ML20210N707

Safety Evaluation Supporting Upper End Fittings & Loading & Storage of 55 Gallon Drums Inside Overpack Container

ML20210N707
Person / Time
Site:	Three Mile Island
Issue date:	09/25/1986
From:	NRC
To:
Shared Package
ML20210N685	List: ML20210N680 ML20210N707
References
NUDOCS 8610060618
Download: ML20210N707 (2)

Text

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ATTACHiiEliT SAFETY EVALUATION Introduction During defueling the licensee intends to place end fittings in shielded 55 gallon druns which will be inside an overpack container. The druus will be trensferred to and placed in a storage area adjacent to the West "D" ring on the 347 ft. elevation of the reactor building. As tooling and ic.ethodologies are developed tne end fitti: 9 will be sized to fit through the openings in defueling canisters and ultimately transferred off site. There may be scme fuel attached to or packed in flow spaces in the end fittings. Since the accumulated fuel conte.ined in a drum or several druns could exceed the mininua mass required for criticality, criticality evaluations were performed taking gecaetry and neutron absorbtion into account.

Evaluation GPUH perforiaed criticality caleilations that indicated a shutdcun mars in significantly greater then 5% (K uas .918 for the worst case plenar array).

The model they used was very conNvative. Among the principal conservatists are:

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1. lieglecting neutron absorption by the stainless steel end fittings.

2. Use of drums full of fuel when a few kilograms at most is expected.

3. Use of entirely region 3 fuel (highest enrichment) and opticum fuel to water ratio.

The NRC staff's calculations using similar conservative models independently confirned GPUN's results. The affects of dropping a 55 gallon druu of end fittings or dropping a load onto a stored drum are bounded by previously unalyzed canister drop accidents. '

Conclusions The staff has determined that the transfer and storage of end fittings in shielded 55 gallon drenas does not present a significant criticality risk provided that 4950 ppm boron is maintained in any contained water. Load drop accident.s have been beunded by previous analyses regarding fuel canisters.

The scope of activitics fclls within the bounds of the activities previously analyzed in the Programatic Environmental Impact Statement. The end fitting transfer and storage does not constitute en unreviewed safety question as defined by 10 CFR 50.59 end can be inplenented without significant risk to the health and safety of the public.

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s TMI-2 SERVICE LIST Dr. Thomas Murley Willis Bixby, Site Manager Regional Administrator U.S. Department of Energy U.S. Nuclear Regulatory Commission P.O. Box 88 631 Park Avenue Middletown, PA 17057-0311 King of Prussia, PA 19406 David J. McGoff John F. Wolfe, Esq., Chairman Office of LWR Safety and Administrative Judge Technology Atomic Safety and Licensing Board Panel NE-23 U.S. Nuclear Regulatory Commission U.S. Department of Energy Washington, D.C. 20555 Washington, D.C. 20545 Dr. Oscar H. Paris William Lochstet Administrative Judge 104 Davey Laboratory Atomic Safety and Licensing Board Panel Pennsylvania State University U.S. Nuclear Regulatory Commission University Park, PA 16802 Washington, D.C. 20555 Frank Lynch, Editorial Dr. Frederick H. Shon The Patriot Administrative Judge 812 Market Street Atomic Safety and Licensing Board Panel Harrisburg, PA 17105 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Robert B. Borsum Babcock & Wilcox Dr. Judith H. Johnsrud Nuclear Power Division Environmental Coalition on Nuclear Power Suite 220 433 Orlando Avenue 7910 Woodmont Avenue State College, PA 16801 Bethesda, MD 20814 Ernest L. Blake, Jr., Esq. Michael Churchhill, Esq.

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