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Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Thermo-Hydraulic Phenomena Subcommittee Meeting - November 13-14, 2000

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
THERMAL-HYDRAULIC PHENOMENA SUBCOMMITTEE MEETING:
GENE TRACG THERMAL-HYDRAULIC CODE
NRC RES T/H RESEARCH PROGRAM
NOVEMBER 13-14, 2000
ROCKVILLE, MARYLAND

Contact: P. Boehnert (301/415-8065 - pab2@nrc.gov

TOPICAL AGENDA

	TOPIC				SPEAKER	TIME
November 13, 2000
I.	Introduction				G. Wallis, Chairman	8:30 a.m.
II.	GE Nuclear Energy Presentation:
	TRACG Code (Closed - all or part)
	A. Introduction				J. Klapproth	8:45 a.m.
	B. Technical presentation				JGM Andersen, FT Bolger, CL Heck
		What is TRACG and it's intended application? Licensing requirements Submittals
			Approach: CSAU
				(Stress application rather than generic descriptions)
	Step			Description	Application LTR or Other Reference
	1			Scenario Specification	Section 2.7
	2			Nuclear Power Plant Selection	Section 2.8
	3			Phenomena Identification and Ranking	Section 3.0
	4			Frozen Code Version Selection	Model LTR, ECP control
	5			Code Documentation	Model LTR, ECP docs.
	6			Determination of Code Applicability (Presentation of TRACG models and their applicability)	Sec. 4.1, Qual. & Model LTR
	7			Establishment of Assessment Matrix (Summary of TRACG assessment)	Section 4.2
	8			Nuclear Power Plant Nodalization Definition (Basis for BWR nodalization and sensitivity studies)	Section 5.2, Qual. LTR
	9			Definition of Code and Experimental Accuracy (Summary of PIRT uncertainties)	Section 5.1, Qual. LTR
	10			Determination of Effect of Scale (Qualification against full scale BWR plant data)	Section 5.3, Full scale data
	11			Determination of the Effect of Reactor Input Parameters and State	Section 6.0
	12			Performance of Nuclear Power Plant Sensitivity	Sections 7.0 and 8.0
	13			Determination of Combined Bias and Uncertainty	Sections 7.0 and 8.0
	14			Determination of Total Uncertainty (Confirmation of code uncertainty and demonstration cases)	Sections 7.0 and 8.0
		Concluding Comments
III.	NRC Presentation (Open)				R. Landry, NRR	6:00 p.m.
	Status of Code Review Future Actions/Schedule Milestones
IV.	Subcommittee Caucus (Open)					6:30 p.m.
		Follow-on Items for this Issue Future Actions Committee Action
V.	Recess					6:45 p.m.
November 14, 2000
VI.	Reconvene				G. Wallis, Chairman	8:30 a.m.
V.	NRC RES Presentation: T/H Phenomena Research Program
	A. Introduction/Overview				F. Eltawila/J. Flack, RES	8:40 a.m.
		1. Overview of T/H Research Activities
		2. Program Status
			Program Accomplishments to Date Schedule for Completion Canceled/Completed Programs
		3. Relationship of Research Programs to Long-Term Needs
	B. Status of On-Going Research Programs				J. Uhle/D. Bessette/ C. Boyd, RES
		1. Code Consolidation
		2. Code Modeling Research
			Flow Regime Modeling/Phase Separation @ Tees/Subcooled Boiling
		3. Experimental Programs
			PUMA Test Facilities OSU Test Facilities Rod Bundle Heat Transfer
		4. CFD Program
	C. Concluding Comments				F. Eltawila/ J. Flack	2:45 p.m.
VI.	Subcommittee Caucus					3:00 p.m.
	Follow-on Items for this Issue Future Actions Committee Action
V.	Adjourn					3:15 p.m.

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