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[1-SOUTH CAROLINA ELECTRIC AND GAS COMPANY

VIRGIL C. SUMMER NUCLEAR STATION ,

NUCLEAR OPERATIONS^

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NUCLEAo ove-$ \ ' [jf f/

EMERGENCI OPERATING PROCEDURE,

IE0P-5,

REACTOR TRIP ,

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REVISION 2 j

OCTOBER 6, 1980 |

SAFETT RELATED,

Reviewed by:9

ORIGINATOR-lof this revision) Date

QUALIFIED REVIEWER . Date

Approved:,

OPERATIONS SUPERVISOR Date

Date Issued: [ je i

Fors AP-101-2 (1/80) | ||'.i

801121 O Y67 |'

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30P-5 -

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Page i,

REVISION 2~10/06/80

LIST OF EFFECTIVE PAGES

, PAGE -< . REVISION - . ,

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1 2

2 2

3 2 .,

4 2

ATTACHMENTS REVISION

I 2

II 2,

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EOP-5.

PAGE 1'

REVISION 210/6/80

1.0 PURPOSE

1.1 The purpose.of this procedure is to place the unit in a stableconfeition after a reactc~ trip to allow evaluation and possiblereturn to power operatica.

2.0 REFERENCES AND GLOSSARY

2.1 Reference

2.1.1 V. C. Summer Technical Specification -

2.1.2 V. C. Summer General Operation Procedures

A. GOP-2, Plant Startup from Hot Shutdown to PowerOperation

B. GOP-6, Plant Shutdown from Hot Standby to Hot Shutdown

C. GOP-7, Plant Shutdown from Hot Shutdown to ColdShutdown

2.1.3 E0P-13, Natural Circulation

2.1. 4 SOP-214 r Heater Vents and Drains !!

I2.2 Glossary,

None

30 CONDITIONS

31 Symptoms '

J.1.1 Any one of the 23 reactor trip first out annunciators,

indicating Attachment I conditions.

4.0 AUTOMATIC ACTIONS

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 contro) and shutdown rods fully inserted byd.igital rod position indication and rod botton lights. j

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E0P-5PAGE 2REVISION 210/6/80

A. IP reactor has not tripped:'

'' 1) ' Trip the reactor and' turbine manually from'the

main control board.

2) IF reactor does not trip, place Bus 1B1 and 101BUS TIE BKR in MANUAL and open 1B1 and 101 FDRBKRS from the main control board.

NOTE: Bus 1B1 and 101 may be re-energized when rods areinserted.

5.t.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.

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

5 1.4 Verify turbine trip:

A. IF, turbine has not tripped:

1) Manually trip the turbine from the main controlboard OR

2) Stop EHC Pumps A and B and pull to lock oil

3)- Manually trip the turbine from the turbine frontstandard

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52 Verify one Reactor Coolant Pump running, IF NOT proceed toE0P-13 for establishing natural circulation.

53 Verify RCS temperature iecreasing to no load Tave by operationof steam dumps.

54 Verify pressurizer level and pressure commence recovering fromtransient. t

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

symptons. If necessary, safety inject and go to E0P-1,Safety Injection.

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55 Verify generator trip approximately 30 seconds after turbine |'

trip.

5.5 1 Generator output breaker open.

552 Main Generator field breaker open. ]-5.5.3 Main turbine speed decreasing.

56 Announce Reactor trip over paging system.

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E0P-5~

PAGE 3REVISION 2,

10/6/80~

6.0 FOLLOW-UP ACTION<- .

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NOTE: Check or initial steps as indicated when satisfactorilycompleted.

6.1 Verify all automatic and immediate action steps have beencompleted.

6.2 Verify feedwater isolation at Tavg 563*F. Reduce feedwater pumpspeed to minimum governor speed.

63 7erify Tavg at or approaching no-load value of 557*F.

631 If cooldown rate is uncontrollec, start emergencyboration by OPENING MYT-8104 and verifying flow on FI-110

; AND:

6.3 2 Evaluate conditions for safety injection symptoms and goto E0P-1, Safety Injection, if necessary.1

6.4 When Tavg reaches 557*F, place both Steam Dump InterlockSwitches to RESET then BYP INTLK and transfer STEAM DUMP MODESELECTOR switch to STM PRESS mode.

6.4.1 Verify steam pressure mode controller is set to maintain1092 psig.

6.4.2 If condenser is not available:

A. Switch the MS LINE SD/PWR RLF valves (IPV2000, 2010,- 2020) to POWER RELIEF position.

B. Verify the MS POWER RELIEF Controllers are set tomaintain 1090 peig.

65 If the PZR POWER RELIEF VALVES (PCY 444B, 445A, 445B) actuatedduring the transient, verify their closure when pressurizerdrops below 2335 psig.

6 5.1 If a pressurizer, power operated relief valve fails to,

close, CLOSE the associated. RELIEF ISOLATION valve' -

(MVG-8000A, B OR C).-

6.6 Shutdown and isolate BTRS system to prevent inadvertent dilutionof the reactor coolant system:

6.6.1 OPEN BTRS Bypass Flow Valve, HCV 387

6.6.2 Place BORON THERMAL REGEN SELECT to 0FF.

6.7 Verify Source Range High Voltage comes on as intermediate powerrange drops below P-6 (10-10 amps). Select both source rangechannels on N45

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

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E0P-5^*

PAGE 4 -

REVISION 210/6/80

6.8 Verify main suction oil pump and turning gear oil pump start atapproximately 1700 rpm. (Turbine speed)

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Start motor dr'ven emergency feedwater pumps A and 'B and69 ithrottle emergency feedwater flow to maintain steam generator atnc load level of 25% narrow range span.

6.10.1 The flow control valves must be RESET and returned toMANUAL before they can be throttled.

6.10 Trip all operating main feedwater pumps.

6.11 Notify load dispatcher.

6.12 As turbine speed apprcaches 900 rpm verify turbine rotor liftpumps are running.

6.13 Adjust main turbine oil cooler ITV-4211 to maintain oiltemperature of 90*P as indicated on TI-4211.

6.14 Stop condensate and feedwater booster pumps as desired for plantconditions..

6.15 Open turbine system drain valvec as per SOP-214, Section6.1 3.E.

6.16 Obtain boron sample and verify SD margin.

6.17 Verify turbine turning gear engages when turbine is at zerospeed.

6.17 1 IF NOT secure Seal'S.t,5.am and Break Condenser Vacuum.,

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6.18 Complete Attachment II to determine subsequent action forachieving final conditions.

6.19 complete STP-345 001, Punctional Test of P-4 interlock bothbefore and after resetting Reactor Trip breakers.

NOTE: Test performed by I & C Technicians. j

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' '' 70 FINAL CONDITIONS - - J

7.1 If a normal startup and return to power is permissible proceedwith start-up as per GOP-2 as determined by existingconditions.

7.2 If cause of reactor trip cannot be determined or corrected, unit,

may be maintained in hot shutdown condition or placed in a coldshutdown condition per GOP-6 'and GOP-7, at the discretion of theShift Supervisor after consultations with the OperationsSupervisor or Plant Manager.

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30P-5ATTACHMENT IPAGE 1 of 1REVISION 2

REACTOR TRIPS AND SETPOINTS

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1. MANUAL2. SAFETY INJECTION Any of 5 signals3 SOURCE RANGE HIGH FLUX 102 CPS4. INTERMEDIATE RANGE HIGH FLUI - Current = 25% Power5 POWER RANGE HIGH FLUX (LOW SETPOINT) 25% Power6.- POWER RANGE HIGH FLUI (HIGH SETPOINT) 109% Power7 POWER RANGE POSITIVE RATE +5%/2 Sec8. POWER RANGE NEGATIVE RATE -5%/2 Sec

19 OVERTEMPERATURE AT 118% + Penalties10. OVERPOWER AT 109% ! Penalties11. LEVEL HIGH PRESSURIZER 92% Span12. PRESSURE HIGH PRESSURI"ER 2380 PSIG13 PRESSURIZER LOW PRESSURE (RATE SENSITIVE) 1870 PSIG14. SINGLE LOOP LOSS OF FLcW <90% Plow in 1 of 3 loops15 TWO LOOP LOSS OF FLOW <90% Flow in 2 of 3 loops16. RCP BUS LOW VOLTAGE 4830 Volts17 LOW LOW S/G WATER LEVEL Programmed18. S/G PEEDWATER MISMATCH Programmed19 TURBINE TRIP-(above 15% Rx Power) 800 psig EHC Press or 4/4

Stop Valves Closed20. RCP. Low Frequency 57.5 HZ

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E0P-5ATTACEMENT IIPa6e'1 of 2REVISION 2 -|

REACTOR TRIP RECOVERY EVALUATION

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)''

C. Reactor Coolant Pressure: psig ..1-

3. Operation (s) in progress at-time of Reactor Trip: (i.e., normaloperation, load changing, surveillance testing, boration or.dilution, etc.)

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; 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

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j 2. Has any Limiting Safety Setting (Tech Spec 22) been exceeded?; YES NOi

; 3. Does condition (s) which' caused the trip still exist? YES NO<

l4. Are there any Tech Spec LCO actio'.1 statements outstanding that

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preclude a return to power? YES NO I

i 5. Does the event require prompt notification to the NRC asdefined in Tech Spec Section 6 91.8. IES NO

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ATTACEMENT IIPage 2 of 2REVISION 2

6. If questions above are answered NO, a normal startup andret :rto power is permissabl.a. Notify the Operations,

Supervisor or Plant Manager no later than the first normalworking day following the reactor trip.

7. If any question is answered YES notify the OperationsSupervisor or Plant Manager immediately.

A. If question 1 is answered YES proceed to COLD SEUTDOWII asper GOP-6 and GOP-7

E. If questions 2 cnr 3 are answered YES remain in HOT STANDBY;

or HOT SEUTDOWN as per GOP-5 until the conditions which i

caused the trip or exceeding the Limiting Safety System'

'Settings have been evaluated and corrected.

C. If questions 4 is answered YES proceed to the mode ofoperation required by the appropriate Tech Spec actionstatement until the LCO has been satisfied.

D. If question 5 is answered YES subsequent action will be atthe discretion of the Shift Supervisor after consultationwith the Operations Supervisor or Plant Manager.

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III Action Taken.

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Senior Reactor Operator /

Signature Date4

Shift Supervisor /, .. '

Date' Signature *. ,

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