ML19276F590

Requests Inclusion of NEDE-23749-1-P, Comparison of Analytical Model for Computing Safety Relief Valve Discharge Line Transient Pressure & Forces to Monticello T-Quencher Test Data, in Docket

ML19276F590
Person / Time
Site:	Cooper
Issue date:	03/29/1979
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Ippolito T Office of Nuclear Reactor Regulation
References
NUDOCS 7904060254
Download: ML19276F590 (1)

Text

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'" MAinEL"&s"ifsT2 March 29, 1979 Director, Nuclear Reactor Regulation Attention: Mr. Thomas A. Ippol' ,, Chief Operating Reactors Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Mark I Containment Program - General Electric Rep.rt NEDE-23749-1-P, " Comparison of Analytical Model for Computing Safety / Relief Valve Discharge Line Transient Pressures and Forces to Monticello T-Quencher Test Data" Cooper Nuclear Station NRC Docket No. 50-298, DPR-46

Dear Mr. Ippolito:

The subject report was transmitted to the NRC by the General Electric Co.

by letter from L. J. Sobon to V. Stello dated March 20, 1979. This report compares safety / relief valve discharge line transient pressures and forces predicted by an analytical model to Monticello T-Quencher test data and was provided as part of task 7.1.2.2 of the Mark I Con-tainment Program. Since this report will be utilized in support of the Cooper Nuclear Station Containment Evaluation Program, we would like to request that the subject report be included on NRC Docket No. 50-298 for Cooper Nuclear Station.

Should you have any questions or comments relative to the above, please do not hesitate to contact me.

Sincerely, M

ay M. Pilant Director of Licensing and Quality Assurance

/cmk

/

Ok) 9 7904060254