ML19224B285
| ML19224B285 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/31/1975 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| TM-0299, TM-299, ZAR-751231-1, NUDOCS 7906140382 | |
| Download: ML19224B285 (21) | |
Text
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SYSTEM DESCRIPTION (Index No. 45B)
REACTOR BUILDING EMERGENCY COOLING WATER SYSTEM (B&R Dwg. No. 2033, Rev. 15)
JERSEY CENTRAL POWER & LIGHT COMPANY THREE MILE ISLAND NUCLEMt STATION
. UNIT NO. 2 Issue Date December, 1975 9
Prepared by:
H.
Iskyan f
Burns and Roe-Inc.
700 Kinderkamack Road
- Oradell, N.J.
07549 197 004
,.r TABLE OF COh"I'ENTS FOR REACTOR BUILDING EMERGENCY COOLING WATER SYSTEM Section Pace
1.0 INTRODUCTION
1 1.1 System Functions 1
1.2 Summary Description of the System 1
1.3 System Design Requirements 2
2.0 DETAILED DESCRIPTION OF SYSTEM 3
2.1 Components 3
2.2 Instruments, Controls, Alarms and 6
Protective Devices 3.0 PRINCIPAL MODES OF OPERATION 8
3.1 Startup 8
3.2 Normal Operation 8
3.3 Shutdown 10 3.4 Special or Infrequent Operation 10 3.5 Emergency 11 4.0 HAZARDS AND PRECAUTIONS 12 197 005
=e4
A PPENDIX TITLE TABLE Reactor Building Emergency 1
Cooling Booster Pumps Instrumentation and Controls 2
Panel Mounted Annunciators and 3
Computer Inputs
.e 197 006
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2 -
REACTOR BUILDING EITEh3ENCY COOLING WATER SYSTEM l'. O INTRODUCTION 1.1 Svstem Functions The function of the Reactor Building Emergency Cooling Water System is to provide cooling to the Reactor Building Cooling Units in the event of a loss of coolant accident.
This system has an interface with the following systems.
(Dwg. Nos. refer to B&R Flow Diagrams.)
1.
Nuclear Services River Water (2033) 2.
Reactor Building Normal Cooling (2046) 3.
Reactor Building Ventilation and Purge (2041) 1.2 S ummary Descriotion of the Svstem (Ref. B&R Dwa. No. 2033, Rev. 15)
The Reactor Building Emergency Cooling Water System consists of four R.B.
emergency cooli~ng booster pumps, and five R.B.
cooling units containing cooling coils and fans, (see Reactor Building Ventilating anc Purge, Index No. 35A). Water is supplied to the bcoster pumps suction frcm both of the Nuclear Services River Water System headers.
The pumps are divided into pairs, each pair feeding a separate emergency cooling water header.
Each header supplies three cooling coils, one coil being fed by both headers.
The cooling unit fans circulate air over the coils.
Return water is discharged through the Mechanical Draf t Cooling Tower.
Connections are provided for circulation of normal coo.ing water through the coila (see Reactor Building Normal Cooling Water System, Index No. 45A).
The water supply to the coils is automatically switched from normal cooling water to emergency cooling wate:- during a LOCA.
197 007
= -
a 1.3 Svstem Desian Recuirements The system is designed to supply sufficient river water to the Reactor Building cooling units to adequately cool the Reactor Building atmosphere after a LOCA.
The Reactor Building emergency cooling booster pumps supply water at 6000 GPM from the two independent Nuclear Services River Water headers to the five cooling units.
The five coils are designed to remove 240 x 10 BTU /hr with a river water temperature of 85 F and a Reactor Building ambient tempera-ture of 286 F.
The system is designed to preclude a single failure during
, a LOCA.
Two independent headers are fed by two pairs of R.B.
emergency cooling pumps.
Each pair of pumps receives power from either the red or green bus.
The pump suctions are cross-connected so either pair can be lined up to receive water from either NSRW header.
In the event of a loss of a diesel, one R.B.
emergency cooling pump, feeding two cooling units and one-half of the Reactor Building Spray System can supply adequate cooling for the Reactor Building after a LOCA.
'2he system is designed to minimize the possibility of radioactive contamination of the river water during a LOCA.
Pressure control valve maintains the pressure of cooling water in the Reactor Building above 60 psig.
"his pressure is above the expected Reactor Building pres-sure during a LOCA and therefore any system leakage will be into the Reactor Building rather than into the R.B.
Emergency Cooling System.
1 -
15' 008
~:
The Reactor Building Emergency Cooiing Water S ystem is
[
conventional piping of Quality Control Level 4 except at the penetrations th rough the wall of th e Reactor Building where it changes to Nuclear Class 2 piping with a Quality Control Level 1.
The entire system is classified Seismic I and Cleanliness - D.
The piping inside the containment is designed,fabricatedrand inspected in accordance with ANSI.
Nuclear Power Piping Code 33.1.7; piping outside containment in accordance with ANSI B31.1.
2.0Property "ANSI code" (as page type) with input value "ANSI B31.1.</br></br>2.0" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. DETAILED DESCRIPTION OF THE SYSTEM 2.1 Comconents 2.1.1 R.B. Emercencv Coolina Booster Pumos, RR-P-LA, 1B, 1C, 1D The Reactor Building emergency cooling booster pumps (see Table 1) are located in the south east corner of the Auxiliary Building at elevation 280'-6".
These four (4) pumps are horizontal, double suction, single stage centrifugal pumps 4fo with a rated capacity of 3000 GPM at 160 ft. TDH.
The pump casings are split horizontally with flanged side suction and discharge connections.
The impelle-- is a closed type.
Each pump 'is driven by a 200 HP motor with split sleeve bearings and oil lubrication.
The pumps are provided with ball type Ehrust and radial bear-ings.
Lubrication of the bearings is carried out by a self contained constant level oiler and indicator.
The recommended oil level is marked on the bearing housing.
The stuffing boxes have close clearance shaft sleeves and lantern rings with internal piping and valves for recirculation of water from the pump case to the stuffing box.
The pump motors are cooled '7y Nuclear Services Closed Cooling Water.
During testing, the pump will not start without cooling water flow.
Pump indication is provided locally and 3
on Panel No. 3 and Panel No. 13.
The pump is normally controlled from Panel 3 by a TEST-OFF-AUTO-BACKUP switch.
Additionally, the pump may be controlled locally by a JOG-NORMAL-STOP.
Pumps RR-P-1A and 1B Pre powered from MCC 2-llE.
P':mps RR-P-lC and 1D are powered from MCC 2{ 4
}
i.
2.1.2 Maior Svstem Valves Reactor Building Emercency Booster Pumo Discharce Valve, RR-V2A throuch 2D One 12",
150 lb. ANSI, 85 F,
CS, electric motor operated, gate valve is located in the discharge of each Reactor Building emergency booster pump.
The valves may be controlled locally or from Panel No. 3.
Indication is available locally and on Panel No. 3 and No. 13.
The valves open on an ES signal.
Valves RR-V2A & 2B receive power from MCC 2-llEA and valves RR-V2C & 2D receive power from MCC 2-21EA.
Reactor Building Cooling Fan Unit Inlet Valves RR-V5A, SB, SC, 6C, 6D and 6E One 8 ", 225 lb. ANSI, 85 F,
CS, electric motor operated, gate valve is located in the inlet to Reactor Building fan cooling units AH-C-13A/14A, 13B/14B, -
13D/14D and 35E/14E.
RR-VSC and RR-V6C are in the inlet to cooling unit AH-C-13C/14C.
The valves are controlled by local and remote (Panel No. 15) pushbutton stations.
Valve indication is available locally and on Panels No. 13 and 15.
Those valves shut are opened by an ES signal.
Valves RR-VSA, SB and SC are powered from MCC 2-llE and valves RR-V6A, 6B and 6C are powered frsa MCC 2-21E.
Reactor Buildina Coolina Unit Back-Pressure Reculator RR-VllA throuch llE
- J One 6",
225 lb. ANSI, 2000 F, CS, diaphragm operated globe
~
valve is located in each Reactor Building cooling unit emergency discharge.
The valves are controlled by a 197 010 -
pressure controller upstream of the valve.
During operation of the RB Emergency Cooling System, the control valve maintains 60 psig in the coils so that Reactor Building atmosphere will not leak into river water discharge.
- Duri, Tormal operation with the RB Normal Cooling flow through the coils, the valves are a boundary between the RB Normal and Nuclear Ri/er Water System The valves fail open on loss of air.
Reactor Buildina Coolina Unit Normal Discharce Valves, RR-V25A throuch 25?
0 One 6",
225 lb. ANSI, 200 F,
CS, air cylinder operated gate valve is located in each Reactor Building cooling unit normal discharge.
The valves are shut by an ES signal 'o t
isolate the cooling units from the Reactor Building Normal Cooling Water System.
Indication and control is available on Panel No. 15 and No. 13.
The valves fail closed with a loss of instrument air.
Reactur Buildina Coolina Unit Cutlet Valve, RR-V26A throuch_
26E and RR-V79 0
One 8",
225 lb. ANSI, 200 F,
CS, electric motor operated gate valve is located in the outlet from Reactor Building cooling units A, B,
D and E.
Unit: C has two valves RR-V26C and RR-V79 in its outlet.
Control and indication is available locally and from Panel 15.
The valves are not r' positioned by an ES signal.
RR-V26A, 26B and 26C e
are powered from MCC 2-llEA.
Valves RR-V79, RR-V26D and 26E are powered from MCC 2-21EA.
j 4 197 011
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2'. 2 Instruments, Controls, Alarms and Protective Devices
=
The following instrumentation and controls (See Table 2) are provided to control and monitor the system operation.
Pressure transmitters and remote indicators are provided for each of the Emergency Booster Pumps.
Pushbutton controls are provided for the valves on the discharge of each of the Emergency Booster Pumps and the inlet lines to each of the cooling coil units.
Orifice plates and flow transmitters are installed in each line downstream
~
of the cooling coils for monitoring both Normal and Emergency flow Temperature elements are installed in the lines from each of the cooling units.
The output of these elements are interconnected to the computer.
An orifice plate and differential pressure indicator is located in the 10" discharge branch line for testing the discharge Of the Emergency Cooling Booster Pumps.
Flow indication is provided on Panel No. 25.
Pressure Control Valves and Pressure Controllers are provided in i
the discharge lines of each cooling coil to regulate the pressure in the cooling units to 60 psig.
This back-19/
012
precsure will help prevent contamination of the river water during a LOCA, i.e.
if there is a leak in the system, river water will flow out instead of Reactor Building atmosphere leaking in.
Pushbutton controls are provided on Panel 15 to operate block valves for each of the cooling units.
Each pump his JOG-NORMAL-STOP local control switch and a TEST-OFF-AUTO-BACKUP control switch on Panel No.
3.
One pump switch in each pair is placed in AUTO and the other pump switch is placed in BACKUP.
During testing (without ES signal) the pumps will not run without Nuclear Services Closed Cooling water flow.'
Pressure switches are pro-vided in the discharge of each of the Emergency Cooling Booster pumps to stop the pump, if its discharge pressure falls below 50 psig.
The backup pump of this pair will automatically start if the running pump stops.
Each pump has a low Nuclear River Water Suction Pressure alarm on Panel No.
8.
On an SFAS signal, all discharge valves on the Emergency Cooler Booster pwmp open.
One booster pump of each pair starts..
.. c ~
all cooling o,
inlet valves open, and RB Normal Cooling coil outlet valves close.'
With a loss of normal power and an ES signal, the RB 2 197 013
~
Emergency Booster Pumps are sequentially powered in accordance with the diesel loading sequence.
3.0 PRINCIPAL MODES OF OP] RATION
- 3. l ~
Startuo The Reactor Building Emergency cooling is not used in norma.1 power operation.
The system is in standby startup status.
The control switch of one pump of each pair is put in AUTO, and the remaining two are plTced in BACKUP.
With an ES signal, the RB Normal Cooling System will be automatically shutdown, and the RB Emergency System started up.
3.2 Normal Coeration Three of the five Reactor Building air cooling units are normally operated, using the normal cooling water system, refer to System Description Index No. 45A, Reactor Building Normal Cooling Water System.
During normal operation, the inlet valves of two fan coil units are shut, and all Booster Pumps are idle.
On a SFAS Signal the RB Normal Cooling System Pump and j
Evaporator are shutdown and isolated.
The six inlet ^
197 014
6 to the five cooling units open and.the RB Normal outlet _
valves close.
Pump suction is tNken from the Nuclear River Water Header through a check valve.
After passing througa the pump discharge check valve and isolation valve, the four 12" lines from each pump combine into two 16" headers.
The header from.RR-P-LA/B supplies cooling units AH-C-13A/14A,
?.3B/14B and 13C/14C.
The header from RR-P-lC/D supplies AH-C-13C/14C, 13D/14D ar_d 13E/14E.
Each cooling unit inlet has a remote controlled ES actuated valve, a check valve and manual isolation valve.
The twc unit C supply lines combine before entering the Reactor Building.
Inside the building are second check valves RR-V27A through E and isolation valves RR-V9A through E.
At the cooling units each line divides into six 3" lines for the cooling coils, recombining on the cooler discharge.
The discharge lines contain isolation valves RR-V10A through E, and remotely operated isolation valves RR-V26A through E and RR-V79.
After leaving the Reactor Building,
~
the discharge lines divide into 6" lines and 8" lines.
The 6" lines have remotely operated isolation valves RR-V25A
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2 through E, waich isolate the Normal Cooling Water System on an SEAS signal.
The emergency cooling water flows through the 8" lines, through pressure regulating valves RR-VllA through E, and isolation valves RR-V12A through E.
The five cooli.g unit discharge lines are combined into one 14" return line.
This line is increased to 30",
and is cross connected to both Nuclear Services River Water return headers before continuing to the Mechanical Draft Cooling Tower.
3.3 Shutdown After clearing the ES signal, the RB Normal Pumps may be stopped and the system isolated.
However, before resuming operation with the RB Normal System, the coils and it:s associated piping must be completely flushed of rive' water and normal chemistry conditions restored.
3.4 Soecial or Infrequent Ooeration Because river water should not be pumped through the fan coils, except under abnormal conditions, a test line and an associated flow element are provided to verify pump capacity.
During pump testing ahd.the normal 5
-t discharge, valves RR-V2A, 23, 2C and 2D remain shut.
- l9[ Qlf
~
Flow is directed through the pump's nonnally shut gate valves, RR-V3A, 3B, 3C or 3D, and the header isolation valve RR-V29.
Flow indication is available in the path
~
to the Mechanical Draft Cooling Towers.
3.5 Emeraency During a LOCA only two Reactor Building cooling units are required.
If a LOCA> icss of normal power and loss of a diesel occur simultaneously only one pamp will run and supply water to three cooling units.
Cooling unit C acts as a backup for either the red or green cooling units.
The pressure in the cooling piping in the Reactor Building is maintained above the maximum expected pressure the Reactor Building.
If a leak in the piping occurs during a LOCA, water will flow out of the pipe preventing radio-active contamination of the river.
A leak can be isolated by shutting the cooling unit inlet and outlet valves RR-VSA, B or C or RR-V6C, D or E and RR-V26A, B, 'C,
D, E or RR-V79.
The pressure regulat4 ag valve RR-VilA, B,
C, D
or E will shut automatically when the pressure is reduced
.~
below 60 psig.
To ensure cooling unit isolation the manual valve downstream of the pressure regulating valve should also be shut.
197 017
A discussion or the operation of RB Cooling with a loss of instrument air is discussed in System Description No. 45A.
4.O HAZARDS AND PRECAUTIONS During pump capacity testing, ensure that the discharge valve to the fan coil units, (RR-V2A, 2B, 2C and 2D) remain shut, and that there is a flow path to the river.
If the running RB Emergency trips on low discharge pressure, the pump trip should be reset by opening pump breaker.
s i
- 1 7
018
TABLE 1
' Reactor BuiAdinc Emercencv Coolinc Booster Pumos Pumo Details Identification RR-P-1A, BR-P-1B, RR-P-lC.
RR-P-lD Number Installed 4
Manufacturer Ingersoll-Rand Model No.
6x18 SE Type Horizontal, double suction, single stage, centrifugal Rated Speed, rpm 1750 Rated Capacity, gpm 3000 Rated Total Dynamic Head, ft.
160 NPSH required at rated flow, ft.
15 Design Pressure, ca s lity,
ft.
170 O
Desien Temperature, F
85 Lubricant / Coolant oil / air Min. Flow Requirements, gym 150 Motor Details Manufacturer General Electric Type Squirrel cage Enclosure TEWC Rated Horsepower 200 Speed, rpm 1750 Lubricant / Coolant Oil / Water Power Requirements 460V, 35, 60 Hz, 230 amps full load Power Source RR-P-1A and B, 480V Bus 2-llE RR-P-lC and D, 480V Bus 2-21E Classification Level Code C
Quality Control 4
Seismic I
C1..eanlines s D
5 197 019
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Ident i f icat ion
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Input Range Outint panse set Point Rm-PT-346 Press. BefrR.
Transmit biech. press. of 5==p pa-t-la to 5 sees. Indicator kack 443 Cage Frees.
0-150 pelg 10-50 M EJC N/A pm-PI-344.
RA-PI-346 Press. Indicator indloa t e se disch. press, of gamp RR-P-!A Tanel 3 Hil11 ammeter 10-50 MA tC 0-150 pelg N/A 38-PT-347 Press. zarra.
Trenmatt disch. press, of ymp Ra-P-la to press, indicator amek 443 cage Press.
0-150 palg 10-50 HA (C N/A RA-PI-347 Ra-PI-341 Press. Indicator Indicates disch, press. of pump RR-P-Is Penel 3 Hil11 ammeter 10-50 MA CC 0-150 pelg N/A Ra-vP-348 Presa. INTR.
Transat t disch. press, of ymp RR-P-IC to press. Indicator Rack 444 cage Prese.
0-150 peig 10-50 MA EC H/A BA-PI-348 f
RA-PI-348 Press. Indicator InJ! cates diach. press. of pump RR-P-lC Panel 3 Hilliammeter 10-50 HA EC 0-150 poig M/A DA-PT-349 Press, 1sfrR.
Transmit disc.h. press, of pump BA-P-lD to prees. Indt.:stor Rack 444 Cage Presa.
0-150 peig 10-50 MA CC N/A RR-PI-349 RA-PI-349 Press. Indicator Indicates disch. prese, of pasp RA-P-10 Panel 3 Hil11 ammeter 10-50 MA OC C-150 peig H/A l
Rae-fits-3 0 0 Pushbutton (gerstas block valve RA-V-3A for gamp RR-P-1A Panel 3 C-H Type E-30 N/A N/A N/A Ra-Pits-3 09 Pushbutton (gerates block valve RA-V-38 for pump BR-P-It Panel 3 C-H Type E-30 N/A N/A H/L Ra-Pits-390 Pushbutton operates block valve SA-V-2C for 5***p BA-P-1C Panel 3 C-H Type E-30 N/A N/A
'4/A pm-FILS-391 Pustbut ton (perates block valve RA-V-3D for pmp RR-P-IC Panel 3 C-il Tyge E-39 N/A N/A N/A RA-P13-1015 Pushbutton Operates block valve RR-V5A for Cooling Colle AH-C-13A 6 Panel 15 C-H 'Iype P4 A N/A N/A N/A l
AH-C-14A SA-PILS-1017 Pushbutton oper.tes block valve RA-V5s for Cooling Colle AH-C-138 6 Pacel 15 C-H Type E O H/A N/A N/A I
AH-C-148 i
RA-Pats-1019 Pushbutton (pastee I' lock valve RR-V5C for Cooling Colls All-C-13C &
Panel 15 C-H Type h:-30 N/A N/A N/A AlH:-14C an-P12 1030 Pushisut t on rgerates block valve Ra-V6C for Cooling Colle Ais-C-13C 6 Par.el 15 C-H Type E-30 N/A N/A AIM-14C RA-PhS-1023 Pustbutton (4erates block valve sm-v6D for Coollrq Colle AH-C-13D 6 Fanet 15 C-H Type E-30 N/A N/A 4/A g
AlW -14D l
I RB-Pis-1034 Pushbutton Operates block valve RS-V6E for Cuoling Colle All-C-11E 6 Panel 15 C-H Type E-30 H/A N/A N/A fN' AH-C-14F f..a. See arr7 3a
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-INSTidMWifTA rlON aND CC4fTHOI9 Identification fan scr i pt io*.
runction riping ortfloe 0-1800 cru 0-100 W 0 W/A 2
Detect flw for f1w transmitter pJt-rT-1025,1026,1027 33-rs-1025, 1026 Oriftee 1024 and 1029 respe-.voly pack 428 for D/r Cell 0-100*
10-50 MA tc M/A 3C27, 1028 6 1029 Trane=lt differential pressure algnal to equare soot l 8 1025, 1026 converted RA-rY-1025,1026,1027,102e end 1029 respectively pa-FT-1025, 1036 rlw 1021, erra at 1027, F28,1029 Tsaneetttes for 1028, 1029 i
ge Cable Room sq. at.
10-50 NA tc 10-50 MA DC N/A Convest differentist pressure signal to flw elgnal for Convester am-rt-3045, 1026 square poot indicatore Anett-5620, 5621, 5623, 562) and 5624 tonel 25 vertical D!st 10-50 HA DC 0-1500 CPn M/A 1027, 1026 s 1029 Converter
. i Indicates water flou through peactor D*'.adis>3 cooAirg rette M1111 ammeter Alt-rl-5620, 5621, riaw A,
F., C, D and a sospectively 5422, St2l,e 5624 Indicator i
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Piping tasel Rtt).
0-225 r 92.92-141.94 M/A Temp. Detect. - B.B. Air Cooling Colle A outlet.
SA-TB-3040 Ex4el RTD signal for computer I
0-235*r 92.92-141.94 N/A Piping taael RTD Temp. Castec t. - R. S. Air Cooling Colas B outlet.
r.A-TE-10 41 thaal RTD signal for cosaputer.
outlet Paping tasal RTD 0-225 r 92.92-141.94 N/A Temp. Detect. R.B. Air Cooling Colle C RR-T3-1042 thael RTD signal for computer RA-TR-1043 Dual RTD Temp. Detect. - R.D. Air Coolang Colle D outlet Piping tasal RTD 0-235 r 132.92-141.94 N/A signal f or oc=puter 0-22 5* r 92.92-141.94 N/A Piping tasal RTD outlet.
Tamp. Detect. - R.S. Air Cceling Colle a pa-TE-1044 Dual irrD signal for computer.
renet 15 rust.bu t ton H/A N/A N/A mm-rits-156)
Hand suitch operatee 1. lock valve Ra-v25A 3.3. Normal cooling ranel 15 Pushbutton W/h N/A N/A Operates block valve Ra-V253 P A-rHS-15 61 isand switch
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p.e. normal cooling.
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u-Pin-1562 Hand swito.
Operates block salve RA-V35C R.B. normal cooltreg.
Panet 15 Pushbutton M/A N/A1 M/A i
RA-PIS-1561 Hand Switch Operates block valve RA-V25D R.B. normal cooling.
Panel 15 Puollutton N/A N/A N/A RA-Pto-1564 Hand Switch Operates block valve RA-V355 R.B. normal cooling.
Panel 14 Punta.tton M/A N/A N/A RA-PE-1755 Oritice Orifice plate sc r RA-Del-l?55 Piping orifice 0-3000 GI'M 0-180*H 0 N/A 2
RA-DPI-1755 Diff. Pr e s e.
Plow Indicator for local test Mtg. A41 pourdon Tulse 0-100* 48 0 0-250* H 0 N/A 2
Indicator RA-K-3541 Press. Controller segulatae RA-VILA (RA-KV-3541)
Piping Dourdon/
J-150 pelg 3-15 peig 60 pelg Bellows Diel'graV 3-15 pelg H/A 60 pelg p-PCV-3541 Press. Control Controla AH-C-13A/14Aoutlet Press Piping 4
Globe RA-rc-3 5 8 3 '.
Prese. Control Regulatee Ra.v11a IRA-nCV-3642)
Piping bourdon/
0-150 polg 3-15 peig 60 peig Bellowe RA-PCV-3543 Press. Cont.
Controle AH-C-13n/14e outlet Press.
Piping plagAgram/
3-15 peig M/A 60 poig Valve Glolee u-sc-3543 Prese. Contr.
Regulates M-V11C (RA-KV-3543)
Piping Dourdon/
0-150 peig 3-15 peig 60 peig Bellows i
p -PCV-:3543 Press. Conte.
Controle RH-C-13C/14C outlet Press.
Piping Dia6Agram/
3-15 pelg M/A 60 peig Globe Ra-K-354 4 Press. Contr.
Regulates RR-V110 (RA-KV-35 44)
Piping Bourdon/
0-150 peig 3-15 pelg 60 peig Bellowe e
RA-KV-3544 Prese. Contr.
Cosetrole AH-C-13D/140 outlet Pressure Piping Dia6Agram/
3-15 pelg H/A 60 peig Glove RA-K-3545 Press. Controllar Regulates RA-vils (u-KV-3545)
Pipiry Bourdon/
0-150 peig 3-15 peig 60 54 t g Bellows RA-ICV-1 * *
- Press. Control Pressure Control valve Piping Diptera =/
3-15 peig N/A 60 peig i
Globe uR-Plo-3546 Hand Switch Operates block walve RA-V26A Co11
'A' Out14t Panel 15 Pushbutton M/A N/A H/A En-Pie-3547 Itand switch Operates b!ack velve RA-V26a Colt *aa outlet panel IS Pusthutton H/A H/A n./ A i
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TAbts 3 (Conlinued)
IlUTMe4La.hv10N AND COtmtGL Ime t ton, h
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_ Output Ra ng e 6et Point IA' s,oation g oodpt h Punction Panet IS Puelhutton M/A N/A N/A 33.Ph3 354e Hand switch Operates bloek valve SA-V36C Coll *C' Outlet.
Panet 15 Pusthutton H/A N/A N/A 33.rus.3549 Hand switch Operates block valve Ra-V36D Cell "D" (Antlet.
Panel 15 puntautton H/A N/A N/A RA-Pus.3550 HanJ Switch Operates 1. lock valve RR-V365 Cell *8* Outlet.
Rack 441 Diaphragm 4-400 pelg N/A 50 peig sm-N-3561 Pr es s, Pwitch polemeos droy out circuit RR-r-1A, starte RA-P-13
=,ck 443 Diephrage 4-100 peig H/A 50 pelg 33 59-3563 Press. Switch peleasse drop out strault p*-r-la, starte pa-P.1A
.ck 444 Disphrage 4-100 pelg H/A 50 psig 3a.95 3563 Press Switch palesses drop out circuit RA-P-IC, starte RA-P-ID Sm PS-3564 Press, ewitch peleases dzop oat circuit Ra-P-10, starte SR-P-1C Back 444 Diaphragm 4 100 peig H/A 50 peig Panet 15 Italbut ton M/A N/A N/A RR-PHS-3433 Hand Swi tch (perates block valve RR-V79 Panel 3 SbH H/A DVA M/A pg.y1A.H13 Hand Switch Operat RA-P-1A nanal 3 8Ha H/A N/A N/A km.P13-HIS tLadd switch Operate RA-P-1B Panel 3 SBM H/A N/A N/A RR-PIC-H13 Hasus $ sis.h Operate RR-P-1C Panel 3
$bH H/A N/A N/A 33.PIO-H13 Itand bd tch Operate R2-P-ID G
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TAbiz 3 CN I*taL WNarTED Atee ACIATuta Alase H1 Izad Input Soutoe Var, Ranjo Patel n,.
identification No, Ma sured Ve r t able, tan t t e _
H/A N/A Pump Ou's nyh a
R.W. Emstgency Cool.ing sooeter Puse, Trip.
.I RR-LA-4539
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CCs4WrER IWPtRS
- r WA N/A BR-715-10 4 0 0-4 081
- R.e. Cooli.v3 Coll Unit A Chatlet Teagera$are.
1020 H/A N/A PA-TI-1041 0-Re P F
R.a. Corting coil trnit, 3, Outlet T w erature, 1021 N/A N/A RR-TM-1042 0-309 R.B. Cooling Cc!! Unit, C, Chatlet T**6erature, F
1022 N/A VA RR-TE-1041 0-200 R.S. Cooling coil Unit. D Outlet Tongerature, 't 1023 H/A N/A RR-Ts-1044 0 200 R.S. Cooling Cell Unit, E, Outlet Toegwrature, F 1034 H/h H/A
- 012, H/A R.S. Emergency Cooling Booster Puey, BR-P-11, overload 2639 WA WA 012 H/A R 8 tmergency Coo 11u3 Booster Pump, RR-P-la, overload 2540 N/A N/A 014 N/A R,s smergency Cooling sooeter Pump, RR-P-1c, overload 2641 N/A VA Out N/A R a, Emergency Coolin3 Boo ster pump, RR-P-10, overloeJ 2642 M/A WA RR-PT-346 0-150 peig 8..B. Emergency Cooltag Booster Pump, RR-P-1A, Discfarge Press.
0170 N/A N/A PR-PT-347 O-150 peig 0171 L.B. Emergency cooling Booster Puse RR-P-18, Dischange Prese.
H/A N/A BR-PT-348 0-150 peig Emergency Cooling Bocator Pump, RA-P-1C Discharge Pruse.
0173 A.B.
0173 b.s. Emergency Cooltr=3 booster Pump, DR-P-to. Discharge Press.
H/A N/A ka-PT-3'S 0-150 psig
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