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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.

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