ML19220B497
| ML19220B497 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/08/1975 |
| From: | Harley S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904260393 | |
| Download: ML19220B497 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, O.
C.
20555 December 8, 1975 00CXET NO:
50-320 APPLICANT:
Metropolitan Edison FACILITY:
Three Mile Island Unit 2
SUMMARY
OF MEETING CN TRANSIENT LOADINC CF SUBCCMPARTMENT STRUCTURES Representatives of the applicant and his contractors met with members of the NRC staff on December 2,1975 to discuss the capability of the contain-ment subcompart ent structures to resist transient pressures.
The acplicant provided tables as attached to clarify his original design.
It was noted that the ultimate pressure capacity of the structures exceeded the design pressure (1.5 Pa) because of other design considerations, such as shielding. Also, it was assumed in the analysis that pressures on the back side of all walls during the period of interest was essentially containment ambient pressure.
After further discussion on the justification of structural capability in excess of design capacity, the applicant indicated he would furnish descrip-tions of the local area of high pressure, discuss the duration of ceak pressures in relation to the natural frequency of the structures, and present criteria and methods of calculation, in sufficient detail to evaluate that jus ti fication.
The staff indicated we had not yet accepted the applicant's calculated pressures, and would continue our efforts toward this end. The aonlicant has not yct completed their design of the shield plugs, but reiterated their intention to stay within the design limits for the plugs used in their analysis.
It was tentatively agreed that the applicant will present their conceptual design of the shield plugs to the staff in mid-January, 1976.
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A Harley i ver, Project Manager Divisic,a er Reactors Branch 2-2 Light of Reactor Licensing Attachments :
Tacles List of Attendees m-,--
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79042603 D b
DIFFERENTIAL PRESSURES Calculated Pressure 1970 1970 Relap III Design Actual 1970 New Pressure Design Ult ima te Peak Blewdcwn Pa 1.5 x Pa capacity Reactor Cavity 92.9 91 92.9 139.5 210 Steam Generator Cavity 23.5 19.1 23.5 35.2 39 Letdcwn Cooler Cavity 12.5 20 30 45 h
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s' DIFFERENTIAL 9RESSURES AND PIPE RUPTURE 1970 1970 Design Actual Pressure Design Document B Pa (psi) 1.5 Pa 1.25 Pa + Y i Reactor Cavity 92.9 139.5 Not acclicable Steam Generator Jet impingemen t = 2223 k Cavity 23.5 35.2 Equivalent pressure 29.4
+ 6.7 36.1 esi
=
Letdcwn Cooler Jet imp ingement = 28 k Cavity 20 30 Equivalen t pressure 25 + 1 = 26 osi MS/FW Tunnel l Jet incincement 510 kips I
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4 LIST OF ATTENCEES NRC Harley Silver D. Shum P. Baranowsky C. P. Tan A. L. Gluckmann GPUSC Leon Garibian Lou Lanese B&R P. F. Zallnick Jchn C. Areher Owen Mallen s_ ' S.Z g~,
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