ML19225B744
| ML19225B744 | |
| Person / Time | |
|---|---|
| Issue date: | 05/25/1979 |
| From: | Snaider R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907250609 | |
| Download: ML19225B744 (4) | |
Text
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DISTRIBUTION FOR NEET!NG SUMMARIES Central Files TERA SEPB Reading NRR Reading H. Denton E. Case
'/, Stello D. Eise, hut R. Vollmer W. Russell B. Grimes T. Carter T. Ippolito R. Reid G. Knighton V. Noonan A. Schwencer D. Ziemann D. K. Davis G. Lainas J. Scinto, OELD OI&E (3)
ACRS (16)
R. Snaider C. Hofmayer F. Litton R. Johnson (440)
- 8. Morris C. Serpan K. Hoge W. Hazelton S. Weiss R. Hawthorne, NRL J. Sprague, NRL J. Carew, BNL R. Klecker 452 000
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May 25, 1979 MEf"",ANDUM FOR :
D. G. Eisenhut, Deputy Director, Division of Operating Peactors, NRR hgv'D.K. Davis, Chief,SystematicEvaluationProgram THRU:
Branch, 00R FROM:
R. P. Snaider, Systematic Evaluation Program Branch, D0R
SUBJECT:
SUMMARY
OF MEETING WITH NAVAL RESEARCH LABORATORY AND BROOKHAVEN NATIONAL LABORATORY TO DISCUSS RESOLUTION OF THE POTENTIAL PWR NEUTRON SHIELD TANK LOW FRACTURE TOUGHNESS On Friday, May 18, 1979, members of the NRC staff met with representatives of Brookhaven National Laboratory (BNL) and Naval Research Laboratory (NRL) to discuss what action was necessary to resolve the issue of possible PWR neutron shield tank low fracture toughness. A list of attendees is attached.
This issue had been raised in March 1978, when a utility notified the NRC, under 10 CFR 21, that calculations which included low energy (<1 mev) neutron groups had resulted in a large predicted shift in Nil-Ductility Transition Temperature. Such a shift would result in future questions about the toughness of the shield tank materials.
The NRC has, with BNL assistance, recently completed a verification of the input neutron flux levels. The BNL analysis was substantially in agreement with the data submitted with the original Part 21 notifi-cation, as nodified by additional information provided in response to staff questions. BNL noted that the original (licensee) calculations were, in general, conservative. However, the NRC desired actual field data from operating reactors to use as a " benchmark" for further con-firmation of the calculations.
Mr. Serpan of Reactor Safety Research noted that such " benchmark" data are now available, in the form of flux and spectrum measurements from the cavity of Arkansas Nuclear One, Unit 1 Therefore, the decision was made to utilize the available information as a means of verifying the calculations.
SNL, under the direction of the Reactor Safety Branch /
00R, will be responsible for this comparison.
4 2907250 cog 452 002
D. G. Eisenhut May 25, l' 79 Meanwhile, NRL will commence work on the crediction of damage calculations (NDTT shift) for A-537 steel, which was the material of interest in the original submittal. Metallurgical data on this material are available in an NRL-published report.
The NRC staff will begin to gather infor-mation from affected utilities. Such information will include shield tank materials and thicknesses.
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Richard r. Snaider Systematic Evaluation Program Branch Division or~ Operating Reactors
Attachment:
As state <1 4S2 J0:
ATTACHMENT LIST OF ATTENDEES NRC R. Snaider F. Litton R. Johnson B. Morris C. Serpan K. Hoge W. Hazelton S. Weiss R. Klecker BNL J. Carew NRL J. Sprague R. Hawthorne Ax
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