ML20039F435
| ML20039F435 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 04/22/1977 |
| From: | Happell J BABCOCK & WILCOX CO. |
| To: | Cox T NRC |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201120458 | |
| Download: ML20039F435 (3) | |
Text
.
G, /g 4
TET ECOPY Rf*OUCST T H Co A VRC so.
nos.s g 22 1971 E.0C4780M 6MNA, 'Mb mns statars A92.
yj7 car '7243 m _ d ' bl APPfLa -
E flu m gg, GIDER OF P/.0ES 2
., =
r
.i s,
e c- --
~~--A_m I
l 1 i, l
f i
l ',?
i
,a 6.
}
I-
)
I g'.
i-s l
'i
?
t i
i I
y i
t
,\\ <
r.
l
. f,.
i-I 9
l h
t i
.f__
)
I e t h
e
,t j
l t
l a
s f
e i(.,
t-i i
8201120450 810403
~
~
T
.= -,
~..
8 i
n
~~
Amcod. 9 6.2.
Containnent Syntera Contr.innent Tunctionn! Der:f o,
~
t antcinr.cnt syr. tem's denign in doncribed in the applicant's SAR.
Inter-
- criterin required to encore cor patibility between the appliennt's con-2nt syntcm and anbcock-205 equipront are prenented in thin coction.
antair.ent building's donign function in to protect the public frooi the tici radiologient conncquencen of severo accidents, including a postuinted af-coolant s.ccident (LOCA).
cia regnrding the st ructural Integrity requirements for the containimnt followst 5
.a containment omt be denigned to withstand the of fects of the svmt vero naturni phnnocenou and man-enused evente designated an druign banin ent o fer tf.c particular ett o.
The ba ni n for scinnic design of 1411-7 plied equipecnt in given in ocction 3.7.
,a containment and designated interior st ructuren s.ust be denigned to thetend t he ef fectn of af sniten (see s.cction 3.5) as well no the dynanic
' facto conociated with a LOCA. nuch an pipe whip and fluid jet f r pin gnen t.
a boato for denign for a pipe break in the reactor coolant systen in vca in section 3.6.
p np Q
a containment and designated interior structures nunt be designed to with-l and the prennure and thermal forces annocinted with n I.0CA nnd postuinted to otcam line and feedantor line break accidnntn.
Analytien) unethods and j
nunptions and_ent wl isnan and energy rcIcasen for ontulated RC pipo enka are presented M Appendix 6A.
bec c rd - 4 m gp-raio.me-ddo-4m-- a 8
2ctrus-+C-posw4need-y1 e-4 rca;e -luent4ene-viu be-.prouidod_in. tha y p p13-3 l
C o--G4.
IIuon und energy relenses onencinted with pontuinted stenm and r duator line breaks nro provided in Tolh4. Itr.l.M -2 c4 86.8.S - 3. Associ-4 interface criterin for those relessos are provided in sections 5.7. 5 1 10.5.5.
'9 t contclivnent cubecepar tinent in which n I.OCA occurn will pressurire much o rapidly thnn the contninnent on a wholo, renulting in short-lived pron -
o differentisin betucon the nubcortpartracnta of the reactor building.
I
'anure-tcr.perature calculat ionse stuut be innde to determine the required ength of cubconpartment ntructures an well an the pincccent and denign
,[
[p d the cubcoepartreent vent s.
Analyt ient met hods and snr.urpt ionn uned in culct ing LOCA r. ass and energy rolcanghidsTT EnTdf rolense dntah' 5F go the containment unbconpart-n to cro prosented in py tton 6.2.1.2.
pect ruca of postulatesT['pc brcnk locn t i on nM ! I ' awa+LJ t-Juh. -*$~
oa.*t '
rAn.
Ascociated interface criterin lnre provided in r-cct ion k
.25.
{ c,,sta(o wxJ h n d e (. 2.8.Z..
[
violonn s. hall bo imde in the containment nyuten donico to ensuic con-g nacnt integrity ngninst the pote ntini genernt inn of hydtc.nco folinutnn a
ost uint ed LOCA.
Hydrogen generation raten eniculatcJ for the nabcock- '
cro discussed in ocction 6.2.S.
ctAM H
6,2.1.1.
Containment structure (pW- "n*sg p ? j
(__-___
~ _,. _
1
- nu. o e
i 6.2.2.2.
IInr.c and Enorgy RcIcnne for Cut *co_sn r t eren t An 3.yn i s
.62_1_. 2.1.
Reactor Coolant _Sp. ten rear.o end energy relcano used in evalunting r.ubco:partent prer:rm ra t.r a n -
to Jo cciculat ed uitti the CRAFT 2 cathenatical nodel.2 in accordr.nce with Ictory culdeltnen, the t.nne ense CP.AFr2 input is the appr.ved 70.'.-fuel un-ly r,CC rodel, which ia doncr itecd in P.IN top f en t repor t !>N -10101" und 11-7cted in rigurcs (.A.4-1 and GA.4-2 of Apperu!!x 6A.
The seafeguardn power 3 Cf 3876 int, is used in the annlyses.
hn
)
cnd energy relenne intun lor the Initin) 2 :;ocondo of blowdown oro pro-J in enbutor form in t'-
ci- @ canr*.
"l.p.,
!1oul,1c-ended I,rcaks wi t h tut a l 2
creca of 2A, A,.0.5A,.and 1.0 ft (A E pipe flow area) are considered at following locationst l!ot Ic3 at the reactor vecrcl.
fc[
iket lag at the arcan generator.
[
- [ (,
4,7.\\ I
- Cold log at the reactor vessel.
l
- blo I?g at the steam generator.
r.u h rc 5s 3~
kn*. Lo t
ag eenoit ivit y studica in t ie%Ing aJjacent to n bren cau perforued to
{
istrato convorgence in the solution M.- 1 h..u.J the!r =
.-.. v..;
L':? ?..-thc
.s
'cu--
M - ^nov-rw pivt4y-w.e4 44ag _h ! mu j nc r cy r c I c nn e). boc.t 's"f?.-- f = _ u n e p
inted with duuhlo-ended breaks in the prc6667 rce t
j r Itne, prescubaer r.urgo line,. and core flood J'ine, one. peoJat,4 Whe.
J
'o11 cuing crit tent flow codel anrau=ptions are used in the casa and ened co calculations:
'n tbc out. cooled flow regime,. the leak dischargo flow rate in obtained l
roca the turno11 relation, which has the foria O - (2co (P3- (1 - C)P ]..
x<O g
g 2
here I
C - crit.ical n.aso flux,,
e p
naturated liquid density, i
g P3 = upctreca proncure, P2 ~ vapor proe.nura at upstroani teeverature, i
x - lenk pnth fluid quality.
i aleudek nppIted thin roIntion to corrcInte the r.n-called a cc ond-s t op cit ic-a l choked f Iwa cr>ndit lon. 3 E The cr'p t r ica 1 coef ficient C, which is
'tually a function of Py (soc rigure 4-10 of rvfurenco 17),
f= con.crva-Evely input an a count ant value of 0.19.
The upst rean pa m.nore P and a fluid propert ies that are input in t he Burncil equation aro baned on 1
e ctagnat Ion flutd condit ions in the CRAIT code Icak valux.
py