ML20023D305
| ML20023D305 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/27/1983 |
| From: | Justin Poole SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20023D272 | List: |
| References | |
| REF-SSINS-6820 EOP-5, NUDOCS 8305200352 | |
| Download: ML20023D305 (14) | |
Text
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION s
NUCLEAR OPERATIONS wb L
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EMERGENCY OPER TI 10CEbURE E0P-5 RECOVERY FROM REACTOR TRIP REVISION 5 APRIL 26, 1983 O-SAFETY RELATED Reviewed by:
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ORI/IRATOR of this revision)
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DISCIFLINE SUPERVISOR
'Date' Approved:
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- ASSIST ANT MANAGER, OPERATIONS Date' Dste Issued:
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- PAGE i REVISION 5 fg 4/26/83 s.
RECOVERY FROM REACTOR TRIP SECTION PAGE I.
PURPOSE 1
II.
CONDITIONS 1
A.
RECOVERY FROM REACTOR TRIP 1
1.0 SYMPTOMS 1
2.0 AUTOMATIC ACTIONS 1
30 IMMEDIATE CORRECTIVE ACTIONS 1
4.0 FOLLOWUP ACTIONS 4
50 FINAL CONDITIONS 9'
III. REFERENCES 10 IV.
ATTACHMENTS O.
REACTOR TRIP REC 0 VERI EVALUATION ATTACHMENT I 4
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E0P-5 REVISION 5 4/26/83 g-
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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 FROM 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.
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NOTE 2 3 If generator trip is due to a gen-erator fault, generator trip will be instantaneous.
23 Generator trip approximately 30 seconds after turbine trip.
30 IMMEDIATE CORRECTIVE ACTIONS
. ACTIONS ALTERNATIVE ACTIONS 31 Verify reactor trip 31 If reactor trip not l
i as follows:
indicated, perform the following:
a.
Trip reactor manually from Main Control Board.
b.
Rod bottom lights illuminated.
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E0P-5 REVISION 5 4/26/83 g
k' ACTIONS ALTERNATIVE ACTIONS (3 1 Continued) c.
Digital rod position b.
If reactor does not i
indications at zero.
trip, dispatch I
operator to manually open reactor trip and rod drive motor generator set breakers.
32 Verify turbine trip 32 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 O-Control Pumps A and B and PULL-T0-LOCK.
or
- c. Manually trip the turbine from the turbine front standard.
l 33 Verify generator trip 33 If generator trip (after 30 second time is not indicated, delay) as follows:
perform the following:
a.
GEN BKR open.
a.
Trip GEN BKR b.
GEN FIELD BKR open.
b.
Trip GEN FIELD BKR l
c.
EXC FIELD BKR open.
c.
Trip EXC FIELD l
BKR l
d.
Turbine SPEED decreasing.
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- e E0P-5 REVISION 5 g
4/26/83 ACTIONS ALTERNATIVE ACTIONS 34 Verify one' Reactor Coolant 34 If no reactor Pump running.
coolant pump runn-ing, proceed to E0P-13 35 Verify that Pressurizer 35 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 E0P-1.
36 Verify Reactor Coolant 36 ~ perform the follow-If not decreasing, System temperature decreasing to no load Tavg.
ing:
a.
Transfer STM DUMP MODE SELECT to STM PRESS mode.
O-b.
Transfer STM DUMP CNTRL to MAN.
c.
Adjust STM DUMP CNTRL to reduce Tavg.
37 Announce plant conditions over paging system.
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E0P-5 REVISION 5 4/26/83 p_
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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 42 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 O.
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.
43 Transfer NIS recorder NR-45 to one source range and one inter-l mediate range channel.
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a E0P-5 REVISION 5 4/26/83 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.
PCV-445, PZR PWR b.
MVG-800B,PZR RELIEF RELIEF ISOL c.
PCV-445B, PZR PWR c.
MVG-8000,PZR RELIEF RELIEF ISOL 45 Verify FW ISOL annunicator alarm at 564*F.
a.
Verify feedwater isolation valves close:
1 PVG-1611A, A ISOL O.
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 CRNG to minimum governor speed.
4.6 Verify STM DUMP CONTROL set to maintain 1092 psig (setpoint 8.4).
47 When Tavg = 557*F, transfer STEAM DUMP MODE SELECTOR switch to STM PRESS mode.
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a E0P-5 REVISION 5 4/26/83
'ad ACTION ALTERNATIVE ACTION 4.8 VerifythAtastableTavg 4.8 If Tavg is still has been pstablished.
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 prope.r steam dump operation.
d.
If safety injection symptoms exist, manually O.
initiate safety injection and proceed to 20P-1.
49 Verify condenser 49 If condenser is not available as follows:
available, perform the following a.
CNDSR AVAIL PERMISV c-9 light bright.
a.
Verify that POWER RELIEF SETPT l
controllers are set to maintain 1092 psig (set 8.4) point b.
Transfer the following valves to POWER RELIEF position:
c.
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REVISION 5 4/26/83 j
1' 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 EPP B 4.11 Perform the following:
a.
Place the following O.
valves in MANUAL position:
1)
Throttle the following valves to maintain steam generator at no load level of 25% narrow range span:
1)
IFV-3551, MD EFP TO SG C N.s PAGE 7 of 10
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ACTION ALTERNATIVE ACTION 4.12 Trip all operating 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 O
4 15 Verify turbine MSP and TGOP start at turbine speed of approximately 1700 rpm.
4 16 Notify load dispatcher of plant conditions.
4.17 As turbine speed approaches 900 rpm, verify turbine lift pumps are running.
4 18 Adjust ITV-4211, TURB OIL TEMP controller to maintain oil temperature of 90*F.
4.19 Verify temperature on TI-4211, TURB OIL CLR TEMP.
4.20 Secure Condensate and Feedwater Booster Pumps as desired for plant conditions.
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e E0P-5 REVISION 5 4/26/83 p
UL 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 TURN 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.
O.
4 25 Complete STP-345 001, both before and after resetting reactor trip breakers.
5.0 FINAL CONDITIONS 51 If a normal startup and return to power is permissable, l
proceed per GOP-2.
1 52 If the cause of a reactor trip cannot be determined or r
j 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 af ter consultation with Assistant Manager, Operations.
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a E0P-5 REVISION 5 4/26/83 O'
III. REFERENCES 1.
Virgil C. Summer Technical Specifications 2.
Virgil C. Summer General Operation Procedures A.
GOP-2, Plant Startup from Hot Shutdown to Power Operstion B.
00P-6, Plant Shutdown from Hot Standby to Hot Shutdown C.
GOP-7, Plant Shutdown froh Hot Shutdown to Cold Shutdown 3
E0P-13, Natural Circulation 4
80P-214, Main Turbine and Controls O.
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30p_5 ATTACHMENT I Pegs 1 of 2 REVISION.5 A1 REACTOR TRIP REC 0VERY EVALUATION i
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I. Event.
- 1. Time /Date of Reactor Trip:
i
- 2. Operating parameters at time of Reactor Trip:
A. Reactor Power B. Reactor Coolant Temperature:
- F (Tavg) i C. Reactor Coolant Pressure:
psig l
- 3. Operation (s) in progress at time of Reactor Trip: (i.e., normal operation, load changing, surveillance testing, boration or i
dilution, etc.)
1 t
- 4. Cause of Reactor Trip (how determined):
- 5. Corrective Action Taken 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 2.2) been exceeded?
YES NO 1
- 3. Does condition (s) which caused the trip still exist? YES NO l
- 4. Are there any Tech Spec LCO Action statements outstanding that j
preclude a return to power?
YES NO
- 5. Does the event require implementation of the Plant Emergency Plan?
YES N0 ts up i
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l' E0P-5 ATTACEMENT I r
Paga 2 of 2 REVISION 5
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- 6. If all questions above are answered NO, a normal startup and return to power is permissable.
Notify the Assistant Manager, Operations or Plant Manager no later than the first normal working day following the reactor trip.
- 7. If any question is answered YES, notify the Assistant
- Manager, Operations or Plant Manager immediately.
A. If question 1 is answered YES, proceed to COLD SEUTDOWN as per GOP-6 and GOP-7 B. 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.
C. If question 4 is answared YES, proceed to the mode of operation required by the appropriate Tech Spec Action statement until the LCO has been satisfied.
D. 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.
III Action Taken.
O-IV Documentation Attached l
1.
Plant Computer Alarm Printout Yes No 2.
Plant Computer Post Trip Review Printout Yes No l
3 TSC Computer Post Trip Review Printout Yes No 4.
Applicable Recorder Chart (reprodu.1tions)
Yes No
- 5. Statements from personnel involved Yes No 6
Off Normal Occurance Report Yes No
- 7. NRC prompt Notification Form Yes No Senior Reactor Operator
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l Signature Date Shift Technical Advisor
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Signature Date i
Shift Supervisor
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Signature Date O
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