ML19220C848
| ML19220C848 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/24/1975 |
| From: | Washburn B Office of Nuclear Reactor Regulation |
| To: | Kniel K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905150724 | |
| Download: ML19220C848 (2) | |
Text
...
/(v h /._
p
- cc..at y, 32' s
g e.
k vfe a e
';arl Kniel. Chief, light Water p.cactors 3 ranch 2-2 ZI.CC.I. DISCUSSIO:; (MARC 2 2C,1973) CO:;CCE:;Irc u.EE FII'ST-ROCiD QU:STIC' 11.5 - IHRIE MILE ISL\\.'O ECLEAR STATION. O!IT 2 (?!I-27 Participants :
T. Cri ins. C"UEC J. Vann, CprSC R. Kiessel, NRC TR
- 3. *a'ashb urn. RC : L Purpose.
Applican ts ' representatives regrect for discussion and clarificatio: cf firs t-round question ll.I.
The s taf f stated that, by way of clarification of our first-rcund ques-tion 11.5, we would like the applicants to identify these safety-related s tructures, sys te=s, and corcenents where t*- ey migh t anticipate a problem in survival and proper functioning if the criterion for the cenical spread
'f an 'i:Cineing jet f rom a pos tulated pipe break or crack vere-1.
?.ienty-two and one half degrees half angle out to five pipe dia eterm from the centerline of the source pipe followed by a ten degree half angle Graad beyond that point for the i=pinge=ent of high quality steam and air; and Ten degrees half angla for the impingement of all other redia.
It is the staff's understanding that the applicants ' reply to a related acceptance reviev question (9 7) is not ec=plete.
If, as indicatid bv the applicants' representatires in this conversation, the criterion u' sed was a forty-five degree included angle (twentv-two and one half degree half angle) out to five pipe dia=eters frc= the centerline of the source pit a followed by a fif teen degree half angle spread beycud that ooint, the af f vill not require further analysis for the i=pingement of high quality stea= and air.
The response to question 9-7 should be anended to adequately describe the jet shape assu:-ed in the analyses or this infor=ation should be included in the response to request 11.5.
\\\\1 051 L
~
0*CE*
e W * '" * " 8
- cats
- Form AEC.)I d ( Rev.19 3 ) AECM 02+0 sao
- q
- e si es.
s a o.a e.
290s t 50W 4
e
-2 The safet/-related ite"s to be identified are tnose which will h neces >arv to tocerate or control (including the safe shutdown of t.:e reactor, if necessary) the affects of the accident which caused tne pipe creak or crack. This question ap? lies to pipe breaks insida and outside the contain=ent.
7.-
/ % 'i
/
B. I.*ashburn, Project Manager Light Water Reactors 2ranca 2-2 Division of Feactor Licensinc DISTRI3i'TIO::.
Docket File L'4R 2-2 File B'4as hburn MSe r rice RKiessel 117 058 LWR L'
E vr3:TR L'JR 2 '(RL gz n,,,. V.
c"'u
- BWashb, eds RKiessel %. -. _.
Khlel e===-s*
3PgZ... '/ 75 m..
3/2,4 /75 3h /75 Form ATC 913 t Rev 0 9 )) AICM 02 0 2*o c42
- e*
s ao.s e4