ML19210B163
| ML19210B163 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/14/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19210B164 | List: |
| References | |
| NUDOCS 7911040094 | |
| Download: ML19210B163 (2) | |
Text
j,
.. =
DISTRIBUTION:
P December 14, 1976
{
~
Docket No.: 50-289 V. Stello K. R. Goller D**0 *'W s
d R.'
id G. Zwetzig A. Ingram Attorney, OELD Metropolitan Edison Company OI&E (3)
ATTH: Mr. R. C. Arnold D. Eisenhut Vice President - Generation T. B. Abernathy P. 0. Box 542 J. R. Buchanan f
Reading, Pennsylvania 19603 ACRS (16)
[
Gray File Gentlemen:
~
~
During the course of our review of emergency core cooling system (ECCS) evaluation models, it has come to our attention that the Babcock and Wilcox (BGW) ECCS evaluation codel,which was used for your facility. uses a nucleate boiling heat transfer correlation during blowdown after critical heat flux (CHF) is first predicted.
This may not conform'to the requirements of Appendix K to 10 CFR
- 50. The criteria for compliance with Appendix K have been estab-11shed by the NRC staff and discussed with B&W representatives.
Enclosed is a copy of our letter to B&W requesting that a corrected
' ECCS model be submitted for our evaluation as soon as possible.
r This matter is similar to one identified with respect to another nuclear steam system supplier's evaluation mcx 31; and, based on our experience in connection with developing a correction for that model, we have concluded that there are ac ep4able correlations which can be used and which have a small effect on the calculated peak clad traerature.
It is expected that the effect on the cal:ulated peak clad temperature would be small enough so that modification of your Technical Specifications will not be requirad; j
however, this must be verified for your facility by reevaluation of the ECCS cooling performance using a correctedreodel.
L
/
3587 054 79110400 9p p
~*~
Accordingly you are requested to submit as soon as possible, a reevaluation of your ECCS cooling performance using an NRC stuff approved model that does not use a nucleate boiling heat transfer correlation during blowdown after CHF has been predicted by the approved CHF correlation.
Sincerely, i
Robert W. Reid. Chief
~
Operating Reactors Branch #4 Division of Operating Reactors cc: See next page
=
l I
t r
I l
~
I r
l I
icr7 nrr a01 UJJ
/
ORB #4:004_O_RB#3: DOR C-y0.g...
GZweth8n DE1110tt)
RWTdf.__.
12//976 12fb/76.._
12//ff76 o...
Form AEC 3tB (Rev. 9-53) AICM 0240
'# v. s. oovsamment paintino orrices so?4.'ese-see
_.