ML20235C245

Advises That Proposed Inservice Insp Program for Primary Coolant Sys Acceptable,Per .Review of Proposed Reduction in Containment Design Pressure in Progress.Util Should Consider 62 Psig as Value Until Review Complete

ML20235C245
Person / Time
Site:	Brunswick, 05000000
Issue date:	04/27/1970
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Colby P CAROLINA POWER & LIGHT CO.
Shared Package
ML20235B311	List: IA-87-111, Submits Rept on Plant,As Discussed in ACRS 150th Meeting on 721012-14.Listed Items Can Be Resolved During Const & Facility Can Be Constructed W/Reasonable Assurance for Operation W/O Undue Risk to Public Safety IR 05000254/1972009 IR 05000358/1972003 IR 05000358/1973001 IR 05000358/1973002 IR 05000358/1973003 IR 05000358/1973005 IR 05000358/1973006 IR 05000358/1973007 IR 05000358/1974001 IR 05000358/1974002 IR 05000358/1974003 IR 05000358/1975004 ML20235B308 ML20235B364 ML20235B401 ML20235B405 ML20235B424 ML20235B456 ML20235B461 ML20235B465 ML20235B477 ML20235B488 ML20235B507 ML20235B552 ML20235B582 ML20235B585 ML20235B588 ML20235B605 ML20235B618 ML20235B623 ML20235B649 ML20235B656 ML20235B662 ML20235B670 ML20235B679 ML20235B683 ML20235B687 ML20235B702 ML20235B708 ML20235B713 ML20235B714 ML20235B718 ML20235B720 ML20235B730 ML20235B734 ML20235B748 ML20235B754 ML20235B762 ML20235B764 ... further results
References
FOIA-87-111 NUDOCS 8709240396
Download: ML20235C245 (1)

Text

,

1

..c..

'l Distribution-

. Docket (2)v AEC PDR OGC DR Reading ACRS (18) i DRL Reading WNyer (2)

BWR-1 File APR 2 71970 CKBeck Docket Nos. 50-324 MMMann and 50-325.

FSchroeder RSBoyd RDeYoung DSkovholt Mr. P. S. Colby

'T. R. Wilson Senior Vice President E. G. Case, DRS Operating & Engineering Group RRMaccary, DRS

~

Carolina Power & Light Company -

PHowe

'336 Fayetteville Street BGrimes

-Raleigh, North Carolina 27602 DRS/DRL Br. Chiefs WButler

Dear Mr. Colby:

SMKari 4

With your letter of March 9,.1970, you provided a description of the proposed' inservice inspection program for the primary coolant system of the Brunswick Steam Electric Plant and a proposal for reduction of the design pressure from 62 psig to 53 peig for the drywell and torus

]

of the Brunswick containments.

We have completed our review of the proposed inservice inspection program and find it to be acceptable. We request that we be kept informed on j

your progress in developing a device for performing remote examinations i

of the reactor vessel and that you incorporate the proposed inservice

-inspection program in your proposed Technical Specifications for the

)

Brunswick Plant.

J Our review of the proposed reduction in containment design pressure is J

in progress. We expect to complete our evaluation of this item by about mid-June. However, until we complete our review and can conclude that the proposed change in containment design pressure is acceptable, we believe that 62 psig should be considered as the design value for the Brunswick Plant.

Sincerely, PDR8709p403 6 870921

1. rlt aal It'ed by i

poiw a.'merris FO MENZ87-111 pon Peter A. Morris, Director Division'of Reactor Licensing ec: George F. Trowbridge, Esq.

Shaw, Pittman, Potts, Trowbridge, & Madden 9g/

2 l./.'h,O f D 916 17th Street, N. W.

q

(

Washington, D. C.

20006

.O e

DRL/BWR-1 DRL/BWR-1 D /AD:

R DRL DRL DRS

},,

omer >

,5I"*d" h.k.k~r$Q{/70....

.? 5. f/70I.5'.'...

' !".'I....

--c >

our>4/24/70h.

4 71 y /70 -

-4/g70 -

4/2'7/70 4

I