ML20040F595

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Requests Addl Clarification of NRC Guidelines as Stated in NUREG-0800 & NRC Re Design of Low Level Waste Storage at Reactor Sites.Questions Include Recommended Site Boundary Dose Rate & Quarterly Container Insp Program
ML20040F595
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 01/29/1982
From: Lentine F
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0800, RTR-NUREG-800 NUDOCS 8202090391
Download: ML20040F595 (2)


Text

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Mr. Harold R. Denton, Director

'IlPg Of fice of Nuclear Reactor Regulation kB 79 O

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Subject:

Zion Station Units 1 and 2 N

Storage of Low Level Wastes At Power Reactor Sites NRC Docket Nos. 50-295 and 304 References (a):

Standard Review Plan - NUREG 0800, Rev. 2, dated July 2, 1981.

(b):

Letter and Guidance Paper from W. J. Dirks to All Licensees, dated November 10, 1981.

Dear Mr. Denton:

The referenced documents list generally acceptable guidelines for the design of low level waste storage facilities at power reactor sites.

This is to request additional clarification and elaboration o f the NRC's position.

Specifically, we have questions regarding two items that could have significant impact upon. facility design:

1.

The recommended site boundary dose rate is 1 mrem /yr.

Is this considered an absolute maximum?

If not, what technical support would be required to raise the acceptable dose rate?

Is there a threshold value above which installation of the f acility would be considered an unreviewed safety question?

2.

As a minimum, a quarterly container inspection program is recommended.

What percentage of the containers must be inspected at each inspection interval?

Is the inspection interval dependent upon container stack height (i.e., load on the base container)?

Is there a limit on a stack height?

Commonwealth Edison is currently reviewing proposed designs for such facilities.

Resolution of these items is needed if our review is to result in a f acility design that meets our storage 00

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P202090391 820129 iL gg 0 POR ADOCK 05000295 X

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r H. R. Denton Janua ry 29, 1982 needs and adequately addresses regulatory concerns.

Should you have other information that may provide additional clarification in these areas, please include it in your response.

Please address questions regarding this matter to this o f fice.

Very truly yours, F.

G.

Lentine Nuclear Licensing Administrator 1m 3355N L