ML20235C369

Forwards Listed Items,Including Util Transmitting Table for Insertion in Rept on Proposed Containment Design Pressure for Brunswick Steam Electric Plant & AEC 700427 Response to Util Request for Design Change in Containment

ML20235C369
Person / Time
Site:	Brunswick, 05000000
Issue date:	05/04/1970
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Hendrie J Advisory Committee on Reactor Safeguards
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 8709240430
Download: ML20235C369 (1)

Text

__

i Distribution:

Docket (2) #

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jpj BWR-1 File R. S. Boyd Docket Nos. 50-324

w. Butler and 50 325 S

M* K"#1 Dr. Joseph M. Hendrie l

Chairman, Advisory Committee i

on Reactor Safeguards U. S. Atomic Energy Commission Washington, D. C.

20545 l

Dear Dr. Hendrie:

Eighteen copies 'of the following are transmitted l

for the information of the Committee:

CAROLINA POWER & LIGHT COMPANY (Brunswick Steam Electric Plant Units 1 & 2) l l

1.

CP&L letter, dated March 25, 1970, transmitting Table for I

insertion in Report on " Proposed containment Des 1En Pressure for Brunswick Steam Electric Flent." (Report i

previously transmitted to Committee on March 18, 1970.)

l 2.

DRL letter, dated April 27, 1970, in response to CP&L's request for design change in containment pressure and proposed inservice inspection program.

I Sincerely, Peter A. Morris, Director Division of Reactor Licensing

Enclosures:

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