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Forwards Interim Rept Consisting of Graphs of Release Rates of Mass & Energy Into Containment from Selected Accident Sequences to Form Basis of Subsequent Containment Analysis, for Approval by 861201,per 860425 Commitment
	ML20215D149
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	09/30/1986
From:	Tucker H; DUKE POWER CO.
To:	Harold Denton, Youngblood B; Office of Nuclear Reactor Regulation
References
	RS-20-SLB, NUDOCS 8610140010
	Download: ML20215D149 (27)
	v • d • e

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DUKE POWER GOMPANY P.O. DOX 33180 CIIARLOTTE, N.C. E8242 HALH. TUCKER TE LEPHONE vna pas (704) 073-4538 September 30, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Connaission Washington, D. C.

20555 Attention:

Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414 McGuire Nuclear Station Docket Nos. 50-369 and 50-370

Dear Sir:

By letter dated April 25, 1986, Duke Power Company (Duke) presented a plan for the resolution of issues concerning control of combustible gasses in containment following a beyond-design-basis accident. As agreed to with the Staff, the schedule for this resolution called for the submittal of interim results on a periodic basis for Staff review. Attached to this letter you will find the first of those interim reports. This report consists of graphs of the release rates of mass and energy into the containment from the selected accident sequences which will form the basis of subsaquent containment analysis.

The attached graphs were produced using MAAP, Version 2.0B.

This accident analysis code was developed by IDCOR and has been reviewed by the Staff.

In each sequence, emergency core cooling system recovery times were adjusted to produce total hydrogen release rates equivalent to 70-80% cladding reaction. The graphs are self l

explanatory, with the accident sequence for each indicated at the top, and the corresponding mass or energy release parameter at the left side. Note that discontinuities occur in the energy and mass release parameters at certain points because code predictions indicate that the release rates at those points were zero.

This is especially evident because the mass release rates of liquid water and steam were computed separately.

In order for the agreed upon analysis to proceed on schedule, NRC approval of the attached MAAP analysis is needed by December 1, 1986.

Very truly yours,

&k/

Hal B. Tucker 8610140010 860930

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ROS/20/ sib fDR ADOCK 05000369 Q

PDR q

Attachment d

Mr. Harald R. Denton, Dirccter September 30, 1986 Page Two xc:

Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station

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Dear Sir:

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