ML20211K690

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Submits Correction to Attachment 1 to Response 6 to Util 860522 Responses to NRC Comments on Proposed Fuel Surveillance Program.Listed Sentence Partially Omitted in Original Version
ML20211K690
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/19/1986
From: Brey H
PUBLIC SERVICE CO. OF COLORADO
To: Berkow H
Office of Nuclear Reactor Regulation
References
P-86418, TAC-57625, NUDOCS 8606300220
Download: ML20211K690 (2)


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Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 June 19, 1986 Fort St. Vrain Unit No. 1 P-86418 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. H.N. Berkow Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Fort St. Vrain Fuel Surveillance Program

REFERENCE:

1) PSC Letter, Brey to Berkow, dated 5/22/86 (P-86383)

Dear Mr. Berkow:

A review of our letter, P-86383, PSC Responses to the NRC Comments on the Proposed Fuel Surveillance Program for the Fort St. Vrain Nuclear Station has revealed a typographical omission of a partial sentence in the final copy of Attachment 1, PSC Response 6. The corrected version should read as follows:

If the design basis primary coolant activity limits as established by Technical Specification LC0 4.2.8 are exceeded, PSC comits ,

commencing with the following refueling, to a sufficient number of PIES of sufficient scope to determine the cause of the excess activity levels.

This item should replace the last paragraph of Attachment 1 to P-85443. The item is worded nonquantitatively because the appropriate PIE program in response to high activity levels would be determined by the manner in which the LC0 limits are exceeded. For example, while high noble gas activity would be indicative of fuel particle coating failure, high circulating iodine activity could be caused by low plateout per pass in the primary circuit, a condition unrelated to fuel failure. High strontium activity could be caused by higher than expected diffusivity in the graphite webs or lower than expected sorptivity, again conditions unrelated to fuel failure.

e606300220 860619 A 000 (7

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P-86418 Pag 2 June 19,11986 Attachment 2, the revised Fuel Surveillance Program document, remains unchanged from the May 22, 1986 submittal.

If you have further questions or comments on this program, please ,

contact Mr. M.H. Holmes at (303) 480-6960. l l

Very truly yours, MH.L.Brey, Manager N

F Nuclear Licensing and Fuels HLB /EN:pa l

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