ML20138D409
| ML20138D409 | |
| Person / Time | |
|---|---|
| Issue date: | 02/01/1993 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Hodges M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 9302180184 | |
| Download: ML20138D409 (3) | |
Text
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FEB 1 1993 i
MEMORANDUM FOR:
Marvin W. Hodges, Director Division of Reactor Safety FROM:
Jacque P. Durr, Chief Engineering Branch Division of Reactor Safety
SUBJECT:
SUMMARY
OF DROP-IN MEETING WITH MEMBERS OF THE BOILING WATER REACTOR OWNER'S GROUP (BWROG) REACTOR WATER LEVEL ISSUE COMMITTEE On January 19,1993, the chairman of the BWROG reactor water level issue committee requested a meeting, for that same day, with members of the Region I staff. The regional staff met with him and the chairman of the BWROG model test subcommittee on January 20,1993. The purpose of the meeting was to provide the Region I staff the status of committee activities as discussed in a similar meeting held in NRC Headquarters on January 15,1993 (see Cubbage to Jones memorandum, dated January 27,1993). The list of attendees is provided in the enclosure, and a summary of the issues discussed is provided below.
Mr. Beck, the committee chairman, reported that NRC Headquarters personnel were updated the previous Friday. He described the current committee long-term program which included the following elements: obtaining plant specific data, analytical model development, reference leg de-gas and condensing chamber tests, acceptance criterion development, and modification development. He mported that the condensing chamber test was about two months behind schedule at the ABB facility in Chattanooga, TN. He further stated that the BWROG was not trying to avoid or defer modifications, that the analysis and testing was proceeding in parallel with review of active and passive modifications.
Mr. Beck said that preliminary results show that when the relaxation time (or de-gas rate),
hydrostatic head and bubble rise velocity are considered, the calculated errors may be much less than those initially predicted. He emphasized that the testing program needs to be completed before drawing final conclusions.
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. FEB: 11993 I
i Marvin W. Hodges 2
Finally, they used a pressurized clear plastic column to demonstrate some of the physical phenomena involved with depressurizing a column of water. During that demonstration, we also discussed the fact that a pressurized soda can was not a good analogy for a pressurized reference leg because when a soda can is shaken or heated, a chemical reaction will actually increase the pressure in a can. No similar reaction would occur in a BWR reference leg.
The Region I staff concluded the meeting by acknowledging the preliminary nature of the results and thanking the committee members for the information.
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&u Jacq e P. Durr, Chief Engineering Branch Division of Reactor Safety
Enclosure:
As stated cc w/ enclosure:
Public Document Room T. Martin A. Thadani, NRR R. Jones, NRR T. Collins, NRR R. Eaton, NRR E. Kelly, DRP J. Lee, NRR A. Cubbage, NRR P. Blanche E. Hadley
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f,NCI.OSURE MEETING ATTENDEES-NAME AFFILIATION M. Hodges NRC Region 1 J. Durr NRC Region I E. Kelly NRC Region I W. Ruland NRC Region I i
G. Beck PECO/BWROG RWL committee chairman D. Weber PECO/BWROG model test subcommittee 9