ML20078B634

Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan

ML20078B634
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	10/07/1994
From:	RHODE ISLAND, STATE OF
To:
Shared Package
ML20078B629	List: ML20078B624 ML20078B634
References
PROC-941007, NUDOCS 9410260169
Download: ML20078B634 (26)

Text

6 4 RHODE ISLAND NUCLEAR SCIENCE CENTER PROPOSED 3 MW OR HIGHER l EMERGENCY CORE COOLING SYSTEM PLAN l

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t TABLE OF CONTENTS PAGE Introduction 1 Loss of Coolant Review 2 3 MW Decay Heat 3 Table 5-1 4 Facility Water Supply 5 Fire Pump Test Results 6 Present Pool Fill System Operation 7 Proposed Emergency Core Cooling System Operation 7 ECCS Water Supply analysis 9 Table A 10 Conclusions 11 AEPENDICES

-A- ECCS Equipment and Components 12

-B- Plans 13

-C- Piping Schematic 14

-D- Instrumentation Block Diagram 15

-E- Calculations 16

-F- Administrative Controls 18 l l

1

INTRODUCTION The Rhode Island Nuclear Science Center research reactor has a design capability of 5 MW (thermal) power level. The current license and power 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 I 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.

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LOSS OF COOLANT REVIEW The SAR (Part B,Section X) calculated that the loss of ,

l coolant from the pool could occur through a 1/2" diameter 1 hole in a beam port experiment and the 1" beam tube vent / drain line. The calculation from Section XIII, Appendix 3 C of the SAR showed that a minimum of 3.76 gpm was needed to l

keep the core box full (assuming water was directly flowing l into the core box). ,

A typical calculation to determine what flow rate would be required to keep the nool full while the maximum draining is taking place is shown below:

F= . 61A [ 2gH ] 1/2 = . 61 ( . 006 82 ) [ 2x32.2x (13 9. 417-114.13 0 ) ] 1/2 F= .1679 x 7.48 x 60 = 75.35 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 1 1/4" line which serves as a deluge type of discharge to the pool (thereby eliminating an expensive piping system fabrication to the suspension frame and down to the core).

To further reduce the consequence of a LOCA, the 1" beam tube r vents will be fitted with a 1/2" orifice. This will reduce the leakage flow rate

• to:

F = 0. 61a [ 2gH ] 1/2 = 0.61 x 2.727 x 10-3(2 x 32.2 x 25.278)

F = 0.067 x 7.8 x 60 = 30 gpm

• See Appendix E for details 2

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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 j LOCA such that it would take 10 1/2 hours to expose the core and that melting would not occur.

l Applying the decay heat curve to the 3 MW situation and l

knowing that the core must have sufficient cooling until such time that the decay heat has reduced to .049 BTU /sec.

1 For 3 MW Po = .1 x 6.187 = 9.28 BTU /sec (plate) 2 P(ts) = ,049 = .00528 Po 9.28 From the decay curve (Table 5.1), the time after shutdown to reduce the decay heat to below 0.049 is about 7.25 x 104 seconds or 20.19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />.

By reducing the leakage rate to the equivalent of two 1/2" diameter holes the Drain time

• is:

T = 2A [ (h )1/2 - (h2 )1/2]

i Ca (2g ) 1/ 2 T= 2x 150 x (25.2871 1/2 0.61 x 2.727 x 10-3 x (2 x3 2. 2 ) 1/ 2 T= 31.39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> resulting in a drain time safety factor of 155% without adding water to the pool.

• See Appendix E for details 3

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r unctior Power to Reactor Operati ' Power a s .'

Time, t e; , After Shutf.own ANS,T1968)

Time After Time After Shutdown, t Power Ratio Shutdown, t s Power Ratio s P(tn) / Pn P(tc) / Pn (seconds)

(seconds) 6 x 10 4 0.00566 1 X 10-1 0.0675 8 0.00505 1X 10 0 0.0625 1 X 10 5 0.00475 2 0.0590 2 0.00400 4 0.0552 4

0.00339 6 0.0533 6 0.00310 8 0.0512 0.00282 1 X 101 0.0500 S 1 X 106 0.00267 2 0.0450 2

0.00215 4 0.0396 0.00166 6 0.0365 4 6 0.00143 3 0.0346 8 0.00130 1X 10 2 0.0331 1 X 10 7 0.00117 2 0.0275 2 0.00089 4 0.0235 0.00068 6 0.0211 4 6 0.00062 S

0.0196 8 0.00057 1 X 10 3 0.0185 1 X 10 8 0.000550 2 0.0157' 2 0.000485 4 0.0125 4

0.000415 6 0.0112 6 0.000360 8 0.0105 8

0.000303 1 X 10 4 0.00965 0.00 9; 1 X 10 9 0.000267 2

4 0.00625 4

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.

Water at 40 psi is supplied from the Wakefield Water Supply Company to a 300,000 gallon tank located the Bay Campus. The tank booster pump delivers water at 55 psi to the Campus distribution system. If pressure drops or more flow is needed a standby fire pump energizes maintaining system flow rate and pressure. The 3 fire pumps in the system have emergency generator backup. The Bay Campus demand (1992 records) is about 83 gallons / minute. The ECCS flow rate will be set at 50 gpm to provide a safety margin (30 gpm is required). The total Campus demand will be 133 gpm (83 gpm +

50 gpm) . This provides a reserve supply in the 300,000 gallon tank to maintain both the Bay Campus demand and the pool filling requirements for 37.59 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />.

Since the actual drain rate is 30 gpm, this is an additional safety factor of 67%.

A copy of the fire pump test results conducted for the system by Keily Associates, the design firm, is enclosed.

The reliability of the system was discussed in the SAR dated l

December 1992 in Section B, IX.

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

The URI 300,000 gallon tank

• can be cross connected to the Wakefield Water Company who also has a 300,000 gallon tank about 1 mile away providing additional reserve capacity.

• See Appendix F - Administrative Controls 5

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KIELY ASSOCI ATES LTD.

t.lNIS LOUISQVtSSET FREEWAY

• MINERAL SPRING INTERCHANGE P Q. GOX 6644. PROvlDENCE. RHODE ISLAND C2940 T EL EP HONE 124 8850 January 30, 1985 Otis C. Wyatt Jr. , Chief '

Narragansett Fire Department 40 Caswell Street ,

Narragansett, Rhode Island 02882 he: FIN Pump Test Graduate School of Oceanography r University of Rho,de 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 pump, Model 8'AF20B, nominal capacity of 2000 G?M vs 85 psi, 1775 RPM, 125,HP, 3P, 60C, equipped with a Firetrol Model FTA 1500/FTA 900 Controller, was dis-charged thru a Dieterich Model ANR permanent flowmeter and produced the following results:

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 results, by counternigning 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 ) 1

_N' LY__,

DJK/fa Otis C. Wyc ' t . ,[ehier enclosure Narraganse't P Lt: Mr Richard th Gannon , GSO, URI Depa m efi-Mr George Lrban, GSO, URI M :- Nobert ste. art, UR1 6

PRESENT POOL FILL SYSTEM OPERATION The existing pool is filled from the make-up demineralizer system. The pool fill system has an automatic electrically operated valve which opens when the pool level float switch is activated for a nominal one inch drop in pool water level.

The pool fill system has a manual by-pass valve in case the automatic valve fails. Measurements reflect that the make-up i

I system can provide 25 gpm to the pool.

PROPOSED EMERGENCY CORE COOLING SYSTEM OPERATION (Refer to the Emergency Core Cooling System (ECCS) Schematics in the Appendix) 1 1

l l The ECCS will operate under AC power with emergency power l

backup from the emergency generator. This assures operation of electrical components with loss of AC power.

1 i

i At present the RINSC emergency generator has 1600 watts of excess capacity. The solenoid valve and flow measuring  !

instrument would require about 100 watts and would be insignificant.

The reactor control system will be provided with two alarm circuits to be used for 3 MW or higher. The first is an ECCS water line pressure sensor located between the pressure regulator and AV which monitors the water supply line l pressure. A drop in normal water pressure below a preset value will alarm in the Control Room. The second alarm l function would be that of the automatic (AV) ECCS water line valve opening. If the AV is energized (opened) al alarm will sound in the control room.

The line also contains a flow meter indicating ECCS water flow during testing

• or a pool fill event. This unit will read out locally in the Demineralizer Room.

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4 The AV has a manual bypass valve

• in case of the failure of the electrical activator. The manual valves #3 and #4 are used for a system by-pass flow test. i l

1 Manual valve #1 is used to isolate the system. It will be locked open. The four inch supply gate valve to the fire main and the ECCS system will be locked in the open position.

Activation of the AV is from a low level pool switch. The unit will have a low pool level limit of 24 inches below the suspension frame base plate. The ECCS system will cycle (on and off) to maintain the pool water level at the 24 inch limit. This prevents a pool overflow situation.

The reactor is scrammed on a low pool water level limit of 16 inches below the suspension frame base plate from a separate low water level sensor. (Tech. Spec. Table 3.1).

The ECCS will automatically initiate flow to maintain pool i

level at a minimum level of 24 inches below the suspension frame base plate.

• See Appendix F - Administrative Controls I

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l ECCS WATER SUPPLY ANALYSIS An analysis of the 4" supply with the proposed 1 1/4" line supply to the core.

The pressure (supply) at the 4" pipe entering the building is based on the accompanying fire test report Due to high pump pressure available, the proposed 1 *1/4" line (ECCS) should have a pressure reducing value. A 55 psi setting is more than adequate for expected demand. The valve would prevent excessive line pressures when the Bay Campus fire pumps are in use.

The analysis was performed with a 55 psi supply pressure.

Assumptions:

Flow through a 1.25 inch smooth pipe Friction loss 1.25in., 50 psi = 21 psi /100ft of pipe

• Equivalent loss (pipe lengths) for fittings:

1 Press. reducing valve lft 3 valves @ 1 ft/ valve 3ft 7 tees G 3 ft/ tee 21ft 7 elbows 04 ft/ elbow 28ft i i

Total 53ft )

Actual pipe length 68ft Equivalent loss 121ft i

Friction head loss = 121ft/100ft 21 psi = 25.4 psi Elevation head loss = 32ft 0.43 psi /ft = 13.8 psi  !

Total head losses = 25.4 psi + 13.8 psi = 39.2 psi Demand Flow = Supply - Head losses

= 50gpm @ 55pai - 39.2 psi = 50gpm @ 15.8 psi 9

TABLE A HEAD ABOVE INVERT CALCULATED MAXIMUM OF BEAM PORT FLOW RATE (GPM) FROM BEAM PORT 25.29 30.13 24.29 29.53 23.29 28.91 22.29 28.28 21.19 27.64 20 29 26.98 19.29 26.31 18.29 25.62 17.29 24.91 16.29 24.18 15.29 23.42 14.29 22.65 13.29 21.84 12.29 21.00 11.29 20.13 10.29 19.22 9.29 18.26 8.29 17.25 7.25 16.17 6.29 15.02 5.29 13.79 4.'29 12.40 3.29 10.86 2.29 9.06 1.29 6.80 0.79 5.31 l 0.00 0.00 It is assumed that (1) the diaphragm valve to the beamport vent line is OPEN (2) The beamport " shutter" is in the full OPEN position l

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CONCLUSIONS A postulated " Loss of Coolant" accident for 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 times 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 fill system is capable of supplying about 25 gpm, enough water to maintain the entire reactor pool at about 17 feet above the core box (see Table A) . The proposed emergency core cooling system could provide about 50 gpm, enough water to maintain the pool water level at 24.5 feet above the core box with maximum water loss.

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 / drain line, etc.

The proposed ECCS will be safeguarded from electrical power loss with emergency power backup.

I 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.

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Appendix A ECCS EQUIPMENT AND COMPONENTS J

(1) Pressure Switch (2) Level Switch (3) Flow Meter System (4) Manual Valve (5) Auton;atic Valve i

(6) Pressure Reducing Valve l; (7) Piping and Fittings (8) Miscellaneous (9) Pressure Gage 12

4 Appendix B PLANS ,

i (1) URI Bay Campus Water System to Rhode Island Nuclear Science Center RINSC Drawing #2130 (2) North Bunker Areas I

RINSC Drawing #2005-C (Revised to show ECCS pipe routing)

(3) Reactor Room ECCS Piping Plan i RINSC Drawing #2152  ;

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(4) Piping Plan - Reactor Building Supply l RI!ISC Drawing #2150 {

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APPENDIX C EMERGENCY CORE COOLING SYSTEM DIAGRAM FROM ECCS

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TO FIRE REACTOR ROOM FLOOR CCS CONNECfwN TO EXISTING 4 INCH WATER LINE i i PS PG PS FM ihi U

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A E I I 1 - MANUAL SHUT-OFF VALVE 2 - MANUAL BYPASS VALVE i i 3 - MANUAL DRAIN / TEST VALVE 4 - MANUAL SUPPLY / TEST VALVE CHECK PR - PRESSURE REGULATOR VALVE 1 i PG - PRESSSURE GAGE AV - AUTO (ELECTRIC) VALVE FROM 4 INCH FM - FLOW METER SENSOR SUPPLY TO PS - PRESSURE SWITCH FACILITY

1 INSTRUMENTATION BLOCK DIAGRAM Appendix D 4

AV Automatic Fill 110 v AC Valve Emergency Generator '

- 12 volt DC Alarm Pool Level switch Supply Pressure switches l

Flow Indicator System l

Appendix E CALCULATIONS LEAK RATE (IM) i Datum is el. 114.13 (invert of bottom of 8" beam tube) el. 139.417 (water level of pool) l i

head = 139.417ft - 114.013ft = 25 287ft area of leak = two 1/2 inch diameter holes a = 2nr2 = 2n ( 0. 5 /24 ) 2 a = 2.727 x 10-3 feet 2 0.61 - void coefficient /see attached l (Mechanical Engineering Handbook)

Flow through the standard orifice:

?

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V = 0.61a Y2 gh I

l -3,l V = 0.61 x 2.727 x 10 V 2 x 32.2 x 25.287 V = 0.067 ft /sec 7

V = 0.067 ft /sec x 60 sec x .48 gal min l

4 V = 30.127 d min l

l Drain time for two 1/2 inch diameter holes:

i Discharge under falling head i 2A((h7.(E) catig l

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Datum is el. water level of pool 139.417ft invert of bottom of beam tube 114.13ft h1 = 139.417 - 114.13ft = 25.287ft

! h2 = 0 A is he area of surface of pool = 150ft2 C is the orifice coeficient = 0.61

, a is cross sesction area of two 1/2 inch diameter I

holes = 2.727 x 10-3ft2 l

t= 2 x 150 x V23.287 l 3 O.61 x 2.727 x 10 x Y2 x 32.2  ;

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t = 1508,6 = 113,010 seconds t j 0.01335 l

! t = 31.39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> t

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Administrative Controls Appendix F

1. Bay Campus 300,000 gallon Tank Water Level:

The Bay Campus 300,000 gallon tank has an altitude valve that automatically maintains the water level at 128.1 feet using Wakefield Water Company's water supply at 40 psi. The automatic valve is monitored by a remote '

recorder at URI's maintenance, of fice with malfunction alarms at the water station, maintenance and security offices.

I If the Bay Campus tank fails, the pipe line supplying the Bay Campus can be cross connected to the Wakefield Water Ccmpany's 300,000 gallon tank that is about 1 mile away. i This cross connection can provide 200 gpm at 40 psi.

The Bay Campus and the Wakefield Water Company tanks do not provide for gravity feed.

2. Use and testing of the ECCS:

The normal position of the valves are:

Valve #1 - Locked open Valve #2 - Normally closed valve #3 - Locked open Valve #4 - Locked open Gate Valve (4 inch) - Locked open Mannual Operation:

a. Check valve #1 open

b. Check valve #3 closed

c. Check valve #4 open

d. Open valve #2, check for proper flow indication

e. Check all valves in their normal positions and locked.

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t

. Automatic Operation:

Automatic operation is initiated by a low water level sensed by a magnetic float switch.

Testing: .

1 i To test system for proper operation, push float down approximately 1 inch. Water flow can be seen at the deluge outlet pipe located under the reactor bridge.

Check proper flca rate on indication in Demineralizer

- Room. Release float, water flow should stop.

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! Appendix G a

j Mechanical Engineers' Ref, Material 4

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LION EL S. M AllKS. Editor,1916 to 1951 " ' t b' ^d 4 "

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i Ce>eiversinn me nle, ens f t >cr we 6t sN rt min an l r dI er day. ,

U (if orifico does not correfpond to the rent avernge volority of all the water flow ina ryt b3 but to encre than the average; i.e. the actual .liwharge in h-n than that phou ri hv Ib b formul t. (For theoretical principle, are Weira, p. 3-G7.) When the lu ad abo /c th #

renter is equal to the vertical dintension of the orifice, the dish trge is rnely abmat y Toronto L "g0" perreret le**. arul when the head is twice the vertioni dimesi i.m the dimiriurion is neg g New York heim,.mcept for the not pnvisr sort or iuve-ticiti. n , for w hich a .pecint ..:dih,sno,3' chould b. made to deteimine the esact enci'imirnt. For b.wcr hewl , ir 6. r. pu ,.-ut McG1 TAW-IIILL BOOK COMPANY, INC. the he.d shove the center nnd o the height of opening. Tahic 3 gives the p.. .entw.

1958

C100 IIIING SYSII "5 -

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A.cm si e aer :s,/100 -4 *gr ; FPICTICN L OS3 IN HEAD IN LSe, e 2  :. s obi 2 4 6 5 0 3 ~ C E (,. . Ci 2 34 $58s 2 3 ff -+

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.; flCURE Cl.U0 I r an im for f.orly rn FIGURE Cl3.;9 f ncm im fm sre m ) y 3 m. direct-type immersion heater inside the 1  ; age tank. This system shevld be conside instantaneous.tvpe beaters, an accurate approximation for steam can be calcu-lated by multiplyint the epm requirements by 50 lb/h. This type of heater is al- p countered for short periods of time and v most aiwavs ind'irect!v fir'ed using ci:hcr steam or hot water supp!ied trom a cen- ,

i ists. Disadvantages include large amou:

tral heatin'g plant, ste'am utility sistem, or a boiler.  ; .2 Advantages include a low instantaneous Semi-instantaneous. type heaters are simdar to the mstantaneous type except 6 Pomt of-use heaters are used for isola for havine a limitcJ w ater storage capacity, which permus casier control of oudet  ?. economical to run pipmg from the prima

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water tersperature. T his type of heater can be either dircedy or inducctly fire '

The choice of a primary fuel for hs and is preferred over the instantaneous type. The far creater maprity of Instab considerations:

lations arc of the indircet fired type.

3 Avan.abih.t.y of fuct Storage. type heater.s have a larfe storage capacity and lou er recos.ery, rate. ,,2.

This systen$ consists of either a combination storace tank and a dacct. or cost s >

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FIGURE Cl3.1 Resistance of vahes and fittings to now of Duids. Ii j

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