ML20215L134
| ML20215L134 | |
| Person / Time | |
|---|---|
| Issue date: | 06/09/1986 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Boehnert P Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-CT-1849, NUDOCS 8610280487 | |
| Download: ML20215L134 (4) | |
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[j90 June 9, 1986 To:
Paul Boehnert From:
Milton S. Plesset MM
Subject:
Remarks on the ROSA-IV Program You will recall that I promised you some remarks on the ROSA-IV program which is being carried out by the Japan Atomic Energy Research Institute (Jaeri) which I visited last April 21 and 22,1986.
I regret that I did not get this report to you sooner.
ROSA IV is number 4 in the Rig of Safety Assessment and is used "to develop and assess a computer code to be used in the analysis of small break loss of coolant accidents and transients (for PWR's)". The program includes two agreements for international cooperation. The first is an agreement signed in February 1984 with the USNRC which will provide JAERI with (1) Two-phase instrumentation (2) RELAP5 and TRAC codes (3) Experimental analysis results for ROSA IV (4) A resident engineer JAERI in turn will provide USNRC with (1) LSTF and TPTF data (2) Modifications in code and code models (3) Experimental analysis results for ROSA IV (4) A resident engineer It should be explained at this point that LSTF stands for "large scale test facility" in this case ROSA IV, and TPTF stands for "two phase flow test facility" which is a separate facility for research type experiments on two-phase flow in relatively large pipes with mixed flows.
It should be pointed out that JAERI and the French CEA signed an agreement for international cooperation in April 1985 in which CEA provides JAERI with (1)
Integral and separate effects test data (2) CATHARE code (3) Experimental analysis of ROSA-IV data (4) A resident engineer and JAERI provides CEA with (1) LSTF and TPTF data
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i (2) Modifications in code and code models (3) Experimental analysis of ROSA IV tests (4) A resident engineer It is clear that there is a general duplication in this agreement and the USNRC agreement, it follows that there may be some difficulties as a result.
I noted that the Japanese engineer in charge of ROSA-IV has just returned from an extended stay in Grenoble.
ROSA-IV can operate at full scale pressure and temperature and has 1/48 of the number of full scale fuel rods. The steam generator has 1/24 of the number of tubes of a full scale steam generator. The test facility has two such steam generators. The power available for electrical heating of the tubes in the facility corresponds to full scale decay heat.
The tests completed so far include several cold leg breaks of various sizes, a test with locked open PORV (TMI-type), and several tests of natural circulation.
I have the impression that the Japanese are somewhat reluctant to transmit their results until they have done more work on their code development.
If any member of the ACRS or of the ACRS staff wants more details than I have given here I shall be glad to try to furnish it.
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
,E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20555 October 22, 1986 MEMORANDUM FOR: Jim McKnight Document Con rol Systems O
FROM:
Ethed[8 r
Advisory Comni ttee on Reactor Safeguards The attached ACRS Documents are being provided to you for listing on the accessions list. Please forward to the Public Document Room.
Attachments:
As Stated i
j
ACRS MINUTES AND CONSULTANT REPORTS (PDR 102286) 1.
CT-1849 Plesset memo 6/9/86 to Boehnert re Remarks on the ROSA-IV Program 2.
CT-1858 Schrock ltr 9/8/86 to Michelson re 10 CFR 50.46 and Appendix X Revision 3.
CT-1859 Sullivan ltr 9/9/86 to Michelson re Review of Appendix K Supporting Documents 4.
CT-1860 Davis ltr 9/17/86 to Ward re Auxiliary Feedwater Systems 5.
CT-1862 Bender ltr 9/26/86 to Kerr re ACRS Subcte Meeting on NUREG-1150 Applications on 9/24/86 6.
CT-1863 Plesset memo 10/6/86 to Houston re Containment Requirements Subcte Meeting and the Severe Accident Subcte Meeting 9/23-24/86 7.
CT-1865 Catton memo 9/28/86 to Houston re Severe Accidents and Nuclear Plant Chemistry Meeting 9/24/86 on Regulatory Implementation Plan for Severe Accident Plan 8.
ACRS-2412 Fort St. Vrain NGS Subcommittee Meeting 4/2/86 9.
ACRS-2433 Gas-Cooled Reactor Plants Subcomittee Meeting 6/26/86
- 10. ACRS-2439 Improved LWR Designs Subcommittee Meeting 7/9/86
- 11. ACRS-2440 Long Range Plan for the NRC Subcommittee Meeting 7/9/86
- 12. ACRS-2449 Metal Components Subcommittee Meeting 8/4/86
- 13. ACRS-2450 Reactor Operations Subcommittee Meeting 8/4/86
- 14. ACRS-2452 Improved LWR Designs Subcommittee Meeting 8/5/86
- 15. ACRS-2455 Maintenance Practices and Procedures Subcommittee Meeting 8/13/86
- 16. ACRS-2456 Inspection and Enforcement Programs Subcommittee Meeting 8/14/86
- 17. ACRS-2457 Thermal Hydraulic Phenomena Subcommittee Meeting 8/28/86
- 18. ACRS-2458 Decay Heat Removal Systems Subcommittee Meeting 9/9/86
- 19. ACRS-2461 Containment Requirements Subcommittee Meeting 9/23/86
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