ML19323G053

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Submits Info Omitted from Util 800509 Response to NRC 800320 Request for Addl Info on Environ Qualification of Electrical Equipment.Individual Components Not Identified,Since Analysis Is Based on Design Max Actuation Time
ML19323G053
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 05/22/1980
From: Naughton W
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8005300310
Download: ML19323G053 (2)


Text

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h Commonwealth E:~ son 4

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/ oro First N;tiontf Plaza. Chicigo, tilinois

( O 7 Address Reply to: Post Office Box 767

(,/ Chicago. Illinois 60633 May 22, 1980 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Zion Station Units 1 and 2 Additional Information on Environmental Qualification of Electrical Equipment NRC Docket Nos. 50-295 and 50-304 References (a):

March 20, 1980 letter from A.

Schwencer to D. L.

Peopjes (b):

May 9, 1980 letter from D. L. Peoples to A.

Schwencer

Dear Mr. Denton:

In Reference (a), the NRC Staff requested Commonwealth Edison Company to provide the Staff with data necessary for the Staf f calculation of containment environmental parameters.

Reference (b) contained Commonwealth Edison Company's response to that request.

However, in reviewing the information provided in Reference (b), Commonwealth Edison omitted the following information.

The information presented as Attachment 1 to Reference (b) was based upon the most current LOCA analysis (for containment integrity) on the Zion docket.

That analysis was submitted in March, 1973 as Amendment 26 to the Zion FSAR.

With regard to Reference (a), the information presented in Attachment 1 of Reference (b) differs from that requested by the NRC Staff in the following manner:

Item I.D.2.

The Zion analysis is based upon a design maximum actuation time and, therefore, the individual components were not identified; Item I.D.3.

The Zion design does not incorporate a spray heat exchanger; Item I.E.1.

Similar to Item I.D.2.; and Item I.E.2.

A curve of heat removal capability is provided as a function of pressure since one does not exist as a function of temperature.

80053003@ ;P.

j Commonw:cith Edison I

Mr. Harold R. Denton, Director May 22, 1980~

Page 2 Please address any questions that you might have concerning this matter to this office.

One (1) signed original and thirty-nine (39) copies of this l

letter are provided for your use.

j Very truly yours, l

l I

William F. Naughto Nuclear Licensing Administrator Pressurized Water Reactors r

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