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Station blackout at Browns Ferry Unit One - Oak Ridge National ...

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16<br />

The curves of Fig. 3.3 show th<strong>at</strong> the maximum drywell average temper<br />

<strong>at</strong>ure can be kept below 148.9°C (300°F) provided th<strong>at</strong> the oper<strong>at</strong>or takes<br />

action to depressurize within one hour following the loss of drywell cool<br />

ers concomitant with a <strong>St<strong>at</strong>ion</strong> Blackout.* A depressuriz<strong>at</strong>ion <strong>at</strong> the<br />

Technical Specific<strong>at</strong>ions limit of 55.6°C/h (100°F/h) will produce a grad<br />

ual reduction of the drywell ambient temper<strong>at</strong>ure; a rapid depressuriza<br />

tion will produce a faster drywell temper<strong>at</strong>ure reduction, but is probably<br />

not necessary. Certainly, if the oper<strong>at</strong>or perceives developing difficul<br />

ties with the in-drywell equipment such as the relief valve solenoids, he<br />

should convert an ongoing 55.6°C/h (100°F/h) depressuriz<strong>at</strong>ion into a more<br />

rapid one.<br />

Summary. Assuming no independent secondary failures of equipment,<br />

reactor vessel level control and pressure control can be maintained during<br />

a <strong>St<strong>at</strong>ion</strong> Blackout for as long as the DC power supplied by the unit b<strong>at</strong><br />

tery lasts. This is expected to be a period of from four to six hours,<br />

and this portion of the <strong>St<strong>at</strong>ion</strong> Blackout severe accident sequence is<br />

graphically displayed with commentary in Section 7. If AC power is re<br />

gained <strong>at</strong> any time during this period, a completely normal recovery would<br />

follow.<br />

If AC power is not regained, and DC power is lost, remote-manual op<br />

er<strong>at</strong>ion of the primary relief valves would no longer be possible and the<br />

reactor vessel pressure would increase to 7.722 MPa (1105 psig), the low<br />

est setpoint for autom<strong>at</strong>ic actu<strong>at</strong>ion of the relief valves. Thereafter,<br />

the reactor vessel pressure would cycle between 7.722 and 7.377 MPa (1105<br />

and 1055 psig) while the vessel level steadily decreased because injection<br />

capability would be lost as well. The sequence of events following the<br />

loss of injection capability is described in Sections 9 through 11.<br />

*If the backup HPCI system were used for injection, the average re<br />

actor vessel pressure after depressuriz<strong>at</strong>ion would have to be maintained<br />

<strong>at</strong> about 1.14 MPa (150 psig), which corresponds to an average s<strong>at</strong>ur<strong>at</strong>ed<br />

liquid temper<strong>at</strong>ure of 185°C (365°F). This is only 15°C (25°F) higher than<br />

the average temper<strong>at</strong>ure associ<strong>at</strong>ed with RCIC oper<strong>at</strong>ion and would not<br />

significantly increase the drywell temper<strong>at</strong>ures shown in Fig. 3.3.

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