ML19273A963

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Internal Plant Design Change Procedure for the Purpose of Venting High Density Spent Fuel Racks Has Been Processed & Approved.Change Does Not Constitute an Unreviewed Safety Question
ML19273A963
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/12/1978
From: Counsil W
NORTHEAST UTILITIES
To: Ziemann D
Office of Nuclear Reactor Regulation
References
NUDOCS 7812190083
Download: ML19273A963 (2)


Text

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December 12, 1978 Docket No. 50-245 Director of Nuclear Reactor Regulation p, T?P Attn:

Mr. D. L. Zie:: nun, Chief D

U'M E '

Operating Reactors Branch d2 u

U. S. Nuclear Regulatory Cocaission Washington, D. C.

20555

References:

(1)

W. G. Counsil letter to D. L. Ziemann dated November 3,1978.

(2)

W. G. Counsil letter to D. L. Ziennn dated October 13, 1978.

Gentlemen:

Millstone Nuclear Powcr Station, Unit No.1 High Density Spent Fuel Racks In Reference (1), Northeast Nuclear Energy Company (NNECO) forwarded to the NRC Staff the Carborundum Company Test Program Report No. CBO-N-78-299 which described the B4C neutron absorbing material requalification program tests and results.

In addition, a non-proprietary version of the report and answers to specific NRC Staf f questions were attached to Reference (1). Also in Reference (1), NNECO stated the conclusion that the results of the first three tests as contained in the Test Program Report verified the original determination that the B4C material vill maintain its structural integrity when exposed to a spent fuel pool environment. Accordingly, NNECO stated that an internal " plant design change procedure" for the purpose of venting the spent fuel racks, would be processed based on the Test Program Report and reviewed in accordance with 10CFR50.59.

Further, if the design change was approved and found not to con-stitute an unreviewed saf ety question, NNECO stated that the racks would be used in the ver,ted configuration to store spent fuel no earlier than December 1, 1978.

Since that et=e, the above stated " plant design change procedure" has been pro-cessed, appfloved, and found not to constitute an unreviewed safety question, and NNECO has e.ndeavored to keep the NRC Sta f f inforrad as to the progress and re-sults of that review.

In Refera/

(2), NNECO stated that the new spent fuel racks would not be used in nce any coriiguration until such time as approval to do so was received f rom the NRC S ta f f.

In a phone conversation on December 1,1978, the NRC Staf f informed NFECO h*0 781219eo 3 $

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that based on Reference (1) and a meeting between the NRC Staf f, NNECO, other utilities, consultants, and vendors, on October 26, 1978, their concerns had been addressed and they were not opposed to NNECO using the new racks in a vented configuration. This letter documents the verbal understanding that we have your concurrence to use the new racks as soon as necessary.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPRiY

/

I'7/.fl.lic' W. G. Counsil Vice President