ML20127D469
| ML20127D469 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 01/14/1993 |
| From: | Stancavage P GENERAL ELECTRIC CO. |
| To: | Poslusny C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| MFN-005-93, MFN-5-93, NUDOCS 9301150233 | |
| Download: ML20127D469 (2) | |
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m cu r e m sr re u was january 14,1993 MFN No. 006-93 Docket STN 52 001 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
. C. Poslusny, Senior Project Manager Standardization Directorate Associate Directorate for Advanced Reactors and Licensing Renewal Office of the Nuclear Reactor Regulation
Subject:
GE Plan for Resolving Appendix 19F Open items
Reference:
Letter from C. Posiusny (NRC) to P. W. Marriott (GE), Preliminarf input to Final Safety Evaluation Report on Containment Performance, dated December 21,1992.
Dear Mr. Poslusny:
On the reference letter, the NRC requested additional information regarding the median fragility level of the concrete portion of the RCCV (Section II.B.2) and potentialleakage up to the internal pressure value of 134 psig (Section II.C). The GE plan for resolving these open items is as follows:
In order to provide further justification for a median fragility level of 134 psig for the containment structure, Bechtel, under contract to GE, is currently performing a nonlinear analysis for the ABWR standard plant RCCV including liner for a severe accident pressure of 180 psig in combination with dead load. The computer code used is FINEL which is a Bechtel proprietary finite element program for analysis of axisymmetric structures, taking into account nonlinear behavior due _to cracking of concrete and yielding of steel. The analysis results from this evaluation will be submitted to the NRC for review by January 20,1993.
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i C. Poslusny MFN. 006 93 U.S. Nuclear Regulatory Commission January 14,1993 Page 2 With regard to leakage, NRC requested GE to provide assessment of potentialleakage 1
up to 134 psig failute pressure. Legkage area estimates have already been provided up i
to 120 psig (failure pressure at 700. F) in Subsection 19F.3.2.2 of Amendment 21. It is important to note that the leakage areas estimated arg applicable only to the accident sequences which result in temperature exceeding 500 F (seal degradatiog temperature). The 134 psig failure pressure value is associated with 500 F under which the seal is capable of providing sealing action.
Sincerely, mi
&ksucos *W P. P. Stancavage, Acting Manager Safety & Licensing M/C 444, (408) 925-6948 3
cc:
R. C. Berglund N. D. Fletcher DOE F. A. Ross DOE J. F. Quirk -
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