ML19330C321

County 1 Sqrt Test Plan, Revision 1

ML19330C321
Person / Time
Site:	LaSalle
Issue date:	05/12/1980
From:	SARGENT & LUNDY, INC.
To:
Shared Package
ML19330C313	List: ML19330C312 ML19330C316 ML19330C317 ML19330C321 ML19330C323
References
PROC-800512, NUDOCS 8008080234
Download: ML19330C321 (42)

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LASALLECOUNTY-I

. SQRT TEST PLAN s

f May 12, 1980 Revision 1 i-

.T . o SARGENT&LUNDY

> ENGINEERS . ;

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addendum 7 -July 29, 1980 N

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.,p Additional. Equipment.to be' Test'ed .

1. 1PLl7J - Standby Gas Treatment System Control Panel.

2. 1C41-g001 --Standby Liquid Control Pump.

'3. ' Piping Subsystem HP06 with Valve lE22-F012*

4. Piping Subsystem HP02 with valves lE22-2023* and lE22-F010.

5. Piping Subsystem RI65 with valve lE51-F019.

Notes:

1. Valves-noted with *(lE22-F012, 1::22-F023) are currently listed for testing separate from piping subsystem.

2. Revision 2 of the SQRT Test Plan will incorporate appro-

, priate changes to Test Plan, Revisic3 1 and add infor-mation-for equipment listed above. Sections affected by revision 2 inc]ude IV -Scope, and addition of necessary figures or changes to existing figures.

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. SARGENT&LUNDY iENGINEEAS . p - _- _ - -- _- -- _--

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,.- f C Revision 1 TABLE OF CONTENTS

. Page I Background I-l .

II Objective II-l

III' Schedule III-l Figur,e III-l III-2 Figure III-2 III-3 IV Scope IV-1 A.- Equipment to Be Tested IV-1 1 B '. Equipment Selection Criteria IV-2 C. ' Methods of Testing IV-ll i

D. Results _ of Testing IV-12 E. Sensor Requirements IV-12 TABLES IV-1 SQRT Accelerometer Data FIGURES Phase I . l IV-1. Standby Gas Treatment System Equipment Train lVG0lS IV-2: Standby Gas-Treatment System Primary Fan lVG01C

, IV-3. Containment Isolation Butterfly Damper IVR05YA IV-4 Low Pressure Core Spray Pump and Motor lE-1-C001 IV-5 Main .Str . Isolation ValveJLeakage Cont. Sys. Blwr.

lE32-C001 IV 26" Main Steam Isolation-Valve 1B21-F022A i 1

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.IV-7 -24" Reactor Coolant System Flow Control Valve ,

1B33-F060A IV-8 4" Mtr. Oper. Gate Valve (SMB-2 Limitorque Oper.)

lE22-F012 IV-9 14" Mtr. Oper. Gate Valve - (SMB-00 Limitorque Oper. )

.lE22-F001 IV,10- 12" Mtr. Oper. Globe Valve (SMB-4 Limitorque Oper. )

-lE22-F023 IV-ll Main Control Room Panel- (Bench Board) lH13-P601

.IV-12 Main Control Room Panel (Vertical Type) lH13-P609 IV-13 SRM & IRM Panel .(Wall Mounted) lH22-P030 Phase II IV-14--RHR Gate Valve (lE13-F009)

-IV-15 RHR Pump (lE12-C002)

IV-16 Jet Pump Local Instrument Panel "B" (lH22-P009)

IV-17 HPCS Gate Valve (lE22-F015)

.IV-18 Cooling Coil Cabinet (lVYO 3A)-

FINAL PAGE i IV-33 5

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', May-12, 1980

• Revision 1 I. BACKGROUND -

The dynamic ~ qualification of safety-related equipment in.LaSalle County-1 Nuclear Station'was done essentially for soismic loads.

Later, the suppression pool hydrodynamic loads were determined and it wac required to demonstrate the capability of this equip-ment to withstand these additional loads. In the course of doing a

so, the Nuclear Regulatory Commission (NRC),axpressed concern that these new loads may contain frequencies greater than 33 Hz which was in some cases the cutoff frequency for the original seismic qualification. It was difficult in some of these cases to evaluate the sensitivity of the equipment to these high frequencies. Therefore, the NRC-SQRT requested in-plant tests that would consist of two phases as follows:

A. In-Plant Impedance Tests (Phase I)

B. In-Plant SRV Test-SQRT Equipment Monitoring (Phase II)

Phase I of testing, the In-Plant Impedance Test, is done on selected pieces of equipment to verify the dynamic character-

- istics of the equipment and its behavior to high frequency contents.

Phase II would monitor the dynamic response of certain selected pieces of equipment during the In-Plant SRV Tests.

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a. Revision 1 II. OBJECTIVE.

A. The objectives-of Phase I, In-Plant Impedance Tests,"is to obtain the dynamic characteristics of selected pieces of equipment such as:

1. Natural frequencies.in the range between 1 Hz and 100 Hz.

2 Mode shapes for all natural frequencies.

3. Damping associated with each mode.

4. Amount of cross-coupling 5 Data required to calculate the model participation factors assuming the forcing function and the mathema-tical model to be known.

B. The objective of Phase II, In-Plant Equipment Monitoring, is to collect acceleration data on selected pieces of reactor building equipment during the period it is being excited by various SRV lift combinations of the In-Plant SRV Test Program.

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III.- SCHEDULE A. The In-Plant Impedance Testing will be implemented during a period which will not interfere with the preoperational test <

program now in progress at LaSalle County Station. The schedule shown on Figures III-l and III-2 is based on a June 1,- 1980 fuel load date.

B. The In-Plant SRV Test-SQRT Equipment Monitoring will coincide with the In-Plant SRV Test Program. The data acquisition .

system used for the In-Plant SRV Test will be used for the SQRT Equipment Monitoring. - -

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PROJECT NO. 4266-10 FIGURE III-l .

DATE 5-12-80 SQRT ,

REVISION 1 IN-PLANT IMPEDANCE TEST SARGEfJT*aLUfJDY SilEET 1 OF 1 '""*""""*"

PHASE I ITEM l ITEM 1980 NO. J F M A' M l J J A S O N D

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I.A ENGINEERING ANALYSIS - '

I.A.1 Equipment Selection a

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I.A.2 Sensor Designation

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I.B SERVICE PROCUREMENT -

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I.B.1 Spec. nout/ Preparation

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I.B.2 Internal deview '

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I.B.3 CECO Review J

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I.B.5 Response of Bidder ~~ L i g _ .,

I.B.6 Bid Evaluation / Recommendation _,_,,,,,,y .

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I.B.7 Contract Award .i .

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I.C TEST PLAN "._ '.*~..T.,~ ' "

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I.C.1 Preparation _.

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I.D IMPEDANCE TEST c, d E p 2~J

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• I.D.1 Test Procedure Preparation (contracto:-} 6 .' -

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I.D.2 Testi Conduct - - '

1. I.D.3 Test Report (contractor)

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,' . May 12, 1980 Revision 1 a.1 IV. SCOPE A. Equipment to be Tested

1. During Phase I Impedance Testing the following equip- ,

ment will be tested:

a. lVG0lS - Standby Gas Treatment System Equipment Train

b. lVG01.C - Standby Gas Treatment System Supply Fan

c. IVR05Y - Reactor Building Isolation Damper

d. lE21-C001 - Low Pressure Core Spray Pump / Motor

e. lE32-C001 - MSIV Leakage Control System Upstream b~j' ,

Exhaust Blower -

i f. 1B21-F022A - MSIV Inside Containment

g. 1B33-F060A - Reactor Recirc. Flow Control Valve

h. lE22-F012 - High Pressure Core Spray 4" Gate Valve

.i . lE22-F001 - Valve with SMB-00 Motor Operator High Pressure Core Spray 14"

j. lE22-F023 - Valve with SMB-4 Motor Operator High Pressure Core Spray 12"

! k. 1H13-P601 - Main Control Panel Bench Board

l. 1H13-P609 - Main Control Panel Vertical Board

m. 1H22-P030 - SRM & IRM Local Panel a

2. During Phase II Equipment Monitoring the following y equipment will be monitored

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,f 0 a. lE12-C002C RHR Puro C ll-3 .b. 1H22-P009 Jet Pump Inst. Panel-i i

c. .lE22-F015 HPCS Gate Valve SARGEf!T&LUNDY iCNGINEERS .

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May 12, 1980 Revision 1 ,

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d. 1E12-F009 RHR Gate Valve

e. IVYO3A Cooling coil Cabinet

3. In both cases, the equipment will be permanently installed

. without modifications to supporting structures. ,

The testing will not impose any restrictions to normal opera-tion of the selected equipment during Phase II.

B. Equipment Selection Critsria

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1. Equipment to be tested during Phase I was selected i

based on the following:

a. VG0lS - SGTS Equipment Train This unit is used to purify contaminated atmosphere of?

reactor building and vent it to the outside.

1. This unit should be operable during and after i LOCA event.

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2. Train was qualified by Static Analysis.

3. It has a lowest natural frequency of 21 Hz.

4. It also contains several essential components like pressure and temperature transmitters and i

switches, heaters, demisters and filters, most of h

j which were qualified only up to 33 Hz.

I' h? 5. Study of responses of the equipment train to high ,

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!. frequency loads would help in evaluating the SARGENT&LUNDY

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May 12, 1980 Re~ vision 1

.t qualification of the train as well as components

mounted on it . Most of the components may be qualified utilizing-the mode shapes and model l t narticipation factors obtained from the test' .

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b. lVG01 - SGTS Primary Fan This fan is used to drive reactor building air through SGTS unit for purification. It is '

esser. i.al equipment required to operate after a LOCA event.

1. None of the fans in the plant were tested.

2. Operability of the fan was proven by deflection analysis.

3. Fan and motor assembly is mounted on vibration isolators.

4. Equipment was qualified by Static Analysis.  ?

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.i 5 Study of the responses of the assembly and obtaining the mode shapes and model responses would help in qualifying this fan and other safety-related fans for structural integrity as well as operability in the high frequency range.  ;

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c. lVR05Y - R. B. Isolation Damper m ,

This is a 72"$ essential, active butterfly damper to l

. isolate secondary containment in case of reactor SARGEHT&LUNDY l

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May 12, 1980 Revision 1 building contamination.

1. This is the only duct mounted component to be studied.

'2. This damper was qualified by Static Analysis and l operability was proven by deflection analysis.

3. Solenoid of damper operator is being replaced.

4. Study of the responses would be helpful to evaluate the duct - damper interaction and in the qualification of solenoid of damper operator

5. The damper operators that were qualified by testing were of rectangular type. The response of damper and operator mounting a't high freauen-cies for a circular damper is ne.eded to complete the qualification of these dampers.

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d. lE21-C001 - LPCS Pump / Motor This is a large vertical multi-stage pump with motor mounted on the top.

1. Pump and motor were analyzed by Static Analysis.

2. Motor is cantilevered vertically on top of thh pump.

3. Duw to its length (312" to the bottom and 150" to the top from support) responses of the assembly at same locations of the pump could be critical.

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'May 12, 1980 Revision 1

4. Existing analysis is efficient in many ways.

Even the modeling-used to obtain the natural frequency is not adequate.

5. The results of the study of mode shapes and model participation factors would help in evaluating and unqualifying similar pumps (HPCS and RHR) .

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lE32-C001 - MSIV LCS Blower This blower is used for main steam isolation valve leakage' control _and is essential. There are two such blowers in each unit.

1. Blower and motor were tested up to 33 Hz.

2. No resonance was found below 33 Hz.

3. The list meets all the other requirements such as duration, etc.

4. If it can be proven by impedance test that the equipment is not significantly affected in the high frequency range, it can be qualified with minor or no additional effort.

f. 1B21-F022 - MSIV.

Valve size 26" ASME class 1 operation - air cylinder with hydraulic cylinder control and limit switches.

1. Valve was qualified by Static Analysis.

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2. This is an essential valve with essential electrical and mechanical controls.

3. There are 8 MS Isolation valves in each unit.,

. 4 .' Study of the mode shapes and model participation.

factors obtained from impedance test in the high

- frequency range would help to qualify the MSIV and other large valves and their controls.

g. 1B33-F060 - Flow Control Valve Installed in the reactor coolant system, it throttles the discharge flow of a constant speed pump.'

Valve Size 24" ASME class 1.

1. Valve contains electrohydraulic actuator with electrical controls.

2. This is passive equipment.

3. The operator, controls and mounting can be qualified for structural integrity by obtaining the mode shapes and model participation factors.

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'4. Study of the responses would also help in C qualifying other heavy valves which are similar to this valve.

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)J h. lE22-F012 - Gate Valve with SMB-2 Motor Operator b ~

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! -Valve size 4" - 600 lbs. ASME class 2.

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1. ' valve was qualif'ied by Static Analysis.

2. Limitorque motor operators were not tested beyond 35 Hz.

3. Model SMB-2 Limitorque operator was not tested. L

4. Study of the mode shapes and model participation l factors.would help in reevaluating:

(a) Limitorque operator SMB-2 qualification.

(b) Response of the small valve operator assembly in the high frequency range can be used to qualify all similar valves by afditional analysis.

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1. lE22-F001 - Valve with SMB-00 Motor operator (Limitorque)

V '.ve 14" --150 lbs., ASME class 2.

1. Valve was qualified by Static Analysis.

2. Limitorque motor operators were not tested beyond 35 Hz.

3. Model SMB-00 operator was not tested. '

4. Study of the-mode shapes and model participation u factors would help in reevaluating:

(a) Limitorque operators SMB-00 qualification.

(b) Response of the medium size valve operator assembly in the high frequency range can.

be obtained and the results used to qualify SARGENT&LUNDY e..~-. c -- - - - - - -

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. Revision 1 all similar valves by additional analysis.

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j. lE22-F23 - Globe Valve with SMB-4 Motor Operator (Limitorque) U Valve size 12" - 600 lbs., ASME class 2.

. l. . Valve was qualified by Static Analysis.

2. Limitorque operators were not tested beyond 35 Hz.

3. Limitorque operator model SMB-4 was not tested. 4L -

4. Study of the mode shapes and model participation factors would help in evaluating:

(a) Limitorque operators SMB-4 qualification.

(b) Response of th: medium size valve operator assembly in the high frequency range can be obtained and'the results used to qualify all similar valves by additional analysis.

k. lH13-P601 - Main Cont'rol Panel -(Bench Board)

This panel is located in main control room and contains several class lE instruments. Higher I

frequency (above 33 Hz) content of the responses l l

is not critical for this panel since SRV and LOCA j i

loads are not significant for control room.  ;

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1. Tnis panel is the most critical of several ,

.similar panels.

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-2. Several instruments mounted on this panel and other control room panels were qualified i

separately for which available data is inade-quate.

3. By studying the response of this panel- (mode shapes and model participation factors) at various instrument locations, some instruments and most of the main control room panels can qualified with little additional analysis. p

1. lH13-P609 - Main Control Panel (Vertical Board)

This panel is located in main control room and con-tains several class lE instruments. Higher frequency ,

(above 33 Hz)' content of the responses 'is not critical for this panel since SRV and LOCA loads are not significant for control room.

1. This panel-is the most critical of several similar panels.

2. Several instruments mounted on this panel and other control room panels were qualified separate-L ly for which available data is inadequate.

3. By studying the response of this panel (mode shapes and model participation factors) at various instrument locations, some instruments and most of the main control room panels can SARGENT&LUNDY

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, May'12, 1980 a, -Revision 1 qualify with little additional analysis.

m. lH22-P030 - SRM & IRM Pa'ndl (Local)

This pane: contaihs startup neutron monitoring electronics and some process radiation electronics equipment.

1. Panel was tested up to 33 H3.

2. This has lowest natural frequency of 16 Hz and is expected to have natural frequencies between 33 and 50 Hz range. .

3. There are four similarly constructed local panels in each unit.

4. A detailed mode shapes and model participation factors would enable us to qualify the panels and the devices mounted on them with minor u

additional analysis.

2. Equipment to be monitored during Phase II was selected based on the following:

a. To provide a reasonable coverage of different types, dynamics characteristics, safety functions, etc.

b. To associate locations with specific safety relief valve actuations as much as practical without changing the In-Plant SRV Test Program.

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'c. .To. utilize as many a's possible of the other instrumentation readings which will be used.for

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loadings and structural response verification during the In-Plant SRV Test Program.

C. Methods of Testing

1. Phase I Impedance Testing will be performed by exiting the selected equipment at one location, or as many as necessary for meaningful results, with cyclic loading of a constant magnitude sufficiently high enough to detect all significant modes in the frequency range to be covered. Impact, electrodynamic shakers or hydraulic shakers shall be used as appropriate to meet this goal. The input frequency will be varied between 1 Hz and 100 Hz at a sweep rate not more than one octave per minute. The actual sweep _ rate will be determined by the structural damping.of the eauipment being tested. The response will be measured at the required locations necessary to determine the natural

. frequencies and mode shapes of the equipment within the above frequency range.

2. Phase II monitoring will performed during the' performance aof the In-Plant SRV Test. Signals from accelerometers mounted on the' selected equipment will be recorded.on SARGEUT&LUNDY i EiNGINE ERG p _ _ _ _ _ _ _- - ___ _

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.,. Revision 1-FM tape. Signals from' triaxial- accelerometers mounted at the base of the equipment will be recorded as a

'N reference.

D. Results of Testing

1. The results of Phase I testing will be used by Sargent & '

Lundy Engineers to help in evaluating the qualification of various types of safety-related equ.ipment to a higher frequency range. The role that individual pieces of equipment play in this evaluation are discussed in IV.B.l. Results of this evaluation will be presented to Commonwealth Edison Company in the form of a final report.

! 2. The results of Phase II testing will be presented to r

Commonwealth Edison Company in the form of raw data i

without analysis.

E. Sensor Requirements s

1. In-Plant Impedance Test - Phase I

The equipment used shall be that deemed necessary by

,1 fd the test contractor to meet the objectives of II. A.

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(, Proposed locations as shown in Figures IV -I thru

[- IV - 13.

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2. In-Plant SRV Test - SQRT Equipment Monitoring - Phase II The monitoring equipment used during Phase II will

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consist of accelerometers. The accelerometers may be uniaxial, biaxial, or tri~ axial, depending on the data required. The input to each piece of equipment will be measured in three directions and the response will be measured in the directions directed by the physic ;l configuration of the equipment.

The Table IV-1 gives the sensor requirements for this F equipment monitoring. Figures IV-14 through IV-18 show sensor locations. Note 1 denotes those sensors which do not have conductros passing through the con-tainment. Environment E2 is that of the Containment Drywell and E6 is outside primary containment.

R Environment E2 Fluid Air Pressure 15.4 psia Temperature 135*F Relative Humidity 90%

Radiation 50 R/Hrhf; 1.4 x 10 5 n/cm2 - sec

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-I Environment E6 .

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Fluid Air.

Pressure 15.4 psia ,

Temperature 120*F Ralative Humidity 60%

Radiation Negligible i

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. LA SALLE COUNTY'- 1 COM O WEALTH [0150ft COMPANY PAGE IV-15 5835-00

- TE N '

DATE 5-12-80 SQRT ACCELEROMETER DATA aEy i s

SENS0ft. LOCATION

- SENSOR EXPECTED EXPECTED ACCURACY ENVIRON. NOTE 5-NUMBEF RESPONSE FREQUENCY MENT RANGE ,g

.AztMuTH -ELEv. RA0!u5 gg) (Hz) (7,3,3

.(DEG) (FT.IN) (FT-IN)

A39 195 744'-8 17'-7 .01-5.0 1-150 1 E *.

a43 192 744'-8 17'-7 .01-5.0 1-150 1 E2 A41 192 744'-8 17'-7 .01-5.0 1-150 1 E2 A42 192 744'-8 17'-7 .01-5.0 1-150 1 F2 A43 192 744'-8 17'-7 .01-5.0 1-150 1 E2 A44 192 744'-8 17' .01-5.0 1-150 1 E2 A45 220 673'-4 62'-0 .01-5.0 1-150 1 E6 1 A46 .220' 673'-4 62'-0 .01-5.0 1-150' 1 E6 1 A47 220 673'-4 62'-0 .01-5.0 1-150 1 E6 i A40 262 673'-4 62'-0 .01-5.0 1-150 i 1 E6 1 A49 262 673'-4 62'-0 .01-5.0 1-150 1 E6 i A50 262 710'-6 50'-0 401-5.0 1-150 1 E6 1 A51 262 710'-6 50'-0 .01-5.0 1-150 1 E6 1 A52 262 710'-6 50'-0 .01-5.0 1-150 1 E6 1 A53 262 710'-6 50'-0 .01-5.0 1-150 1 E6 1 AS4 276 671'-2 52'-5 .01-5.0 1-150 1 E6 1 A55 276- 671'-2 52'-5 .01-5.0 1-150 1 E6 1 A56 276 6718-2 52'-5 .01-5.0 1-150 1 E6 i A57 276 671'-2 52'-5 .01-5.0 1-150 1 E6 1 A58' 276 671'-2 52'-5 .01-5.0 1-150 1 E6 1 A59 276 671'-2 52*-5 .01-5.0 1-150 1 E6 1 A60 25$ - 694'-6 70'-0 .01-5.0 1-150 1 E6 1 All 255 694'-6 70'-0 .01-$.0 1-150 1 ,E6 1 A62 '255 694'-6 70'-0 .01-5.0 1-150 1 E6 1 A63 255 694'-6 70'-0 .01-5.0 1-150 1 E6 1

- A64 255 694'-6 7'0 ' - 0 .01-5.0 1-150 1 E6 1

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' INPUT EXCITATION EQUIPMENT LOCATION

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X direction: @ Reactor Building; Y.directic.: @ S  ; M-6 Z direction: @@ @

Locally Mounted A/B-11/3

~ Safety-Related Instruments: .

. Differential. Pressure Indicator Differential Pressure Transmitter Differential Pressure Switch

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STANDBY GAS TREATMENT SYSTEM EQUIPMENT TRAIN IVG013

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FAN' LOCATION X direction: @

Y direction:' @, .

Reactor Building' Z direction: @ El A/B-ll r

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-x

)

j#'

suction e' a A- M)

- Z a - I STANDBY GAS TREATMENT SYSTEM PRIMARY FAN -

SARGENT&LUNDY IVG01 = ENGihEERS -

~-

FIGURE IV-2 SKETC.H B DATE .REV-5-12-80 1

o .,

INPUT EXCIThTION -

~ DAMPER LOCATION

• X c'irection: @ Auxiliary Buildir.g.

Y cirection: S&L Dwg. M-6 -

.El. 791'-

Z direction: J/L-14/15 As Shown .: @

Perpendicular Y 2 to Blade g

,  ; - - -.

{

A

,[y h 'NN

\

\

qy[1,qg mw> ., .

\ (3 l' .._  !: '

H ,.F(;; ', [ ~{ 7 _ ,

Y ,

" t Y t -

- z

• f . , ^

g m .= g_J

- -};~Q: Lg

',;w:

e

- ./ e  ;  : )

/ See Sa '

W, / ,

.. i e\n .#'

c /'/

[

' ] '

x *e..

SARGENT&LUNDY

' E NGINEER5 tCONTAINMENT ISOLATION BUTTERFLY DAMPER

~

ivRosY -SKETCH C FIGURE IV-3 DATE REV 5-12-80 1 1

4

• INPUT DIRECTION PUMP LOCATION X direction: @ Reactor Building S&L Dwg. M-ll Y direction: El. 673' Z direction: @ A/B-13/14

. / .

^

c , .

= -

l I

__;

/

2 I

g Discharge I I

~

i i

h Suction -

_ )

- ,y n

i ,x jd 2

/

l SARGEUT&LUNDY

= ENGINE E RS -

SKETCH D LOW PRESSURE CORE SPRAY PUMP-& MOTOR DATE REV '

t lE21-C001 5-12-80 1 IV-19 '

FIGURE IV-4

1!41'UT EXCITATIUti <

X direction: h BLOWER LOCATION *:

Y dircction: @ Reactor Building S&L Dwg. M-ll-

.Z' direction: @ El. 673' H/J-ll/12 i .

J L

[

V:=g yEss 4

c v

- E N f% .

^

ff G m o s 3

h 't l A i ,

+ r -

l I i /

\ Vacuum' pressure s

- j side -

s side EDEJT&LU.1DY

'O """"**"

g.  %  !;  ; ; y' F O. _O 7 1

MAIN STEAM ISOLATION VALVE SKETCH E LEAKAGE CONTROL SYSTEM BLOWER i i lE32-C001- DATE REV.

FIGURE"IV-5 5-12-80 1 s .._ . ~ . . . . . . . . . .

' INPUT EXCITATION *

.. VALVE LOCATION X direction: @ Primary Containment Y direction: @@ S&L. N g. M-8 Bl. 742' Z direction: @@ F/G-12 1

3 Q 2 4

'N y X g '

b 4

q .

z SEGEf3T&LUNDY

.euoisecas 26 in. MAIN STEAM ISOLATION VALVE 1B21-F022

. SKETCH F FIGURE IV-6 ~

DATE REV 5-12-80 1

e.

3 INPUT DIRECTION VALVE LOCATION X direction @ Primary Containment S&L Dwo't M-8 Y direction @ El. 744' Z direction @ D/E-12/13

[

( ,

o o  :

p .

olo i--

' '~ $ = =.N 5 TOP VI8W Y

< 1

/

[! I

'l Il

>m/ f  %.

E X I SAGGEfjT&LUijDY z l ,eusineens 2_4 IN. REACTOR COOLANT SYSTEM FLOW CONTROL VALVE SKETCH G 1B33-F060 IV-22 FIGURE IV-7 DATE REV 5-12-80 1

INPUT EXCITATION . VALVE LOCATION X direction: @ @ Reactor Building Y direction: @ .S.&L Dwg. M-10 r El. 679 Z direction: @ @ G 8.9/10 3

ES

.E=, . E 9- .

b--

d

? /

f ,/ ,

vv ., v 4 l l l l l u

f1 .#3 g '

[

e e v g- 'tu

.=*"%

e / e. n A rn A _A A (h

! s' (L /

'E x

• l, .

.I z

, END VIEW f> 4 IN. MOTOR OPERATED GATE VALVE (SMB-2 LIMITORQUE OPERATOR) lE22-F012 SAfiGEIST&LUiJDY

' ENGINEERS .

FIGURE IV-8 SKETCH H IV-23 DATE REV 5-12-80 , 1

-. . . ~ . . . . ,

. INPUT EXCITATION VALVE LOCATIONS X direction: @@ Reactor Building "9' "~

F Y direction: @ El. 674 Z direction: @@ D/E'-8 . 9/10 o

Sa a B@

E'l

.-., NI, Y

/,

<me, e, u  :

EC J DL. JO

, y y

. - / 6N c ,m o. . r en an

a ya I

V 7'

- u

E.

"% /~

tj ll SARGENT&LUUDY

= ENGINEERS SIDE VIEW 14 IN. MOTOR OPERATED GATE VALVE (SMB-00 Limitorque Operator) SKETCH I lE22-F001 DATE REV .

IV-24 FTCHRE TV-4 5-12-Rr 1

e, .

~ INPUT EXCITATION VALVE LOCATIDNS X direction: hh Reactor Building S & L Dwg . M .10

Y direction: '@ 3 Elev. 696' Z direction: h@ B-10

~~

I \ - -

! \,

r

! It

/

' ~

< N 2

j -

[

. =-

.  ?

l Q .

I c l l I l

. e fTib J '

d rft

/  %

^'

_ , y x l

z I

~

12 IN. MOTOR OPERATED GLOBE VALVE (SMB-4 LIMITORQUE OPERATOR) SARGEUTaLUNDY lE22-F023 .

FIcURE Iv-1 SKETCH J IV-25 DATE REV 9 1?-Rn 1

INPUT EXCITATIUN'

- PANEL LOCATION '.

X direction: @ Auxiliary Building S&L Dwg. lE-1-3465 Y direction: O5 El. 768' Z direction: @ @@ L/5-14/15 .

'N lb __ ___ _

^

\

4 3 2 @

y

, Y Vf -

n

. =

n .

MAIN CONTROL ~ ROOM PANEL (BENCH BOARD) 1H13-P601 '

SARSEjT&l. UNDY eNoiNet=s .

SKETCH K DATE REV 5-12-80 '1 ,

^

.~.__  ;-

INPUT EXCITATION ,

PANEL LOCATION X. direction: @ Auxiliary Building Y direction: S Dwg. 1E-1-3465 El. 768 Z direction: (i) @ L-13 Internal Stiffeners -

Barrier Block of i Aux. Relays j N ,

/l/

l '

N I s

i I

[ Block of __

'f l Switches

'w Q I

g

_' - @' ' /

Time Delay Relays 5

I I ,

i l

Yd g l

g Block of d

., ,i

- Aux. Relays l l P f Contactors

=

/ l W r .

i

]

c g

y y 1 I -

x SIDE VIEW MAIN CONTROL ROOM PANEL (VERTICAL TYPE) ,

. SARGENT&LUNDY

= ENGtNEE RS 1H13-P609 SKETCH L FIGURE IV-12 DATE REV 5-12-8C 1

IhPUT EXCI"ATION -

PANEL LOCATION

'X directions h Reactor Building Y direction: g S&L Dwg. M-8 El. 740 Z direction: @ 'G-10/ll f- ' -

'd 1 l -

1 i 8 I w PREAMPLIFIER b - - - .-- 3 3

"i 1 TOP VIEW -

3 FR- fb1 i

Ie el Y

h

\

(

&x a g z 1 j

. SARGEUT&LUNDY  !

g y enoineens .

l SRM & IRM PANEL (WALL MOUNTED) ' gg lH22-P030 FIGURE IV-13 DATE REY '

IV-28 5-12-80 . 1 t

I

-~

ACCELEROMETERS Sensor No. N '

[

1. 1&4 - X DIRECTION A39&A42 '

1. 2&5 - Y DIRECTION A40&A43 [ '

1. 3&6 - B DIRECTION A41&A44 g / /m g gpy1 I 7,-7?

Y

~

JL S

X

, y i

1 N

1,2,3 H ly ,3 _ j. 7_

o

• ~

H 4 l ![ __'t 8

h

=

• H N

y y .g ,

Uwj u u

, M H I ^

5Y <

N?b 1+9 r =gr 1 al 1 c I

J V m, H Y am CA - I m a s, km y, -

x Q 4,5,6

-4 y- 4,5,6 RHR GATE VALVE

< Q jg @E 9

(lE13-F009)

,, B

- CONTAINMENT 22 SO ELEVATION: 744'-8" g -< .

i' FIGURE IV - 15 ACCELEROMETERS _S nsor No.

1. 1 RADIAL A45

1. 2 TANGENTIAL A46 ,- l 2Y

1. 3 VERTICAL n47

1. 4 RADIAL A48 -

{

1. 5 VERTICAL A49 W MfY f S -

G 2 '- O " T Y

• d R

f, p 4,5 U _

• O d

i- @ 1,2,3

?

l

-l _

/

//

%s RHR PUMP ,

(lE12-C002)

REACTOR nurtoINc SARGENT&LUNDY ,j F DOR ELEVATION: 673'-4" IENGtNEEAS

SKETCH 0 IV - 30 DATE REV 5-12-80 1

o G

ACCI:I.1:ltOMI:T1:Its Sensor No. 4-N '*f.*

1. 1 RADIAL A50 j

• A51 g 2(o2* .-

1. 2 VERTICAL

1. 3 N-S A52 N ( .

1. 4 N-S A53 gpy O .E

.s SO '- O *

MT d N in H v

I o

. R c

o d t:2 H

< H

~~ ~

4 , ,3 4' g 3

, 4 ,

g

• r ='

,, T - I .

W H

) IH I [ i i ii $

ll

• I l ~

l r - -

F . .- e

'I N h l h _ _. _ _ _. _

. ( _ _ _ _ _

q I _

m +

s .

b M m 2> ])

rh o

so cn X

g 1, 2 1,2 -

m M 2

_M JET PUMP LOCAL INSTRUMENT PANEL "B"

$ Z E (lH22-P009)

~D. EC REAETOR BUILDING s $ FIDOR ELEVATION: 710'-6" i*

, ,, . - , - - .. -#t- ,w w- , . - - , ,.m - , , , . . - - - w . ~,.m, -

w- e, - . . 3

ACCELEROMI?fERS

+'8 SODSor No.

4'

1. 1&4 RADIAL A54 & A57 1

1. 2&5 TANGENTIAL A55 & A58'

'#3&6 VERTICAL A56 & A59 7,*

W RPV >

) r

/ .

S b y )g y 52 '--S" m

1,2,3 H m_ 1,2,3 g c

H

<;

• 7' N to

),

~

l.

I 1 ocJ g m ' 7.. j9 g N . 3 il

. ~

, j 4

• Ea) , a s "f, )uR 1 $ a ._ a e. e o a. E.a nn

?

w en M

a o pt;; m , r [

m 2

- -i =4

o O s @e *

(*)

I

~

ia

~

~

! j 4j . s 4,5,6 y 4,5,6 IIPCS GATE VALVE *

-(lE22-F015)

REACTOR BUILDING ELEV'ATION: 671'-2"

- _, _s _ _ . _ _ _ ,- ____.___._i__ _s , mw-e--=-m-, ,---#ww-- w--,-w t wv m -y --e '-

om' em vw- N s* ,-se e e, Sw.aN mm .gg.-- r == w.6= - . . - -

o ACCELEROMETERS SonSor No, g ' ,{

1. 2,5 - X DIRECTION AGO & A63 d -

1. 3,1 - Y DIRECTION A61 & A64 \agg *

1. 4 - B DIRECTION A62 g/ rk 1 _g RPV'{

70 '- O" A n . A /

Y N 1 H 2.

5O 0 0 2 ,3,'4 O g l

< Top View $

I H w <

W I H

co 3>

Ym CA

> i M a b  % h rvi Y

Fri

--4 2 n- -e 5 1 N

• W ~' @

• $W

o eE a l3 \

m C3 /

$# Front Elevation ,

2,3,4 -

COOLING COIL CABINET-(IVYO3A)

REACTOR BUILDING g

. FLOOR ELEVATION: 694'-6"

- .