ML20059E547
| ML20059E547 | |
| Person / Time | |
|---|---|
| Issue date: | 03/04/1992 |
| From: | Sullivan H Advisory Committee on Reactor Safeguards |
| To: | Catton I Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-CT-2013, NUDOCS 9311030260 | |
| Download: ML20059E547 (1) | |
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NUCLEAR REGULATORY COMMISSION 3g 2;
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March 4, 1992 MEMORANDUM FOR:
I.
- Catton, Chairman, Thermal Hydraulic Phenomena Subcommittee r#aroldSu'i FROM:
H
/an, ACRS Consultant
SUBJECT:
ROSA-IV AND THE INTEGRAL SYSTEM TEST ISSUE ROSA-IV was designed to model a large four-loop H reactor.
RES has proposed to use this facility as the integral system test (IST, high pressure, full-height) facility to simulate the AP600 plant.
ROSA-IV has known scaling deficiencies, and RES has proposed a set of changes to improve its fidelity for simulation of transients for AP600.
The ACRS has questioned RES about the extent and applicability of these proposed modifications.
These issues still exist after several meetings with RES.
NRR has stated that high-pressure tests will be required to address the integral effects of concern to them (condensation, stratification, low driving forces, etc.) in order to allow design certification; they believe that the H tests at OSU and the CMT separate ef fects tests may not provide the needed confidence. This
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situation results in the placing of additional importance on the IST facility parameters selected in order to ensure adequate simulation of AP600.
Currently, RES has not performed the required scaling and computer analysis to provide the ACRS with the confidence that ROSA-IV data will support AP600 certification.
Several key components of ROSA have associated major scaling concerns (e.g. vessel and steam generators), and the ability to correct this problem is questionable.
RES should continue their scaling studies and associated computer analyses in order to provide NRR and the ACRS with the technical confidence that will be required to support the AP600 certification effort.
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