ML20041A272

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Emergency Operating Procedure EOP-5, Reactor Trip, Revision 3
ML20041A272
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/18/1981
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20041A267 List:
References
EOP-5, NUDOCS 8202190354
Download: ML20041A272 (10)
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Text

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. SOUTE CAROLINA ELECTRIC AND GAS COMPANY -

(';' . VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS

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EMERGENCY OPERATING PROCEDURE g.. . . . E0P-5 .

REACTOR TRIP REVISION 3 OCTOBER 22, 1981 b

SAFETY RELATED Reviewed by:

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  • REVISION 3 '

10/22/81 LIST OF EFFECTIVE PAGES -

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PAGE REVISION 1 3 -

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ATTACHMENTS REVISION -

I 3 II, Pages 1 and 2 3

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. 0 E09-5 REVISION 3 10/22/81 - r 1.0 PURPOSE _

(- 1.1 The purpose of this procedure is to place the unit in a stable condition after a reactor trip to allow evaluation anc possible return to power operation. ,

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2.0 REFERENCES

AND GLOSSARY -

2.1 Reference , ,

2.1.1 Virgil C. Summer Technical Specification. ,

2.1.2 Virgil C. Summer G'e neral Operation Procedures.

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A. GOP-2, Plant Startup from Hot Shut,down to Power Operation B. GOP-6, Plant Shutdown froni Hot Standby to Hot -

Shutdown C. GOP-7, Plant Shutdown feca Hot Shutdown to Cold

. Shutdown 2.1.3 E0P-13, Natural Circulation 2.1.4 SOP-214, Heater Vents and Drains 2.2 Glossary ,

AMP - Ampere -

BTRS - Boron Thermal Regeneration System I & C - Instrument and Control MG - Motor generator set ppm - parts per million psig - pound per square inch, gauge -

l RCS - Reactor Coolant System I rpm - revolutions per minute l SD - Shutdown Tavs - Reactor Coolant Average Temperature i 3.0 CONDITIONS 3.1 Symptoms 3 1.1 Any one of the 23 reactor trip first out annunciators indicating Attachment I conditions.

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. E0P-5 ,

REVISION 3 -

10/22/81 . 4:

4.0 AUTOMATICACTbCNS .

4.1 Reactor trip .

4.2 Turbine trip 4.3 Generator trip (after 30 second time delay). -

50 IMMEDIATE OPERATOR ACTION 51 Verify Reactor Trip / Turbine Trip ,

5 1.1 verify all control and shutdown rods fully inserted by digital rod position indication and rod bottom lights. .

A. E reactor haa not tripped:

. . . 1) Trip the reactor and turbine manually from the ~

- - main control board.
2) IP reactor does not trip, dispatch an operator to the reactor trip breakers, located on 463 level, Intermediate Building and manually open the Reactor Trip and Rod Drive MG set breakers.

5 1.2 Emergency borate 17 minutes (approximately 100 ppm) for each control or shutdown rod not fully inserted by opening MVT-8104 and verify flow on FI-110. ,

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513 Verify Reactor power decreasing and transfer NIS recorder, NR - 45, to one source range and one intermediate range channel.

5.1.4 verify turbine trip:

A. E turbine has not tripped:

1) Manually. trip the turbine from the main control board OR .
2) Stop EEC Pumps A and B and pull to lock OR
3) Manually trip the turbine fecm the turbine front standard.

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. EOP-5 i REVISION 3 -

10/22/81 - r 52 Verify one Reactor Coolant Pump running, IP NOT proceed to- .

f E0P-13 for establishing natural circulation.

5.3 Verify RCS temperature decreasing to no load Tavg by operation of steam dumps.

i' 5.4 Verify pressurizer level and pressure commence recovering from .-

transient.

A. If not recovering, evaluate conditions for safety injection [

symptoms. If necessary, safety inject and go to EOP-1, .

Safety Injection. .

5.5 Verify generator trip approximately 30 seconds after turbine trip. .

5.5.1 Generator output breaker open.

5.5.2 Main Generator field breaker open. .

553 Main turbine speed decreasing.

5.6 Announce Reactor trip over paging system.

6.0 POLIDW-UP ACTION NOTE:. Check or initial steps as indicated when satisfactority ecmpleted. ,

6.1 Verify all automatic and immediate action steps nave been completed.

6.2 Verify feedwater isolation at Tavs 564*F. Reduce feedwater pump

. speed to minimum governor speed.

6.3 Verify Tavs at or approaching no-load value of 557'F.

6.3.1 If cooldown rate is uncontrolled, start emergency boration by OPENING MVT-8104 and verifyinie flow on FI-110 -

AND:

6.3.2 Evaluate conditions for safety injection' symptoms and go to EOP-1, Safety Injection, if necessary.

6.4 When Tavg reaches 557'?, transfer STEAM CUMP MODE SELECTOR switch to STM PRESS mode.

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E0P-5 ' .

REVISION 3

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10/22/81 .

6.4.1 Verify steam pressure mode controller is set to maintain ,

1092 psig.

6.4.2 If condenser is not available:

A. Verify the MS POWER RELIEF Controllers are set to .

maintain 1092 psig. ..

. B. Switch the MS LINE SD/PWR RLF valves (IPV2000, 2010, -

2020) to POWER RELIEF position.  :

-T 6.5 If the PZK POWER RELIEF VALVES (PCV 444B, 445A, 4453) actuated

  • during the transient, verify their closure when pressurizer -

decps below 2315 pais.

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6.5 1 If a pressurizer power operated relier valve fails to  ?

CLOSE the associated RELIEF ISOLATION valve close$000A,BOR0).

(MVG- '

6.'6 ' Shutdown and isolate BTRS system to prevent inadvertent dilution -

of the reactor coolant system: ___

6. 6.,1 OPEN BTRS Bypass Flow Valve, RCV-387. .

6.6.2 Flace BORON THERMAL REGEN SELECT to 0FP.

6.7 itage c (

Verify range Souree drops belowRange High P-6 (10Yp5 amps)omes . on asboth Select intermediate source power (

range channels on N45 _

6.7.1 IF NOT RESET Source Range Train A and Train B.

6.8 Verify motor auction oil pump and turning gear oil pump start at approximately 1700 rpm (Turbine speed).

6.9 Start motor driven emergency feedwater pumps A and B and throttle emergency feedwater flow to maintain steam generator at no load level of 25% narrow range span.

6.9.1 The flow control valves must be RESET and returned to MANUAL before they can be throttled.

l 6.10 Secure all operating main feedwater pumps.

6.11 Notify load dispatcher. .

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'" goP-5 1 1 REVISION 3 .

5' 10/22/81 ,  ;

6.12 As turbine speed approaches 900 rpm verify turbine rotor Lift -

Pumps are running.

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6.13 Adjust ma'in turbine oil cooler ITV-4211 to maintain oil temperature of 90*F as indicated en TI-4211.

6.14 Secure condensate and feedwater booster pumps as desired for ..

plant conditions.

6.15 open turbine system drain valves as per SOP-214, Section 6.1.3.E. 3 6.16 obtain baron sample and verify SD margin.

6.17 Verify turbine turning gear engages when turbine is at zero speed. 7 6.17.1 IF NOT break condenser vacuum and seuure seal steam witnin the following 30 minutes.

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  • 6.18 Complete Attachment II to determine" subsequent action for achieving final conditions.

6.19 Complete STP-345.001, Functional Test of P-4 interlock both; "

before and af ter resetting Reactor Trip breakers.

NOTE: Test performed by I & C Technicians.

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. 7.0 FINAL CONDITIONS 7.1 If a normal startup and return to power is permissible proceed with start-up,as per GOP-2 as determined by existir4 conditions.

7.2 If cause of reacter trip cannot be determined or corrected, unit e may be maintained in hot shutdown condition or placed in a cold shutdown condition per GOP-6 and GOP-7, at the discretion of the Shif t Supervisor after consultations with the Operations SupervtMr or Plant Manager.

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  • 1 EDP-5 .

ATTACHMENT I PAGE 1 of 1 .:

REACTOR TRIPS AND SETPOINTS .

h. I
1. MANUAL N/A
2. SAFETY INJECTION Ang of 5 signals
3. SOURCE RANGE HIGH FLUX 103 CPS
4. INTERMEDIATE RANGE HIGH FLUX Current = 25% Power -
5. POWER RANGE HIGH FLUI (LOW SETPOINT) 25% Power -
6. POWER RANGE HIGH FLUI (HIGH SETPOINT) 109% Pcwer 7 POWER RANGE POSITIVE RATE +55/2 See  !
8. POWER RANGE NEGATIVE RATE -55/2 See (

-- ' 9. OVERTEMPERATURE & T 109.6% + Penalties '

10J OVERPOWER &T , 109.1% ! Penalties 11.._ LEVEL HIGH PRESSURIZER 92% Span

12. PRESSURE HIGR PRESSURIZER 2380 PSIG ..

1 + 13.-- FRESSURIZER LOW PRESSURE 1870 PSIG .

~Z: ' I4.- SINGLE LOOP LOSS OF FLOW <90% Flow in 1 of 3 loops 15 TWO LOOP LOSS OF FLOW <90% Plow in 2 of 3 loops ,

16. RCP BUS LOW VOLTAGE 4830 Volts '

- ' + - 17 .: LOW I4W S/G WATER LEVEL Programmed

18. S/G FEEDWATER MISMATCH Programmed 19 TURBINE. TRIP (above 10% Rx Power) 800 psig EHC Press or 4/4 Stop Valves Closed
20. RCP Low Frequency 57.5 HZ h
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.* ATTACHMENT II Page 1 of 2 ' '

REVISION 3 REACTOR ' TRIP RECOVERY EVALUATION

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I. Event.

1. Time /Date of Reactor Trip:
2. Operating parameters at time of Reactor Trip:

A. Reactor Power  %

B. Reactor Coolant Temperature: 'F (Tave) ,

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- C. Ifenctor Coolant Pressure: psig 1,._Opttation(s)inpbgressat;timeofReactorTrip: (i.e., normal operation, load changing, surveillance testinL boration or dilution, etc.) -

4. Cause of Reactor Trip:

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II. Event Evaluation. .

(Detail all Yes answers) .

1. Has any Safety Limit (Tech Spec 2.1) been exceeded? YES NO
2. Has any Limiting Safety Setting (Tech Spec 22) been exceeded?

YES NO

3. Does condition (s) which caused the trip still exist? YES NO
4. Are there any Tech Spec LCO action statements outstanding that preclude a return to power't YES NO
5. Does the event require prompt notification to the NRC as defined in Tech Spec Section 6 9 1.12. YES NO

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ATTACHMENT II -

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REVISION 3

6. If all questions above are answered NO, a normal startup and return to power is permissable. Notify the Operations {

Supervisor or Plant Manager no later than the first normal working day following the reactor trip. ,

7. If uly question is answered YES notify the Operations .

, Supervisor or Plant Manager immediately.

A. If question 1 is answered YES proceed to COLD SHUTDOWN as ,;

per GOP-6 and GOP-7. '

B. It questions 2 or 3 are answered YES remain in HOT STANDBY -

.: or HOT SBUTDOWN as per GOP-5 until the conditions which caused the trip or exceedips the Limiting Safety System  :

Settings have been evaluated and corrected.

C. If question 4 is answered YES proceed to the mode of operation required by the appropriate Tech Spec action ,

statement until the LCO has been sattsfied.

D. If question 5 is answered YES subsequent action will be at the discretion of the Shift Supervisor af ter consultation with the Operations Supervisor or Plant Manager.

III Action Taken.

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! Senior Reactor Operator /

signature Date i

l Shift Supervisor /

signature Date t

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BOARD NOTIFICATION DISTRIBUTION W 2 8 1982 Docket File LB#1 Deading ci m Board Notification File ,d Q D. Eisenhut .'

NRC PDR J[ RECEIVED 9 Local PDR DL Branch Chiefs d FEB3 1982>

12 M. Kane Gd V win ma c==n B. J. Youngblood \,2, " $7* "

M. Rushbrook A f R. H. Vollmer 67 W "

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M. Jambor R. Mattson S. Hanauer B. Snyder R. Hartfield, MPA OELD OIE (1)

TERA NSIC TIC ACRS (16)

H. R. Denton/E. Case PPAS W. J. Dircks V. Stello S. Goldberg, ELD -

J. O'Reilly, Region II l J. Sniezek, IE Hqrs.

R. L. Tedesco H. Thompson D. Ziemann l

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