ML20077E624

Forwards Tech Spec Change Request 201,suppl 1 Re Spent Fuel Pool Rerack

ML20077E624
Person / Time
Site:	Three Mile Island
Issue date:	06/06/1991
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077E625	List: ML20077E624 ML20077E781 ML20077E793
References
C311-91-2043, NUDOCS 9106110120
Download: ML20077E624 (2)

Text

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l GPU Nuclear Corporation b Nuclear nom =8o Middletown, Ponnsylvania 17.,57 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

"? -948-8005 June 6, 1991 0311-91-2043 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 201, Supplement 1 Spent Fuel Pool Rerack - Revised Licensing Report in accordance with 10 CFR 50.4(b)(1), enclosed are one (1) original, and four (4) copies of Technical Specification Change Request No. 201, Supplement 1.

A'so enclosed is one signed copy of the Certificate of Service for this request -

v,ich reflects service to the chief executives of the township and county in which the facility is located, as well as the Bureau of Radiation Protection.

This supplement provides revised pages to the Licensing Report for Pool A Reracking, Three Mile Island Unit 1, Holtec Report H1-89047, previously submitted via GPUN letter C311-90-2120, dated November 14, 1990. The enclosed revised pages represent Revision 7 to HI-89407 and should be inserted into the previously submitted document. Revision 7 incorporates minor dimensional changes in the rack storage cell height, rack support leg height, and cell pitch. Section 4.0, Criticality Safety Analyses, is updated in Revision 7 to l H1-89407 as a result of these rack dimensional changes and should be replaced I with the enclosed Section 4.0. The acceptance criteria and conclusions for the l criticality analysis remain unchanged.

Revision 7 to HI-89407 also documents adminhtrative changes to pages 7-3, 4-3, 1 1-2, 2-7 and 10-3 which have comprised internal GPUN Revisions 4, 5 and 6, to H1-89407 prior to this submittal. No additional revisions are anticipated at this time.

• 106.110120 910606 PDR ADOCK 0S000209 P PDR 8/

,', c y C .} GPU Nuclear Corporabon 's a subsidiary of Genemi Putahc Utat;es Ccnaoranon /[/

"Occument Control Desk C311-91-2043 Page 2 The revisions to the Licensing Report for Pool A Reracking, TMl-1, H1-89407 have no effect on the safety evaluation justifying the proposed amendment or on the corresponding no significant hazards conclusions previously submitted.

Pursuant to 10 CFR 50.91(a) of the regulations we have provided a copy of this letter and the enclosed revision to Licensing Report H1-89407 to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania.

Sincerely,

!'d%

T. G. Brou.iton

\ lice President and Director, TM1-1 DJD/amk

Enclosure:

Revision 7 Replacement Pages for " Licensing Report for Pool A Reracking, 1MI-1" Holtec Report H1-89407 cc: TMl-1 Senior Project Manager Administrator, Region 1 TMl Senior Resident inspector Director, Project Directorate, IV

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