ML17254B023

Amend 65 to License DPR-18,increasing Spent Fuel Pool Storage Capacity

ML17254B023
Person / Time
Site:	Ginna
Issue date:	11/14/1984
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML17254B024	List: ML17254B023 ML17254B025 ML17254B026
References
NUDOCS 8411200353
Download: ML17254B023 (9)

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UNITEDSTATES NUCLEAR REGULATORY COMMISStON WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.

E.

GINNA NUCLEAR POl(ER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 65 License No.

DPR-18 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated April 2, 1984 and supplemented by letter dated June 12, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the'ommon defense and security "or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

84ii200353 841ii4 PDR 'ADOCK'5000244 P

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2.

Accordingly, the license is amended by changes to the Technical Specifications.

as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No.

DPR-18 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

Attachment:

Changes to the Technical Specif ications FOR THE NUCLEAR REGULATORY CON'~SSION John

. Zwol inski, Chief Opera ing Reactors Branch b5 Division of Licensing Date of Issuance:

November 14, 1984

ATTACHMENT TO LICENSE AMENDMENT NO. 65 PROYISIONAL OPERATING LICENSE NO. DPR-18 DOCKET NO.60-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages contain the captioned amendment number and marginal lines which indicate the area of changes.

REHOVE 5.4-1 INSERT 5.4-1 5.4-2 5.4-3 5,4 4 5.4-5

5.4.

t Fuel Storage SDecification.

5.4.1 5.4.2 5.4.3 The new and spent fuel pit structures are designed to withstand the anticipated earthquake loadings as Class I structures.

The spent fuel pit has a stainless steel liner to. ensure against loss of water.

,s'f The new and spent fuel storage racks are designed so that

't is impossible to insert fuel assemblies in other than the prescribed locations.

The spent fuel storage racks are divided into two regions's depicted on Figure 5.4-1.

The fuel is stored vertically in an array with sufficient center to center distance between assemblies to.assure Keff <

0. 95 for (1) unirradiated fuel assemblies delivered prior to January 1,

1984 (Region 1-15) containing no more than 39.0 gms U-235 per axial cm, and (2) unirradiated fuel assemblies delivered after January 1,

1984 containing no more than 41.9 gms U.-235 per axial cm.

Both cases assume unborated water used in the pool.

ln Region 2 of the spent fuel storage

racks, fuel is stored in a close packed array utilizing fixed neutron poisons in each of the stored locations.

For discharged fuel assemblies to be stored in Region 2, (1) 60 days must have elapsed since the core reached not shutdown prior to discharge and (2) the combination of assembly I

average burnup and initial U-235 enrichment must be such that the point 'dentified by these two parameters on t

Figure 5.4-2 is above the 1'e applicable to the part'ular uel assembly d=-sign, there=ore assur'ng that Kezz

< 0.95.

n Aille n GIAe"t pro p 1, 6Q, 65

5.4 '

The spent fuel storage pit*'s filled with borated water at a concentration io match ihat used in the reactor cavity and refueling canal during refuel'ng operations whenever there is fuel 'n the pit.

Bas~ s The cente to center spacing of Region. 1 insures.that Keff <.'/

0.95 for the enrichment limitations specified in 5.4.2~,

and for

.a postulated missile impact the resulting dose at the EAB would j

be wiihin the guidelines of 10CFR100~.

p Zn Region 2, Keff < 0. 95 is insured by the addition of fixed neutron poison (boraflex) in each of the Region 2 siorage locations, and a minimum burnup reauirement as a function o~ initial en ichmeni or each fuel assembly design.

The 60 day cooling time reauirement insures that for a postulated missile impact the resulting dose at the HAS would be within the guidelines of'0CFR100.

The two curves of Figure 5.4-2 divide the fuel assembly designs into two groups.

The first group is all fuel delivered p ior to January 1,

1984.

This incorporates a13. exxon and westinghouse

=-EPPES designs used at Ginna~

The second curve 's for ~he Westinghouse Optimized Fuel Assembly design delivered to Ginna beginning in February 19843 The assembly average burnup is calculatea using ENCORE generated powe sharing data and ihe actual plant operating h'to v.

The calculaiea assembly average burnup should be reducea by 10% to account for uncertainties.

An uncertainty of 4% is I'ssocia-ed with the measurement o

power sharing.

The aaditional 6% provides aadiiional margin io bound the burnup unce=iainty 5.4-2 Amendment Ho.

65

associated with the time between measurements and updates of core burnup.

The curves of Figure 5.4-2 incorporate the uncertainties of the calculation of assembly reactivity.~

The calculations of fuel as'sembly burnup for comparison to the curves of Figure 5.4-2 to determine the acceptability for storage in Region 2 shall be independently checked.

The records of these calculations shall be kept for as long as fuel assemblies

,remain in the pool.

References 2.

3.

4 Letter, J.E. Maier to H.R. Denton, January 18, 1984.

Letter J.E. Maier to H.R. Denton, January 18, 1984.

Criticality Analysis of Region 2 of the Ginna MDR Spent Fuel Storage Rack, Pickard, Lowe and Garrick, Inc.

March 8, 1984.

Letter, T.R. Robbins,

Pickard, Lowe and Garrick, Inc. to J.D.

Cook, RGS=

M. rch 15, 1984..

Amendment No.

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