2 NC B 2.000 DIA A0 C/FC BTC M3 FST M3 PIT Y2

        ,                        FUNCTION : CRD SCRAM DISCHARGE VOLUME (SDV) DRAIN                                                      4 0302 025A           E7 ' NC        B           1.000 503                          So           D                        STE      CS   CS 038 FUNCTION : CRD ALTERNATE RCD INJECTION SCRAM (SOLEN 0lD) VALVES 0302 0258          E7 NC          B           1.000 503                           S0          D                        STE      CS  .CS 035 FUNCTION : CRD ALTERNATE RCD INJECTION SCRAM (SOLEN 0ID) VALVES 0302 C 4           E8 . NC        B            1.000 502                           50         C/F0                      8T0 '   CS-  CS 038 FST    CS   CS 038 FUNCT10N : CRD ALTERNATE ROD INJECTION SCRAM (30LEN0!D) VALVES 0302 181B         E8 NC          B            1.000 S02                            SO         C/F0                      5T0    CS   CS 038 FST   CS    CS 038 FUNCT10N : CR0 ALTERNATE RQD INJECTION SCRAM-(SOLEN 0ID) VALVES 0302 182A         F8 NC           8           1.000 S02                             80        C/F0                       BTO    CS   CS 038 FST    CS   CS 038 FUNCTION : CRD ALTERNATE RCD INJECTION SCRAM ($0LtnOlM VALVES 0302 1828          F8 NC          8           1.000 $02                             So        C/F0                       BT0    CS   CS 038 FST    CS   CS 038 FUNCTION : CR0 ALTERNATE RCD INJECTION SCRAM (SOLENOID) VALVES 0305 000 ,RPD      E 10 1         D             .250 RPD                             SA        C                         DT M NT              TV 038 FUNCTION : CRO ACCUNULATOR RUPTURE DISK (TYPICAL OF 177)

O ! Revision 3 VALVES 4 152

t GUAD CITIES NUCLEAR' POWER STAfl0N, UNITS 1 AND 2 INSERVICE , TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALyt LISTING DRAWING M 0083 1 DRAWING TITLE : CONTROL RCD DRIVE HYDRAUllC RELIEF. NORMAL REQUE$T DWG IST FUNCTION SIZE' BODY ACTU- POSI : TEST TEST OR COLD TECHNICAL" VALVE NUNBER COOR CLASS CATEGORY (INCH) STYLE ATOR T10N TYPE FREQ SHUTDOWN POSITION. 0305 114 E9 2 C 750 CK SA SYS CTC RR RV 03A TV 03A CTO RR av 03A FUNCTION : CRD HCU BACKFLOW PROTECTON (TYP. OF 177) 0305 115 'E 10 1 C .500 CK SA STS AT 06 Y2 CTC CS CS 03A TV 03A FUNCTION : CRD ACCUNULATOR DISCHARGE BACKFLOW PROTECTON (TYP. OF.177) 030$*117 E9 NC B .375 S03 30 E BTD RR RV 03A TV 03A-FST' RR RV 03A FUNCTION : SCRAN PILOT $0LEN0!D VALVES (TYP. OF 177) 0305 118 E 9. NC B .375 S03 So E ITD - RR RV 03A TV 03A FST RR RV 03A FUNCTION : SCRAM PILOT SOLENotD VALVES (TYP. OF 177) 0305 120 FCV C-10 1 B 1.000 $02 S0 C/FC- BTC M3 TV 03A FST M3 FUNCT!0N : CRD HCU DIRECTIONAL (WITHDRAW) CONTROL VALVE (TTP. OF 177) 0305 121. 50 C9 1 B .750 502 30 C/FC BTC M3 TV 03A FST- M3 FUNCTION : CRD HCU DIRECTIONAL (INSERT) CONTROL VALVE (TYP. OF 177) 0305 122 So C-9 1 B .750 $02 $0 C/FC BTC M3 TV 03A FST M3 FUNCTION : CRD HCU DIRECTIONAL (WITHDRAW) CONT *1L VALVE (TYP. OF 177) 0305 123 FCV C 10 - 1 B 1.000 802 So C/FC BTC M3 TV 03A FST M3 FUNCTION : CRD HCU DIRECTIONAL (INSERT) CONTROL VALVE (TYP. OF 177) 0305 126 CV D 10 1 B 1.000 DIA A0 C/F0 BTO RR RV 03A TV 03A FST RR PIT Y2 FUNCTION : CR0 ACCUM. DISCHARGE TO SPEED SCRAM INSERTION (TYP. OF 177) Revision 3 VALVES 4 153

t.- GUAD CITIES NUCLEAR POWER STAT 10N, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2

UNIT 2 VALVE LISTING. .

DRAWING : N 0083 1 DRAWING TITLE : CONTROL RCD DRIVE HYDRAULIC RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Pos!* TEST TEsf OR COLD TECHNICAL VALVE NUNGER COOR CLASS CATEGORY (INCH) STYLE A f 0R TION TYPE FREQ SHUTDOWN POSITION 0305 127 CV D9 1 5 .750 DIA A0 C/F0 BT0 RR RV 03A TV 03A FST RR Pli Y2 FUNCil0N : DISCHARGE CR0 HCU TO THE SCRAN DISCHARGE VOL.(TYP. OF 177) 0305 138 C 10 1 C .500 CK SA SYS CTC M3 TV 03A FUNCTION CRD DRIVE WATER BACKFLOW PROTECT 0N (TYP. OF 177) Revision 3 VALVES 4 154 t !:

4 OUAD CITIES NUCLEAR POWER STAfl0N, UNITS i AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0084 1 DRAWING fiTLE : 0FFGAS PIPNG RELIEF NWtMAL REQUEST-DWG !$T FUNCTION $1ZE BODY ACTU. P081 . TEST TEST OR COLD TECNNICAL VALVE NUMBER C00R-CLASS CATEGOP.Y (INCN) STYLE ATOR T10W TTPE. FREQ $NUTDOWN P0$lf!ON 5401 A A0 E8 NC B 18.000 STF A0 O/FC BTC M3 FST M3 P!T Y2 FUNCTION OFF GAS . CONDENSER ISOLATION VALVE 5401 A.CK 2 99 NC C .001 CK SA SYS AT.06 Y2 CTC RR FUNCT10N 0FF GAS . CONDENSER !$0LAT!0N VALVE ACClat. CNECK VALVE 5401 A 50 ' E7 NC B .001 504 $0 E BTD M3 FST M3 FUNCTION : OFF GAS . CONDENSER ISOLATION VALVE SOLENCID 5401 8 A0 EB NC B 18.000 STF ,A0 0/FC BTC M3 FST M3 P!T- Y2 FUNCTION t off GAS . CONDENSER ISOLATION VALVE-5401 B CK Z 99 NC C. .001 CK SA SYS AT 06 Y2 CTC RR FUNCTION : OFF GAS . CONDENSER !$0LAT10N VALVE ACCUM. CNECK VALVE 5401 B 30 E.7 NC 8 .001 504 So E BTD - M3 FST M3 FUNCTION,t OFF GAS . CONDENSER ISOLATION VALVE $0LEN010 5402 A A0 D3 NC 8 18.000 GA A0 0/FC BTC M3 FST M3 Pli Y2 FUNCTION : OFF GAS . CONDENSER ISOLATION VALVE 5402- A CK Z 99 NC C .001 CK SA SYS AT 06 Y2 CTC RR FUNCTION : OFF GAS . CONDENSER ISOLATION VALVE ACCUM. CNECK VALVE 5402- A.50 02 NC' B .001 $04 So E BTD M3 FST M3 Revision 3 VALVES 4 155

1 1 4 l l i GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

      .',li .                                           INSERVICE TESTING PLAN VALVES 1

\ - Table 4.0 2 UNIT 2 VALVE LISTING

                                                              ' DRAWING : M 0084 1 DRAWING TITLE : OFFGAS PIPNG RELIEF NORMAL                        REQUEST DWG    IST     FUNCTION $12E 8@T          ACTU-   POSI* TEST    TEST .0R COLD TECHNICAL VALVE NUMBER                C00R CLASS CATEGORY -(INCN) STYLE ATOR           TION TYPE FREQ $NUTDOWN POSITION FUNCTION : OFF GAS CONDENSER ISOLATION VALVE SOLENCID 5402-    B A0                 D3 NC          B           18.000 GA      A0    0/FC     BTC    M3 FST    M3 PIT    Y2 -

FUNCTION : OFF GAS

CONDENSER ISOLATION VALVE 5402- . B CK 2*99 NC C .001 CK SA SYS AT*06 Y2 CTC RR FUNCTION : 0FF GAS - CONDENSER ISOLATION VALVE ACCUM. CHECK VALVE 5402- B 30 - D2 NC B .001 $04 So E BTD ' M3 FST IG FUNCTION : OFF GAS
CONDENSER ISOLATION VALVE $0LEN010 --

t

d I-I' Revision 3. VALVES 4-156 l-

i QUAD CITIES NUCLEAR POWER STATION, UNITS 1 Age 2 - INSERVICE TESTING PLAN bALVES 1 feele 4.0 2 UNIT 2 VALVE LISTING DRAWING M 0085 DRA6.4G TITLE REACTOR SUILDING EQUIPMENT DRAINS RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE 80DY ACTU- POSI. TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCM) STYLE ATOR- fl0N TYPE FREQ~ SMUTDOWN POSITION 2001 003 A0 F7 2- _A 3.000 GA A0 C/FC AT 01 RR BTC M3 FST M3

                                                                                                                 ' PIT        Y2 FUNCTION RX BLOG EQUIP DANS.          PRIMARY CONTAINMENT ISOLATION VALVE 2001 003 50         F 7. NC     B              .001 503           to   D                      STD      M3 FST      M3 FUNCTION RX BLOG EQu!P DANS. *-PRIMART CONT. ISOLATION VALVE SOLENCID 2001 004 A0 -       F7 3          A           3.000 GA             A0    C/FC                  AT 01 RR BTC     M3 FST     M3 PIT     Y2 FUNCTION RX SLDG EQUIP DANS.          PRIMARY CONTAINMENT ISOLAfl0N VALVE 2001 004 So        F7- NC        B              .001 SG3          30    D                       STD     M3 -

FST M3 FUNCTION RX BLDG EQUIP DANS. PRIMARY CONT. ISOLATION VALVE SOLENCID 2001 015 A0 04 2 A 3.000 GA A0 C/FC AT 01 RR BTC M3 FST M3 PIT Y2 FUNCTION 1 RX SLDC EQUIP DANS.

PRIMARY CONTAINMENT ISOLAfl0N VALVE 2001 015 So E4 NC B .001 503 50 0 STD M3 FST M3 FUNCTION : RX BLDG EQUIP DRMS. PRIMARY CONT. ISOLATION VALVE SOLEN 010 2001 016 A0 D3 2 A 3.000 GA A0 C/FC AT 01 RR STC M3 FST M3 Plf Y2 FUNCTION RX BLDG EQUIP DRNS.
PRIMARY CONTAINMENT ISOLATION VnLVE 2001 016 50 E3 NC B .001 $03 $0 0 STD M3 Revision 3 VALVES 4 157

QUAD CITIES NUCLEAR POWER STATION, UhlfS 1 AND 2

                                 -INSERVICE TES11NG PLAN

VALVES i'

Table t. 0 2 UNil 2 VALVE LISTING DRAWINO : M 0085-DRAWING TITLE REACTOR BUILDING EQUIPMENT DRAINS RELIEF NORtLAL - REQUEST-DWG IST FUNCil0N- SIZE BODY ACTU- POSl* TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR TION . TYPE FREQ SHUTD WN POSlfl0N

                                                                                                                * = **=
       .................. .... ..... ........ ...... ..... ..... ... .- ....* . . = ... .*

2001 016 S0 E3 NC B .001 503 So D FST M3 FUNCTION : RX BLDG EQUIP DRNS. . PRIMARY CONT. ISOLAfl0N VALVE SOLEN 01D O i 1 Revision 3 VALVES 4 158

QUAD CITIES' NUCLEAR POWER STATION, UNITS 1 Ald) 2 INSERVICE TESTING PLAN * ' VALVES -- Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0067

                                       ~ DRAWING TITLE : HPCI (HIGH PRESSURE COOLANT INJECTION)

RELIEF NORMAL REQUEST DWG- IST ' UNCTION $12E BODY ACTU. Post. TEST TEST OR COLD TECHNICAL VALVE NUMBER COOR CLASS CATEGORY (INCH) STYLE ATOR TION TYPE- FRE0 SHUTDOWN POSITION 2301 SV A-7 2 B 24.000 PLG NO C BTC M3 ITO M3 PIT Y2 FUNCTION : HPCI TURBINE STOP VALVE 2301 003 Mo -A7 2 B 10.000 GA Mo C Bio M3 PIT Y2 FUNCTION : HPCI STEAM SUPPLY / BLOCKING VALVE, PRE

HEATS THE SUPPLY LINE 2301 004 Mo. C9 1 A 10.000 GA MO O AT*01 RR BTC CS CS 23A BTO CS CS 23A PIT Y2 FUNCTION : HPCI STEAM SUPPLY FROM THE REACTOR VESSEL To THE TURBINE 2301 005 M0 B 10 1 A 10.000 GA M0 O AT.01 RR-BTC CS CS 23A BTO CS CS 23A PIT Y2 FUNCTION : HPCI STEAM SUPPLY FROM THE REACTOR VESSEL TO THE TURBINE 2301 007 .A0 E-6 ' 2 C 14.000 CK A0 SYS CTO CS CS 00A PIT Y2 FuhCTION : HPCI INJECT 10N LINE TO FEEDWATER BACKFLOW PREVENTION 2301 006 .M0 E6 2 B 14.000 GA M0 C BT0 M3 PIT Y2 FUNCTION : HPCI INJECTION LINE TO FEEDWATER ISOLAfl0N 2301 009 M0 E5 2 B- 14.000 GA M0 0 BTO M3 PIT Y2 FUNCTION : HPCI INJECTION LINE TO FEEDWATER ISOLATION 2301 010 M0 E5 2 8 6.000 GL Mo C BTC M3 PIT T2 FUNCTION : HPCI FULL FLOW TEST RETURN TO CONDENSATE STORAGE TANK Revision 3 VALVES 4 159

GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES

 '{b['                                               Table 4.0 2 WIT 2 VALVE LISTING DRAWING t M 0087 DRAWING TITLE : HPCI (MIGH PRESSURE COOLANT INJECTION)                                           ;

RELIEF NORMAL REQUEST I T' DWG IST FUNCTION SIZE BODY ACTU- POSI- TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORT (INCH) STYLE ATOR TION TYPE FREQ SHUTDOWN POSITION i 2301 014 M0 C6 2 B 4.000 GL M0 C BTC M3 BT0 M3- ! PIT Y2 FUNCTION HPCI MINIMUM FLOW RECIRCULATION LINE ISOLATION 2301-020 E1 2 C 16.000 CK SA SYS CTC SE RV 00F FUNCTION : HPCI TO CONDENSATE STORAGE TANK BACKFLOW PREVENil0N ' r 2301 023 RV A3 -2 C 1.500 RV SA C CT SP Y5 FUNCTION : HPCI B00 STER EUCTION LINE OVERPRESSURE PROTECTION l 2301- 6- D 10 1 A/C 1.000 XFC SA SYS AT-02 RR l-g .CTC RR ~! FUNCTION : MAIN STM TO HPCI DP/P H! SIDE EXCESS FLOW CK VLV l 2301 027. D 10 1 A/C 1.000 XFC SA SYS AT 02 RR CTC RR FUNCTION MAIN STM TO HPCI DP/P LO SIDE EXCESS FLOW CK VLV 2301 028 B9 2 B 1.000 GL A0 C/F0 BTO M3 FST M3 i PIT Y2 FUNCTION HPCI STEAM LINE DRAIN POT DISCHARGE TO SUPPRES$10N CHAMRER 2301 028 80 B9 NC B .001 803 50 0 BTD' M3 FST M3 FUNCTION : HPCI STEAM LINE DRAIN POT DISCHARGE TO TORUS SOLENCID { 2301 029 B 10 2 B 1.000 GL A0 0/FC BTC- M3 FST M3 PIT Y2 FUNCTION : HPCI STEAM LINE DRAIN POT DISCHARGE TO THE MAIN CONDENSER 2301 029 $0 B 10 NC B .001 S03 50 0 BTD M3 FST M3 N"'JTION HPCI STEAM LINE DRAIN PCT DISCHARGE TO CONDENSER SOLENCID s-s Revision 3 VA1.VES 4*160

i

                                                                                                                              -I GUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

, A. INSERVICE TESTING PLAN VALVES . l' ^* Table 4.0 2- 1 UNIT 2 'JALVE :.lSTING DRAWING : M 0087 l DRAWING TITLE : HPCI (HIGH PRESSURE COOLANT INJECTION) < 1 RELIEF WORMAL REQUEST DWG !$T FUNCTION SIZE 80DY ACTU- POSI- TEST TEST OR COLD TECHNICAL-VALVE NWISER COOR CLASS CATEGORY (INCM) STYLE ATOR TION TYPE FRE0 SHUTDOWN POSITION FST M3 P!T Y2 FUNCTION : HPCI STEAM LINE DRAIN POT DISCHARGE To THE MAIN CONDENSER 2301 030 50 B 10 NC s .001 503 SO D BTD M3 ; FST M3 FUNCTION : HPCI STEAM LINE DRAIN POT DISCHARGE TO CONDENSER SOLENCID , , 2301 032 50 .C7. 2 B 1.000 GL SC C/FC BTC M3 FST M3 [] PIT Y2 V FUNCTION MPCI DRAIN PCT TO GLAND SEAL CONDENSER 2301 034 C8 2- A/C- 2.000 CK SA SYS AT 01 RR l CTC SL RV 23e CT0 RR . 'RV 00E FUNCTION : HPCI, ALL DRAIN POTS, DISCHARGE TO SUPPRES$10N CHAMBER I 2301 035 *M0 E7' 2 8 16.000 GA Mo C sio M3 PIT Y2 FUNCTION HPCI SUPPRES$10N CHAMBER SUCTION LINE ISOLATION 2301 036 MO E9 2 B 16.000 GA M0 C BTC M3 BT0 M3 PIT Y2 FUNCTION : HPCI SUPPRESSION CHAMBER SUCTION LINE !$0LATl0N 2301 039 E8 2 C 16.000 CK SA STS CTO SF RV 00E CTOP M3 RV*00E , FUNCTION : HPCI SUPPRESSION CHAMBER SUCTION BACKFLOW PREVENTION 2301 040 D7 .2 C 4.000 CK SA SYS CTO M3 FUNCTION : HPCI MINIMUM FLOW RECIRCULATION LINE BACKFLOW PREVENTION 2301 045 B6 2 A/C 24.000 CK SA SYS AT 01 RR CTC RR Rv 238

Revision 3 VALVES 4 161

A GUAD CIT ES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN . VALVES Table 4.0 2 ! UNIT 2 VALVE LISTING DRAWING : M 0067 DRAWING TITLE HPCI (HIGH PRESSURE COOLANT INJECTION) RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE BODY ACTU- Post. TEST' TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCH) STYLE ATOR T10N TTPE FREQ SHUTDOWN. POSITION

            . 2301 045                       B8 2                  A/C                  24.000. CK                            SA       SYS                      CTO      M3 FUNCTION HPCl TURBINE EXHAUST BACKFLOW PREVENTION 2301 048 .M0                   B4 2                   3                      4.000 GA                           M0       O                         BTO     M3 PIT     Y2 FUNCTION : HPCI LUBE OIL AND GLAND SEAL COOLING WATER RETURN ISOLATION 2301 049 M0                    E4' -2                 8                      4.000 GA                           M0        C                        BTC     M3 PIT     Y2 FUNCTION t NPCI LUBE DIL AND GLAND SEAL COOLING WATER RETURN ISOLATION 2301 050                       C5 2                  C                      4.000 CK                            SA       SYS                       CTO     SG   RV.00E CTOP M3 . RV 00E FUNCTION : HPCI LUBE CIL COOLER AND GLAND SEAL CONDENSR TO B0OSTER PUMP 2301 051                       Ci         2           C                     4.000 CK                            SA        SYS                      CTC     SH   RV 00F CTCP M3      RV 00F FUNCTION : HPCI GLAND SEAL / LUBE OIL COOLING PUNP SACKFLOW PREVENTION 2301 053 RV                    C4 2                   C                      4.000 .RV                           SA       C                         CT SP V5 FUNCTION : HPCI GLAND SEAL / LUBE DiL OVERPRESSURE PROTECTION 2301 064-                      A7 2                   8                      1.000 GL                            A0        0/FC                      BTC   M3 FST   M3 PIT   Y2 FUNCTION : HPCI TURBINE STOP VALVE ABOVE SEAT DRAIN DISCHARGE 2301 064 50                     A6 NC                  8                       .001 $03                          50        D                         BTE    M3 FST    M3 FUNCTION : HPCI TURBINE STOP VALVE ABOYE SEAT ORAIN DISCHARGE SOLEN 0ID i

2301 065 A8 NC B 1.000 GL A0 0/FC BTC M3 FST M3 P!T Y2 FUNCTION- HPCI TUR81NE STOP VALVE ABOVE SEAT DRAIN DISCHARGE 2301 065 50 A.7 NC 8 .001 $03 SO D BTE O M3 Revision 3 VALVES ) 4 162 Y. k

QUAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0087 DRAWING TITLE : HPCI (HIGH PRESSURE COOLANT INJECTION) RELIEF NORMAL REQUEST DWG IST FUNCTION SIZE SODY ACTU- POSl* TEST TEST OR COLD TECHNICAL

         -VALVE NUMBER         COOR CLASS CATEGORY (INCH) STYLE ATOR                      T10N TYPE FREQ SHUTDOWN POSITION 2301 065 50              A7 NC            B               .001 503        50      0          EiT   M3 FUNCTION : HPCI TURBINE STOP VALVE AB0VE SEAT DRAIN DISCHARGE SOLEN 01D 2301 068                 A6 2             0            16.000 RPD         SA       C         DT M NT             Tv 23A FUNCTION : HPCI TURSINE EXHAUST LINE RUPTURE DIAPWtAGM 2301 069                  A6 2            0            16.000 RPD         SA       C         DT M NT             TV 23A FUNCTION : HPCI TURBINE EXHAUST LINE RUPTURE O!APHRAGM 2301 G71                 D8 2             A/C            2.000 SCK        SA       C/LO      AT 01 RR CTC    RR  RV 238 C      St  Rv 00E FUNCTION : HPCI, ALL DRAIN POTS, 0.ISCHARGE To SUPPRES$10N CHAMBER 2301 074                  C8 2            A/C          12.000 SCK         SA       C/LO      AT 01 RR CTC    RR   RV 238 CTO    M3 FUNCTION : HPCI TURBINE EXHAUST BACKFLOW PREVENTION 2301 075                 84 2             C            .4.000 CK          SA       SYS      CTO    RR   RV 00E CTOP M3     RV 00E FUNCTION : HPCI CCST TO GLAND SEAL / LUBE OIL C00'.ER BACKFLOW PREVENTION 2301 076                 E4 2             C             2.000 CK          SA       SYS       CTC   RR   RV 00F CTCP M3    RV 00F FUNCTION : HPCI GLAND SEAL CONDENSER RETURN P W P BACKFLOW PREVENil0N                      ,

2301 108 C1 2 C .750 CK SA SYS CTC RR RV 00F FUNCTION : HPCI ECCS FILL SYSTEM To NPCI BACKFLOW PROTECTION 2399 005 D8 2 C 2.000 CK SA SYS CTC RR RV 00F CTO RR RV 00E FUNCTION : HPCI TURBINE ENHAUST VACULM BREAK!R 2399*006 D8 2 C 2.000 CK SA SYS CTC RR RV 00F CTO RR RY 00E Revision 3 VALVES 4 163 l

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

       ,m;
         *                                  ' INSERVICE TESTING PLAN VALVES 3

Table 4.0 2 UNIT 2 VALVE LISTING ORAWING N 0087

ORAWING TITLE I NPCI (NIGN PRESSURE CCOLANT .INJECTsDN) RELIEF NORNAL REQUEST OWG IST FUNCTION SIZE- BODY ACTU- POSI* TEST TEST OR COLD' ' t f rN? % VALVE NUN 8ER ':00R CLASS CATEGORY (INCN) STYLE ATOR TION TTPE FREQ SNUTDOWN Pk TUNCTION t NPCI TURBINE EXNAUST VACULM BREAKER i 2901 010 07 ? C 4.000 CK SA SYS CTC SJ RV 00F L FUNCTIM HPCI SAFE SMUTDOWN NAKE UP TO HPCI SACKFLOW PROTECTION ! i i si 5 [

      . t.y i

l-1 V 1 k-l' l l l l l t f

     '(                                                                                                                    .

Revision 3 VALVES 4 164

     ' 73.                                                                                                                                               {
  'I '                                                                                                                                                   [
             $ r QUAD CITits NUCLEAR POWER STAflow, UNITS 1 AND 2

[p INSERVICE TESTING PLAN

VALVES

("'J fable 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0088 DRAWING TITLE : REACTOR WAfth CLEANUP RELitF NORMAL RieUEST DWG IST FUNCTION $12E toDT ACTU- Post. TEST ffst OR COLD TECHNICAL VALVE NUMSER 'C00R CLAtt CAftGORT (INCN) STTLE ATOR T10N TYPE FRio $NUTDWN POSIT!M 1201 002 M0 B6 1 A 6.000 GA MD 0 AT*01 RR BTC M3 Plf T2 FUNCil0N : RWCU

PSIMART CONTAINMENT ll0LAfl0N VALVE 1201 005 M0 BT 1 A 6.000 GA M0 O AT*01 RR BTC M3 Plf T2 7

FUNCTION : RWCU

PRIMART CONTAINMENT ISOLAfl0N VALVE lV k.

L i

-~

f ,. L i Revision 3 VALVES 4 165

l GUAD ClflES WUCLEAR POWER STAfl0N, UNITS 1 AND 2 j

   /N -                                                             lWSERVICE TESTING PLAN VALVES I

I Table 4.0 2 UNIT 2 VALVE lit!!NG l DRAWING : N 0009 DRAWING TITLE : RC'C P! PING (kEACTOR CORE ISOLAtl0N COOLING) l l RELIEF

NORMAL REQUEST 1 DWG 18T FLP.CTION $12E 80DT ACTU* PO$1- TEST TEST OR COLD TECHNICAL VALVE NumRER C00R CLA$$ CATEGORY (INCM) $ffLE ATOR T10N TYPE FREO $NUTDOWN POSITION 1301 015A A*P 1 A 1.00C XFC SA STS AT 02 RR OTC RR FUNCTION 1301 0158 .B2 1 A 1.000 XFC $A STS AT 02 RR CTC RR FUNCTION : e 1301 016 M0 02 1 A 3.000 GA MO O AT*01 RR STC M3 l' FUNCTION : RCIC TURBINE STEAM FEED 150LAfl0N VALVE PIT T2 1301 017 No B3 1 A 3.000 GA M0 O AT 01 RR BTC M3 PIT T2 FUNCTION : RCIC TUR$1NE STEAM FEED !$0LAfl0N VALVE , 1301 040 03 NC A/C 2.000 CK SA SYS AT 01 RR CTC RR RV 13A FUNCTION : RCIC TURBINE D18 CHARGE !$0LAT10N VALVE, PCIV 1301 041 02 NC A/C 8.000 CK SA $TS AT 01 RR CTC RR RV 13A FUNCil0N 3 RCIC

TURBINE DISCHARGE ISOLATION VALVE, PCIV 1301 0% D3 NC A/C 2.000 $CK SA C/LO AT*01 RR CTC RR RV 13A FUNCTION : RCIC
TURBINE DISCHARGE ISOLATION VALVE, PCIV 1301 064 D2 NC A/C 8.000 $CK SA C/LO AT 01 RR CTC RR RV 13A FUNCTION : RCIC TURBINE DISCHARGE ISOLATION VALVE, PCIV u

r Revision 3 VALVES 4 166 i _ _____.____________m_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ __ . . _ _ . _ _ -

GuAD CIT!!$ NUCLEAR POWER STAfl0N, UNITS 1 AND 2

  ,f^                                       INSERVICE ft5flNG PLAN . VALVES A

Table 4.0 2 UNIT 2 VALVE LitTING l w+ "i : M 0641 2 DRAWING T-lLE : Cok lutWT Afm0sPMERE MONITout RELiff NORMAL Ra0UEST - DWG IST FUNCTION SIZE 80DY ACTU* POSl* ftsf TEST OR COLD TECHNICAL VALVE meeBER C00R CLASS CATE00RY (INCN) FffLt ATOR TION TYPE PRIO SMUTDOWN POSIfl0N

2499 001A 80 D6 NC B .500 802 to C/FC BTO M3 RV 00C
. FST M3 Plf Y2 FUNCil0N: CAM . DRYWELL $4MPLE PATH $ELECil0N VALVE 2499 0018 80 03 NC B .,500 s02 $0 C/FC eTo M3 RV 00C F8T M3 Plf Y2 FUNCTION CAM . DRYW LL SAMPLE PATM SELECil0N VALVE 2499 002A*S0 06 NC A .500 $02 80 C/FC Af*01 RR l ,

GTC M3 RV 00C l \ BT0 M3 RV 00C FST M3 Pli Y2 FUNCil0N CAM

DRYWELL SAMPLE PATM SELECTION VALVE 2499 0028 90 D3 NC A .500 802 to C/FC AT.01 RR BTC M3 RV 00C STO M3 RV 00C FST M3 t- PIT Y2 FUNCTION : CAM . DRYWELL SAMPLE PATH SELECTION VALVE l v l 2499-003A so B7 NC B .500 802 to C/FC BTO M3 RV 00C j-FST M3 Plf Y2 FUNCT10N CAM . SUPPRES$10N CHAMBER SAMPLE PATH SELECTION VALYE 2499 0038 30 B2 NC B .500 802 to C/FC BTO P3 RV 00C FST M3 PIT Y2 FUNCTION CAM SUPPRES$10N CNAMBER SAMPLE PATH SELECTIDW VALVE 2499 004A 80 36 NC A .500 802 to C/FC AT 01 RR BTC M3 RV 00C

   /                                                                                              BTO     M3     RV 00C k

Revision 3 VALVES 4 167

eunD CITIES MUCLEAR POWER $fATION, UNITS 1 AND 2 I [

INSERVICE TESTING PLAN + VALVE 8 Table 4.0 2 UNIT 2 VALVE LISTING i DRAWING I M*0641 2 I DRAWlNG TITLE CONTAINMENT ATMDSPMERE MONITW 1 RELIEF k NWMAL REGLEST DWG IST FUNCil0N $12E t@Y ACTU. Poll. TEST TEdf OR COLD TECHNICAL VALVE NUMBER C00R CLAll CATEGORY (INCN) STYLE ATOR TION TYPE .FRE0 SNUTDOWN POSITION 2499 004A*t0 B6 NC A' .500 802 to C/FC FST M3

Plf Y2 . FUNCTION CAM

SUPPRES$10N CNAMBER SAMPLE PATH SELECTION VALVE I

2499 0048 s0 03 NC A .500 502 to C/FC AT*01 RR l BTC M3 RV 00C ) BTO M3 RV*00C < FST M3 I PIT T2 FUNCTION i CAM

SUPPRES$10N CHAMBER SAMPLE PATH SELECTION VALVE i

[ 2499 022A C7 NC A/C .500 CK SA SYS AT 01 RR CTC RR RV 24A CTO RR RV 00E ! CTOP M3 RV 00E < FUNCTION CAM

ATNOSPNERE SAMPLE RETURN CHECK VALVE I

2499 022s C2 NC A/C .500 CK SA STS AT 01 RR CTC RR RV 24A CTO ER - RV 00E

CTOP M3 RV 00E '

FUNCTION i CAM ATMORPMERE SAMPLE RETURN CHECK VALVE e i /

I ( Revision 3 VALVES 4 168

OVAD CITIES NUCLEAR POWER $1Afl0N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES Table 4.0 2 UNIT 2 VALVE LISTING DRAWING : M 0642 2 DkAWING TITLE : ATN0$PMERE CONTAINNENT ATMDSPHERE DlLUTION RELIEF NORMAL REQUEST DWG !$1 FUNCTION litt DODY ACTU* P061* TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLASS CATEGORY (INCN) $TYLE ATOR TION TYPE FREQ SMUTDOWN Postil0N 2599 002A A0 05 NC A 1.500 GL A0 C/FC AT 01 RR STC M3 BTD M3 FST M3 Pli Y2 FUNCTION : ACAD . AIR INJECTION INTO THE DRYWELL SELECTON VALVE 2599 002A 80 D6 NC B 1.000 803 30 D BTD M3 STE M3 FST M3 FUNCTION : ACAD Alt INJECTION INTO THE DRTWLL SELECTION VALVE SOLEN.

2599 0028 A0 D4 NC A 1.500 GL Ao C/FC AT 01 RR STC M3 BT0 M3 FST M3 PIT Y2 FUNCTION : ACAD . AIR INJECTION INTO THE DRYWLL $ ELECT 0N VALVE 2599 0028 30 D3 Nc 8 1.000 803 . 90 D STD M3 STE M3

                                                                              '$T
                                                                              <           M3 FUNCTION : ACAD AIR INJECTION INTO TNE DRYWLL ', ELECTION VALVC S0LEN.

t 2599 003A A0 C6 NC A 1.000 GL A0 C/FC AT 01 RR STC M3 810 M3 FST M3 PIT Y2 FUNCTION : ACAD AIR INJECTION INTO THE SUPPR. CHAMBER SELECTION VLV. 2599 003A 50 C7 NC 8 1.000 803 S0 0 BTD M3 BTE M3 FST M3 FUNCTION : ACAD AIR INJ. INTO THE SUPPR. CNAB. SELECil0N VALVE SOLEN. 2599 0038 A0 C3 NC A 1.000 GL A0 C/FC AT 01 RR Revision 3 VALVES 4 169

f

RJAD ClflES NUCLEAR POWER STAfl0N, UNITS 1 AND 2

   '^                                                                                                                                                                                                ,
    /                                                                INSERVICE TElf!NG PLAN . VALVES
   \
     \

fable 4.0 2 UNIT 2 VALVE LISTING DRAWING : N 0642 2 DRAWING TITLE : ATNOSPMERE CONTAINNENT ATNOSPMERE DILUTION RELIEF Nr2 MAL REeutST DWG IST FUNCTION ll2E 80DY ACTU- POSI. TEST TElf OR COLD TECHNICAL' VALVE NtmtEk COUR CLASS CATEGORY (INCH) STYLE ATOR fl0N TYPE FRED SNUTDOWN POSlfl0N 2599 0038 A0 C3 NC A 1.000 GL Ao C/FC BTC h3 ITO N3 FST N3' PIT Y2 FUNCTION : ACAD . AIR INJECTION INio THE SUPPR. CHANBER SELECTION VLV. 2599 0038 50 C2 NC B 1.000 803 30 D OfD M3 BTE N3 FST C FUNCTION : ACAD . AIR IWJ. INTO THE SUPPR. CNAS. $ ELECT 0h VALVE SOLEN. _g O 2599 004A A0 F3 NC A 1.000 GL A0 C/FC AT 01 RR STC M3 8f0 M3 _ . FST M3

l. PIT Y2 FUNCTION : ACAD . PRESSURE BLEED OFF ISOLATION VALVE 2599 004A so F3 NC B 1.000 803 to D BTD N3 IfE N3 FST Y2 FUNCTION : ACAD . BLEED 0FF ISOLAfl0N VALVE SOLEN 0ID 2599 0048 A0 E3 NC A 1.000 GL A0 C/FC AT 01 RR BTC N3 STO M3 FS1 M3 - l l

FIf Y2 FUNCTION : ACAD

PRESSURE BLEED 0FF ISOLAfl0W VALVE ;

2599 0048 30 E3 NC B 1.000 303 to D BTD M3 STE N3 ; FST Y2 ) FUNCTION : ACAD . BLEED OFF ISOLAfl0N VALVE SOLEN 0ID 2599 005A FCV F5 NC A 1.000 DIA A0 C/FC AT*01 RR FST N3 ( Revision 3 VALVES 4 170 1 l 1 ._ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ -~ ,

t I l 1 l l GUAD Cit!ES NUCLEAR POWER STATION, UNITS 1 AND 2 l INSERVICE TESTING PLAN VALVES V(N Table 4.0 2 UNIT 2 VALVE Litf!NG I 1 DRAW!hG : M 0642 2 l DRAWING TITLE : ATMO$PMERE CONTAINMENT ATMOSPHERE DILUTION l l RELIEF NORMAL REQUE$f DWG IST FUNCfl0N SIZE 8(BY ACTU. Po$la TEST TEST OR COLD TECHNICAL VALVE NUMBER C00R CLA$$ CATEGORY (INCN) STYLE ATOR TION TYPE FRE0 SMUTDOWN POSITION 2599 005A FCV F5 NC A 1.000 DIA Ao C/FC PIT Y2 ; FUNCTION : ACAD

PRESSURE BLEED 0FF !$0LAfl0N AND THROTTLING /FCV VALVE l

{ 2599 00$A 80 F5 NC 8 1.000 503 $0 0 Fsi M3 l ! FUNCTION : ACAD

BLEED 0FF ISOLAfl0N AND FCV VALVE SOLEN 0ID 2599 0058 FCV E5 NC A 1.000 DIA A0 C/FC AT 01 RR j FST M3 i PIT Y2 i FUNCTION : ACAD PRES $URE SLEED 0Fr it0LAfl0N AND THROTTLING /FCV VALVE

 't       2599 0058 $0        E5 NC          8'             1.000 803    SO    D        FST ' M3 FUNCTION : ACAD SLEED OFF ISOLAfl0N AND FCV VALVE SOLEN 0ID 1

2599 006 F8 NC C 1.000 CK SA SYS CTO M3 FUNCTION : ACAD

BLEED OFF BACKFLOW CNECK VALVE 1

I ! 2599 022 A7 NC C 1.500 CK SA SYS CTO M3 1 i FUNCTION : ACAD = Alt COMPRESSOR BACKFLOW PROTECTION CHECK VALVE 1 1 2599 023A C*6 NC A/C 1.500 CK SA SYS AT 01 RR

                                                                                       -CTC    RR  RV 25A CTO    M3 FUNCTION : ACAD

AIR INJECTION INTO THE DRYWELL CNECK VALVE 2599 0238 C3 NC A/C 1.500 CK SA SYS AT 01 RR CTC RR RV 25A CTO M3 FUNCTION : ACAD Alt INJECTION INTO THE DRYWELL CHECK VALVE 2599 024A C6 NC A/C 1.000 CK SA Sit AT 01 RR CTC RR RV 25A CTO M3 FUNCTION : ACAD A!R INJECT 10N INTO THE SUPPR. CHAMBER CHECK VALVE l

2599 0248 C3 NC A/C 1.000 CK SA SYS AT 01 RR l [] CTC RR Rv 25A l D l ' l Revision 3 VALVES l 4 171 L

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (m INSERVICE TESTING PLAN VALVES

 '(                                                Table 4.0 2 UNIT 2 VALVE LISTINC DRAWING N 0642 2 DRAWING TITLE : ATMOSPMERE CONTAINMENT ATMOSPHERE DILUTION RELIEF NORMAL                     REQUEST DWG      IST FUNCTION         $12E BODY    ACTU-   P0$la TEST     TEST OR COLD TECHNICAL VALVE NLMtER    C00R CLASS CATEGORY (INCN) $TYLE ATOR              TION TYPE      FREQ $NUTDOWN POSITION 2599 0248          C3 NC            A/C          1.000 CK     $A    SYS      CTO     M3 FUNCTION : ACAD AIR INJECT 10N INTO THE SUPPR. CHAMBER CNECK VALVE 2599 998 RV        85 NC            C             .001 RV     SA    C        CT.SP T5 FUNCTION ACAD

AIR COMPRESSOR SAFETT VALVE 2599 999 A6 NC C 1.250 CK SA SYs CTO M3 FUNCTION t ACAD
AIR COMPRESSOR BACKFLOW PROTECTION CHECK VALVE i

i N I l C e

                                                                                                                   )
                                                                                                                   )

(

Revision 3 VALVES A 172

1 t i euAD CITIES NUCLEAR POWER STAT 10N, UNITS 1 AND 2 INSERVICE TESTING PLAN

VALVES QJ Table 6.0 2 UNIT 2 VALVE LISTING I

DRAWING I N 1061 1 DRAWING TITLE : L10UID SAMPLING SYSTEM RELIEF

                                                                              - NORMAL                    REQUEST DWG     IST FUNCTION SIZE DCCY          ACTU-         Poll. TEST   TEST OR COLD TECHNICAL VALVE NUMBER   C00R CLASS CATEGORY (INCN) STYLE ATOR                 T10N TYPE     FREG SNUTDWN POSITION 8941 705 NCY      C6 2          B            .500 DIA     A0          C/FC- BTC      N3 FST   M3 Plf    Y2 FUNCTION : CORE SPRAY

SAMPLING SELECT VALVE 8941 705 MSV C7 NC 8 .001 303 to D BTD M3 FST M3 FUNCTION CORE SPRAY
SAMPLING SELECT VALVE SOLEN 0!D 8941 709 xCV E5 2 B 1.000 DIA A0 C/FC STC - M3 FST M3 p

i 1 PIT Y2 FUNCTION : kNR

SAMPLING SELECT VALVE e

8941709 KSV E5 NC e .001 803 to D BTD M3-FST M3 FUNCTION : RNR SAMPLING SELECT VALVE SOLEN 0ID , a l 8941 710 XCV D5 2 5 1.000 DIA A0 C/FC STC N3 FST M3 FIT Y2 FUNCTION : RNR . SAMPLING SELECT VALVE , 8941 710 *x5V D5 NC B .001 803 30 D BTD M3 FST N3 FUNCTION : RNR

SAMPLING SELECT VALVE 80LEN0!D I

l l Revision 3 VALVES l 4 173 j

i auAD CITIES NUCLEAR POWER STAfl0N, UNITS 1 AND 2 ,

  ' [~Y                                     INSERVICE TESTING PLAN

VALVES

\v)

I Table 4.0 2

       <                                         UNIT 2 VALVE LISTING                                                                                      l l

DRAW!NG : N 1062 DRAWING TITLE : CONI AINMENT AIR SAMPLING STSTEN i l RELIEF l WORMAL REQUEST l I DWG IST FUNCTION SIZE SQDT ACTU. P051- TEST TEST OR COLD TECHhlCAL VALVE NUMSER COOR CLASS CATEGORT (INCN) STYLE ATOR T10N TTPE FRE0 SNUTDOWN Postil0N l 8941 101 XCV C6 NC $ .500 DIA A0 C/FC STC M3 I FST M3 ) PIT Y2 FUNCTION : S$GT/CAS

SAMPLING ISOLAfl0N VALVE (FOR ACAD 8 DRTW, PURGE) 8941 101 XSV C6 NC $ .001 803 to D STD M3 ,

M3 I FST FUNCTION : 88GT/CAS

SAMPLING ISOLAfl0N VALVE SOLEWOID f

l '% E L e [ ( Revision 3 YALVES 4 174

QUAD Citit$ NUCLEAR POWit $1Atl0N, UNIf8 1 AND 2 IN$tRVICE ttsflkG PLAN VALVfl table 4.0 2 UN11 2 VALVE LllflNG DRAWING t M 1551 DRAWINC title : CONTROL ROOM HVAC RELiff NORMAL REQUEST DWG IST FUNC110N $12t 800Y ACTU- PO$la TE$1 ftST OR COLD llCNNICAL TION TYPE FREQ $NUTDOJN PO$lt!ON VALVE NUMBER COOR CLAS$ CAftGORY (INCH) 11YLE ATOR

 .................. .... ..... ........ ...... ..... ..... ...... ..... .... ........ ......... CTC                    M3 5799 3B6          C2 3           C            2.500 CK          SA            SYS FUNCT10N : CONTR. RM. HVAC RNR5W BACKFLOW PROTECTION CHECK VALVE Revision 3                                        ValW8                                                                                        i 4+175 1

I . . . . . . . . - - - - - - - - _ - - . - g

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 0202-005A-MO M-0035-2 D-6 1 28.000 GA MO 0202-005B-MO M-0035-2 D-3 1 28.000 GA MO 0203-001A-AO M-0013-1 F-4 1 20.000 GL AO 0203-001A-AP2 M-0013-1 F-4 NC .001 PLT AO 0203-001A-AP4 M-0013-2 F-7 NC .001 SO4 SO 0203-001A-SOAC M-0013-1 F-4 NC .001 SO3 SO 0203-001A-SODC M-0013-1 F-4 NC .001 SO3 SO 0203-001B-AO M-0013-1 D-4 1 20.000 GL AO 0203-001B-AP2 M-0013-1 F-4 NC .001 PLT AO 0203-001B-AP4 M-0013-1 F-4 NC .001 SO4 SO 0203-001B-SOAC M-0013-1 F-4 NC .001 SO3 SO 0203-001B-SODC M-0013-1 F-4 NC .001 SO3 SO 0203-001C-AO M-0013-1 C-4 1 2L.000 GL AO 0203-001C-AP2 M-0013-1 F-4 NC .001 PLT AO 0203-001C-AP4 M-0013-1 F-4 NC .001 SO4 SO 0203-001C-SOAC M-0013-1 F-4 NC .001 SO3 SO 0203-001C-SODC M-0013-1 F-4 NC .001 SO3 SO 0203-001D-AO M-0013-1 B-4 1 20.000 GL AO O' 0203-001D-AP2 M-0013-1 F-4 NC .001 PLT AO 0203-001D-AP4 M-0013-1 F-4 NC .001 SO4 SO 0203-001D-SOAC M-0013-1 F-4 NC .001 SO3 SO 0203-001D-SODC M-0013-1 F-4 NC .001 SO3 SO 0203-002A-AO M-0013-2 F-7 1 20.000 GL AO 0203-002A-AP2 M-0013-2 F-7 NC .001 PLT AO 0203-002A-AP4 M-0013-1 F-4 NC .001 SO4 SO 0203-002A-SOAC M-0013-2 F-7 NC .001 SO3 SO 0203-002A-SODC- M-0013-2 F-7 NC .001 SO3 SO 0203-002B-AO M-0013-2 E-7 1 20.000 GL AO 0203-002B-AP2 M-0013-2 F-7 NC .001 PLT AO 0203-002B-AP4 M-0013-2 F-7 NC .001 SO4 SO 0203-002B-SOAC M-0013-2 F-7 NC .001 SO3 SO 0203-002B-SODC M-0013-2 F-7 NC .001 SO3 SO 0203-002C-AO M-0013-2 D-7 1 20.000 GL AO 0203-002C-AP2 M-0013-2 F-7 NC .001 PLT AO 0203-002C-AP4 M-0013-2 F-7 NC .001 SO4 SO

                                                                              .001 0203-002C-SOAC          M-0013-2               F-7    NC                   SO3    SO 0203-002C-SODC          M-0013-2               F-7    NC           .001     SO3   SO 0203-002D-AO            M-0013              B-7    1       20.000        3L    AO 0203-002D-AP2           M-0013-2               F-7    NC           .001     PLT   AO 0203-002D-AP4          M-0013-2               F-7    NC            .001    SO4    SO 0203-002D-SOAC         M-0013-2               F-7    NC            .001    SO3    SO 0203-002D-SODC         M-0013-2               F-7    NC            .001    SO3    SO 0203-003A              M-0013-1               F-7    1         6.625       SRV    SAP

{ Revision 3 VALVES 4-175

l QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES i gN ' Table 4.1-1 UNIT 1 VALVE LISTING ; l DWG IST SIZE BODY ACTU- l P&ID NUMBER COOR CLASS (INCM) STYLE ATOR i VALVE NUMBER ---- ----- ------ ----- ----- M-0035-2 D-6 1 28.000 GA MO 0202-005A-MO 28.000 GA MO 0202-005B-MO M-0035-2 D-3 1 0203-001A-AO M-0013-1 F-4 l' 20.000 .GL AO ) 0203-001A-AP2 M-0013-1 F-4 NC .001 PLT AO l M-0013-2 F-7 NC .001 SO4 SO l 0203-001A-AP4 .001 SO3 So 0203-001A-00AC M-0013-1 F-4 NC M-0013-1 F-4 NC .001 SO3 SO 4 0203-001A-SODC GL AO 0203-001B-Ae M-0013-1 D-4 1 20.000 J 0203-001B-AP2 M-0013-1 F-4 NC .001 PLT AO j M-0013-1 F-4 NC .001 SO4 SO 0203-001B-AP4 So 0203-001B-SOAC M-0013-1 F-4 NC .001 SO3 i 0203-001B-SODC M-0013-1 F-4 NC .001 SO3 SO l M-0013-1 C-4 1 20.000 GL AO j 0203-001C-AO .001 PLT AO 0203-001C-AP2 M-0013-1 F-4 NC 0203-001C-AP4 M-0013-1 F-4 NC .001 SO4 SO 0203-001C-SOAC M-0013-1 F-4 NC .001 SO3 SO , 0203-0012-SODC M-0013-1 F-4 NC .001 SO3 SO ! M-0013-1 B-4 1 20.000 GL AO I 0203-00'.D-AO PLT 0203-001D-AP2 M-0013-1 F-4 NC .001 AO 0203-001D-AP4 M-0013-1 F-4 NC .001 SO4 SO y- F-4 NC .001 SO3 SO l

 ;    0203 -001D-SOAC         M-0013-1                                                 l M-0013-1               F-4   NC       .001   SO3   50     1 0203-001D-SODC                                                       GL    AO     l 0103-002A-AO            M-0013-2               F-7   1     20.000                 l M-0013-2               F-7   NC       .001    PLT  AO 0203-002A-AP2                                                  .001 SO4    SO 0203-002A-AP4           M-0013-1               F-4   NC                          1 0203-002A-SOAC         M-0013-2               F-7   NC        .001 SO3    SO    j 0203-002A-SODC          M-0013-2              F-7   NC        .001 SO3    SO    ,

0203-002B-AO M-0013-2 E-7 1 20.000 GL AO 0203-002B-AP2 M-0013-2 F-7 NC .001 PLT AO 0203-002B-AP4 M-0013-2 F-7 NC .001 SO4 SO I M-0013-2 F-7 NC .001 SO3 So 0203-002B-SOAC .001 SO 0203-002B-SODC M-0013-2 F-7 NC SO3 , 0203-002C-AO M-0013-2 D-7 1 20.000 GL AO I 0203-002C-AP2 M-0013-2 F-7 NC .001- PLT AO ' 0203-002C-AP4 M-0013-2 F-7 NC .001 SO4 SO 0203-002C-SOAC M-0013-2 F-7 NC .001 SO3 SO 1 0203-002C-SODC M-0013-2 F-7 NC .001 SO3 SO l M-0013-2 B-7 1 20.000 GL AO 0203-002D-AO .001 PLT AO 0203-002D-AP2 M-0013-2 F-7 NC 0203-002D-AP4 M-0013-2 F-7 NC .001 SO4 SO 0203-002D-SOAC M-0013-2 F-7 NC .001 SO3 SO 0203-002D-SODC M-0013-2 F-7 NC .001 SO3 SO 0203-003A M-0013-1 F-7 1 6.625 SRV SAP Revision 3 VALVES 4-176

/~

k 4

--m

I QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 0203-003A-SO M-0013-1 F-7 NC .001 SO3 SO M-0013-1 E-6 1 6.000 RV SO 0203-003B RV SO 0203-003C M-0013-1 C-8 1 6.000 M-0013-1 B-8 1 6.000 RV SO 0203-003D 6.000 RV SO 0203-003E M-0013-1 E-8 1 M-0013-1 F-8 1 6.000 SV SA 0203-004 A RPD SA 0203-004A-RPD M-0013-1 F-8 NS 8.000 M-0013-1 E-5 1 6.000 SV SA 0203-004B RPD SA 02 03-004 B-RPD M-0013-1 D-5 NS 8.000 M-0013-1 C-5 1 6.000 SV SA 0203-004C RPD SA 0203-004C-RPD M-0013-1 C-5 NS 8.000 M-0013-1 B-5 1 6.000 SV SA 0203-004D RPD SA 0203-004D-RPD M-0013-1 B-5 NS 8.000 M-0013-1 F-8 1 6.000 SV SA 0203-004E 8.000 RPD SA 0203-004E-RPD M-0013-1 F-8 NS M-0013-1 E-5 1 6.000 SV SA 0203-004F SA 0203 -004 F-RPD M-0013-1 D-5 NS 8.000 RPD M-0013-1 C-5 1 6.000 SV SA

    . 090?-C04G                                                           RPD    SA 0203-004G-RPD         M-0013-1            C-5    NS        8.000 M-0013-1            B-5     1        6.000    SV     SA 0203-004H                                                                  SA 0203-004H-RPD         M-0013-1            B-5    NS        8.000    RPD O      0220-001 -MO 0220-002 -MO 0220-017 A M-0013-1 M-0013-2 M-0013-2 E-4 E-7 E-8 1

1 1 3.000 3.000 1.000 GA GA XFC-MO MO SA M-0013-2 D-8 1 1.000 XFC SA 0220-017 B XFC SA 0220-017C M-0013-2 C-8 1 1.000 0220-017D M-0013-2 B-8 1 1.000 XFC SA 0220-018A M-0013-2 E-8 1- 1.000 XFC SA M-0013-2 D-8 1 1.000 XFC SA 0220-018B XFC SA 0220-018C M-0013-2 C-8 1 1.000 0220-018D M-0013-2 B-8 -1 1.000 XFC SA 0220-019 A M-0035-2 B-6 1 1.000 XFC SA M-0035-2 B-3 1 1.000 XFC SA 0220-019 B 1.000 XFC SA 0220-020A M-0035-2 B-6 1 0220-020B M-0035-2 B-3 1 1.000 XFC SA 022 0-021A M-0035-2 D-8 1 1.000 XFC SA 0220-021B M-0035-2 D-1 1 1.000 XFC SA 0220-022A M-0035-2 D-8 1 1.000 XFC SA M-0035-2 D-1 1 1.000 XFC SA 0220-022B GL AO 0220-044 M-0035-2 E-2 1 .750 0220-044 -SO M-0035-2 E-2 NC .001 SO3 SO 0220-045 M-0035-2 E-1 1 .750 GL AO 0220-045 -SO M-0035-2 E-1 NC .001 SO3 SO Revision 3 VALNES 4-177 O :

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

   \/                                     Table 4.1-1 UNIT 1 VALVE LISTING   _ __ _

DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR ' CLASS (INCH) STYLE ATOR 0220-051 M-0035-1 E-5 1 .500 DIA AO 0220-051 -SO M-0035-1 E-5 NC .999 SO3 SO M-0035-1 E-6 1 1.000 XFC CA 0220-054 18.000 SA 0220-058A M-0015 E-2 1 CK - 0220-05BB- M-0015 F-2 1 18.000 CK SA M-0015 F-2 2 18.000 CK SA 0220-059B SA 0220-062A M-0015 E-2 1 18.000 CK M-0015 F-2 1 18.000 CK SA 0220-062B 1.000 XFC SA 0220-067A M-0035-2 E-6 1 SA 0220-067B M-0035-2 F-6 1 1.000 XFC M-0035-2 E-6 1 1.000 XFC SA 0220-067C 1.000 XFC SA 0220-067D M-0035-2 F-6 1 SA 0220-067E M-0035-2 E-6 1 1.000 XFC SA M-0035-2 F-6 1 1.000 XFC 0220-067F 1.000 XTC SA 0220-067G M-0035-2 E-6 1 SA M-0035-2 F-6 1 1.000 XFC 0220-067h NC 1.000 CK SA 0220-081A M-0034-1 E-4 SA 0220-081B M-0034-1 E-4 NC 1.000 CK M-0034-1 E-4 NC 1.000 CK SA 1 0220-081C NC 1.000 CK SA 0220-081D M-0034-1 E-6 SA l M-0034-1 E-6 NC 1.000 CK i 0220-081E ' C' 0220-084A 0220-084B M-0013-1 M-0013-1 F-3 F-3 NC NC-1.000' 1.000 CK CK SA SA M-0013-1 F-3 NC 1.000 CK SA 0220-084C NC 1.000 CK SA 0220-084D M-0013-1 F-3 SA M-0013-2 F-7 NC 1.000 CK 0220-085A NC 1.000 CK SA 0220-085B M-0013-2 T-7 SA 0220-085C M-0013-2 F-7 NC 1.000 CK ' 0220-085D M-0013-2 F-7 NC 1.000 CK SA M-0035-2 E-1 l' 1.000 XFC SA 0220-089A 1.000 XFC SA > 0220-089B M-0035-2 E-1 1 0220-105A M-0034-1 D-4 NC 8.000 CK SA M-0034-1 E-4 NC 8.000 CK SA 0220-105B NC 8.000 CK SA 0220-105C M-0034-1 D-5 SA 0220-105D M-0034-1 D-5 NC 8.000 CK M-0034-1 E-5 NC 8.000 CK SA 0220-105E XFC SA 0262-2-005A M-0035-2 B-7 1 1.000 ' M-0035-2 B-2 1 1.000 XFC SA 0262-2-005B 1 1.000 XFC SA 0262-2-006A M-0035-2 B-7 SA M-0035-2 B-2 1 1.000 XFC 0262-2-006B E-6 1.000 XFC SA 0263-2-011 M-0035-1 1 SA M-0035-1 D-6 1 1.000 XFC 0263-2-013A D-3 1 1.000 XFC SA-0263-2-013B M-0035-1 Revision 3 VALVES 4 - 178

l QUAD CITIES RUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES O- Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR. VALVE NUMBER .... ----- ...... ..... ..... M-0035-1 D-6 1 1.000 XTC SA 02 63-2-015 A D-3 1 1.000 XFC SA 02 63-2-015B M-0035-1 1.000 XFC SA 02 63-2 -017 A M-0035-1 D-6 1 M-0035-1 D-3 1 1.000 XFC SA 02 63-2-017 B C-6 1 1.000 XFC SA 02 63-2-019 A M-0035-1 M-0035-1 C-3 1 1.000 XTC SA 0263-2-019 B B-6 1 1.000 XFC SA 0263-2-020A M-0035-1 1.000 XFC SA 0263-2-020B M-0035-1 B-6 1 M-0035-1 B-3 1 1.000 XFC SA 0263-2-020C B-3 1 1.000 XFC SA 0263-2-020D M-0035-1 M-0035-1 C-6 1 1.000 XFC SA 0263-2-023A C-6 1 1.000 XFC SA 0263-2-023B M-0035-1 M-0035-1 B-3 1 1.000 XFC SA 0263-2-023C B-3 1 1.000 XFC SA 0263-2-023D M-0035-1 1.000 XFC SA 0263-2-025 M-0035-1 B-6 1 0263-2-027 M-0035-1 A-6 1 1.000 XFC SA 0263-2-031B ' M-0035-1 C-6 1 1.000 XFC SA 0263-2-031C M-0035-1 C-6 1 1.000 XFC SA 02 63 031D M-0035-1 C-6 1 1.000 XFC SA' M-0035-1 C-6 1 1.000 XFC SA 02 63 031E 1.000 XFC SA 0263-2-031G M-0035-1 C-6 1 1.000 XFC SA O- 0263-2-031H 02 63-2-031J M-0035-1 M-0035-3 C-6 C-6 1 1 1.000 XFC SA M-0035-1 C-6 1 1.000 XFC SA 0263-2-031K C-3 1 1.000 XFC SA 02 63 031M M-0035-1 M-0035-1 C-3 1 1.000 XFC SA 0263-2-031N C-3 1 1.000 XFC SA 02 63-2-031P M-0035-1 M-0035-1 C-3 1 1.000 XFC SA 0263-2-031R C-3 1 1.000 XFC SA 0263-2-031T -M-0035-1 M-0035-1 C-3 1 1.000 XFC SA 0263-2-0310 C-3 1 1.000 XFC SA 0263-2-031V M-0035-1 M-0035-1 C-3 1 1.000 XFC SA 0263-2-031W B-3 1 1.000 XFC SA 0263-2-033 M-0035-1 0263-2-042A M-0035-1 C-6 1 1.000 XFC SA-0263-2-042B M-0035-1 C-3 1 1.000 XFC SA M-0041-1 E-8 NC .500 SO3 SO 0302-020A E-8 NC .500 SO3 SO 0302-020B M-0041-1 M-0041-1 E-6 2 1.000 DIA A0 0302-021A E-6 NC 1.000 DIA A0 0302-021B M-0041-1 DIA M-0041-1 F-1 2 1.000 A0 0302-021C F-1 NC 1.000 DIA A0 0302-021D M-0041-1 M-0041-1 F-5 2 2.000 DIA AO 0302-022A F-5 NC 2.000 DIA AO 0302-022B M-0041-1 Revision 3- VALVES 4-179 O

i QUI.D CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

 /    'i i.
    /                                            Table 4.1-1 UNIT 1 VALVE LISTING DWG    IST         SIZE     BODY  ACTU-VALVE NUMBER                  P&ID NUMBER                COOR CLASS       (INCH)     STYLE ATOR 0302-022C                       M-0041-1                      T-3  2             2.000    DIA   AO 0302-022D                       M-0041-1                      F-2  NC            2.000    DIA   AO 0302-025A                       M-0041-1                      E-7  NC            1.000    S03   SO          1 0302-025B                       M-00 41-1                     E-7  NC            1.000    S03   SO 0302-181A                       M-0041-1                      D-8  NC            1.000    SO2   SO 0302-181B                       M-0041-1                      D-8  NC            1.000    SO2   SO 0302-182A                       M-0041-1                      F-8  NC-           1.000    SO2   So          i 0302-182B                       M-0041-1                      F-8  NC            1.000    SO2   SO 0305-000 -RPD  -

M-0 041-1 E-10 1

                                                                                            .250   RPD   SA          l 0305-114                        M-00 41-1                     E-9  2               .750   CK    SA 0305-115                        M-0041-1                      E-10 1               .500   CK    SA          1 0305-117                        M-0041-1                      E-9  NC              .375   SO3   SO 0305-118                        M-0041-1                      E-9  NC              .375   SO3   SO 0305-120 -FCV                   M-0041-1                      C-10 1             1.000    SO2   SO 0305-121 -So                    M-0041-1                      C-9  1~              .750   SO2   SO 0305-122 -SO                    M-0041-1                      C-9  1               .750   SO2   SO 0305-123 -FCV                   M-0041-1                      C-10 1             1.000    SO2   So        J 0305-126 -CV                    M-0041-1                      0-10 1             1.000    DIA   AO         i 0305-127 -CV                    M-0 041-1                     D-9  1               .750   DIA   A0         j l         0305-138                        M-0041-1                      C-10 1               .500   CK    SA          l r~N    0737-001A                       M-0024-2                      P-7  NC              .375   BAL   SO

( ,) 0737-001B 0737-001C M-0024-2 M-0024-2 F-7 F-7 NC NC

                                                                                            .375
                                                                                            .375 BAL BAL SO SO 0737-001D                       M-0024-2                      F-7  NC              .375   BAL   So.

0737-001E M-0024-2 F-7 NC .375 BAL S0-0737-002A M-0024-2 F-7 NC .375 SHR EXP 0737-002B H-0024-2 F-7 NC .375 SHR EXP 0737-002C M-0024-2 F-7 NC .375 SHR EXP i 0737-002D M-0024-2 F-7 NC .375 SHR EXP l l 0737-002E M-0024-2 F-7 NC .375 SHR EXP 0743 M-0024-2 B-7 NC .375 CK SA 1 1001-002A M-0039-2 C-7 3 12.000 CK SA 1001-002B M-0039-2 B-7 3 12.000 CK SA 1001-002C M-0 C0 9-2 D-2 3 12.000 CK SA l 1001-002D M-0039-2 B-2 3 12.000 CK SA 1001-007A-MO M-0037 B-6 2 14.000 GA MO 1001-007B-MO M-0037 E-6 2 14.000 GA. MO l 1001-007C-MO M-0037 B-6 2 14.000 GA. MO. 1001-007D-MO M-0037 E-6 2 14.000 GA MO-1001-016A-MO M-0039-1 A-7 2 18.000 GL MO 1001-016B-MO M-0039-1 A-2 2 18.000 GL MO 1061-018A-MO M-0039-1 C-6 2 3.000 GA MO 1001-018B-MO M-0039-1 C-3 2 3.000 GA MO i Revision 3 VALVES ' 4-180 l ("'N l Q l

k l i QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 s INSERVICE TESTING PLAN -' VALVES I

 \-                                        Table 4.1-1 UNIT 1 VALVE LISTING                             -

l DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 1 1001-019A-MO M-0039-1 B-8 2 18.000 GA MO I 1001-019B-MO M-0039-1 B-2 2 18.000 GA MO 1001-020 -MO M-0039-1 B-3 2 3 .000 GA MO 1001-021 -MO M-0039-1 B-3 NC 3 .000 GA MO 10 01-02 2 A-RV .M-0039-1 E-8 2 1.000 RV SA l 10 01-02 2 B-RV M-0039-1 E-2 2 1.000 RV SA : 1001-023A-MO M-0039-1 E-6' 2 10.000 GA MO 1001-023B-MO M-0039-1 E-3 2 1 0.000 GA MO 10 01-02 6 A-MO M-0039-1 E-5 2~ 1 0.000 GA MO-1001-026B-MO M-0039-1 E'4 2 1 0.000 GA MO M-0039-1 E-6 2 1 6,000 GL MO ) 10 01-02 8A-MO GL 1 1001-028B-MO M-0039-1 E-3 2 1 6.000 MO 1001-029A-MO M-0039-1 E-6 1 1 6.000 GA MO 1001-029B-MO M-0039-1 E-3 1 1 6.000 GA MO 1001-034A-MO M-0039-1 E-7 2 1 6.000 GA MO j 1001-03 4 B-MO M-0039-1 E-3 2 1 6.000 GA MO : 1001-036A-MO M-0039-l' E-7 2 1 4.000 GL MO l 1001-036B-MO M-0039-1 D-3 2 14.000 GL MO 1001-037A-MO M-0039-1 E-7 2 6 000- GL MO 1001-03 7 3-MO M-0039-1 D-3 2 6 000 GL MO i I~ 1001-04 3 A-MO M-0037 B-4 2 1 4.000 GA MO :

 \        1001-043B-MO            M-0037                        E-4   2                14 000   GA     MO       l i

1001-043C-MO M-0037 B-8 2 14 000 GA MO 1001-043D-MO M-0037 D-8 2 14 000 GA MO 1001-047 -HO M-0039-1 C-4 1 20 000 CA MO 1001-050 -MO M-0039-1 D-4 1 20 000 GA MO M-0039-1 F-3. 2 1 000 RV SA 1001-0o9 SA 1001-067A M-0037 B-3 2 12 000 CK 1 1001-067B M-0037 E-3 2 12 000' CK SA M-0037 B-9 2 12 000 CK SA 1001-067C SA 1001-067 D M-0037 E-9 2 12 000 CK > j 1001-06BA-AO M-0039-1 E-5 1 16 000 CK AO l 1001-068B-AO M-0039-1 E-4 1 16 000 CK AO M-0037 B-5 2 1 000 RV SA 1001-12 5 A-RV 1 000 RV SA 1001-125B-RV M-0037 E-5 2 1001-125C-RV M-0037 B-7 2 1 000 RV SA M-0037 E-7 2 1 000 RV SA 1001-125D-RV 3 000 CK SA 1001-131 M-0039-1 B-7 2 ' M-0039-1 D-8 2 3 000 CK SA 1001-136A 3 000 CK SA 1001-136B M-0039-1 E-2 2 M-0037 B-3 2 2 000 CK SA 1001-142A 2 000 CK SA 1001-14 2 B M-0037 D-3 2 M-0037 B-9 2 2 000 CK SA 1001-142C Revision 3 VALVES 4-181 l

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

   ,s                           INSERVICE TESTING PLAN - VALVES
 't   )

(_/ Table 4.1-1 UNIT 1 VALVE LISTING '

                               - _ _ = - -

DWG IST SIZE BODY ACTU- ' VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 1001-142D M-0037 E-9 2 2.000 CK SA 1001-165A-RV M-0037 A-2 3 4.000 RV SA 1001-165B-RV M-0037 A-10 3 4.000 RV SA 1001-166A-RV M-0037 A-2 2 1.000 RV SA , 1001-166B-RV M-0037 A-10 '2 1.000 RV SA 1101-015 M-0040 C-3 1 1.500 CK SA 1101-016 M-0040 C-3 1 1.500 CK SA 1101-043A M-0040 D-6 2 1.500 CK SA 1101-043B M-0040 D-6 2 1.500 CK SA 1105- A-RV M-0040 C-7 2 1.500 RV SA 1105- B-RV M-0040 E-6 2 1.500 RV SA 1106- A M-0040 C-4 2 1.500 SHR EXP 1106- B M-0040 D-4 2 1.500 SHR EXP 1201-002 -MO M-0047 B-6 1 6.000 GA MO 1201-005 -MO M-0047 B-7 1 6.000 GA MO 1301-015A M-0000 A-2 1 .001 XFC SA M-0050 B-2 1 .001 XFC SA 1301-015B GA MO 1301-016 -MO M-0050 B-2 1 3.000 1301-017 -MO M-0050 B-3 1 3.000 GA MO 1301-040 M-0050 D-4 NC 2.000 CK SA 1301-041 M-0050 D-2 NC 8.000 CK SA

/ '

1301-055 M-0050 D-3 NC 2.000 SCK SA ( SCK SA 1301-064 M-0050 D NC 8.000 1402-003A-M0 M-0036 F-7 2 18.000 GA MO 1402-003B-MO M-0036 F-5 2 18.000 GA MO 1402-004A-MO H-0036 B-8 2 8.000 GL MO ' 1402-004B-M0 M-0036 C-8 2 8.000 GL MO M-0036 E-9 2 12.000 SCK SA 1402-008A SA 1402-008B M-0036 E-6 2 12.000 SCK - 1402-009A-AO M-0036 C-3 1 10.000 CK AO 1402-009B-A0 M-0036 C-3 1 10.000 CK AO 1402-013A M-0036 E-9 2 1.500- SCK SA M-0036 E-6 2 1.500 SCK SA 1402-013B GA MO 1402-024A-MO H-0036 B-2 2 10.000 1402-024B-MO M-0036 B-5 2 10.000 GA MO 1402-025A-MO M-0036 C-2 1 10.000 GA MO 1402-025B-MO M-0036 C-5 1 10.000 GA MO M-0036 C-9 2 2.000 RV SA 1402-028A-RV SA 1402-028B-RV M-0036 D-6 2 2.000 RV M-0036 D-3 1 .750 XFC SA 1402-031A XFC SA 1402-031B M-0036 D-4 1 .750 1402-038A-MO H-0036 E-8 2 1.500 GA MO 1402-038B-MO M-0036 E-7 2 1.500 GA MO Revision 3 VALVES 4-182 O

~ ~ ~ . . . .. I I QUAD CITIES NUCLIAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR M-0036 D-7 2 1.500 CK SA 1402-071 BTF AO

          -1601-020A-A0            M-0034-1            D-9         NC        20.000 M-0034-1            A-2         NC            .001       PLT     A0 1601-020A-AP                                                                     CK      SA 1601-020A-Chi           M-0034-1            A-2          NC           .001 M-0034-1            A-2          NC           .001       CK     -SA 1601-020A-CK2                                                     20.000         BTF     AO 1601-020B-AO            M-0034-1            E-9          NC M-0034-1            A-2          NC           .001       PLT     A0 1601-020B-AP                                                          .001       CK       SA 1601-020B-CK1           M-0034-1            A-2          NC M-0034-1            A-2          NC           .001        CK      SA 1601-020B-CK2                                                     18.000          BTF     A0 1601-021 -AO           M-0034-1            C-6          NC M-0034-1             A-2         NC           .001        PLT     A0 1601-021 -AP                                                         .001        CK      SA 1601-021 -CK1           M-0034-1           A-2          NC M-0034-1            A-2          NC          .001        CK      SA 1601-021 -CK2 1601-022 -AO            M-0034-1            C-6          NC       18.000         BTF     A0 1601-022 -AP            M-0034-1            A-2          NC          .001        PLT     AO 1601-022 -CK1           M-0034-1            A-2          NC          .001        CK      SA 1601-022 -CK2           M-0034-1            A-2          NC           .001       CK      SA M-0034-1            B-3          NC     +18.000          BTF     A0 1601-023 -AO                                                                     PLT     A0 1601-023 -AP            M-0034-1            A-2          NC           .001 1601-023 -CK1           M-0034-1            A-2          NC           .001       CK      SA M-0034-1            A-2          NC           .001       CK       SA 1601-023 -CK2                                                     18.000         BTF      A0 O-     1601-024 -AO 1601-024 -AP M-0034-1 M-0034-1 B-2 A-2 NC NC          .001        PLT     A0 1601-024 -CK1           M-0034-1            A-2           NC          .001        CK      SA M-0034-1            A-2           NC          .001        CK      SA 1601-024 -CK2 1601-031A              H-0034-1             D-9          NC      20.000          CK      SA 1601-031B              M-0034-1             E-9          NC      20.000          CK      SA 1601-032A              M-0034-1             E-2          NC           .001       CK      SA 1601-032B               M-0034-1            E-2          NC           .001       CK      SA 1601-032C               M-0034-1            E-2          NC           .001       CK      SA 1601-032D               M-0034-1            E-2          NC           .001       CK      SA M-0034-1            E-2          NC           .001       CK      SA 1601-032E                                                             .001       CK      SA 1601-032F               M-0034-1            E-2          NC 1601-033A               M-0034-1            E-7          NC           .001       CK      SA M-0034-1            E-7          NC           .001       CK      SA 1601-033B                                                              .001      CK       SA 1601-033C               M-0034-1            E-7          NC M-0034-1            E-7           NC           .001      CK       SA 1601-033D                                                              .001      CK       SA 1601-033E.              M-0034-1            E-7           NC M-0034-1            E-7           NC           .001       CK      SA 1601-033F                                                              .001       SO4     SO 1601-050A-SO           M-0034-1             D-9          NC 1601-050B-SO           M-0034-1             E-9          4C           .001       SO4     SO M-0034-1             C-6          NC           .001       SO4     So 1601-051A-SO                                                                     SO4     S0-1601-051B-SO.          M-0034-1             C-7          FC           .001 Revision 3                        VALVES 4-183 0

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES O Table 4.1-1 UNIT.1 VALVE LISTING DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR VALVE NUMBER ......... ..... .... ...-- ...... ----. .....

     ..................                                             .001      SO4     SO M-0034-1          C-2      NC 1601-052A-SO                                C-2      NC        .001      SO4     SO 1601-052B-SO              M-0034-1                           4.000       GA      AO 1601-055                  M-0034-1          A-6      NC A-6      NC        .001      SO3     SO 1601-055 -SO              M-0034-1                          18.000        BTF    AO M-0034-1          D-6      NC 1601-056 -AO                                A-2      NC         .001      PLT    AO 1601-056 -AP              M-0034-1                              .001      CK      SA M-0034-1          A-2       NC 1601-056 -CK1                                A-2      NC        .001      CK       SA 1601-056 -CK2             M-0034-1                            1.000       GL      MO M-0034-1           D-8      NC 1601-057                                     D-7      NC      1.000       GL       AO 1601-058 -AO             M-0034-1                            1.000       GL        AO 1601-059 -AO             M-0034-1           D-7      NC M-0034-1          E-1      NC    18.000        BTF        AO 1601-060 -AO                                A-2      NC        .001      PLT        AO 1601-060 -AP              M-0034-1                              .001     CK         SA 1601-060 -CK1             M-0034-1          A-2      NC M-0034-1          A-2      NC         .001      CK-       SA 1601-060 -CK2                               F-1      NC      2.000        GL        AO 1601-061 -AO              M-0034-1                           2.000 .GL              AO 1601-062 -AO              M-0034-1           B-3      NC A42       NC     6.000 BTF              AO 1601-063 -AO              M-0034-1                              .001 PLT            AO 1601-063 -AP              M-0034-1           A-2      NC A-2      NC        .001      CK        SA' 1601-063 -CK1             M-0034-1                              .001      CK        SA A-2      NC O    1601-063 -CK2 1601-065.-S0 1601-066 -SO M-0034-1 M-0034-1 M-0034-1 D-7 D-7.

NC NC

                                                                       .001
                                                                       .001
                                                                       .001 SO4 SO3 SO3 SO SO SO 1601-067 -SO             M-0034-1           D-6      NC M-0034-1           F-1      NC         .001      SO4       SO 1601-068 -So                                F-1      NC          .001     SO3       SO 1601-069 -SO             M-0034-1                                .001     SO3       SO 1601-070 -SO             M-0034-1            B-3     NC M-0034-1          A-3       NC         .001     SO4       SO 1601-071 -SO                                 F-7      2       3.000       GA        AO 2001-003 -AO              M-0043                                 .001     SO3       SO 2001-003 -SO              M-0043             F-7      NC M-0043             F-7      3       3.000       GA        AO 2001-004 -AO                                 F-7      NC         .001     SO3       SO 2001-004 -SO             M-0043                                          GA         AO M-0043             E-4      2       3.000 2001-015 -AO                                E-4      NC          .001    SO3        SO 2001-015 -SO             M-0043                              3.000       GA         AO 2001-016 -AO             M-0043             E-3      2 E-3      NC          .001     SO3       SO 2001-016 -SO             M-0043                            24.000         PLG       HO 2301-        -SV         M-0046             A-7       2 A-7       2    10.000         GA        MO 2301-003 -MO             M-0046                            10.000         GA        MO M-0046             C-9       1 2301-004 -MO                                 B-10     1     10.000        GA        MO 2301-005 -MO             M-0046                                           CK        AO M-0046              E-6      2     14.000 2301-007 -AO                                E-6      2     14.000        GA        MO 2301-008 -MO            M-0046                                           GA        MO 2301-009 -MO            M-0046              E-5      2     14.000 Revision 3                       VALVES 4-184 0                                                                                              1 I;
                                                                                               ]

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-COOR CLASS (INCH) STYLE ATOR VALVE NUMBER P&ID NUMBER ...__ __.... ..... __ ._

          .......___. ______                                                                         GL     MO 2301-010 -MO          M-0046                     E-5              2           6.000 M-0046                     C-6              2           4.000        GL     MO 2301-014 -MO                                     E-1               2        16.000         CK     SA 2301-020              M-0046                                                  1.500        RV     SA 2301-023 -RV          M-0046                     B-3               2 D-10              1          1.000        XFC    SA 2301-026              M-0046                                                               XFC    SA M-0046                     D-10                1        1.000 2301-027                                          B-9               2          1.000       GL     AO 2301-028              M-0046                                                     .001       SO3    SO 2301-028 -SO          M-0046                      B-9               NC M-0046                      B-10               2         1.000        GL     AO 2301-029                                   '

B-10 NC .001 SO3 SO 2301-029 -SO M-0046 GL AO 2301-030 M-0046 B-10 NC 1.000 M-0046 B-10 NC .001 SO3 SO 2301-030 -SO C-7 2 1.000 GL SO 2301-032 -SO M-004A SA M-00a6 C-8 2 2.000 CK 2301-034 E-7 2 16.000 GA MO 2301-035 -MO M-0046 2301-036 -MO M-0046 E-9 2 16.000 GA MO E-8 2 16.000 CK SA 2301-039 M-0046 CK SA M-0046 D-7 2- 4.000 2301-040 B-8 2 24.000 CK SA 2301-045 M-0046 4.000 GA MO 2301-048 -MO M-0046 B-4 2 E-4 2 4.000 GA MO 2301-049 -MO M-0046 O 2301-050 2301-051 M-0046 M-0046 M-0046 C-5 C-5 C-4 2 2 2 4.000 4.000 4.000 CK CK RV SA SA SA 2301-053 -RV A-7 2 1.000 GL AO 2301-064 M-0046 M-0046 A-6 NC .001 SO3 SO 2301-064 -SO A-8 NC 1.000 GL AO 2301-065 M-0046 .001 SO3 SO 2301-065 -SO M-0046 A-7 NC M-0046 A-6 2 16.000 RPD SA 2301-068 A-6 2 16.000 RPD SA 2301-069 M-0046 2301-071 M-0046 D-B 2 2.000 SCK SA M-0046 C-8 2 12.000 SCK SA 2301-074 B-4 2 4.000 CK SA 2301-075 M-0046 2.000 CK SA 2301-076 M-0046 E-4 2 C-1 2 .750 CK SA 2301-108 M-0046 SA M-0046 D-8 2 2.000. CK 2399-005 D-8 2 2.000 CK SA 2399-006 M-0046 M-0641-1 D-6 NC .500 SO2 SO 2499-001A-SO D-3 NC .500 SO2 SO 2499-001B-SO M-0641 .500 SO2 SO 2499-002A-SO M-0641-1 D-6 NC M-0641-1 D-3 NC .500 SO2 SO 2499-002B-SO B-7 NC .500 SO2 SO 2499-003A-SO M-0641-1 M-0641-1 B-2 NC .500' SO2 SO 2499-003B-SO Revision 3 VALVES 4-185 0

'i

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2

 ,- m                       INSERVICE TESTING PLAN - VALVES

(.I Table 4.1-1

 's > .

UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLI ATOR 2499-004A-SO M-0641-1 B-6 NC .500 SO2 SO M-0641-1 B-3 NC .500 SO2 SO 2499-004B-SO CK 2499-022A M-0641-1 C-7 NC .500 SA M-0641-1 C-2 NC .500 CK SA 2499-022B GL A0 2599-002A-AO M-0642-1 C-4 NC 1.500 2599-002A-SO M-0642-1 D-3 NC 1.000 SO3 SO 2599-002B-AO M-0642-1 C-5 NC 1.500 GL A0 2599-002B-SO M-0642-1 D-6 NC 1.000 SO3 SO + M-0642-1 C-3 NC 1.000 GL A0 2599-003A-AO SO3 2599-003A-SO M-0642-1 C-2 NC 1.000 SO 2599-003B-AO M-0642-1 C-6 NC 1.000 GL A0 2599-003B-SO M-0642-1 C-7 NC 1.000 SO3 SO 2599-004A-AO M-0642-1 F-3 NC 1.000 GL A0 M-0642-1 F-3 NC 1.000 SO3 So 2599-004A-SO GL A0 e 2599-004B-AO M-0642-1 E-3 NC 1.000 J M-0642-1 E-3 NC 1.000 SO3 SO 2599-004B-SO A0 2599-005A-FCV M-0642-1 F-5 NC 1.000 DIA 2599-005A-SO M-0642-1 F-5 NC 1.000 SO3 SO 2599-005B-FCV M-0642-1 E-5 NC 1.000 DIA AO 2599-005B-SO M-0642-1 E-5 NC 1.000 SO3 SO 2599-008 M-0642-1 F-8 NC 1.000 CK SA ' l' 2599-022 M-0642-1 A-7 NC 1.500 CK SA 2599-023A M-0642-1 C-3 NC 1.500 CK SA 2599-023B M-0642-1 C-6 NC 1.500 CK SA 2599-024A M-0642-1 C-3 NC 1.000 CK SA 2599-024B M-0642-1 C-6 NC 1.000 CK SA 2599-998 -RV M-0642-1 A-5 NC .001 RV SA i NC 1.250 CK SA j 2599-999 M-0642-1 A-6 2901-010 M-0046 D-7 2 4.000 CK SA : 3702- -MO M-0033 B-3 NC 8.000 GA MO

                      -MO           M-0033                B-1   NC      8.000   GA      MO 3703-                                                                  GA      MO 3706-        -MO           M-0033               'B-1   NC      8.000 3799-031                   M-0033                B-3   NC      8.000   CK      SA    1 3999-085                   M-0022-1              E-2   3       8.000   CK      SA M-0022-1              E-2'  3       8.000-  CK      SA 3999-086                                                       6.000   CK      SA' 3999-088                   M-0022-1              E-2   3 M-0022-1              C-4   3       2.500   CK      SA 3999-560                                                               CK      SA 3999-561                   M-0022-1              C-4   3       4.000 M-0058-3              D-5   NC      3.000   GA      M 4399-045                                                               CK      SA 4399-046                   M-0058-3              D-5   NC      3.000 4699-046                   M-0025                E-3   NC      1.000   GL      M     !

4699-047 M-0025 E-3 NC 1.000 CK' SA M-0043 C-9 NC 1.500 CK SA 4699-048 - -1/2 Revision 3 VALVES 4-186 O

c- ) QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING - DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 4699-123 M-0025 D-9 NC 1.500 CK SA 4699-196 M-0025 D-9 NC 1.500 CK SA 4699-196 - -1/2 M-0043 C-9 NC 1.500 CK SA 4699-226 M-0025 Z-99 NC 1.500 DIA AO 4699-226 - -1/2 M-0043 C-7 NC .001 GL AO 4699-306A M-0025 Z-99 NC .750 RV SA 4699-306A- -1/2 M-0043 Z-99 NC .001 RV SA 4699-306B M-0025 Z-99 NC .750 RV SA 4699-306B- -1/2 M-0043 Z-99 NC .001 RV SA 4699-306C M-0025 Z-99 NC .750 RV SA 4699-306C- -1/2 M-0043 Z-99 NC .001 RV SA 4699-306D M-0025 Z-99 NC .750 RV SA 4699-306D- -1/2 M-0043 Z-99 NC .001 RV SA 4699-307A M-0025 Z-99 NC .500 CK SA 4699-307A- -1/2 M-0043 Z-99 NC .500 CK SA 4699-307B M-0025 Z-99 NC .500 CK SA i 4699-307B- -1/2- M-0043 Z-99 NC .500 CK SA 4699-309 M-0025 Z-99 NC 1.500 CK SA ; 4699-309 - -1/2 M-0043 Z-99 NC .001 CK SA 4699-310 M-0025 Z-99 NC .250 SO3 So ;

  /   4699-310 -          -1/2 M-0043                  Z-99 NC           .001 SO3   So     l

(_,N/ 4711- -RV M-0034-1 D-8 NC 1.500 RV SA DIA 4720 M-0024-2 D-3 NC 1.000 AO 4721 M-0024-2 D-3 NC 1.000 DIA AO 4799-155 M-0024-2 E-2 NC 2.000 CK SA 4799-156 M-0024-2 E-3 NC 2.000 CK SA 4799-158 M-0024-2 F-4 NC .500 CK SA 4799-159 M-0024-2 F-4 NC .500 CK SA 4799-281A M-0024-2 B-2 NC .500 CK SA i 4799-485 .M-0024-2 D-3 NC .001 SO3 SO 4799-486 M-0024-2 D-3 NC .001 SO3 SO 5199-157 M-0029 C-6 NC 1.000 CK SA 5199-157 - -1/2 M-0029 C-6 NC 1.000 CK SA 5199-158 .M-0029 C-6 NC .750 CK SA 5199-158 - -1/2 M-0029 C-6 NC .750 CK SA 5201- -RV M-0029 E-4 NS 1.500 RV SA 4 5201- -RV -1/2 M-0029 E-4 NS 1.500 RV SA 5201- -SO M-0029 D-4 NS 1.000 SO2 SO 5201- -SO -1/2 M-0029 F-6 NS 1.000 SO2 SO 5299-003 M-0029 F-4 NS 1.500 CK SA 5299-003 - -1/2 M-0029 F-4 NS 1.500 CK SA 5299-005 M-0029 F-4 NS 1.500 CK SA 5299-005 - -1/2 M-0029 F-4 NS 1.500 CK SA Revision'3 VALVES 4-187

l QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 I INSERVICE TESTING PLAN - VALVES Table 4.1-1 UNIT 1 VALVE LISTING DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STY 12 ATOR VALVE NUMBER ___. . ... ...__. _____ ..__. 5401- A-AO M-0042-1 E-8 NC 18.000 BTF AO A-CK M-0042-1 Z-99 NC .001 CK SA 5401- E-7 NC .001 SO4 SO 5401- A-SO M-0042-1 5401- B-AO M-0042-1 E-8 NC- 18.000 BTF AO 5401- B-CK M-0042-1 Z-99 NC- .001 CK SA 5401- .B-SO M-0042-1 E-7 NC .001 SO4 SO 5402- A-AO M-0042-1 D-3 NC 18.000 GA AO 5402- A-CK M-0042-1 Z-99 NC .001 CK SA 5402- A-So M-0042-1 D-2 NC .001 SO4' SO B-AO M-0042-1 D-3 NC 18.000 GA AO 5402- .001 CK SA 5402- B-CK M-0042-1 Z-99 NC M-0042-1 D-2 NC .001 SO4 SO 5402- B-SO DIA AO 5741-306 -XCV M-1551 D-7 NC 1.000 M-1551 D-7 NC .001 SO3 SO 5741-306 -XSV C-2 3.000 DIA AO 5741-319B- -1/2 M-1551 3 5741-319B-XSV -1/2 M-1551 C-2 NC .001 SO3 SO M-1551 B-3 3 2.000 RV SA 5741-345 -PSV ~1/2 C-2 3 2.500 CK SA 5799-386 M-1551 7503- -MO M-0044 B-2 .NC 18.000 BTF MO M-0044 D-3 NC 6.000 BTF MO 7504- A-MO -1/2 A-3 NC 6.000 BTF MO

                                                   -1/2               M-0044 7504-       B-MO                                                                                                         BTF    MO 7505-      A-MO         -1/2               M-0044                                        D-3      NC     24.000 M-0044                                        B-3      NC     24.000         BTF     MO 7505-     B-MO         -1/2                                                             D-9      NC      24.000        BTF     MO 7507-     A-MO         -1/2               M-0044                                                                               MO M-0044                                        B-9      NC      24.000        BTF 7507-     B-MO         -1/2                                                                      NC           .500     DIA     AO 8801-     A-FCV                           M-0034-1                                      C-3 8801-     A-SO                            M-0034-1                                      C-3      NC           .001- SO3        SO B-FCV                           M-0034-1                                      D-3       NC          .500     DIA     AO 8801-                                                                                                                  SO3     SO 8801 -    B-SO                            M-0034-1                                      D-3       NC          .001 C-FCV                           M-0034-1                                      D-3       NC          .500     DIA     AO 8801-                                                                                                         .001     SO3     SO 8801-      C-SO                           M-0034-1                                      D-3       NC D-FCV                           M-0034-1                                     E-3'      NC          .500     DIA-    AO 8801-                                                                                                                  SO3-    SO 8801-      D-SO                            M-0034-1                                     D-3       NC          .001 A-FCV                           M-0034-1                                     C-3       NC           .500     DIA    AO 8802-                                                                                                                  SO3     SO 8802-     A-SO                            M-0034-1                                     C-3       NC           .001 B-FCV                           M-0034-1                                      D-3      NC           .500     DIA     AO 8802-                                                                                                                  SO3     SO 8802-     B-SO                            M-0034-1                                      D-3       NC          .001 8802-     C-FCV                           M-0034-1                                      D-3       NC          .500     DIA. AO M-0034-1                                      D-3       NC          .001     SO3     SO 8802-     C-SO                                                                                                         DIA 8802-     D-FCV                           M-0034-1                                      E-3       NC          .500             AO 8802-     D-SO                            M-0034-1                                      E-3       NC          .001     SO3     SO 8803                                      M-0034-1                                      C-6       NC          .500     GL      AO M-0034-1                                      C-6       NC          .001     SO3     SO 8803-       -SO Revision 3                                                            VALVES 4-138 O

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

  .- / 3
  .( /.                                        Table 4.1-1 UNIT 1 VALVE LISTING DWG     IST    SIZE     BODY    ACTU-VALVE NUMBER             P&ID NUMBER       COOR  CLASS  (INCH)     STYLE   ATOR 8803- 1D                  M-0034-1              D-3   NC          .500  GA      M 8803- 1E                  M-0034-1              D-3   NC          .500  GA      M 8803- 1F                  M-0034-1              D-3   NC          .500 GA       M     -l 8803- 1G                  M-0034-1              D-3   NC          .500 GA       M        l 8803- 1H-                 M-0034-1              D-3   NC          .500 GA       M 8803- II                  M-0034-1              D-3   NC          .500 GA       M       3 8803- 1J                  M-0034-1              D-3   NC          .500 GA       M      i 8803- 1K                  M-0034-1              D-3   NC          .500 GA       M        l 8803- .1 L                M-0034-1              D-3   NC          .500 GA       M 8803 - 1M                 M-0034-1              D-3   NC          .500 GA       M 8803- IN                  M-0034-1              D-3   NC          .500 GA       M 8803- 10                  M-0034-1              D-3   NC          .500 GA       M 8803- 1P                  M-0034-1              D-3   NC          .500 GA       M 8803- 1Q                  M-0034-1              D-3   NC          .500 GA       M 8803- 1R                  M-0034-1              D-3   NC          .500 GA       M        I 8803- 1S                  M-0034-1              D-3   NC          .500 GA       M        i 8803- 1T                  M-0034-1              D-3   NC          .500 GA       M        l 8803- 1U                  M-0034-1              D-3   NC        -.500   GA      M l

8803- IV M-0034-1 D-3 NC .500 GA M l 8803- 1W M-0034-1 D-3 NC .500- GA M I I' 8803- 1X M-0034-1 D-3 NC .500 GA M l

    \       8803- 1Y                  M-0034-1              D-3   NC          .500 GA       M        J 8803- 2D                  M-0034-1              D-3   NC          .500 GA       M l

8803- 2E M-0034-1 D-3 NC .500 GA M 8803- 2F M-0034-1 D-3 NC .500 GA M 8803- .2G M-0034-1 D-3 NC .500 GA M. 8803- 2H M-0034-1 D-3 NC .500 GA M 8803- 2I M-0034-1 D-3 NC .500 GA M 8803- 2J M-0034-1 D-3 NC .500- GA M 8803- 2K M-0034-1 D-3 NC .500 GA M 8803- 2L M-0034-1 D-3 NC .500 GA M 8803- 2M M-0034-1 D-3 NC .500 GA. M 8803- 2N M-0034-1 D-3 NC .500. GA M 8803- -20 M-0034-1 D-3 ,NC .500 GA M ' 8803- 2P M-0034-1 D-3 NC' .500 GA M 8803- 2Q M"0034-1 D-3 NC .500 GA M 8803- 2R M-0034-1 D-3 NC .500 GA 'M 8803- 2S. M-0034-1 D-3 NC .500 GA M 8803- 2T M-0034-1 D-3 NC .300 GA M 8803- 2U M-0034-1 D-3 NC .500 GA M 8803- 2V M-0034-1 D-3 NC .500 GA M 8803- 2W M-0034-1 D-3 NC .500 GA M 8803- 2X M-0034-1 D-3 NC' .500 GA- M-t- Revision 3 VALVES L 4-189 <

l l I QUAD CITIES NUCLEAR POWER STATIOK, UNITS 1 AND 2

 .f-                               INSERVICE TESTING PLAN - VALVES                                   ,

l

 .t  .

Table 4.1-1 i UNIT 1 VALVE LISTING l DWG IST SIZE BODY ACTU-VALVE NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR 8803- 2Y M-0034-1 D-3 NC .500 GA M M-0034-1 D-6 NC .500 GL AO 8804 8804- -SO M-0034-1 D-6 NC .001 SO3 SO 8941-101 -XCV M-1057 C-6 NC .500 DIA AO 8941-101 -XSV M-1057 C-6 NC .001 SO3 SO , 8941 005 -XCV M-1056-1 C-6 2 .500 DIA AO l M-1056-1 C-7 NC .001 SO3 SO l 8941-70b -XSV DIA AO 8941-709 -2CV M-1056-1 E-5 2 1.000 l 8941-709 -XE'V M-1056-1 E-5 NC .001 SO3 SO l 8941-710 -XCV M-1056-1 D-5 2 1.000 DIA AO l 8941-710 -XSV M-1056-1 D-5 NC .001 SO3 SO l l (O Revision 3 VALVES 4-190

l-QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES O- Table 4.1-2 UNIT 2 VALVE LISTING DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR VALVE NUMBER ____ _____ _____. _____ ...__ 0202-0057-MO M-0077-2 D-6 1 28.000 GA 3K) 0202-005B-MO M-0077-2 D-3 1 28.000 GA llo 0203-001A-AO M-0060-1 F-4 1 20.000 GL AO 0203-001A-AP2 M-0060-1 F-4 NC .001 PLT AO 0203-001A-AP4 M-0060-1 F-4 NC .001 SO4 SO 0203-001A-SOAC M-0060-1 F-4 NC .001 SO3 SO 0203-001A-SODC M-0060-1 F-4 NC .001 SO3 SO 0203-001B-AO M-0060-1 D-4 1 20.000 GL AO 0203-001B-AP2 M-0060-1 F-4 NC .001 PLT AO M-0060-1 F-4 14C .001 SO4 SO' 0203-001B-AP4 .001 SO3 SO 0203-001B-SOAC M-0060-1 F-4 NC M-0060-1 F-4 NC .001 SO3 SO 0203-001B-SODC GL AO 0203-001C-AO M-0060-1 C-4 1 20.000 0203-001C-AP2- M-0060-1 F-4 NC .001 PLT AO M-0060-1 F-4 NC .001 SO4 SC 0203-001C-AP4 SO3 SO 0203-001C-SOAC M-0060-1 F-4 NC .001 0203-001C-SODC M-0060-1 F-4 NC .001 SO3 SO 0203-001D-AO M-00CO-1 B-4 1 20.000 GL AO 0203-001D-AP2 M-0060-1 F-4 NC .001 PLT AO 0203-0010-AP4 M-0060-1 F-4 NC .001 SO4 SC-SO3 SO 0 0203-001D-SOAC 0203-001D-SODC 0203-002A-AO M-0060-1 M-0060-1 M-0060-2 M-0060-2 Ft 4 F-4 F-7 F-7 NC NC 1 NC

                                                                               .001
                                                                               .001 20.000
                                                                               .001 SO3 GL PLT SO AO AO 0203-002A-AP2                                                           .001 0203-002A-AP4          M-0060-2               F-7    NC                           SO4     SO 0203-002A-SOAC         M-0060-2               F-7    NC                 .001      SO3     SO 0203-002A-SODC         M-0060-2               F-7    NC                  .001     SO3     SO 0203-002B-AO           M-0060-2               E-7     1            20.000         GL      AO 0203-002B-AP2          M-0060-2               F-7    NC                  .001     PLT     AO 0203-002B-AP4           M-0060-2              F-7    NC                  .001     SO4     SO 0203-002B-SOAC          M-0060-2              F-7     NC                 .001     SO3     SO 0203-002B-SODC          M-0060-2              F-7     NC                 .001     SO3     SO 0203-002C-AO           .M-0060-2              D-7     1            20.000         GL      AO 0203-002C-AP2           M-0060-2              F-7     NC                 .001     PLT     AO 0203-002C-AP4           M 0060-2              F-7     NC                  .001    SO4     SO 0203-002C-SOAC          M-0060-2              F-7     NC                  .001     SO3     SO 0203-002C-SODC         M-0060-2               F-7    NC                  .001     SO3     SO 0203-002D-AO           M-0060-2               C-7    1             20.000         GL      AO 0203-002D-AP2          M-0060-2               F-7    NC                  .001     PLT     AO 0203-002D-AP4          M-0060-2               F-7    NC                  .001     SO4     S0-0203-002D-SOAC         M-0060-2               F-7    NC                  .001     SO3     SO 0203-002D-SODC         M-0060-2               F-7     NC                  .001    SO3-    SO 0203-003A              M-0060-1               F-7     1               6.625       SRV     SAP Revision 3                        VALVES 4-191 0

1

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES i: 9 Table 4.1-2 UNIT 2 VALVE LISTING

DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR VALVE NUMBER ____ _____ _ _____ _____ ' 0203-003A-SO M-0060-1 F-7 NC _____01

                                                                                                                                             .0                 SO3       SO M-0060-1                                D-6                         1                              6.000                RV        SO 0203-003B                                                                                                                  6.000                 RV       SO
 ~~

0203-003C M-0060-1 C-8 1 SO M-0060-1 B-8 1 6.000 RV

?"              0203-003D                                                                                                                  6.000                 RV       SO

0203-003E M-0060-1 D-8 1 M-0060-1 F-8 1 6.000 SV SA

    ,_          0203-004A                                                                                                                  8.000                 RPD      SA 0203-004A-RPD           M-0060-1                                  F-8                       NS SA M-0060-1                                  E-5                        1                             6.000                   SV 0203-004B                                                                                                                  8.000                   RPD     SA

= 0203-004B-RPD M-0060-1 D-5 NS M-0060-1 C-5 1 6.000 SV SA 0203-004C C-5 NS 8.000 RPD SA i 0203-004C-RPD M-0060-1 M-0060-1 B-8 1 6.000 SV SA 0203-004D SA .~'- 3 0203-004D-RPD M-0060-1 B-8 NS 8.000 RPD M-0060-1 F-8 1 6.000 SV SA 0203-004E 8.000 RPD SA

           -     0203-004E-RPD           M-0060-1                                   F-8                      NS M-0060-1                                   E-5                       1                             8.000                  SV      SA
    =_           0203-004F                                                                                                                                         RPD     SA 0203-004F-RPD           M-0060-1                                   D-5                       NS                            8.000 M-0060-1                                   C-5                       1                             6.000                  SV      SA 0203-004G                                                                                                                  8.000                  RPD     SA 0203-004G-RPD           M-0060-1                                   C-5                       NS M-0066-1                                    B-8                      1                             6.000                    SV     SA 0203-004H                                                                                                                  8.000                    RPD    SA 0203-004H-RPD           M-0060-1                                    B-8                      NS M-0060-1                                    E-4                       1                            3.000                    GA     MO 0220-001 -MO                                                                                                                                        GA     MO 0220-002 -MO           M-0060-2                                     E-7                      1                            3.000 M-0060-2                                     E-8                      1                            1.000                    XFC    SA 0220-017A                                                                                                                                          XFC    SA 0220-017B              M-0060-2                                     D-8                      1                            1.000 M-0060-2                                     C-8                      1                            1.000                    XFC    SA 0220-017C                                                                                                                                          XFC    SA 0220-017D              M-0060-2                                      B-8                     1                             1.000 M-0060-2                                     E-8                     1                             1.000                   XFC    SA 0220-018A                                                                                                                                          XFC    SA 0220-018B               M-0060-2                                     D-8                     1                             1.000 M-0060-2                                      C-8                    1                             1.000                   XFC    SA 0220-018C                                                                                                                                          XFC    SA 0220-018D               M-0060-2                                      B-8                     1                            1.000 M-0077-2                                      B-6                     1                            1.000                   XFC    SA 0220-019A                                                                                                                                           XFC    SA 0220-019B               M-0077-2                                       B-3                    1                            1.000 M-0077-2                                      B-6                     1                            1.000                    XFC    SA 0220-020A                                                                                                                  1.000                    XFC    SA 0220-020B               M-0077-2                                      B-3                     1 M-0077-2                                       D-8                    1                            1.000                    XFC    SA 0220-021A                                                                                                                                           XFC    SA 0220-021B              M-0077-2                                       D-1                    1                            1.000 M-0077-2                                       D-8                    1                            1.000                    XFC    SA 0220-022A                                                                                                                 1.000                    XFC    SA 0220-022B              M-0077-2                                        D-1                    1 0220-044               M-0077-2                                        E-5                    1                             .750                   GL     AO M-0077-2                                        E-5                   NC                             .001                   SO3    SO 0220-044 -SO                                                                                                                                       GL     AO 0220-045               M-0077-2                                        E-7                    1                              .750 M-0077-2                                         D-7                   NC                             .001                  SO3    SO 0220-045 -So Revision 3                         VALVES 4-192 O

l v 1

                                                                                                             -l QUAD CITIES NUCLEAR POWER STATION,-UNITS 1 AND 2                                   H l

c INSERVICE TESTING PLAN - VALVES i 3' Table 4.1-2 l UNIT 2 VALVE LISTING a I DWG IST SIZE BODY ACTU-- l VALVE NUMBER P&ID NUMBER- COCR CLASS (INCH) STYLE ATOR 0220-051 M-0077-1 E-5 1 .500 DIA AO l M-0077 E-5 NC .999 SO3 SO. 0220-051 -SO XFC 'SA 0220-054 M-0077-1 E-6 1 1.000 M-0062 E-2 1 18.000_ CK: SA l 0220-058A 18.000 CK SA 0220-058B M-0062 F-2 l' M-0062 F-2 2 18.000 CK SA 0220-059B 18.000 CK SA 0220-062A- 'M-0062 E-2' 1 M-0062 F-2' 1 18.000 CK SA 0220-062B 1.000 XFC SA 0220-067A M-0077-2 F-6 1 M-0077-2 F-6 1 1.000 XFC SA 0220-067B 1.000 XFC SA 0220-067C M-0077-2 F-6 1 M-0077-2 F-6; 1 1.000 XFC 'SA 0220-067D 1.000 XFC SA I 0220-067E M-0077-2 E-6 1 , M-0077-2 F-6 1 1.000 XFC SA i 0220-067F 1.000 XFC SA 0220-067G M-0077-2 E-6 1 M-0077-2 F-6 .1 1.000 XFC SA 0220-067H. SA 0220-081A- M-0076-1 E-4 NC 1.000 CK , SA 0220-081B M-0076-1 E-4 NC 1.000 CK M-0076-1 E-4 NC 1.000' CK SA 0220-081C 1.000 CK- SA t 0220-081D M-0070-1 E-6 NC CK SA 0220-081E M-0076-1 E-6 NC 1.000 L [_.T NC 1.000 CK SA

-- \_/        0220-084A               M-0060-1                F-3                                          !

M-0060-1 F-3 NC 1.000 CK SA 0220-084B ~1.000 CK~ SA 0220-084C M-0050-1 F-3 NC , M-0060-1 F NC 1.000 CK SA ; 0220-084D CK SA 0220-085A M-0060-2 F-7 NC. 1.000 . M-0060-2 F-7 NC 1.000 (M( SA l' 0220-085B CK. SA 0220-085C M-0060-2 F-7 NC 1.000 M-0060-2 F NC 1.000 CK- SA 0220-0850 1.000 XFC- SA 0220-089A M-0077-2 E-1 1 M-0077-2 E-1 1 1.000 XFC SA 0220-089B 8.000- CK- SA 0220-105A M-0076-1 D-4' NC 0220-105B M-0076-1 E-4 NC 8.000 - (M< 'SA , 0220-105C M-0076-1 E-5 NC 8.'000' CK- SA M-0076-1 -D-5 NC B . 0 00 - CK SA i 0220-105D 8.000 CK SA 0220-105E M-0076-1 E-5 NC i M-0077-2 B-7 1 1.000 XFC SA 0262-2-005A 1.000 XFC SA 0262-2-005B M-0077-2 B-2 1 M-0077-2 P-7 i 1.000 XFC SA 0262-2-006A 1.000 XFC SA 0262-2-006B M-0077-2 B-2 1 M-0077 E-6 1 1.000 AFC SA < 0263-2-011 D-6 1 1.000 XFC CA 0263-2-013A M-00*; 7 -1 1.000 XFC SA 0263-2-013B M-0077 D-3 1 Revision 3 VALVES 4-193 r~) V

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES O- Table 4.1-2 UNIT 2 VALVE LISTING DWG IST -SIZE BODY = ACTU-P&ID NUMBER' COOR CLASS . (INCH) . STYLE ATOR VALVE NUMBER' ____ _____ ______ _____ _____ D-6 1.000 XFC SA 0263-2-015A M-0077-1 1 XFC SA M-0077-1 D-3 l' 1.000 0263-2-015B D-6 1.000- XFC SA 0263-2-017A M-0077-1 1

    -e 0263-2-017B                                    M-0077-1                                                D-3      lt                1.000- XFC           SA C-6       1                 1.000       XFC     SA-0263-2-019A                                    M-0077-1                                                                                         XFC:   SA M-0077-1                                                C-3       1                 1.000 0263-2-020?                                                                                                      1                 1.000        XFC     SA 02 63-2 -720 A                                 M-0077-1                                                 B-6 XFC     SA 0263-2-02::b                                   M-0077-1                                                  B-6     1                 1.000 M-0077-1                                                   B-3    1.                1.000        XFC-    SA 0263-2-020c-                                                                                              B-3     1                1.000        XFC     SA 0263-2-020D                                    M-0077-1                                                                                         XFC     SA M-0077-1                                                   C-6     1              -1.000 0263-2-023A                                                                                               C-6                      1.000        XFC      SA 0263-2-023B                                     M-0077-1                                                            1 SA M-0077-1                                                  B-3       1              1.000        XFC 0263-2-023C                                                                                                         1              1.000        XFC. SA 0263-2-023D.                                   M-0077-1                                                  B-3'
                                                                                                                                                                              .S7c M-0077-1                                                  B-6         1            1.000        XFC 0263-2-025                                                                                                                        1.000        XFC        SA 0263-2-027                                     M-0077-1                                                  A-6         1 0263-2-031B                                    M-0077-1                                                  C-6         1             1.000 .XFC             SA M-0077-1                                                  C-6         1             1.000       XFC        SA 0263-2-031C                                                                                              C-6         1             1.000- XFC             SA 0263-2-031D                                    M-0077-1                                                                                         XFC       SA M-0077-1                                                   C-6        1             1.000 4

0263-2-031E 1.000 XFC SA 0263-2-031G M-0077-1 C-6 1 0263-2-031H M-0077 C-6 1 1.000 -XFC SA M-0077-1 C-6 1 1.000 XFC SA 0263-2-031J 1 1.000 XFC SA 0263-2-031K- M-0077-1 C-6 SA M-0077-1 C-3 1- 1.000 XFC

                      -0263-2-031M-                                                                                                          1            1.000        XFC        SA 0263-2-031N                                   M-0077-1                                                   C-3 SA M-0077-1                                                   C-3         1            1.000        XFC 0263-2-031P                                                                                                                       1.000        XFC     -SA 0263-2-031R                                   M-0077-1                                                   C-3         1 SA M-0077-1                                                 -C-3         1            1.000        XFC' 0263-2-031T                                                                                              C-3                       1.000       XFC        SA.

0263-2-031U M-0077-1 1

                                                                                                                                                                               -SA M-0077-1                                                  C-3         1             1.000        XFC    -

0263-2-031V 1 1.000 XFC SA 0263-2-031W M-0077-1 C-3

                                                                                                                                                                               -SA M-0077-1                                                   B-3         1            1.000        XFC 0263-2-033                                                                                                            1            1.000-       XFC       SA 0263-2-042A                                    M-0077-1                                                   C-6 XFC      .SA M-0077-1                                                   C-3         1            1.000 0263-2-042B                                                                                                           NC              .500      SO3        SO 0302-020A                                      M-0083-1                                                   E-8 SO M-0083-1                                                   E-8         NC              .500      SO3 0302-020B                                                                                                             2            1.000        DIA       AO 0302-021A                                      M-0083-1                                                   E-6 M-0083-1                                                   E-6         NC             1.000      DIA         AO 0302-021B-                                                                                                           2              1.000      DIA-          AO 0302-021C                                     M-0083-1                                                   F-1 M-0083-1                                                   F-1         NC             1.000      DIA           AO 0302-021D                                                                                                            2              2.000      DIA           AO 0302-022A                                     M-0083-1                                                   F-5 0302-022B                                     M-0083-1                                                   F-5         NC             2.000       DIA          AO Revision 3                                               VALVES 4-194 O

l

                                                                       ;.-......~____..      -

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-2 UNIT 2 VALVE LISTING DWG IST SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH)- STYLE ATOR VALVE NUMBER ---- ----- ---- ----- ----- 0302-022C M-0083-1 F-3 2 -2.000 DIA AO. M-0083 F-2 NC 2.000 DIA AO 0302-022D SO3 SO 0302-025A M-0083-1 .E-7 NC ' 1.000 M-0083-1 E-7 NC 1.000 SO3 SO 0302-025B SO2 SO 0302-181A M-0083-1 E-8 NC 1.000 M-0083-1 E-8 NC 1.000 SO2 SO 0302-181B NC 1.000 SO2 SO 0302-182A M-0083-1 F-8 SO2 SO M-0083-1 F-8 NC 1.000 0302-182B SA 0305-000 -RPD M-0083-1 E-10 1 .250 RPD=

M-0083-1 E-9 2 .750. CK SA-0305-114 CK SA 0305-115 M-0083-1 E-10 1 .500 M-0083 E-9 NC .375' SO3 SO 0305-117 NC .375- SO3 SO 0305-118 M-0083-1 E-9 SO M-0083-1 C-10 1 1.000 SO2-0305-120 -FCV C-9 1 .750 SO2 SO 0305-121 -SO M-0083-1 SO2 SO 0305-122 -30 M-0083-1 C-9 1 .750 M-0083-1 C-10 1 1.000 SO2 SO 0305-123 -FCV D-10 1.000 DIA AO 0305-126 -CV M-0083-1. 1 M-0083-1 D-9 1 .750 DIA AO 0305-127 -CV C-10 1 .500 CK .A S 0305-138 M-0083-1 0737-001A M-0071-2 F-7 NC .375 BAL SO M-0071-2 F-7 NC .375 BAL S0-0737-001B BAL SO 0737-001C M-0071-2 F-7 NC .375 M-0071-2 F-7 NC .375 BAL SO 0737-001D BAL SO= 0737-001E M-0071-2 F-7 NC .375 0737-002A M-0071-2 F-7 NC .375 SHR EXP-0737-002B. M-0071-2 F-7 NC .375 SHR- EXP M-0071-2 F-7 NC .375 SHR EXP 0737-002C .375 SHR EXP 0737-002D M-0071-2 F-7 NC 0737-002E M-0071-2 F-7 NC .375 SHR' EXP 1001-002A -M-0081-2 C-7 3 12.000 CK SA 1001-002B M-0081-2 B-7 3 12.000- CK SA 1001-002C M-0081-2 D-2 3 12.000 CK SA 1001-002D M-0081-2 B-2 -3 12.000 CK SA M-0079 B-6 2 14.000 GA MO 1001-007A-MO 14.000 GA MO M-0079 E-6 2 1001-007B-MO 14.000 GA MO 1001-007C-MO M-0079 B-6 2 1001-007D-MO M-0079 E-6 2 14.000 GA MO' M-0081-1 A-7 2 18.000 GL MO 1001-016A-MO GL 1001-016B-MO M-0081-1 A-2 2 18.000 FK) M-0081-1 C-6 2 3.000 GA- MO 1001-018A-MO C-3 2 3.000 GA MO 1001-018B-MO M-0078 M-0081-1 B-8 2 18.000 GA MO 1001-019A-MO Revision 3 VALVES 4-195 0

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-2 UNIT 2 VALVE LISTING _ DWG If.T SIZE BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR VALVE NUMBER ---- ----- ----- ----- ----- M-0081-1 D-2 2 18.000 GA MO 1001-019B-MO 3.000 GA MO 1001-020 -MO M-0081-1 B-7 2 M-0081-1 C-7 NC 3.000 GA MO 1001-021 -MO 1.000 RV SA 1001-022A-RV M-0081-1 E-8 2 M-0081-1 E-2 2 1.000 RV SA 1001-022B-RV GA MO 1001-023A-MO M-0081-1 E-6 2 10.000 M-0081-1 E-3 2 10.000 GA MO 1001-023B-MO GA MO 1001-026A-MO M-0081-1 E-5 2 10.000 M-0081-1 E-4 2 10.000 GA MO 1001-026B-MO 2 16.000 GL MO 1001-028A-MO M-0081-1 E-6 M-0081-1 E-3 2 16.000 GL MO 1001-028B-MO 16.000 GA MO 1001-029A-MO M-0081-1 E-6 1 M-0081-1 E-3 1 16.000 GA MO 1001-029B-MO 16.000 GA MO 1001-034A-MO M-0081-1 E-7 2 M-0081-1 E-3 2 16.000 GA MO 1001-034B-MO GL MO 1001-036A-MO M-0081-1 E-7 2 14.000 M-0081-1 D-3 2 14.000 GL MO 1001-0368-MO 6.000 GL MO 1001-037A-MO M-0081-1 E-7 2 M-0081-1 D-3 2 6.000 GL MO 1001-037B-MO 14.000 GA MO 1001-043A-MO M-0079 B-4 2 M-0079 E-4 2 14.000 GA MO O 1001-043B-MO 1001-043C-MO 1001-043D-MO M-0079 M-0079 B-8 D-8 2 2 14.000 14.000 GA GA MO MO MO M-0081-1 C-4 1 20.000 GA 1001-047 -MO 20.000 GA MO 1001-050 -MO M-0081-1 D-4 1 M-0081-1 F-3 2 1.000 RV SA 1001-059 B-3 2 12.000 CK SA 1001-067A M-0079 M-0079 E-3 2 12.000 CK SA 1001-067B CK SA 1001-067C M-0079 B-9 2 12.000 M-0079 E-9 2 12.000 CK SA 1001-067D 1 16.000 CK AO 1001-068A-AO M-0081-1 E-5 M-0081-1 E-4 1 16.000 CK AO 1001-068B-AO RV SA lv01-125A-RV M-0079 B-5 2 1.000 M-0079 E-5 2 1.000 RV SA 1001-125B-RV 1.000 RV SA 1001-125C-RV M-0079 B-7 2 M-0079 E-7 2 1.000 RV SA 1001-125D-RV CK SA 1001-131 M-0081-1 B-2 2 3.000 M-0081-1 D-8 2 3.000 CK SA 1001-136A CK SA 1001-136B M-0081-1 E-2 2 3.000 M-0079 B-3 2 2.000 CK SA 1001-142A 2.000 CK SA 1001-142B M-0079 E-3 2 M-0079 B-9 2 2.000 CK SA 1001-142C 2.000 CK SA 1001-142D M-0079 E-9 2 Revision 3 VALVES 4-196 9

ik . 3l: ; n " , , ,

                             ' QUAD CITIES NUCLEAR. POWER STATION, UNITS 1 AND 2

(;m INSERVICE TESTING PLAN - VALVES () Table 4.1-2 UNIT 2 VALVE LISTING

}0 DWG            IST     . SIZE            BODY'   ACTU-VALVE NUMBER              P&ID NUMBER              COOR        CLASS      (INCH)            STYLE   ATOR
                  ------------------         ---------------               ----       --u--      ------            -----   ---- .

1001-165A-RV- M-0079 A-2 3 4.000 RV- SA 1001-165B-RV- M-0079 A-10 3 4.000 RV SA' 1001-166A-RV M-0079 A-2 2 1.000 RV SA 1001-166B-RV M-0079 A-10 2 1.000 107 SA' 1101-015 M-0082' C-3 1 1.500 CK :SA-1101-016 M-0082 C-4 1 1.500 CK SA 1101-043A M-0082 D-6 2 =1.500 CK: SA 1101-043B M-0082 E-6 2 1.500 CK SA' 1105- A-RV M-0082 C-7 2 .1.500 RV SA 1105- B-RV M-0082 E-6 ~2 1.500 RV SA 1106- .A M-0082 C-4 2 1.500 .DIA EXP

                  -1106-         B           M-0082                          D-4       2               1.500 DIA            EXP.

1201-002 -MO M-0088 B-6 1 6.000 GA- MO - 1201-005 -MO- M-0088 B-7 1 6.000 GA' MO - 1301-015A M-0089 A-2 1 1.000 XFC-- SA' 1301-015B. M-0089 B-2 1 11.000- XFC SA. 1301-016 -MO M-0089 'B-2 .1 3.000- GA MO 1301-017 -MO M-0089 B-3 1 3.000 GA. MO 1301-040 M-0089 D-3 NC 2.000 CK SA

  '    'E 1301-041                   M-0089                          D-2      NC              8.000        CK      SA~

1301-055 -M-0089 D-3 NC '2.000 SCK SA O 1301-064 1402-003A-MO 1402-003B-MO

                                            .M-0089 M-0078 M-0078 D-2 F-7 F-5 NC 2

2-8.000 18.000 18.000 SCK GAL GA SA MO

                                                                                                                           ~MO 1402-004A-MO              M-0078                           B-8      2             -8.000        GL      MO 1402-004B-MO              M-0078                           C-8      2              8.000        GL      MO 1402-008A                 M-0078                           E-9      2            12'.000 .SCK            SA 1402-008B                 M-0078                           E-6      2            12.000 SCK.             SA 1402-009A-AO              M-0078                           C-3      1            10.000 CK               AO 1402-009B-AO              M-0070                           C-4      1             10.000 CK              AO 1402-013A                 M-0078                            E-10    2             .1.500 SCK            .SA 1402-013B                 M-0078                         ~E-6       2               1.500 SCK-           SA 1402-024A-MO              M-0078                       'B-2          2            10.000 GA              MO-
                   .1402-024B-MO              M-0078                            B-5      2            10.000 GA-             MO-1402-025A-MO              M-0078                            C-2      1            10.000 GA              MO 1402-025B-MO              M-0078                            C-5      1            10.000 GA              MO.

1402-028A-RV M-0078 C-9 2 2.000 RV- SA-1402-028B-RV M-0078 D-6 2 2.000' RV SA-1402-031A M-0078 D-3 1 .750 XFC SA-1402-031B M-0078 D-4 1 .750 XFC: SA-1402-038A-MO M-0078 D-8 2 1.500 GA MO. 1402-038B-MO M-0078 E-7 2 1.500 GA MO 1402-070 M-0078 E-7 2 -1.500 CK SA Revision 3 VALVES 4-197 i

g, QUAD' CITIES NUCLEAR' POWER STATION, UNITS'l AND'2-INSERVICE TESTING PLAN - VALVES Table 4.1-2. UNIT 2 VALVE LISTING DWG IST SIZE BODY ~ ACTU-COOR CLASS (INCH) STYLE ATOR VALVE. NUMBER P&ID NUMBER ----- ------ ----- ....--

                             ------------------                                                                        BTF           AO M-0076-1            D-9            NC           20.000 1601-020A-AO                                 A-9            NC                .001        PLT           AO
                            .1601-020A-AP             M-0076-1                                             .001-       CK-           SA M-0076           A-8             NC 1601-020A-CK1                                A-8             NC               .001        CK            SA
                            -1601-020A-CK2            M-0076-1                                                         BTF           AG.

M-0076-1 E-9 NC 20.000 1601-020B-AO A-9 NC. .001 PLT AO. 1601-020B-AP M-0076-1 .001'oCK SA-M-0076-1 A-8 NC 1601-020B-CK1 A-8 NC .001- CK SA 1601-020B-CK2 M-0076-1 BTF AO 1601-021 -AO M-0076-1 C-6 NC 18.000 M-0076-1 A NC. .001 PLT AO 1601-021 -AP NC .001 CK- SA 1601-021 -CK1 M-0076-1 A-8 M-0076-1 A-8 NC .001 CK SA 1601-021 ~CK2 C-6 NC 18.000 BTF AO 1601-022 -AO M-0076-1 .001 PLT AO M-0076-1 A-9 NC 1601-022 -AP A-8 NC .001 CK 15A

                             -1601-022 -CK1            M-0076-1                                              .001       CK-            SA M-0076-1             A-8              NC 1601-022 -CK2                                 B-3             NC         18.000          BTF            AO
                              '1601-023 -AO            M-0076-1                                              .001 ' PLT                AO M-0076-1              A-9             NC 1601-023 -AP                                  A-8              NC             .001- CK?                ES A -

1601-023 -CK1 M-0076-1 .001 CK SA-1601-023 -CK2 M-0076-1 A-8 NC M-0076-1 B-2 NC 18.000 BTF AO 1601-024 -AO A-9 NC .001 PLT AO O> 1601-024 -AP

                              '1601-024 -CK1 M-0076-1 M-0075-1              A-8               NC             .001       CK            SA M-0076-1              A-8               NC             .001" CK                  SA 1601-024 -CK2                                 D-9               NC        20.000          CK             SA 1601-031A               M-0076-1 M-0076-1             E-9               NC        20.000          CK             SA 1601-031B                                    E-2                NC            .001       CK             SA 1601-032A               M-0076-1                                                         CK              SA 1601-032B               M-0076-1              E-2               NC          -.001 M-0076-1              E-2                NC            .001      CK              SA 1601-032C-                                    E-2                NC            .001       CK             SA 1601-032D               M-0076-1 M-0076-1              E-2:               NC            .001       CK              SA 1601-032E                                     E-3                NC            .001- CK                   SA 1601-032F               M-0076-1 M-0076-1              E-7                NC            .001 CK                    SA 1601-033A                                     E               NC            .001 'CK                    SA.

1601-033B M-0076-1 M-0076-1 E-7 NC .001 CK SA 1601-033C E-7 NC .001 CK SA 1601-033D M-0076-1 M-0076-1 E-7 NC .001 CK SA 1601-033E E-7 NC . 001 CK SA 1601-033F M-0076-1 .001 SO4 SO 1601-050A-SO M-0076-1 D-9 NC M-0076-1 E-9 NC- .001 SO4 SO 1601-050B-SO' C-6 NC .001 SO4 SO 1601-051A-SO M-0076 SO4 SO 1601-051B-SO M-0076-1 C-7 NC .001 M-0076-1 C-2 NC .001 SO4 SO 1601-052A-SO Revision 3 VALVES 4-198 O , l 1

  ,1 l 3wl K'       ,,

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND'2 INSERVICE TESTING PLAN - VALVES

>O- -                                        Table 4.1-2 UNIT 2 VALVE LISTING L

DWG IST SIZE' BODY ACTU-P&ID NUMBER COOR CLASS (INCH) STYLE ATOR-VALVE NUMBER ____ _____ ______ _____ _____ M-0076-1 C-3 NC .001 SO4- SO 1601-052B-SO NC 4.000 GA AO 1601-055 M-0076-1 A-6 SO3' SO ' M-0076-1 A-6 NC .001 1601-055 -SO D-6 NC 18.000 BTF AO 1601-056 -AO M-0076-1 PLT AO. 1601-056 -AP :M-0076-1 A-9 NC .001 NC .001 CK SA 1601-056 -CK1 M-0076-1 A-8 CK SA-M-0076-1 A-8 NC .001 1601-056 -CK2 D-8' NC: 1.000- GL MO 1601-057 M-0076-1 GL. AO 1601-058 -AO M-0076-1 D-7 NC 1.000 M-0076-1 D-7 NC 1.000 GL- AO 1601-059 -AO- E-1 NC 18.000 BTF AO 1601-060 -AO. M-0076-1 PLT. AO 1601-060 -AP ~M-0076-1 A-9 NC .001 M-0076-1 A-8 NC .001 CK. SA 1601-060 -CK1 A-8 NC .001 CK SA 1601-060 -CK2 M-0076-1 1601-061 -AO M-0076-1 F-1 NC 2.000 GL AO M-0076 B-3 NC 2.000 GL AO 1601-062 -AO A-2 NC 6.000 BTF AO

              '1601-063 -AO            M-0076-1 1601-063 -AP            "-0076-1            A-9     NC             .001       PLT                      AO-A-8      NC            .001       CK                       SA 1601-063 -CK1-          M-0076-1 1601-063 -CK2          M-0076-1            A-8      NC            .001       CK                       SA M-0076-1            D-7     NC            .001       SO4                       SO 1601-065 -SO                                D-7     NC            .001       SO3                     -SO M-0076-1 1601-066 -SO.                               D-6     NC             .001      SO3                        SO.

M-0076 - 1601-067 -SO' .M-0076-1; F-1 NC .001 SO4 SO 1601-068 -SO F-1 NC .001 SO3 SO 1601-069~-SO -M-0076-1 M-0076-1 B-3 NC .001 SO3 SO 1601-070 -SO A-3 NC .001 SO4 SO 1601-071 -SO M-0076-1 GA AO 2001-003 -AO. M-0085 F-7 2 3.000 2001-003 -SO M-0085 F-7 NC .001 SO3 SO M-0085 F-7 3 3.000 GA. AO 2001-004 -AO- NC .001 SO3 SO 2001-004 -SO 'M-0085 F-7 GA -AO M-0085 D-4 2 3.000 2001-015 -AO E-4 NC .001 SO3 ' S0-2001-015 -SO M-0085 GA AO

                -2001-016 -AO           M-0085               D-3     2         '3.000 2001-016 -SO           M-0085               E-3     NC             .001      SO3-                       SO 2301-     ' SV
                            -           M-0087               A-7     2         24.000         PLG                        HO 2301-003 -MO           M-0087               A-7     2         10.000         GA                         MO-2301-004 -MO           M-0087               C-9      1        10.000         GA                         MO M-0087               B-10     1        10.000         GA                         MO 2301-005 -MO                                E-6      2        14.000         CK                         AO 2301-007 -AO            M-0087 2301-008 -MO-           M-0087              E-6      2        14.000         GA                         MO M-0087              E-5      2        14.000         GA                         MO 2301-009 -MO                                 E-5     2           6.000        GL                        MO 2301-010 -MO            M-0087 Revision 3                       VALVES 4-199 O
                                                                                               '-                   I  L! I I I II , lu

rI S

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN VALVES Table 4.1-2 UNIT 2 VALVE LISTING
a DWG IST . SIZE LBODY 'ACTU-P&ID NUMBER CCOR CLASS (INCH) STYLE ATOR VALVE NUMBER ____ _____ ______ _____ _____

M-0087 C 2 4.000 GL. MO 2301-014 -MO CK SA 2301-020 M-0087 E-1 2' 16.000 2301-023 -RV M-0087 A-3 2 1.500 RV SA 2301-026 M-0087 D-10 1 1.000 XFC SA D-10 1 1.000 XFC SA 2301-027 M-0087 AO. 2301-028 M-0087 B-9 2- 1.000: GL M-0087 B-9 NC .001 SO3 SO 2301-028 -SO B-10 2 1.000: GL. AO-2301-029 M-0087 ' M-0087 B-10 .NC .001 SO3 SO 2301-029 -SO GL AO 2301-030 M-0087 B-10 NC 1.000 2301-030 -SO M-0087 B-10 NC .001 SO3- SO C-7 1.000 GL SO M-0087 2 j e 2301-032 -SO C-8 2 2.000 CK 'SA. 2301-034 M-0087 " 2301-035 -MO M-0087 E-7 2 16.000 GA MO 2301-036 -MO M-008" E-9 2 16.000 GA- MO 2301-039 M-0057 E-8 2 16.000 'CK- SA : M- O'; 87 D-7 2 4.000 CK - SA 2301-040 24.000 CK SA. 2301-045 M ';087 B-8 2 2301-048 -MO M 0087 B-4 2 4.000 GA MO- ,

                                                ).-0087                E-4                   2                4.000          GA          MO        1 2301-049 -MO          >

4.000 CK- SA i C-5 0 2301-050 2301-051 2301-053 -RV M-0087 M-0087 M-0087 C-5 C-4 A-7 2 2 2 2 4.000 4.000 1.000 CK 107 GL SA SA AO-

1

                                                                                                                                                   -i 2301-064                 M-0087 23 01-064 : -SO          M-0087                 A-6                   NC                 .001 SO3                 SO             .

2301-065 M-0087 A-8' NC 1.000 GL. AO j 1 M-0087 A NC .001 SO3 So

                      -2301-065 -SO                                                                       16.000 RPD                     SA 2301-068                  M-0087                A-6                    2 M-0087                A-6                    2           16.000 RPD                    .SA 2301-069                                                                               2.000 SCK                   SA 2301-071                  M-0087                D-8                    2                                                           ,

M-0087 C-8 2 12.000. SCK .SA- l 2301-074 CK. SA 2301-075 M-0087 B-4 2 4.000 2301-076 M-0087 E-4' 2 2.000 CK SA M-0087 .C-1 2 .750 .CK SA l 2301-108 2.000 CK SA l 2399-005 M-0087 D-8 2 2399-006. M-0087 D-8 2- 2.000 CK SA 2499-001A-SO M-0641-2~ D-6 NC .500 SO2- SO 2499-001B-SO M-0641-2 D-3 NC .500 SO2 So i' M-0641-2 D-6 NC .500- SO2 SO 2499-002A-SO .500 SO2 S0-2499-002B-SO M-0641-2 D-3 NC 2499-003A-SO M-0641-2 B-7 NC .500 SO2 SO 2499-003B-SO M-0641-2 B-2 NC .500 SO2. So

2499-004A-SO M-0641-2 B-6 NC .500 SO2 SO Revision 3 VALVES 4-200 l ( 1 H 1.'b l

 %      T W .,

W 9 'QUADL CITIES NUCLEAR POWER. STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES E i ' Table 4.1-2

UNIT 2 VALVE LISTING

 ^                                                                DWG         IST          SIZE        BODY    ACTU-P&ID NUMBER       .COOR      CLASS      (INCH)          STYLE   ATOR VALVE NUMBER                                ___.      _____    ______            _____   _____

M-0641-2 B NC .500 SO2 SO 2499-004B-SO C-7 NC .500 CK SA 2499-022A- M-0641 CK SA 2499-022B M-0641-2 C-2' NC .500 M-0642-2 .D-5 NC 1.500 GL AO 2599-002A-AO 1.000 SO3 SO 2599-002A-SO M-0642-2 D-6 NC M-0642-2 D-4 NC 1.500. GL AO 2599-002B-AO SO3 SO-2599-002B-SO M-0642-2 D-3 NC .1.000 M-0642-2 C-6 NC 1.000 GL . AO

              -2599-003A-AO                                                                 1.000 SO3-          SO 2599-003A-SO:                 M-0642-2              C-7      NC 1                                                                                        1.000 .GL           AO 2599-003B-AO                  M-0642-2              C-3       NC
                                            -M-0642-2              C-2       NC             1.000 SO3           SO 2599-003B-SO                                                                             GL      AO 2599-004A-AO                 M-0642-2             :F-3       NC             l'.000 M-0642-2              F-3       NC             1.000 'SO3          SO 2599-OO4A-SO                                                                1.C00 GL            AO 2599-004B-AO                 M-0642-2              E-3       NC M-0642-2              E-3       NC              1.000 SO3          SO 2599-004B-SO                                                                 1.000 DIA         .AO 2599-005A-FCV                M-0642-2              F-5       NC M-0642-2              F-5       NC            '1.000       SO3      SO 2599-005A-SO                                                                 1.000 DIA           AO 2599-005B-FCV                M-0642-2              E-5       NC' M-0642-2             E-5       NC              1.000 SO3           SO.

2599-005B-SO 1.000 CK SA' 2599-008 M-0642-2 F-8 NC O 2599-022 2599-023A. 2599-023B M-0642-2 M-0642-2 M-0642-2 A-7 C-6 C-3 NC NC NC 1.500- CK-1.500 CK 1.500 CK SA SA SA M-0642-2 C-6 NC .1.000- CK SA= 2599-024A 1.000 CK SA

               -2599-024B-                    M-0642-2              C-3       NC 2599-998 -RV'             M-0642-2              B-5       NC                .001 RV          SA' M-0642-2              A-6       NC             1.250 CK            SA-2599-999                                                                 4.000 CK            SA 2901-010                  M-0087                D-7       2 3702-         -MO        'M-0075'               B-3       NC              8.000 GA           MO 3703-         -MO-        M-0075'               B-1       NC            .8,000       GA      MO 3706-        .-MO.        M-0073                B-1       11C             8.000 GA           MO M-00'/5                B-3       NC             8.000 CK            SA 3799-031                                                                  8.000 CK            SA 3999-086                  M-Or69-2               A-10      3 M-0069-1               B-9'      3              6.000 CK          =SA 3999-088                                                                  6.000' CK           SA 3999-139                  M 'J069-1              D-99      3 M40069-1               D-7       3              2.500 CK            SA 3999-560                                                                  4.000 CK            SA 3999-561                  ?s-0069-1              D-7       3 4399-045                   M-0058-3              A-4       NC             3.000 GA            M A-4       NC             3.000 CK            SA ,

4399-046 M-0058-3 4699-046 M-0072 E-6 NC 1.000 GL M M-0072' E-6 NC 1.000 CK SA 4699-047 CK SA 4699-123 M-0072 D-10 NC 1.500 = M-0072 D-10 NC 1.500 CK SA 4699-196 Revision 3 VALVES 4-201 O ,

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.1-2 UNIT 2 VALVE LISTING DWG IST SIZE BODY ACTU-VAL', : NUMBER P&ID NUMBER COOR CLASS (INCH) STYLE ATOR M-0072 D-9 NC 1.500 DIA AO 4699-226 .750 RV SA 4699-306A M-0072 Z-99 NC M-0072 Z-99 NC .750 RV SA 4699-306B .750 RV SA 4699-306C M-0072 Z-99 NC M-0072 Z-99 NC .750 RV SA 4699-306D CK SA 4699-307A M-0072 Z-99 NC .500 M-0072 Z-99 NC .500 CK SA 4699-307B SA 4699-309 M-0072 Z-99 NC 1.500 CK M-0072 Z-99 NC .250 SO3 SO 4699-310 RV SA 4711- -RV M-0076-1 D-8 NC 1.500 4720 M-0071-2 D-3 NC 1.000 DIA AO 4721 M-0071-2 D-3 NC 1.000 DIA AO E-2 NC 2.000 CK SA 4799-155 M-0071-2 2.00C CK SA 4799-156 M-0071-2 E-3 NC F-4 NC . 50f > CK SA 4799-158 M-0071-2

                                                                                                                         .500          CK                  SA 4799-159                                 M-0071-2                F-4              NC M-0071-2                B-2              NC                          .500          CK                  SA 4799-281A                                                                                                                   SO3                 SO 4799-482                                 M-0071-2                D-3              NC                           .00.

4799-483 M-0071-2 D-3 NC .00L SO3 SO M-0029 C-6 NC 1.00) CK SA 5199-157 .750 CK SA M-0029 C-6 NC 9 5199-158 5201-5201-

                             -RV
                              -SO M-0029 M-0029 E-4 D-4 NS NS 1.500 1.000 1.500 RV SO2 CK SA SO SA 5299-003                                M-0029                   F-4              NS M-0029                   F-4              NS                       1.500            CK                  SA 5299-005                                                                                                18.000              BTF                 AO 5401-        A-AO                        M-0084-1                E-8              NC A-CK                       M-0084-1                Z-99             NC                           .001         CK                  SA 5401-5401-         A-SO                       M-0084-1                E-7              NC                           .001         SO4                 SO 5401-         B-AO                       M-0084-1                E-8              NC                    18.000              BTF                 AO B-CK                       M-0084-1                Z-99             NC                           .001         CK                  SA 5401-5401-         B-SO                       M-0084-1                E-7              NC                           .001         SO4                 SO 5402-         A-AO                       M-0084-1                D-3              NC                    18.000              GA                  AO A-CK                       M-0084-1                Z-99             NC                           .001         CK                  SA 5402-                                                                                                                                            SO 5402-          A-SO                      M-0084-1                D-2               NC                          .001          SO4 5402-          B-AO                      M-0084-1                D-3               NC                    18.000              GA                  AO B-CK                      M-0084-1                Z-99              NC                           .001         CK                  SA 5402-5402-          B-SO                      M-0084-1                 D-2              NC                           .001         SO4                 SO M-1551                   C-2              3                        2.500            CK                  SA 5799-386                                                                                                                                        SA 743                                     M-0071-2                 B-7              NC                           .375         CK 7503-              -MO                   M-0044                  D-2              NC                    18.000              BTF                 MO 8801-          A-FCV                     M-0076-1                C-3              NC                           .500         DIA                 AO 8801-          A-SO                      M-0076-1                C-3              NC                           .001         SO3                 SO 8801-           B-FCV                    M-0076-1                D-3               NC                          .500         DIA                 AO Revision 3                                          VALVES 4-202 O

l

y 'y

 .r QUAD CITIES NUCLEAR POWER. STATION, UNITS.1 AND 2 INSERVICE TESTING: PLAN - VALVES O                                       Table 4.1-2 UNIT 2 VALVE LISTING DWG      IST      SIZE         BODY        ACTU-VALVE NUMBER            P&ID NUMBER       COOR   CLASS    (INCH)         STYLE       ATOR B-SO         M-0076-1              D-3    NC            . ' e 01  SO3         SO 8801-8801-      C-FCV        M-0076-1              D-3    NC            .500      DIA         AO C-SO        M-0076-1              D-3    NC            .001      SO3         SO 8801-                                                                        DIA 8801-       D-FCV       M-0076-1              E-3    NC               500                AO 8801-       D-SO        M-0076-1              E-3    NC               001    SO3~         SO A-FCV        M-0076-1             C-3    NC              .500. DIA            AO 8802-8802-       A-SO        M-0076-1              C-3    NC              .001    SO3          SO B-FCV'       M-0076-1              D-3   NC            -.500      DIA         AO-8802-                                                                         SO3         SO 8802-       B-SO         M-0076-1              D-3   NC             .001 B402-      C-FCV        M-0076-1              D-3    NC            .500      DIA         AO C-SO         M-0076-1              D-3    NC            .001      SO3          SO 8802-8802--     D-FCV       'M-0076-1              E-3    NC             .500     DIA       -AO
                       -D-SO         M-0076-1              E-3    NC             .001 -SO3             SO 8802--

8803 M-0076-1 D-6 NC .500 GL AO 8803- -SO M-0076-1 C-6 NC .001 SO3 - SO 8803- 1D M-0076-1 D-3 NC .500 GA M

            -8803-     1E             M-0076-1             D-3    NC             .500     GA           M 8803- 1F                 M-0076-1             D-3    NC             .500     GA           M 8803- IG                -M-0076-1             D-3    NC             .500     GA           M 8803- 1H                 M-0076-1             D-3    NC              .500    GA'          M 8803- II-                M-0076-1             D-3    NC              .500    GA           M 8803- 1J                 M-0076-1              D-3   NC              .500    GA=          M 8803 . 1K               M-0076-1              D-3    NC             .500 13A             M M-0076             D-3    NC'            .500 GA             .M 8803- 1L                                                                                 M 8803- lLM               M-0076             D-3    NC             .500 GA 8803- IN                M-0076-1              D-3    NC             .500 GA               M 8803- 10                M-0076-1              D-3    NC             .500 GA               M 8803- 1P                M-0076-1              D-3    NC             .500 GA               M 8803- 1Q                M-0076-1              D-3    NC'            .500 lGA              M 8803- 1R                M-0076-1              D-3    NC             .500 .GA              M 8803- 1S-               M-0076-1              D-3    NC             .500 GA               M 8803- IT                M-0076-1              D-3    NC              .500    CA           M 8803- 1U                M-0076-1              D-3     NC             .500    GA           M 8803- 1V                M-0076-1               D-3    NC             .500    GA           M 8803- 1W                M-0076              D-3    NC             .500    GA           M-8803- 1X               M-0076-1               D-3    NC             .500- GA             M 8803- 'lY               M-0076-1              D-3    NC             .500    GA           M 8803- 2D.               M-0076-1.             D-3    NC             .500    GA           M 8803- 2E                M-0076-1              D-3   HNC             .500    GA           M 8803- 2F                M-0076-1              D-3    NC              .500   GA           M 8803- 2G                M-0076-1              D-3    NC              .500   GA            M 8803- 2H                M-0076-1              D-3    NC              .500   GA            M 8803- 2I                M-0076-1              D-3    NC              .500    GA           M Revision 3                         VALVES 4-203 O

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               'M QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN -' VALVES N_/=                                        Table 4.1-2 UNIT'2' VALVE LISTING DWG        IST          SIZE       BODY 'ACTU-VALVE NUMBER             P&ID NUMBER'        COOR     CLASS         (INCH): . STYLE    ATOR 8803-     2J            M-0076-1                 D-3      NC                 .500 ~ GA    'M 8803-     2K           ~M-0076-1                 D-3      NC                 .500 GA       M 8803-     2L            M-0076-1                'D-3      NC                 .500 GA       M        .l 8803-     2M            M-0076-1                 D-3      NC-                .500 GA      -M          j 8803-     2N            M-0076-1                 D-3     .}U:                .500 GA       M          t 8803-     20            M-0076-1                 D-3      NC-                .500 GA       M           l 8803-     2P            M-0076-1                 D-3      NC                 .500 GA       M 8803-    2Q-           M-0076                D-3      NC                 .500 GA       M 8803-'    2R'           M-0076-l'               .D-3      NC                 .500 GA       M 8803-    2S            M-0076-1                 D-3      NC                 .500 'GA      M-8803-    2T            M-0076                D-3      NC                 .500- GA      M 8803-    20           .M-0076-1                 D-3      NC                 .500 'GA'     M 8803-    2V-           M-0076-1                 D-3      NC                 .500   GA     M 8803-    2W            M-0076-1                .D-3      NC                 .500   GA     M        ]i 8803-    2X.           M-0076-1                 D-3      NC                 .500   GA'    M-         l 8803-    2Y            M-0076-1                 D-3    'NC-               ' .500   GA     M         1 8804                   M-0076-1                 C-6      NC                 .500. GL      A'O        i 8804--      -SO        M-0076-1                 D-6    .NC                  .001   SO3    SO         j 8941-101 -XCV          M-1062                   C-6      NC                 .'500  DIA    AO'        j 8941-101 -XSV          M-1062                   C-6     HNC                 .001   SO3    SO          .
          /~'       8941-705 -XCV          M-1061-1                 C-6      2                  .500   DIA    AO       i

( -8941-705 -XSV M-1061-1. C-7 NC . 2

                                                                                                .001 1.000. DIA SO3    SO.

AO: 8941-709 -XCV M-1061-1 E-5 8941-709 -XSV M-1061-1 E-5 NC . Col SO3 So ! 8941-710 -XCV M-1061-1 D-5 2 1.C00 .DIA AO - ' 8941-710 -XSV' M-1061 D-5 NC . 0 11 SO3- S0-i i

                                                                                                                       ]
                                                                                                                        -i 1
                   . Revision 3                          VALVES 4-204 1
                                                                                                   .i

QUAD CITIES NUCLEAR POWER STATION, t. WITS 1 AND 2 INSERVICE TESTING PLAN - VAL \~ES Table 4.2-1 ACTUATOR ABBREVIATIONS ACTUATOR DESCRIPTION AO AIR OPERATOR DIAPHRAGM, CYLINDER, AND OTHER TYPES OF AIR OPERATORS ?$ EXP EXPLOSIVE ACTUATOR HO HYDRAULIC OPERATOR M MANUAL OPERATOR HAND-WHEEL, CHAIN-WHEEL, AND OTHER TYPES OF NON-POWER OPERATORS MO MOTOR OPERATOR ALTERNATING CURRENT (AC) AND DIRECT CURRENT (DC) ELECTRIC MOTOR OPERATORS O l Revision 3 VALVES i 4-205 l

                                            .l-- . . . .' ' " . ' -     "' . . . - " .

o

      '                           .-QUAD CITIES NUCLEAR POWER STATION, ' UNITS 1 AND 'l
                                          ' INSERVICE TESTING , PLAN -' VALVES Table 4.2-1,

ACTUATOR ABBREVIATIONS ACTUATOR DESCRIPTION SA' SELF-ACTUATING THE DESIGN OF THE VALVE ALLOWS THE VALVE 'TO SENSE SYSTEM' CONDITIONS AND RESPOND' ACCORDINGLY. CHECK, RELIEF, SAFETY,.

AND TRIP VALVES ARE SELF-ACTUATING. w. 1;; __ ._ SAP SELF ACTUATED AND PILOT OPERATED SO SOLENOID OPERATOR h e Revision 3 VALVES 4-206

        ,     o

_ --_. - .- w v t

            )
                         <                                - QUAD. CITIES NUCLEAR. POWER STATION, UNITS 1- AND 2 INSERVICE TESTING PLAN - VALVES.

O-- - Table.4.2-2 BODY STYLE ABBREVIATIONS

                                                -BODY STYLE                                                                                             DESCRIPTION

___ __ -. _-___4

t. BAL BALL VALVE 1 s t

_-_-1 _ _- BTF BUTTERFLY, VALVE

                   .c CK               CHECK VALVE DIA-              DIAPHRAGM VALVE GA                GATE VALVE
                      ;v
                   ,+

1 Revision 3 VALVES l 4-207 l l

.r.

             - QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2
                       . INSERVICE ' TESTING PLAN - VALVES Table . 4 .- 2-2 BODY STYLE ABBREVIATIONS '

BODY STYLE DESCRIPTION

     .GL         GLOBE. VALVE 1
     'PLG         PLUG VALVE g.-

PLT PILOT VALVE RPD RUPTURE DIAPHRAGM RV RELIEF VALVE O , Revision 3' VALVES 4-208

                                                                                                                       ---w-  _
       .i, QUAD CITIES NUCLEAR. POWER STATION, . UNITS 1 AND 2=
                                -INSERVICE TESTING PLAN - VALVES-Table-4'.2-2 BODY STYLE ABBREVIATIONS BODY STYLE                                                                                DESCRIPTION" SCK.        STOP-CHECK-VALVE i

SMR SHEAR VALVE-SO2 SOLENOID VALVE, 2-WAY SO3 SOLENOID VALVE, 3-WAY SO4 SOLENOID VALVE, 4-WAY 9 Revision 3 VALVES 4-209

  -=                 ,            . . . . , . . . , , , - - - - - - - . . . . - - ,                                h

QUAD CITIES NUCLEAR POWER STATION, UNITS l' AND 2

                                  ' INSERVICE TESTING PLAN - VALVES
                                                           -Table 4.2                                                      BODY-STYLE ABBREVIATIONS          ,

BODY STYLE =- DESCRIPTION-SRV DUAL FUNCTION SAFETY / RELIEF VALVE SV SAFETY VALVE XFC EXCESS FLOW CHECK t

 .iL 1

O Revision 3 VALVES l 4-210

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.2-3 FUNCTION CATEGORY ABBREVIATIONS FUNCTION CATEGORY DESCRIPTION A PER IWV-2200(A), CATEGORY A APPLIES TO VALVES FOR WHICH SEAT LEAKAGE IS LIMITED TO A SPECIFIC MAXIMUM AMOUNT IN THE CLOSED POSITION FOR FUFILLMENT OF THEIR FUNCTION. A/C FUNCTION _ CAT 'A' AND 'C' APPLY . PER IWV-2200(B), CATEGORY B APPLIES TO VALVES FOR WHICH SEAT 9 B LEAKAGE IN THE CLOSED POSITION 10 INCO!! SEQUENTIAL FOR FUFILLMENT OF THEIR FUNCTION. [THIS CATEGORY INCLUDES POWER OPERATED VALVES THAT MUST BE EXERCISED OR FAIL SAFE TESTED, AND PASSIVE VALVES THAT DO NOT REQUIRE A SEAT LEAKAGE TEST THAT MUST BE INCLUDED IN THE HRC SUBMITTAL. ] B/C FUNCTION _ CAT ' B' AND 'C' APPLY. C PER IWV-2200(C), CATEGORY C APPLIES TO VALVES WHICH ARE SELF ACTUATING IN RESPONSE TO SOME SYSTEM CHARACTERISTIC SUCH AS PRESSURE (RELIEF VALVES) OR FLOW DIRECTION (CHECK VALVES) 9 Revision 3 VALVES 4-211

                 .. ,- , - . , , , , , - . . . - - - - . . - - - , _ - - - -                           --m                    m                         C

a e QUAD CITIES' NUCLEAR POWER STATION, UNITS 1 AND 2-INSERVICE TESTING' PLAN - VALVES Table 4.2-3 FUNCTION CATEGORY ABBREVIATIONS 1 FUNCTION DESCRIPTION CATEGORY i: , b [, 'D PER IWV-22 00 (D) , CATEGORY D APPLIES TO' VALVES WHICH ARE ACTUATED BY AN ENERGY SOURCE CAPABLE OF ONLY'ONE OPERATION,1 '

                                                                   -SUCH AS RUPTURE DISKS OR EXPLOSIVE ACTUATED VALVES.;:.

py-

                          .    \

1

W k

   -                   c.            .
                                       -f i

4 e y R l Revision 3 VALVES 4-212 O . Y

.,f

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.2-4 NORMAL POSITION ABBREVIATIONS NORMAL POSITION DESCRIPTION C NORMALLY CLOSED C/FC NORMALLY CLOSED, WILL FAIL CIDSED C/FO NORMALLY CLOSED, WILL FAIL OPEN C/KL NORMALLY CLOSED, KEY LOCK ON THE HAND SWITCH IN THE CONTROL ROOM C/LO NORMALLY CIASED, LOCKED OPEN VIA A REMOTE ADMINISTRATIVE POSITION CONTROL SUCH AS A PADLOCK (E.G., A STOP CHECK VALVE)

9 Revision 3 VALVES

4-213

I QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4.2-4

        .                          NORMAL POSITION ABBREVIATIONS NORMAL POSITION-                                   DESCRIPTION-0-        NORMALLY DE-ENERGIZED E         NORMALLY ENERGIZED O         'NORMALLY OPEN O/FC. NORMALLY OPEN, . WILL FAIL CLOSED O/KL      NORMALLY OPEN, KEY LOCK ON THE HAND SWITCH IN THE CONTROL ROOM w

.e. N 2 - Revision 3 VALVES 4-214 1

       . l:                                                                                 .

QUAD CITIES!NUCLIAR-POWER STATION, UNITS 1 AND 2 INSERVICE TESTING :)LAN . - VALVES-O 1 Table 4.2-4

                                                . NORMAL POSITION ABBREVIATIONS NORMAL-POSITION                                    DESCRIPTION SYS '          THE VALVE POSITION IS DEPENDENT ON SYSTEM CONDITIONS
                                          - CHECK VALVES O

Revision 3 VALVES 4-215 O u

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4

            - -. j .

net

                              -QUAD. CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 6              >

INSERVICE TESTING PLAN - VALVES Table 4.2-5 TEST' FREQUENCY ABBREVIATIONS-TEST

                     - FREQUENCY                                  DESCRIPTION
. i. .

CS. . COLD SHUTDOWN, BUT NOT MORE FREQUENTLY THAN ONCE EVERY 91 DAYS. NOTE: NO (0) DURATION IN DAYS IS APPLICABLE'TO THIS (TEST _,FREQ ) LECAUSE IT DOES NOT HAVE A REPETITIVE DURATION. 1 M3 QUARTERLY (ONCE EVERY THREE MONTHS) TESTING 'IS REQUIRED PER TECHNICAL SPECIFICATION TABLE 4.2-3, QUARTERLY IS DEFINED AS ONCE EVERY NINETY-TWO (92) DAYS O, M6- SEMI-ANNUAL (ONCE EVERY SIX MONTHS) TESTING IS REQUIRED PER TECHNICAL SPECIFICATION TABLE 4.2-3, . SEMI-ANNUAL IS DEFINED AS ONCE EVERY ONE HUNDRED EIGHTY-TWO (182) DAYS. NT NOT' TESTED SEE APPLICABLE RELIEF REQUEST OR TECHNICAL APPROACH-AND POSITION RR REACTOR REFUELING NOTE: NO (0) DURATION IN DAYS IS APPLICABLE TO THIS (TEST _FREQ) BECAUSE IT DOES NOT HAVE A' REPETITIVE DURATION.. O Revision 3 VALVES 4-216

                                                                                    .-_n- . .

p

'1

, l QUAD CITIES NUCLEAR POWER STATION,: UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES }f 's . Table 4.2-5 TEST FREQUENCY ABBREVIATIONS

             .a te, TEST                                                                               I
          .             FREQUENCY                                   DESCRIPTION'

[ S2 EXPLOSIVE CHARGE SAMPLE - 20%:EVERY/ REFUELING SB CHECK VALVE DISASSEMBLY GROUP.B./ CVIS. GROUP A16- 3 NOTE: NO (0) DURATION IN~ DAYS.IS APPLICABLE TO THIS (TEST _FREQ) BECAUSE IT-'DOES.NOT.HAVE A REPETITIVE DURATION. !

                                   ~IN ACCORDANCE WITH GENERIC LETTER 89-04,KPOSITION 2,.-ONE'            '!

VALVE IN THIS SAMPLE' GROUP.WILL BE DISASSEMBLED AT'EACH REACTOR REFUELING. l - ; SC -CHECK VALVE DISASSEMBLY GROUP C / CVIS~ GROUP A18 1

      >                             NOTE: NO (0) DURATION IN DAYS IS APPLICABLE TO THIS                     I (TEST _FREQ) BECAUSE:IT DOES'NOT.HAVE-'A REPETITIVE, DURATION..

IN-ACCORDANCE WITH GENERIC LETTER 89-04, POSITION'2, ONE i VALVE IN THIS SAMPLE GROUP'WILL BE DISASSEMBLED AT EACH ' REACTOR REFUELING.

                                                                                                          'i
       ":               SD' CHECK VALVE DISASSEMBLY GROUP D / CVIS GROUP B10
                                   . NOTE: NO (0) DURATION IN DAYS'IS~ APPLICABLE TO THIS (TEST _FREQ}=BECAUSE IT DOES'NOT HAVE A REPETITIVE: DURATION.

IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2',.ONE VALVE IN THIS SAMPLE GROUP:WILL BE DISASSEMBLED AT EACH REACTOR REFUELING., SE' CHECK VALVE DISASSEMBLY GROUP E / CVIS GROUP-B23 -4

    , .          ,                  NOTE: NO (0) DURATION-IN DAYS IS APPLICABLE TO THIS Nis                                   (TEST _FREQ) BECAUSE IT DOES NOT HAVE A' REPETITIVE DURATION.

IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE VALVE'IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH .

REACTOR-REFUELING. I 4 Revision 3 VALVES 4-217

t

                           . QUAD CITIES NUCLEAR POWER STATION,' UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES Table 4~.2-5' TEST FREQUENCY ABBREVIATIONS TEST FREQUENCY-                                                 DESCRIPTION SF          CHECK VALVE DISASSEMBLY GROUP F / CVIS GROUP B25 NOTE: NO (0) DURATION IN DAYS IS APPLICABLE TO THIS (TEST _FREQ) BECAUSE IT DOES NOT HAVE A REPETITIVE DURATION.

IN ACCORDANCE.WITH GENERIC LETTER 89-04, POSITION 2,10NE VALVE IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH REACTOR REFUELING. SG CHECK VALVE DISASSEMBLY GROUP.G / CVIS GROUP B28 NOTE: NO (0) DURATION IN DAYS IS APPLICABLE TO THIS

                               -(TEST _FREQ} BECAUSE IT DOES NOT HAVE A REPETITIVE DURATION.

IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE. VALVE IN.THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH REACTOR REFUELING. SH CHECK VALVE DISASSEMBLY GROUP H / CVIS GROUP B29 NOTE: NO (0) DURATION IN DAYS IS' APPLICABLE TO THIS (TEST _FREQ} BECAUSE'IT DOES NOT HAVE A REPETITIVE DURATION. IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE VALVE IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH REACTOR REFUELING. SI CHECK VALVE DISASSEMBLY GROUP I / CVIS GROUP B30 NOTE: NO (0) DURATION IN DAYS.IS APPLICABLE TO THIS' (TEST _FREQ} BECAUSE IT DOES NOT HAVE A REPETITIVE DURATION. IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE VALVE IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH REACTOR REFUELING. SJ CHECK VALVE DISASSEMBLY GROUP J / CVIS GROUP B36 NOTE: NO (0) DURATION I'N DAYS IS APPLICABLE TO THIS.' (TEST _FREQ) BECAUSE IT DOES NOT HAVE A REPETITIVE DURATION. IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE VALVE'IN THIS SAMPLE GROUP WILL'BE DISASSEMBLED AT EACH REACTOR REFUELING. s Revision 3 VALVES l 4-218

 +     3 e ,

f QUAD CITIES NUCLEAR POWER' STATION,-UNITS 1 AND-2 INSERVICE TESTING PLAN - VALVES Table 4.2-5 TEST FREQUENCY ABBREVIATIONS TEST FREQUENCY DESCRIPTION

                                                                          ---2.

SK CHECK VALVE DISASSEMBLY. GROUP K / CVIS-GROUP Ct , NOTE: NO (0) DURATION IN. DAYS IS APPLICABLE TO TT'

                       '(TEST _FREQ} BECAUSE IT DOES NOT HAVE A REPETI: - T TO J. TION.

IN ACCORDANCE WITH GENERIC LETTER 89-04, POSIT' JOE ), 3NE VALVE IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH REACTOR REFUELING.- SL CHECK VALVE DISASc'MBLY GROUP L / CVIS GROUP C18 NOTE: NO (0) DURATION IN DAYS IS' APPLICABLE TO THIS (TEST _FREQ)-BECAUSE IT DOES NOT HAVE A REPETITIVE DURATION. IN ACCORDANCE WITH GENERIC LETTER 89-04, POSITION 2,.ONE VALVE.IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH: REACTOR REFUELING. SM CHECK VALVE DISASSEMBLY GROUP M / NO CORRESPONDING CVIS NO.

G CVIS NO.0) D?TRATION IN DAYS IS APPLICABLE TO THIS (TEST _FREQ}'BECAUSE IT DOES NOT HAVE.A-REPETITIVE-DURATION. IN'ACCURDANCE WITH GENERIC LETTER 89-04, POSITION 2, ONE VALVE IN THIS SAMPLE GROUP WILL BE DISASSEMBLED AT EACH

                       , REACTOR REFUELING.

Y2 TESTING REQUIRED'ONCE EVERY TWO YEARS TWO (2) YEARS IS DEFINED AS ONCE EVERY SEVEN HUNDRED THIRTY (730) DAYS Y5 TESTING REQUIRED ONCE EVERY FIVE YEARS FIVE (5) YEARS IS DEFINED AS ONCE EVERY ONE THOUSAND EIGHT

                        - HUNDRED TWENTY-SIX DAYS , (1826) , WHICH ACCOUNTS FOR- ONE LEAP YEAR IN THE FIVE YEAR INTERVAL.

O Revision 3 VALVES ! 4-219

J j

  ,       ,                                                                                      1 l'

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 l INSERVICE TESTING PIAN - VALVES

i. Table 4.2-6 l" TEST TYPE ABBREVIATIONS TEST TYPE DESCRIPTION 1 i<*,

    .                                                                                           }

AT-01 TYPE C AIR LEAKAGE - f 10CFR50, APPENDIX J, TYPE C IOCAL LEAK RATE TEST (LLRT) OF :

1. A PRIMARY CONTAINMENT ISOLATION VALVE (CIV). THE VALVE SEAT ,

l"lg. ' LEAKAGE MEASURED DURING THIS. TEST IS INCLUDED IN THE SUM OF l i' THE LEAKAGE VS. O.6 LA EVALUATION. \; y

      .ti                                                            w                          ,

AT-02 XFC LEAKAGE EXCESS FLOW CHECK VALVE SEAT LEAKAGE TEST WILL BE CONDUCTED y IN ACCORDANCE WITH TECHNICAL SPECIFICATION 4.7.D ! J AT-03 PIV LEAKMR PRESSURE IsOIATION VALVE SEAT LEAKAGE SEE NUREG-0677; ANSI /ANS 56.3-1977; EGG-NTAP-6175; NRC GENERIC LETTER 87-06 AND CECO RESPONSES DATED 6/11/87, . l; 11/5/87, 5/18/87 & 2/1/88 . I L AT-05 WW/DW LEAKAGE WETWELL (SUPPRESSION POOL) TO DRYWELL VACUUM SREAKER SEAT > LEAKAGE WETWELL TO DRYWELL VACUUM BREAKER SEA'r JJAKAGE WILL BE J CONDUCTED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 1 4.7.A.4.B.4 - l AT-06 ACCUM. LEAKAGE ~ 1 AIR OPERATED VALVE ACCUMULATOR SEAT LEAKAGE i t Revision 3 VALVES 4-220 __ ]

1 l' 4 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PIAN - VALVES Table 4.2-6 TEST TYPE ABBREVIATIONS TEST TYPE DESCRIPTION BTC EXERCISE CLOSED

FULL STROKE EXERCISE TEST TO THE CLOSED POSITION, AND 4 MEASURE THE STROKE TIME. 1 l

l BTD DE-ENERGIZE FULL-STROKE EXERCISE TEST TO DE-ENERGIZE POSITION l 1 [ ) BTE ENERGIZE F -' FULL-STROKE EXERCISE TEST TO ENERGIZED POSITION. j i BTO EXERCISE OPEN FULL STROKE EXERCISE TEST TO THE OPEN POSITION, AND MEASURE THE STROKE TIME. i. CT-SP SET POINT VERIFY RELIEF VALVE OR SAFETY VALVE SET POINT VERIFICATION TEST i Revision 7 VALVES 4-221 , r ee

i QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PLAN - VALVES

                               .                                              Table 4.2-6

! TEST TYPE ABBREVIATIONS TEST t TYPE DESCRIPTION 1 l CTC CHECK TO CLOSED CHECK VALVE EXERCISE TEST TO THE' CLOSED POSITION ! i l i CTCP CHECK TO PART. CI4SE CHECK VALVE PARTIAL STROKE EXERCISE TEST TO THE CLOSE . POSITION i l l l

    -                                                                                                                                                                                                        I CTO         CHECK TO OPEN                                                                                                                                                                              l i                  CHECK VALVE EXERCISE TEST TO THE OPEN POSITION J

CTOME MECH. EXER. OPEN MECHANICAL EXERCIZE TO THE OPEN POSITION CTOP CHECK TO PART. OPEN l CHECK VALVE PARTIAL STROKE EXERCISE TEST TO THE OPEN l POSITION I l t Revision 3 VALVES 4-222 i I

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 INSERVICE TESTING PIAN - VALVES O' Table 4.2-6 TEST TYPE ABBREVIATIONS TEST ! TYPE DESCRIPTION ! DT-E EXPIASIVE VALVE TEST t eene / DT-M RUPTURE DIAPHRAGM RUPTURE DIAPHRAGM TEST PER MANUFACTURERS RECOMMENDATION i i FST FAIL-SAFE TEST-9 1 PIT POSITION INDICATION A POSITION INDICATION TEST IS USED TO VERIFY THAT THE REMOTE j POSITION INDICATION DEVICE (S) ACCURATELY PROVIDE VALVE ; POSITION INFORMATION. f Revision 3 VALVES 4-223

_ . .-. . . . . . . . . _ - . - .~ ~. . . . . .._-. . - - . . . . - . . . - . - - . - I! *3 a Qutd Citico Nuclcor Pow 3r Staticn, Unito 1 cnd 2 o, INSERVICE TESTING PROGRAM - VALVES

,7. .
     .. {,

Q l I I c-A VALVE AUGMENTED INSERVICE TESTING REQUIREMENTS. ; li s t:

i

          %)>                                                                                                                                                                              '

l-l' l i e L . l , f

       .g i

Revision-3 VALVES 5-1

Quad Citico Nucloor Pswor Station, Unita 1 and 2 3, INSERVICE TESTING PROGRAM - VALVES l 5.0 AUGMENTED INSERVICE TESTING REQUIREMENTS The following augmented inservice testing requirements are being implemented at Quad Cities:

a. Diesel Generator Fuel Oil Transfer does not perform a safety function. Certain Diesel Fuel Oil Transfer valves have been included in the IST Plan at the NRC's request.

b. Reactor Core Isolation Cooling (RCIC) does not perform a safety function, and.no credit is taken for the RCIC system in any UFSAR accident analyses. Certain RCIC valves have been included in the IST Plan at the NRC's request.

O O

     . Revision 3                    VALVES 5-2                            ,

i I Qued citioc Nuclocr.Pcwor StGtion, Unita 1 and 2 INSERVICE TESTING PROGRAM -' VALVES O , l 1 I l l J J l VALVE REFERENCES l 1 1 l l l l

                                                                          . . _                             I I

l l l O Revision 3 VALVES I 6-1

s

t. ~ j ' -p.

f.

   .EL i                        Qutd Citico Nuclo r Psw r Staticn, Unito 1 end 2 INSERVICE TESTING PROGRAM - VALVES t
      ' em -

6.0 REFERENCES

     "           )          The references used to develop this Inservice Testing Program for valves includes u                          a. ASME Boiler and Pressure    Vessel Code, Section XI,              ;

W Division I, " Inservice Inspection of Nuclear Power Plant Components", the 1980 Edition through and including the Winter 1980 Addenda. V

b. ASME/ ANSI OM, " Operation and Maintenance of ,

                ,                      Nuclear Power Plants", including the 1988 Addenda.                ;
   . i-        P                      -Part 10.     " Inservice Testing of Valves in Light-Water Reactor Power Plants"

c. Final Safety Analysis Report, Update 8, Quad Cities Nuclear Power Station, Units 1 and 2 ;

d. Technical Specifications, Amendment 119, Quad ;

Cities Nuclear Power Station, Units 1 and 2 l I 1

                                                                                                      'l 4

1 L ([])

l Revision 3 VALVES i I

6-2

 ._m___-_._______

_ _. _ _ . . .- _ _ .}}

@@ Line 2: / Line 2: @@
 | number = ML20055E810
 | issue date = 07/01/1990
-| title = Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2.
+| title = Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2
 | author name =
 | author affiliation = COMMONWEALTH EDISON CO.

ML20055E810: Difference between revisions

Latest revision as of 17:22, 13 November 2023

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SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

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SUMMARY

SUMMARY

SUMMARY

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SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Reference:

SUMMARY

Reference:

6.0 REFERENCES

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ML20055E810: Difference between revisions

Latest revision as of 17:22, 13 November 2023

Text

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Reference:

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Reference:

6.0 REFERENCES

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