ML19326C355
| ML19326C355 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/11/1971 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004220900 | |
| Download: ML19326C355 (2) | |
Text
__ _
6g 5d&ggr.yqTyn,{,f &,.. w:
-" Q p
o e..
1, ge i.,-
Gj~g
%f ;' W.,
.:s : W
- &^
5g-
. ; 1s
' lL,% 7, w ;
s.
^; *
-.c
.. u _,
... -... _, ~ n. x 1 07I THIS DOCUMENT CONTAINS Docket No. 50-313 POOR QUAUTY PAGES Arkansas Power & Light Company ATTN:
Mr. J. D. Phillips Vice President and Chief Engineer Sixth & Pine Streets Finn Bluff, Arkansas 71601 Gentlessa:
On June 19, 1971 the AEC adopted interim acceptance critaria for the performance of emergency core cooling eyetems (ECCS) in light-water nuclear power plants. A copy of the Cosmtission's interim policy acate-ment on this matter is enc'esed for your information. In accordance with Section IV.B. of the interim policy statement, before we can complete our evaluation of the ECCS for the Arkansas Nuclear One, Unit No.1, we need information to show that the system meets the get eral criteria of Section IV.A. using a suitable evaluation model. We are continuing discussions with representatives of the Babcock & Wilcor i
Company (BW) that are directed toward establishing a suitable evalua-tion model using BW computer codes for avaluation of plants incorporat-ing a nuclear steam supply system designed by B&W.
The information that we need regarding these analyses is:
(1) For the break size range, location and type unntioned in Appendix A, Part 1, of the interim policy atatement, provide information per-taining te (a) the system pressure, (b) the hot-spot clad tempera-ture, Ioeal mass velocity, fluid temperature, and heat transfer coefficient, (c) the core pressure drop, quality, and uses velocity, (d) the heat flom distribution in the hot channa1, (e) the flow rates in tbt upper and icwr plenues, (f) the flow rates in the.
l broken and intact cold-lag and hot-lag piping, (g) the flow rate out of the break, and (h) percent clad metal-water reaction.
(2) Provide a detailed discussion of the e@.culation used to predict heat transfer during the reflood portion of the transient.
(3)
Discwe in detail any deviations in the evaluation model used in the foregoing studies from that described in Appendix A, Part 1 of the interim policy statement, if that model is used.
OFFMa >
- 4) %/ U 'A _ _ C.a.k M>
4 ' ^^ ^
y
.s &
4 OATE >
g_
l Fora ABC-3ie (Asv.9-53) ABCM 0240
& u. s. covEmmeENT mosTDsG OFFRCO ggy3 ggg.4g9 Y
.. ~.. _ _,. _
. __,_._ wm
_,.,,.,_l
,,e i
\\
AUG 11 1971 Arkansas Power & Light Company In addition, you should submit for our review any changes to the Taehnf e=1 Specifications for the plant that may be required on the basis of the results of your analyses.
When you have obtained the required information, pisase submit it as an amendzent to your application.
Sinceraly, Original Si@8!DI Ette!$.W!.
Peter A. Morris, Director Division of Reactor Licensing Raelosure:
AEC Interim Policy Statement i
1 as: Horace Jewell, Esq.
Bouse, Holas, & Jewell l
1550 Tower Building Little Rock, Arkansaa 72201 DISTRIBUTION:
DocketM
-.'ilson ARC PDR OGC Local PDR ACES (16)
DR Reading WNyer (2)
DRL Reading Seismic Design Consultant PWR-3 Reading J)ticGough CKBeck le0iana SIGianauer FSchroeder RSBoyd RCDeYoung DSkovholt TRWilson ECCase RHaccary RWKlecker DRS/DRL BC's i
l CRESS omes, _DRL _PWR-3 DRL:AD/PWR's DEL:DIR p
.pRL.tpIR Phorris T-1/R 6
FS r
r g
tianiti am>
f/.f/71 8/j/71 8/),/71
.8/[]71 Foran MC-5Ie (Rev.9-53) AECM 0240
- u s covewmuswr 8stMrmo orect iem.-en ne
,.~.- -. _ _.- - -..
.... _... -. ~.
..