ML20214N323

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Approves Loading & Storage of Single Drum in 347-ft Elevation Storage Area.Approval of Storage in Array Anticipated Upon Completion of Independent Calculations
ML20214N323
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/10/1986
From: Travers W
Office of Nuclear Reactor Regulation
To: Standerfer F
GENERAL PUBLIC UTILITIES CORP.
References
CON-NRC-TMI-86-090, CON-NRC-TMI-86-90 NUDOCS 8609160242
Download: ML20214N323 (1)


Text

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DISTRIBUTION:

DN 50-320 Local PDR NRC PDR 1

DCS TMI Site r/f TMI HQ r/f September 10, 1986 WDTravers NRC/THI 86-090 MTMasnik LChandler Docket No. 50-320 ACRS I&E Hr. F. R. Standerfer M-Town Office Vice President / Director, THI-2 Service List o

GPU Uuclear Corporation P. O. Box 480 Middletown, PA 17057

Dear Hr. Standerfer:

4

Subject:

Storage of Upper End Fittings

References:

1.

GPUN letter, 410-86-L-0132, dated August 16, 1986, F. R.

Standerfer; to W. D. Travers, " Storage of Upper End Fittings" 7

2.

GPU4 letter, 4410-86-L-0160, dated September 9, 1986, F. R.

Standerfer to W. D. Travers, "End Fitting Storage" x

3.

GPUN Report on Foreign Materials Allowed in the THI-2 RCS, dated Septecher 30, 1985 7

4.

NRC memorandum C. H. Berlinger to R. A. Weller, " Review of THI-2 ' Foreign Materials' Criticality Report", dated December 2, 1985 The Nuclear Regulatory Commission (HRC) staff has reviewed your August 16, 1986 proposal for storage of upper end fittings and the additional information provided in your September 9,1986 letter (references 1 and 2). The nethodology and assumptions used in your calculational models are o

conservative. The results indicate that there is more than adequate shutdown margin for a single drum. The calculation case for a single drum is strongly supported by your Foreign Materials Report (reference 3) which has been c

l previously reviewed by the NRC staff (reference 1).

He therefore approve loading and storage of a single drum in the 347 ft, elevation storage area. An additional drum may be loaded and stored on the shielded work platform or in the refueling canal. The staff is currently performing independent confirmatory criticality calculations. When these independent calculations are complete we anticipate approval of storage in an array. This approval is contingent upon submittal of related procedures subject to Technical Specification 6.8.2 and implementation of cuergency procedures in accordance with 10 CFR 70.24 a (3).

Sincerel ORlGiNAL #g m yrigiam D. Trown

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