ML13302A170
| ML13302A170 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/04/1981 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13302A166 | List: |
| References | |
| SO23-3-5.1, NUDOCS 8102090175 | |
| Download: ML13302A170 (14) | |
Text
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-5.1 UNITS 2 AND 3 EMERGENCY Page 1 of 12 Revision 2 EMERGENCY PLANT SHUTDOWN 1.0 SYMPTOMS 1.1 Alarms.
1.1.1 RPS Trip Path Activated.
1.1.2 Reactor Trip Undervoltage Relay Tripped.
1.1.3 Reactor Trip Circuit Breaker.
1.1.4 PPS Channel Trouble.
1.1.5 Reactor trip/pretrip.
1.1.6 Turbine-Generator trip/pretrip.
1.2 Indications.
1.2.1 Reactor trip breakers open.
1.2.2 CEA rod bottom lights on.
1.2.3 Turbine control and stop valves closed.
1.2.4 Moisture Separator Reheater line steam inlet valves closed.
1.2.5 Unit CBs open.
1.2.5.1 CB-4062 and CB-6062 for Unit 2.
1.2.5.2 CB-4152 and CB-6152 for Unit 3.
1 .3 Key Parameters.
1.3.1 Reactor power - decrease.
1.3.2 Pressurizer pressure - decrease.
1.3.3 RCS temperature - decrease.
1.3.4 Pressurizer level - expected to decrease {until nature of emer gency is known the pressurizer level should not be relied upon as an indication of RCS inventory).
1.3.5 Steam generator pressure - increase.
1.3.6 Steam generator level - decrease.
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SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 2 of 12 Revision 2 2.0 AUTOMATIC ACTIONS 2.1 Turbine trip (initiated by reactor tripped signal).
2.2 Unit CBs open.
2.3 Unit auxiliaries transfer to the reserve auxiliary transformers.
2.4 Steam Bypass Control System (SBCS) operates to establish and maintain steam generator pressure at 1000 psia.
2.5 Feedwater Control System reactor tripped override closes the main feedwater valves FCV-1111 & FCV-1121, positions the main feedwater bypass valves HV-1105 and HV-1106 for 5% flow (- 25% open) and decreases the main feed water pump speed to minimum.
2.6 Pressurizer Level Control System restores pressurizer level to the pro grammed no load setpoint (27.7% level).
2.7 Pressurizer Pressure Control System restores pressurizer pressure to 2250 psia.
3.0 IMMEDIATE OPERATOR ACTION 3.1 Verify all reactor trip breakers indicate open and reactor power is decreasing.
3.1.1 If the reactor is not tripped, push all four manual reactor trip pushbuttons.
3.2 Verify the turbine tripped and all HP Stop and HP Governor valves are closed.
3.2.1 If the turbine is not tripped, push the manual trip pushbutton.
3.3 Verify the unit output breakers open on low forward power as indicated by receipt of the "Generator Protection Trip" alarm and verify turbine speed is decreasing after the output breakers open.
3.3.1 If the unit output breakers fail to open within one (1) minute after the turbine trips, manually open the unit output breakers.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 3 of 12 Revision 2 3.0 IMMEDIATE OPERATOR ACTION (Continued) 3.4 Verify unit auxiliaries have transferred to the reserve auxiliary transformers.
3.4.1 If the unit auxiliaries have not transferred, manually transfer them to the reserve auxiliary transformer.
3.5 Verify the SBCS is controlling steam generator pressure at 1000 psia.
3.5.1 If condenser vacuum is lost or if the MSIVs are closed, use the atmospheric dump valves to control steam generator pressure at ' 1000 psia.
3.6 Verify main feedwater flow is not less than 5% on FR-1011 and FR-1021.
3.6.1 If main feedwater flow is less than 5%, actuate EFAS
- 1 and EFAS #2.
3.7 Use the Public Address System to notify on-site personnel con cerning the nature of the emergency.
4.0 SUBSEQUENT OPERATOR ACTION INITIALS
- CAUTION: Do not place systems in "manual" unless misoperation in "automatic" is apparent. Systems placed in "manual" must be checked frequently to ensure proper operation.
4.1 Verify all immediate operator actions have been initiated as follows:
4.1.1 If more than one CEA has not fully inserted, com mence emergency boration per Emergency Operating Instruction S023-3-5.10, "Emergency Boration of the Reactor Coolant System" performing applicable steps concurrently with the steps in this instruction..
- The initial column is an optional operator aid and is intended to be used as follows:
Initial each completed action. Do not write N.A. Leave blank, items that are not applicable. Proceed through the instruction performing all applicable steps fre quently re-checking those steps passed over to ensure action is taken when applicable.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 4 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.1.2 If reactor power prompt drop does not reduce reactor power to less than 6% in less than 10 seconds or 10 or more CEAs have not fully inserted, carry out Emergency Operating Instruction S023-3-5.3, "Re actor Protection System Failure" and terminate use of this instruction.
4.1.3 If any HP Stop and its associated in line HP Gover nor valve remains.open, close the MSIVs.
4.1.4 If unable to trip the turbine from the control room dispatch an operator to open the DC supply breaker to the Unitized Actuator dump valve solenoids.
4.1.5 Within one minute after the turbine trips, verify open or open the Unit Auxiliary Transformer low side breakers, then verify open or open the Unit output breakers.
4.1.6 Verify energized or energize the following 6.9KV and 4KV Busses.
4.1.6.1 A01 and A02..
4.1.6.1.1 If A01 and A02 cannot be energized, use Operating Instruction S023-3-2.31, "Nat ural Circulation Guidelines", to confirm that natural circulation has been estab lished performing applicable steps con currently with the steps in this instruction.
4.1.6.2 A03 and A07..
4.1.6.2.1 If A03 and A07 cannot be energized, use the atmospheric steam dumps and the auxiliary feedwater system to control steam generator pressure and level.
4.1.6.3 A08 and A09.
4.1.6.4 A04 and A06.
4.1.6.4.1 If A04 and A06 cannot be energized, carry out Emergency Operating Instruction S023 3-5-4, "Complete Loss of Offsite Electrical Power Concurrent with a Turbine Trip", per forming applicable steps concurrently with the steps in this instruction.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 5 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.1.6.5 If offsite power is available to the opposite unit and if A01, A02, A03, A07, A08 or A09 busses cannot be energized, carry out Emergency Operating Instruction S023-3-5.4.1, "Loss of Offsite Elec trical Power to a Unit Concurrent with a Turbine Trip", performing applicable steps concurrently with the steps in this instruction.
4.1.6.6 If all offsite AC power is lost, carry out Emer gency Operating Instruction S023-3-5.4, "Complete Loss of Offsite Electrical Power Concurrent with a Turbine Trip", performing applicable steps con currently with the steps in this instruction.
4.1.7 If EFAS #1 is actuated, check flow on FI-4725. If flow is less than 700 gpm, verify started or start auxiliary feedwater pumps P-141 and P-140, open aux iliary feedwater control valves HV-4706 and HV-4713 and isolation valves HV-4715 and HV-4731.
4.1.8 If EFAS #2 is actuated, check flow on FI-4720. If flow is less than 700 gpm, verify started or start auxiliary feedwater pumps P-504 and P-140, open aux iliary feedwater control valves HV-4705 and HV-4712, and isolation valves HV-4714 and HV-4730.
4.1.9 If unable to establish at least 350 gpm feedwater flow to each steam generator, perform the following:
4.1.9.1 If steam generator pressure has rapidly decreased to the MSIS setpoint, go to Emergency Operating Instruction S023-3-5.9, "Steam Line Rupture",
performing applicable steps concurrently with the steps in this instruction.
4.1.9.2 If steam generator pressure is gradually de creasing or increasing, go to Emergency Oper ating Instruction S023-3-5.30, "Loss of Feed water", performing applicable steps concur rently with the steps in this instruction.
4.1.9.3 If unable to establish feedwater flow to at least one steam generator, establish emergency feed water flow by performing the following:
4.1.9.3.1 Verify aligned or align auxiliary feed water pump's manual valving.
4.1.9.3.2 Vent auxiliary feedwater piping and pump casings.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 6 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.2 Determine if the RCS pressure boundary is intact by verification of the following:
4.2.1 On PR-010OA/B, check that pressurizer pressure is be tween .2225 psia and 2275 psia.
4.2.1.1 If pressurizer pressure is not between 2225 psia and 2275 psia, attempt to establish and maintain the required pressurizer pressure per Emergency Operating Instruction 5023-3-5.17, "Pressurizer Pressure Control System Malfunction". _
4.2.2 On LR-011OA/B, check that pressurizer level is trending to 27.7% level (programmed setpoint for no load Tavg)._
4.2.2.1 If pressurizer level is not trending toward 27.7% level, attempt to establish and maintain the required level per Emergency Operating Instruction S023-3-5.24, "Loss of Pressurizer Level Control".
4.2.3 Check that the pressurizer safety valves indicate closed.
4.2.4 On LI-0226A check that the Volume Control Tank level is between 37% and 51%.
4.2.4.1 If VCT level is not between 37% and 51%, verify the makeup system is functioning properly per Operating Instruction S023-3-2.2, "Makeup Operations".
4.2.5 On TI-9903-1 and TI-9911-2 check that the containment temperature is between 800 F - 120 0 F.
4.2.5.1 If containment temperature is not between 800 F 120 0 F, verify the containment normal heat removal system is functioning properly per Operating Instruction S023-1-4, "Containment Normal Heat Removal".
4.2.6 On PI-0351-1, PI-0351-2, PI-0351-3 and PI-0351-4 check that the containment pressure is between
+ 1.5 psig and - 0.3 psig.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 7 of 12 Revision 2' 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.2.7 On LI-5853-1 and LI-5853-2 check that the containment normal sump level is not increasing.
4.2.8 At Radiation Control Panel L-103 check that the con tainment activity is within limits.
Indicator Limits RI-7804A1 & RI-7807A2 Iodine-less than 4.6xlO 2 CPM RI-7804B1 & RI-7807B2 Particulate-less than 5.7 x 102CPM RI-7804C1 & RI-7807C2 Gaseous-less than 8.OxlO 5 CPM _
4.3 If any parameter in Step 4.2.above fails to respond as indi cated or does not return to its specified range after com pletion of prescribed action, go to attached Figures 1 and 2 to identify the event in progress.
4.3.1 If use of another Emergency Instruction is indicated, in conjunction with "Emergency Plant Shutdown", per form all applicable steps concurrently with the steps in this instruction.
4.4 Use Operating Instruction S023-3-2.30, "Determination of Ade quate Core Cooling" to confirm that conditions are not trending toward an inadequate core cooling event performing applicable steps concurrently with the steps in this instruction.
4.5 If main feedwater is available, verify proper operation of the Reactor Tripped/Feedwater Control System Override by completing the following:
4.5.1 Verify that the main feedwater valves (FCV-1111 and FCV-1121) indicate closed or closing on HIC-1111 and HIC-1121. If either main feedwater valve does not indicate closed or closing, complete the following:
4.5.1.1 On HIC-1111 (for SG #1) and/or HIC-1121 (for SG #2) use the manual control knob to match the manual output indicator with the auto output indicator.
4.5.1.2 Transfer the auto/manual transfer switch to manual.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 8 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.5.1.3 Using the manual control knob decrease the valve position to zero.
4.5.1.4 If FCV-1111 remains open, close HV-4051 and if FCV-1121 remains open, close HV-4047.
4.5.2 Verify that the main feedwater bypass valves (HV-1105 and HV-1106) indicate closing to or at the 5% flow position (V 25% open position) on HIC-1105 and HIC 1106. If either main feedwater bypass valve does not indicate closing to or at the (25%) open position, complete the following:
4.5.2.1 On HIC-1105 (for SG #1) and/or HIC-1106 (for SG #2) use the manual control knob to match the manual output indicator with the auto out put indicator.
4.5.2.2 Transfer the auto/manual transfer switch to manual.
CAUTION: Avoid overfeeding the steam genrators to prevent an undesirable cooldown (Tavg below 540'F and decreasing) of the RCS.
4.5.2.3 Using the manual control knob position the affec ted valve(s) to establish a gradual (less than 2%
per minute) level recovery to -.65% steam gener ator narrow range level indication.
4.5.3 Verify that main feedwater pump's speed is decreasing to or at "u 3200 rpm as indicated on SR-4500 and SR-4501. If either main feedwater pump does not indicate speed is decreasing to or at -.3200.rpm, complete the following:
4.5.3.1 On HIC-1108 (FW Pump Speed Setpoint K006) and/
or HIC-1107 (FW Pump Speed Setpoint K005) use the manual control knob to match the manual output indicator with the auto output indicator.
4.5.3.2 Transfer the auto/manual transfer switch to manual.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page 9 of 12
- Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.5.3.3 Using the manual control knob set the affected main feedwater pump(s) speed to n 3200 rpm as indicated on SR-4500 (K-006) and/or SR-4051 (K-005).
4.6 If there is an undesirable cooldown of the RCS (Tavg below 540 0 F and decreasing), complete the following:
4.6.1 If main feedwater is available, take manual control of HIC-1105 and HIC-1106 and reduce the rate of steam generator level recovery as follows:
4.6.1.1 On HIC-1105 and HIC-1106 use the manual control knob to match the manual output indicator with the auto output indicator.
4.6.1.2 Transfer the auto/manual transfer switch to manual.
CAUTION: Do not reduce feedwater flow below the requirement to maintain a constant or increasing level.
4.6.1.3 Using the manual control knob position the valves to establish a gradual (less than 2% per minute) level recovery to -,65% steam generator narrow range level indication.
4.7 If there is an exces.sive cooldown of the RCS (Tavg below 530'F and decreasing) caused by excessive auxiliary feedwater ad dition, reduce the number of operating auxiliary feedwater pumps as follows (listed in order of preference):
4.7.1 If P-140 is.supplying both steam generators, then override and stop P-141 and P-504.
4.7.1.1 If steam generator level cannot be maintained, restart P-141 and/or P-504 to re-establish adequate flow.
4.7.2 If both P-141 and P-504 are supplying their respec tive steam generators,then override and stop P-140.
4.7.2.1 If steam generator level cannot be maintained, restart P-140.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 EMERGENCY Page'10 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.8 After steam generator narrow range levels reach 30%, reset EFAS-1 and EFAS-2, at the Train A and Train B ESFAS Aux iliary Relay Cabinets.
NOTE: Reseting EFAS-1 and EFAS-2 disables the override stop signals, re-aligning EFAS for automatic actu ation of the auxiliary feedwater pumps and valves.
(Failure to do so could result in a loss of heat sink.)
4.8.1 When EFAS-l is reset, verify open or open HV-4731.
Provided HV-4731 is open, verify closed or close HV-4715.
4.8.1.1 If HV-4731 cannot be opened, open HV-4715.
4.8.2 When EFAS-2 is reset, verify open or open HV-4714.
Provided HV-4714 is open, verify closed or close HV-4730.
4.8.2.1 If HV-4714 cannot be opened, open HV-4730.
NOTE: HV-4730 and HV-4715 should remain closed except when an EFAS is present or during surveillance testing. This avoids a steam line break scenario concurrent with the loss of 125 VDC busses Dl or D2 which would result in feeding a rup tured steam generator.
4.8.3 If the steam generator blowdown is necessary for chem istry control, or to facilitate steam generator level reduction, establish steam generator blowdown per Operating Instruction S023-9-4, "Steam Generator Blowdown Processing System".
NOTE: EFAS isolates blowdown.
4.9 Establish auxiliary feedwater flow to each steam generator and secure the main feedwater flow as follows:
4.9.1 Verify started or start auxiliary feedwater pump P-141.
4.9.1.1 Jog open or close as necessary HV-4713 by inter mittently depressing HS-4713-1 to establish a gradual (less than 2% per minute) S/G #1 level recovery to % 65% narrow range level.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-5.1 UNITS 2 and 3 EMERGENCY Page 11 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.9.1.2 If P-141 cannot be started or if HV-4713 can not be positioned as desired, verify started or start P-140.
4.9.1.2.1 Jog open or closed as necessary HV-4706 by intermittently depressing HS-4706-2 to. establish a gradual S/G #1 level re covery to - 65% narrow range level.
4.9.1.3 Close main feedwater bypass valve HV-1105 using HIC-1105._
4.9.2 Verify started or start auxiliary feedwater pump P-504.
4.9.2.1 Jog open or closed as necessary HV-4712 by intermittently depressing HS-4712-1 to es tablish a gradual (less than 2% per minute)
S/G #2 level recovery to -u65% narrow range level.
4.9.2.2 If P-504 cannot be started or if HV-4712 can not be positioned as desired, verify started or start P-140.
4.9.2.2.1 Jog open or closed as necessary HV-4705 by intermittently depressing HS-4705-2 to es tablish a gradual S/G #2 level recovery to , 65% narrow range level.
4.9.2.3 Close main feedwater bypass valve HV-1106 using HIC-1106.
4.9.3 Stop main feedwater pumps per Operating Instruction S023-2-1, "Main Feedwater Pump and Turbine Operation".
4.10 Place NI audible count rate in operation to monitor the change in shutdown margin.
4.11 Verify a shutdown margin greater than 5.15% AK/K on the Plant Monitoring System or by Operating Instruction S023-3-3.29, "Determination of Shutdown Margin".
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.1 UNITS 2 and 3 - EMERGENCY Page 12 of 12 Revision 2 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.11.1 If shutdown margin is less than 5.15% AK/K, immediately start emergency boration per Emergency Operating In struction S023-3-5.10, "Emergency Boration of the RCS" performing applicable steps concurrently with the steps in this instruction.
4.12 Carry out turbine shutdown per Operating Instruction S023-10-2, "Turbine Shutdown" performing applicable steps concurrently with the steps in this instruction.
4.13 Upon a unit trip, the Watch Engineer shall notify the "duty" Station Administrator and Shift Technical Advisor and discuss the situation. If unable to contact any Station Administrator in the normal reporting chain within fifteen (15) minutes following the event, notify the NRC via .the red phone.
4.13.1 Notify the Systems Operating Supervisor concerning the nature of the emergency.
4.14 If extended shutdown is anticipated, continue operations per Operating Instruction S023-5-1.5, "Plant Shutdown from Hot Standby to Cold" and terminate the use of this instruction.
4.15 If plant startup is anticipated, continue operations per Operating Instruction S023-5-1 .3, "Plant Startup from Hot Standby to Minimum Load" and terminate the use of this instruction.
5.0 ATTACHMENTS 5.1 Figure 1, Small Break Accident Identification.
5.2 Figure 2, Large Break Accident Identification.
H. E. MORGAN Superintendent Units 2 and 3 APPROVED:
J. M. CURRAN Plant Manager VBF/sa
ACCIDENT IDENTIF TION SMALL BREAK PRESSURIZER PRESSURE AND LEVEL I DECREASING AT A SLOW RATE OBSERVE T-AVG AND REACTOR POWER, T-AVG DECREASING & RX POWER INCREASING I-AVG AND REACTUR POWER CONSTANT OBSERVE TURBINE LOAD LOCA OR .G. TUBE RUPT CONSTANT OR DECREASED NTAINMENT EXCESS STEAM
[ TEMPERATURE, HUMIDITY AND SUMP LEVEL
.FLOW ACCIDENT OBSRV. CONT. PRES., TEMP.,
UMDITY AND SUMP LEVEL S.G. TUBE INCREASING NORMAL LOCA OUTSIDE
- 4. 4,CONTAINMENT STEAM BREAK STEAM BREAK INSIDE OUTSIDE OBSRV-lNC ACT IN CONTAINMENT CONTAINMENT MN STM LNS, OR STEAM DUMP BLWDl SMPL RD OR TURBINE MON, CON AIR SEE STEAM LINE BYPASS VALVE EJECTOREXHAUST RUPTURE EMERG.* OPEN I 0.1. S023-3-5.9 J 4, OBSERVE STEAM DUMP & BYPASS VALVE POSITION S.G. TUBE SE[ CVCS LOSS OF
'INDICATION RUPTURE COOLANT ACCIENT OPW
'OPEN 03352 01. 5023-3-5.28 SEE STEAM LINE RUPTURE EMER.
0.1. 023-3-5.9C
FlE 2 ACCIDENT IDENTIFICATION LARGE BREAK PRESSURIZER PRESSURE DECREASING OR UNEXPLAINED CHANGE IN PRESSURIZER LEVEL OBSERVE STEAM GENERATOR PRESSURES ABNORMALLY LOW IN ONE STEAM GENERATOR PRES URE INITIALLY NORMAL OR BOTH STEAM GENERATORS OR RISING.THEN SUBSEQUENTLY RETURNS TO NO-LOAD VALVE AFTER A REACTOR TRIP STEAM LINE RUPTURE fLOCA OR.S.G. TUBE RUPTURE OBSERVE CONTAINMENT PRESSURE, RADIATION AND SUMP LEVEL ' OBSERVE CONTAINMENT PRESSURE, RADIATION AND SUMP LEVEL CONTAINMENT PRESSURE NORMAL 4v INCREASING, NO INCREASING CONTAINMENT NORMA ICREASED STEAM BREAK PRESSURE AND ACTIVITY OUTSIDE +
STEAM BREAK INSIDE CONTAINMENT LOCA SEE EMERG. VERIFY INCREASED CONTAINMENT, SEE SEE EMERG. 01 0.I. S023-3-5.6 ACTIVITY IN MAIN EMERGENCY 0.1. S023-3-5.9 . STEAM LINES, 5023-3-5.9 _BLOWDOWN SAMPLE RADIATION MONITOR OR CONDENSER AIR EJECTOR EXHAUST S.G. TUBE RUPTURE SEE EMERGENCY
.0.I. 5023-3-5.29