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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36<br />
7. COMPUTER PREDICTION OF THERMAL-HYDRAULIC<br />
PARAMETERS FOR NORMAL RECOVERY<br />
7.1 Introduction<br />
The purpose of this chapter is to present the results of BWR-LACP<br />
calcul<strong>at</strong>ions (see Sect. 4) of system behavior for two different portions<br />
of the <strong>St<strong>at</strong>ion</strong> Blackout:<br />
1. Normal Recovery: DC power from the unit b<strong>at</strong>tery remains available<br />
during this period; therefore RCIC and HPCI injection flows are assumed<br />
available throughout, and<br />
2. Loss of 250 vdc B<strong>at</strong>teries: The b<strong>at</strong>teries are assumed to fail after<br />
four hours, causing failure of RCIC and HPCI injection, ultim<strong>at</strong>ely leading<br />
to uncovering of the core about eight hours after the <strong>blackout</strong>.<br />
The normal recovery portion of the <strong>St<strong>at</strong>ion</strong> Blackout is discussed in<br />
detail in Sects. 3 and 6. Oper<strong>at</strong>or actions assumed here are consistent<br />
with those sections. Results were calcul<strong>at</strong>ed to five hours* for normal<br />
recovery in order to provide some overlap with the MARCH code severe ac<br />
cident calcul<strong>at</strong>ions (see Sects. 9 and 10), which assume th<strong>at</strong> the boil-off<br />
begins after four hours from a fully pressurized condition. The Loss of<br />
250 vdc B<strong>at</strong>teries results are given in this section in order to provide an<br />
estim<strong>at</strong>e of system behavior possible after loss of dc power if the plant<br />
is depressurized during the normal recovery period.<br />
7.2 Conclusions<br />
Major conclusions drawn from the calcul<strong>at</strong>ed results are given below,<br />
succeeded by a detailed discussion of code input assumptions and transient<br />
results.<br />
7.2.1 Normal Recovery — Conclusions<br />
If power were recovered within five hours of the inception of the<br />
<strong>St<strong>at</strong>ion</strong> Blackout, a normal recovery would be possible. System parameters<br />
are within acceptable ranges after five hours:<br />
1. The 250 vdc b<strong>at</strong>teries, by assumption, last the full five hours.<br />
2. Reactor vessel level is within the normal control range, about 5.08 m<br />
(200 in.) above the top of active fuel.<br />
3. Reactor vessel pressure is being controlled <strong>at</strong> about 0.69 MPa (100<br />
psia).<br />
4. About 354 m3 (93,500 gal.) of w<strong>at</strong>er have been pumped from the Con<br />
dens<strong>at</strong>e Storage Tanks, which had an assured capacity of 511 m3<br />
(135,000 gal.) before the <strong>blackout</strong>.<br />
5. Suppression pool temper<strong>at</strong>ure is about 82°C (180°F), but this should<br />
not be a problem for the T-quencher type of SRV discharge header pip<br />
ing.<br />
6. Containment pressures are elev<strong>at</strong>ed to about 0.17 MPa (25 psia), well<br />
below the 0.53 MPa (76.5 psia) design pressure.<br />
*These results are extended to seven hours in Appendix G.