Text

Revs 3 & 4 to Sections 3.0 & 4.0 to Preservice/Inservice Testing Program Plan for Pumps Valves,Respectively
	ML20099G437
Person / Time
Site:	Byron
Issue date:	11/16/1984
From:	Flowers D; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20099G432	List: ML20099G428; ML20099G437;
References
	PROC-841116, NUDOCS 8411270297
	Download: ML20099G437 (95)
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ATTACitENT A ORGANIZATION OF BYRON _1 FIRST 10-YEAR INSERVICE INSPECTION AND TESTING PROGRAM SECTION 1.0 - Introduction SECTION 2.0 - Inservice Inspection Program Plan for Nondestructive Examination SECTION 3.0 - Preservice/ Inspection Testing Program Plan for Pumps SECTION 4.0 - Preservice/ Inservice Testing Program Plan for Valves SECTION 5.0 - Inservice Inspection Program Plan for Component Supports SECTION 6.0 - Inservice Inspection and Testing Program Plan for Snubbers 9447N 8411270297 841116 PDR ADOCK 03000454

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Revision 3 SECTION 3.0 PRESERVICE/ INSERVICE TESTING PROGRAM PLAN FOR PUMPS Prepared by: David F. Flowers i-(0297M)

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Revision 3 Table of Contents 3.0 Preservice/ Inservice Testing Program for Pumps Page 3.1 Program Description 3-1 3.2 Program Tables 3-3 3.3 Notes 3-5 Note 1 " Deleted" Note 2 3-6 Pumps Lubricated by Pumped Fluid 3-6 Note 3 Pump Idle Suction Pressure Note 4 3-6 Diesel Oil Transfer Pump Differential Pressure 3-6 3.4 Relief Requests 3-7 PR-1 Pump Vibration PR-2 3-8 Pump Bearirs Temperatures PR-3 3-11 Essential Service Water Make-up Pumps 3-13 PR-4 " Deleted" PR-5 3-15 Use of Ultrasonic Flowmeters 3-16 l 1

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1 Rt. vision 3 e

3.1 PROGRAM DESCRIPTION l

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Rev. 3 Program Description l

The Pump Preservice/ Inservice Testing Program for Byron Nuclear Power l

Station Unit 1, is implemented in accordance with the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition, through the Winter of 1981 Addenda. Where these requirements are determined to be impractical, specific relief is requested. Additional pump relief requests may be necessary and these will be identified during subsequent inservice tests. The pumps subject to ISI testing are those pumps which are identified in the Byron FSAR as Active, and have an emergency power source. Active pumps are defined as those which are called on to perform a safety function as well as to accomplish ard maintain a safe reactor shutdown. The only exceptions are the diesel driven auxiliary feedwater pump, (1AF01PB), and essential service water makeup pumps, (OSXO2PA, OSXO2PB), which are included in the program, although they are not supplied by an emergency power source.

Pump reference values shall be determined from the results of a preservice test, which may be run during preoperational testing, or from the results of the first inservice test run during power operation.

Reference values shall be at points of operation readily duplicated during subsequent inservice testing. Additional refererece values may be necessary and these will be taken in accordance with IWP-3111 and 3112.

In the event a pump must be declared inoperable as a result of inservice testing, limitations on plant operation will be as stated in the Technical Specifications.

Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of any Technical Specification.

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Revision 3 e

3.2 PROGRAM TABLES 3-(0297M)

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Revision 3 TABLE DESCRIPTION The following informatian is included in the summary tables: ,-

The first four columns include the unique Byron Station Equipment Piece Number, the Pump Name, the Code Class, and the P & ID on which the pumps are located.

Speed :

Speed will be measured by a tachometer for variable speed drives.

Inlet pressure:

Inlet pressure will be measured via permanently installed gauges or other means, provided the equipment accuracy meets the requirements of IWP-4150. This is to be measured both before pump startup and during the test.

Differential pressure:

Differential pressures will be measured using calibrated differential pressure gauges or by recording the difference between calibrated inlet and outlet pressure gauges.

Flow rate: Flow rates will be measured using permanently installed instru-mentation or other means, provided that equipment accuracy meets the requirements of IWP-4150.

Vibration: Vibration measurement shall be made using portable or hand held instruments at locations as marked on the pumps.

l Bearing Temperature: Bearing temperature will be measured by permanently installed deviccs where such devices are present. Portable measurement devices will be used where temperature wells are provided.

Per IWP-3300, bearing temperatures are required only once per year. Byron Station takes the data for bearing temperatures once per year during summer testing.

Test Interval: An inservice test shall be run on each pump nominally every 3 months during normal plant operation, in accordance with IWP-3400.

Lubrication Level: Lubrication level will be observed through sight glasses for the pumps listed in the program.

Revision: The current revision of the program is listed.

Table Page: The table pages are numbered sequentially ard show the total number of pages.

4-(0297M)

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I Revision 3 S

3.3 NOTES i

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NOTE 1 Revision 3

" Deleted" NOTE 2 :

The Diesel Oil Transfer, Residual Heat Removal and Containment Spray pumps cannot be measured for lubrication 1.svel.

hence have no indication for lubrication level.These pumps are lubricated by the fluid pumpe I

NOTE 3 g

These pumps are in a system which is in continuous operation. The idle inlet pressure, therefor e cannot be obtained.

Proper pump operation is assured by continuous parameter s. pump operation as well as quarterly monitoring of the remaining ISI pump NOTE 4 The Diesel Oil Transfer pumps are positive displacement pumps. The pump differential pressure is not a factor affecting pump performance but rather deperdent only on the inlet pressure to the pump. As the pump discharge pressure is constant, and the inlet pressure operational varies with tank level, the differential pressure is not a valid parameter.

For this reason, pump discharge pressure will be used to evaluate pump perfornance in lieu of using pump differential pressure.

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Revision 3 3.4 RELIEF REQUESTS 7

(0297M)

Revision 3 RELIEF REQUEST NO. PR-1

1. PUMF NUMBER: All pumps in the program plari. - '

2. NUMBER OF ITEMS: 23 pumps.

3. ASME CODE CLASS: 2&3

4. ASME CODE, SECTION XI REQUIREMENTS: In r efer ence to Table IWP-3100-2,

" Allowable Ranges of Test Quantities", pump vibration is to be measured in and compared to values given in mils displacement.

5. BASIS FOR RELIEF: The measurement of pump vibration is required so that developing problems can be detected and repairs inii;iated pr for to a pump becoming inoperable. Measurement of vibration only in displacement quantitles does not take into account frequency which is also an important factor in determining the severity of the vibration.

6. ALTERNATE TESTING: The ASME Code minimum standards require measure-ment of the vibration amplitude in mils (displacement).

Byron Station proposes an alternate program of measuring vibration velocity (inches per second) which is more com-prehensive than that required by Section XI. This technique is an industry-accepted method which is much more meaningful and sensitive to small changes that are indicative of devel-l oping saechanical problems. These velocity measurements l

detect not only high amplitude vibration, that indicate a major mechanical problem, but also the equally hartriful low amplitude, high frequency vibration due to misalignment, unbalance, or bearing wear, that usually go undetected by simple displace-i ments measurements.

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(0297M)

I Revision 3 The " General Machinery Vibration Severity Chart" published by IRD Mechanalysis, Inc., (see attached) will he used in place of Table IWP. 3100-2 for the Allowable vibration ranges.

The " Alert Range" will be .314 in/sec i V < .628 in/sec. The required action range will be V 2 628 in/sec. Evaluation of data, to assign equipment to the alert or action ranges, will be done within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> (per IWP-3220 of Section XI). This will be done using industry accepted vibration analysis equipment, such as a full spectrum analyzer.

7. JUSTIFICATION: Measurements of vibration in mils displacement are not sensitive to small changes that are indicative of developing mechanical problams. Therefore, the proposed alternate of measuring vibration amplitude in inches /second provides added assurance of the continued operability of the pumps.

8. APPLICABLE TIME PERIOD:

This relief is requested once per quarter during the first inspection interval.

9-(0297M)

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{ Revision 3 RELIEF REQUEST NO. PR-2

1. PUMP NUMBE_R: OCC01P, ICC01PA, ICC01PB, ICS01PA, ICS01PB,-~

1RHOIPA, 1RH01PB, OSXO2PA, OSXO2PB, 10001PA, 10001PB, 10001PC, 10001PD, OWOO1PA, OWOO1PB

2. NUMBER OF ITEMS: 15 pumps

3. ASME CODE CLASS: 2&3

4. ASME CODE, SECTION XI REQUIREMENTS:

Per IWP-3100, Inservice Test Procedure pump bearing temperatures are required to be measured to detect any change in the mechanical character-istics of a bearing. IWP-3500(b) requires three successive readings taken at ten minute intervals that do not vary more than 3%.

5. BASIS FOR RELIEF:

a. These pumps' bearings are not provided with permanent temperature detectors or thermal wells. Therefore, gathering data on bearing temperature is impractical, b.

The only temperature measurements possible are from the bearirr; housing. To detect high bearzng temperature at the bearing housing would require that the bearings in question be seriously degraded, c.

Measurement of housing temperature on many of these pumps does not provide information on bearing condition or degra-dation. For example, the bearings on the Essential Service Water pumps (OSXO2PA, OSX02PB) and Diesel Oil Transfer Pumps (10001PA, 10001PB, 10001PC, 10001PD) are cooled by the fluid pumped.

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Revision 3 Therefore, any heat generated by degraded bcarings is carried away by the cooling fluid and would not be directly measured at the bearing housing.

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6. ALTERNATE TESTING:

No direct alternate test is proposed for bearing temperatures.

However, measurement of hydraulic parameters and vibration readings do provide a more positive method of monitoring pump condition and bearing degradation.

7. JUSTIFICATION:

By measuring pump hydraulic parameters and vibration velocity, (as described in PR-1), pump operability and the trending of mechanical degradation is assured. Also, since these parameters (i.e., Hydraulic parameters and vibration) are measured quarterly, the pump rachanical condition will be more accurately determined than would be possible by measuring bearing temperature on a yearly basis.

8. APPLICABLE TIME PERIOD:

This relief is requested once per year, during the first inspection interval.

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12-(0297M)

l Revision 3 RELIEF REQUEST NO. PR-3 .

1. PUMP NUMBER: OSXO2PA, OSXO2PB

2. NUMBER OF ITEMS: 2 pumps

3. ASME CODE CLASS: 3

4. ASME CODE, SECTION XI REQUIREMENT: Per IWP-3100, differential pressure shall be measured on all pumps that are tested.

5. BASIS FOR RELIEF: It is impractical to measure the inlet pressures of these pumps. Instrumentation for directly measuring the inlet pressure for these pumps does not exist. These pumps are vertical well type pumps which take a suction from the river screen house forebay.

6.

ALTERNATE TESTING: These pumps will be evaluated using pump discharge pressure.

Additionally, delta level across the traveling screens will be measured to assure adequate suction level.

There is differential level instrumentation provided, which indicates the difference in level between the river height and the reservoir height in inches. This delta level will be recorded in lieu of inlet pressure for the pumps.

7.

JUSTIFICATION: The level of plant safety is not affected by not tak-ing suction pressure data on vertical well type pumps.

These pumps cannot suffer from cavitation as long as their l

impellers are submersed in the pumped fluid reservoir.

Recordino the delta level across the traveling screens ensures that the pumps will be submersed in the river since no other poscible obstructions between the river aruf pump bays exist.

13-(0297M) l 1

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l Revision 3

8. APPLICA8LE TIME PERIOD: This relief is requested once per quarter i

during the first inspection interval. '

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ReJision 3 RELIEF REQUEST NO. PR-4

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Revision 3 RELIEF REQUEST NO. PR-5

1. PUMP NUMBER: OCC01P, ICC01PA&B, 1CV01PA&B, OSXO2PA&B, ISXO1PA&B, ID001PA-D

2. NUM8ER OF ITEMS: 13 pumps

3. ASME CODE CLASS: 2&3

4. ASME CODE, SECTION XI REQUIREMENTS: Per IWP-4120, the full scale range of each instrument shall be three times the reference value or less.

5. BASIS FOR RELIEF: The full scale range of ultrasonic flowmeters, used to collect Section XI flow data, exceed three times the reference value.

6. ALTERNATE TESTING: Ultrasonic ficaneters, with digital readouts and totalizer features will be utilized to obtain Section XI flow data.

t

7. JUSTIFICATION:

Ultrasonic flowmeters provide an accurate means of measuring flowrate. They utilize a digital display whose accuracy is independent of the full scale range. In addition, use of the totalizer feature, and integrating the flow for five minutes provides an accuracy of less than i 1% of the reading. This is well within the requirements of IWP-4110, which refers to an instrument accuracy of f 2% of full scale.

8. APPLICABLE TIME PERIOD: This relief is reauested once per quarter, during the first inspection interval.

16-(0297M) a

INSERVICE TESTING PROGRAM PLAN UNIT 1 ,

CLASS 1, 2, & 3 PUMPS BYRON NUCLEAR POWER STATION REVISION _ _ _ _

TABLE PAGE C 3 1 of 3 L TEST PARAMETERS A

S It'LET DIFF FLOW LUBRI-PLMP NtMBER P(MP NAME BEARING TEST S P & 10 CATION SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL REMARKS 1AF01PA Auxiliary feedwater 2 M-37 No pump Yes Yes Yes PR-1 Yes Quarterly Yes 1AF01PB Auxiliary feedwater 2 M-37 Yes Yes Yes Yes pump (Diesel) PR-1 Yes Quarterly Yes OCC01P Component cooling 3 M-66-3 No Yes Yes PR-5 pump PR-1 PR-2 Quarterly Yes Note 3 1CC01PA Component cooling 3 M-66-3 No Yes Yes PR-5 PR-1 pump PR-2 Quarterly Yes Note 3 ICC01PB Component cooling 3 M-66-3 No Yes Yes PR-5 PR-1 pump PR-2 Quarterly Yes Note 3 ICSO1PA Containment spray 2 M-46 No pump Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 1CSOIPB Containment spray 2 M-46 No Yes pump Yes Yes PR-1 PR-2 Quarterly No Note 2 1CVO1PA Centrifugal charging 2 M-64-3 No Yes pump Yes PR-5 PR-1 Yes Quarterly Yes Note 3 1CVO1PB Centrifugal charging

2 M-54-3 No Yes pump Yes PR-5 PR-1 Yes Quarterly Yes Note 3

INSERVICC TESTING PROGRAM PLAN UNIT 1 CLASS 1, 2, & 3 PUMPS BYRON NUCLEAR POWER STATION REVISION ~

C 3 TABCE PAGE 2 of 3 L TEST PARAMETERS A

S LUBRI-P(MP NUMBER PUMP NAME INLET DIFF FLOW S P & ID BEARING TEST CATION SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL 1RH01PA Residual heat REMARNS 2 M-62 No removal pump Yes Yes Yes PR-1 PR-2 Quarterly No Note 2 1 RHO 1PB Residual heat i 2 M-62 No removal pump Yes les Yes 3R-1 PR-2 Quarterly No Note 2 ISIO1PA Safety injection 2 M-61-1 No pump Yes Yes Yes PR-1 Yes Quarterly Yes ISIO1PB Safety injection 2 71- 6 1 - 1 No pump Yes Yes Yes PR-1 Yes Quarterly Yes ISXO1PA Essential service 3 M-42-1 No Yes water pump Yes PR-5 PR-1 Yes Quarterly Yes Note 3 ISX31PB Essential service 3 M-42-1 No water pump Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 OSX22PA Essential service 3 M-42-6 water makeup pump Yes PR-3 PR-3 PR-5 PR

PR-2 Quarterly Yes '

(Diesel)

OSX22PB Essential service 3 M-42-6 water makeup pump Yes PR-3 PR-3 PR-5 PR-1 PR-2 Quarterly Yes (Diesel) ,

i 1D001PA Diesel oil transfer 3 M-50-1 No Yes No

! pump PR-5 PR-1 PR-2 Quar'erly No Note 2, 4 '

10001PB Diesel oil transfer 3 M-50-1 No Yes No pump PR-5 PR-1 PR-2 Quarterly No Note 2, 4

INSERVICE TESTING PROGRAM PLAN UNIT 1 ,

CLASS 1, 2, & 3 PUMPS BYRON NilCLEAR POWER STATION REVISION TABLE PAGE 3 3 of 3 C

L TEST PARAMETERS A

S LUBRI-PIMP NUMBER INLET DIFF FLOW BEARING TEST CATION PUMP NAME S P & ID SPEED PRES PR.ES RATE VIBRATION TEMP INTERVAL LEVEL REMARKS 10001PC Diesal oil transfer 3 M-50-1 No Yes No PR-5 PR-1 PR-2 Quarterly pump No Note 2 l

10061PD Diesel oil transfer 3 M-50-1 No Yes No PR-5 PR-1 PR-2 Quarterly pump No Note 2 OWOO1PA Control room 3 M-118-1 No Yes Yes Yes chilled water PR-1 PR-2 Quarterly Yes OWOO1PB Control room 3 M-118-1 No Yes Yes Yes chilled water PR-1 PR-2 Quarterly Yes

Revision 4 SECTION 4.0 PRESERVICE/ INSERVICE TESTING PROGRAM PLAN FOR VALVES Prepared by: David F. Flowers 1-

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Table of Contents 1 4.0 Preservice/ Inservice Testing Program Plan for Valves -

Page 4.1 Program Description 4-1 4.2 Program Tables 4-3 4.3 Notes Note 1 Main Steam Isolation valves 4-10 Note 2 CV emergency boration system flowyth valves 4-10 l, Note 3 Main Feedwater Isolation Valves 4-10 hote 4 CV system letdown and make-up isolation valves 4-10 Note 5 RHR pump suction isolation valves 4-10 Note 6 Intersystem 1,0CA valves 4-10 Ncte 7 Reactor Vessel head vent valves 4-11 Note 8 CV. RHR pump discharge check valves 4-11

' Note 9 CV, RHR SCCS check valves 4-11 Note 10 Main Feedwater waterhasumer prevention valves 4-11 I Note 11 VQ Purge Supply ar.d Exhaust Isolation Valves 4-11 Note 12 AF Suction and Steam Generator Check Valves 4-11 Note 13 CV High Head Injection Isolation Valves 4-12 Note 14 SVAG Valves 4-12 1 , 4.4 Relief Requests VR-1 Appendix J valves 4-14 VR-2 Containment spray NaOH additive check valves 4-16

VR-3 Safety Injection ECCS check valves 4-17 3

VR-4 Containment Spray discharge and ring header 4-18 check valves VR-S Accumulator discharge check valves 4-19 -

VR-6 SI pump suction check valve 4-20

{ VR-7 Exemption from timing solenoid operated valves 4-21

, VR-8 Component Cooling RC pump thermal barrier valves 4-22 VR-9 RC pump seal injection CV check valves 4-23 l VR-10 Instrument Air Containment Isolation Valves 4-24 l VR-11 position Indication Test 4-25 l 11-i

I Rev. 4 4.1 PRCCRAM DESCRIPTION J.

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Rev. 4 Procram DescriDtion The Preservice/ Inservice Testing Program for Class 1, 2, & 3 valves meets the requirements of Subsection IW of the ASME Section XI Code.1980 Edition, through the Winter of 1981 Addenda. there code requirements are determined to be impractical, specific requests for relief are written, referenced, and included with the tables.

Additional valve relief requests may inservice be necessary and these will be identified during subsequent rats.

i The tables list all code class 1. 2 & 3 valves which have been YI.

of Section assigned a specific code category as airected by Subsection IW by code cl.+ The tables are c:ganized by system and further identified and code category, using p & ID references.

After installation end prior to service, all valves ~ identified in this program will be tested as required by subsection IW-3100 of Section XI of the ASME Code.

These tests those to be experienced willsubsequent during be conducted undertests.

inservice conditions similar to

' When a valve or its control system has been replaced or undergone maintenance that could affect its performance. it will be retested, prior to its return to service, to demonstrate that all performance parameters are within acceptable limits.

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In the event a valve must be declared inoperable as a result of inservice testing limitations Technical on plant operations will be as stated in the Specifications.

Section XI of the ASME Boiler and Pressure Vessel Code shall not be

construed to supersede the requirements of the Technical Specifications.

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1 E Rev. 4 4.2 PROGRAM TABLES e

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.. l Rev. 4 Table Description The following information is included in the sunsaary tables:

A. SYSTEM

.The system in which a valve is located is denoted by the abbreviated system identification.

B. P & ID The P & ID column references the specific P & ID number and sheet number, which the valves are located on.

C. REVISION 1 The revision corresponds to the current revision of the program.

D. PAGE The pages are numbered sequentially and show the total number of tables.

E. VALVE NUBBER The valve number references the uniaue Byron Station equipment piece

number (EPN). This specific valve number identifies the unit and system.

< F. COORD The coordinates reference a specific location on a particular P & ID. via an X-Y coordinate system.

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c. Cqylg The class refers to the ASME class assigned to the specific valve.

H. VALVE CATEGORY The valve category identifies the valve category defined in subarticle IW-2200 of ASME Section XI.

I. VALVE SIZE The valve size lists the nominal pipe size of each valve in inches. l l

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7. part-Stroke Test (Xt)

If only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercised during plant operation and full-stroke exercised during cold shutdowns, in accordance with IW-3412 or IW-3522.

O. MAX STROKE TIME For power operated valves requiring a full stroke test (St) in order to meet the requirements of IW-3413. the maximum allowable stroke time is specified in seconds. N/A indicates that time is not a factor,affecting valve operability.

p. TEST MODE Denotes the frequency and plant condition necessary to perform a given test. The following abbreviations are used:

Normal Operation (OP) l Tests designated "Op" will be performed once every 3 months, except in those modes in which the valve is not required to be operable.

Cold Shutdown (CS)

Valves that cannot be operated during plant operation shall be full stroke exercised during cold shutdowns. Completion of cold shutdown valve testing is not a prerequisite to plant startup. Valve testings which are not completed during a cold shutdown shall be completed during subsequent cold shutdowns to meet the code specified testing frequency. In case of frequent cold shutdowns, valve testing need not be performed more often than once during any three-month period.

Reactor Refuelino (RR)

Tests with this designation will be conducted during reactor refueling outages only.

i i

7-l

- -_._ _ - - ,- .- ~ - - _ . - _ _ . . _ . - . - _ - - - .

f. Rev. 4 Q. RELIEF REQUEST Relief requirements.

requests reference a specific request for relief from code presentation tables. All relief requests are included immediately following the i

l i

8-i l

O I

Rev. 4 4.3 NOTES 9

9- .

Rev. 4 NOTE I Closure of the Main Steam isolation valves. INS 001A-D. during unit operation would result in reactor trip and safety injection actuation. To avoid this transient, these valves will be partially stroked every three months. Full stroke testing will be done during Mode 4 following, or preceding cold shutdown.

per IW-3412. .

I NOTE 2 The testing of any emergency boration flowpath valves during unit operation is not practical. Stroke testing the Boric Acid injection isolation valve. ICV 8104, and check valve. ICV 8442. the RWST to CV pump suction check valve. ICV 8546. the RH to CV pump suction isolation valve. 1CV8804A. or the RWST to CV pump suction isolation valves ICV 112D.E. could result in boration of the RCS. resulting in a cooldown transient. Aligning the system in this configuration even for a short duration, is therefore, unacceptable. These valves will be strols tested during cold shutdown in accordance with IW-3412.

NOTE 3 These valves are the Main Feedwater isolation valves. IPw009A-D. and cannot be fully stroked during operation as feedwater would be terminated causing a reactor trip. They will, however, be partially stroked tested during operation as well as full stroke tested during cold shutdown per the requirements of IW-3412.

NOTE 4 Closure of these letdown and isakeup valves. ICV 112B. C. ICV 8149A-C, ICV 8105.

ICV 8106. 1CV8152 and ICV 8160 during normal unit operation would cause a loss of

charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactcr trip. These valves will be full stroke exercised durino cold shutdown as required by IW-3412.

NOTE 5 The IRH8701A.B and 1RH8702A.B are the isolation boundary between the Residual Heat Removal pumps and the Reactor Coolant System. Opening one of these valves during unit operation will leave only one valve isolating RHR from the high RCS pressure. This would place the plant in an undesirable condition. Therefore, the valves will be a full stroke tested during cold shutdown, per IW-3522.

N7fE 6 The following valves have been identified as intersystem LOCA valves. They form l a pressure boundary between the RCS and other essential components in order to protect these components from damage. These valves will be leak tested ir, accordance with the Byron Technical Specifications.

Byron Unit 1 Intersystem LOCA Valves IRH8701A.B ISI8702A.B IRH8705A.B ISI8815 ISI8818A-D ISI8905A-D ISI8819A-D ISI8948A-D l ISI8841A.B ISI8949A-D l ISI8900A-D ISI8956A-D 1 1 10-(00077) i l _.- .___ .-. , _ . ._ . . _ _ _ _ _ - - - . . _ -

- - ~_ - - - _ ~ . -

4

Rev. 4 M

The reactor pressure vessel vent valves, 19C014A-D cannot be stroked during unit-operation as they provide a pressure boundary between the Reactor Coolant system and containment atmosphere. Failure of one of these valves in the open position I

would result in leaving only one valve as the high pressure boundary.- These

, valves will be stroked when the BCS pressure is at a minimum during cold shutdown, per IW-3412.

E !

The Residual Heat Removal pump discharge check valves. IRH8739A.B. and the '

4 Centrifugal Charging pump discharge check valves. ICV 8481A.B. cannot be full stroke exercised during unit operation due to the high RCS pressure.. These check i valves will be partial stroke tested, however, on a quarterly basis and full i stroke exercising during cold shutdown. This is in accordance with IW-3522.

lME1 Due to the RCS pressure, the cinck valves listed below cannot be full strok) exercised during unit operation:

l ISI8818A-D Rl5t Cold Leg Injection ,

} ISI8948A-D Ritt/ Accumulator /SI Cold Leg Injection j

ISIS 841A,B RDEt Hot Leg Injection ISI8949A.C RHR/SI Hot Leg Injection ISI8958A.B RWBT to RDEt pump Suction 5

, ISI8815 CV Cold Leg Injection i ISI8900A-D CV Cold Leg Injection

! E l These valves will be full stroke exercised during cold shutdown. in accordance i with IW-3522.

i NOTE 10 l l The IFw039A-D valves cannot be stroke tested during unit operation as closure of '

i these valves would result in termination of the waterhasmer prevention feedwater '

l flow. This would result in undesirable affects on the Steam Generators. These valves will be full stroke tested during cold shutdown per IW-3412.

i

! NOTE 11 l The primary Containment purge Supply and Exhaust Valves. IVQ001A.B. and l IVQ002A.B. cannot be stroke timed during unit operation. These 48 inch valves are the only isolation points between the containment atmosphere and the environment. Stroking these valves at any time ottwr tien mode 5 or 6 would be a

! violation of tim Byron Technical Specifications. These valves will be full i stroke tested during cold shutdown in accordance with IW-3412.

t ;

i NOTE 12

{ The Auxiliary Feedwater clwck valves. IAF001A.B. lAF003A.B. lAF014A-H and ;

1AF029A.B cannot be full stroke tested during unit operation, as this would '

induce potentially damaging thermal stresses in the upper feedwater nozzle piping. The 1AF001A.B and IAF003A.B valves will be partially stroke tested ;

during operation, and all valves full stroke tested during cold shutdown. This '

will be performed per Tech. Spec. 4.7.1.2.2 and is in accordance with IW-3522.

l 11- i (00077)

I

1 N'V- 4 NOTE 13 The High Head Injection Isolation Valves. ISIB801A.B. cannot be si.roke tested during unit operation. These valves isolate the CV system from the RCS. Opening them during operation would enable charging flow to pass directly into the RCS, bypassing the regenerative heat exchanger. The temperature difference of the charging flow and the ?tCS could result in damaging thermal stresses to the cold leg nozzles as well as causing a reactivity change which would, in turn, cause a plant transient. These valves will be full stroke tested during cold shutdown in accordance with IW-3412.

NOTE 14 The safety injection system SVAG (Spurious Valve Actuation Group) valves cannot be stroke tested during unit operation. These valves are required by the Technical Specifications to be de-energized in their proper positions during unit operation. Stroking them would be a violation of the Technical Specifications as well as defeating the de-energized SVAG valve principle. These valves will be stroked tested during cold shutdown when they are not required to be de-energized. This is in accordance with IW-3412.

I e

i i

I l

12-(0007T) l ~ - - --- - - . ._ __ _ _ _ _ _ _

k,,

Rev. 4 4.4 RELIEF REQUESTS -

p 4

13-u

VR-1 Rev. 4

1. Valve Number:

All primary containment isolation valves in this program are listed as Category A:

VALVE # VALVE 4 VALVE #

1) ICC685 45) IPS9354A 89) IVQOO2A

2) ICC9413A 46) IPS93548 90) IVQOO2B

3) ICC9414 47) IPS9355A 91) IVQOO3

4) ICC9416 48) IPS93558 92) IVQ004A

5) ICC9438 49) IPS9357A 93) IVQOO4B

6) ICC9486 50) IPS9357B 94) IVQ005A

7) ICC9518 51) IPS9356A 95) IVQOOSB

8) ICC9534 52) IPS93568 96) 1VQ005C

9) ICS007A 53) 1RE9159A 97)

10) ICS007B IVQOl6

54) 1RE91598 98) IVQOl7

11) ICS008A 55) 1RE9160A 99) IVQOl8

12) ICS0088 56) 1RE91608 100) IVQOl9

13) ICV 8100 57) 1RE9157 101) IWM190

14) icv 8112 58) 1RE9170 102) IWM191

15) icv 8113 59) 1RE1003 103) IWOOO6A

16) ICV 8160 60) 1RF026 104) IWOOO68

17) icv 8152 61) 1RF027

' 105) IWOOO7A

18) IFC009 62) 1RY8026 106) IWOOO7B

19) IFC010 63) 1RY8025 107) IWo020A

20) IFC011 64) 1RY8028 108) IWOO20B

21) IFC012 65) 1RY8046 109) IWOO56A

22) IIA 066 66) 1RY8047 110) IWOOS6B

23) IIA 065 67) 1RY8033 111) IPR 002E

24) IIA 091 68) ISA033 112) IPR 002G

25) 10G057A 69) ISA032 113) IPR 033A

26) 10G079 70) ISD002A 114) IPR 033B

27) 10G080 71) ISD002B 115) IPR 002F

28) 10G081 72) ISD002C 116) IPR 002H

29) 10G082 73) ISD002D 117) IPR 033C

30) 10G083 74) ISD002E 118) IPR 033D

31) 10G084 75) IS0002F

32) 10G085 76) ISD002G

33) IPR 001A 77) ISD002H

' 34) IPR 001B 78) ISD005A

35) IPR 066 79) ISD0058

36) IPR 032 80) ISD005C

37) IPS228A 81) ISD005D

38) IPS2208 82) ISI8888

39) IPS229A 83) ISI8880

40) IPS2298 84) ISI8871

41) IPS230A 85) ISI8964

42) IPS2308 86) ISI8968

43) IPS231A 87) IVQ001A

44) IPG231B 88) IVQ001B i

14

1 Rev. 4

2. Number of Items: 118.

3. ASME Code Cateoorv: A.

4. ASME Code.Section XI Requirements:

Seat Leakage Measurement per IW-3420.

5. Basis for Relief:

Primary containment isolation valves will be seat leak tested in accordance with 10 CFR 50. Appendix J. For these valves.Section XI testing requirements are essentially equivalent to those of Appendix J.

6. Alternate Testino:

Primary containment isolation valves will be seat leak tested in accordance with the Appendix J requirements of 10 CFR 50,

7. Justification:

No additional information concerning valve leakage would be gained by

performing separate tests to both Section XI and Appendix J. Therefore,

, overall plant safety is not affected.

8. Applicable Time Period:

i This interval.relief is requested once per year during the first inspection i

I -

t 15-

_, . - , - .-.r-, -- -- .-< w - - - -- --

VR-2 Rev. 4

1. Valve Number: ICS020A .

ICS0208

2. Number of Items: 2

3. ASME Code Cateoory: C

4. ASME Code,Section XI Requirements:

Exercise for operability (Ct) of check valves every 3 months. per IW 3521.

5. Basis for Relief:

The check valves in the spray additive system cannot be stroked without introducing NaOH into the CS system.

6. Alternate Testino:

These valves will be dismantled each refueling outage in order to demonstrate operability. In addition to this, they will be full flow tested once every five years. The full flow test will be performed in lieu of dismantling the valves.

7. Justification:

This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant by testing the valves as often as is safely possible.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspecticn interval.

I l 16-

l 1

VR-3 Rev. 4

1. Valvt Number: ISI8905A-D ISI89498.D -

ISI8819A-D ISI8922A.B

2. % d f Items: 12

3. ASME Code Catet.p n : AC & C

4. ASME Code.Section XI Requirements:

Exercise for operability (Ct) of check valves every 3 months, per IW-3521.

5. Basis for Relief:

These check valves cannot be full flow tested during operation as the shutoff head of the Safety Injection pumps is lower than the reactor coolant system pressure, performance of this test with the RCS

depressurized, but intact could lead to inadvertent overpressurization of the system. The alternate method of protecting against overpressurization by partially draining the RCS to ptovide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.

6. Alternative Testino:

i These valves will be full stroke tested during cold shutdowns provided the reactor vessel head is removed. The testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.

7. Justification:

This alternative will adequately maintain the system in a state of operational readiness while not sacrificing the safety of the plant. by testing the valves as often as safely possible.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval. '

17-4

VR-4 Rev. 4

1. Valve Number: ICS008A. B ICS003A, B ~

2. Number of Items: 4

3. ASME Code Catocory: AC & C

4. ASME Code.Section XI Requirenents:

Exercise for operability (Ct) of check valves every 3 months, per IW-3521.

5. Basis for Relief:

The ICS008A. B and ICS003A. B valves cannot be full flow tested during unit operation as water from the CS pumps would be discharged through the CS ring headers causing undesirable effects on system components inside containment.

6. Alternate Testing:

The ICS008A. B valves will be partial stroke tested, using air on a quarterly basis and full flow tested. or dismantled to demonstrate operability, each refueling outage. The ICS003A. B valves will be partial

, stroke tested during the quarterly pump surveillance and dismantled, to demonstrate operability, each refueling outage.

l

7. Justification:

Partial stroke testing of the ICS008A. B check valves, using air. is an adequate means to demonstrate operability. Positive verification of disk movement will be accomplished by noting the rush of air of through the test connection. Performance of a partial stroke test. during the CS pump quarterly surveillance, on the ICS003A. B check valves will ensure adequate check valve operation.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

l 18-l i

_ _ _ _ _ . _ _ __ _ _ _ _ - -~

VR-5 Rev. 4

1. Valve Number: ISI8956A-D

2. Number of Items: 4

3. ASME Code Cateoory: AC

4. ASME Code.Section XI Requiroments:

Exercise for operability (Ct) of check valves every 3 months. per IW-3521.

5. Basis for Relief:

The acetanulator check valves cannot be tested during unit operation due to the pressure differential between the accumulators (650 psig) and *he reactor coolant system (2235 psig). Full stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system.

6. Alternate Testing:

These valves will be partial stroke tested during cold shutdown by providing a surge volume in the pressurizer and " burping" the accumulator discharp isolation valves. positive verification of valve operability will be by noting a change in accumulator level.

7. Justification:

This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

l 19-(0007T) l

VR-6 Rev. 4

1. Valve W r: ISI8926

2. Number of Items: 1

3. MBE Code Cateoory: C

4. ASME Code.Section XI Requirements:

Exercise for operability (Ct) of check valves every 3 months, per IW-3521.

5. Basis for Relief:

Full stroke exercising of the Safety Injection pump suction check valve.

ISI8926, cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full flow injection conditions. performance of this test with the reactor coolant system system.

intact could lead to an inadvertent overpressurization of the The alternate method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate i water level above the reactor core.

6. Alternate Testino:

The ISIE926 valve will be partia* stroke tested during periodic inservice tests with the SI pumps in the recirculation mode.

for the valve will be done during cold shutdown, providing the reactorFull stroke vessel head is removed. This testing frequency will be each refueling j

outage as a minimum, but no more frequently than once per quarter.

) "J . Justifiestion: '

> This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant. by s

testing the valves as often as safely possible.

8. Applicable Time Period:

This interval.relief is requested once per quarter during the first inspection i.

I 20-t l

i

VR-7 Rev. 4

1. Valve % r

IPS228A B IRC014A-D IPS229A. B ISX101A IPS230A, B

2. Number of Items: 11

3. ASIE Code Catacory: A&B

4. ASME Code Section Reaulraments:

Stroke timing (St) of power operated valves per IW-3411.

5. Basis for Relief:

Stroke timing of Solenoid operated valves is impracticle due to the fast actuation of these valves.

6. Alternate Testino:

The PS and SX valves will be demonstrated operable by quarterly full stroke testing and fail testing.

The RC valves will be tested in accordance with Note 7.

7. Justification:

Proper valve operation will be demonstrated by verifying that the valves stroke to their required positions.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

i 21-

1 l

l I

l l

l VR-8 Rev. 4

1. valve

W r: ICC645 1CC9438 1CC9413A. B ~

ICC9414 1CC9416

2. Ember of Itens: 6

3. M Code C3 tea 9_tY: A <

4. ASfE Code,Section XI Reauirements:

Exercise for operability (St) of Category A and 8 valves every 3 months, per IW -3411.

5. Basis for Relief:

Component cooling water flow to the reactor coolant pumps is required at all times while the pumps are in operation and for an extended period of time while in cold shutdown. Failure of one of these valve:2 in a closed position during an exercise test would result in a loss of cooling flow to the pumps and eventual pump damage and/or trip.

6. Alternate Testina:

These valves will be exercised during cold shutdown. provided all of the reactor coolant pumps are not in operation. This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.

7. Justification:

This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.

8. Applicable Time period:

1 This relief is requested once per quarter during the first inspection j interval.

f l '

l l

1 l

22-

VR-9 Rev. 4

1. Valve Number:

ICV 8100 -

ICV 8112 l

2. Number of Items: 2

3. ASME Code cateoorv: A .

4. @ Code.Section XI Requirements:

Exercise for operability (St) of Category A & B valves every 3 months per IW-3411.

5. Basis for Relief:

These valves cannot be tested during unit operation as seal water flow to the reactor coolant pumps is required at all times while the pumps are in operation. Failure of one of these valves in the closed position during an exercise test would result in seal water return flow being diverted to l the PRT by lifting a relief valve upstream of the isolation valves.

6. Alternate Testino:

These valves will be exercise tested during cold shutdown, providing all reactor coolant pumps are not in operation. This testing period will be

each refueling outage as a minimum, but no more frequently than once per j quarter.

7. Justification:

This alternative will adequately maintain the system in a state of 4

operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.

8. Applicable Time Period:

This relief is requested once per quarter during the first inspection interval.

i 4

4 23-I

. _ _ . _ - - - _ . _ _ _ _ , _ _ . _ __ _ _ _ _ _ _ _ - _ - - ~ - __ _ _ _ _ _ _ . . _ _ . _ _ . _ _ - .

. l l

VR-10 Rev. 4 !

1. Valve thaber: IIA 066 IIA 065 -

2. Number of Items: 2

3. ABE Code Cate.gggy: A

4. ASfE Code,Section XI Reautrements:

Exercise for operability (St and Ft) of category A and a valves overy 3

months per IW-3411.

5. Basis for Relief:

Stroke testing of these valves during plant operation would isolate the air operated instruments and valves inside the contairunent building.

a

6. Alternate Testina:

1, These valves will be exercised during cold shutdown, providing that all ;

necessary equipment required for cold shutdown operations would not be ;

1 affected. '

This testing period will be each refueling outage as a minimum, but no ;

j more frequently than once per quarter. i.

7. Justification:

Stroke exercising of these valves would be impractical because if these valves failed in the close position during unit operation instrumentation i

i would not function properly and valves would stroke to their failure position, causing the loss of support equipment and possibly a reactor

! trip. This alternative will adequately maintain the system in a state of

} operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.

l 8. Acolicable Time Period:

)

l This relief is requested once per quarter during the first inspection !

j interval. '

I

~

I I

i

i

( l 24-i J

~. ._._,.___-_._....,_m._.,__.- . _ _ _ _ . _ _ - . . . . . _ . . . _ _ - , . _ _ _ _ _ _ _ , , _ _ _ . . _ . . . _ _ , _ _ _ - . _ _ _ . . ,

l 4

VR-ll Rev. 4

1. Valve Number: All valves subject to Travel / Position Indication Test

2. Number of Items: 183

3. AalE Code Cateaory: A&B

4. ASIE Code.Section XI Requirenents:

Observation of remote position indicators once every 2 years to verify that the valve operation is accurately indicated per IW-3300.

5. Basis for Relief:

Position indication checks are required once every two years.

Historically, plants have been on a one year refueling cycle and thus, performed this test every other refueling outage. Therefore, the intent of the code appears to be that the test be executed every other refueling outage.

Byron Station. however, is on an 18 month refueling cycle.

Executing a position indication test by either coming down in power or every refueling outage is not practical. Increasing the frequency of testing in radiation areas, would increase personnel exposure by as much as 25% over plants on a two year refueling cycle.

+

6. Alternate Testing:

Position / Travel indication examinations will be performed on a frequency of outage.

approximately once every 3 years, or once every other refueling All active power operated valves (except 50V's) listed in the ISI Valve Program will be stroked timed. For valves with remote indication.

timing is done remotely. This time is then recorded in a procedure which trends the stroke time of each valve. If the maximum stroke time for the valve is exceeded, a local stroke timing of the valve will be initiated.

provided AIJutA concerns allow such a test. If the local time varies by more than 20% or 1 second, whichever is greater. from the remote time, the limit switches will be adjusted accordingly.

7. Justification:

Position indication tests executed on a frequency of once every 3 years, along with a case by case investigation of Position / Travel Indication discrepancies, will adequately maintain the system in a state of operational readiness. In addition to this, radiation exposure levels for personnel will be greatly reduced.

8. Applicable Time Period:

i '

This inspection relief is requested every refueling outage during the first interval.

i 25-(0007T)

-l N At Ill EDISON INSERVICE ~TE511NG PRdCiAM ISI Cl ASS 1, 2 aruf 3 VALVES '

BYRON NUCLEAR POWER STAIION UNIT 1 SYSit M Ad P & 10 REVISION PAGE 4 g of 47

ALVE val.VE VALVE VALVE ACT.

MUMBE3 CDORD C1 ASS NORMAL STRONE MAX.STRONE IEST CATEGORY SIZE TYPE TEST RELIEF REMARKS 1YPE POSITION DIRE CT . TIMF MEIHOD MODE (IN ._ ) NfQUEST (SEC.)

~

PAGE DfLETED l

_M-' __w, l

l l

t l

l O

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0118 9 *

.~

INSERVICE 1ES11NG PROGRAM COPTIONWE A! IH F DISON ISI CLASS 1, 2 and 3 VALVLS BYRON NUCLFAR POWER STATION UNIT I SYSlEM At P & 10 REVISION PAGE M-37 4 2 of 47

' VALVE VALVE VALVE VALVE ACT.

NUrtbE M COORD CIASS NORMAL SIROKE MAX.STR$E TEST CATEGORY SIZE TYPE TYPE 1EST RELIEF REMARKS POSIIION DIRECI. 11ME (IN.) (SEC. )

MEIHOD f100E REQUEST IMOOlO D-2 3 C 6.0 CK S.A. C O N/A CL CS Note 12 1M oolB B-2 3 XL OP C 6.0 CK S.A. C

_ O N/A Ct CS Note 12 Inito34 D-5 3 C 6.0 CK' XL OP S.A. C O N/A Ct CS Note 12 1AFOO3B B-5 Xt OP 3 C 6.0 CK S.A. C O N/A Ct CS Note 12

'IM OO64 E-3 3 8 6.0 XL OP CA M.O. C O 15.0 St OP IM OOb8 B-3 3 8 lt RR VR-Il 6.0 GA M.O. C O

__ 15.0 St OP

'1AfCl4A C-8' 2 C 4.0 CK S.A.

It RR VR-11 C O N/A Ct CS Note 12 IM C148 A-8 2 C 4.0 CK S.A. C O N/A CL CS Note 12 l

l l

l 6

l

['

C(X't10NWEAllit iDISON INSERVICE 1ESTING PROGRAM ISI CLASS 1, 2 aruj 3 VALVLS UNIT 1 BYRON NUCLEAR POWER STAR ON SYSitM Af P & ID REVISION PAGE M-37 4 3 of 47

'vnt VE VALVE VALVE VALVE ACT. NORMAL NUMhER COORD CIASS STRONE MAX.STROME TEST 1EST CAILGORY SIZE TYPE TYPE RELIEF REMARNS POSITION DIRE CT. TIME MEIHOO (IN.) (SEC.)

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VALVE 10 of 47 VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORMAL CATECORY SIZE TYPE TYPE STROKE MAX STROKE TEST TEST RELIEF POSITION DIRECT. REMARKS (IN.) TIME METHOD MODE REQUEST ICV 8481A C-4 2 C (SEC.)

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COMMONWLAllit EDISON ISI CLASS 1, 2 aruf 3 VALVES BYRON NUCLEAR POWER STATION UNIT I SYSIEM CV P & 10 REVISION PAGE M-64-5 4 12 of 47 VALVE ,

VALVE VALVE VALVE ACT.

NUMBER COORD C1 ASS NORMAL STROKE MAX. STROKE TEST CAIEGORY SIZE 1YPE 1ESE RELIEF REMARKS TYPE POSITION DIRECT, TIME ME1 HOD

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" VALVE 16 of 47 VALVE VALVE VALVE NUMBER COORD ACT. NORMAL CLASS CATEGORY SIZE STROKE MAX. STROKE TEST TEST TYPE TYPE RELIEF REMARKS (IN.) POSIf10N DIRECT. TIME ME.lH00 MODE If WOO 9A 0-5 REQUEST 2 8 16.0 GA (SEC.)

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COMMONWEAtlli EDISON INSERVICE TESilNG PROGRAN ISI Cl. ASS 1, 2 aruf 3 VALVES BYRON NUCIEAR POWER ST,ATION UNIT 1 SYSIEM 1A P & 10 REVISION M-55-2 PAGE 4

1/ of 47

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VALVE NUMBER VALVE VALVE VALVE COORD CLASS ACT. NORMAL CAIEGORY SIZE TYPE TYPE STRONE MAX.STRONE TEST 1EST RELIEF (IN.) POSITION DIRLCT. TIME METHOD REMARKS 1I0066 E-7 2 MODE REQUEST A 3.0 CL A.O. O (SEC.)

C 15.0 Lt RR VR-1 St CS VR-lO 110065 Ft CS VR-10 E- 6 2 A 3.0 GL A.O. O It RR VR-il C 15.0 Lt RR VR-1 St CS VR-10 ft CS VR-lO IIA 091 F-7 2 It A 0.75 CK S.A. C RR VR-il C N/A Lt RR VR-1 Passive O

COMMONWEAllit LDISON INSERVICE IL5T]NG PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSIEM MS P & ID REVISION PAGE M-35-1 4 VALVE 18 of 47 VALVE VALVE VALVE ACT.

NUMHER COORD NORMAL CLASS CAIE(X)RY SIZE TYPE S1ROKE MAX. STROKE TEST TEST RELIEF TYPE POSIFION DIRECT. REMARKS TIME .hEfH00

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INSERVICE TESTJNG PROGRAM COMMONWt Al.Ill EDISON ISL CLASS 1, 2 aruj 3 VALVES DYRON NUCLEAR POWER S1AIION UNIT I SYSILM MS P & ID R1 VISION PAGI M-35-2 4 19 of 47 VALVE VALVE VALVE VALVE ACT.

NUMilE R COORD NORMAL STROKE MAX. STROKE TEST CLASS CalEGORY SIZE TYPE TYPE lEST RELIEF REMARKS POSITION DIRECT. TIME MEll100 (IN.) NODE REQUEST QEC.)

INS 00ln C-4 2 St/Xt CS/0P B 30.25 GA 11. 0 . O C Note 1 5.0 It RR VR-11 IrrdolC E-4 2 8 32.75 SL/XL CS/0P Note 1 GA' H.O. O C 5.0

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_ _ . _ . - - N/A Rt RR IMS0144 f-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR INS 014C F-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IMSol5A F-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IMSolSC F-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt ER IM50164 I-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IMSolbC t-3 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IMS01/n F-2 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IMS01/C F -2 2 C 6.0X10.0 SV S.A. C 0 N/A Rt RR IM3101A C-4 2 0 4.0 GA St OP A.O. C C 10.0 s -- - It RR VR-Il Passive IMS101C E-4 2 B 4.0 St OP

- CA A.O. C C 10.0 It

- . _ . _ RR VR-Il Passive IMS0183 D-1 2 C 8.OX10.0 PORV M.0, C C 20.0 St OP IMSol8C t -1 It RR VR-11 2 C '8.0X10.0 PORV N.O.

Passive C C 20.0 St OP It RR VR-Il Passive i

C0ftK)NWf Allit EDISON INSERVICE 1ESTING PROGRAM ISI CLASS 1, 2 ard 3 VALVES BYRON NUCLEAR POWER STATION UNIT I SYSifM OG P & ID REVISION ._

PAGE M-47-2 4 untVE 20 of 47 VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORMAL CATEGORY SIZE TYPE TYPE STROKE MAX. STROKE TEST TEST RELIEF POSIT' ION DIRECT. TIME REMARKS 10G057A E-6 (IN.) METHOD MODE REQUEST 2 A 3.0 BTF (SEC.)

M.O. C C 60.0 Lt RR VR-1 Passive St OP 10G0/9 L-6 2 A 3.0 .DIF M.O. C It RR VR-Il C 60.0 Lt RR VR-1 Passive St OP 10C080 E-S 2 A 3.0 BIF M.0. C It RR VR-Il C 60.0 Lt RR VR-l Passive St OP 10C081 D-5 2 A 3.0 Bif M.0. C It RR VR-il C 60.0 Lt RR VR-1 St Passive 10C082 OP E-6 2 A 3.0 It RR BTF M.O. C C VR-11 60.0 Lt RR VR-1 St Passive OP 10G083 0-6 2 It A 3.0 DIF M.O. C C RR VR-Il 60.0 Lt RR VR-1 Passive St OP 10G084 E-4 2 A 3.0 BTF M.0. C It RR VR-ll C 60.0 Lt RR VR-1 Passive St OP 10G085 D-4 2 A 3.0 HIF M.0. C It RR VR-Il C 60.0 Lt RR VR-1 Passive

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COMMONWE AL ill EDISON INSERVICE TISIING PROGRAN ISI CL ASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSTEM PR P & ID REVISION PAGE M-78-6 4

' VALVE 21 of 47 VALVE VALVE VALVE NUMBER COORD ACT. NORMAL CL ASS CATEGORY SIZE STROKE MAX.SIROKE IEST TYPE TYPE TEST RELIEF REMARKS (IN.) POSII1ON DIRECT. TIME MEiH00 MODE IPR 00?E REQUEST C-5 2 A 2.0 (SEC.)

Gl M C C N/A Lt IPR 002G RR VR-1 Passive C-5 2 A 2.0 CK S.A. C C N/A Lt IPR 033A NR VR-1 C-8 2 A 2.0 Passive GL M C C N/A Lt IPR 0338 RR VR-1 C-8 2 A 2.0 Passive GL M C C N/A Lt IPR 00?f RR VR-1 C-5 2 A 2.0 Passive GL M C C N/A Lt IPR 002if RR VR-1 Passive C-5 2 A 2.0 CK S.A. C C N/A Lt RR IPR 033C C-8 VR-1 Passive 2 A 2.0 Gt M C C N/A Lt RR VR-1 IPR 033D C-8 2 Passive A 2.0 GL M C

--- C N/A Lt RR VR-1 Passive

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C0rNONWf ALIll EDISON INSERVICE TESTING PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION HNIT I SYSTEM PR P & ID REVISION PAGE M-78-10 4

' VALVE 22 of 47 VALVE VALVE VALVE NUMffLR COORD ACT. NORMAL C1 ASS CATECORY SIZE SlROKE MAX. S TROKE TESI TYPE TYPE TEST RELIEF REMARKS (IN.) POSIIION DIRECT. TIME MEIHOD MODE 1PR001A F-7 REQUEST 2 A 1.0 GL A.O. (SEC.)

O C 4.5 Lt RR VR-1 Ft OP St OP IPROO!B F- 8 2 A 1.0 GL A.O. O It RR VR-Il C 4.5 Lt RR VR-1 Ft OP St OP IPR 066 E-2 2 lt A 1.0 GL RR VR-11 A.O. O C 5.0 Lt RR VR-1 ft OP lt RR VR-11 IPR 032 E-I 2 A 1.0 St OP CX S.A. C C N/A Passive 6-O

COM10NWEAllit EDISON INSERVICE TESTING PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEOR POWER STATION UNIT 1 SYSTEM PS P & 10 REVISION \

PAGE M-68-1 4 Val VE 23 of 47 VALVE VALVE VALVE EUMUI R COORD ACT. NORMAL CL ASS CAIEGORY SIZE STROKE MAX. STROKE TEST TESF TYPE TYPE RELIEF REMARNS POSITION DIRECT. TIME (IN.) MElHOD MODE REQUEST (SEC.)

IPS9354A D-6 2 St A .375 GL A.O. C OP C 10.0 Lt RR VR-1 Passive It RR VR-11 IPS93548 D-6 2 A .375 GL A.O. St OP-C C 10.0 Lt RR VR-1 It Passive IPS9355A RR VR-11 D-6 2 A .375 St GL A.O. C OP C 10.0 Lt RR VR-1 1t Passive RR VR-11 IPS93SSB D6 2 A .375 St GL A.O. C OP C 10.0 Lt RR VR-1 Passive It RR 1PS935/A C-6 VR-11 2 A .375 GL A.O. C St OP C 10.0 Lt RR VR-1 Passive It RR VR-11 IPS935/8 C-6 2 A St

.3/5 GL A.O. OP C C 10.0 Lt RR VR-1 Passive It RR 1PS9356A C-6 VR-11 2 A .375 GL A.O. St OP C C 10.0 Lt RR VR-1 Passive It RR VR-11 IPS93568 C-6 2 A .375 GL A.O. St OP C C 10.0 Lt RR VR-1 It kR Passive VR-11 h* man,m,.,. ._

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COMMONWEAllH EDISON INSERVICE TESIING PROGRAM ISI CLASS 1, 2 and 3 VALVES

_.__ - BYRON NtX'. LEAR POWER SIATION UNIT 1 SYSILM PS P & ID REVISION PAGE M-68-7 4 VALVE 24 of 47 VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORMAL CATEGORY SIZE TYPE S1ROKE MAX. STROKE TEST TEST RELIEF TYPE POSITION DIRECT. REMARKS (IN.) TIME NE TH00 - MODE REQUEST (SEC.)

IPS228A E-7 2 A 0.50 GL S.O. O C Lt RR VR-1 N, A St OP VR-7 ft OP lt RR VR-Il IPS2?on E-6 2 A LL RR 0.50 GL S.O. O VR-1 C N/A St OP VR-7 ft OP It RR VR-11 IPS230A D-7 2 Lt A O.50 GL S.O. O RR VR-1 C N/A St OP VR-7 Ft OP IPS231A D-8 2 A It RR VR-11 0.50 CK S.A. C C N/A Lt RR VR-l Passive IPS228H C-/ 2 A 0.50 GL S.O. O C Lt NR VR-1 N/A St OP VR-7 Ft OP It RR VR-11 IPS/>911 C-6 2 Lt A O.50 GL S.O. O RR VR-l C N/A St OP VR-7 ft OP IPS2308 It RR VR-il 8-7 2 A O.50 GL Lt RR VR-1 S.O. O C N/A St OP VR-7 Ft OP IPS231B B-8 2 It RR VR-l!

A 0.50 CK S.A. C C Lt N/A R2 VR-1 Passive

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4

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COm0NWt ALill EDISON INSERVICE TESTING PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT I SYSitM RC P & ID REVISION PAGE M-60-1 4 VALVE 25 of 47 VALVE VALVE VALVE ACT.

NIN181 R COORD CLASS NORMAL S1ROKE MAX.STROME 1EST CATEGORY SIZE TYPE TYPE TEST RELIEF REMARKS POSITION DIRECT. T]ME IRCol4A (IN.) METHOD tt00E REQUEST E- 5 i B 1.0 GL (SEC.)

S.O. C O N/A St CS VR-7 Note 7 ft CS IRC0148 f- 5 I B 1.0 GL S.O. C O It RR VP-Il N/A St CS VR-7

Note 7 ft CS IRC014C F-5 I It B 1.0 (a S.O. C 0 RR VR-Il N/A St CS VR-7 Note 7 Ft CS IRC0140 E-5 It 1 B 1.0 GL S.0. C 0 RR VR-ll N/A St CS VR-7 Note 7

_ . _ _ ft CS It RR VR-Il

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COPF10NWEALIH EDISON INSERVICE 1ESlING PROGRAM ISI CLASS 1, 2 armi 3 VALVES BYRON N_UCLEAR POWER SIATION UNIT 1 SYSILM RE P & ID REVISION PAGE M-/O-1 4 26 of 47 VALVE VALVE VALVE VALVE ACT.

NUMBER COORD NORMAL S1ROKE MAX. STROKE TEST CLASS CAIEGORY SilE TYPE TEST RELIEF REMARKS TYPE POSIIION DIRECT. TIME ftETHOD MODE 1RE91590 D-3 DM. ) (SEC.)

REQUEST 2 A .75 D A.O. O C 10.0 St OP It RR VR-11 ft OP Lt RR VR-1 1RE9159B D-2 2 A St OP

./5 0 A.O. C C 10.0 Lt RR VR-1 Passive 1RE9160A D-3 ~ 2 A 1.0 D A.O.

It RR VR-11 O C 10.0 St OP It RR VR-11 Ft OP 1RE91608 D-2 2 Lt A 1.0 D A.O. O C RR VR-1 10.0 St OP It RR VR-11 FL OP IRE 9157 C-2 2 Lt A 1.0 D A.O. O C RR VR-1 10.0 St OP It RR VR-11 ft OP 1RE9170 H-2 2 Lt A 3.0 0 A.O. O RR VR-1 C 10.0 St OP It RR VR-11 Ft OP Lt RR VR-1 1REl(X)3 8-3 2 A 3.0 0 St OP A.O. C C 10.0 Lt RR VR-1 Passive It NR VR-Il O

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Cortt0NWfAlTH EDISON INSERVICE TESIING P D .=.

ISI CLASS 1, 2 aruf 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYS1EM Ril P & ID REVISION PAGE M-62-1 4 VALVE 28 of 47 VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORfvt. S1ROKE MAX.SIROKE 1EST CAltGORY SIZE 1YPE 1YPE TEST RELIEF REMARKS POSITJON 01 RECT. TIME METHOO (IN.) M00E REQUEST 1RH8/OIA E-2 ~ 1 A 12.0 CA (SEC.)

M.O. C 0 120.0 St CS Note 5 l It RR VR-11 1Ril870lfs E-1 Lt 1 A 12.0 GA M.O. C 0 RR Note 6 l 120.0 St CS Note 5 It RR VR-11 IRH8702A D-2 Lt 1 A 12.0 GA M.O. C O RR Note 6 120.0 St CS It Note 5 RR VR-11 1RH8/02fs D-1 Lt 1 A 12.0 GA M.O. C O RR Note 6 120.0 St CS Note 5 It RR VR-il IRil8/05A D-1 1 A O.75

1. t RR Note 6 CX S.A. C C N/A LL RR IRH8/0511 Note 6 C-1 2 A O.75 Passive CX S.A. C C N/A LL RR Note 6 IRil8730A E-3 2 C Passive 8.0 CK S.A. C 0 N/A Ct/Xt CS/OP Note 8 1RH87300 B-3 2 C 8.0 CK S.A. C 0 N/A Ct/Xt CS/OP Note 8 1Ril8708A E-2 2 C 3.OX4.0 RV S.A. C O N/A Rt RR 1RH8/08B O- 2 2 C 3.OX4.0 RV S.A. C 0 N/A Rt RR W

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TO SH ET TE t t t M R R R tt tt tt it N SI SI SI SI O E I K S O )

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C0rT10MEALTH EDISON INSERVICE lESIING PROGRAM ISI CLASS 1, 2 arul 3 VALVES BYRON NUCLEAR POWER STAT [ON UNIT 1' SYSIEM RY P & ID REVISION PACE M-60-6 4 VALVE

~

30 of 47 VALVE VALVE VALVE ACT.

NUMI51 R COORD NORMAL CLASS CATEGORY SIZE TYPE STROKE MAX. STROKE 1EST TEST RELIEF REMARKS TYPE POSI' LION DIRECT. TIME ftLTHOD 1RY8026 F-3 (IN.) (SEC.)

MODE REQUEST 2 A .375 GL A.O. O C 10.0 i t. RR VR-1 St OP It RR VR-11 Ft OP 1RY8025 F-2 2 St OP A .375 GL A.O. C C 10.0 Lt RR. VR-1 Passive It RR VR-11 1RY8028 i-2 Ft 2 A 3.0 0 A.O. O OP C 10.0 Lt RR VR-1 St OP It RR VR-11 1RY8046 f-3 2 Ft OP A 3.0 CK S.A. C C N/A Lt RR VR-1 IRY8047 Passive F-3 2 A .75 CK S.A. C C N/A Lt RR VR-1 Passive IRY8033 E-2 2 A .75 D A.O. O C 10.0 Lt RR VR-1 St OP It RR VR-11 Ft OP 6

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COMMONWEALTil EDISON INSERVICE lESilNG PROGRAM ,

ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT I SYSTEM SD P & ID REVISION PAGE M-48-5 4 VALVE 32 of 47 VALVE VALVE VALVE ACT.

NUMBLR COORD NORMAL CL ASS CAIEGORY SIZE lYPE STRONE MAX. STROKE TEST TEST RELIEF REMARKS TYPE POSITION DIRECT. TIME METHOD ISD002A E-8 2 (IN.) (SEC.)

N00E REQUEST A 2.0 GL A.O. O C 7.5 Lt RR VR-1 St OP It RR VR-11 ISD0028 E-7 Ft 2 A 2.0 GL A.O. O OP C 7.5 LL RR VR-1 St OP It RR 'VR-11 ISD002C ~E-7 ft 2 A 2.0 GL A.O. O OP C 7.5 Lt RR VR-1 St OP It RR VR-11 ISDOO2D E-6 2 A 2.0 Ft OP GL A.O. O C 7.5 Lt RR VR-1 Gt OP It RR VR-11 ISD00?E l'- 5 2 ft A 2.0 Gl. A.O. O C OP 7.5 Lt RR VR-1 St OP It RR VR-11 ISD002F E-4 2 A 2.0 GL Ft OP A.O. O C 7.5 Lt RR VR-1 St OP It RR VR-11 ISD002G E-3 2 0 ft OP 2.0 GL A.O. O C /.5- Lt RR VR-1 St OP ISD002H It RR VR-ll E- 3 2 A 2.0 Ft OP GL A.O. O C 7.5 Lt RR VR-1 St OP It RR VR-!!

ft OP

INSERVICE TESTING PROGRAM CONMONWI Al Til EDISON ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSTEM SD P & ID REVISION PAGE

_. M-48-5 4 VALVE 33 of 47 NUMBER VALVE VALVE , VALVE' ACT, NORMAL COORD CLASS CATEGORY SIZE- STROKE MAX. STROKE TEST TEST RELIEF lYPE TYPE POSITION DIRECT. REMARKS TIME NETHOD (IN.) '

(SEC.)

MODE REQUEST

_ "3 4 IS0005A D-8 2 S t. OP A .375 GL d.0, C

' C 3.0 Lt RR VR-1 Passive It RR VR-11 IS00058 D-/ 2 St OP A .375 CL A.D. ' C

'C ~ 3.0 Lt RR

_ VR-1 Passive It RR '

ISD005C D-5 2 A St OP '__ VR-11

.3/5 GL A.O. C C 3.0 Lt RR VR-1 Passive >

It RR VR-11 ISD0050 0-4 2 .St '

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'i INSERVICE TESTING PROGRAM COMMONWEAL.Ill LDISON ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSIEM SI P & 10 REVISION PAGE M-61-1 4 34 of 47 VALVE VALVE VALVE VALVE ACT. NORMAL N(PIBER COORD Ct. ASS CATEGORY SIZE STROKE MAX. STROKE TEST TEST RELIEF REMARNS TYPE 1YPE POSIrlON DIRECI. TIME MEll100 MODE IS188048 (IN.) (SEC.)

REQUEST B-4 2 8 8.0 GA M.O. C O 10.0 St OP ISI8806 B-3 2 8 8.0 It RR VR-11 GA M.O. O C 15.0 St CS Note 14 l ISI680/A C-3 2 8 6.0 GA It RR VR-11 M.O. C 0 15.0 til OP ISI8807B C-3 2 8 6.0 It RR VR-11 GA M.0. C 0 15.0 St OP It RR VR-11 IS189220 C-5 2 C 4.0 CK S.A, C 0 N/A CL CS VR-3 1S189228 U-5 2 C 4.0 CK S.A. C O N/A Ct CS VR-3 18I8926 H-3 2 C 8.0 CK S.A. C O N/A Ct/Xt CS/0P VR-6 ISI8924 D-3 2 8 6.0 GA M.D. O C 15.0 St

, OP It RR VR-11

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INSERVICE TESTING PROGRAM COMMONWEAllit EDISON ISI CLASS 1, 2 and 3 VALVES UNIT 1 8YRON NUCLEAR POWER STATION SYSTEM SI P & ID REVISION PAGE M-61-2 4 35 of 4/

VALVE VALVE VALVE VALVE ACT. NORMAL NUMBER COORD CLASS STROKE MAX. STROKE TEST TEST RELIEF REMARKS CAlEGORY SIZE TYPE TYPE POSIll0N DIRECT. TIME MElHOD MODE (IN.) (SEC.)

REQUEST ISI880ln D-5 2 0 4.0 GA M.O. C 0 10.0 St CS Note 13 l

IS188018 D-5 2 8 4.0 GA It RR VR-il M.O. C 0 10.0 St CS Note l' l It RR VR-11 ISI8900A E-8 1 AC 1.5 S.A.

CK C 0 N/A Ct CS Note 9 lt RR Note 6 IS18900H E-8 AC 1.5 1 CK S.A. C 0 N/A Ct CS Note 9 Lt RR Note 6 IS18900C 0-8 AC 1.5 1

CK S.A. C 0 N/A Ct CS Note 9 1S189000 it RR Note 6 C-8 1 AC 1.5 CK S.A. C 0 N/A Ct CS Note 9 Lt RR Note 6 1318815 D-6 AC 3.0 1 CK S.A. C 0 N/A Ct CS Note 9 Lt RR Note 6 O

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b COMMONWL'Allil FDISON INSERVICE TESTING PROGRAN ISI CLASS 1, 2 ard 3 VALVES UNIT 1 BYRON NUCLEAR POWER STATION SYSILM SI P & ID REVISION PAGE M-61-3 4 VALVE 36 of 47 VALVE VALVE VALVE NUMBER COORD ACT. NORMAL CL ASS CATEGORY SIZE TYPE STROKE MAX. STROKE TEST TEST RELIEF TYPE POSIIION DIRECT. REMARKS ISI8802A E-3 (IN.)*"' TJNE MEll100 MODE REQUEST 2 D 4.0 (SEC.)

GA M.0. C 0 10.0 St CS ISI8110211 D- 3 2 Note 14 l B 4.0 GA It RR VR-Il M.O. C 0 10.0 *i

. IN ISI8840 B-4 2 Note 14 l 8 12.0 CA M.O. It RR VR-11 C 0 15.0 St CS Note 14 It l IS i nutill E-3 RR VR-Il 2 A , .75 GL A.O. St OP C C 10.0 Lt RR VR-1 IS18905A Passive E-5 l AC 2.0 It RR VR-il 7 CK S.A. C 0 N/A CL CS VR-3 /~

ISl'890SB D-/ Lt RR 1 AC 2.0 CK S.A. C Note 6 0 N/A CL CS VR-3 3 SIB 905C D-/ Lt RR 1 AC 2.0 CK S.A. Note 6 C 0 N/A CL CS VR-3 181090SD E-4 Lt RR 1 AC 2.0 CK S.A. C 0 Note 6 N/A CL CS VR-3 LS18835 C-4 2 0 Lt RR 4.0 CA M.0. O Note 6 C 10.0 St CS IS18949A F-8 It Note 14 l 1 AC 6.0 CK S.A.

RR VR-il C 0 N/A Lt RR LS18949B D-8 Ct CS Sote 6 1 AC 6.0 CK S.A. Note 9 l C 0 N/A Lt RR

.SI8949C C-8 CL CS Note 6 1 AC 6.0 VR-3 CK S.A. C 0 N/A Lt RR S18949D E-8 Ct CS Note 6 1 AC 6.0 CK S.A. C Note 9 l 0 N/A ll RR Sl8819A A-5 Ct CS Note 6 1 AC 2.0 CK VR-3 S.A. C 0 N/A IL 'RR Note 6 B188190 A-/ 1 AC Ct CS VR-3 2.0 CK S.A. C 0 N/A Lt NR Note 6 SIBS 19C A-6 1 CL CS VR-3 AC 2.0 CK S.A. C 0 N/A It RR S188190 Note 6 A-S 1 AC Ct CS VR-3 2.0 CK S.A.

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REQUEST ISI8809A E-4 2 B 8.0 GA M.O. O C 10.0 St CS Note 14 I IS18809B D-4 2 8 8.0 GA It RR VR-il M.O. O C 10.0 S t. CS Note 14 l IS188110 0-5 2 8 24.0 GA M.O.

It RR VR-!!

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COPT10NWEnlill EDISON INSERV1CE TESTING PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSlEM SI P & ID REVISION PAGE M-61-6 4 40 of 47 VALVE VALVE VALVE VALVE ACT, NORMAL NUMBER COORD C1 ASS STROKE MAX.STRONE TEST TEST RELIEF CATEGORY SIZE TYPE lYPE REMARMS POSITION DIRECT. TIME METif00 NODE (IN.) (SEC.)

REQUEST ISI8880 F-3 2 A 1.0 St OP GL A.O. C C 10.0 Lt RR VR-1 Passive ISIB956C B-/ 1 AC 10.0 It RR VR-11 CK S.A. C 0 N/A Lt RR Ct Note 6 ISIB956D B-4 1 AC 10.0 CS VR-5 CK S.A. C O N/A Lt RR Note 6 IS18948C B-8 Ct CS VR-5 1 AC 10.0 CK S.A. C o Ct N/A CS Note 9 ISIB9480 B-5 Lt RR 1 AC 10.0 CK S.A.

Note 6 C O N/A Ct CS Note 9 Lt RR Note 6 1SI88/1 A-3 2 A ./5 St OP GL A.O. C C 10.0 1.t

__ RR VR-1 Passive It NR VR-11 1S18964 D-3 2 SL OP A .75 GL A.O. C C 10.0 Lt RR VR-1 Passive ISI8968 F-4 2 A 1.0 It RR VR-11 CK S.A. C C N/A Lt RR VR-1 Psssive D

e

INSERVICE TESTING PROGRAM COMPKmWt ALTH EDISON ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSTEM SX P & ID REVISION PAGE M-42-3 4 VALVE 41 of 47 VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORMAL SIROME MAX.STROME TEST CATEGORY SIZE TYPE TEST RELIEF REMARMS TYPE POSITION DIRECT. TIME ISX112A E-5 (IN.) (SEC.)

METHOD MODE REQUEST 3 8 12.0 BTF A.O. O C 6.0 St OP It RR VR-11 1SX114A E-3 3 8 12.0 BTF Ft OP A.O. O C 6.0 St OP It RR VR-11 1SX112B C-5 3 8 ft OP 12.0 BIF A.O. O C 6.0 St OP It RR VR-11 ISX1148 C-5 3 0 12.0 Ft OP BIF A.O. O C 6.0 St OP It RR VR-11 ISX101A E-3 3 0 1.5 GL Ft OP S.O. C O N/A St OP VR-7 ISX173 C-3 Ft 3 8 6.0 GA A.O. C OP 0 5.0 St OP 1SX178 A-3 3 8 6.0 GA Ft -

OP A.O. C 0 5.0 St OP ISX169A F-8 3 8 10.0 BIF Ft OP A.O. C 0 20.0 St OP It RR VR-11 JSX1698 D-8 3 ft OP 0 10.0 BTF A.O. C 0 20.0 St OP It RR VR-11 Ft OP e

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COMMONWE Al.TH EDISON INSERVICE TESTING PROGRAM ISI CLASS 1, 2 and 3 VALVES BYRON NUCLEAR POWER STATION UNIT 1 SYSitM VQ P & ID REVISION PAGE M-lOS-1 4 44 of 47 untVE VALVE VALVE VALVE ACT.

NUMBER COORD CLASS NORMAL CATEGORY SIZE TYPE TYPE STRONE MAX.STRONE TEST TEST RELIEF REMANNS POSITION DIRECT. TIME IVQ001A E-5 (IN.) METHOD MODE REQUEST 2 A 48.0 BIF (SEC.)

(1. 0 . C C 5.0 Lt RR VR-1 Passive St CS Note 11 IVQ001B E-6 l 2 A 48.0 BTF 11. 0 . C C It RR VR-li 5.0 Lt RR VR-1 Passive St CS IVQOO2A E-4 Note 11 l 2 A 48.0 It RR VR-Il BIF H.O. C C 5.0 11 RR VR-1 Passive St CS IVQ0028 ~ E-3 2 Note 11 l A 48.0 BTF H.O. C C It RR VR-11 5.0 Lt RR VR-1 Passive St CS IVQOO3 C-4 2

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Note 11 l A 8.0 BTF A.O. C C It RR VR-11 5.0 Lt RR VR-1 Passive St OP IVQOO4A D-5 2 A 8.0 It RR VR-11 BTF A.O. C C 5.0 Lt RR VR-1 Passive St OP IVQOO4B D-6 2 It A 8.0 BTF A.O. C C RR VR-il 5.0 tt WR VR-1 P0ssive St OP IVQOOSA E-4 2 It A 8.0 BTF A.O. RR VR-11 C C 5.0 Lt RR VR-1 Passive St OP IVQOO58 E-4 2 It A 8.0 BTF A.O. C RR VR-Il C 5.0 Lt RR VR-1 Passive St OP IVQOOSC E-4 2 A 8.0 It RR VR-Il BTF A.O. C C 5.0 Lt RR VR-1 Passive

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