ML20212H362

Notice of Violation from Insp on 980208-0314.Violation Noted:On 891221,licensee Failed to Provide Complete & Accurate Info Re Behavior of Dry Shielded Canister in Site Specific License Application for Use of NUHOMS Sys

ML20212H362
Person / Time
Site:	Calvert Cliffs
Issue date:	04/15/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20212H360	List: ML20212H356 ML20212H362 ML20212H369
References
50-317-98-01, 50-317-98-1, 50-318-98-01, 50-318-98-1, NUDOCS 9804210360
Download: ML20212H362 (2)

Text

i

'1 ENCLOSURE 1 i

NOTICE OF VIOLATION I 1 1 l

l l Baltimore Gas and Electric Company Docket / License Nos. 50-317; DPR-53 l Calvert Cliffs Nuclear Power Plant 50-318; DPR-69 72-8; SNM 2505 During an NRC inspection conducted from February 8, to March 14,1998, two violations l of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG 1600, the violations are listed below:

A. 10 CFR 72.11 requires that information provided to the Commission by an applicant for a license shall be complete and accurate in all material respects.

Contrary to the above, on December 21,1989, BGE failed to provide complete and accurate information regarding the behavior of the dry shielded canister in the site specific license application for use of the NUHOMS system at the Calvert Cliffs independent spent fuel storage installation. Specifically, the original calculations performed to support the Updated Safety Analysis Report (USAR) noted that during a vertical top end drop accident the clip angles, which attach the guide sleeves to the bottom support plate, would failin shear at an acceleration of 35 G. The USAR indicates that the maximum spacer disk deflection was computed as 0.077 inches and that the guide sleeve to fuel assembly gap was computed to exceed 0.5 inches.

However, BGE determined through analysis and testing that the clips actually tailed by bending (not shearing) at approximately 43 G and that the guide sleeve would pinch the fuel assemblies. I This is a Severity Level IV violation (Supplement l-Reactor Operations).

B. 10 CFR 72.48(a)(1) allows, in part, license holders to make changes to the independent Spent Fuel Storage Installation (ISFSI) or procedures as described in the Updated Safety Analysis Report unless the proposed change involves a change in the license conditions or an unreviewed safety question.10 CFR 72.48(a)(2) requires, in part, that a proposed change be deemed to involve an unreviewed safety question if a possibility for a malfunction of a different type than any evaluated previously in the Updated Safety Analysis Report may be created.

10 CFR 72.48(c) requires submittal of an application for a license amendment for changes to the ISFSI or procedures described in the USAR which involve an unreviewed sa.%ty question.

Contrary to the above, as of February 17,1998, BGE made a change to the evaluation for the dry shielded canister vertical top end drop accident, without prior NRC approval, which involved an unreviewed safety question. Specifically, BGE safety evaluatinn, ES199601368, supplement 2, revision 0, did not identify that a new malfunction was created when the gap between the guide sleeve and the fuel assembly was eliminated by the change to the evaluation for the dry shielded canister vertical top end drop accident such that a failure of the guide sleeve clip 9804210360 900415 PDR ADOCK 05000317 f:

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. 2 shielded canister in the license application for the independent spent fuel storage installation; and, (2) failure to identify a that an unreviewed safety question resulted from a change in the evaluation of the dry shielded canister vertical top end drop accident.

You are required to respond to this letter and should follow the instructions specified in the onclosed Notice when preparir.g your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with l regulatory requirements.

In accordance with 10 CFR 2.7SO of the NRC's " Rules of Practice," a copy of this letter, its enclosure (s), and your response will be placed in the NRC Public Document Room (PDR).

l Sincerely, gw ,

kW

• l Lawrence T. Doerflein, Chief

) Projects Branch 1

! Division of Reactor Projects

)

l Docket / License Nos.: 50-317/DPR 53 50-318/DPR-69 72-8/SNM-2505 l

Enclosures:

l 1. Notice of Violation l 2. NRC Region 1 Integrated inspection Report Nos. 50-317/98-01 and 50-318/98-01 l

l cc w/encis: 4 T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP) l R. McLean, Administrator, Nuclear Evaluations  !

J. Walter, Engineering Division, Public Service Commission of Maryland K. Burger, Esquire, Maryland People's Counsel

! R. Ochs, Maryland Safe Energy Coalition State of Maryland (2) l l

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