ML20129E959
| ML20129E959 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/27/1985 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20129E940 | List: |
| References | |
| AOP-0001, AOP-1, NUDOCS 8507170132 | |
| Download: ML20129E959 (7) | |
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RIVER BEND STATION t r-APPROVAL SHEET j
l STATION OPERATING PROCEDURES i
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NO.
TITLE
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SAFETT RELATED TES X 1
TECHNICAL REVIEW REQUIRED TES X
NO REV.
, PAGES INDEP.
TECH.
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' ISSUED REVIEW REVIEW APPROVED BT
.EFFECT
'1 NO.
SIGNATURE /DATE SIGNATURE /DATE SIGNA'ITJRE/DATE
~~! DATE 0
1 THRU 5 8I Md 10/18/84 v 4..
1 1 THRU 6 7-24 8 03/27/85
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RECEIVED MAR 281985
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C'!RC 8507170132 850709 (DR ADOCM 05000458 PDR I
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l REACTOR SCRAM l
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8l TABLE OF CONTENTS l
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l SECTION PAGE NO.
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1.0 PURPOSE / DISCUSSION 2
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2.0 SYMPTOMS 2
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.l 3.0 AUTOMATIC ACTIONS 3
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4.0 IMMEDIATE OPERATOR ACTIONS 4
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.l 5.0 SUBSEQUENT OPERATOR ACTIONS 5
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l 1.0 PURPOSE / DISCUSSION l
.l 1-l 1.1 To provide instructions for the operator in the event of a l
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reactor scram.
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1.2 This procedure may interface with the Emergency Plan and l
I Emergency Operating Procedures.
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1.3 A reactor scram results in the rapid, simultaneous insertion of I
l all withdrawn Control Rods. The Reactor Protection System I
I automatically initiates a Reactor Scram if an unsafe plant i
I condition exists.
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1.4 The Operator. "At-The-Controls" will manually initiate a reactor I
l scram whenever:
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l-1.4.1 A scram setpoint is exceeded and an au.omatic scram did l
l not occur or l
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l 1.4.2 It is determined that the plant is in a Unsafe Condition l
l not covered by Automatic Actions and a manual reactor l
l scram will allivate the consequences of this condition.
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2.0 SYMPTOMS l
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I 2.1 Reactor scram trip annunciator.
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2.2 Eight white scram solenoid valve lights are out.
I 2.3 Indication of rods inserted.
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l 2.4 Reactor power rapidly decreasing.
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2.3 One or more of the following scram setpoints are exceeded:
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2.5.1 CRD instrument volume high water level trip (equal to or l
l less than 36% of full scale).
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l 2.5.2 Main Steam Line High-High Radiation (3 x normal).
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2.5.3 Main Steam Line Isolation Valves Closure (equal to or less l I
than 8*. closed).
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2.5.4 Reactor Vessel High Pressure (1065 Psig).
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2.5.5 Reactor Vessel Low Water Level (LEVEL 3).
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2.5.6 Reactor Vessel High Water Level (LEVEL 8).
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2.5.7 Turbine Stop Valve Closure Trip (equal to or less than 5%
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closed).
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2.5.8 Control Valve Fast Closure Trip (equal to or greater than I
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530 Psig).
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2.5.9 Non-CoincidInt; SRM's High-High (5 x 10ES) or INOP.
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'l 2.5.10 Intermediate Range Monitor Neutron Flux-High (120 l
divisions of full scale) or INOP.
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l 2.5.11 Average Power Range Monitor Neutron Flux-High and not in l
.l Run mode (15% of Rated Thermal Power) or INOP.
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2.5.12 Average Power Range Monitor Thermal l'ower Trip in Run mode l l
(.66W + 48%) or (118%) or INOP.
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l 2.5.13 Drywell High Pressure (1.68 Psig).
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2.5.14 Manual Scram or Mode Switch in SHUTDOWN.
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l 3.0 AUTOMATIC ACTIONS l
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l 3.1 All control rods insert to position 00, scram valves de-energize, l l
backup scram valves energize and scram discharge volume vent and l
l drain valves close.
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3.2 If reactor water level decreases to Level 3 the Reactor Feedwater l l
Level Controller will automatically increase its setpoint by 50%
[.
l to approximately 54" for 10 seconds. The setpoint will then be l
l automatically reduced to 50% of normal to approximately 18"-and
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stay there until the SET POINT SETDOWN RESET pushbutton is l
l pushed.
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3.3 The Recirculation Pump.s.will. shift to low speed and the loop flow l l
controllers will shift to manual on any of the following signals: l l
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3.3.1 Less than 30% Feedwater flow (15 second time delay).
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3.3.2 Reactor water level below level 3.
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I l-3.3.3 Main Steam Line to Recire Pump Suction differential l
l temperature less than 8*F (15 second time delay).
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3.3.4 Turbine trip.
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l 4.0 IMMEDIATE OPERATOR ACTIONS l
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CAUTION l
l Steps 4.1 and 4.2 must be L l
l l done sequentially per IEN l l
l l 83-42.
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l 4.1 ARM and DEPRESS all four manual scram pushbuttons, RPS Div 1, 2, l
l 3, 4 on panel 1H13-P680.
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4.2 Place the Mode Switch to SHUTDOWN.
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4.3 Verify all control rods are fully inserted by depressing RAW DATA I l
and ALL RODS pushbuttons.
If all rods are inserted, the core l
l display for all rods will be blank and a full-in green light will l l
be displayed.
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4.4 Verify power decreasing as indicated on the APRM's.
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4.5 Verify the Feedwater System is operating to restore reactor water l l
level.
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4.6 Verify reactor pressure is being maintained by either the turbine l l
bypass valves or safety relief valves.
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l 4.7 Manually downshift the'.reacior.recire pumps by simultaneously l
l depressing both " TRANSFER TO MG" pushbuttons.
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4.8 Verify Turbine / Generator trips en reverse power or trip manually. l l
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4.8.1 Verify Generator Output Breakers open 1WC-20635 a*.td 1WC-l l
20640.
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4.8.2 Start Turning Gear Oil Pump and Motor Suction Pump.
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. -l 4.8.3 Verify Exciter Field Breaker open.
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5.0 SUSEQUENT OPERATOR ACTIONS
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l 5.1 Select and drive in the SRM and IRM detectors. Switch IRM/APRM l
3 recorders to I2M's.
l 5.1.1 Downrange IRMS' as necessary to verify reactor power l
l decreating.
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5.2 If any control rods have position indication greater than 04, l
l enter AOP-0021 " Anticipated Transient Without Scram".
l 5.3 Verify reactor water level stabilizes at +18" or higher on narrow l g
range level indication.
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5.3.1 Switch to single element control and secure operating l
l pumps and level control valves as necessary to maintain a
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g stable water level. Leave at least one reactor feed pump l
l running.
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5.3.2 As Condensate /Feedwater flow is reduced secure the number g
of on-line Condensate Polishers per SOP-0093 to maintain l
g flow rates through operating polishers between 1250 Gpm l
g and 2350 Gpm. This should correspond to a differential l.
pressure of between 20 Psid and 30 Psid as read on [lH13-l g
g P680].
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l CAUTION l
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g l Do not attempt to reset the scram l l
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g l scram to prevent CRI7 damage.
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When the scram signal has cleared, reset the scram and return the 5.4 l
CRD System to normal.
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g If any control rods have position indication between 00 and 04 l
l individually select and drive these rods to position 00.
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5.6 Restart the Reactor Water Cleanup System, if tripped, per SOP-l l
g 0090.
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l 5.6.1 Reject water as necessary to maintain level.
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5.7 To reestablish normal water level perform the following:
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5.7.1 Line-up Startup Level Control Valve by placing the l
g controller in " MANUAL" and set at 0*;.
Open the LVL CONT l
g BYP ISOL [lFWS-MOV105]. Slowly open the startup valve l
g until the MASTER LEVEL CONTROLLER fully closes operating g
level control valves.
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l 5.7.2 Whtn opsrating 1sval control valvas ara full clostd, pitcs l I
the Master Level Controller in " MANUAL" and decrease l
l controller output to zero. Verify Startup Level Control l
l Valve is maintaining reactor water level.
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5.7.3 When operating level control valves are full closed and l
l Startup Level Control Valve can safely handle feedwater l
l demand isolate u;se valves by closing [1FWS-MOV27A, 27B l
-l and 27C].
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5.7.4 Depress the SETPOINT SETDOWN RESET pushbutton. Null out l
l auto setpoint deviation meter on Startup Level Controller l
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and place controller in "AUT0".
Slowly increase RPV level l l
to approximately 36" using aito/setpoint tape.
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5.8 If reactor recirc pumps are operating in slow speed, place the l
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flow control valves to the maximum open position.
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l 5.9 Notify Radiation Protection of reactor scram for investigation of l l
existing radiological conditions throughout the plant areas.
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5.10 Perform Subsequent Actions of A0P-0002 " Main Turbine and l
l Generator Trips".
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l 5.11 Implement Emergency Operating Procedures and Emergency l
l Implementing Procedures as directed by the Shift Supervisor.
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5.12 When all parameters have stabilized enter GOP-0007 " Scram l
l Recovery".
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END l
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