Text

Assessment of Postulated Degraded Core Accidents in Grand Gulf Reactor Plant, Draft Informal Rept
	ML20072L681
Person / Time
Site:	Grand Gulf, 05000000
Issue date:	06/30/1982
From:	Gasser R; BROOKHAVEN NATIONAL LABORATORY
To:	; NRC
Shared Package
ML20072L675	List: ML20072L681; ML20072L685; ML20072L689; ML20072L699; ML20072L710;
References
	FOIA-83-81 NUDOCS 8303310465
	Download: ML20072L681 (247)
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s AN ASSESSMENT OF POSTULATED DEGRADED CORE ACCIDENTS IN THE GRAND GULF REACTOR PLANT

- i' R. D. Gasser.

Department of Nuclear Energy .

. BROOKHAVEN NATIONAL LABORATORY Upton, New York 11973 i June 1982 '

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Prepared for -

U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Under Interagency Agreement DE-AC02-76CH00016 4

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ABSTRACT ,

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An analysis on the effects of delayed ECCS operation in the Grand Gulf reactor plant is described. In particular, the potential for H2 generation during core uncovery and degradation is calculated. Transient initiated events with ECCS failure (TQUV), small break LOCA and ECCS failure (SZE) were studied.

The results obtained using the MARCH code indicate that the quantities of 1

hydrogen produced and the severity of the hydrogen burns are sensitive to the time at which ECC is restored and the degree of ECC restoration. In addition, it appears that utilization of the HPCS system is preferred over use of the ADS in canbination with the LPCS or LPCI systems for successful reflooding of the core and suppression of H2 production.

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TABLE OF CONTENTS _ ,

Page ASSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii LIST OF TABLES . . . . . . . . . . . . . . . .-. . . . . . . . . . . . . vi I. INTRODUCTION AND

SUMMARY

. . . . . . . . . . . . . . . . . . . . . 1 II. MARCH MODELING FOR GRAND GULF BWR. . . . . . . . . . . . . . . . 3 III. DELAYED PARTIAL ACQUISITION OF ECC (WITHOUT CHR) . . . . . . . . . 5 A. Transient Events Without ECC (TQUV) . . . . . . . . . . . . . .

5 B. Small Break LOCA 2 (S E) . . . . . . . . . . . . . . . . . . . .

9 IV. DELAYED TOTAL ACQUISITION OF ECC (WITH CHR). . . . .'. . . . . . . 11 7

e)) A. Transient Events with Delayed HPCS (TQUV). . . . . . . . . . . 11 S. Transient Events with Delayed ADS-LPCS . . . . . . . . . . . . 13

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C. Small Break LOCA with Delayed HPCS 2 (S E) . . . . . . . . . . . 14 V. ANTICIPATED TRANSIENTS WITHOUT SCRAM CR ECC (ATWS). . . . . . . . . 19 V1. COMPARISON WITH INDEPENDENT ANALYSIS. . . .'. . . . . . . . . . . . 21 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 APPENDIX A - Graphical Results of MARCH Calculations . . . . . . . . . . 23

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LIST OF TABLES- '

.. a lU Table Title Page I TQUV (HPCS) . . . . . . . . . . . . . . . . . . . . . . 12 II TQUV (ADS & LPCS) . . . . . . . . . . . . . . . . . . . 15 III SgE (HPCS). . . . . . . . . . . . . . . . . . . . . . . 18 D

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I. INTRODUCTION AND SUP.P.ARY- .

This report is divided into five main sections. The first section con-tains a brief outline of MARCH modeling problems. In the second section, transients and small break LOCA (TQUV and2 S E) with delayed partial acquisi -

tion of ECC are considered. In this .section, it is assumed that the contain-ment heat removal system (CHRS) is inoperative.and that malfunction of the ECC system (in this case, the High Pressure Core Spray System, HPCS) limits the pumping capability to about 1/5 of the. rated flow with subsequent failure in recirculation. In the third section, the TQUV and S E2 accidents are con--

sidered with delayed, but total acquisition of ECC. In this section, the ECC pumps deliver their rated flow rates and do not. fail in recirculation. In ad-dition, the containment heat removal system is assumed to operate immediately..'

The CHRS consists of the RHR pumps which draw water from t'h'e suppression pool',

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pump it through the RHR heat exchangers and then pass-it back into the sup-pression pool or direct it into the containment spray headers. Since MARCH cannot.model the former case, the spray alternative is used exclusively in this section. The fourth section contains a brief discussion of the ATWS se-quence and the fifth and final section is a comparison with other analyses.

It should be mentioned in passing that the scenarios considered in this

report may not necessarily be the most likely to occur under ' accident condi-tions. For example, the use of the HPCS system after a delay in which the

!' core has been voided and perhaps partially melted, would represent' a situation l

in which the normal procedures would be overridden. Under normal operation, the Automatic Depressurization System (ADS) would be activated by receiving

" simultaneous signals indicating an elevated drywell pressure, a low vessel

. .,a water level, and a pressure signal from a LPCI or a LPCS pump. It must be 9,

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kept in mind, however, that for the situation to arise in which the ECC sys-tsms are initially unavailable, implies conditions that are abnormal and may

require unusual operator action. Re-acquisition of electrical power to ECC pumps aftar a delay of two hours would normally result in activation of the ADS to depressurize the vessel with subsequent in,jection by the LPCI or LPCS."

However, a less severe situation with respect to H2 prod:Jction may be ob-tained by overriding the ADS, maintaining vessel pressure while incorporating-the HPCS system.

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I II. ' MARCH M00Elit4G FCR GRAtiD GliLF BWR

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'J A number of probl'e m areas have been encountered during the effort to model the Grand' Gulf' reactor. systems using the MARCH code. Some of these re-late to differences in design between the earlier MARK I & II containments compared to Grand Gulf which utilizes 'a MARK III- containment. Other problems arise frca inflexibilities in the MARCH code options.

The MARK III containment i,s characterized by a drywell which vents by way of a weir through 3 sets of circular ports or vents located at different heights near the bottom of the dry well. The steam-air mixture in the dry well vents through these po'rts directly into an annular suppression pool in the wet well. The pressure must build up in-the dry well high enough to de-press the water level in the weir and. uncover part or all of the successive-levels of vents. The-net effect here is that flow is delay ~ed until the re-quired ap is generated, and the flow area is a strong function of the pressure ,

difference between the dry and wet well. .The MARCH code'is unable to model either. of these phenomena.

A second modeling problem exists-because of the reactor vessel pressure .

relief system. The system consists of 22 separate valves in 5 groups that-

. open at 5 progressively higher pressure set points. Here again the flow area for vessel pressure relief is a function of the pressure differential and can-not be modeled exactly by MARCH.

A third problem arises in modeling the High Pressure Core Spray system (HpCS). The pump characteristic curve is nearly a linear function of the ves-

, sel pressure. MARCH allows a choice between a constant flowrate or a para-bolic pump curve, and therefore, cannot handle a linear puinp characteristic

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Probably of more significance as it relates to degraded core accident

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s~equences is the question of hydrogen production. For the sequences con-sidered in this report, ECC is restored in time to prevent vessel' failure.

However, restoration may not.be in time fto prevent partial core melting. The actual mode of reflooding may make significant differences in hydrogen produc- .

tion. Two of the three ECC systems consist of core spray systems in which coolant is introduced through the top of the core. MARCH does not model this type of reflooding. In MARCH, the ECC water enters only up through .the bottom of the core. The rate of reflood in-the uncovered core region (and therefore, the H2 generation rate) for these two injection systems may not be the same.

It- should be kept in mind that, although 2 of the 3 B;!R ECC systems are core spray systems, MARCH is constrained to treating them as cold leg injection systems. ,

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9 III. DELAYE0 PARTIAL ACOUISITION OF ECC '(WITHOUT CHR},

7 .

c.) -A . Transient Events Without ECC (TOUV)

The configurations which have been analyzed in this section for the TQUV consist entirely of cases in which the containment heat removal systems are assumed to be inoperative. In addition, it is assumed that the HPCS pumps can deliver only about 1/5 of their rated flow, and that the ECC system fails when the RWST is empty and an attempt is made to initiate the. recirculation mode.

A baseline case was run in which the ECC systems were not restored.

Figure la (see'the Appendix for graphical results) shows the containment pres-sure history for the baseline case. The MARCH default concrete (limestone 80".

CACO 3 ) was used due to lack of information regarding the concretes used in the Grand Gulf plant. _In this case, whatever differences,that might exisii are unimportant, since the primary purpose of the baseline case was to determine

' ;f

. the times at which various events occur (i.e., core slumping, vessel failure, etc.).

~

For the baseline case, core melting appears to commence at about 112 min-utes and slumps onto the lower vessel head at 144 minutes. Vessel head fail-ure occurs at about 160 minutes, and a large hydrogen burn takes place subse-quent to vessel head failure which results in 'a pressure spike to 75 psia.

l~

The design parameters for Grand Gulf calls for a design pressure of 30 psia for the dry well and a design temperature of 185'F (which corresponds to I roughly 25 psia for a saturated atmosphere) for the reactor containment build-ing. A burn of this magnitude would clearly seriously challenge the contain-l ment. The NRC suggests a failure pressure of about 70 psia.

l

! .~-

l M.

l

Although the maximum amount of clad reacted by the end of slumping was limited by input' to 0.528, the fraction reacted in the core region at 140 min- G utes (the last printout before slumping) was .26 with the reaction rate accel-

.. )

erating. From Figure le the fraction of clad reacted just prior to core slumping amounts to about 34%.

The quantity of hydrogen generated in the quenching process, therefore, may have been under-estimated.

To establish the maximum delay times beyond which restoration of ECC will not prevent core slumping or vessel failure, and to determine the effect of such delay times on the hydrogen production rate, a series of cases were run-in Which the High Pressure Core Spray (HPCS) pumps were turned on at times varying from 70 minutes to 130 minutes. The HPCS system was assumed to fail in the recirculation mode. The results of these cases (Figures 2-6) show some

interesting trends. Apparantly, for these limited flow ra'tes, unless HPCS flow is established before incipient core melting, the HPCS system (as .modeled ff in MARCH).cannot prevent the core from slumping (slumping is constrained to occur at 75% of total core melting). In fact, if the HPCS is started between 110 minutes and incipient melcing (112 minutes) the' core will slump onto the vessel head and remain coolable in that location until the HPCS fails in re-circulation. At some point in time between 112 minutes and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , acquisi-tion of HPCS will not prevent vessel failure and will, in fact (again accord-ing to MARCH modeling), decrease the time at which failure occurs. The cases for which reduced ECC function does not prevent vessel failure differ only slightly from the baseline case with the exception that the peak hydrogen burn pressures are somewhat higher.

Cases in which reduced ECC function is restored within only 10 to 15 min-utes before melting starts may yield small H2 burns early on in the accident

(150 to 200 minutes), but .if makeup water is restored by 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , H2 burns do not occur until after ECC fails in recirculation (after about 900 minutes),

..) an'd the vessel head fails. Figures 2a through 9a show the pressure histories for these cases. In general, when ECC is acquired in time to prevent core slumping, the containment is pressurized slowly at about 1.0 psi /hr until the vessel is failed, at which time a series of H2 burns may result in pressure spikes up to 95 psia.

One additional case was perforced in which reduced HPCS was turned on -

immediately and the recirculation mode was successfully established with the exception that the RHR heat exchanger was assumed to fail so that no heat was removed frcm the suppression pool water before injection into the vessel. Be-cause hotter water is being injected after recirculation is established, the rate of pressurization is subsequently higher with the result that the pre,s-surization rate averages about 2.1 psi /hr between 1000 minui;es and 3000 min-

] utes. But, since the core is kept flooded, negligible quantities of hydrogen

.?

are formed and no burns occur. The results for this case are seen in Figure 7a through 7f.

Without active heat removal during the recirculation phase and in the ab- ,

sence of' containment sprays, the containment will ultimately be failed by ex-cess steam pressure.

In the event that the high pressure core spray system is inoperativt or inadequate and if the required signals are forthcoming, the ADS (Automatte Oe-pressurization System) reduces the vessel pressure by steady operation of the pressure relief valves in the ADS mode. When the vessel pressure has been re-duced to about 305 psia, the LPCS (Low Pressure Core Spray System) begins to inject water into the core. This system does not have an initial injection M %

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phase in which water is taken from a cold water source or tank.- It operates in the re-circulation mode, immediately taking suction from the suppression b pool.

One additional TQUV case has been performed to date. In this case, the ADS system is allowed to depressurize the vessel and the LPCS system at rated flow is utilized. The further assumption is made that the containment heat removal system is inoperative. This system functions by using the RHR pumps to draw water from the suppression pool, put it through the RHR heat ex-changers and return it either to the suppression pool or into the vessel.

Tnis configuration with the absence of heat removal capability is similar to the previous case. Figure 8a shows the containment pressure response. It-is similar but more severe than the previous case, because unlike the-TQUV with HPCS operating in both cold injection and recirculation it has no cold water injection phase and goes fanediately to the circulation of Oncooled suppres- ,, .;, .

. Ca sion pool water into the vessel.

The average pressurization rate up to 3000 minutes is'about 2.4 psi /hr. It can be concluded from the limited number of cases perfomed to-date for the TQUV accident sequences that, if heat removal

~

systems are not available and if the HPCS system operated at 1/5 rated flow:

1. If ECC is not restored' before core melting begins, the vessel will be breached at about 160 minutes and H2 burns may challenge containment at i that time. .

2. If HPCS can be recovered before core melting connences, the containment may not be seriously challenged until the attempt is made to go to j i

recirculation.

P hi I

3. If recirculation fails, the vessel will be breached and the con ainment may be failed immediately by hydrogen burns.

p. ,

'y 4 If recirculation is acquired in the absence of heat removal, a more rapid pressurization will ensue (about twice as fast as during the injection phase) and the challenge to containment will be more gradual, but never-

. theless, inevitable.

., 5. Cparation of the LPCS at rated flow in conjunction with the ADS and

-3 without CHRS results in an immediate. recirculation phase which produces more rapid pressurization and can be expected to challenge containment earlier.

B. Small Break LOCA (S;E)

Anin-depthanalysisofthelossofcoolantaccidentjithpartialECO x

restoration was not performed. The results of a baseline case for the S E 2

-%),

accident sequence are, however, given here. As in the TQUV baseline case, lack of information regarding concrete types in the Grand Gulf plant made it

~

necessary to take the conservative approach and utilize the default concrete composition in the MARCH code, which approximately corresponds to limestone Concrete.

In the baseline case a 1.0 inch diameter hole is assumed to be opened in a steam line. The emergency core cooling systems are assumed to be inopera-tive so that the ADS does not depressurize the system. The hole that opens in the steam line is placed high enough (in the MARCH modeling) so that the flow out of the break is single phase steam throughout the entire event.

Figure 9a shows the containment pressure response for the S2E baseline case. It appears quite similar to the baseline TQUV case except that the f)

. 9

_ .. = _ .__ _ - .

pressure spike generated by the hydrogen burn whenh t'e vessel fails is consid-erably more severe being in the neighborhood of'130 psia. The results of this cdse suggest that for a situation in which the vessel is failed in a gross '.

canner, the sudden flux of hydrogen ~ released from the vessel may swamp a hy-drogen ignition system and may, in fact, ignite the hydrogen when it'is in ex-

.pl os ive concentrations just above the suppression pool and before,it can be diffused into a merely fl'ammable concentration. '

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IV. DELAYED TOTAL ACOUISITION OF ECC'(WITH CHR) ,

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'd A. Transient Events with Delayed HPCS (TOUV)

In this accident scenario, a transient event without makeup water'(TQUV) is altered by subsequent delayed acquisition of full ECC flow.- The CHRS is also assumed to operate by taking water from the suppression pool, cooling it in the RHR heat exchanger and delivering it to the containment as a spray.

This functica in effect cools the suppression pool and thus serves the added function of a heat sink for the HPCS in the recirculation mode. The spray system is assumed to be operating under the RHR mode in which the pump de-livers 5700 gpm.

A series of 5 cases were considered in which the ECCS was restored at times varying from 100 minutes to 200 minutes after shutdown. The results of these cases are shown in Figures 10 through 14. -Table I gives the maximum r.}.

fractions of clad reacted and core melted as well'as the times at which these occur. It is apparent from Table I that with rated HPCS flow.the acquisition of ECC flow can be delayed perhaps 30 minutes longer (130 minutes as compared ;

to 100 minutes) than for the case with reduced ECC function without. reacting large fractions of the cladding and producing dangerous quantities of hydro-gen. For delay time of 125 minutes, for example, only 14% of the core melts, and only 5% of the clad is reacted. This represents about 350 lb of hydrogen.

For this reason, the 100 and 125 minutes delayed ECC cases (Figures 10 and 11) do not have hydrogen burns. If the ECC is delayed by 150 minutes, however, 91% of the core is melted and 66% of the cladding is reacted. The result is a series of hydrogen burns soon after ECC acquisition . producing con-tainment pressure of about 69 psia. The 175 and 200 minute delay cases are Q

9

7 _

[

Table I . - .

TQUV (HPCS) l Maximum Clad Reacted Maximum Core Melted Start of HPCS Time Time (min) Fraction (mi n ),_* ,,

Fraction (min) 100 10-4 100' 0 -

125 .05 125 l .14 125 150 .66 175 .91 160 (150)* (.65) -(175) (.98) (175) 175 .72 205 '.'96 175 .q.. .-

. 3 200 .72 230 ] .96 210 Y

4 e

h 4

et o

um em o m

similar with small H2 burns occurring at about 150 m'inutes from the hydrogen generated in the boil-off period and more severe (90 to 100 psia) burns occur-

. . . ring at about 200 minutes primarily from H2 generated in the reflooding process.

The assumed flammability limit for all five of the above cases was from 8% to 4%. A sixth case in this configuration was run'in which the flammabil-ity limits were changed so that combustion was initiated at 10% H2 and burned down to 0%. The 150 minute delayed case was used. Figure 15'shows the results for this sixth case. Comparison of this case with the 150 minute case (Figure 12) for the lover flammability limit' reveals that the series of burns that yield pressures which vary from about 60 to 69 psia are replaced with two larger burns with pressures of 65 and 83 psia.

B. Transient Events with Delayed ADS-LPCS ', "

3 In this accident sequence, the HPCS system is assumed inoperative and

.cf after a delay in which no makeup water is supplied to the core the automatic depressurization system, ADS, is activated. When the vessel pressure is re-duced to about 305 psia, the low pressure core spray (LPCS) system begins to deliver coolant to the vessel. The LPCS system differs from the HPCS sys-tem in that it does not have an injection mode, that is, it does not pump water from the refueling water storage tank. Rather, it takes suction from the suppression pool, immediately going to the recirculation mode. In this

, scenario, the suppression pool is cooled, as before, by operation of the CHRS wherein the RHR system pumps hot water from the suppression pool, runs it through the RHR heat exchangers and direct it into the containment spray headers.

4%

1

A series of 4 cases were analyzed with the MAR'CH code for this scenario.

~

These cases include four delay times 100, 125, 150 and 200 minutes. These _

cases'are graphically displayed in Figures 16 through 19, and Table II shows the maximum fractions of core melted and cladding reacted.

Apparantly, operation of the L?CS system in conjunction with the ADS'is a bit more sensitive to the delay time. If initiation of the ADS occurs before the core starts to melt, no significant amounts of hydrogen will be proddced.

If operation of the ADS is suspended until 125 minutes (only 13 minutes after incipient melting) 90% of the core will be melted and 91% of the clad reacted.

The problem arises for this configuration in getting water back into the ves-sel once part of the core is molten. Although the ADS depressurizes the sys-tem quite rapidly and LPCS initially enters the vessel only a few minutes .

after ADS initiation, rapid vaporization of the incoming water drives the pressure above the pump setpoint and the ECC flow becomes'intennittent with 6.[4 considerable delay between injection phases until the core is adequately quenched. The time to quench the core in this manner may be over 100 minutes,

~

and with small quantities of water intermittently injected onto a hot care, significant H2 generation results. The hydrogen burns for these cases (8%-4% limits)donotappeartoexceed60ps{a,buta10%to0%H2 burn could result in a pressure rise to 70 psia.

l~

C. Small Break LOCA with Delayed HPCS (S9E) .

t This scenario is characterized by a small break (1.01nch diameter) in a steam line. As in the TQUV sequences, the ECC is delayed but ultimately re-l l stored before the core slumps. The HPCS system operating at rated flows is ,

used in the same manner as was done for the TQUV cases discussed in Section A.

m The CHRS is also assumed to operate in the spray mode as in Section A. 9

, , - - - - - . . - -- . . - - - -. - .- -.J

Table II .

i,.[

TQUV (ADS + LPCS)

'a Maximum Clad Reacted Maximum Core Melted Start of ADS -

Time Time .

(min) Fraction (min) Fraction- (minL

. '100 '

.0022 130 1 0 -

3 1 125 .91 320 0.90 180 0

150 l .9994 190- 1.00 170

$ 200 .9994 220 1.00 210 T T

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7 Five cases with delay times ranging from 100.to'200 minutes were run for the'S2E sequence. These results are depicted in Figures 20 through 24 and in Table III. Inspection of. Table III indicates that if the rated ECC flow is restored by 100 minutes' (before incipient melting), a negligible quantity.of hydrogen will be produced with nol potential for combustion. A delay of 125

~

minutes will, however, result.in almost 60% core melting and over 30% of the

~

clad reacted. As expected, increased delay times' result in increased frac-tions of the core melted. -However, the S2E cases show a " leveling off" of the fraction of clad reacted'with increasing delay time and actually indicates .

a smaller fraction of cladding reacted for the 175 minute case than for the 150 minute case. This is because for the case in which ECC flow is restored

at 159 minuces, the primary system pressure is higher than for the 175 minutes case (ccmpare Figures 22b and 23b). Consequently, ECC flow is higher for .the .

175 minutes case (less head to pump against) than for the 150 minutes case (ccmpare Figures 22d and 23d). This.in turn means that for the 175 minutes f case, the core is rapidly reflooded and further metal oxidation and fuel melt-ing is, prevented. However, reflooding the core takes a longer time for the-3 150 minutes case during which time further metal oxidation and fuel melting i can occur. The difference between the results in Table II related to the 150 and 175 minutes cases can therefore be explained in terms of the time required to reflood the core. b 1

The 125,150 and 175 minute cases all produce a hydrogen burn in excess n

i of 60 psia, while the 150 minute case (Figure 22) yields a pressure exceeding

[, 70 psia. The 200 minute case, rather unexpectedly gave significantly lower f H2 burn pressures (50 psia). This is due to the fact that the hydrogen was 3 consumed in five separate lower amplitude burns compared to only 3 or 4 burns I

O l

. ...,.. . ...,.........w..,,, ,

for the other three cases.which.had hydrogen b' urns. " Clearly these results

~

, point 'out the urgency of establishing. ECC flow before or at- the' latest only a - .

a-).

f$w minutes after incipient core melting.

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r Table III .

S2E (HPCS)

Maximum Clad Reacted I Maximum Core Melted Time Time Start of HPCS Fraction (min) Fraction (min) .

100 .01 100 .02 100

. 125 l .32 140 I .57 130 l

150 .54 173 .83 157 175 l .43 177 .80 177 l ..

(175) (.42) (174) (.72) -(177) h

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2d0 . .53 203 '

.89 203 L

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V. ANTICIPATED TRANSIENTS WITHOUT SCRAM OR ECC (ATWS) ,

5/ ' The ATWS accident sequence even without the complication of ECC injection is an extremely scenario-dependent phenomenon that would require the running of a themal-hydraulic code in parallel with the MARCH code to identify'the initial conditions at the end of the neutronic portion of the accident. De-pending on a number of conditions, various degrees of core disassembly'or de-gradation may already have occurred during the oscillating power transient characteristic of an ATWS. In fact, the available themal-hydraulic codes cannot handle the cases in which significant core degradation has occurred in advance of a stable neutronically shutdown condition. A number of conditions can strongly effect the ATWS scenario. _If the re-circulation pumps are tripped immediately, the accident scenario is tenninated within a few minutes.

The peak power (which occurs in the initial power spike) does not exceed about 1.25 times full power and at no time do the heat fluxes in the core exceed

]

CHF. If pump trip is delayed by a few seconds, the peak power may be in the area of 10 times full power, but in none of the ATWS cases reported in the literature do the heat fluxes in the core exceed CHF so that the clad tempera-tures remain well below the threshold temperature for the zirconium-water reaction. To our knowledge, there have been no reported cases run in which the re-circulation pumps were not tripped within 5 seconds. Therefore, in the event that the re-circulation pumps are not tripped, it is not at all clear what the long-tenn transient will look like. The vessel pressure would con-tinue to rise for some time because the relief valve system may not be de-signed to handle all the steam generated at full power. The pressures thus ,

obtained may cause the head to " lift", pipe breaks to occur, or some other

. .n

catastrophic failure of the primary system boundary [ The accident would,then-become a LOCA rather than an ATWS. In any case, nothing is currently known b,m -

about the pressures, power levels, or core. temperatures during an uncontrolled ATUS (non-tripped recirculation pumps). Under these extreme conditions core degradation and/or melting may occur.

Due to the repeated voiding and bubble collapse cycles characteristic of -

such a " runaway" ATWS, there may be a potential for the generation of signifi-cant quantities of hydrogen in-vessel before final neutronic shutdown. .For this reason the ATWS may be of interest for small size containments which uti-lize steam suppression devices such as suppression pools or ice condensers.

Of particular concern is the rate at which steam may be vented to the suppres-sion pool of a BWR during an uncontrolled ATWS. If the suppression ' pool 1s ,

, heated at such a rate that the Containment Heat Removal System (CHRS) cannot cool it, or if the CHRS is inoperative, then the containment may be failed by ove rpressure. ,

Possible approaches to this problem are being studied together with the available tools or conputer codes which may be used in combination with the MARCH code to determine the containment response. Special emphasis will, of course, be given to the hydrogen problem. .

i

VI. COMPARISON WITH INDEPENDENT ANALYSIS .

i .

..- / Comparison of the results obtained in this analysis with those obtained elsewhere are inconclusive. In terms of the containment' prersures generated during an H2 burn, a preliminary calculation done by MP&L (see Ref. A) to demonstrate the effectiveness of their H2 igniter system suggested that the peak pressures are on the order of 56 psia. This is consistent with the cases .

considered in this analysis, which assume H2 flammability limits of 8%-4%.

A set of three cases were ' performed by Batt'elle (see Reference B) using

, the MARCH case.. Two of these cases are directly comparable. The first case was a transient (TQUV) with ECC delayed 150 minutes. The containment response graphs were not available, but the core ceit fractions and clad reacted frac-tions agree very well with those obtained here (see the data in parenthese,s in Table I). Sufficient information regarding the configurations for these runs was not available to detennine which ECC systems were used in these cases, but

]l]) <

the Battelle results seem to be consistent with the.present results obtained for utilization of the HPCS system. Similarly, excellent agreement was seen for the second case which was an S2E accident with ECC delayed by 175 min-utes (see Table III). The third case essentially corresponded to the baseline TQUV case (no ECC, Figure I) except that in the baseline case the core was al-lowed to slump when 75% was melted. Again, up to the point of slumping, the two cases agree quite well during the boil-off phase.

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_-_ __ ,_ -___ - _ - ____-. _ _ . _ _ - _ _ _ ~ _ _ _ _ _ _ - ____ - _ _ _ _ _ _ - _ _

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REFERENCES , . . .

./ -

.i (A) " Preliminary Evaluation of Additional . Hydrogen Control Measures for the '

Grand Gulf Nuclear Station," Miss. Power _ & Light Co. . docket #'s 50-516, 50-417..

- (B) Private communication with J.'Long, U. S. Nuclear Regulatory Commission.

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! 22 - - -

APPENDIX A ,

3 The graphical results of the cases discussed in the text are presented in' this Appendix. Table A-1 gives a brief description of each of the 12 cases.

Table A-2 outlines the contents of the various parameters shown for each case.

The figure numbers used for each graph begins with the figure number from Table A which identifies the case. Appended to this number is a lcwer case letter (a through i) frc:n Table B which _ identifies .the parameter shown'in the graph.

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Table A-1 ,

7

\- ,

ECC Containment Injection Break-Accident Time On Heat Size Ficure Type (min) Recire. Type Spray Removal (in) 1 No No TQUV -

No No N.A.

2 TOUV 100 No HPCS* No No N.A.

. 3 TQUV 110 No HPCS* No No N. A.

4 TQUV 112 No HPCS* No No N.A.

'S TQUV 120 No HPCS* No No N.A.

6 TQUV 130 No HPCS* No ' No N.A.

7 TQUV 0 Yes HPCS* No No ' N. A.

8 .

TQUV No 0.0 LPCS No No N.A.

9 SE2 No No -

No No 1.0 10 TQUV 100 Yes HPCS Yes Yes N.A.

s 11 TQUV 125 Yes HPCS Yes Yes N.A.

12 TQUV 150 Yes HPCS Yes Yes N.A.

13 TQUV 175 Yes HPCS Yes Yes N.A.

14 TQUV 200 Yes HPCS Yes Yes N.A.

15 TQuV 150** Yes HPQS Yes Yes N.A.

16 TQUV 100+ Yes LPCS Yes Yes N.A.

Reduced ficw rates

- H2 burn limits, 10" to 07, ;...

+ LPCS has no injection phase l

l

. , - - . . . . . - - - - ... - - - - - - . .- -- - . . . ~ . -

y

Table A-1 (Cont'd) ,

ECC Containnent Injection Break Accident Time Cn Heat Size Figure- Type- (min) Rectre. Type Spray- -Removal (in) 17 TQUV 125+ Yes LPCS Yes Yes N.A.

18 TQUV 150+ Yes LPCS Yes Yes N.A.

19 TQUV 200+ Yes LPCS Yes Yes. N.A.

20 SE2 100 .Yes HPCS Yes Yes 1.0 21 SE2 125 Yes HPCS 'Yes Yes 1.0 22 SE2 150 .Ye s HPCS Yes .Yes 1.0 23 SE2 175- Yes .HPCS Ys5. Yes 1.0

, 24- SE2 200 Yes HPCS Yes Yes 1.0 c:.

Reduced flow rates

- H2 burn limits,10% to 0%

+ LPCS has no injection' phase O

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Table A-2 ,

Sub Description a Containment Pressure b Primary System Pressure c Average Core Temperature ,

d- ECC Flowrate e Fraction Clad Reacted ,.

f Fraction Core Melted -

9f '-

g Mass of Hydrogen in Primary System h Hydrogen Leakage Rate from Primary System I

1 Coolant Leakage Rate from Primary System

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ML20072L681

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