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) ' UNITED STATES COVER.JENT Memorandum DATE: To Filee ff THRU Roger S. Boydd Chief, Research & Power Reactor Safe Branc Jivision of Reactor Licensing arch & Power Reactor Safety Branch l FROM : l v on o Reactor Licensing t suBJEcr: EODFriA BAY AFTER-HEAT REM 07AL SYSTEMS oi~0,& 0 5 A number of heat sinks are provided in the proposed design of A number of questions have been raised 1 the Bodega Bay reactor. I as to the sequence of events that might be expected ehould various postulated eccidents occur to the reactor facility. In this memorandum, a brief description is given for the systems designed to make the reactor subcritical and the systems pro-l l vided for decay heat removal. In addition, the anticipated performance of these systems in the event of accidents is discussed. u A. Systems To Make The Reactor Suberitical ~,t s -, ~%. The normal ' system for controlling core reactivity is the 1~ H control rod drive system. The Bodega Bay design incorporates W 145 control rod drives which are supplied during normal H operation by two positivo displacement pumps. During emer-gency scram actuation the energy for fast insertion of all y ~m. rods is supplied by pressure accumulators, one accumulator per . n.. i f.W_i drive, or by reactor pressure. Both of the above sources are Q.,._ stated to be independent of the hydraulic system for normal rod movement. The drive mechanisms are located within the dry well, however, the control rod drive valves, accumulators, fgh etc., are located in the refueling building. In the event u.c+? - the lines to a drive unit were sheared at the containment MQ wall (dry well) the ability to scram or move the blade by normal means would be lost b.weu4dir (cwn w.Jc. hw-b AeAs, f In addition to the control rod system, a second independent system of shutting down the reactor is provided. This system is a liquid poison system which consists of a storage tank, J two ponitive displacement pumps, valves, and piping. Liquid U I polson (solution of sodium pentaborate) may be injected into the reactor recirculation piping at full reactor pressurt. The reactivity worth of the system is normally 207. ak with I an insertion rate of 0.57. hk per minute. The system worth l would be zuch less when the refueling pool is connected to the reactor. For example, if the refueling pool is filled, i however, the storage pool is not connected to the refueling pool the total reactivity worth to the poison, is stated to B709230122 851217 ~ PDR FOIA FIRESTOB5-665 PDR - =......p -
1 .) ') 2 be 5%. The components of this system except for some piping are located outside the containment wall in the reactor building. 1 l B. Best Removal Systems I 1 \\ The main condenser which is provided to condense exhausted ~ turbine steam is also designed to serve as a heat sink for axcess reactor steam which may be dumped directly to the j condenser through a steam bypass system. The bypass system j is designed to condense steam bypassed around the turbine l up to 40% of full rated steam flow. The secondary side of l the main condenser is designed for salt water service since l l , 7,.. water is drawn from the Bodega Bay and Harbor, circulated i I through the condenser, and then discharged to the Pacific y.- " Ocean. In.1ddition to the main condenser there are other heat removal systems which mey be used to remove heat after l l shutdown and during an emergency. The featuresof these l l w systema are described below: l ff (1) Caerzency condenser Cooling System
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- 4 The emergency cooling system is a high pressure system which provides the means for removing heat from the
%~: reactor in the svent of loss of the main condenser as a j h@ heat sink. The emergency condenser has two tube bundles l .%M located in a tank of water. The condenser is actuated by opefting a valve in the return line to the reactor and iLT the flow is maintained through the condenser by natural circulation. The stated design heat removal capacity l per bundle at reactor peessure and temperature is 18 Hw. As shown in the attached decay heat curve, the heat generation from fission product decay is down to 36 Hw (capacity of both tube bundles) in about 2 minut.n and is down to 18 Hw in about 20 minutes. The components of this system are located adjacent to the spent fuel storage pool on the reactor operating floor. (2) Bhed and Feed system Steam can be vented from the main' steam line to the I suppression pool whenever a solenoid operated steam dump a valve is actuated. The system is automatically actuated ,5 l 3 .,. _ _ _._. g
1 ,. ~. -.. .x ~ ; -.. r. ,, -..... ~.... i ...... ~.. ~ c --) i 1 .3 - by high reactor pressure, or annually by operator action. .j A high pressure feed water supply must be available to. replace water that is vented from the system. After reactor shutdown the feed wetsr to the system can be supplied by the electrically driven euxiliary feed water j pump if off-site electrical power is available. Tble .l pump is electrically powered _by a 500 horsepower, 4160 t I volt motor (the emergency generator is a 480 volt system I of unspecified power capacity and therefore it is assumed that this pump cannot be~ powered from the emergency I source). The flow capecity of this pump is'700. gym, ] therefore used with the feed, and bleed system is capable .l of removing 60 Mr. This pump is located.in the turbine-I - ' = generator structure. l r. 1 A second source of high pressure feed-water is the control' v. rod drive pumps. These are two pumps provided in'the design (oral acataments have indicated'a_ third pump has been added) with a capacity orally stated to be c' i 50 syn. When used in connection with feed and bleed . e.1 these pumps alone would remove about 5 Mr. These pumps are also physically located in the turbine-generator 5:.E structure. .e+n. -.~.:.i A third. set of high pressure pumps which may be used to c, {gJ inject water in the core are the poison feed pumps. Two ' = y' such pumps are provided in the design, howeverj 'jha [M pumpias capacity and the size of storage Esservoir are 2.f not specified. These pumps and the poison storage tank ~ ~ - are physically located' adjacent to the spent fukt storage pool at about grade elevation. (3) Shutdown Coolian System ' ^ ~ ' A forced circulation systes.with associated heat exchangers Is provided for decay heat removal during shutdown. This system contains 2 puups and 2 heat exchangers. The system is"a low pressure (150 paig) system with a total i heat removal capacity of 18 Mr. The reactor is-initially-cooled by controlled scess flow to-the main condenser. After igitial cooling and depressurisation to less than 150 psig the shutdown cooling systen may be placed in' operation. The shutdown pamps and coolers are' physically located outside the containment within the reector building about 30 feet below grade level. h 4.,,,,,o- ---a.... ,e.e .m... .w,.,.---. ,,y ., -... ~... .,,..w. o_ 7
i.-_...._. _._. _ _. -a _ _ ~. J J i .I i 4 4 1 \\ (4) Core Soray Srstem 1 A low pressure (150 peig) core spray system is provided. This system takes suction from the suppression pool and enters the vessel through two spray inlet nozzles.- The system is autasatically started when the reactor pressure is less than 150 psig and the reactor water level is Iow. } The system can also be started manually. The core. spray 1 system contains two pumps each of which is specified to j deliver 1200 p at 150 pai. With aciedding temperature limit of 1500 F the heat removal capacity of the spray -~ system is esiculated to (0 Edw. The pumps for this system C. C ara located in a compartment at the loosat level under ^ the dry well within the reactor building. r M (5) Rish Pressure Core Sprav avstem wy -? Provision has also been made to install a high pressure core spray system. This system utilises the same auxiliary feed water pump described in The Bleed and Fecd System. When used for spray cooling, this system 9= bas the same shortcomings as described in the previous gz;[j section on The Bleed and Feed System.
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"~4 (6) Junoression Pool Coolina System &W;- ru.-jj ~ Two pumps and two heat exchangers are provided to recircu-M~ 1ste and c.ool suppression pool water. The hast removal gr capacity of this system is not specified. The pumps WY. are physica11y located in a craspartment at the icwest levels under the dry well within the reactor building. . i The heat exchangers are located outside the dry well ' - ~ - within the reactor building about 30 feet below grade level. 1 C. Accident requence \\ A series'of accidents within the system are postulated ia subsequent sections to demonstrate the espected performance-of the heat resoval systmas. All of these evaluations assume that the initiating event is not severe enough to impare the ability to make the reactor saberitical. Also it was assummed - that the fuel storage pool retained its integrity (since the pool is outside of the primary containment any melting of fuel stored in the poc1 would result in a direct releaseto atacephere). 3 e ,,#,g y.. ..m.-+ -en Ab'***t4.''e9P'4* gehr ge."' eg496g 3,wggpWM ges.% a4"4* M 8M" ' TW 9 4 O 0' *"' ' ' WJYM WW# 'N.
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,~ 2 )- ) 4 i 1 I i i (1) Insa of Turbina-Canarator and off-Site Electrical REESI Under these conditions. the emergency condenser would.be espected to remove all decay heat for a period of at least 8 hours. Any leakage from the reactor system could be. j made up by the control rod drive pumps which can receive power from tiae emergency diesel gemretor. Within 8 l = l Lours additional water aust be added to the emergency condenser tank or reliance must be placed on continued l use of The gleed and Feed System. E though The gleed and 1 l Feed system when using a control rod drive pump for feed; _. i vill remove only S Mw of heat, and this decay power does .i ggJ vet decay to 5'Nw until 14 hours after shutdown, the core i d will not be uncovered.during the intervening time. No ~z.Qg fission products should escape under these conditions. n&g;;-= &;.~,_ (2) pomolete Loss of All A-C Power, 1 C.,,'. With a complete loss of all A-C power the emergency m._." condenser would be aspected to remove all decay heat for a period of 8 hours.- If there were no leaks in the primary E.:cM j2] system (e.g. all f.rassure relief volves were perfectly j 39 sealed).there would be no decrease in water level in the Q @J reactor vessel. Within the 8 hour period some means would i A g;g have to be devised to pump more water into.the emergency j g,1,y condenser..If power co614 not be restored and-no additional Ef'P,,d,.- unter could be added to the condenser, the bleed system 4a-g vois1d allow staan generaged in the vessel to vent to tho' g? suppression pool..Approximately 4.2 hours after (or 12.~2 l NJ hours after the onset of the accideot) the emergency ['T condenser is boiled dry all the water.would be boiled from the reactor vessel. Fission products wo41d escape from the reactor vessel to the containment when'the water level drops below the top of the fuel elements. After 4.2 q ' hours and fuel melting occurs, the subsequent events are not cleae.,.It is possible that fuel could melt through g the pressure vessel;and then through the dry well wall, however, no estimate of the time involved is made. 5 Another possible consequence is that heat conduction, convection and radiative heat transfer transport decay. heat from the pressure vessel to the coatsimment volume. i i causing a~ gradual heat up of the suppression pool water. With these latter assumptions, the containment pressure would begin to increase and would reach 55 psig 2.pproxi-6 mately 35 hours after the onset of the accident. Jk '? m r,w m ~;-3 p y rnu.p zge-~s,*.m: g y,;;q.g 3 m,,y m ....~y.
l ..\\ (3) Loss of 111 Pipes to The Turbine Buildina If an accident were postulated where all pipes e-mica-ting between the reactor building and the turbine pedestal j were sheared and all cooling water lines into the reactor ~ building were unavailable for use, the emergency condenser } would be expected to ree m e decay heat for a period of l S hours. The consequences thereafter could parallel l ~ "j those described for item (2) above "Complace Loss of All., A-C Power." Und6r these accident conditions however, the operator could elect to manually open the solenoid bleed ---. x valves and establish emergency core spray. - With wo external . c.. water supply available in the building to circulate through ~,% the pool coolers the contaimeent pressure venid rise to i l meg about 55 psis in about 35 hours (shes for the previous care). T-3 The gross fuel melting could be delayed until the contain-q ment failed and the water supply for the core spray system (suppression pool) were exhausted due to boiling. Tha 4 time required to completely boil all water in the suppression l ,, g gg pool would be on the order of one month. l .hh '(4) Simultaneous Failure of All Pipes and Electrical Power .~m Tl With a complete loss of olectrical power and loss of lines F,,M to and from the contaimeent vessel, boiling would immediately ~ $I$2 begin in the reactor vessel and the steam would be quenched M by the water iar the suppression pool. Within 2.8 hours ~ y,.;r the reactor vessel would be boiled dry. Fission products "M-would begin to escape from the reactor vessel to the containment when the water level drops below the top of-the fuel elements. When melting occurs if heat transport mechanisms are sufficient to cause a gradual containment heat up rather than localised melting of the pressure vessel and containment vessel, approximately 12 hours are needed before the containment ras ssure would increase to.55 peig. a i h l j f n ~ ~ ---.-,m- ~4, yv, y,,- -m.g,w7mc-g., p. -.n,~,.pypp.g. q rgyy.n.;n, w g mm f + y ;g
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