ML19312D410

From kanterella
Jump to navigation Jump to search
Submits Addl Response to NRC Requirements for Auxiliary Feedwater Sys.Results of Temp Analysis in Turbine Areas Conclude That Safety Equipment Not Degraded to Prevent Safe Shutdown
ML19312D410
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 03/18/1980
From: Naughton W
COMMONWEALTH EDISON CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8003240357
Download: ML19312D410 (2)


Text

_

Commonwealth Edison

. Ono First National Pfara. Chrcago, minois Xddiess R5piy~toTeosi' Office Boi767

- Chicago, Ilknois 60690 -

s March 18, 1980 Mr. Darrell G. Eisenhut, Acting Director Division of. Operating 1 Reactors U. S. Nuclear. Regulatory Commission Washington, DC 20555

Subject:

Zion Station Units 1 and 2 Additional Response to NRC Requirements for Auxiliary Feedwater Systems NRC Docket Nos. 50-295 and 50-304 Reference (a):

December 18, 1979 letter from D. L. Peoples to D. G. Eisenhut

Dear Mr. Eisenhut:

Per Reference (a), Commonwealth Edison Company committed to provide the NRC Staff with the results of an analysis to determine the ambient area temperatures for the turbine driven auxiliary feedwater pump during the two (2) hours subsequent to a complete loss of AC power and of an evaluation of the effect, if any, on equipment in the room necessary for safe shutdown.

Commonwealth Edison's response follows.

A temperature analysis was performed for the Zion Unit 1 and Unit 2 turbine areas. 'The results of this analysis have shown that, for the two hour time period following.a postulated l

complete loss of AC power, the highest temperatures reached in L

the Unit 1 and Unit 2 Auxiliary Feedwater Pump areas would be 116*F and 121* F, respectively.

This analysis also indicated l

that within minutes after.AC power is restored, the temperatures return to normal operating temperatures.

Commonwealth Edison has reviewed this analysis with respect to other. equipment in the room necessary for safe shutdown and has' concluded that these temperatures would not degrade any safety equipment such that a safe shutdown of the plant could not be accomplished.

Please. address any-questions that you might have concerning this matter'to-this office.

9 8003240 3 5 7.

n

+_o.

m.

= -.......

y y-

  • s,

__,l

~ O ~' '

%'.y '

Commonwealth Edison

Mr. ; Darrell. G. (Elienhut,. i Acting iD'1 rector-

. ~ March'18,'1980:

~n

.Page?2 o

One.(1)isigned-' original'and thirty-nine (39) c.opies of

~

this
: letter are provided-'for your use.

~Very truly-yours,

~

~

William-F. Naug on=

Nuclear: Licensing

.-Administrator

' Pressurized Water Reactors

-2422A I-1 l

i V;

r V

af~

.. i. - - --

~' ~

W

  • ' ?, '4 T.,

t

.'..-+- +

sen

.-e.

.e.

-...--...e u

.,