ML13302A168
| ML13302A168 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/04/1981 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13302A166 | List: |
| References | |
| SO23-3-5.29, NUDOCS 8102090161 | |
| Download: ML13302A168 (34) | |
Text
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTIO.N 40 3-3-5.29 UNITS 2 and 3 EMERGENCY 'R1 of 18 EkA4AM P TIO
~A~QRTUBE /RUPTURb 1.0 SYMPTOMS 1.1 Alarms 1.1.1 Steam Generator Blowdown Monitor.
1.1.2 Condenser Air Ejector Airborne Radiation Hi.
1.1.3 Main Steam Line Radiation Hi.
1.1.4 Pressurizer Pressure Level Error Lo.
1.1.5 Pressurizer Pressure Deviation Hi/Lo.
1.1.6 Volume Control Tank T077 Level Hi/Lo.
1.2 Indications 1.2.1 Increased radiation level indicated on RR-7874-1 and RR-7875-1, Main Steam Line Radiation Monitors, Panel L-405.
1.2.2 Increased activity on RR-6753 and RR-6759, Steam Generator Blowdown Sample Radioactivity Monitors, Panel CR-62.
1.2.3 Increasing activity at the condenser air ejector exhaust on RI-7818 at the Process and Effluent Radiation Monitor, Panel L-103.
1.2.4 Decreasing pressurizer level.
1.2.5 Initial increase in affected steam generator level followed by return to programmed level setpoint (may not be observable).
1.2.6 Feedwater flow less than steam flow on affected steam generator (may not be observable).
1.2.7 Unbalanced charging and letdown flows.
1.2.8 Increasing activity and presence of boric acid in steam generator samples.
8 102090 II
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 2 of 18 Revision 1 2.0 AUTOMATIC ACTION (some or all of the following may occur)
NOTE: The time delay for the initiation of these events varies considerably depending on the size of the break.
2.1 A steam generator blowdown monitor will close HV-3773, BPS Neut. Sump Overboard valve.
2.2 Letdown control valves close to a minimum value and backup charging pumps are started as pressurizer level decreases.
First backup charging pump starts at - 2.5% level deviation and second backup charging pump starts at - 3.9% level deviation.
2.3 Reactor trip, if pressurizer pressure decreases to DNBR setpoint.
2.4 If pressurizer pressure drops below 1806 psia, a SIAS and CCAS will be generated.
2.5 Turbine trip (initiated by reactor tripped signal).
3.0 IMMEDIATE OPERATOR ACTION 3.1 Verify containment pressure, temperature, radiation and sump levels are normal and not increasing, to ensure that the event in progress is not a LOCA.
3.2 Verify the Pressurizer Level Control System is functioning to restore pressurizer level to the programmed setpoint (27.7% to 57.7% depending on Tavg.)
3.2.1 If not, start additional charging pumps and reduce or isolate letdown to restore pressurizer level.
3.2.2 If pressurizer level can be maintained, reduce turbine load and reactor power at a rate which will not cause a reactor trip.
3.2.3 If pressurizer level 6annot be maintained, verify the reactor tripped or trip the reactor.
3.2.3.1 Carry out all immediate and subsequent post trip actions per Emergency Operating Instruction S023-3-5.1, "Emer gency Plant Shutdown".
3.2.4 Use the public address system to notify on-site personnel con concerning the nature of the emergency.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 3 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION INITIALS
- NOTE: Anticipated Scenario Explanation:
If the SGTR causes leakage in excess of the capacity of the charging system, pressurizer pressure will decrease, causing a DNBR trip. The subsequent cooldown following the trip combined with the continued leakage into the steam system will result in SIAS and CCAS actuation on low RCS pressure. Continued RCS depressurization will result in the RCS reaching saturated conditions. The possibility then exists for void formation in the RCS which may impede heat transfer and/or render the pres surizer level indication invalid as an indicator of RCS inventory.
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 Go to Figure 1 and 2 attached and verify that the event in progress is a SGTR.
4.1.1.1 If use of another Emergency Instruction is indi cated, in conjunction with a SGTR, perform all applicable steps concurrently with the steps in this instruction.
4.1.1.2 If a SGTR is not in progress, use the indicated Emergency Instruction and terminate use of this instruction. _
- The initial colum 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 ap plicable. Proceed through the instruction performing all applicable steps frequently rechecking those steps passed over to ensure action is taken when applicable.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 4 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.1.2 Verify the Pressurizer Level Control System is func tioning to restore pressurizer level to the programmed setpoint (27.7% to 57.7% depending on Tavg).
4.1.2.1 If not, start additional charging pumps and re duce or isolate letdown to restore pressurizer level.
4.1.2.2 If pressurizer level can be maintained, proceed to Step 4.1.3 of this instruction.
4.1.2.3 If pressurizer level cannot be maintained, manually trip the reactor and proceed to Step 4.1 .4 of this instruction.
4.1.3 Reduce turbine load and reactor power to 30% at the maximum rate which will not cause a reactor trip, as follows:
4.1.3.1 Use the turbine CVOL to reduce turbine load.
4.1 .3.2 Use emergency boration to reduce reactor power.
If reactor power reduction lags turbine load reduction by more than 10% or if Tavg exceeds Tref by more than 50 F, use CEA insertion in conjunction with emergency boration to re duce reactor power.
4.1.3.3 Verify the Pressurizer Pressure Control System is automatically maintaining pressurizer pressure between 2225 psia and 2275 psia. If not, take manual control of the pressurizer heaters and sprays per Step 4.2 of Emergency Operating In struction S023-3-5.17, "Pressurizer Pressure Control System Malfunction", and restore pres surizer pressure to u 2250 psia performing applicable steps concurrently with the steps in this instruction.
4.1.3.4 Isolate steam generator blowdown by closing the blowdown isolation valves.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 5 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.1.3.5 With "Condenser Air Ejector Airborne Radiation Hi" alarm, place the air ejector exhaust unit in the "direct" mode of service, per Operating In struction S023-10-7, "Procedure to Establish Condenser Vacuum", performing applicable steps concurrently with the steps in this instruction.
4.1.3.6 Verify the feedwater control system is main taining - 65% steam generator narrow range level.
If not, take manual control of the feedwater con trol system and maintain % 65% narrow range level.
4.1.3.7 When reactor power is reduced to 30%, manually trip the reactor.
4.1.4 With a reactor trip condition reached, or with a re actor trip, carry out all immediate and subsequent post trip actions per Emergency Operating Instruc tion S023-3-5.1, "Emergency Plant Shutdown", per forming applicable steps concurrently with the steps in this instruction.
4.1 .5 If pressurizer pressure decreases below 1806 psia, verify completed or~complete the following:
4.1.5.1 Verify Train A and Train B SIAS and CCAS actu ation alarms are received. If not, manually actuate SIAS and CCAS.
4.1.5.1.1 If manual actuation from the control room is not successful, dispatch an operator to Train A and Train B Auxiliary Relay Cab inets and open the associated trip leg circuit breakers.
4.1.5.2 After a SIAS due to low pressurizer pressure and as soon as possible after it has been verified that all CEAs have been fully inserted for at least five (5) seconds, stop all operating RCPs.
4.1.5.2.1 If SIAS is actuated due to containment high pressure, then when pressurizer pressure decreases to the SIAS setpoint, stop all operating RCPs.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-5.29 UNITS 2 and 3 EMERGENCY Page 6 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.1.5.2.2 After any SIAS or CIAS, then within 30 min utes restore CCW to the RCPs per Emergency Operating Instruction S023-3-5.26, "Loss of Component Cooling Water to a RCP", per forming applicable steps concurrently with the steps in this instruction.
4.1.5.3 Verify the electric driven auxiliary feedwater pumps restart 30 seconds after SIAS actuation due to load sequencing. If not, manually restart them. .
4.1.5.4 Verify aligned or align all SIAS and CCAS af fected components per the Actuated Alignment Check-Off Lists contained in Operating Instruction S023-3-2.7, "Safety Injection System Operation".
4.1.5.5 When pressurizer pressure decreases below the shutoff head (- 1450 psia) of the HPSI pumps, verify HPSI flow to the cold legs from at least one train.
4.1.6 If not done previously (during the turbine load re duction), perform the following:
4.1.6.1 Isolate steam generator blowdown by closing the blowdown isolation valves.
4.1.6.2 With "Condenser Air Ejector Airborne Radiation Hi" alarm, place the air ejector exhaust unit in the "direct" mode of service per Operating Instruction S023-10-7, "Procedure to Establish Condenser Vacuum", performing applicable steps concurrently with the steps in this instruction.
4.2 If all RCPs are stopped, verify that natural circulation has been established per Operating Instruction S023-3-2.31, "Natural Circulation Guidelines", performing applicable steps concurrently with the steps in this instruction.
4.3 Use Operating Instruction S023-3-2.30, "Determination of Adequate Core Cooling", to confirm that conditions are not trending to ward an inadequate core cooling event performing applicable steps concurrently with the steps in this instruction.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 7 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION. (Continued) INITIALS 4.4 Perform the following to minimize the transfer of condensate activity:
4.4.1 Close LV-3245, condenser draw.off valve.
4.4.2 Redirect the turbine sumps as follows:
4.4.2.1 Close HV-5849, discharge to oily waste sump.
4.4.2.2 Open HV-5850, discharge to radwaste sump.
4.5 Establish radiation control areas in the area of blowdown pro cessing system to minimize personnel exposure to surface con tamination, radiation and airborne contamination.
4.6 Determine which steam generator has the tube rupture by per forming the following:
4.6.1 Checking main steam line radiation monitor recorders RR-7875-1 and RR-7875-1 on Pnl L-405 for increased activity.
4.6.2 Checking steam generator blowdown sample radioactivity monitor recorders RR-6759 and RR-6753 on Pnl CR-62 for increased activity.
4.6.3 Sampling steam generators for activity and presence of boron.
4.6.4 Possible unexplained changes in steam generator level on steam generator level recorders.
4.6.5 Possible unexplained decrease in steam generator feedwater flow as compared to steam flow on steam flow/feedflow recorders.
4.6.6 If the affected steam generator has not been iden tified by the above methods, use the level rise method contained in Step 4.6.
CAUTION: Do not isolate the steam generator until hot leg temperatures are 535 0 F plus or minus 10oF.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 8 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.7 Cooldown the RCS until hot leg temperatures are 535 0 F, plus or minus 10aF as follows: (Do not exceed a cooldown rate of 750 F/hr.)
4.7.1 Commence emergency boration per Emergency Operating Instruction S023-3-5.10, "Emergency Boration of the RCS", until a cold shutdown boron concentration has been reached performing applicable steps concur rently with the steps in this instruction.
4.7.1.1 Use Operating Instruction S023-3-3.29, "Deter mination of Shutdown Margin", to calculate the required boron concentration.
4.7.1.2 Sample the RCS and Pressurizer and determine that the desired boron concentration has been reached prior to reducing Thot below 525oF.
4.7.2 If the SBCS is available, establish and maintain a RCS cooldown per Operating Instruction S023-3-2.18, "Steam Bypass System Operation", performing applicable steps concurrently with the steps in this instruction.
4.7.2.1 Lower the variable MSIS setpoints when the pre trip alarms are received.
4.7.3 If the SBCS is not available, cooldown the RCS using the atmospheric steam dump on the unaffected steam generator, if known.
4.7.4 If the SBCS is not available, and both steam gener ators are affected, or the affected steam generator has not been identified, notify the NRC via the red phone.
4.7.4.1 Unless directed otherwise by the NRC, cooldown the RCS using the atmospheric steam dump on the unsuspected or least affected steam generator.
4.7.4.2 Closely monitor the blowdown and main steam line radiation indicators for indications of in creased activity to either identify the af fected steam generator or determine which steam generator is least affected.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29
) UNITS 2 and 3 EMERGENCY Revision 1 Page 9 of 18 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.8 After the RCS hot legs have been cooled down to 535 0 F plus or minus 100 F, isolate the affected (i.e. most affected or suspec ted) steam generator as follows:
4.8.1 Close the Main Steam Isolation Valve associated with the steam generator being isolated.
4.8.1.1 HV-8204 for SG-l.
4.8.1.2 HV-8205 for SG-2.
4.8.2 Close the Main Steam Isolation Valve Bypass Valve as sociated with the steam generator being isolated.
4.8.2.1 HV-8202 for SG-l.
4.8.2.2 HV-8203 for SG-2.
4.8.3 Close the Main Feedwater Isolation Valves, associated with the steam generator being isolated.
4.8.3.1 HV-4052 for SG-l.
4.8.3.2 HV-4048 for SG-2._
4.8.4 Close the Auxiliary Feedwater Isolation Valves in cluding the steam driven pump steam supply valve, associated with the steam generator being isolated.
4.8.4.1 HV-4714, HV-4730 and HV-8200 for SG-1.
4.8.4.2 HV-4715, HV-4731 and HV-8201 for SG-2.
4.8.5 If the affected steam generator has not been iden tified, monitor the isolated steam generator water level.
NOTE: The level in the affected steam generator will rise due tothe leak.
4.8.5.1 If the level does not rise within. 30 minutes, or other indications point to the possibility of having isolated the wrong (i.e. non-leaking) steam generator, return the isolated steam gen erator to normal'and isolate the other steam generator.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 10 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.9 The Watch Engineer shall notify the "duty" Station Administrator and Shift Technical Advisor and discuss the situation.
4.9.1 An assessment of the plant status and safety shall be made and the event classified per Table 4-1 of the SONGS 2 & 3 Emergency Plan.
4.9.2 If an emergency is declared (Alert, Site or General) use the following Emergency Procedures to implement the SONGS 2 & 3 Emergency Plan.
4.9.2.1 Alert - S023(later) 4.9.2.2 Site - S023(later) 4.9.2.3 General - S023(later) 4.9.3 If unable to contact any Station Administrator in the normal reporting chain within fifteen (15) minutes fol lowing the declared emergency, notify the-NRC via the red phone.
4.9.4 Notify the Systems Operating Supervisor concerning the nature of the emergency.
4.10 After isolating the affected or most affected steam generator, commence RCS cooldown and depressurization as quickly as pos sible. Do not exceed a cooldown rate of 750 F/hr.
4.10.1 Use the SBCS, if available, and cooldown per Oper ating Instruction S023-5-1.5, "Plant Shutdown from Hot Standby to Cold", performing applicable steps concurrently with the steps in this instruction.
4.10.2 If the SBCS is not available, use the atmospheric steam dump on the unaffected or least affected steam generator.
4.10.3 If the RCPs have been tripped, cooldown using natural circulation per Operating Instruction S023 3-2.31, "Natural Circulation Guidelines", performing applicable steps concurrently with the steps in this instruction.
SAN ONOFRE NULCEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 11 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.11 During the initial phase of the cooldown (Thot above 500'F) establish and maintain 500 F subcooling in the RCS.
4.11.1 Use the Subcooled Margin Monitor indicators as the primary method to determine RCS subcooling.
4.11.2 Use pressurizer pressure and Thot, or incore thermo couples if indicating a higher temperature, as the secondary method to determine RCS subcool-ing.
4.11.3 Use pressurizer heaters and sprays to control and lower pressurizer pressure in order to maintain 500 F subcooling as the RCS cools down per Emergency Operating Instruction S023-3-5.17, "Pressurizer Pressure Control System Malfunction", performing applicable steps concurrently with the steps in this instruction.
4.11 .4 If SIAS has not been actuated, and at least 500 F RCS subcooling is being maintained, lower the variable SIAS setpoints when the pretrip alarms are received.
4.11 .5 If SIAS was actuated, then when pressurizer pressure decreases to the shutoff head of the HPSI pumps perform the following:
4.11 .5.1 Verify RCS subcooled margin is at least 500 F.
4.11.5.2 Verify pressurizer level is between 28% and 57%.
4.11.5.3 Verify RCS cold leg temperatures are stable or decreasing.
4.11.5.4 When the above conditions are satisfied, throttle HPSI flow as necessary to maintain pressurizer level between 28% and 57%.
4.11.5.5 If, due to the reduction in primary to second dary differential pressure, the leakrate de creases to within the capacity of the charging system, stop the HPSI pumps.
4.11.5.6 If at least 500 F subcooling cannot be maintained, restart the HPSI pumps and re-open the throttled HPSI valves. _
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 12 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.11.6 When Thot reaches 500 0 F, allow the subcooled margin to increase as the cooldown progresses by maintaining pressurizer pressure nu 50 psi above the isolated steam generator secondary pressure, to prevent RCS boron dilution.
4.12 If SIS is operating, terminate emergency boration of the RCS within 30 minutes of the time that SIS initiated emergency boration as follows:
4.12.1 Override and stop the charging pumps and boric acid makeup pumps.
4.12.2 If pressurizer pressure is above the shutoff head of the HPSI pumps, return the charging pumps to service as follows:
4.12.2.1 Open LV-0277C, gravity feed valve from RWST.
4.12.2.2 Verify closed or close LV-0277B (VCT discharge).
4.12.2.3 If the RCS is subcooled, start and stop the charging pumps as necessary to maintain pres surizer level between 28% and 57%. If the RCS is not subcooled, run all available charging pumps continuously until 500 F sub cooling can be maintained.
NOTE: In the above charging pump align ment HV-9247 (BAMU pump discharge),
HV-9235 and HV-9240 (BAMT gravity feed), remain open for a backup supply. Since the RWST elevation head is greater than the BAMT elevation head, the Boric Acid line check valves will close.
4.13 When the following conditions are established, reset SIAS per Step 4.14 of this instruction.
4.13.1 RCS hot and cold leg temperatures are at least 500 F subcooled.
4.13.1.1 Use the Subcooled Margin Monitor indicators as the primary method of determining RCS subcooling.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 13 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.13.1.2 Use pressurizer pressure and Thot, or incore thermocouples if indicating a higher temper ature, as a backup method for determining subcooling.
4.13.2 Both pressurizer level safety channels indicate a level greater than 28% and levels are stable or increasing.
4.14 When all of the conditions in Step 4.13 of this instruction are satisfied, proceed as follows:
4.14.1 Lower the SIAS pressurizer pressure setpoint on all four safety related channels below the existing pres surizer pressure using the "Low Prz Press Setpoint Reset" on the PPS Remote Control Modules.
4.14.2 Unlock (arm) and depress the SIAS and CCAS reset push bottons at the Plant Protection Panel.
4.14.3 Depress the Train A SIAS and CCAS reset pushbuttons and Train B SIAS and CCAS reset pushbuttons at the ESFAS Auxiliary Relay Cabinets.
4.14.4 Stop the LPSI, HPSI and Containment Spray Pumps.
4.14.5 Restart the HPSI pumps as necessary to maintain a subcooled margin of 500 F.
4.15 If offsite power is available, establish normal charging and letdown as per Operating Instruction S023-3-2.1, "CVCS Charging
.and Letdown" and Operating Instruction S023-3-2.2, "Makeup Operations", performing steps concurrently with the steps in this instruction.
4.15.1 If offsite power is not available, line up charging pump suction to gravity feed from the RWST to main tain pressurizer level as follows:
4.15.1.1 Open LV-0277C, gravity feed from RWST.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 14 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.15.1.2 Verify closed or close the following:
4.15.1 .2.1 LV-0227B, VCT 'discharge.
4.15.1.2.2 HV-9247, BAMP discharge.
4.15.1.2.3 HV-9235 and HV-9240, BAMT gravity feed.
4.16 If RCPs were stopped, restart the RCPs in the unaffected loop per Operating Instruction S023-3-1.7, "RCP Operation".
4.16.1 If a RCP is restarted., continue cooldown per Oper ating Instruction 5023-5-1.5, "Plant Shutdown from Hot Standby to Cold", performing the applicable steps concurrently with the steps in this instruction.
4.16.2 If the RCPs cannot be restarted, continue cooldown per Operating Instruction S023-3-2.31, "Natural Circulation Guidelines", performing applicable steps concurrently with the steps in this instruction.
4.17 During the RCS cooldown, maintain the affected steam generator water level at - 65% narrow range level as follows:
4.17.1 If the steam generator blowdown processing system is available and sufficient storage capacity exists in the miscellaneous radwaste storage system, perform Step 4.18 and 4.19.
4.17.2 If the steam generator blowdown processing system is not available, or sufficient storage capacity in the miscellaneous radwaste storage system does not exist, perform Step 4.20 and 4.21.
4.18 Establish blowdown on the affected steam generator per Operating Instruction S023-9-4, "Steam Generator Blowdown Processing System Operation", with the following exceptions, performing applicable steps concurrently with the steps in this instruction.
4.18.1 Align the blowdown flash tank to the condenser by placing control switch HS-4084 to the "CONDENSER" position.
4.18.2 Contact the Health Physics Department and request the necessary support prior to entering the potentially contaminated blowdown processing demineralizer area..
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 15 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.18.3 Align the Blowdown Demineralizer Neutralization sumps discharge to Chemical Waste Tank, T-064, as follows:
4.18.3.1 Verify closed or close HV-3773, discharge to circulating water system by close indication on HS-3773.
4.18.3.2 Open S2(3)1318MU035, discharge isolation valve to Chemical Waste Tank, T-064.
4.18.3.3 Position sump pump discharge selector switch to "Radwaste". _
4.18.3.4 Start the selected sump pump by depressing Sump Pump Start pushbutton.
4.19 When the affected steam generator water level decreases to 65% narrow range initiate auxiliary feedwater to the affected steam generator per Operating Instruction S023-2-4, "Auxiliary Feedwater Pump Operation" and maintain level at -.65%, per forming applicable steps concurrently with the steps in this instruction.
4.20 If steam generator blowdown is unavailable, and provided 500 F subcooling margin can be maintained, then reduce pressurizer pressure until the primary and secondary pressure equalize as indicate by a constant (not increasing or decreasing) level in the isolated steam generator.
4.20.1 If pressurizer pressure cannot be reduced due to the
- requirement to maintain 500 F RCS subcooling, continue to cooldown the RCS until the margin exceeds 500F, then lower pressurizer pressure.
4.20.2 If RCS void formation is suspected prior to equalizing primary and secondary pressures, vent the reactor head to the Quench Tank until pressurizer pressure can be reduced without re-initiating void formation.
NOTE: Rapid void formation can be identified by ob serving that pressurizer spray flow induces a pressurizer level rise, rather than a pressure reduction. Backflow from the isolated loop, prior to the indicated pres sures equalizing, can be identified by a level decrease in the isolated steam gen erator and/or by a RCS boron dilution.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 16 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued)' INITIALS 4.20.3 If the indicated pressurizer pressure is reduced to 50 psi below the indicated steam generator pressure and the steam generator level continues to rise, per form the following:.
NOTE: If the affected steam generator level is still rising, either the isolated feed water is leaking through or the pressure indicators are out of calibration.
4.20.3.1 Check the main and auxiliary feedwater lines and close additional in-line isolation valves as necessary to stop the through leakage.
4.20.3.2 If feedwater leakage is not found, have I & C check the pressurizer and steam generator pres sure indicators for accuracy.
4.20.4 When primary and secondary pressure have equalized, adjust pressurizer pressure up or down as necessary to maintain a constant steam generator level.
4.21 When the BPS becomes available and/or when the Chemical Waste Tank contents have been processed, initiate cooldown of the isolated steam generator per Step 4.18 and 4.19 of this instruction.
4.22 Sample the RCS for boron concentration once every hour. Emer gency borate, as per Operating Instruction S023-3-5.10, "Emer gency Boration of the RCS" as required to maintain shutdown margin greater than 5.15% AK/K as calculated per Operating Intruction S023-3-3.29, "Determination of Shutdown Margin".
4.23 Verify effective isolation of the affected steam generator by completing the following:
4.23.1 Shutdown all turbine building ventilation per Operating Instruction S023-1-9, "Turbine Building Ventilation Operation".
4.23.2 Sample the condensate system to determine activity levels during cooldown and after the cooldown.
4.23.3 Take air particulate and air gaseous samples in the area of the air ejector after condenser and gland steam condenser combined vent.
SAN ONOFRE NULCEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 17 of 18 Revision 1 4.0 SUBSEQUENT OPERATOR ACTION (Continued) INITIALS 4.23.4 Take local area and offsite surveys for indications of unusually high radiation or airborne levels.
4.23.5 Establish radiation control areas to minimize person nel exposure to surface contamination, radiation and airborne contamination.
4.23.6 Sample turbine building sumps for any increase activity.
4.23.7 Monitor steam generator blowdown sample activity on RI-6759 and RI-6753 at PNL 2/3 L-27.
4.23.8 Use control room indication to monitor steam gen erator main steam piping for increased activity.
4.23.9 Monitor condenser air ejector exhaust on RI-7818 at PNL L-103.
4.24 If the transient has stabilized.and ESF busses are.being supplied from offsite power, stop the emergency diesel generators within 30 minutes per Operating Instruction S023-2-13, "Diesel Generator Operation".
4.24.1 If the diesels are providing power to the ESF busses, then when offsite. power becomes available transfer the ESF busses to the reserve auxiliary transformers and stop the diesels per Operating Instruction S023-2-13, "Diesel Generator Operation 4.25 If the SIAS and CCAS has been reset, return the safety injection system and containment cooling system to normal per Operating Instruction S023-3-2.7, "Safety Injection System Operation".
0 4.26 When the plant is cooled and depressurized to 350 F and 361 psig, initiate shutdown cooling. per Operating Instruction S023-3-2.6, "Shutdown Cooling System Operation".
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-5.29 UNITS 2 and 3 EMERGENCY Page 18 of 18 Revision 1 5.0 ATTACHMENTS 5.1 Attachment 1 - Accident Identification Small Breaks (Figure 1).
5.2 Attachment 2 - Accident Identification Large Breaks (Figure 2).
H. E. MORGAN Superintendent Units 2 and 3 APPROVED:
J. M. CURRAN Plant Manager VBF/sa
ACCIDENT IDENTIFITON SMALL BREAK PRESSURIZER PRESSURE AND LEVEL; DECREASING AT A SLOW RATE OBSERVE T-AVG AND REACTOR POWER.
T-AVG DECREASING & RX POWER INCREASING T-AVG AND REACTUR POWER CONSTANT OBSERVE TURBINE LOAD
- L.G. TUBE RUPTORE
'4 4 CONSTANT OR DECREASEDCONTAINMENTPRESSURE
-O -AN R ECEAE TEMPERATURE, HUMIDITY AND
.P LEVEJ EXCESS STEAM 4 FLOW ACCIDENT I NOMA 08SRV. CONT. PRES., TEMP.
HUMDITY AND SUMP LEVEL S.G. TUBE 1 LOCA SEEMER.
44,RUPTURE OR 0.1. S023-3-5.6.
NORMAL COTIE INCREASING STEAM BREAK STEAM BREAK INSIDE OUTSIDE VN T N CONTAINMENT CONTAINMENT OR STEAM DUMP BLWDt SMPL RD OR TURBINE EJECO AUS SEE STEAM LINE BYPASS VALVE EJECTOREXHAUST RUPTURE EMERG. OPEN 0.1. S023-3-5.9 1 '4' OBSERVE STEAM 4, DUMP & BYPASS VALVE POSITION S.G. TUBE SEE CVCSIOSS OF
'INDICATION RUPTURE COOLANT ACCIDENT SEE EMERG. 0.1. EMERGENCY OPEN' 4' 523-35,2901.S023-3-528O SEE STEAM LINE RUPTURE EMER.
0.1. O .23-3-.5.9T
SFie 2 '
ACCIDENT IDENTIFICATION LARGE BREAK PRESSURIZER PRESSURE DECREASING OR UNEXPLAINED CHANGE INfPRESSURIZER LEVEL OBSERVE STEAM GENERATOR PRESSURES ABNORMALLY LOW IN ONE STEAM GENERATOR PRESSURE INITIALLY NORMAL OR BOTH STEAM GENERATORS OR RISING.THEN SUBSEQUENTLY RETURNS TO NO-LOAD VALVE AFTER A REACTOR TRIP STEAM LINE RUPTURE LOCA Ok S.G. TUBE RUPTURE OBSERVE CONTAINMENT PRESSURE, RADIATION AND SUMP LEVEL' OBSERVE CONTAINMENT PRESSURE, 41 -__ 4 __ - - 1 .RADIATION AND SUM P LEVEL ONTAINMENT PRESSURE ORM4 INCREASING, NO INCREASING CONTAINMENT NO C S ACTIVITY PRESSURE AND ACTIVITY STEAM BREAK INSIDE 1~~STEAM BREAK INSIDEOUTSIDE CONTAINMENT LOCA SEE EMERG.
VERIFYINCREASED 1VERIFY INCREASED CONTAINMENTOSEE SEE EMERG. 01 0.I . 0 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.S023-3-5.29
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Revision 2 Page 1 of 3 DETERMINATION OF ADEQUATE CORE COOLING 1.0 OBJECTIVE 1 .1 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during post trip conditions.
1.2 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during power operation with indications of a core anomaly.
1.3 This instruction provides notification action steps required when inadequate core cooling or an approach to inadequate core cooling is identified, inde pendent of the involved operator requirements to impliment the appropriate emergency instructions.
2.0 REFERENCES
2.1 The following Emergency Operating Instruction require utilization of this instruction:
2.1.1 S023-3-5.1, "Emergency Plant Shutdown".
2.1.2 S023-3-5.6, "Loss of Coolant Accident".
2.1.3 S023-3-5.9, "Steam Line Rupture".
2.1.4 S023-3-5.29, "Steam Generator Tube Rupture".
2.1.5 S023-3-5.30, "Loss of Feedwater".
2.2 The following provides the basis for this instruction.
2.2.1 CE Operational Guidance for Inadequate Core Cooling.
3.0 PREREQUISITES 3.1 A Shift Technical Advisor (STA) or a Control Room Operator, not fulfilling a licensed operator requirement for the involved unit, is available to perform this instruction.
3.2 Utilization of this instruction is required per one or more of the refer enced instructions during post trip conditions.
810209nn
- SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Revision 2 Page 2 of 3 3.0 PREREQUISITES (Continued) 3.2 Utilization of this instruction is required upon receipt of one or more of the following alarms or indications during power operations.
3.2.1 Nuclear Power Deviation Hi/Lo.
3.2.2 Pre-trip or trip alarms on DNBR or Local High Power Density.
3.2.3 Azimuthal Tilt.
3.2.4 Kw/ft. Power Operating Limit Margin.
3.2.5 DNB Operating Limit Margin.
3.2.6 Letdown Process Radiation High.
4.0 PRECAUTIONS 4.1 Operational decisions shall not be based solely on.a single plant parameter or instrument when more than one confirmatory indication is available.
4.2 If high energy fluid is released into the containment, readings from non qualified instruments must be used with caution and verified against qualifi-ed instrument readings.
5.0 CHECK-OFF LISTS 5.1 Calculation Sheet 1, Reactor Coolant Performance Evaluation.
5.2 Calculation Sheet 2, Secondary Heat Sink Performance Evaluation.
5.3 Calculation Sheet 3, Localized DNB Evaluation.
6-.0 PROCEDURE 6.1 Complete Calculation Sheets 1 and 2, Reactor Coolant Performance Evaluation and Secondary Heat Sink Performance, when required, to evaluate core cooling per any of the Emergency Operating Instructions listed below.
6.1.1 S023-3-5.1, "Emergency Plant Shutdown".
6.1.2 S023-3-5.6, "Loss of Coolant Accident".
6.1.3 5023-3-5.9, "Steam Line Rupture".
6.1.4 S023-3-5.29, "Steam Generator Tube Rupture 6.1.5 S023-3-5.30, "Loss of Feedwater".
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 3 of 3 6.0 PROCEDURE (Continued) 6.2 The Calculation Sheets contain the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data,*and contain re quired notification actions if an approach to inadequate core cooling is identified, or degraded secondary heat sink performance is identified.
6.3 Complete Calculation Sheet 3, Localized DNB Evaluation, when required, to evaluate core cooling due to receipt of one or more of the following anomaly indications.
6.3.1 Nuclear Power Deviation Hi/Lo.
6.3.2 DNBR Pre-trip or Trip Alarms.
6.3.3 LPD Pre-trip or Trip Alarms.
6.3.4 Azimuthal Tilt.
6.3.5 Kw/ft Power Operating Limit Margin.
6.3.6 DNB Operating Limit Margin.
6.3.7 Letdown Process High Radiation.
6.4 Calculation Sheet 3 contains the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data, and contains required notification actions if localized DNB is identified.
7.0 RECORDS 7.1 Discard the Calculation Sheets after review by the Watch Engineer.
8.0 ATTACHMENTS 8.1 Not Applicable.
H. E. MORGAN Superintendent Units 2 and 3 APPROVED:
J. M. CURRAN Plant Manager VBF/sa
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 023-3-2.3u UNITS 2 and 3 Check-Off List 1 Page 1 of 4 Revision 2 REACTOR COOLANT PERFORMANCE EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess reactor cooling.
2.0 DATA COLLECTION 2.1 Record the following data:
2.1.1 RCS Subcooled Margin Initial 10 min. 20 min.
2.1.1.1 TI 911-1 2.1.1.2 TI 921-2 2.1.2 Pressurizer Pressure 2.1.2.1 PI 102-1 2.1.2.2 PI 102-2 2.1.2.3 PI 102-3 2.1.2.4 PI 102-4 2.1.3 Steam Generator #1 AP 2.1.3.1 PDI 0979-1 2.1.3.2 PDI 0979-2 2.1.3.3 PDI 0979-3 2.1.3.4 PDI-0979-4 2.1.4 Steam Generator #2 AP 2.1.4.1 PDI 0978-1 2.1.4.2 PDI 0978-2 2.1.4.3 PDI 0978-3 2.1.4.4 PDI 0978-4
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued) Initial 10 min. 20 min.
2.1.5 RCP Motor Amps 2.1.5.1 P001 2.1.5.2 P002 2.1.5.3 P003 2.1.5.4 P004 2.1.6 RCS Temperature Loop 1 2.1.6.1 Th TR-0111 2.1.6.2 Tc TR-0115 2.1.6.3 AT (Th - Tc) 2.1.7 RCS Temperatures Loop 2 2.1.7.1 Th TR-0121 2.1.7.2 Tc TR-0125 2.1.7.3 AT (Th - Tc) 2.1.8 Incore Thermocouples (random 14% sample) 2.1.8.1 TRE 02 2.1.8.2 TRG 04 2.1.8.3 TRL 06 2.1.8.4 TRR 09 2.1.8.5 TRT 13 2.1.8.6 TRW 18 2.1.8.7 TRA 08 2.1.8.8 TRC 13
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 -Page 3 of 4 Revision 2 2.0 DATA COLLECTION (Continued) Initial 10 min. 20 min.
2.1.9 HPSI Flow 2.1.9.1 FI 0311-2 2.1.9.2 FI 0321-1 2.1.9.3 FI 0331-1 2.1.9.4 Fl 0341-2 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that inadequate core cooling may exist, and advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction S023-3-5.1, "Emergency Plant Shutdown", are being carried out.
3.1.1 RCS subcooling greater than 100 F.
3.1.2 Pressurizer pressure greater than 2000 psia.
3.1.3 Steam Generator AP greater than.20 psi.
3.1.4 RCP motor amps greater than 600 amps.
3.1.5 Th less than 620 0 F.
3.1.6 Tc less than 560 0 F.
3.1.7 AT less than 60'F.
3.1.8 Incore T/C less than 620 0 F.
3.1.9 If Pressurizer Pressure is less than 1250 psia, HPSI flow greater then 415 gpm.
4.0 TREND EVALUATION 4.1 Take subsequent data at nu10 minute intervals until conditions stabilize within the acceptance criteria provided in Step 3.1, or until long term cooling is established.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 4 of 4 Revision 2 4.0 TREND EVALUATION (Continued) 4.2 If a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
4.3 If an approach to ICC has been tentitively identified, use the following criteria to positively identify an approach to ICC.
4.3.1 Th not decreasing with time.
4.3.2 If RCP's are running, RCP motor amps decreasing with time or steady below 50% at normal 4.3.3 Incore T/C indicate superheat conditions.
4.3.3.1 If any of the random sample T/C indicate superheat conditions, then for all subsequent data collection print out all incore T/C's and all incore flux detectors.
4.4 If inadequate core cooling is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction -S023-3-5.6, "Loss of Coolant Accident" are being carried out.
Completed By:
Reviewed By:
FILE DISPOSITION: Discard after Watch Engineer review.
VBF/sa
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 1 of 3 Revision 2 SECONDARY HEAT SINK PERFORMANCE EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess secondary heat sink performance.
2.0 DATA COLLECTION 2.1 Record the following data:
Initial 10 min. 20 min.
2.1.1 Steam Generator #1 Wide Range Level 2.1.1 .1 LI 1115-1 2.1.1.2 LI 1115-2 2.1.2 Steam Generator #1 Pressure 2.1.2.1 PI 1013A1 2.1.2.2 PI 1013A2 2.1.2.3 PI 1013A3 2.1.2.4 PI 1013A4 2.1.3 - Steam Generator #1 Feedwater Flow 2.1.3.1 FR 1011 2.1.3.2 FI 4725-2 2.1.4 Steam Generator #2 Wide Range Level 2.1.4.1 LI 1125-1 2.1.4.2 LI 1125-2 .
2.1.5 Steam Generator #2 Pressure 2.1.5.1 PI 1023A1 2.1.5.2 PI 1023A2 _
2.1.5.3 PI 1023A3 2.1.5.4 PI 1023A4 .
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 2 of 3 Revision 2 2.0 DATA COLLECTION (Continued) Initial 10 min. 20 min.
2.1.6 Steam Generator #2 Feedwater Flow 2.1.6.1 FR 1021 2.1.6.2 FI 4720-1 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that Secondary Heat Sink performance may be de graded, and advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruc tion S023-3-5.1, "Emergency Plant Shutdown", are being carried out..
3.1.1 At least one steam generator indicates greater than 50% wide range level.
3.1.2 Steam Generator pressure greater than Tc saturation pressure.
NOTE: If steam generator pressure is less than the corresponding Tc saturation pressure, dry out has occured.
3.1.2.1 If steam generator dryout is detected, advise the Watch Engineer that the provisions and limitations for refilling a dry steam generator contained in Emergency Operating Instruction S023-3-5.30, "Loss of Feedwater" apply.
3.1.3 Main feedwater flow greater than 3% or auxiliary feedwater flow greater than 350 gpm.
NOTE: If steam generator level is greater than 30% narrow range level, and is increasing, the acceptance criteria for minimum feedwater flow does not apply.
4.0 TREND EVALUATION 4.1 Take subsequent data at 10 minute intervals until conditions stabilize within the acceptance criteria provided in Step 3.1, or until long term cooling has been established.
4.2 If.a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 3 of 3 Revision 2 4.0 TREND EVALUATION (Continued) 4.3 If degraded secondary heat sink performance has been tentitively identified, use the following criteria to positively identify degraded performance.
4.3.1 Wide range level not increasing with time.
4.3.2 Steam generator pressure below Tc saturation pressure.
4.3.3 No feedwater flow to either steam generator.
4.4 If total loss of secondary heat sink is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction S023-3-5.30, "Loss of Feedwater",
are being carried out.
Completed By:
Reviewed By:
FILE DISPOSITION: Discard after Watch Engineer's review.
VBF/sa
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 3 -Page 1 of 4 Revision 2 LOCALIZED DNB EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess localized DNB.
2.0 DATA COLLECTION 2.1 Record the following data:
Initial 10 min. 20 min.
2.1.1 Azimuthal Tilt 2.1.2 LPD Margin 2.1.2.1 Ch A 2.1.2.2 Ch B 2.1.2.3 Ch C 2.1.2.4 Ch D 2.1.3 DNBR Margin 2.1.3.1 Ch A 2.1-.3.2 Ch B 2.1.3.3 Ch C 2.1.3.4 Ch D 2.1.4 Incore Thermocouples
-2.1.4.1 Display the following incore T/C's and record below any T/C's which exceed RCS hot leg temperature by more than 200F.
2.1 .4.1.1 TRA 08, 14 2.1.4.1.2 TRC 04, 06, 09, 13, 18 2.1.4.1.3 TRE 02, 04, 06, 09, 13, 18, 20
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30
-UNITS 2 and 3 Check-Off List 3 Page 2 of 4
'Revision 2 2.0 DATA COLLECTION (Continued) 2.1.4.1.4 TRG 02, 04, 06, 09, 13, 18, 20 2.1.4.1.5 TRL 02, 04, 06, 09, 13, 18, 20 2.1.4.1 .6 TRR 02, 04, 06, 09, 13, 18, 20 2.1.4.1.7 TRT 02, 04, 06, 09, 13, 18, 20 2.1.4.1.8 TRW 04, 06, 09, 13, 18 2.1.4.1.9 TRY 08, 14 2.1.4.2 Initial 10 min. 20 min.
ID Value ID Value ID Value 2.1.5 Incore flux Monitors.
2.1.5.1 Record the following SPND's and record below any SPND's which exceed the planar average by more than 1.35.
2.1.5.1.1 CSAO8, 14 (-1 to -5)
CSC 04, 06, 09, 13, 16, 18 (-1 to -5)
CSE 02, 04, 06, 09, 13, 16, 18, 20 (-1 to -5)
CSG 02, 04, 06, 09, 13, 16, 18, 20 (-1 to -5)
CSL 02, 04, 06, 09, 13, 16, 18, 20 (-1 to -5)
CSR 02, 04, 06, 09, 13, 16, 18, 20 (-1 to -5)
CST 02, 04, 06, 09, 13, 16, 18, 20 (-1 to -5)
CSW 04, 06, 09, 13, 16, 18 (-1 to -5)
CSY 08, 14 (-1 to -5)
SAN ONOFRE NUCLEAR GENERATING STATION 'OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 3 of 4 Revision 2 2.0 DATA COLLECTION (Continued)
Initial 10 min. 20 min.
ID Value ID Value ID Value 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that localized DNB may exist, and advise the Watch Engineer that reactor power should be reduced, until the data falls within the acceptance criteria.
3.1.1 Azimuthal Tilt less than .01.
3.1.2 LPD Margin greater than (later).
3.1.3 DNBR Margin greater than (later).
3.1.4 Incore T/C less than 580 F above Th 3.1.5 Incore SPND's less than 2 times the midplane average.
4.0 TREND EVALUATION 4.1 Take subsequent data at 10 min. intervals until conditions stabilize within the acceptance criteria.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 4 of 4 Revision 2 4.0 TREND EVALUATION (Continued) 4.2 If a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
Completed By:
Reviewed By:
FILE DISPOSITION: Discard after Watch Engineer review.
VBF/sa