ML20024B328
| ML20024B328 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/19/1979 |
| From: | Rosalyn Jones BABCOCK & WILCOX CO. |
| To: | Lightle R BABCOCK & WILCOX CO. |
| References | |
| TASK-06, TASK-6, TASK-GB GPU-2449, NUDOCS 8307080441 | |
| Download: ML20024B328 (7) | |
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Attached is a response to ':7A letter T.-3020 deall=g with s=all break LOCA "M
~~
analyses
- This response is based em a qualitative, not quantitative, re-fi view of the concepts presented in the paper, "Decsy Heat Re= oval During A 1
Very Scal 1 Break for a 3G 205-Tuel-Assembly Pk'1," by c. Michelson, January, pJ-i 1978, which was attached to the letter. If you have any questioca, please 6
5
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contact ne on extension 2066.
K.
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'*Q/A: Reviewed and approved,for con-
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Ras;onse to T*/A Letter K-5020. E ergency Core Cooling Syste= -
g 5 211 Break tecA Analvsis N4w-2-la(AM. Acril 27. 1973 2
V.-
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Via r/A Letter K-5020, 7/A trans=itted to 3&W a report entitle'd. " Decay Rest g$
lenoval During a Very Small LCCA for a E&W 205-Tuel-Asse=bly PW7.." by C.
liichelsen, dated January,1973. This report presents a si=plified, hand
[..J calculatica review of the s=all break transient and potential consequences M
for very s=all breaks not explicitly exz=ined within the s=all break topical
$g j
for the 205 FA plant, 3AW-10c74A. Rev. 1.
Within this paper, the following concerns were expressed for tne very s=all breaks:
6 W.
1 1.
Eov is decay heat re=ovedt U
. i1
---p 2
Will systa= repressurimstion occur? If so, could a s= aller case be a g
E>:.
worst breas?
I.f the operater isolates the break, vill syste= repressuri:stion occur?
E 3.
If so, will tha pressure relie.f valves be subjected to slug or two-phase
{
flowf n
a; Iasponses to these concerns are developed in the subsequent paragraphs.
i Before discussing these concerns, a general overview of the s=alk break tran-g.
sient in a B&W 205 plant needs to be briefly discussed. S=all LOCAs can be v
viewed as a slow transient during vnich the RCS can be described as a sealed k
=ano=eter.
See:use of the internals vent valves, no extensive steam bubble M
v111 for= within the reactor vessel while any significant liquid inventory
.X.-
re= sins in the loop. Many exper1=ents have been run which show that so long U
as a fluid, with qualities less than 70% or so, covers the core, no adverse K
core ta=perature excursica vill occur at TeEy heat power levels. Thus, any Y
proble=s with s=all breaks vill only occur after the ECS loops have depleted
[
y choir inventory.
a Decay haat re= oval fren the core regica is no problem as stated above. How-E.
ever, decay heat re= oval frc= the syste= as a whole needs to be examined further. There are two vays of re=ovin; decay heat frc= the systa=; via the break and/or via the steam generator. Both of these ite=s are discussed in detail in the TIA letter. For the very s all LOCAs of interest in this dis-cussion, it was shown that the break alone is not capable of re=oviag_A.R the
?
_ decay heac and heat re= oval via gne stes= generatcr 2.s necessary.
k~ nile the 'N a
T/A-precicted hteak size that this occurs at was not checked quantatively, tha actual break si:e that it occurs at is incensequentisl. Such a break j,
size does exist where the steam generators are necessary.
Ths role of the steam generator as a heat rc= oval source is basically as described in the letter. Initially, oatural circulation vill be =sintained in the systen.nd the necessary hest re= oval is easi.17 sce==plished. Once a steam bubble of sufficient si:e necessary to fill the U-bend at the top of the hot legs is for=ed, natural cir:ulation vill cease. The inter =itesnt naturs1 circulation discussed in ene letter vill not occur due to the slow n:ture of the s=.111 bresk tr..nsacnt.
Octe nstur:1 circulation ceases, the
?
systen will repressurite se evnst until the SC pri=sry side liquid level d::ps
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below the SG secondary side level and condensation helt transfer is established.
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During this period between the natural circulation and condensation heat re-
= oval codes, the it.tter excresses concer..s that the liquid inventory within 2
the syste= will be depleted at a rate in e= cess of the rates for the breaks 7
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analyzed by Z&W because of the pm W a1 represcurization of the syste=.
t.s concerned that this ulti=stely will result in = ore core uncovery than that a
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shown in the s tll break topical recort 3AW-lC074A. This is not the case.
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During the natural circulation phase, it is obvions that the s= aller the break, E
p the slower the loss of system inventory and the longer the period of catural circulation. After natural circulation ceases, syste= pressure vill be con-y trolled by a "volu=e balance." That is, the syste= pressure vill balancs at 5
a peint unere the volu=e of fluid discharged through the break equals the y
volu=e qf steam being created in the core. Since the cold leg fluid enthalpy -
R renains unchanged during a s=all break transient, the volu=e relief out hfk
?
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The vol-the break increases vi-M 'ncreasine svste= oressure ane. :reak st=e.
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1Ee of stean beint generated dn the core ceereases with increastw oressure.
i k
' As Enibreak decreases in size. the RC syste= v111 reoressuri=e to a higher value; enus the volu=e relief out tne break necessarv to narch tne volume _
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ci stes.n beins; creacea cecreases. Tnere ore, cae system inventory vill be E
. lost at a slower race as cream, size decreases. Once the SG becoces.va11able 5
.for condensation
- neat re= oval, the pri=ary system pressure vill depressurize k
to approxi=ately the SG secondary side pressure. Since the secondary side p
2 break
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of the SG vill respond in a sh-9mr manner to that of the 0.05 ft analy=ed in the topical, the pri=ary side pressure response, following tbs 2
7 (1
advent of condensation heat re_ oval, vill be s4-4'ar to that of the 0.05 ft
?
break. Thus, for the s-miler breaks, the svsta= inventory vill always be greater than that for the 0.05 ft break and the core vill always re=ain 2
U covered and will noc undergo a te=perature excursion.
. (
i In the paper concerns are raised relative to isolation of the break after g
natural circulation is lost. The sce=ario presented in the letter is reason-g able. Should the break be isolatesi at that ti=e, systen repressurization to the pressuri:er safety valve setpoint is probable. 'No-phase or liquid flov through the. safety valves vill also probably occur. 0=ce the syste= depletea sufficient inventory to establish condensation heat transfer across.he SG, 1
The the syste= will depressuri:eand =o further loss of inventory vill occur.
core vill re=si corerad for this secenario and no te..perature exc=rsion
. Should the pressuri:er safety valves become da= aged because of the occurs.
two-phase flow out the valves, the response of the system would thes be si=ilar to that presented in the FSA't for the pressuri=er safety valve stuck open accident and no core uncovery occurs.
.is far as the appropriateness of the operator using pressurizer level indica-tien to trip the EFI pu=ps, 35% agrees that the level indication is not a reliable indication of the state of the R:5. Ecuever, use of the pressuri:er level indicacica, along with syste= te=perature and pressure ceasurements to ensure that the system is still in a suos antially st.bcooled state, will pro-vide sufficient guidance for operator action.
In s -r/. While the TVA pacer raises valid concerns and gives a detailed.
4xar.in. tion of ene small break transic=t. the s=211 bre:L topteal resort provides suf fi:icnt :n:1.ses to ensure tne ability of the S&W'2:5 plant ICCf syste= to control s= 11 brc:k in tne 105.
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References:
(1)
- 3. M. Duna to J. Taylor, sa:e subject, Tebru::y 9, 2973.
(2)
- 3. H. Dunn :o J. Taylor, sa=e subjec:, Tehruary.16,1978.
y; t-
?.eferences 1 and 2 (attached) rece==esd a change i= 31*J's philesephy for E?!
s-E j
syste: use duria; icu-pressure :: ancien:s. 3esi::117, they rec==end leaving
[
the K?I pu=;2 cn, on=c EP! h:s been inizi::cd, until 1: c:= be de:!e-*-~' -hs:
the ho: le; ter.pera:ure is =cre :h:.s.30*F helev Tsar f== the RCS pressure.
f 4
r
.... 2:aeles: Ser.ica believes this code can cause the ?.03 (inc1" g..:he. pre.ssurizer).
p.
i-to go solid.
he pressuri:e reliefs vill lif:, vi:h a va:e surge th:=u;h the discharge piping in:o the quench tank.
~ - " ' " * * *
- We believe the !c11cri:;;; incides:s she:Id be evalus:ed:
1.
If the pressurire: ;;ees solid vi:h one or = ore E?! pu=;s cc :inutzg ze operate, veuld :here he a ;; essure spike befc"re :he reliefs o;en which could cause da= age to :he ?.CS2 2.
Wha: da.= age veuld the vs:c: surge :hree;;h the relief valve dischs:g'e piping =d quench tank cause?
To date, ::u: lear Service h:s n:: no:ified our cpers:i=; plan:s :o ch:.n;;c EFI policy
~
}
consistant with 2:ferrnees 1 and 2 because of cur cheve-s: ::d ques:icas. Ye:. the l
referenc:s su;;es: :he possibili:y of uncoverin;; the core if ;;esca: E?! policy is con:inued.
j I
Ve :=qu.N : th : :::e;;s:icn resolve :he issue of hev the HP: sys:e= should be used.
Ve sie sv..il ':le to.h.* p as neded.
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