Station blackout at Browns Ferry Unit One - Oak Ridge National ...
Station blackout at Browns Ferry Unit One - Oak Ridge National ...
Station blackout at Browns Ferry Unit One - Oak Ridge National ...
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As a portion of their review of the draft of this report, the Elec<br />
trical Engineering Branch <strong>at</strong> TVA performed a b<strong>at</strong>tery capacity calcul<strong>at</strong>ion<br />
which shows th<strong>at</strong> the unit b<strong>at</strong>teries <strong>at</strong> the <strong>Browns</strong> <strong>Ferry</strong> plant can be ex<br />
pected to provide power for as long as seven hours under st<strong>at</strong>ion <strong>blackout</strong><br />
conditions. Since a b<strong>at</strong>tery life of four hours was assumed for the calcu<br />
l<strong>at</strong>ions of this work, a new Appendix G has been added in which all of the<br />
possible failure modes other than b<strong>at</strong>tery exhaustion th<strong>at</strong> were considered<br />
in Sections 3, 7, and 8 are re-examined for applicability to the period<br />
between four and seven hours after the inception of a <strong>St<strong>at</strong>ion</strong> Blackout.<br />
The magnitude and timing of the release of the fission product noble<br />
gases and various forms of iodine to the <strong>at</strong>mosphere are discussed in<br />
Volume 2. This includes the development of release r<strong>at</strong>e coefficients for<br />
the escape of these fission products from fuel as a function of tempera<br />
ture, specific<strong>at</strong>ion of the various chemical forms, determin<strong>at</strong>ion of the<br />
optimum str<strong>at</strong>egy for the modeling of precursor/daughter exchange, and the<br />
study of the particular auxiliary systems involved to determine the appli<br />
cable fission product release p<strong>at</strong>hways. These results are incorpor<strong>at</strong>ed<br />
into a vehicle for the calcul<strong>at</strong>ion of the transport of the individual fis<br />
sion products from the reactor core, through the primary and secondary<br />
containments to the <strong>at</strong>mosphere, control volume by control volume.<br />
The primary sources of inform<strong>at</strong>ion used in the prepar<strong>at</strong>ion of this<br />
report were the <strong>Browns</strong> <strong>Ferry</strong> Nuclear Plant (BFNP) Final Safety Analysis<br />
Report (FSAR), the Nuclear Regul<strong>at</strong>ory Commission BWR Systems Manual, the<br />
BFNP Hot License Training Program Oper<strong>at</strong>or Training Manuals, the BFNP <strong>Unit</strong><br />
1 Technical Specific<strong>at</strong>ions, the BFNP Emergency Oper<strong>at</strong>ing Instructions, and<br />
various other specific drawings, documents, and manuals obtained from the<br />
Tennessee Valley Authority*. Additional inform<strong>at</strong>ion was g<strong>at</strong>hered by means<br />
of one visit to the BFNP and several visits to the TVA Power Oper<strong>at</strong>ions<br />
Training Center <strong>at</strong> Soddy-Daisy, Tennessee. The excellent cooper<strong>at</strong>ion and<br />
assistance of Tennessee Valley Authority personnel in the g<strong>at</strong>hering of in<br />
form<strong>at</strong>ion necessary to this study are gr<strong>at</strong>efully acknowledged.<br />
*The setpoints for autom<strong>at</strong>ic action used in this study are the<br />
safety limits as given in the FSAR. In many cases these differ slightly<br />
from the actual setpoints used for instrument adjustment <strong>at</strong> the BFNP be<br />
cause the instrument adjustment setpoints are established so as to provide<br />
margin for known instrument error.