ML20053A276
| ML20053A276 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/11/1982 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20053A183 | List: |
| References | |
| EP-6-1, NUDOCS 8205250164 | |
| Download: ML20053A276 (7) | |
Text
.-
EP-6-1 Fort Calhoun Station Unit No. 1
(;g EMERGENCY PROCEDURE EP-6 Uncontrolled Heat Extraction A.
PURPOSE To describe the procedure to be taken in the event of an Uncon-trolled Heat Extraction.
If the cause of the uncontrolled heat e:ttraction is a rupture with a simultaneous complete loss of 0FF-SITE AC power, follow'EP-29.
B.
SYMPTOMS 1.
Any one or more of the following alarms may be present:
a.
Pressurizer level Lo b.
Pressurizer Level Lo-Lo c.
Pressurizer pressure Lo d.
Pressurizer safety injection signal Lo-Lo pressure
.7, e.
TM/ Low Pressure channel trip
(:?:!
f.
Low pressure SG-2A channel trip g.
Low pressure SG-2B channel trip h.
SGLS circuit "A" actuated j
i.
SCLS circuit "B" actuated 1
j.
Reactor trip k.
Safety injection actuation channel A 1.
Safety injection actuation channel B 2.
Any one or more of the following indications may be present:
l a.
Rapid reduction in steam generator pressure b.
Increasing containment pressure c.
Reduction in RCS temperature causing a corresponding l
decrease in pressurizer level and pressure d.
Sceam generator level oscill-* ions g
e.
Steam flow-feed flow mismatch g
MAN 111982 R14 5-11-82 8205250164 820517 PDR ACOCK 05000285 p
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EP-6-2 B.
SYMPTOMS (Continued) 2.
f.
Change in generator electrical output g.
Noise if a steam line/ feed line rupture occurs outside containment.
C.
IMMEDIATE ACTION 1.
Depress the manual reactor trip pushbutton.
Insure that all regulating and shutdown CEA's have been fully inserted and that reactor power is decreasing.
2.
Insure trubine has tripped and all stop and intervept valves closed.
3.
Insure generator breakers 4 and 5 have tripped and that the generator field breaker has opened.
4.
Shut the MSIV's (Main Steam Isolation Valves).
5.
Secure the main feedwater pumps.
6.
Insure all available charging pumps are operating.
D.
FOLLOW-UP ACTION k
1.
If the Engineered Safety Features System was actuated:
a.
Insure safety injection flow is being delivered.
b.
Insure containment spray flow exists if CPHS occurred.
c.
Insure emerger.cy boration of the RCS is taking place.
d.
Trip all operating reactor coolant pumps.
2.
If MSIV closure did not terminate the transient:
a.
Find the affected steam generator (affected steam generator will experience a more rapid pressure de-crease while the unaffected will be at the saturation pressure corresponding to the RCS temperature.
b.
Secure all feedwater flos to the affected steam generator, c.
Verify that auxiliary feedwater flow is being delivered to the unaffected steam generator and maintain normal level (greater than 80% level if the auxiliary feedwater nozzles are being used).
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l D.
FOLLOW-UP ACTION (Continued)
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- n 3.
If CIAS occurred, and if CCW pump discharge pressure is greater than 133 psig and CCW pump motor amps are less than 300A, restore j
CCW flow to the RC pumps by placing HCV-438A/438B/438C and 438D l
control switches in the " pull to Over-Ride" position.
CAUTION:
Indicated water level relative to actual water level may j
be in error due to the effects of varying fluid pressure j
and flashing of reference leg to steam on the water level l
measurements.
Reference:
Technical Data Book - Steam Generator Level Correction Curves, III.3.a.
through III.3.g.
l 4.
Insure RCS pressure is being maintained to achieve at least i
50 F subcooling.
RCS subcooling should not exceed 200*F.
l a.
Throttle auxiliary feedwater flow to the unaffected l
steam generator (s) to aid in RCS pressure recovery.
b.
Insure main feedwater isolation valves closed (HCV-1385, 1386) if CIAS occurred.
l 5.
If containment pressure is below 3 psig and containment air cooling /
l filtering units are operating, see Section 3.a of EP-35 to reset CSAS.
CAUTION:
Indicated water level relative to actual water level may be in error due to the effects of varying fluid pressure and 4
flashing of reference leg to steam on the water level measurements.
l
Reference:
Technical Data Book, Pressurizer Level Correction Curves (III.1.b. - III.1.e. ).
4 6.
Establish a water level in the pressurizer above the heater cutoff 3
level and verify that the RCS is 50 F subcooled.
Secure the charging pumps to prevent the RCS pressure from exceeding that allowed by the cooldown curves.
Proceed to EP-35 to terminate safety injection.
I j
CAUTION: The charging and HPSI pumps are capable of overpressurizing the RCS during a steamline break. The charging and HPSI pump operation should be regulated such that the cooldown i
curves of the Technical Specifications are not violated.
If the 100 F/hr cooldown rate curve is violated, RCS i
pressure shall be decreased to bring the pressure within l'
the cooldown curve limits.
7.
Monitor reactor coolant system parameters to verify natural circulation.
This circulation can be verified by the following:
O Core exit thermocouple temperatures are stable and at least 50'F a.
Q below the saturation temperature for the existing RCS pressure, I
as indicated on subcooled margin monitor, hgy 111982 R14 5-11-82
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EP-6-4 D.
FOLLOW-UP ACTION (Continued)
Da (IT' 7.
b.
Core exit thermocouples and RCS hot leg temperatures reading approximately the same, c.
A 6T across the core of not greater than 50*F; yet representative to the decay heat power level.
Immediately after a 100% trip it is anticipated to be <20'F, 8.
If MSIV closure isolated the leak, attempt to isolate the com-ponent which caused tha heat extraction.
9.
Borate to cold shutdown margin unless emergency boration has already taken place.
10.
Decay heat can be removed by performing any one or more of the following:
a.
Operation of the steam driven auxiliary feedwater pump (FW-10) u,th steam being supplied from unaffected steam generator (s).
NOTE:
If A steam generator has the rupture, ensure YCV-1045A is closed and open YCV-1045B.
If B steam generator has the rutpure, ensure YCV-1045B is closed and open YCV-1045A.
C79 b.
Periodic remote operation of the power operated steam generator safety valve on the unaffected steam genera-tor (s).
c.
Opening the main steam isolation valve bypass on the un-affected steam generator and operation of the atmospheric dump valve, or steam bypass valve if condenser vacuum is satisfactory.
Gland seal must be re-established before steam bypass will be available.
NOTE 1:
If steam line rupture was isolated by MISV closure, heat could be removed by modulated opening of the main steam isolation valve bypasses which will blow steam through any rupture.
NOTE 2:
CPilS or SGLS closes the MSIV's and MSIV by-passes.
Either the accident signal must be reset or power removed from the MSIV bypass valve actuator before bypass valve operation is possible, d.
Initiation of steam generator blowdown.
NOTE:
CIAS secures blowdown. Only after accident i,,..,'.h relays are reset can blowdown be restored.
~
R14 5-11-82 MAY 111982 j
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m EP-6-5 D.
FOLLOW-UP ACTON (Continued)
(h 11.
Refer to EP-1 for applicable follow-up actions.
12.
If radioactivity above normal background is present in the steam generator secondary sides, initiate the Site Emergency Plan and ensure that the Control Room is tenable by:
a.
Checking all access doors closed.
b.
Ensure that the control room ventilation system is in the filtered air makeup mode by placing the mode switch on the ventilation panel in the filtered air makeup mode.
c.
Ensure a positive pressure exists in the Control Room (don respiratory protection if a positive pressure does not exist).
13.
Refer to EP-35 for safeguards reset guidelines.
14.
Implement the Emergency Plan if appropriate.
Refer to EPIP-OSC-1 for emergency classification and to EPIP-OSC-2 for the method of implementing the Emergency Plan.
e Vd R14 5-11-82 MAY 111982
EP-6-6 E.
DISCUSSION
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<'M The major objective for the uncontrolled heat extraction is to minimize the RCS cool-down and to ensure adequate reactor shutdown margin. To achieve this it is important to:
1.
Ensure that the Main Steam Isolation Valves (MSIV's) are closed. This will terminate the transient if the uncon-trolled heat extraction occurred downstream of the MSIV's.
Closing the MSIV's ensures that only one steam generator can contribute to an uncontrolled heat extraction if the uncontrolled heat extraction is occurring upstream of the MSIV's.
2.
Secure the main feedwater pumps.
This will, terminate an uncontrolled heat extraction transient due to excessive feedwater addition.
Also, if an uncontrolled heat extrac-tion occurs upstream of the main steam isolation valves, the affected steam generator will have to be boiled dry to terminate the transient.
If feedwater flow continues to the affected steam generator the transient will continue.
3.
Verify that the RCS boron concentration is such that at least the cold shutdown condition is assurred.
Emergency boration by way of the CVCS can be utilized if required.
Emergency boration is automatically actuated if the Engineered Safety Features System is actuated (SIAS).
/
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