ML17254A419

Responds to Questions Raised at 850604 Meeting Re Criticality Safety Analysis.Calculations & Graphs Prepared by Pickard,Lowe & Garrick,Inc Encl

ML17254A419
Person / Time
Site:	Ginna
Issue date:	06/26/1985
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
NUDOCS 8507030236
Download: ML17254A419 (12)

Text

REGUlATORY I ORMATION DISTRIBUTION SYS (RIDS) 1 ACCESSION NBR;8507030236 DOC CHOATE'5/06/26 NOTARIZED; NO DOCKET FACIL:50 244'obert Emmet Ginna Nuclear Planti Uni,t li Rochester G

05000244 AUTH'AME>>

AUTHOR AFFILIATION KOBER'r R i H ~

Rochester Gas 8 Electric Corp, RECIPtNAHE>>

RECIPIENT AFFILIATION ZI>>IOLINSK43l,A~

Operating Reactors Branch 5

SUBJECT:

Responds" to questions raised at>> 850604 meeting re" critical-ity >>safety analysis.Calclulations 8 graphs prepar>>ed by Pickar diLoie>>'8 Gar r ickiInc encl- ~

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555'M ROCHESTER, N.Y. 14649-0001 ROGER W. KOSER VICE Pt)ESIDENT ELECTRIC St STEAM PI)ODUCTION TELEPHONE

• RCA CODE TIS 546-2700 June 26 I l985 Director of Nuclear Reactor Regulation Attention:

Mr. John A. Zwolinskii Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Nashingtoni D.C.

20555

Subject:

Response

to NRC Staff Questions R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Zwolinski:

On February 27I 1985I Rochester Gas and Electric Corporation submitted an Application for Amendment to Operating License to allow the storage of consolidated fuel at Ginna.

At our meeting of June 4I 1985, the NRC Staff raised several questions concerning the criticality safety analysis.

Attached>

in response>

are some additional calculations performed by Pickardi Lowe and Garrick.

V r truly yours>

Roger N. Kober 850708023b 85062024 PDR

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Question:

Please discuss the effects on criticality of the storage of fewer than 179 rods per half canister such as in a failed fuel configuration.

Response

The discussion below summarizes the results of calculations performed to determine at the optimum pitch the k for fuel rod storage in a failed fuel configuration.

In addition< results are presented to show the effect of burnup on the k~ of both an infinite lattice of fuel rods and the fuel storage rack containing these fuel rods as a function of the number of fuel rods present in a,,consolidated fuel rod storage canister '(resul,ts fo'r zero burnup were" previously presented in Figure 7 of the criticality analysis in.

the February"27<'985 submittal).

The calculations were performed for an Exxon fuel assembly design with an initial enrichment of 3.13 w/o and for a burnup of 21 MWD/KGU.

This fuel type was selected because all of the burnup dependent input data required for the current calculations were readily available from the results of previous calculations.

However<

good estimates of the corresponding results for the fuel stored at West Valley were obtained by comparing the k~ burnup dependence of the Exxon fuel assembly with that of a W Core 1 fuel assembly with an initial enrichment of 2.78 w/o.

The stainless steel tubes which are intended to contain failed fuel rods for storage in consolidated fuel canisters have a 0.75 inch outer diameter with a wall thickness of 0.035 inch.

Based on these tube dimensions and the dimensions of the consolidated fuel storage canister>

geometric considerations limit the number of tubes that can be accommodated in one-half of a canister to 55 when the rods are arranged on a triangular or hexagonal pitch. If the tubes could be constrained to a square pitch> the limiting number of tubes would be reduced to 50 per half canister.

Using these two cases as a lower limit on the water-to-nonwater volume ratio, this ratio was then increased by increasing the pitch on a square lattice<

and the resulting k

is shown in Figure 1 for an infinite lattice of stainless steel tubes containing Exxon type fuel rods at 3.13 w/o initial and with a burnup of 21 MWD/KGU.

Due to the presence of the stainless steel tubes<

the maximum k~ of about 0.83 is obtained for the dryest lattices>

and increasing the water volume (by increasing the pitch) results in a uniform reduction in k

due to increased neutron absorption in the stainless steel tubes and/or the water.

Based on the low k~'s obtained for an infinite lattice of these fuel rods<

there is no need to evaluate the reduction in k~ which

~

~

ih k

would occur if these rods were placed in canisters and stored in the Region 2 racks.

A similar set of calculations were performed using the same fuel rods but without the presence of the stainless steel tubes.

In this case the maximum number of fuel rods per half canister is 179.

The results are shown in Figure 2 for both the k of an infinite lattice and the h

of the storage rack containing the canisters.

In this case>

the maximum lattice h is about 1.16> but the maximum rack k~ is only about 0.87.

Figure 3 shows a comparison of k vs. burnup behavior for an Exxon fuel assembly at 3.13 w/o and a 2.78 w/o fuel assembly stored at West Valley.

The k ~ of the two types of fuel assemblies is the same for a burnup of 21 MWD/KGU; so the data shown in Figures 1 and 2 should also be applicable to West Valley fuel assemblies with a burnup of 21 MWD/KGU.

However>

the minimum burnup of the fuel assemblies stored at West Valley is about 15.5 MWD/KGU for an initial enrichment of 2.795 w/o.

The k~

of the 2.78 w/o fuel assemblies at a burnup of 15.0 MWD/KGU was selected as being representative of the minimum burnup maximum k fuel stored at West Valley~

and based on the data shown in Figure 3< the difference in k~ for this fuel at burnups of 21 and 15 MWD/KGU is

.0535 6k~.

This reactivity difference has been applied to the data generated for the Exxon fuel and the results are shown in Figures 4 and 5.

These figures show that for the minimum burnup maximum h fuel stored at West Valley< the maximum infinite lattice h for the fuel rods in stainless steel tubes is about 0.88~

and for.the fuel rods stored in canisters in the storage rack>

the maximum k~ is about 0.93.

However<

a situation in which between 75 and 100 fuel rods per half canister are uniformly spaced in more than one storage rack position would have to be considered a low probability accident situation.

In that case< credit should be allowed for the presence of 2000 ppm boron which would further reduce the k ~ of the rack by more than

.20 hk In conclusion there appears to be no criticality safety concerns for storage of failed or nonfailed fuel.

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