ML19256D189

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Discusses Review of 671016 Draft of B&W Submittal,Suppl 2,re Thermal Shock on TMI Reactor Vessel Due to Operation of Eccs.Lists Items to Be Covered at 671017 Meeting W/Applicant
ML19256D189
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/18/1967
From: Pawlick S
US ATOMIC ENERGY COMMISSION (AEC)
To: Lang C
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7910170687
Download: ML19256D189 (1)


Text

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  • Charlas G. Iong, Chief, Reactor Project Branch f3 Division of Reactor Licensing
1. C. DeYoung, Chief, Con mir = t & Component Technology Branch e

THRU:

Stefan S. Paulicki Containment & Component Technology Branch TnuRE-MILE ISLAND - THEmfAL SHOCK ON REACTOR VESSEL

{d-d C&CTB DEL: SSP RT 200 We have reviewed the draft of the Babcock & Wilcos submittal (Supplement No. 2, October 16, 1967) on the thermal shock on the Three Mile Island rector vessel, des to the operation of the emergency core cooling system.

The informatica submitted on the dsetila yielding mode of failure seems to be adequata to allow sa evaluation of the problem. We would like, however, to have more details on the fracture mechanics analysis, reported sa page 11-1-2 of the draft. Specifically we seuld like to know:

The critical stress intensity faster (KIC) actually used, a.

b.

The init.: t rruk geometry and size assumed in the analysis, Equations and to correlata crack size with stress intensity.

c.

We wonder also if the applicant critically reviewed the v=14<fity of the experimental data reported in the WAPD paper by Landerman, Tanichko, and Hazelton. We intend to discuss these items in the course of the October 17, 1967 meeting with the applicant.

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