ML20056E246
| ML20056E246 | |
| Person / Time | |
|---|---|
| Issue date: | 06/15/1993 |
| From: | Kauffman J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Rosenthal J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| Shared Package | |
| ML20056E247 | List: |
| References | |
| AEOD-T93-01, AEOD-T93-1, NUDOCS 9308230061 | |
| Download: ML20056E246 (2) | |
Text
JUN 151993 MEMORANDUM FOFgack E. Rosenthal, Chief g
"" Reactor Operations Analysis BrancY Division of Safety Programs Office for Analysis and Evaluation of Operational Data FROM:
John V. Kauffman Reacter Systems Section CE and GE Reactor Operations Analysis Branch Division of Safety Programs Office for Analysis and Evaluation of Operational Data SUBJEQ PRIMARY SYSTEM INTEGRITY, PRESSURIZED WATER REACTOR COOLANT SYSTEM LEAKS The enclosed technical review report documents the results of analyses of reactor coolant system (RCS) leaks at U.S. pressurized water reactors (PWRs). Events from 1980 through May,1992 were included in the study. The events were chosen to identify primary system problems with technical similarities between U.S. and Czech and Slovak nuclear power plants (NPPs). The study excluded steam generator (SG) tube leaks because of design differences between U.S. and Czech and Slovak SGs.
This study was initiated and prepared by Mr. Jan Stuller of the Czechoslovak Atomic Energy Commission (CSKAE) (currently Mr. Stuller is Director of the State Office for Nuclear Safety for the Czech Republic) during an assignment at NRC that resulted from bilateral agreements between NRC and CSKAE. The purpose was to identify issues, problems, or ' lessons learned" from U.S. operating experience that might be applicable to Czech and Slovak NPPs.
None of the individual findings or events from the study warrants further action. The study's results, however, offer insights into the number and extent of RCS leaks at PWRs, systems and components most likely to leak, and the causes of the leaks.
Original signed by John V. Kauffman Reactor Systems Section CE and GE Reactor Operations Analysis Branch Division of Safety Programs Office for Analysis and Evaluation of Operational Data
Enclosure:
As stated j
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