ML20129E959

Rev 1 to Station Operating Procedure AOP-0001, Reactor Scram

ML20129E959
Person / Time
Site:	River Bend
Issue date:	03/27/1985
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20129E940	List: ML20129E953 ML20129E959 ML20129G075 RBG-21-510, Forwards Revs to Station Operating Procedures,Including ADM-0022, Conduct of Operations, AOP-0001, Reactor Scram & GOP-0007, Scram Recovery, in Response to Re Generic Ltr 83-28
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

A0P-0001 REACTOR SCRAM

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NO.

TITLE

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SAFETT RELATED TES X 1

TECHNICAL REVIEW REQUIRED TES X

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' ISSUED REVIEW REVIEW APPROVED BT

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'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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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l all withdrawn Control Rods.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%

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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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