ML20206A293

Forwards Fuel Drop Accident Load Reassessment Analysis Rept for Maine Yankee Spent Fuel Storage Racks, Showing Crushed Distance of 1.48 Inches for Rack Corner Impact & 2.03 Inches for Top Edge Impact.Ie Bulletin 80-11 Should Be Closed

ML20206A293
Person / Time
Site:	Maine Yankee
Issue date:	03/31/1987
From:	Whittier G Maine Yankee
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20206A297	List: ML20206A293 ML20206A308
References
8585L-GDW, GDW-87-81, IEB-80-11, MN-87-42, NUDOCS 8704070477
Download: ML20206A293 (2)

Text

-.

l MAIRE HARHEE ATOMICPOWERCOMPARUe avaugr,Yl,,Te%,

(207) 623-3521 e

March 31, 1987 MN-87-42 GDH-87-81 l

United States Nuclear Regulatory Commission Attention: Document Control Desk i Washington, D. C. 20555 i

References:

(a) License No. DPR-36 (Docket No. 50-309)

Subject:

Spent Fuel Pool Masonry Hall Gentlemen:

On December 18 and 19, 1986, NRC personnel and their consultant reviewed Maine Yankee's spent fuel pool masonry wall failure consequence analysis. The only item of concern identified from this review was that the rack buckling loads and deformation due to a fuel bundle drop (used to bound the masonry wall impact) may not have represented a bounding calculation. ,

1 In order to address this concern, par Systems Corporation, the fuel rack j vendor, reanalyzed the fuel bundle drop to show that the wall segment impact '

energy does not cause more than the maximum allowable deformation (approximately 11 inches to the top of the spent fuel).

The results of this reassessment are presented in the attached report, entitled " Fuel Drop Accident Load Reassessment Analysis Report for the Maine Yankee Spent Fuel Storage Racks". The reanalysis showed a crushing distance of 1.48 inches for a rack corner impact and 0.97 inches for a top edge impact. The edge impact crushing distance increases to 2.03 inches if lateral stiffening effects of adjacent canisters are conservatively ignored.

These calculated deformations are greater than those originally reported (0.928 inches), however, they remain well below the 11 inch distance to the i top of the spent fuel.

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B704070477 670331 PDR 1

G ADOCK 05000309 i PDR g

8585L-GDH l\

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United States Nuclear Regulatory Commission Page Two Attn: Document Control Desk MN-87-42 1

The reanalysis confirms the acceptability of the deformations caused by a spent fuel assembly drop. He trust this information will allow closure of the remaining issue from IE Bulletin 80-11. ,

Please contact us if you have any questions.

Very truly yours, MAINE YANKEE ATOMIC P0HER COMPANY bhW G. D. Whittier, Manager Nuclear Engineering and Licensing GDH/hbg Enclosure ,

cc: Mr. Ashok C. Thadani Dr. Thomas E. Murley Mr. Pat Sears Mr. Cornelius F. Holden 1

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