ML19276F590
| 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) | |
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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