ML19320A215

From kanterella
Jump to navigation Jump to search
Requests Addl Info Re Analysis of double-ended Break in Line Connecting Core Flooding Tank to Reactor Vessel.Info Needed to Complete FSAR Evaluation.Analysis Should Be Conducted Using Approved Model Per Interim Policy Statement
ML19320A215
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/13/1972
From: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
To: Phillips J
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8004210517
Download: ML19320A215 (2)


Text

_ _ _ _ _ __

p

.t

__v...,.+-

m

^m [y*

/

2,*

Of

.s

. x

x42

..M_ a.. a mu ad.1 ~m. ~.%

.w -

IM AMI

  • Docket No. 50-313 I3 E I

99D A*=====

Power & Light Company

}

U,. g ATTE:

Mr. J. D. Phillips c

r}

Vice President-&

g' TD Chief Engineer Sixth & Pine Streets iha d

g Pisa Bluff, Arkansas 71601 Gentlemsa:

On the basis of our continuing review of the Pinal Safety Analysis Report for A*===as Nuclear One - Unit 1, we find that we need additional informa-tion to couplete our evaluation. The specific information required is an analysis of a double-ended break, in the line that connects a core flooding tank (CPT) to the reactor vessel. The location of this break should be between the reactor vessel nosale and the first check valve leading to the CFr. This analysis should be conducted using the evaluation model approved eder the Interim Policy Statement, Appendix A. Part 4.

In order to =mintain our licensing review schedule, we will need a completely adequate response by.tagust 14, 1972. Please inform as within 7 days after receipt of this letter of your confirmation of the schedule or the date you will be able to meet. If you cannot meet our specified date or if your reply is not fully respewise to our requests, it i-nighly likely that the everall schedule for completing the licensing reviet for this project will have to be ascendad. Since reassignment of the staff's efforts will require completion of the new assiasmant prior to returning to this project, the extent of extension will most likely be greater than the extent of delay in your response.

Please contact us if you desire any discussion or clarification of the material requested.

Sincerely.

Original signed by

p. C. DeYoung
1. C. DeYoung, Assistant Director for Pressurized Water Reactors

/

Directorate of Licensing

)

ces See neat page 3-2 O 5

.. ~..

..- w

/

8004210 5 ' _

~

- - ~ -

' ~ " ~

~~~

{'

y.

.p.

-~

V..

Aukenses Feues" & @ Campany 2

I 3 1972 f

est' Esemos Josell, Esq.

Eeuse, Belas & Jampe11 1350 Tamer w t m=,

Metle Beek, A*-

722 1 7

2 1

DISTRIBUTION:

[l D

AEC PDR SHHanauer

,U g j

local PDR RSBoyd 2

g Docke DSkovholt DRL Reading FSchroeder PWR-4 Reading RRMaccary RCDeYoung, L DKnath I

PWR Branch Chiefs RTedesco RWKlecker HDenton Licensing Assistant OGC Project Leader DDavis R0 (4) f I

l CRESS:dp L:PWR-4 L:PWR-4 L:RSYS L: AD/PWR /

/

f T4132, Y-Y'

  • avis AS etiter-~~ ~VStelTb RCDeYbarni"'

i T6104 R34 hO

', 7/1d/77"' * ~7/j{72-77 72 7/f1/72 7h7f-t72' f

j

.... k...

DATE

  • Fonn AEC-318 (Rev, 9-53) AECl4 0240

.