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)

Text

" , *f4- ?

o RIVER BEND STATION I

, t r- APPROVAL SHEET j l STATION OPERATING PROCEDURES i

NO. A0P-0001 TITLE REACTOR SCRAM ~-

l

. .... - - . u l

SAFETT RELATED TES X NO] 1 TECHNICAL REVIEW REQUIRED TES X NO ,.: .- l REV. , PAGES INDEP. TECH.

~

NO. ' ISSUED REVIEW REVIEW APPROVED BT

. .EFFECT

]{'1 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 l p- 3/22/95 Z97W .%$

= es g, ,,e s.

s. a u m. . ,, s

'i 'g. s KR INFORMATION ONLY l -9La o Q) wom

?\

.- wI .

O w , i; +ne S t mon y/

'O

. ca. uron d Occument ,

4 se g

% ~/y '

C

.Q, 415 e.;,.: -

i.

~

RECEIVED

. MAR 281985

~y} '

C'!RC 8507170132 850709 (DR ADOCM 05000458 PDR  !

r I i SON-003

g i

=*

!1 l f- I i

l REACTOR SCRAM l

l 1

8l l TABLE OF CONTENTS l

l l SECTION PAGE NO. l l-l l 1.0 PURPOSE / DISCUSSION 2 l 1

l l 2.0 SYMPTOMS 2 l 1

I

.l 3.0 AUTOMATIC ACTIONS 3 l l

1 3 . .. l . 4.0 IMMEDIATE OPERATOR ACTIONS 4

., l

.l 5.0 SUBSEQUENT OPERATOR ACTIONS 5 l 1

1 ll -

I I

l

-1 I I

I

-1 I

>l ._

l

. ,1 I,.

~ 11 1 8 .I l

I

-I -

1 I

i l

1

--1 I

-1 I

1 l

v1 I

'I I

.I I I

I I

I I

I I

I I

I

.I I

I I

I I

I I

i l i I I

I I l 1I I I I i N/A l N/A ll A0P-0001 l REV - 1 l PAGE 1 0F 6 l 1 I ll l l l

I

' J. I I l 1.0 PURPOSE / DISCUSSION l

.l 1-1.1 To provide instructions for the operator in the event of a 8

l ' l l reactor scram. I I l l

1.2 This procedure may interface with the Emergency Plan and l I Emergency Operating Procedures. l I I l 1.3 A reactor scram results in the rapid, simultaneous insertion of I l all withdrawn Control Rods.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. I 1 I i 1.4 The Operator. "At-The-Controls" will manually initiate a reactor I l scram whenever: I

1. I l- 1.4.1 A scram setpoint is exceeded and an au.omatic scram did l l not occur or l l I

, 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. l

--~

l l' l 2.0 SYMPTOMS l l I I 2.1 Reactor scram trip annunciator. l .

I I l 2.2 Eight white scram solenoid valve lights are out. I 2.3 Indication of rods inserted.

I I l 2.4 Reactor power rapidly decreasing. I I I l 2.3 One or more of the following scram setpoints are exceeded: l

. I l

] 2.5.1 CRD instrument volume high water level trip (equal to or l l less than 36% of full scale). I i l I l 2.5.2 Main Steam Line High-High Radiation (3 x normal). I I I I 2.5.3 Main Steam Line Isolation Valves Closure (equal to or less l I than 8*. closed). I i l i 2.5.4 Reactor Vessel High Pressure (1065 Psig). I I I I 2.5.5 Reactor Vessel Low Water Level (LEVEL 3). I I I I 2.5.6 Reactor Vessel High Water Level (LEVEL 8). l l .

l l 2.5.7 Turbine Stop Valve Closure Trip (equal to or less than 5% l l closed). I I I l 2.5.8 Control Valve Fast Closure Trip (equal to or greater than I 8 l I

I 530 Psig). I I

I I I il l I I i l N/A I N/A ll AOP-0001 1 REV - 1 I PAGE 2 0F 6 l l l l ll l 1 I  !

. n I

I l 2.5.9 Non-CoincidInt; SRM's High-High (5 x 10ES) or INOP. '

l l

l

'l 2.5.10 Intermediate Range Monitor Neutron Flux-High (120 l l

divisions of full scale) or INOP. l l

1 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. l l I l 2.5.12 Average Power Range Monitor Thermal l'ower Trip in Run mode l 3

l (.66W + 48%) or (118%) or INOP. l l

l l 2.5.13 Drywell High Pressure (1.68 Psig). l l

I 4

l 2.5.14 Manual Scram or Mode Switch in SHUTDOWN. l l

l l 3.0 AUTOMATIC ACTIONS

~

l l

l 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.

l 1

l 3.2 I 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 ~l l stay there until the SET POINT SETDOWN RESET pushbutton is l l pushed. ,

l l

3.3 I The Recirculation Pump.s.will. shift to low speed and the loop flow l l

l controllers will shift to manual on any of the following signals: l @.

l l

l 3.3.1 Less than 30% Feedwater flow (15 second time delay).

l 1

l l 3.3.2 Reactor water level below level 3. l l

3.3.3 I l- Main Steam Line to Recire Pump Suction differential l l temperature less than 8*F (15 second time delay). l l

• l l 3.3.4 Turbine trip.

l l

1 I

I I

I I

I l 1 I

I I

I I I I

I I

I l -

l l

l l I I

I 1

N/A 1- il i I I l l N/A ll AOP-0001 l REV - 1 l PAGE 3 0F 6 l l l ll l l l

Ig -

l l r

l 4.0 IMMEDIATE OPERATOR ACTIONS l

I I I i 1

~

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. l l l 1 I I I I l 4.1 ARM and DEPRESS all four manual scram pushbuttons, RPS Div 1, 2, l l 3, 4 on panel 1H13-P680. l l

1 l 4.2 Place the Mode Switch to SHUTDOWN. l l

I l 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. l l

I l 4.4 Verify power decreasing as indicated on the APRM's. l l

l 4.5 l Verify the Feedwater System is operating to restore reactor water l l level. . -

l l

1 l 4.6 Verify reactor pressure is being maintained by either the turbine l '

l bypass valves or safety relief valves. l 8

l -

l l 4.7 Manually downshift the'.reacior.recire pumps by simultaneously l l depressing both " TRANSFER TO MG" pushbuttons. l l

• 1 l 4.8 Verify Turbine / Generator trips en reverse power or trip manually. l l

I l 4.8.1 Verify Generator Output Breakers open 1WC-20635 a*.td 1WC- l l 20640.

l 1

I l 4.8.2 Start Turning Gear Oil Pump and Motor Suction Pump.

• l I

I

. -l 4.8.3 Verify Exciter Field Breaker open. l

.; I I

l l

1 1

I I

I I

I I

I

- I l

I I

I I

1 l

l .

1 I

I I

I I ll 1 1 I l N/A l N/A ll AOP-0001 l REV - 1 l PAGE 4 0F 6 l 1 I ll l l 1

^

5.0 SUSEQUENT OPERATOR ACTIONS '

[ 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.

l l I g 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.

l 1 I y 5.3.1 Switch to single element control and secure operating l l pumps and level control valves as necessary to maintain a [

g stable water level. Leave at least one reactor feed pump l l

running.

l

~

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.

" g .

pressure of between 20 Psid and 30 Psid as read on [lH13- l g P680]. --

l l I ..

I I

l I l I g l CAUTION l <

?~ l g l . . -

l l

~

g l Do not attempt to reset the scram l l g l for at least 10 seconds after the l l g l scram to prevent CRI7 damage. l l l l I I l

.j g 5.4 When the scram signal has cleared, reset the scram and return the l l

CRD System to normal. l l

l

• g 5.5 If any control rods have position indication between 00 and 04 l l

l individually select and drive these rods to position 00. [

l I

l 5.6 Restart the Reactor Water Cleanup System, if tripped, per SOP- l g 0090.

~ l l

l 5.6.1 Reject water as necessary to maintain level. l l

l l

l 5.7 To reestablish normal water level perform the following: l 1

5.7.1 I l 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 l g level control valves. l l

N/A l

N/A ll l l l g g ll A0P-0001 l REV - 1 g PAGE 5 0F 6 l 1 l 11 I I I

n .

o ..g l

[ .

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. l l

l l 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]. l I

I l 5.7.4 Depress the SETPOINT SETDOWN RESET pushbutton. Null out l l auto setpoint deviation meter on Startup Level Controller l

} and place controller in "AUT0". Slowly increase RPV level l l to approximately 36" using aito/setpoint tape. I I

I l 5.8 If reactor recirc pumps are operating in slow speed, place the l 1

l. flow control valves to the maximum open position. I I

I l 5.9 Notify Radiation Protection of reactor scram for investigation of l l existing radiological conditions throughout the plant areas. l I

I l 5.10 Perform Subsequent Actions of A0P-0002 " Main Turbine and l l Generator Trips".

l.

I I

l 5.11 Implement Emergency Operating Procedures and Emergency l

l Implementing Procedures as directed by the Shift Supervisor. l ,

I I

l 5.12 When all parameters have stabilized enter GOP-0007 " Scram l l Recovery". _

- l l .... .-

" l l END l

l 1

I .

. I I

I I

I I

I I

I I

I l

• 1 l

l I

I I

I I

l I

I I

I I

l -

l I

I I

I I

I i ,

I I

I I

I e

I lI l 1 I II I I I l N/A l N/A ll A0P-0001 l REV - 1 l PAGE 6 0F 6 1 1 I II I I I 9 - w. y .,7 - - - +e - - - - -