ML20127M435
| ML20127M435 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 01/20/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20127M438 | List: |
| References | |
| NUDOCS 9301280204 | |
| Download: ML20127M435 (1) | |
Text
I
)
~
GE Nuclear Enugy n
l-y January 20,1993 Docket No. STN 52-001 Chet Posiusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal
'^-
Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Reviev, Schedule - ABWR Containment Ultimate Strength
Reference:
- 1) Letter from P. P. Stancavage to C. Poslusny, GE Plan for Resolving Appendix 19F Open items, dated January 14, 1993
- 2) Letter from C. Postusny to P. W. Marriott, Preliminary input to Final Safety Evaluation Report on Containment Performance, dated December 21,1992
Dear Chet:
Enclosed is a summary report by Bechtel for the ABWR RCCV nonlinear analysis. This report provides rcsolution of Reference I plan in response to Reference 2.
As stated in the report, both Level C and ultimate pressure capabilities of the axisymmetric concrete components (including liner plate') of the ABWR standardized containment structure are predicted from the nonlinear FINEL analysis. For the top slab (including liner plate) which is non-asixymmetric, the Level C pressure value is predicted frem the linear design analysis using a 3D model. The analy;is results show that the top slab is the controlling region and its Level C pressure capability is 164 psig. This is already higher than the median fragility level of 134 psig associated with the drywell head. A prediction of;he top slab ultimate pressure capability is therefore not necessary and median fragility level of 134 psig for the contaimnent structure is justified.
In order to eliminate the issue regarding non-proprietary version of the SSAR, GE intends to replace the RCCV test information given in Appendix 19F with the analysis results in a later SSAR amendment since the objective of demonstrating pressure capability of the concrete portion of t:te containment to be higher than 134 psig can be achieved by analysis alone.
Sincerely, 26003G Jack Fox Advanced Reactor Programs cc: Jack Duncan (GFi
/
Nore :in Fletcher (.
d) nuo7 4
9301280204 930120 yN PDR ADOCK 05200001 j !g PDR A
.