ML17192A672
| ML17192A672 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/12/1980 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17192A611 | List: |
| References | |
| DGA-2, NUDOCS 8005080492 | |
| Download: ML17192A672 (5) | |
Text
il 8oososo4-'1').._
LOSS OF COOLANT (SLOW LEAK)
A.
. SYMPTOMS
- 1.
902(3)-3 Alarms
- a.
Rx Bldg. Vent Channel A(B) Hi Radiation
- b.
Isolation Condenser Vent Hi Radiation
- c.
Rx Bldg. Ch A or Ch B High Radiation
- d.
Isolation Condenser High Temperature
- e.
Turbine Bldg. High Radiation
- f.
Isolation Condenser Level Hi/Lo
- g.
Area High Temperature
- 2.
902(3)-4 Alarms
- a.
Drywell Equipment Sump High Level
- b.
Drywell Floor Drain Sump High Level DGA-2 Revision 2 January 12, 1980
- c.
Drywell Equipment Drain Sump High Temperature
- d.
Drywell Floor Drain Pump High Discharge Flow
- e.
Rx Bldg. Floor Drain Sump A(B) High Level
- f.
Turbine Bldg. Equipment Drain Sump High Level
- g.
Rx Bldg. Equipment Drain Tank High Level
- h.
Rx Bldg. Equipment Drain Tank High Temp L
Valve Leak Detector System High Temp
- 3.
902(3)-5 Alarms Main Steam Line Leakage 1 of 5 AopRn\\1r-o
\\ *--* 'i ~
JAN 12'80 0.0.S.R.
I
lFL>n-l Revision 2
- 4.
902(3)-6 Alarms
\\
- a.
Cond Booster Pump' Suction Low Press
- b.
Condensate Pump Discharge Low Press
- c.
RFP Suction Low Pressure
- 5.
902(3)-7 Alarms Air Ejector 2A(2B) Stm Low Press
- 6.
Other symptoms:
- a.
Area temperature increasing.
(Drywell temperature will increase approximately 1° for a 2 gpm leak.)
- b.
Increase in area radiation levels.
- c.
Noise of high pressure steam escaping.
- d.
Increase in air sample activities.
- e.
Water accumulations.
- f.
Increasing drywell pressure.
(Drywell pressure will increase approximately
.03 psig for a 1 gpm leak.)
- g.
Increasing RBCCW and TBCCW outlet temperatures.
(RBCCJ temperature change across drywell coolers will increase approximately 5°F for 3 gpm steam leak or a 7.5 gpm liquid leak.)
- h.
Increase in water flows to radwaste.
B.
AUTOMATIC ACTIONS
- 1.
Possible Group I, II, III, IV or V Isolation.
- 2.
Possible Reactor Scram.
- 3.
Possible Load Reduction.
2 of 5 APPROVED JAN 12 '8(i D.O.S.R.
C.
IMMEDIATE OPERATOR ACTIONS DGA-2 Revision 2
- 1.
Maintain water level with Feedwater Control System.
MONITOR level by using more than one indication.
NOTE A steam* environment may damage safety-related equipment, cause erratic indications or result in inadvertent trips or initiations.
Such results must be evaluated for safety significance.
CAUTION Do not dispatch personnel to an.area of a*suspected pipe break without consideration of adverse environments.
- 2.
Notify Shift Supervisor.
- 3.
Attempt to locate and isolate the leak.
- 4.
Evacuate personnel from the affected area.
- 5.
IF drywell pressure*increases.to +2 psig, follow Lo"ss of Coolant (Break Inside Drywell), DGA-1.
- 6.
IF a primary containment isolation occurs with less than 2 psig drywell pressure, follow Loss of Coolant (Break Outside Drywell), DGA-3.
D.
SUBSEQUENT OPERATOR ACTIONS CAUTION The reactor must be in cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the leakage to the primary containment from an unidentified source exceeds 5 gpm or if the total leakage, the floor drain and equipment drain sump combined discharge exceeds 25 gpm.
Refer to Tech Specs Section 3.6.D. Coolant Leakage.
- 1.
MONITOR leakag~ rate.and waier level by all available indications.
- 2.
MONITOR suppression pool temperature and initiate contain-ment cooling before water tempera.ture reaches 95°F.
3 of 5
- i-: **.. ~* !;
APPRn\\1r::o
\\'.J..,,_
~N 12'80 0.0.S.R.
-* **~-r:--.-.------*-------'
- 3.
- 4.
. 5.
- 6.
Limit access to the affected area.
DGA-2 Revision 2 Initiate radiation protection procedures to monitor the plant and environs
- Ensure Technical Specifications release limits are not violated.
Restore to service any ECCS components which are available but not in service.
Do not turn OFF any ECCS without assurance that there is no potential for inj~ry to personnel, for off-site releases above Technical Specifications limits or for damage to equipment.
- 7.
Evaluate the effect of operating without the isolated system or component.
- 8.
Evaluate the necessity for shutdown.
E.
DISCUSSION This procedure assumes a loss of coolant at a rate small enough that neither a reactor scram occurs on high drywell pressure no_r a primary containment isolation condition exists.
If the loss of coolant is large enough to produce a reactor scram and/or a primary containment isolation, on high drywell pressure, then the operator should follow Loss of Coolant (Break Inside Drywell), DGA-1.
If the loss of coolant is large enough to produce a primary containment isolation but dryw~ll pressure is below 2 psig, then the operator should follow Loss of Coolant (Break Outside Drywell), DGA-3.
A small steam leak can create an emergency condition that can lead to a plant shutdown due to high airborne radio-activity release.
A steam leak may cause a plant shutdown due to damage of equipment, even though no radioactivity hazard is present.
Area temperature monitors detect changes in temperature in various areas of the plant and printout on Panels 902-2(903-2) and 902-21(903-21).
The stack gas radiation levels are monitored by recorders in the Control Room.
These recorders will show an increase in stack radioactivity if a leak is substantial.
A small steam leak will have little effect on the monitor since the activity will be diluted with ventilating air before it reaches the stack.
.4 of 5
-~'
APPROVED JAN 12'80 o.o.s.R.
I I I J.Furi-Z.
Revision 2
- ' e I
Abrupt increases in steam 1or feedwater flows without turbine power inc'reases will indic:ate possible leaks.
I I
A high reactor level indidates a oossible steam leak due to decrease in pressure causibg sweli of the coolant.
I I
s of s (FINAIJ
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APPROVED JAN 12'80 o.o.s.R.
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