ML20024C603

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Evaluation of Transient Behavior & Small RCS Breaks in 177 Fuel Assembly Plant, Suppl 2 to Vol 1,Section 6.0, Small Break in PORV W/No Auxiliary Feedwater & Single Failure of ECCS W/Realistic Decay Heat.
ML20024C603
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 05/12/1979
From:
BABCOCK & WILCOX CO.
To:
Shared Package
ML20024C595 List:
References
TASK-07, TASK-GB GPU-2214, NUDOCS 8307120863
Download: ML20024C603 (19)
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Text

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" EVALUATION OF TRANSIENT BEHAVIOR AND SMAU.

REACTOR COOLANT SYSTEM 3RIA:S IN THE 177 FUEL ASSEMBLT PLANT" ,.

VOLUME: 1 SICTION 6.0 - SUPPLIMD.'T 2 .

MAY 12, 1979

).

"SMALL 3REAK IN THE PPJ SURIIER (PORV)

  • TITE .

NO AUXILIARY PEI:{JATER AND SINGLE FAILURE OF TEE ECCS WITE RZALISTIC DECAT HEAT"

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l 8307120063 790512 -

PDR ADOCK 05000289

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P HOL .

5=all' 3 eak ih the Pressuri:er (PORY "ith No Auxiliary Feedvater and a Single Tailure of the ICCS ,

l L'ith Realistic Decav Hent

1. Introduction The evaluation of s all breaks in the pressurizer in Chapter 6.2.3 of the main report. covered the followi=g two cases: . .
1. Loss of r.ain feedwater resulting in a stuck open PORV, no loss of offsite power, and one EPI train available for energency core cooling.

. 2. Stuck open PORY vith loss of offsite power a2d one EPI train.

This supple:sent provides the additional analysis of a s=all break of the PORY vithout.feedvarer availability and a single failure in the energency cera cool-ing systen with realistic decay heat. i*or this assu=ption, the 177 fuel asse=bly

~

lowered-loop plants fall into two categories:

)

1. Oconee vill have one EPI pu=p injecting through one train for 10 minutes and two EPI pt._ps injecting through two trains thereafter. ,
2. All others vill have one EPI punp injecting through one train for 10 =inutes .

and one EPI pu=p injecting through two trains thereafter.

. This evaluation is b'ased on ths flow eouivalent to one EPI pump. Consideration of the reshits for Oconee is given in Section 4.

The evaluation shers no core uncover and no cladding te=perature excursion. By the end of the analysis long tern cooling has been established via EPI injec-1 l

l tion and the criteria of 10 CFR 50.46 are net.

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2. Method of Analvsis The analysis

=ethed used for the evaluation is that described in Chapter 5 o.f. r.efer.ence u.. .... 4., 3AU-10104.,.

Rev. 3, "3&W's ECCS EvaluaE1on Model," along with the

o.d.el c.odificatio.ns

. .. ......_.. .. o.f. .refere.nce

. . . . ... 5. As dictated by reference 6, the se==ou111 c.o.r.r.elat.........a ion was _. .use.d

. . fo: s.ubcooled

.. . . . . .. flow rather than the modified Zaloudek cor-r.ela.t.

. .. .. ion, as pr.o.. posed . .. . in r.efe.rence

5. The following conditions and systes re-s.po.ns.es

. . . were . . .as.s.u=_ed. . . .. .. dur.in..g the. t.r.ansient.

a... D...e. r.e.a.ctor .... _. . . is . .operat.ing at.102: of a steady-state power level of 2772 2iit. .

De.c.ay heat. .is...

. . . . . ba... sed on 1.0.'ti=es the 1971 ANS 5.1 standard for

  • 34 *te re-

~

at.t.o.r. o.peration (;ealistic decay beat). .

b.. ' .Th..e

. . . . . . leak . . o.c.c.u s i.n..s.t.a;t.aneously, and a discharge coefficient of 1.0 is used. for.' t.he, e tire analys.is. Begoulli's eqt$ation was used for the sub-c.oo.

. ... led por. ..

.. ..._ tion . .of . the. . . tr.ansient,

. _ . while Moody's correlation was usef in

) t.he t.wo-ph.ase po.r.d.on. -

c .

No o.f.f.s'it.e pove; is ayailable. . -

d.. . D. e. r.eac.t.o.:. t.r.ips on lo.w.. .. pr.. .essure (1900 psig)...

e.. . n. e s_afety r.ods begin e=tering the core after a 0.5 second delay frc= the t.i=e

_s t.he r.eacto; t..ip

.. . .... sig a1 is r.eached.

f.

.. The RC...a pt_-.ps t.;.ip and coastdown coincide .t with reactor trip.

3, . One

. ... c.c.=.plet.e t. rain of ..t.he energency safeguards syste:s fails to operste,

. .learing a .. two CITs and only one EPI and one LPI system available for ,__,.ed Anject.

ion t.o =_itigate .......

t.he. consequences of the LOCA.

h. -

T.he aiw414ery. .feedwater (L*) system is assumed not to be available during -

t.he. t.r.a.n.s.ient. .

1.

-. The

..a ISTA.S t.r.ip, i.n. cluding s.ign.al errors, occurs at a RC pressure cf N*! .

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3. F.esults l Tigures 2 through 15 show the evolution of several key reactor coolant syste=

variables for this event. The CRAIT2 noding diagram for this analysis is pre. -

sented in Figure 1. The following table presents key results of the analysis:

Secuence of events Time, s 3reak occurs (1.05 in.2-9 top of pres , 0.0 suri=er equal to a PORY break)

. Reactor trip

. '53.0

. . ioss of o'ffsite power, RC pu=ps coa'st- 58.0 -

down occurs F.ain feedvater coastdown ends 72.0 l . .

EPI injection starts 210.0 .

~

Natural cir=ulation essentially lost 1690.0 Y.axi=un repressurizatio= reached 1590 psia G 4630 see

). .

Iess te:m cooling establish.ed

. 4 700 Y.in s.cz core nixture level d

16.9 fe e 2290 see .

Peak cladding te=perature 720F (initial value)

The RCS depressurizes s-ith the initiation of the break as shown in Figure .2.

- o Since the break is in the steam space of the pressuri=er, the RCS depressurizes rapidly to the ISTAS setpoint, thus initia:ing the EPI injection. At 1000 seconds in:o the transient, the RCS repressurized because the pressurizer ,

goes solid as shown in Figure 3. As shown in Figure 4, tiie SG secondary side ,

liquid volu=a goes dry (approximately 950 see) just prior to the pressurizar going solid. The reduced primary to secondary heat transfer also precipitates t'ha increase la RCS pressure. The pressure continues to increase until the RCS net volune balance is met at 4700 seconds. This ne't volume balance is the difference be:vcen the EPI volume injected, leak volu=e, core boil-off

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volu=e, and stea= condensation by the EPI. Also, at this time, the EPI in- >

jaction rate exceeds the core boil-off rate. Thereafter, syste= pressure vill decreasi proportienal with decay power, thus ft:=1y establishing long term e.coling. Core covery is assured, thereby assuring no increase in cladding te=perature. Thus, criteria of 10 C7R 50.46 is satisfied without the use of auxiliary feedvater or an addirional EPI train.

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( 4. 5 all 3:eak in Oconee Pressurizer Secan Spac's

Mithout Teed scer i

The discussion of systen response in sections 2 and 3 was based on one opera:i=g EPI Pu=p. Iven with a single active failure, Oconee vill have two pu=ps avail- l able within 10 minutes following ISTU actuation. The Oconee EPI pu=ps are approxi=ately 10: lover in capacity than the generic EPI capacity used in sec-tions 2 and 3. For the first 250 seconds up to ESTAS action systen response v111'be identical. Following that, for 10 ninutes, the Oconee systen liquid i 3 l inventory will lag the generic calculation slightly (naxi=un effect - 70 ft

, at 950 seconds). At 950 seconds Oconen vill establish two EPI puEps or about l 180% of the injection used in the generic evaluation. Ther~efore, Oconee vill  !

i achieve long tern cooling such earlier than .the generic evaluation and the re=ainder of that evaluation will bound the results for Oconee. ~

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