ML20077A641
| ML20077A641 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/16/1983 |
| From: | Williams B, Woodward K SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20077A625 | List: |
| References | |
| EOP-5, NUDOCS 8307220387 | |
| Download: ML20077A641 (15) | |
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUM'MER NUCLEAR STATION NUCLEAR OPERATIONS o
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EMERGENCY OPERATING PROCEDURE E0P-5 RECOVERY FROM REACTOR TRIP REVISION 6 JUNE 10, 1983 SAFETY RELATED Reviewed by:
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$/flb ORIGINATOR (of this revision)
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OISCIPLINE SUPERVISOR Date l
l Approved:
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l ASSISTANT MANAGER, OPERATIONS Date Date Issued:
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8307220387 830712 DRADOCK05000g
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E0P-5 REVISION 6 6/10/83 I.,
PURPOSE This procedure provides instructions for placing the unit in a stable condition after a reactor trip, and provides a means for evaluation and possible return to power operation.
II., CONDITIONS A.
RECOVERY FRON~ REACTOR TRIP 1.0 SYMPTOMS 1.1 Illumination of any one of the reactor trip first out annunciators.
2.0. AUTOMATIC. ACTIONS 2.1 Reactor trip.
2.2 Turbine trip.
NOTE.2.3 If generator trip is due to a Een-erator fcult, generator trip will be instantaneous,.
23 Generator trip approximately 30 seconds after turbine trip.
3.0- IMMEDIATE. CORRECTIVE. ACTIONS ACTIONS ALTERNATIVE. ACTIONS 3.1 Verify reactor trip 3.1 If reactor trip not as follows:
indicated, perform the following:
a.
Trip reactor
- a. Dispatch operator manually from to manually open Main Control reactor trip and Bo ard.
rod drive motor generator set b.
Rod bottom lights breakers.
illuminated.
AND b.
If reactor does not trip refer to E0P-10,Section II.B.
PAGE 1 of 10
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E0P-5 REVISION 6 6/10/83 ACTIONS ALTERNATIVE. ACTIONS (3 1 Continued) c.
Digital rod position indications at zero.
d.
Nuclear power decreasing as indicated on NR-45 t
3.2 Verify turbine trip 3.2 If turbine trip is as follows:
not indicated, per-form the follow-ing:
a.
Turbine MAIN.STOP a.
Manually trip VLVS closed, turbine from Main Control Board.
b.
TURBINE TRIP light or illuminated.
b.
Stop Electro-Hydraulic Control Pumps A and B and PULL-T0-LOCK.
or
- c. Manually trip the turbine from the 3.3 Verify generator trip turbine front (after 30 second time standard.
delay) as follows:
3.3 If generator trip is not indicated, a.
GEN BKR open.
perform the following:
b.
GEN FIELD BKR open.
a.
Trip GEN BKR c.
EXC FIELD BKR open.
b.
Trip GEN FIELD BKR d.
Turbine SPEED decreasing.
c.
Trip EXC FIELD BKR
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E0P-5 REVISION 6 6/10/83 ACTIONS ALTERNATIVE ACTIONS 3.4 Verify one Reactor Coolant 3.4 If no reactor Pump running.
coolant pump runn-ing, proceed to E0P-13.
35 Verify that Pressurizer 3.5 If not recovering, level and pressure have evaluate conditions commenced recovery from prerequisite for transient.
safety injection.
If appropriate, manually initiate safety injection and proceed to EOP-1.
3.6 Verify Reactor Coolant 3.6 If not decreasing, System temperature decreasing perform the follow-to no load Tavg.
ing:
a.
Transfer STM DUMP MODE DELECT to STM PRESS mode.
b.
Transfer STM DUMP CNTRL to MAN.
c'.
Adjust STM DUMP CNTRL to reduce Tavg.
3.7 Announce plant conditions over paging system.
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E0P-5 REVISION 6 6/10/83 4.0 FOLLOWUP ACTONS NOTE 4.0 Initial each step as it is completed.
ACTIONS ALTERNATIVE ACTIONS 4.1 Verify that automatic actions and immediate corrective actions have been completed.
4.2 Verify that all control 4.2 If one or more or shutdown rod clusters control or shut-fully inserted.
down rod cluster (s) has failed to fully insert, perform the following:
a.
Emergency borate approximately 100 ppm for each additional rod not fully inserted by opening MVT-8104, EMERG BORATE.
b.
Verify flow on FI-110, EMERG BORATE FLOW.
4.3 Transfer NIS recorder NR-45 to one source range and one inter-mediate range channel.
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PAGE 4 of 10
E0P-5 REVISION 6 6/10/83 ACTION ALTERNATIVE ACTION 4.4 If the following valves 4.4 If pressurizer actuated during the power relief valves transient, verify their fail to close, closure when Pressurizer close the follow-pressure drops below ing associated 2315 pais:
isolation valves:
a.
PVC-444B,PZR PWR a.
MVG-8000A,PZR RELIEF RELIEF ISOL b.
POV-445, PZR PWR b.
MVG-800B,PZR RELIEF RELIEF ISOL c.
PCV-445B, PZR PWR c.
MVG-8000,PZR RELIEF RELIEF ISOL 4.5 Verify FW ISOL annunicator alarm at 564*F.
a.
Verify feedwater isolation valves close:
- 1) PVG-1611A, A ISOL 2).PVG-1611B, B ISOL
- 3) PVG-16110, C ISOL
- 4) PVG-1678A, FIBV A
- 5) PVG-1678B, FIBV B
- 6) PVG-16780, FIBV C B.
Lower FEEDWATER PUMP SPEED CNTRL and SPEED CHNG to minimum governor speed.
4.6 Verify STM DUMP CONTROL set to maintain 1092 psig (setpoint 8.4).
4.7 When Tavg = 557 F, transfer STEAM DUMP MODE SELECTOR switch to STM PRESS mode.
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20P-5 REVISION 6 6/10/83 ACTION ALTERNATIVE ACTION 4.8 Verify that a stable Tavg 4.8 If Tavg is still has been established.
decreasing, perform the following:
a.
Initiate emergency boration by opening MVT-8104, EMERG BORATE.
b.
Verify flow on FI-110, EMERG BORATE FLOW.
c.
Verify proper steam dump operation.
d.
If safety injection symptoms exist, manually initiate safety injection and proceed to E0P-1.
49 Verify condenser 4.9 If condenser is not available as follows:
available, perform the following:
a.
CNDSR AVAIL PERMISV c-9 light bright.
a.
Verify that POWER RELIEF SETFT controllers are set to maintain 1092 psig (setpoint 8.4).
b.
Transfer the following valves to POWER RELIEF position:
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n EOP-5 REVISION 6 6/10/83 ACTION ALTERNATIVE ACTION (4.9 Continued) 1)
IPV-2000, MS LINE SD/PWR RLF 2)
IPV-2010, MS LINE SD/PWR RLF 3)
IPV-2020, MS LINE SD/PWR RLF 4.10 Ensure the following Motor Driven Emergency Feedwater pumps start:
1)
MD EFP B 4.11 Perform the following:
a.
Place the following valtes in MANUAL position:
1)
b.
Throttle the j
following valves to j
maintain steam generator at no load level of 25% narrow j
range span:
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1)
TO SG C i
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E0P-5 REVISION 6 6/10/83 ACTION ALTERNATIVE ACTION 4.12 Trip all operatin5 Main Feedwater Pumps.
4.13 Shutdown and isolate the Boron Thermal Regeneration System as follows:
a.
Open HCV-387, BTRS BYP FLOW VALVE.
b.
Turn BTRS SELECT switch to 0FF position.
4.14 Verify SR DET VOLT LOSS 4.14 If SR DET VOLT LOSS annunciator alarm clears annunciator alarm as intermediate range does not clear, amps drop below P-6.
reset Source Range Train A and Train a.
Select both source B.
channels on NR-45.
4.15 Verify turbine MSP and TGOP start at turbine speed of app'roximately 1700 rps.
4.16 Notify load dispatcher of plant conditions.
4.17 As turbine speed approaches 900 rpm, i
verify turbine lift pumps are running.
l 4.18 Adjust ITV-4211, TURB OIL TEMP controller to I
maintain oil temperature of 90*F.
4.19 verify temperature on TI-4211, TURB OIL CLR TEMP.
4.20 Secure Cor.densate and Feedwater Booster Pumps as 4esired for plant conditions.
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.e E0P-5 REVISION 6 6/10/83 ACTION ALTERNATIVE ACTION 4.21 Open turbine system drain valves per SOP-214.
4.22 Obtain boron sample and verify shutdown margin.
4.23 Verify that turbine T RN 4.23 If turbine TURN GEAR starts and engages GEAR does not start when turbine is at zero and engage, break speed.
condenser vacuum and secure seal steam within 30 minutes.
4.24 Complete Attachment I.
NOTE 4.25 The following test should be delegated to I&C technicians.
4.25 Complete STP-345.001, both before and after resetting reactor trip breakers.
5.0 FINAL CONDITIONS 5.1 If a normal startup and return to poteer is permissable, proceed per GOP-2.
5.2 If the cause of a reactor trip cannot be determined or corrected, the plant may be placed in hot shutdown or cold shutdown per GOP-6 or GOP-7, at the direction of the Shift Supervisor after consultation with Assistant Manager, Operations.
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PAGE 9 of 10
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E0P-5 REVISION 6 6/10/83 III. REPERENCES 1.
Virgil C. Summer Technical Specifications 2.
Virgil C. Summer General Operation Procedures A.
GOP-2, Plant Startup from Hot Shutdown to Power Operation B.
GOP-6, Plant Shutdown from Hot Standby to Hot Shutdown C.
GOP-7, Plant Shutdown fecm Hot Shutdown to Cold Shutdown 3.
E0P-13, Natural Circulation 4.
SOP-214, Main Turbine and Controls
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E0P-5 ATTACHMENT I Pags 1 of 4 REVISION 6 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 (Tavg)
C. Reactor Coolant Pressure:
psig
- 3. Operation (s) in progress at time of Reactor Trip: (i.e., normal operation, load changing, surveillance testing, boration or dilution, etc.)
- 4. Cause of Reactor Trip j
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- 5. How cause of Reactor Trip determined:
- a. First out annunciator
- b. Sequence of Events
- 6. Corrective Action Taken:
- 7. Did Reactor Protection System Function properly YES NO (explain no)
- 8. Was ESF Actuation Required YES NO
- 9. How ESF was. Actuated AUTO MAN N/A l
II. Plant Response MAI MIN 1., Pressurizer Pressure
- 2. Pressurizer Level
- 3. RCS TAVG
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E0P-5 ATTACHMENT I Page 2 of 4 REVISION 6
- 4. Did pressurizer safety valves actuate YES NO
- 5. Did pressurizer PORVS actuate YES NO MAX MIN
- 6. Steam Generator Levels A
B C
7.
Steam Pressure 8.
Did Steam Line Safety Valves Actuate YES NO 9.
Did Steam Line PORVs Actuate YES NO 10.
Did Steam Dump Valvis Function Properly YES NO 11.
Explain any abnormal responses:
III. 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 2.2) 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?
YES NO 5.
Does the event require implementation of the Plant Emergency Plan?
YES NO o
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E0P-5 ATTACHKENT I Page 3 of 4 REVISION 6 6.
If all questions above are answered NO, a normal startup and return to power is permissable per GOP-2 and GOP-3 7
If question 1 is answered YES, proceed to COLD SHUTDOWN as per GOP-6 and GOP-7 8
If questions 2 or 3 are answered YES, remain in HOT STANDBY or HOT SHUTDOWN as per GOP-5 until the conditions which caused the trip or exceeding the Limiting Safety System Settings have been evaluated and corrected.
9 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 satisfied.
10.
If question 5 is answered YES, subsequent action will be at the discretion of the Shift Supervisor after consultation with the Assistant Manager Operations or Plant Manager.
11.
If Item I.4 or I.5 cannot be determined or answered fully, subsequent action will be at the discretion of the Plant Manager.
IV. Action Taken.
V. ' Documentation Attached 1.
Plant Computer Alarm Printout Yes No 2.
Plant Computer Post Trip Review Printout Yes No 3
TSC Computer Post Trip Review Printout Yes No 4.
Applicable Recorder Chart (reproductions)
Yes No 5
Statements from personnel involved Yes No 6.
Off Normal Occurance Report Yes No Yes No 7
NRC prompt Notification Form VI. The cause of the reactor trip is understood or adequately evaluated to determine that a restart is permissable, the co'ndition has beEh corrected and a restart is permissable.
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Agree Disagree Reactor Operator
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SIGNATURE DATE
E0P-5 ATTACF24ENT I Page 4 of 4 REVISION 6 Agree
' Disagree i
Senior Reactor Operator
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SIGNATURE DATE Shift Technical Advisor
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SIGNATURE DATE l
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l Shift Supervisor
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SIGNATURE DATE l
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l Plant Management
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DATE l
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l SIGNATURE (PM, AMO, S0)
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