ML19289F920

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Evaluation of Radiolysis Associated W/TMI-2 Incident
ML19289F920
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/31/1979
From: Conine J, Krommenhoek D, Logan E
KNOLLS ATOMIC POWER LABORATORY, OAK RIDGE NATIONAL LABORATORY
To:
Shared Package
ML19289F911 List:
References
ZAR-790531, NUDOCS 7906210139
Download: ML19289F920 (10)


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EAFL ?.aluation of Radic) vsis Ascocir.ted '7ith The Three Mile Island Unit-2 Incident 3/

J. C. Conine D. J. Krc=.cnhoek D. E.uutuel Logan May 1979 7 9 0 6 21Q33 24 79

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I h";' HO DU C'"!O N Subsequent to an 4nciicat en March T8, 1979 at Unit-? of the Three

!Cle Island Pv.cer Plant, the Nuclear Ber.ulstory Ccericcien (:GC) 7 e-quested Department of Eacrry (EGE) cc:ictance to ansess the accu.u-lation and explosive pctentia.1 cf a bubble within the reactor vesrel.

This FAFL doeurent prencnts the chronalecy of FAPL radio 1;rsis parti-cipatica with NRC in the following areas:

1.

Cembustible limits for cxygen/hydrcgen mixtures

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Nature of initial ncn-cendensibles in reactor vessel

1.. Oxygen buildup rate in reacter vessel 5

Reactor radic1/ sis in the event of a main ecclant pump failure e yv,.a,,en

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m Tnece f./?I,calcul:.tiens reauired many assu ptions relative to pla't

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ceterc to maximise hydrocen cnd cryr,en production.

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F./FL assistace en ra iclysic evaluation associated with the Threc d

!hle Islan] Unit-2 Incident was initiated on Satu'-day, March 31, 1979

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rcr..en".cck, 15L 3 31/'l9). This assistance was provided Rt a tire then emer:ency ccnditior prevailed, and direct ec=nunication was es-tablished bct :cen :'!.FL cr.d the !SC per NR FaFL agrectent (Telecon,

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o A ru.rary of the I?.C c.ucstionc, time of question, !3C centact, and YaFL responce is given colcu.

1.

Enat are the expletion and detonaticn precsures for hich pressure exygen, hydrecen, water vapor rirtures?

(3/3179, R. Tedesco, ::?C)

Fesuitc frca laPL cpenscr2d !!alta Test Station and Mir.c Safety Appliance explocien tects were transmitted to :iRC.

Information, relative to the T::1-2 reactor vessel conditions cf 1000-1500 ft; 0

non-condensible can and steas bubble at lO^.r0 psia and 300 F was provided by the 120.

The ccabustica and detonation limits for v A,f a- -~ c.e. 3 ar.a

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v are shmm cn Figure 1.

1.e 42 081

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2.

What is the car. position of gas in the bubble in the *ecetor vessel?

(3 /31/ ly, R. TeJesco, NRC)

At the tine this question was received, NRC hai one estinate of 96%

Hp, and 4% 0, er very close to the combustion limits.

UFC infor-2 nation indicated that the bubble wac forze1 after reactor scran.

KAFL provided an upper bound for the cr/ gen /hydrngen releace rate for an arcunea 0.00 watts /gm ga.T. a heating rate (~1% power) in the liquid. The upper bound was based on naxinug theoretical release rate in a ?OOD ft3 of liquid and gave ~50 ft3 of hydrogen and oxygen 0

per day at 1000 psia and 300 F.

Tnus, it was not possible to produce a large non-condensible bubble frc radiclysis, and furthermore, the mixture was evaluated ne not cc bustible.

Tne bubble was pri-narily cceposeJ cf hyd:ccen, with lesc than 15 exygen.

KAFL experience with hydregen/ oxygen mixtures watP strong dissolved gas return to the ganca flux rqicn choued a ctrong hydrogen /cr/ gen rcccabination cchani;.

D.PL stated that continued operation of the main ecclect pumps is very favorabic to prc :te reccabination of any cxygen that may have formed during the incident. Additional calculations on oxygen release were reported to URO cn h/2/79 3

What is the rate of non-condensible babble growth due to radiolysis for a 0.3$ pouer decay heat level? (3/31/79,o. Tedesco, NRC)

KAFL calculated that the rate of reactor vecsel bubble growth is less than 30 ft3/ day. Additional best estimate calculations giving 3

than 1.0 ft /eay ucre provided to nRC en 4/2/79 All calcula-les:

tiens indicated that radiolysis wou'.d represent an insignificant contributien to the bubble growth.

4.

What are the consequences of venting the bubble fre reacter vessel to the contain=cnt building? (3/31/79,R.Tedesco,NRC)

KAPL calculaticas indicated the folleving:

a) The bubble in the reactor vessel was not combustible.

b) Crygen in tha bubble will recc;bine with hydr: gen in a gants flux region.

c) Transfer of gas frc reactor vessel to containment will raise containment hydrccen concentration by ~3.0%.

Since measured containment hydrogen was given as 1.3 and 1.7%, this would exceed the k$ hydregen upward flame propagation limit.

d) Equilibrium dissolved hydrogen in primary coolant wa: c alcu-lated a: 1700-2000 sec/kg for 1000 p:1 hydrogen at 3CC0F.

e) The reacter vessel bubble will not grew due to radiolysis, however, it vill expand on depressurization.

f) A slow de;as of the primary ecclant (as cpposed to a more rapid depressurization) will result in significant reduction in reactor vessel bubble size with the high calculated primary coolant dissolved concentrations. 242 03z

a-a 5

What i s the c a c c.t of radiolysis in contu$ic.c% iraildir.g?

(4/1/Yy, b. Teacaco, N.T)

Based on the results of one primary coolpat sc;,plc used to est$blish energy depositicr. in the viter and an estimated 100,C00 gallons of water in the contaiment the maximu:n hydregen and c/ygen production was calculatei to be 10 ctd ft3/ day in the 2,000,000 ft3 containment building.

~

6.

Ic rcactor veccel hydrogen concentration beinC reducel due to hy-drogen per. cation:

(4/1/79,R.Tcdecco,I;RC) 0 O

DF', data at 300 F, and applied to the 3OO F assur.ed temperature for the reacter pressure vescel boudnary showed hydrogen per= cation to be insignificant.

7.

Results of edditions.1 calculations in recp nse to questica number 2 and 3 s:cre rcrcrted on 4/2/79 to Eutler, NRC.

Tne calculations substantiated initial conclusions that the reactor veccel bultic 1: : cc.:pocad of very little origen from radiolysis.

E/.FL ctatad that sere hydrogen (grec.ter than 1.0 sec/k ) should be B

=cintaincd in the coolcnt to suppresc cubsequent cr/ gen production.

Uith !!'iC e:ticates of 15% of the core in boiling, it is necessary to maintain hydrc;;cn excocs to suppress oxygen production.

8.

Unat are flrr.ebility licits for use in hydrogen, orfgen rtixtures ct 3000 pain and 3COOF? (h/2/79, W. A. Riehl, Technical Advisory Support at T!2)

D.FL provided the scre oxygen limits as given in cuestion 1, and alco limit: for hydrogen. A conservative set of fic:= ability le " e 4-

+he absence of unter vapor were identified as follo.:s:

% Py Vcl u.c Hydrogen oxygen (Eenainder Air)

(Remainder Hydronen)

Upvard Flanc Propeisation 4

e Ctchic Eurning 8

6 Datonation 15 10 9

Did an explocion or detonation occur in containment, and what are recombination techanicas in containment? IiRC provided information on contaircaent pressure increase (28 psi) and containment gas semples as follows:

(4/2-3/79,Butic",IiRC)

Secole Recults N2 + Other:

02 H2 Air 79 21 0

2330 4/1/79 78.9 18.9 2.3 06304/2/79 79 9 17.6 2.4 242 083 :

m.

L KA?L supnlied the following:

a)

The canna, cod beta induced recembination in the containnent building at 60)0 r/hr reduces an initial hydrogen concentration of P,',by 0.125 per day.

b) The pressure incroace of 23 psi in the containrent building, the decrease in containnent pressure, and the decrease in oxygen conce ation are consistent with ccabustion in containment.

10.

Whct is the effect of paintn, and organics in the containment en radiolysis?

(4/3/79, Butler, NRC) iAFL has no experience in this area.

11.

What is dependence of radiclysis en temperature?

(4/4/79, Butler, v.a. - )

Lower tcrperature increases ox 6e'.# production, but still yields small release rates for present assumed reactor condition of 0.3%

pcwer decay heat.

M L also presented results of additional ca.1-culatiens for 0.067:/peuer, no hydrogen in coolant, and 60 see H /kg in coolant.

2 12.

What is the extent of radiolysis at 10 KJ for each of the following:

(a) no hydrogen in coolant; (b) discharge of coolant into contain-ment; and (c) no primary ccolant flow? (4/5/79,F.Witt,Nac) a) Total maximum hydrogen and oxygen production equals 15 std 3

ft/daywith10$ofcoreinboiling.

b) Eased on coolant sc ple maximum hydrogen and oxyged production equals 1 std ft3/ day for 100,000 callons of water.

c) Total maximum hydrogen and oxycen production equals 10 std ft >/d ay.

13 Wat ic raximum rate of recc binatien of hydrogen in 250,000 gallons of contain:ent liquid? (h/9/79,F.Witt,NEC)

The maginun hydregen reccabination in liquid is c11culated as 32 ctd f J/ day baccd en activity of cemple. The totcl hydrogen in ecntcirncnt Cas sp;ce equalled 40,000 sto ft3 lb. Uhat is a recer.cnded hyccocen peroxide addition to the primary coolant to reduce the dissolved hydrcgen cencentration and what are dissolved hydrogen recenbination rates in the presence of hydrogen peros ide? (4/9/79,F.Uitt, NRC)

ICSL did not p:.tride a rocc endation or information on this questfon. NEC provided inforcation on previous experience on the effects o!' hydregen peroxide en shu.J.... cratistry tran-sients in nreccurized vator rc1cters (EFR1 NP 692, dated h/78).

'.02L end 1[hc c r_ d that eclculations cculd not be perforned u.t.icun be ccer c..a..lu4 cf plune ecolant concentrations and coolcnt activity eutd i:.. purity levcls.

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O O.3 0.0 0.7 1.0 GOLE FRACTIOiJ V!ATER VAPOR Explesica Test F.esults for Mixtures of F4/drogen, Origen, c.nl k'ater Vapor in Closed Contair.ers at 5500F.

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Pristry Coole.nt Ecturns H02 2 and Diccolved Hp, 02 V

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T:E-2 RADICLYSIS MODEL Ficure 2 242 088

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