ML20002C984

Forwards Addl Info Re Accident Analyses of EEI-U Dioxide- Pu Dioxide Fuel Contained in Tech Specs Proposed Change 19 Per Request.Proposed Change 19 Will Permit Irradiation of Pu-U Mixed Oxide Fuel

ML20002C984
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/13/1970
From:	Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Morris P, Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101150649
Download: ML20002C984 (5)

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-'s General Offices: 212 West Michigan Avenue Jackson, Michigan 40201. Area Code 517 788-0550 February 13, 1970 Dr. P. A. Ucrris, Director Re: Ibeket 50-155, DPR-6 ZEK Division of Reactor Licensing Additional Information United States Atomic Energy for Proposed Tech Spec Commission Change No. 19 "ashington, DC 205h5

Dear Dr. Morris:

Attention: Mr. D. J. Skovolt Transmitted herewith are h0 copies of a second set of ad-ditional information requested by your staff relative to the accident analyses of the "EEI-UO -PuO " fuel contained in our recently sub-2 2

mitted Technical Specifications - Proposed Change No. 19 (12-22-69).

Proposed change (No.19) will enable Consumers Power Cc p ny to insert into the reactor at Big Rock Point a fuel design des gnated as "EEI-UO -Pu0 " which will permit the irradiation of 2

2 plutonium-uranium mixed oxide fuel. The purpose of this irradiation is to provide needed data on the operating characteristics of mixed oxide fuel with a statistically significant number of fuel rods.

It is our intention to insert no more than three "EEI-UO -Pu0 " fuel bundles into the Big Ibck Point Reactor during our 2

2 next refueling outage which is currently scheduled to begin February 16, 1970. We would, therefore, be most appreciative of an expeditious handling of this Request for a Technical Specifi-cations Change so that we might receive approval as soon as possible.

Yours very truly, GJW/dmb Gerald J. Walke

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ADDITIONAL INFORMATION

..:. Cy, Changs No. 19 Consumers Power Company Request for Change to the Technical Specifications

)-/ 3 Jg License No. DPR-6 A c.3,;

EFFECT-0F BETA CHANGES ON REACTIVITY ACCIDENT

~7 Accidents involving transients have typically been evaluated with an effective delayed neutron fraction which is not spatially dependent. The introduction of plutonium to the core has the effect of reducing the de-layed neutron fraction and creating a potential for local regions with lower than average delayed neutron fraction. We have evaluated these effects through the use of an " effective delayed neutron fraction".

The average delayed neutron fraction is given by 01 "_i 1

i i "i where P is fission power in region i is neutron / fission in region i v

and S is delayed fraction in region 1.

S Implies an effective average over all the isotopes contributing (particu-g larly.U-235, Pu-239, and U-238).

An " effective" delayed neutron fraction is obtained by weighting the spatially dependent importance of neutrons contributing to the multiplication procesa (adjoint flux). We have approximated this weighting distribution by the power distribution and obtain:

O 1 1 i "1 0

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eff

{ P{ vg The following results are obtained for the power distributions associated with the Big Rock Point rod drop accident, for the case (Case A) of a single i

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plutonium bundle at the power peak next to the dropped rod and the other

' two bundles at average locations and for the case (Case B) with all three Pu bundles at the rod drop location.

Case A Case B Average 8,8

.589 %

.578 %

Effective 8, 8

.579 %

.550 %

gg These values are to be coupared to values of.605% for the exposed ufanium fuel and.385% for the fresh plutonium fuel assemblies. The value for fresh uraninm assemblies is.724%.

The reduced S,gg has the effect of reducing the period for a given Ak inserted into the reactor. The relative enthalpy rise in a rod drop accident as a function of S,ff is shown in the attached figure. From this it can be seen that the effect of changing 8,ff from uranium at.605% to three clustered Pu assemblies at.55% is about 1.3%.

If one made the artificial assumption that 8 were that of the plutonium assemblies (.385%) the enthalpy increase would be about 5%.

These results were calculated for same conditions used to calculate the accident in previous analyses.

The relatively small dependence on 8 can be understood by noting that in super-prompt critical excursion the excursion is turned around when the energy in the fuel is sufficient to compensate for h

-S.

This is e ess relatively slowly varying with S when k is large.

In addition, in ramp excess type accidents, the shorter period associated with smaller 8 turns the accident around with less reactivity inserted and therefore less energy inserted. This is a relatively small effect but is in the direction to diminish the effect of reductions in S.

February 13, 1970

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