ML19211C525
| ML19211C525 | |
| Person / Time | |
|---|---|
| Issue date: | 09/24/1979 |
| From: | Meyer R Office of Nuclear Reactor Regulation |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-09, REF-GTECI-SY, TASK-A-09, TASK-A-9, TASK-OR NUDOCS 8001110594 | |
| Download: ML19211C525 (2) | |
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30, UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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September 24, 1979 MEMORANDUM FOR:
A. Thadani, Task Manager, A-9 FROM:
R. O. Meyer, Section Leader Reactor Fuels Section, Core Performance Branch, DSS
SUBJECT:
SUBMITTAL OF INFORMATION REQUIRED FOR VERIFICATION OF ADEQUACY OF ATWS ALTERNATIVE #3 FIX Perusal of (a) your recent Ssptamber 13 memoranda to Dr. Hanauer re-garding sumaries of meetings held with the various LWR vendors, along with (b) vendor comunications, such as the September 13 letter from James H. Taylor (B&W) to Dr. Hanuaer, prompt us to ask you to take whatever action is necessary to ensure that the vendors will submit adequate analyses of the estimated fuel failure (including PCI) for their respective worst-case scenarios. We are concerned that the afore-mentioned meeting sumaries (NRC/CE meeting, NRC/BWR 3-Owners /GE meeting, and NRC/W-Owners meeting) do no mention fuel failure estimates at all.
And, where fuel failure is mentioned in vendor responses (as in the B&W letter to Dr. Hanauer), it is in terms of estimates of the number of fuel pins experiencing DNB only.
As we have unswervingly reiterated both verbally and in numerous memoranda, we believe that there is a significant probability for PCI failure during power-increasing ATWS events. We, therefore, strongly urge you to ensure that the PWR vendors, in particular, are aware of the fact that (a) we expect them to provide estimates of the number of rods that would fail due to PCI during worst-case power-increasing ATWS events, and (b), if acceptable estimates are not provided, we will make the estimates ourselves, using the PCI model PROFIT. As we have indicated in previous ATWS staff positions, the BWR fuel failure analysis situation is in somewhat better shape, in the sense that we believe that the number of rods predicted to be in boiling transition will approximate the number that fail due to overheating and PCI combined.
...f&- ?-
-ea.W" Ralph 0. Meyer, Leader Reactor Fuels Section Core Perfonnance Branch Division of Systems Safety cc: See next page
Contact:
Mike Tokar, x27603 1736 197 go 1110 59 o
A. Thadani 2
cc:
S. Hanauer M. Aycock R. Mattson F. Schroeder R. Tedesco R. Denise J. Knight R. Bosnak R. Novak M. Srinivasan A. Thadant T. Su L. Ruth M. Tokar F. Cherny K. Desai D. Vassallo D. Ross S. Varga E. Eisenhut R. Grimes' V. Noonan K. Parczewski H. Vander Molen D. Muller F. Akstulewicz L. Soffer S. Keblusek B. Youngblood S. Coplan J. Norberg, OSD E. Jakel, OELD H. Richings R. Meyer K. Kniel 1736 198