ML20212N500

Discusses Concerns in & Questions Raised Re Possibility of Obtaining Support for Further Steam Chugging Work at Lll.Nrc Active W/Chugging Investigations at Mit & UCLA

ML20212N500
Person / Time
Issue date:	05/24/1979
From:	Tong L NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Pitts J LAWRENCE LIVERMORE NATIONAL LABORATORY
Shared Package
ML20209A640	List: IA-85-782, Trip Rept of 801013-17 Visit to Jaeri Near Mito,Japan & Science & Technology Agency in Tokyo,Japan Re Results of Recent Mark II Tests & Analysis at Jaeri & Future Mark II Work at Jaeri ML20209A634 ML20209A707 ML20209A810 ML20209A830 ML20209A933 ML20209A963 ML20209B245 ML20209B868 ML20209C147 ML20209C925 ML20209C978 ML20209D016 ML20209D625 ML20209E039 ML20209E824 ML20209G011 ML20209G065 ML20209G081 ML20209G265 ML20209G286 ML20209G485 ML20209G649 ML20209G673 ML20209G932 ML20209H023 ML20210A798 ML20212H660 ML20212K727 ML20212K817 ML20212K925 ML20212L027 ML20212L203 ML20212L218 ML20212L306 ML20212L356 ML20212L974 ML20212L982 ML20212M176 ML20212M357 ML20212M505 ML20212M533 ML20212M571 ML20212M605 ML20212M670 ML20212M754 ML20212M785 ML20212M858 ML20212M981 ML20212N037 ... further results
References
FOIA-85-782 NUDOCS 8701300438
Download: ML20212N500 (2)

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s Dr. J. H. Pitts Lawrence Livemore Labtratory University of California P.O. Box 808 Livermore, California 94550

Dear Dr. Pitts:

Your letter of April 26, 1979 indicated your concern about steam chugging loads and raised questions regarding the possibility of obtaining support for further steam chugging work at LLL.

While we agree that chugging loads merit careful consideration, we feel that the multifaceted efforts underway will effectively address the problem. As you are aware NRC has been sponsoring generic research con-cerning the pool dynamic load phenomena for Mark I and Mark II containments.

The NRC recognizes the potential significance of steem chugging loads and has been vigorously pursuing resolution via these generic programs. A (i wide range of efforts both within the U.S. and abroad have input to our i

programs. The Mark I Owner's Group has sponsored full scale testing of a l sector of a torus to measure chugging loads on containment structures

( directly. For Mark II, full scale chugging tests for a single vent were conducted at General Electric's 4T. facility. Additional steam condensation tests are planned at this facility. In addition, both owner's groups have pursued analytical descriptions and correlations for the chugging phenomenon.

The NRC has been active, as you noted, with chugging investigations at both MIT and UCLA.

- Major current foreign activities include the GKSS tests in Germany and' the JAERI Mark II tests in Japan. The JAERI tests model a segment of a Mark II containment with seven full size vents and will evaluate the full range of pool dynamic loads including chugging. The GKSS tests are also of great interest to us and we have been closely cooperating with the experimenta11sts.

NRC is planning to establish a U.S. liaison for the GKSS tests; most likely Ed McCauley from your laboratory. The liaison will be our focal point of GKSS related activities including receipt of data, processing and dissemination of reduced data reports, evaluation of test results and feedback to GKSS.

a 8701300438 PDR FOIA 870120 MORROW 85-782 PDR

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! Dr. J. H. Pitts KO.Y 2 41979

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. 1 The current emphasis is on experimental measurement of chugging loads in I full scale rather than analytical descriptions or correlations. However, i we recognize the value of periodically bringing together experts in the field and jointly assessing the results and merits of the NRC sponsored  !

research programs. A Containment Review Group meeting is scheduled for June,1979 (date not yet fixed). We would like to extend an invitation for you to attend this meeting and make a presentation on your analytical work related to chugging.

Please contact R. Cudlin of ny staff for details of the meeting.

1 Sincerely,  !

OriginalSigned By:

L S. Tong L. S. Tong, Assistant Director for Water Reactor Safety Research cc: D. Eisenhut, NRC Division of Reactor Safety Research F. Tokarz, LLL L. Cleland, LLL

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