LD-93-145, Forwards Evaluation of Sys 80+ Std Design for SG Tube Rupture Events. Rept Should Be Provided to Reactor Sys Branch

Forwards Evaluation of Sys 80+ Std Design for SG Tube Rupture Events. Rept Should Be Provided to Reactor Sys Branch

ML20057F142
Person / Time
Site:	05200002
Issue date:	10/06/1993
From:	Brinkman C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ASEA BROWN BOVERI, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20057F143	List: LD-93-145, Forwards Evaluation of Sys 80+ Std Design for SG Tube Rupture Events. Rept Should Be Provided to Reactor Sys Branch
References
LD-93-145, NUDOCS 9310140185
Download: ML20057F142 (1)

Text

.

ABB ASEA BROWN BOVERI 0ctober 6, 1993 LD-93-145 Docket No.52-002 L

i Attn: Document Control Desk t

U.S. Nuclear Regulatory Commission L

Washington, D.C.

20555

Subject:

System 80+TM Information for Issue Closure l

Dear Sirs:

Enclosed with this letter is the report " Evaluation of the System 80+

. Standard Design for Steam Generator Tube Rupture Events.

This report should be provided to the Reactor Systems Branch.

-If you have any questions, please call me or Mr. Stan Ritterbusch at (203) 285-5206.

Very truly yours, COMBUSTION ENGINEERING, INC.

tw a

C. B. Brinkman Acting Director Nuclear Systems Licensing CBB/ser

Enclosure:

As Stated cc:

J. Trotter EPRI NRC))

T. Wambach P. Lang (D0 )

L 12-119 go@

l' l

ABB Combustion Engineering Nuclear Power comt.use Eno nmn sac wo Nsme w %d 1eennre eau ces 19n Pont Ottace Bon SN fax Co.h Pe5 9512 9310140185 931006ADOCK 05200002 @gt

- f wee commemas so Teo 99m couacN WSM PDR

-A PM d

..