ML20054J952
| ML20054J952 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/02/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-I-1, 5-1-2-I-1, NUDOCS 8206300234 | |
| Download: ML20054J952 (5) | |
Text
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PLANT OPERATIONS MANUAL r
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volume 05 05-1-02-I-l Section 02 Revision:
11 Date: 6/2/82
' I 0FF-NORMAL EVENT PROCEDURE REACTOR SCRAM SAFETY RELATED
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List of Effective Pages:
Page:
1-4 List of TCN's Incorporated:
Revision TCN No.
10 None 11 None 8206300234 820625 PDR ADOCK 05000416 P
,E GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE t
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Title:
Reactor Scrtm No.: 05-1-02-I-1 l Revision: 11 Page: 1 I
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1.0 PURPOSE / DISCUSSION I
1.1 To provide instructions for the operator in the event of a Reactor Scram.
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1.2 This procedure may interf ace with the Emergency Plan and Emergency Procedures.
1.3 A Reactor Scram results in the rapid, simultaneous insertion of all withdrawn Control Rods. The Reactor Protection System automatically I
initiates a Reactor Scram if an unsafe plant condition exists. However, the operator will manually initiate a Reactor Scram whenever a scram setpoire. is exceeded and an automatic scram did not occur or when the operator determines that the plant is in an unsafe condition, not covered by automatic actions.
2.0 SYMPTOMS
,r 2.1 Reactor Scram trip annunciator 2.2 7i~ght wtiite scram solenoid valve' lights are"*out '
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.m Indication of rods inserted 2.3
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2.4 Reactor power rapidly decreasing 2.4.1 APRM recorder's in i ate a one to two decade instantaneous drop.
s 2.4.2 IRM recorders readings will decrease, if recorder is selected to IRM's and if IRMs have been ranged up and inserted.
2.4.3 SRM recorders will indicate a one to two decade instantaneous j
drop.
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2.5 One or more of the following conditions exists:
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2.5.1 CRD Instrument volume high water level trip (36 of full scale, 26 l'
gal.)
2.5.2 Main Steam Line High Radiation (3.0 x normal) 2.5.3 Main Steam Line Isolation valves closure (6% closed) 2.5.4 Reactor Vessel High Pressure (1065 psig) 2.5.5 Reactor Vessel Low Water Level (11.4 inches) j
4 GE*A!!D GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE f
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Title:
Reactor Scram No.:
05-1-02-I-l Revision:
11 Page:
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4 2.5.6 Reactor Vessel High Water Level (53.5 inches) 2.5.7 Turbine Stop Valve closure Trip ( 40 PSIG) 2.5.8 Control Valve Fas t Closure Trip ( 44.3 PSIC) 2.5.9 Intermediate Range Monitor Neutron Flux-High (120/125 divisions of full scale) 2.5.10 Average Power Range Monitor Neutron Flux-High and not in Run mode (15% of Rated Thermal Power) 2.5.11 Average Power Range Monitor thermal power trip in Run mode (.66 W
+ 48%, 6 second time delay).
2.5.12 Drywell High Pressure ( l.73 PSIG) 5 2.5.13 Manual Scram 3.0 AUTOMATIC ACTIONS
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~. y 3.1 All control rods insert to position 00, backQp scram valve energize, and*
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scram discharge volume vent and drain valves close.
3.2 Reactor Feedwater Level Controller will automatically increase its setpoint by 50% t6 approximately 54" for 10 seconds.
The setpoint will then be autowatically reduced to 50% of normal to approximately 18", and stay there until the SET POINT SETDOWN RESET pushbutton is pushed.
3.3
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The Recirculation Pumps will shift to low speed 'and the loop flow controllers will shift to manual on any of the following signals:
i 3.3.1
< 30% Feedwater flow with the flow control valves in minimum
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position (15 second time delay).
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'+11.4Reactorwate[ level
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3.3.2 3.3.3 Main Steam Line to Recirc Pump Suction differential temperature
<8'F (15 second time delay).
3.3.4 Turbine trip 4.0 IMMEDIATE OPERATOR ACTION 4.1 If any of the monitored parameters in Section 2.0 exceed the setpoint given without an automatic scram, manually sc ram the reactor.
4.2 Place the Mode Switch to SHUTDOWN.
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f C?.AND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Reactor Scram No.:
05-1-02-I-1 Revision:
11 Page:
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T 4.3 AFM and DEPRESS all four manual scram pushbuttons, RPS Div 1, 2, 3, 4 on panel IH13-P680.
4.4 Verify all control rods are fully inserted by observing the full-in green light for each rod is~ displayed. Also, OD-7 may be uced, indicating position 00. AA g
4 gdg gg 4.4.1 If any control rods have position indications greater than 06 and reactor power greater than 3% rr ^ " ' Oi',,e n t e r EP-10,
Reactivity Control.
-t-sN 5"/ U Q G7'-jo..If 4.4.2 If any control rods are not inserted and kn"a r^ r i " ^^-
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-sedien**nn- ' :.muu 00 00 perform the following:
a.
Place the RPS Div 1, 2, 3, & 4 CRD DISCH VOL HI TRIP BYP switches to the bypass position.
b.
Place the RPS Div 1, 2, 3, & 4 SCRAM RESET switches to reset, verify scram reset.
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' Allow HCU's to recharge, then drive 7he co'ntial ' rods tha d ra
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t not full-in, to position 00.
4.5 SELECT the six SRM's and the eight IRM's and DRIVE IN, and switch IRM/APRM LVL recorders to IRM's, 4.6 Verify power decreasing as indicated on the nuclear instrumentation.
4.7 If two Reactor Feed Pumps are operating and Reactor Water Level is being maintained, trip one of the pumps.
4.8 Verify that the Recirculation Pumps have shifted to low speed, or shift them manually.
4.,9, Verify Reactor Water Level stabilizes near +18" on lH13-P680.
4.10. Verify that the Turbine ard Generator trips on reverse power (15 seconds time delay, 5 seconds time delay if the turbine. has already tripped), or trip manually.
Refer to ONEP 05-1-02-I-2, Turbine and Generator Trips.
4.11 If an MSIV closure occurs, enter EP-1, Level Control.
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l 4.12 Verify reactor pressure is maintained with either the bypass valves or relief valves.
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- ., ' dk4ND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l
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Title:
Reactor Scram l tha. :
05-1-02-I-1 Revision:
11 Page: 4 I
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l 5.0 SUBSEQUENT OPERATOR ACTIONS 5.1 Restart the Reactor Water Cleanup System, af ter Reactor Wate-Level and pressure have stabilized, per SOI 04-1-01-G33-1.
Reject water as necessary to maintain level.
5.2 Af ter reactor water level has stabilized at about 18", perform the following:
5.2.1 Switch to single element feedwater control.
5.2.2 Depress the SET POINT SETDOWN RESET pushbutton and verify reactor water level slowly increases from 18" to 36".
5.3 When the scram signal has cleared, reset the scram and return the CRD system to normal as follows:
s' 5.3.1 Bypass the Scram Instrument Volume High Level scram by placing the CRD DISCH VOL HI TRIP BYP switches RPS Div 1, 2, 3, 4 to BYPASS.
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CAUTION Do not attempt to reset the scram for at least 10 seconds af ter the scram to prevent CRD damage.
5.3.2 Reset the scram by placing. the SCRAM RESET handswitches RPS Div 1, 2, 3, 4 to RESET.
5.3.3 When the Scram Discharge Volume has drained below the scram setpoint, as indicated by the CRD DISCH VOL WIR LVL HI TRIP annunciator clearing, place the CRD DISCH VOL HI TRIP BYP switches to NORMAL.
s 5.4 Implement an Emergency Procedure as entry conditions dictate or the Emergency Plan as directed by the Shift Superintendent.
5.5 When the reactor water level is about normal and stable, reactor pressure is stable, and all scram signals are reset, refer to I0I 03-1-01-4, Scram Recovery.
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