ML20069H478

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Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan. W/Three Oversize Drawings
ML20069H478
Person / Time
Site: Rhode Island Atomic Energy Commission
Issue date: 06/01/1994
From:
RHODE ISLAND, STATE OF
To:
Shared Package
ML20069H472 List:
References
PROC-940601, NUDOCS 9406130168
Download: ML20069H478 (27)
v • d • e


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RHODE ISLAND NUCLEAR SCIENCE CENTER l PROPOSED 3 MW OR HIGHER EMERGENCY . CORE COOLING SYSTEM PLAN l 1

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-l 9406130168 940601 i PDR ADOCK 05000193  !

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i TABLE OF CONTENTS PAGE i Introduction 1 Loss of Coolant Review 2 3 MW Decay Heat 3

  • Facility Water Supply 4 l Fire Pump Test Results 5 l Present Pool Fill System Operation 6 f Proposed Emergency Core Cooling System Operation 6-7 f ECCS Water Supply analysis 8 i i

Table A 9 Pipe Sizing Calculation 10 l Conclusions 11 ,

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APPENDICES .

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-A- ECCS Major Equipment and Components

-B- Plans l

-C- Piping Schematic .;

-D- Instrumentation Schematic j i

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r INTRODUCTION The Rhode Island Nuclear Science Center research reactor has a design capability of 5 MW (thermal power) level. The current license level of operation is 2 MW. The recent conversion to the LEU fuel necessitated a Safety Analysis Review (SAR) which addressed a postulated loss of coolant. The Nuclear Regulatory Commission approved the SAR and related information for the 2 MW case.

This report addresses the 3 MW situation and the proposed emergency core cooling required. Since the original GE reactor design did not include provisions for emergency cooling, it was necessary to originate a design plan which would incorporate some of the positive features available at the site.

If the basic plan, herein described, is acceptable, a final refined version can be formulated in order to obtain a higher power license (3 MW) in the future.

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LOSS OF COOLANT REVIEW The SAR (Part B,Section X) calculated that the loss of coolant from the pool could occur through a 1/2" diameter hole in a beam port experiment and the 1" beam tube vent drain. The calculation from Section XIII, Appendix C of the SAR showed that a minimum of 3.76 gpm was needed to keep the core box full (assuming water was directly flowing into the core box). A typical calculation to determine what flow rate would be required to keep the cool full while the maximum ,

draining is taking place is shown below:

F= . 61 A [ 2gH ] 1/2 = .61(006176) [2 x 32.2 x (139.917-114.463)]

F= .15 x 7.48 x 60 = 67.78 gal / min Using this equation, A " flow rate vs. elevation" table was developed (see Table A of this report). In addition to the normal make-up water system, the proposed ECCS is basically a

" redundant" water supply line, a 2" line which serves as a deluge type of discharge to the pool (thereby eliminating an expensive piping system fabrication to the suspensinn frame and down to the core).

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3 MW DECAY HEAT The SAR (December 1992) for the 2 MW LEU core shows calculations for decay heat generation (Section X) during a LOCA such that it would take 10 1/2 hours to expose the core and that melting would not occur.

T Assumption #5 included the remote possibility that the automatic fill line also did not operate upon loss of coolant.

Applying the decay heat curve to the 3 MW situation and knowing that the core must have sufficient cooling until such time that the decay heat has reduced to .049 BTU /sec.

For 3 MW Po = .1 x 6.187 = 9.28 BTU /sec (plate) 2 Po = .049 = .00528 l 9.28 I Frcm the decay curve (Table 5.1), the time after shutdown is about 7 x 104 seconds or 19.44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.

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FACILITY WATER SUPPLY The Wakefield Water Supply Company provides water to the University of Rhode Island Bay Campus. The Rhode Island Nuclear Science Center facility is located on the Bay Campus.

The water is supplied to the Bay Campus at 30 psi to the 30,000 gallon tanks. The tank booster pump delivers water at 55 psi to the distribution system. If pressure drops or more flow is needed the fire pump comes on boosting flow rate and pressure to 85 psi. All 3 pumps in the system have emergency generator backup. The Bay Campus demand (1992 records) is about 83 gallons / minute, including the reactor building. l This means that a reserve supply in the tanks exists for 602 hours0.00697 days <br />0.167 hours <br />9.953704e-4 weeks <br />2.29061e-4 months <br /> for normal Bay Campus demand.

A copy of the fire pump test results conducted for the system by Keily Associates, the da-ion firm, is enclosed. j The reliability of the system was discussed in the SAR dated December 1992 in Section B, IX.

Refer to the plans in the appendix for the system piping.

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KlELY ASSOCI ATES LTD.

9 1.:\ NI S LOUISQUISSET FREEWAY

  • MINERAL SPRING INTERCHANGE
  • P. O DOK 6644. PROVIDENCE. RHODE ISL AND 02940 TELEPHONE 724 8850 January 30, 1985 l l

Otis C. Wyatt Jr., Chief l Narragansett Fire Department 40 Caswell Street Narragansett, Rhode loland 02882 he: Fire l' ump Tes t l

Graduate School of Oceanography

  • University of Rhode Island Narragansett Bay Campus

Dear Chief Wyatt:

We would like to acknowledge and thank you and the members of your staff for their attendance and interest during the January 29, 1985 fire pump test at Narragansett Bay Cam-pus, University of Rhode Island.

The Peerless fire purnp , Model 8'AF 2 0 H , nominal capacity of 2000 GPM vs 85 psi, 1775 RPM, 125,HP, 3P, 600, equipped with a Firetrol Model FTA 1500/FTA 900 Controller, was dis- .

charged thru a Dieterich Model ANR permanent flowmeter and l produced the following results: 1 2000 GPM - 2200 GPM at 85 psi 3000 GPM - 3200 GPM at 55 psi  !

It would be appreciated if you would attest to the observed l results, by countersigning this correspondence and return-ing to our office at the above address.

We have enclosed, for your record and file, a copy of results of Test //169248, as performed by the Peerless Pump Company, manufacturer of the fire pump. .

Very truly yours, KIELY ASSOCIATES LTD Attest:

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. Daniel J Kiely DJK/fa Otis C. fY t., ' h1Tf .

enclosure Narragan e t F .- e 1 cc: Mr. Richard McGannon, GSO, URI Departme ,

Mr George Erban, GSO, URI Mr. Robert Stewart, URI 5 j L __.

PRESENT POOL FILL SYSTEM OPERATION The existing pool is filled through the make-up line from the make-up demineralizer. The system has an automatic electrically operated valve which opens when the pool level float switch 31 activated due to a drop in pool level. The pool fill valve has a manual by-pass valve in case the electric valve fails. At the present time the electrically operated float switch and electrically operated valve "do not" have emergency power.

It is proposed that, for 3 MW or higher, these components should be tied into the facility emergency generator power supply system. Measurements reflect that the system can ,

provide 25 gpm (minimum) to the pool.

PROPOSED EMERGENCY CORE COOLING SYSTEM OPERATION (Refer to the Emergency Core Cooling System (ECCS) Schematics l in the Appendix)

In addition to the present pool fill (make-up) system, major components of the ECCS will operate under AC power with emergency power backup from the emergency generator. This ,

assures operation of electrical components with loss of AC power.

The reactor control system will require the addition of two scram circuits to be used for 3 MW or higher. The first is the ECCS water line pressure sensor which monitors the feed line. A drop in normal water pressure below a preset valve  ;

will scram the reactor.

The second scram function would be that of the automatic (AV)

ECCS water line valve opening, either from a signal from the (LS) low pool level switch or an electrical malfunction.

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The proposed pressure sensor, level sensor, automatic valve ,

l. (position indication) components will have remote readout [

capability for both the control room and the Emergency Control Center (ECC). The line also contains a flow meter  !

j- for actual flow measurement during testing or a pool fill  !

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event. This unit can also have a remote readout capability.

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! The (AV) has a manual override in case of the failure of the l electrical activator. The manual valves #2 and #3 are used l: for a system by-pass flow test.

t Manual valve #1 is used to isolate the system. It is to be  ;

i locked open. It is proposed to ' provide "after hours"

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monitoring of the ECCS by integrating it to the facility f l surveillance system. All the other components are located in j the reactor room.

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l- Proposed activation of the opening of the ECCS AV is from the l low pool switch. The unit has a low level setting (10"-254")

which would be set for a drop in pool level of 6 feet (el.

133'4"). While filling the pool to a 3 feet rise (el.

j 136'4"), the unit would shut off and reset. This prevents.an-

overflow situation.

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ECCS WATER SUPPLY ANALYSIS i An analysis of the 4" supply with the proposed 2" line supply to the core, was performed using a computer program called Service Sizer".U)

The program has built-in piping tables, valve and fitting tables and fixture unit tables. Input to the pipe size 4

calculation includes demand flow, demand pressure elevation difference, supply pressure, pipe length, other equivalent pipe length losses, numbers of value and fittings and also a permitted velocity. The program output includes calculated pipe size, actual velocity, head loss and demand pressure.

The pressure (supply) at the 4" pipe entering the building is based on the accompanying fire test report. Due to high pump i pressure available, the proposed 2" line (ECCS) should have a  !

pressure reducing value. A 55 psi setting is more than adequate for expected demand. The valve would prevent t l excessive line pressures when the Bay Campus fire pumps are ,

in use or when testing is conducted.

I The analysis was performed with a 55 psi supply pressure. The

, enclosed computer printout summarizes the results. j i

i (1) Parkcon, Inc., 250 N. Center Street, P. O. Box 5980, Woodland Park, Colorado 8086-5980 8

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l TABLE A I I

l HEAD ABOVE CENTER CALCULATED MAXIMUM OF BEAM PORT FLOW RATE (GPM) FROM BEAM PORT 24.954 67.78 22 63.64 20 60.68 18 57.57 16 54.27 14 50.76 12 47 10 42.9 8 38.38 6 33.23 4 27.14 1.25 (top of core box) 15.17 It is assumed that (1) the gate valve to the beamport vent line is not shut (2) The beamport " shutter" is not in the down position 9

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, --S1 ZING CALCULATION------------------------------------Printed On: 5/13/1994 i

supply Location: Reactor building 4" supply line 55.0 psi, supply pressure available during demand l r

Demand Location: Reactor pool 47.0 gpm demand flowing at 37.0 psi pressure ,

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--Head Loss Data--------------------------------------------------- ----------

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Elevation Difference: 30.0 ft (minus if demand location lower than supply i

Pipe Length: 150.0 ft Other Loss In Equivalent Pipe Length: ft Number of Valves & Fittings: ,

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Corp Stop  : Curb Stop 3: Gate Valve  : Globe Valv  : Angle Vald

' :Bfly Valve  : Swing Chk 1: Side Tee  : Straight T 10:Std Elbow'

Long Elbow :45 Elbow -

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Gackflow Prev: psi Water Meter: psi PRV: 1.0 psi Other: psi

--Design Calculation---------------------------------------------------------

Permitted Vclocity: fps Pipe Type: CUM Calculated Pipe Size: 2 iq

, i Actual Velocity: 4.8 fps Head Loss: 17.8 psi Pres at Demand: 37.2 psi

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--DEMAND CALCULATION-------------------------------------------------------~~j Predominantly Flushometers: N Public Use: dj

-NumberofFixtures----------------------------------------------~~~~-------k i

Bathtub  ; Bar Sink  : Bidet  : Clothes Washr!
Cuspidor  : Dishwasher  : Drinking Ftn  : Hose Bib  !
Kitchen Sinh  : Lavatory  : Laundry Tub  : Shower. Head i
Service' Sink.  : Urinal Pedest  : Urinal Wall  : Urinal Tank' l
Wash Sink  : WC Flushomett- :WC Tank  :  !

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Additional: fixture units Total: fixture units Continuous Demand: gpm Fixture Demand: gpd Total Demand: spd i

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CONCLUSIONS '

A postulated " Loss of Coolant" accident to power levels above the existing 2 MW licensed power level would lead to possible reactor core damage due to heat generation. The decay analysis defines the need for additional emergency cooling water during decay time.s up to 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after shutdown at 3 MW. The existing pool feed system is capable of supplying about 25 gpm, enough water to maintain the entire reactor pool at about 2 ,

feet above the core box (see Tab'e A). The proposed emergency t

core cooling system could provide about 47 gpm, enough water to maintain the pool level at about 10 1/2 feet above the core box-at maximum water loss. Together the two systems could provide about 62 gpm. In the unlikely case of a simultaneous loss of coolant accident and termination of water to the Wakefield Water Company, the Bay . Campus storage tanks are capable of supplying reserve water for an extended time sufficient to reduce decay time to below the minimum for core damage. ,

The above analysis is conservative in a number of areas. The  !

LOCA assumes maximum drainage times with no operator actions to close the beamport shutter, close the vent line drain, etc. 1 The water supply and the proposed ECCS are safeguarded from -

electrical power loss with emergency power backup. l It is our conclusion that the proposed system can sustain the proper level of cooling required and maintain acceptable levels  :

of reliability within minimum risk. l 11

ECCS MAJOR EQUIPMENT AND COMPONENTS (1) Pressure Switch Omega, PSW-327 (2) Level Switch Omega, LV-222 (3) Flow Meter System Omega FTB-109 (4) Manual Valve Apollo 71-108 (5) Automatic Valve 2" Apollo 71-108 with EVA-Acuator (6) Pressure Reducing Valve 2" Series 25 AUB (7) Piping and Fittings 2" 304 Stainless Steel (8) Miscellaneous Switches, Gauges, Indicators,-etc.

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FTB-102 l 991 l .75-7.5 l l l i _ -
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PSW-329 230 80 to 400 PSI .56 to 2.8 MPa 6 to 11 2400 PSI TWO 15A SPDT PSW-330 285 200 to 1000 PSI 1.4 to 7 MPa 10 to 42 12000 PSI TWO 15A SPDT b'. -

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Q 290 20 to 100 PSI {140 to 700 kPa 2.8 to 5.6 1000 PSI TWO 15A SPDT

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i 4"51240 sgi  ; i NSET me JLV-220 Series switches are SPECIFICATIONS

roprocessor controlled non- af iI sact dual point level devices. Range
10" to 180* (25.4 cm to 460 cm)  !

!l i fuse ultrasonic echo Repeatability: 1.25" typical hnology to measure levels operation Modes: Four switchable

%rately from 10" to 255" from the modes (only 2 relay outputs); He and Lo; f-AutoEmpty/ Auto Fill (can be set for both lsor face (25.4cm to 648cm). To * "

  • finate costly down time, a built in l .

Ultrasonic Frequency: 50 KHz 31 epprocessor ehminates the use Beam Angle: Conical 12*(typical) It

_ ibration targets and permits Enclosure Type: NEMA-4 watertigist asurements with a repeatabihty explosion-resistant: Class I, Grriup C &

i? to %" The LV 220 level D; Class 11, Group E, F & G; Ciass 111 iches are, compact units Transducer Material: CPVC at Kynare .

n #1GHLIGHTED MODELSSTDCKED

. oining sensor and electronics Up to 50 PSIG (3i2 kg/cm2) operating can be installed or removed for pressure FORFASTDELIVERY ce Without special tools or Temperature Range: Sensor: -22*F to How to Order j ctions. Four operational modes + 158 F (-30 C to +70 *C', ._

p itch selectable: independent low alarm, automatic fill, Electronics: + 10*F to 158'F (-12*C to 70 C),(operating)  % g _ _,

l atic empty and high/ low level Weight: 8 lb (3.6 kg)

LV-221 $1240 CPVC 5

. For a wide range of Operating Power: 115V,50/60 Hz; 230 V. ;j l compatibility, the sensor is 50/60 Hz or 24 Vdc optional LV 222 1366 Kynar* g bla in CPVC, Kynar' or Switch Contacts: 2 SPDT Independent:

To order units with 24 Vdc power, add suffix h gt, 5 A at 24 Vdc; 3 A at 115 Vac; 2 A at 3 230 Vac (non-inductive load)

-24V to model no. Add $72 to cost. To order umts with 230 Vac power, add suffix -230V to r y

.g Power Consumption: 2 to 5 watts

% model no. Add $100 to cost. 1 7 Mounting: 2" NPT Ordering Example: LV-221-24V cafts for a g w' .

9 J CPVC Type Level Switch w;th 24 Vdc Power. is 9

=

M Price $t240 + 72 = $1312.

4 yy 4-K-6 CedW }r mggy p.'

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n. .m - - ~~~~ " W W oc ^w - = ~ ~ ~ ~ ~ " " " ~ ' ~ ~ * ~ ~ ~

-~ -

m 71 .W, b e n.eS 3 ronze Apo. .o*

O Wita Y- ourr:ing .3.ac y , y.

FEATURES o Designed for deadman spring return handle, '

actuator mounting and panel mounting o Reinforced TFE seats and stuffing box ring o Meets WW-V-3SC Type: 11 Composition: BZ Style: 3 E

l' OPTIONS s [

o Deadman spring return handle through 2" D o 316 stainless steel ball and stern k ^2 ~

o Adjustable stop lever o Static grounding devices A

C

(+)

v 7 l;j

}

o Rough chrome plating D o Steel tee handles through 2" *8* "

o Round handles through 2"  : c  :

o Original balancing stop ,

y o Virgin TFE seats and seals .p_ ,_ g __ l l Sees 4" h to 2" &

-g f '

TAPPING. H -

  • =4 G'
  • 3 W \

TAPPING: H + t 8 VYV+%\

^

( ('

---* F "

f ,

,/ ,

u 0 ) J T Stze ,

1 I

BRONZE - THREADED NUMBER SIZE

  • A B C D E F G H  !71-104  % .68 1.50 3.00 2.12 4.87 .87 1.37 10-24 NC 71-105 1 .87 1.68 3.37 2.25 4.87 .87 1.37 10-24 NC .

71 106 1% 1.00 2.00 4.00 2.62 S.50 .93 1.50  % 20 NC fl 71 107 IW 1.25 2.18 4.37 3.05 8.00 .93 1.50  %-20 NC :i r-. -

71 108 2 1.50 2.34 4.68 3.24 8.00 .93 1.50  %-20 NC l v 71-100 3 2.50 3.37 6.75 4.12 8.00 2.75 3.37  %-20 NC -

NOTE: Cv factor same as 70100 Senes. 'For sizes other than shown, see 77-100 Series. !i t

11

_4 Apo:.:.o' EVA Series lec:ric Ac:ua: ors t

'C-s N s

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m. m' te weu,m_.p. ,y i a .. . . . 76,d 7',A Fy ,

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  • 1 '

e"ms w;g ys .c lc m.3 LM.AA .. . di. ,. J ,,,

h Higiigats anc Ac. vantages i o Fe' manual c,vernde standard on a!! umdirectional e Rugged cast alummum housmg and cover; gesketed at i through nhaf ted morMs Sunply turn the shaf t in the joints and sealed at all penetrations for watertight  ;

norma! rotational direction (up to 1809 NEM A 4 ratmg.

o 'I< p cf all nha!ts actc as valve position indicator on all

  • Prewired terminal stnp on all through shaft models.  ;

nm wh nuMs

  • Built m open and closed position mdicatmg hmit switch oi- . ntly lubnc ated tuHy enclosed gear tram. concacts standard on all models.

n oI: n cut. heat treated ahoy steel gears for durabihty

  • Compact and lightweight construction (7-8 lbs.). j

{ u ni structural mtegrity

  • Choice of rugged simple shaded pole motor for  ;

's a A ut0matic thennal uverload protection built into all AC unidirectional models and low current draw. -

mc mrs capacitor start AC or permanent magnet DC motors for reversible umts. All with the same output torque rating.

Specifications Operating Temperature - 40c t > 150" F Entry . Ni T Conaua Q nnet tivn Enclosure - Nawrnaht NEMA 4 Limit Switches - - Open and Cosed Positan Control and Indicanon 11 Amo @ 11Sv.

Duty Cycle - Umdireen:nai IS& below 100* F except 700 #1N Senes 5% oelow 100 F AC Heversible - 20 start,s/)hr.  ;

C.mun.a bn tanon DC 25 9 below 100* F Mounting = AC mver -ab:e and DC na restrn; tons AC umdirecton al - Shatt must be honzontai or above O!m *.'t ! vtary L:r sh.es Leiaw honzontah Stanc arc. Options anc. Accessories o Voltages - Urnduectonal rede!s .!4 I15 & 220v 50/60 Hz . Ac & 12 & 24v DC. Reversible AC models 11Sv S0/60 Hz. DC models 12 24 & 48v o Limit Switches - Can b, ordered with one or two additonal ad;ustaMe hmit switches

,- 3 o Potentiometer - Can be rdered wnh a 1000 OHM 2 wan 10 ; > hneanty (reversible made:c < 2:y) l() o Hssters - Thermostancauy connoiled stnp heater element o Extra Corrosion Resistant - NEM A 4x endosure mc!udes corrosien resistant epoxy paint and stamless steel f asteners

[

o Fct adJenal remm>: ..nts contact your loco! representative o NOTE: !n a:! anhcaonc ach EVA Actusar rnust be cent Med by an indiv; dual set ci e ertnca! centact pcles j 75 I

1 3 l Water pre 55Mre

.- hh Serie. us rw mus meets the rewirements of A.S.S E. Std,1003. ANSI A112.26.2 CSA Std. B356;

, r e d U CIft g V a IV e 5 Sournern Standard eiumbing cooe and is listed by IAPMO.

( ,

i Series US, USB Series 25AUB STANDARD CAPACITY Water Pressure .

Bronze Body Reducing Valves with Integral Strainer Water Pressure Regulator f or residentbl.commercialandindustrial For supply water pressures up to 300 lbs.and can be adjusted from apphcations. Furn:shed with union inlet 25 to 75 lbs. The standard setting is 50 lbs. The by pass feature connection with threaded tailpiece, for incorporated into these valves accurately controls build-up of system sites h" through 2" Suitable for initial pressure and thermal expansion by equal-pressures up to 300 lbs Reduced pressure iring the system and supply pressure when range 25 75 lbs. Set for 50 lbs no flow relief setting is in excess of available j pressure unless otherwjse speafied supply main pressure. Max. temp.180*F. g Max. teniperature 180 F. USB

  • Renewable stainins sted seat with Gauge .

w th Gauge ; i Suffix GG / *. S t8'"I"5 5'"l in tmal """ . Suffix GG

  • N'gh temwature mm% mnte OPTIONS %" 2" Suffix:

diaphragm f or hG or coht water LP low pressure range 10 35 lbs, Set f or 3016 no flow pressure. Max. A,,.._l_ DPTIONS (Suffixh pressure 200 lbs. Max. temp. 200 F. t

! S with sweat union inlet x NPT outlet HP high pressure range 75100 lbs. i c DU -with threaded union inlet and outiet Set f or 90 lbs no flow pressure.

r' g_ y { gg .with gauge tapping and 0-100 lb. gauge S sweat union m!et connections.

OPTIONS %" 1" k 1 A

, 4 d s SC sealed sprinD cage f or hi. rise appbcations S-DU Sweat union inlet and outlet #*

Z3 f or waterworks pit installations.  !

REM- ^" HP High pressure range 75125 lbs.

Has sealed spring tage and corrosion. Set for 90 lbs. no flow pressure.

resistant u}vsting and cage screws Z3 for waterworks pit installations. Has scaled SC sealed '.;pring cage f or hi rise USB BY PASS FE ATURE spring tage and corrosion resistant adjusting apphcat ons. and cage screws %"- 1" "1 G9 with 100 lb. gauge and tapping. j) Z7 400 lb. max. initial pressure %" only s l

\ lhoon body rmnt ocNn i m uso ,,

p! . } p nun. .i " No Sue llached DIMENSIONS Hnched hght n

\C n

f a Sta. nim steel mtep! stramtr j gg d[lY/ 25Au8 3s 2 1/2,3 :4 5 2 1 4 3 D ibs

  • Rantmble stainicu sitel seat
  • %h urnpechture reinting diaphragm 25AuB MAuB tRIW D4 204 25 Au 8 2 1 6 93 a 304 2

W2 4

63c4 202 242 20 602 ibs D 10 Ws 151tn

- gf[kj4 O

Series USB Sizes %" 2" - has built in, thermal expansion by-pass equanting f eature to relieve thermal expansion in closed systems.

i However, to be effective, the pressure rehef setting of a rehef valve must be highet than the available supply main pressuie to the reducing va!ve. Latest allowable working pressure standerds f or gas and electric water heaters is 150 lbs. which exceeds the niajority of supply pressures.

Inlet DIMENSIONS Sin C on nec tio n A B C Weight

  • b Umon bV l's 5" 4lbs ,
  • 34 Umon Gh" 1%" 5%" b lbs.

I' Union 6%" 2" 6" 6 lbs ,* ,

1 '4 " U n.o n 'A" 2W 6%" 9 % lbs.

1%" Umon 9 '/2 3" 6%" 14 4 lbs 2" Unmn 11" 3v 9" 23lbs Save on energy - The EPA estirnates that 30% of the water used in households is heated. Reducing consumption also saves on

'US avadable m W. W and l',si2e only. enugy.

F LOW CAPACITIES Save 00 wastewater - When we can save 1/3 of the water Chart shows the flow capacities in gallons per minute based on average previously Consumed, this al,,o represents a similar saving of water conditions and reduced pressure fMI.ctf due to demand. For specific which will not be going into S a sewer system, rapatitws under various flow conditions. refer to F-US.

Cgaaties shown are based on a difference of 50 lbs. or rnare between , go;cg guc;t .

the m.ba! pressure a 4 the regalator lock up pressure. Where this es much water tlows runmng time l '~~ As d tferents $s less than 50 its.. deduct 20% from capacity shown- at 150 lbs. than 50 lbs., most of which . Q .?%

7 50 . res 30 T-Series  %~  %,, 1,, 1%. 1%. 2 2%o 3,, 4.,

< US,USB 17 27 40 50 64 100 - - -

is wastes.

Reducing the water \ 65 - J6 n 1 i 25 AU B 16 25 38 52 60 85 - - - pressure win result too, #  ;

in savmg because kss

- 223 23 36 50 88 132 162 170 - - water tiows at lower 7o- ,, q ,

N2238 - - - - -

- 285 375 - 8 *55"*

N223F - - - - - -

- 210 - t 127W - - - - - -

- 250 300 Write f or our "23 Q& A's" brochure on water and energy savings.

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ECC INSTRUMENT BLOCK DIAGRAM SENSORS WATER O POOI. LEVEI POSITIONS FLOW O PRESSURE d

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(3) Reactor Room ECCS Piping Plan RINSC Drawing #2152 (4) Piping Plan - Reactor Building Supply RINSC Drawing #2150 d

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