ML20195E031

Application for Amends to Licenses DPR-53 & DPR-69,changing Tech Specs 5.6.1 & 5.6.2 to Increase New & Spent Fuel Racks from 4.1 to 5.0% U-235,per 10CFR50.92.Fee Paid

ML20195E031
Person / Time
Site:	Calvert Cliffs
Issue date:	06/09/1988
From:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20195E036	List: ML20195E031 ML20195E046
References
NUDOCS 8806230278
Download: ML20195E031 (4)

Text

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DA UTIMORE GAS AND ELECTRIC CHARLh8 CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN vict Patsrotat NucLEAn Entnov June 9, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 6 50-318 Criticality - New And Spent Fuel Storage Technical Specification Gentlemen:

The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License Nos. DPR 53 and DPR-69 for Calvert Cliffs Unit Nos. 1 & 2, respectively, with the submittal of the proposed changes to the Technical Specifications.

CHANGE (BG&E FCR 07-3004)

Change Technical Specification 5.6.1 and 5.6.2 for Unit 1 and Unit 2 to increase the enrichment limit of the new and spent fuel storage racks from the current 4.1 wt% U-235 to a maximum of 5.0 wt% U 235 as shown on the marked up copies attached to this transmittal. -

DETERMINATION OF SIGNIFICANT HA7ARDS This proposed change has been evaluated against the standards in 10 CFR 50.92 and has been determined to involve no significant hazards considerations, in that operation of this facility in accordance with the proposed amendment would not:

1. involve a significant increase in the probability or 3 consequences of an accident previously evaluated; or wQ

$E[O An increase to a maximum enrichment of 5.0 wt% U 235 does not involve g$ a significant increase in the probability or consequences of an ono 0)O accident previously evaluated. Because of the conse rvative techniques and assumptions used to calculate the maximum possible pd neutron multiplication factor, there is more than reasonable Ng assurance that there are no significant hazards involved in storing

@c fuel assemblies enriched as high as 5.0 wt% U-235 in the new and y spent fuel storage racks under both normal and postulated accident o ct conditions. As shown in the attached criticality analysis 8h # /9/dM f,4

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Documsnt Control Dssk Juna 9, 1988 l Page 2 3

(Attachment 1), storing unirradiated fuel at 5.0 wt% U-235 in the i most reactive configuration in the spent fuel racks results in a f maximum multiplication factor of 0.945, including all uncertainties, i Also, if a 4 inch axial gap in the poison material was imposed at the active fuel centerline in every poison sheet in the spent fuel racks, the increase in the multiplication factor would be 0.004 In all )

cases the values of the multiplication factor are below the required I limit of 0.95.

ii. create the possibility of a new or different type of I accident from any accident previously evaluated; or The proposed change to the enrichment limit does not result in any change in the configuration of the plant, equipment design, or equipment use nor does it require any change in the accident analysis methodology. Therefore, the proposed change will not create the possibility for an accident or malfunction of a different type from any previously evaluated.

iii. involve a significant reduction in a margin of safety.

The proposed changes sere evaluated for potential impact on the following systems:

New Fuel Storare Racks The maximum multiplication factor with 5.0 wt% U 235 fuel assemblies is 0.89. The previous analysis for 4,1 wt% U-235 fuel assemblies also resulted in a multiplication factor of 0.89. The reason that the maximum multiplication factor remains constant while the enrichment has been increased is due to the better modeling of the new fuel storage racks.

The previous analysis assumed a thick close fitting concrete reflector above the active region of the storage facility. The current analysis used the as-built design which has no concrete structure immediately above the facility.

Scent Fuel Storage Racks The most reactive configuration for unirradiated 5.0 wt% U 235 fuel assemblies results in a maximum multiplication factor of 0.945. When 4 inch axial gaps in the poison material are uniformly imposed at the active fuel center line in every cell, the increase in the multiplication factor is 0.004 In the previous analysis for 4.1 wt%

U 235 fuel assemblies a maximum multiplication factor of 0.936 resulted. The maximum change in multiplication factor from increasing enrichment to 5.0 wt% U 235 is .009. The multiplication factor of 0.945 for 5.0 wt% U 235 fuel is still below the required limit of 0,95.

The margin of safety has been reduced for the spent fuel storage racks but not significantly the maximum possible multiplication factor is still below the limit of 0.95.

Document Control Desk June 9, 1988 Page 3 ENVIRONMENTAL ASSESSMENT OF PROPOSED CllANGE The only potential for significant adverse environmental impact associated with the storage of more highly enriched fuel lies in the area of accidental criticality. However, in support of the Technical Specification change, the degree of suberiticality of all fuel storage racks at Calvert Cliffs has been reevaluated, with the conclusion being that criteria for the required degree of subcriticality continue to be met at the increased enrichment level.

Consequently, i'. is concluded that the requested increase in enrichment level:

a) does not create the potential for new types of accidents, and b) does not increase the cansequences of accidents beyond those previously reviewed and approved.

The alternative to increasing allowable enrichment to 5.0 wt% U 235 would be continued operation with 4.1 wt% U 235 fuel assemblies, which would increase the number of fuel assemblies required per reload. That, in turn, would increase the amount of fuel stored on site prior to shipment to the repository, increasing the additional on site capacity needed and making it needed sooner.

There would also be an increased number of shipments of spent fuel to the repository, and a larger volume of high level waste to be stored. These actions would have a greater environmental effect than the proposed change.

It is concluded that there is no adverse environmental iupact associated with the proposed increase in allowable enrichment to 5.0 wt% U-235.

SAFFTY COMMITTEE REVIEV These proposed changes to t'ae Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Off-Site j Safety Review Committees, and they have concluded that implementation of these

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changes vill not result in an undue risk to the health and safety of the public.

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Documsnt Control Desk Juns 9, 1988 Page 4 FEE DETERMINATION Pursuant to 10 CFR 170.21, we are including BG6E Check No. 1916543 in the amount of $150.00 to the NRC to cover the application fee for this request.

Very truly yours, hA STATE OF MARYIAND  :

TO WIT :

hn hoc haa n u

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i I hereby certify that on the h day of ,it e ,

i 9.[.[t., before me, the subscriber a Notary Public of the State of Maryland in and for

! $ T. M A A v 's , personally appeared Joseph A. Tiernan, being l duly sworn, and states that he is Vice President of the Baltimore Gas and -

! Electric Company, a corporation of the State of Maryland; that he provides the  ;

i foregoing response for the purposes thtrein set forth; th-t the statements made '

j are true and correct to the best of his knowledge, information, and belief; and I

that he was authorized to provide the response on behalf of said Corporation.

WITNESS my Hand and Notarial Seal: ,

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' 7Notarylublic ' ~~

l My Commission Expires: 7 " / "k8 h# ' '

f Date-JAT/RHB/cew Attachment l

cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC ,

S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC T. Magette, DNR l

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