ML20090D196

Forwards NUREG-0909 Re Ginna 820125 Steam Generator Tube Rupture,Engineering Evaluation & LER Re Salem 820114 Load Transient & Engineering Evaluation & LER Re Brunswick 820116 Loss of RHR Svc Water.W/O Encl

ML20090D196
Person / Time
Site:	Salem, Brunswick, Ginna, 05000000
Issue date:	07/10/1984
From:	Zukor D NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Hopps J CHARLES STARK DRAPER LABORATORY
Shared Package
ML082380335	List: ML20090B377 ML20090B412 ML20090B428 ML20090B436 ML20090B439 ML20090B458 ML20090B472 ML20090B481 ML20090B485 ML20090B490 ML20090B493 ML20090B501 ML20090B505 ML20090B507 ML20090B511 ML20090B514 ML20090B519 ML20090B525 ML20090B528 ML20090B531 ML20090B534 ML20090B545 ML20090B659 ML20090B672 ML20090B676 ML20090D196 ML20090E676 ML20090E683 ML20090E686 ML20090G527 ML20090G531 ML20090G578 ML20090H603 ML20090H617 ML20090J352 ML20090J369 ML20090J521 ML20090J804 ML20090J811 ML20090J855 ML20090J859 ML20090J918 ML20090K082 ML20091B798
References
FOIA-91-106 NUDOCS 8407180021
Download: ML20090D196 (1)

Text

- - - - - _ _ - -..

UNITED ST AYES go arco

/

jo, NUCLEAR REGULATORY COMMISSION 2

4.

g W ASalNGToN D. C. 20555 g

~~ t

• • 4 u

%,.v f'

JUL 101984

.s MEMORANDUM FOR: Dr. John H. Hopps Manager, Energy Program Development The Charles Stark Draper Laboratories 3*

FR(ti:

Dorothy J. Zukor Reactor Systemt 2 Reactor Operations Analysis Branch

SUBJECT:

DATA ON NUCLEAR PLANT TRANSIENTS

[

In response to our recent telephone discussion, I am sending you another copy of the infomation which was previously ser.t to you.

The reports for the following events are included:

1.

Ginna Steam Generator Tube Rupture on January 25, 1982.

a NUREG 0909

'D 2.

Salsa Unit 2 Load Transient on January 14, 1982.

o Engineering Evaluation by N. Trehan o Supplemental Reportable Occurrence on LER 82-04/03X-1.

3.

Brunswich Unit 2 Loss of Residual Heat Removal Service Water on January 16, 1982.

o Engineering Evaluation sy T. Wolf, o LER 82-005/0T-1 1 hope you find the enclosed infomation useful.

If you should need any further assistance, please feel free to contact me at (301) 492-4431.

D 4

Dorbthy J. Zuk Reactor Systems 2 Reactor Operations tnalysis Branch

Enclosure:

1.

NUREG 0909 - Ginna SGTR 2.

Engineering Evaluation "Salen Unit 2 Load Transient" with LER 82,04 /03X-1-_,.,_

i A ( Engineering Evaluatiori'^ w I

l i

"a ynswich t,Init 2 Loss N

//

L./['//

/

r of xdA Service Witer N

y kO~lf f()$ f J

?

~