ML14351A308

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10 CFR Part 21 Notification for a Defect in LOCA Analyses for B&W Plants
ML14351A308
Person / Time
Site: Davis Besse, Oconee, Arkansas Nuclear, Crane  
Issue date: 12/16/2014
From: Salas P
AREVA, AREVA
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC:14:070
Download: ML14351A308 (3)


Text

A AREVA December 16, 2014 NRC:14:070 U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852 10 CFR Part 21 Notification for a Defect in LOCA Analyses for B&W Plants This letter provides notification of a reportable defect in accordance with 10 CFR Part 21. This situation was reported to the NRC Operations Center by facsimile on November 25, 2014. The information required by 10 CFR Part 21 is provided in the attachment to this letter.

The affected utilities have been informed of this defect.

If you have any questions related to this information, please contact Ms. Gayle F. Elliott, Product Licensing Manager, by telephone at (434) 832-3347 or by e-mail at Gayle.Elliott@areva.com.

Pe'h -Sas, Director Licensing & Regulatory Affairs AREVA Inc.

cc:

J.

G.

Rowley Project 728

Attachment:

A.

TACO3 Defect Report AREVA INC.

3315 Old Forest Road. Lynchburg, VA 24501 Tel.: 434 832 3000 - www.areva.com

Reportable Defect (i) Name and address of the individual or individuals informing the Commission.

Gayle Elliott, AREVA Inc., 3315 Old Forest Road, Lynchburg, VA 24501 (ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.

The defect is in the LOCA analyses provided by AREVA Inc. for B&W plants.

(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.

AREVA Inc.

(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.

The defect is related to the thermal conductivity model in the codes TACO3 and GDTACO which are used in the AREVA LOCA model for B&W plants The thermal conductivity model does not adequately represent the change in conductivity with burnup for the fuel. The correction of the thermal conductivity model results in the peak cladding temperature limit in 10 CFR 50.46 (2200 degrees F) being exceeded.

(v) The date on which the information of such defect or failure to comply was obtained.

October 19, 2014 (vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.

The defect exists for the following plants:

Oconee Nuclear Station Unit 1, Oconee Nuclear Station Unit 2, Oconee Nuclear Station Unit 3, Arkansas Nuclear One Unit 1, Three Mile Island Unit 1, Davis-Besse Unit 1 Page I of 2

(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.

AREVA Inc. recommended to the affected plants that the LHR limits be reduced by 2 kw/ft at middle-of-life conditions. This reduction in LHR limits will result in the peak cladding temperature limit being met. The individual utilities are responsible for this action and AREVA believes that this action has been implemented by each utility.

(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.

AREVA Inc. recommended to the affected plants that the LHR limits be reduced by 2 kw/ft at middle-of-life conditions.

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