B14138, Forwards Corrected Table 3,correcting Typo in Spent Fuel Pool Criticality Analyses,Previously Submitted in 920416 Proposed License Amend

Forwards Corrected Table 3,correcting Typo in Spent Fuel Pool Criticality Analyses,Previously Submitted in 920416 Proposed License Amend

ML20113G877
Person / Time
Site:	Millstone
Issue date:	05/07/1992
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B14138, NUDOCS 9205130102
Download: ML20113G877 (4)

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l May 7, 1992 Docket No. 50-3M Dl4138 Re: 10CFR50.90 10CFR50.91 U.S. Nuclear Regulatory Commission L=

Attention. Document Control Desk Washington, DC 20555 Gentlemen:

Millstone & clear Power Station, Unit No. 2 Proposed Revision to Technical Specification Spent Fuel- Pool Reactivitv--Correction in a letter dated April 16, 1992 W Northeast Nuclear Energy Company proposed to amend .its 0perating License DPR-65 by incorporating changes that were identified in an attachment, into the technical specifications of Millstone Unit ; . 2. A second attachment to that submittal contained detailed, technical information which constituted spent fuel pool criticality analyses.

The purpose of this letter is to correct a typographical error in the previously submitted spent fuel pool criticality analyses attachment. The previously submitted Attachment 2, Table 3, contained a typographical error for the data column headings for spent fuel pool regions A and B. The l

designations ' A': and' 'B' were reversed. Attachment i to this letter provides a corrected Table 3. This revised Table 3 supersedes the same page submitted in the April 16, 1992, pro)osed license amendment. P1 nase remove the previous Table 3 and replace it wit 1 the corrected Table 3, attached.

! NNECO considers this a minnr typographical correction to the April 16, 1992, proposed licence amendment; therefore, the significant hazards consideration review documented in that submittal remains fully acceptable.

t We apologize fcr- any inconvenience that ray be caused by this typographical L error. Please contact my staff if you have any questions.

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(1) J. F. 0peka letter to U.S. Nuclear Regulatory Commission, " Millstone Nuclear Power Staticn, Unit No. 2, Proposed Revision to Technical 1 Specifications, Spent fuel Pool Reactivity," dated April 16, 1992, 10 0 n "!"

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U.S. Nuclear Rcgulatory Commission B14138/Page 2 May 7, 1992 In accordance with 10CFR50.91(b) we are hereby providing the State of Connecticut with a copy of this amendment correction.  :

Very truly yours, NORTHEAST NUCLEAR EllERGY COMPAfiY Q

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E F. Opekh U Executive Vice President cc: T . T . Mar +.in, Re9 13n 1 Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 STATE OF 0NNECTICUT)

) ss. Berlin COUNTY OF HARTFORD )

Then personally appeared before me, J. F. Opeka, who being duly sworn, did state that he is Executive Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the Q

statements contained in said information are true and correct to the best of his knowledge and belief. q .

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!/?b' Notary Plihiic 14CommP.4bnExpires Mych31,lM3 l

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Docket flo. 50-331 014138 1_

l Attachment 1 Hillstone Unit No. 2 Proposed Revision to Technical Specification Spent Fuel Pool Criticality Analysis--Correction Teble 3 May 1992

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4 U.S. Nuclear Regulatory Commission Table 3/B14102/Page 1 April 16, 1992 Table 3 Calculations Uncertain +ies and Reactivity Effects nf fianufteturing Tolerances Reactivity 6k Item ._

Reaion B Reaion A Uncertainty in Bias 0,0018 Kell 0 Statistics (95%/95%) 1 0.0019(4)

(or 1 0.0012(5})

B 10 Loading Tolerance 0.0022 i 0.0020 (i 0.003 g B-10/cm2)

Boraflex Width (i 1/16") 0.0009 1 0.0016

( Ent .l. ment Tolerance (i 0.09%) i L 3020 1 0.0020

[ U02 Density Tolerance ( 2%) i 0.0021 i 0.0021 Lattice Spacing (1 0.09") 1 0.0096 1 0.0113 SS Box 10 (i 0.05') 1 0.0042 i 0.0073 SS wall thickness ( 0.012") 1 0.0015 0.0053 Uncertainty in Depletion NA 0.0028 Calculations (5% in burnup)

Statistical Average 1 0.01i5 1 0.0154 (or 1 0.0114) (or 1 0.0153)

(4) For 1000 gcnerations of 500 nautrons each.

(5) For 2500 generations of 500 neutrons each.

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