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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38<br />
HPCI system is actu<strong>at</strong>ed only when level is more than 0.25 m (10 in.)<br />
below the 13.4-m (528-in.) lower limit of control room indic<strong>at</strong>ion<br />
under <strong>St<strong>at</strong>ion</strong> Blackout conditions. Suction for both systems is from<br />
the condens<strong>at</strong>e storage tank (CST). The oper<strong>at</strong>ors actu<strong>at</strong>e HPCI and<br />
RCIC 1 min. after the <strong>blackout</strong>.<br />
3. Following 1 min. of autom<strong>at</strong>ic SRV actu<strong>at</strong>ion, reactor pressure is con<br />
trolled by remote-manual actu<strong>at</strong>ion of the SRVs. Control range dur<br />
ing the first hour is 7.52 MPa (1090 psia) to 6.31 MPa (915 psia).<br />
After 1 hour the reactor is depressurized to about 0.79 MPa (115<br />
psia) <strong>at</strong> a r<strong>at</strong>e consistent with the 55.6°C/h (100°F/h) cooldown r<strong>at</strong>e<br />
limit. After depressuriz<strong>at</strong>ion, pressure is controlled between 0.62<br />
MPa (90 psia) and 0.86 MPa (125 psia).<br />
Manual sequential SRV action is used to spread SRV discharge around<br />
the suppression pool and thereby avoid localized he<strong>at</strong>ing of the pool.<br />
4. The assumed reactor system leakage into the drywell is 0.0089 m /s<br />
(4 gpm).<br />
7.3.2 Normal Recovery — Results<br />
Results for normal recovery are shown on Figs. 7.1 through 7.9.<br />
Each system variable is discussed below.<br />
7.3.2.1 Reactor vessel pressure. Figure 7.1 shows reactor vessel<br />
pressure. During the first minute, reactor pressure cycles between 7.72<br />
MPa (1120 psia) and 7.38 MPa (1070 psia) on autom<strong>at</strong>ic SRV actu<strong>at</strong>ion.<br />
After 1 min. the oper<strong>at</strong>or opens one SRV to lower pressure to 6.31 MPa (915<br />
psia). Since the HPCI is running, pressure continues to decrease to below<br />
6.21 MPa (900 psia) until the HPCI is shut down. During the first hour a<br />
single SRV is cycled open and shut seven times to keep pressure in the de<br />
sired range.<br />
After one hour, the depressuriz<strong>at</strong>ion begins. Initially, intermittent<br />
oper<strong>at</strong>ion of one SRV is sufficient to meet the target depressuriz<strong>at</strong>ion<br />
r<strong>at</strong>e [i.e., 55.6°C (100°F)/h], As pressure decreases, the r<strong>at</strong>e of de<br />
crease begins to slow until finally an additional SRV is opened. For<br />
choked flow of dry steam, the mass flow r<strong>at</strong>e is linearly proportional to<br />
reactor pressure . Therefore an extra valve is required <strong>at</strong> the lower pre<br />
ssure. When depressuriz<strong>at</strong>ion is complete, the oper<strong>at</strong>or controls pressure<br />
between 0.62 and 0.86 MPa (90 and 125 psia).<br />
After depressuriz<strong>at</strong>ion, the steam flow through one SRV is nearly<br />
equal to the core steaming r<strong>at</strong>e, resulting in much slower pressure change.<br />
Under these conditions, the most rapid pressure change is caused by the<br />
RCIC system. When RCIC comes on the 600 gpm injection of cold w<strong>at</strong>er tends<br />
to lower the core steaming r<strong>at</strong>e, causing pressure to decrease. This ef<br />
fect can be seen in Fig. 7.1. At 256 min., the RCIC comes on, reducing<br />
pressure until the open SRV is shut. When the RCIC is shut off 23 min.<br />
l<strong>at</strong>er, pressure increases rapidly until the SRV is reopened.<br />
Steam flow from the reactor vessel is shown in Fig. 7.2. The large<br />
spikes are due to SRV actu<strong>at</strong>ion. Also included in the total steam flow<br />
are the smaller amounts of steam flowing to the RCIC and HPCI turbines<br />
when they are running.