ML20049H836
| ML20049H836 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/16/1980 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20049H835 | List: |
| References | |
| D.2, NUDOCS 8203040204 | |
| Download: ML20049H836 (5) | |
Text
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10/16/80 Rev. 7 D.2 REACTOR / TURBINE TRIP 1.0 PURPOSE This procedure provides the necessary steps to be performed following a reactor / turbine trip.
2.0 DESCRIPTION
.1 Any of the following will cause a reactor trip:
.1 Overpower (Neutron Flux)
.2 Overpower based on RC flow and imbalance
.3 C1.rpv es based on RCP power monitors
.4 RCS pressure high
.5 RCS pressure low
.6 RCS pressure / temperature comparison
.7 RCS Th high
.8 Reactor Building Pressure high
.9 Turbine / generator trip
.10 Main FWP A & B low discharge pressure
.2 Any of the following will cause a turbine trip:
.1 1.ow bearing oil pressure
.2 Turbine overspeed
.3 Condenser vacuum
.4 Thrust wear detector
.5 SCOTS trip
.6 Generator / electrical trips
.7 Reacto trip
.8 Turbine motoring (no steam flow)
D.2-1 Rev. 5 8203040204 820225 PDR ADOCK 05000312 P
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1.0 PURPOSE (Continued)
.2
.9 Mkaual trip button
.10 EH power failure
.11 Gen H temperature high 2
3.0 SYNPTOMS
.1 Any two "RPS Channel-Trip" annunciators.
.2 Safety and Control Rods individual and group IN lights on.
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.3 Rapid decrease in indicated neutron level.
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.4 Turbine " Auto Stop 011 Trip" annunciator.
.5 Turbine throttle / governor valves shut.
.6 Generator OCB's (220 and 230) open.
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.7 Secondary code reliefs and ADV's exhausting steam.
4.0 AUTOMATIC ACTIONS
.1 All safety and control rods drop into core.
.2 Generator OCB's open.
Site electrical loads transfer from l
auxiliary to startup transformers.
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.3 Turbine bypass valves establish steam header pressure at 1000 psi and Reactor Tave %545 F.
.4 Throttle stops and governor valves close.
.5 The following pumps start:
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.1 AC oil pump
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.2 Seal oil pump
.3 Standby condensate pump D.2-2 Rev. 5
I 5.0 I)O!EDIATE OPERATOR ACTION NOTE:
Any parameter marked with an asterisk (*)
shall be verified when step 6.1 is performed.
.1*
Verify all safety and control rods are at their IN limit and neutron level is decreasing.
.2 Verify the generator OCB's exciter breakers are open and all site loads afe transferred to the startup transformers.
.3*
Yerify the turbina bypass system is controlling header pressure at 1000 peig (T y. %545'F).
a
.4 Close the 1,eedown isolation valve SFV 22009.
.5*
Verify pressurizer level 150 + 50 inches.
If HPI is initiated automatically due to low RCS pressure, verify all RCP's tripped.
.6*
Verify BCS is subcooled using T-SAT meter indication.
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.7 Verify the following pumps start:
.1 AC oil pump.
.2 3eal Oil pump.
.3 Standby Condensate pump.
6.0 SUBSEQUENT OPERATOR ACTION
.1 Immediately upon completion of the necessary inunediate manual actions of "Immediate Operator Actions" section, alternate instrument channels shall be checked to confira key parameter readings where available.
.2 Notify Shift Supervisor, System Dispatcher and plant personnel.
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.3 In the event of a loss of main WP's or all RCP's, verify t.he l
following:
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.1 Auxiliary NP's start.
.2 Auxiliary N flow (FI-31801 and FI-31901 at '2PSA).
.3 Main N block valves close.
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.4 Natural circulation flow is established in accordance with B.t. section 6 as applicable.
D.2-3 Rev. 6
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6.0 SUBSEQUENT OPERATOR ACIION (Concinued)
.4 Control RCS latdown/ makeup flow as necessary to maintain the pressurizer level at 150 1 50 inches. Verify level on all available instrumentation.
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.5 If the Makeup Tank reaches to level (alarm) or additional RCS ankaup is required, provide askeup by:
.1 Open SFV-23811, HPI Injection Loop A (normal makeup nozzle).
.2 Start the EPI pump lined up to the 3WST inlet supply.
.3 Throttle SPV-23811 as necessary to control pressurizer level.
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.4 Eastore the system to normal level control as soon as rossible (assual pressurizer level control requires frequent cprator at;*neton).
.5 Continue to operate the additional HPI until RCS pressure ~
is S 2150 pois and pressurizer level is 150 t 50 inches.
Eastart HPI as necessary. - Verify pressurizer level on all available instruments.
.6 Verify all code relief valves and ADV's are properly seated.
Gag or isolate as necessary. If all valves are not properly resented, perform Emergency Procedure D.13 in conjunction with the remainder of this procedure.
.7 Verify CTSG water levels stabilized at 24 inches (normal N flow).
f 30 inchGt (Main NP's tripped) or 50% (RCP's tripped). If OTSG 1evels cannot be mainteined (OTSG's steam dry), initiata HPI (SFAS channels IA and B) at maximum flow to provide the core with cooling flow until feedvater can be established (HPI pop runout at 500 gym). Perform Emergency Procedure D.14 in conjunction with the remainder of this Procedure.
.8 Insure RCS subcooling is maintained. If the Th, Te and/or Incore Tc's indicate super-heated conditions exist in the i
RCS, perform Casualty Procedure C.47 in conjunction with the remainder of this procedure. Use T-Sat meters and/or saturation curve (see Enclosure 7.1) using the highest indicated ecolant 7
i temperature (Th Tc, Incore Tc's).
Indication of void formition in the RCS (RCS at saturation) will require continuous HPI fic.:
until:
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.1 Subcooling is established per T-SAT meters and/or j
saturation curve (Enclosure 7.1).
.2 RCS flow established with RCP or natural convection;
.3 Teedwater flow to at least one OTSG.
NOTE:
s Flow to the PRT via the DOV or Code Relief Valves must continue until OTSG 1evel(s) can be restored.
U DO NOT drain this water from the PRT or reactor building until RCS parameters have been stabilized and with Station Management approval.
@o8-4 iR3v. 7
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6.0 SUBSEQUENT OPERATOR ACTION.(Continued)
.9 In the secondary plant:
.1 Stop both heater drain p g s.
.2 Step one main FWP.
.3 Establish one condensate pump operation.
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.4 Ensure turbina drain valves are open.
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.5 Ensure condensate polishers system on 3 units.
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.10 Determine cause of Reactor / Turbine trip.
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.1 If restart permissible, perform OPOP B.2, Plant Startup.
.2 If restart is not permissible, perform applicable portions of OPOP B.4, Plant Shutdown.
.11 Determine RCS boron concentration as soon as possible and perform a reactivity balance in accordance with OPOP B.6 to verify >1% SDM.
7.0 ENCLOSURES
.1 SATURATE AND SUBC00 LED RELATIONS i
D.2-5 Rev. S