ML20215K193

From kanterella
Jump to navigation Jump to search
Responds to 860925 Request for Addl Info in Support of Proposed Tech Spec Change for Spent Fuel Pool Storage Expansion.Uncertainty in Average Assembly Enrichment Is +0.13 W/O U-235 & Affects Delta K by Less than .01
ML20215K193
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 10/21/1986
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To: Rooney V
Office of Nuclear Reactor Regulation
References
FVY-86-98, NUDOCS 8610280022
Download: ML20215K193 (2)


Text

,

VERMONT YANKEE NUCLEAR POWER CORPORATION RD 5, Box 169, Ferry Road, Brattleboro, VT 05301 y

ENGINEERING OFFICE 1671 WORCESTER ROAD FR AMINGHAM. MASSACHUSETTS 01701 T EL E PHONE 617-872-8100 October 21, 1986 FVY 86-98 United States Nuclear Regulatory Commission Washington, DC 20555 i

Attention:

Office of Nuclear Reactor Regulation Mr. Vernon L. Rooney BWR Project Diractorate #2 Division of BWR Licensing

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter, VYNPC to USURC, FVY 86-34, dated April 25, 1986,

" Proposed Technical Specification Change for Spent and New Fuel Storage" (c) Letter, USNRC to VYNPC,~NVY 86-147, dated July 24, 1986 (d) Letter, VYNPC to USNRC, FVY 86-73, dated August 15, 1985 (e) Letter, VYNPC to USNRC, FVY 86-88, dated September 26, 1986

Subject:

Response to Request for Additional Information - Spent Fuel Pool Expansion

Dear Sir:

In response to your request of September 25, 1986, Vermont Yankee herein provides additional information in support of our proposed Technical Specification change for spent fuel pool storage [ Reference (b)).

In the referenced submittal of the Vermont Yankee high density spent fuel rack design, a K~ infinity acceptance criteria of 1.35 in the cold reactor lattice was specified. This was modelled in the criticality analysis as an 8 x 8 array of fuel rods with a uniform fuel enrichment of 3.25 w/o U235. This modelling clearly bounded the present and expected maximum assembly reactivity and produced a rack K-effective of.9267 with all mechanical and methodology uncertainties applied.

l With regard to the application of the maximum bundle K-infinity l

acceptance criteria, we have quantified the K-infinity acceptance criteria to.

]

account for the following:

1.

Nonuniform enrichment variations within the assembly lattice which

)

would impact the rack K-effective relative to the uniform enrichment

model, l

()0\\

8610280022 861021 g\\g

)

PDR ADOCK 05000271

\\

p PDR j

a United Stat'es Nuclear Regulatory Commission October 21, 1986 Attention:

Mr. Vernon L. Rooney Page 2 2.

Uncertainty in the ability to calculate maximum assembly cold K-infinity, and 3.

Uncertainty in average assembly enrichment.

Accordingly, the K-infinity of 1.35 will ba reduced to 1.31 based on the conservative application of the following bundle uncertainties:

1.

A.02 delta K bounds the reactivity associated with assembly enrichment variations.

I 2.

The ability to calculate cold K-infinity is within.01 delta K with greater than 95/95 percent confidence.

3.

The uncertainty in average assembly enrichment is 1 013 w/o U235 and affects the delta K by less than.01.

We trust that the above is responsive to your request; however, should you have any questions or require further information regarding this matter, please contact this office.

I Very truly yours,

)

VERMONT YANKEE NUCLEAR POWER CORPORATION

[I s

R. W. Capstick Licensing Engineer RWC/dml

... _. _ _ _ - _ _ _ _.., _ _ _