ML19211A745

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Forwards WARD-D-0050,Revision 3, Facility Core Assembly Hot Channel Factors Preliminary Analysis
ML19211A745
Person / Time
Site: Clinch River
Issue date: 12/14/1979
From: Copeland R
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML19211A746 List:
References
NUDOCS 7912200578
Download: ML19211A745 (1)


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Department of Energy Clinch River Breeder Reactor P! ant Project Office R O. Box U Oak Ridge. Tennessee 37830 December 14, 1979 Docket No. 50-537 Mr. Domenic B. Vassallo Acting Director Division of Project Managerent Office of Nuclear Reactor Regul e. ion U. S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Vassallo:

TOPICAL REPORT ON CRBRP'S THERMAL-HYDRAULIC PERFORMANCE Enclosed are seventy (70) copies of the following report:

WARD-D-0050, Rev. 3, "CRBRP Core Assemblies Hot Channel Factors Preliminary Analysis" The CRBRP hot channel factors have been revised and updated in this report to provide the latest rat'onale and methodology available in this area. Work on both the hot channel factors develnprnent and the core thermal-hydraulic analyses, which utilize the hot channel factors, is proceeding in tandem rather than in series.

Because of this, the PSAR thermal-hydraulics analyses (Section 4.4) in some cases utilize pre-viously reported (WARD-D-0050, Rev. 2) hot channel values instead of the most recent (WARD-D-0050, Rev. 3) values. However, the results that are presented in the recently submitted PSAR Section 4.4 envelope the results that would be obtained if the latest hot channel factors were incorporated.

Sincerely, 4

A.-

MA E and '. Cop PS:79:308 c ing ssist D:*ector for Public Safety Toto

Enclosure:

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Topical Report cc: Service List j

Standard Distribution

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