ML19291C992
| ML19291C992 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/30/1966 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011170865 | |
| Download: ML19291C992 (2) | |
Text
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DEC 3 0 W Docket Ec. 50-29 Yankee Atomic Electric C apany 41 Stuart Street Bestcm, Massachusetts 02116 Attention: Mr. Ecger J. Coe Vice President Gentlemen:
Current designs for high power nuclear reacters incorporate extensive previsicas for emergemey ecre cooling in the event of a major rupture in the primary coolant system. Iba purposes of these systems are two-fold:
te limit the please cf fission products frca the ecre and to prctect and maintain containment integrity in the event of such a pratulated accident. 616nificaut advances have recently been made in the techniques for analyring core behavior folleving such a rupture, in order to establish perfermance requirements fcr erergency ecre cooling systems and to evaluate the edequecy and reliability of such systems.
We have recently discussed this matter as it relates to the Yankee resetcr with representatives of your ccupany and hope that you will be able to assign top priority to the nyiew of Yardrie emergency ecre cooling prcvisicas in the light of considersticas being given to projects now in the licensing stage of revies.
In addition to the eensideration that needs to be given to the present emergency core cooling provisions fcr the Yankee facility to determine the need fer additional prerisions to limit the release of fission prc4ucts frca the core in the event of a majcr rupture in the primary cooling system, we believe that you should perform suitable analyses to detemine the degree to which emergency core cooling must be relied upon to maiatain containment integrity.
These smalyses should include, but not necessarily be limited to, the following considerations:
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Analysis of the less of ecolant from the com, for a sufficiant number of piping bnak stres (assuming that the breaks occur very npidly) to define the limiting ecedition, and to ahon the ultimate dissipation of all heat loads sad the effect of the limiting break tire ce naetor vessel integrity. This analysis should ezelude any cooling cf the cora from sources external tc the pressure vessel. It should imelude the thermal and mechanical history of the ecre, includlag decay hast, effective best load of the eore and load en the resetor vessel due to the redistributice of fissica products, and potential metal-water reactions. En affect of significant variations in applicable parameters abould also be included tc show the margins avs.ilable in the neults. Should you ecmelude from the above that the integrity cf the reactor vessel may be jeoparfired, you should ecutinue your analysis to shew the capshility that.v.y be available in your plant from etber eocling systems and components that might be suitable and synil-able fer pnserving the integrity cf ycur nectcr vessel.
2.
Analyses te detersine the performance nquinments fcr systems to prevent ccre moltdown folleving the Icss cf coelant accident for all potential primary coolant piping 1reaks and t aak leesticas. It is also requested that you infera us of any action you plan tc take es a result cf these anaJyses.
It is requested that you infcrm us when a repcrt cf the naults of the abeve analysis will be available to us.
The repcrt should imelude sufficient inforestice, such as mathematical models, assumpticas and their justificatico, computer codes, etc., te permit us te make an independent assessment of your analysis ama its results.
If you believe it would be helpful to discuss this preblem further, we would be happy to wet with you at your ccavenience.
D1ctribution Pub. Loc-6.
SiDeerely yours, Formal y
sui >Iil i erfgine signs ty DEL Eeading Fete r.. e v.
R&?ESE Beading C. Henderson, EED Peter A. Merris, Director bec:
P. A. Morris, DEL Division of Rosetcr Licensing E. G. Case, DEL ACES (18)
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