ML15002A183
| ML15002A183 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/24/2014 |
| From: | Mcneil D NRC/RGN-III/DRS/OLB |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML15002A183 (75) | |
Text
Simulation Facility Braidwood Scenario No.: Operating Test No.: 2014 301 NRC 14-2 Examiners: ______________________ Applicant: _____________________ SRO
______________________ _____________________ ATC
______________________ _____________________ BOP Initial Conditions: IC-31 Turnover: Unit 1 is at 90% power, steady state, equilibrium xenon, BOL. Online risk is green. 1B Heater Drain Pump is OOS for motor replacement for the past 3 days. Expected back in service in 7 days. 1CV8149C was returned to service last shift following maintenance to replace its fuse block. Following completion of turnover, the shift manager requests the BOP swap 75 gpm letdown orifices from 1CV8149B to 1CV8149C per BwOP CV-9, step F.3 for an upcoming clearance order on 1CV8149B to replace its fuse block while the RO monitors reactor power.
Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1HD01PB PTL 1B HD pump OOS IMF CC02B 150 1B CC pump pressure switch failed high IOR ZDI1AF013C OPEN 1AF013C failed open 1 None N-BOP, US Swap 75 gpm Letdown orifices 2 IMF RX15 2195 I-ATC, US Master Pressurizer Pressure Controller fails to 2195 psig (0% demand) 3 IMF CC01B C-BOP, US 1A component cooling pump trip with 1B TS-US component cooling pump discharge pressure switch failure 4 IMF RX17 -4.25 C-ATC, US Rod Control Failure (subsequent ramp with rods in manual, RMCS still available) 5 TH03C 20 60 TS-US 1C SG Tube Leak 6 None R-ATC, US 1BwOA SEC-8 Fast Ramp 7 IMF EG03 90 96 180 C-BOP, US Generator voltage regulator failure 8 In caep file below M-ALL 1C Steam Generator Tube Rupture 9 IMF TH11A 0 M-ALL Loss of PZR pressure control IMF TH03C 300 60 TRGSET 1 "ZLO1IA066(2)==0" IOR ZDI1IA066 (1 0) CLS IOR ZAO1PIRY018 (1 60) 0 30 IMF PN1555 (1 70) ON IMF TH11B 0 IMF FW45C 100 10 In caep setup file C-ATC/BOP 1AF013C failed open and 1AF005C has failed open from the MCR (can be locally closed)
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
SCENARIO OVERVIEW Unit 1 is at 90% power, steady state, equilibrium xenon, BOL. Online risk is green. 1B Heater Drain Pump is OOS for motor replacement for the past 3 days. Expected back in service in 7 days. 1CV8149C was returned to service last shift following maintenance to replace its fuse block. Following completion of turnover, the shift manager requests the BOP swap 75 gpm letdown orifices from 1CV8149B to 1CV8149C per BwOP CV-9, step F.3 for an upcoming clearance order on 1CV8149B to replace its fuse block while the RO monitors reactor power.
After completing shift turnover and relief, the crew will swap 75 gpm letdown orifices. The BOP will manually lower letdown pressure, remove 1CV8149B from operation and place 1CV8149C on-line. The BOP will then restore letdown line pressure and restore letdown to automatic operation After completing the letdown orifice swap, the master pressurizer pressure controller will fail to 2195 psig (0% demand) in automatic. The RO will identify the failure and take manual control to restore pressurizer pressure.
After the master pressurizer pressure controller failure has been addressed, the 1A component cooling water pump will trip. When the 1A CC pump trips, the 1B and 0 CC pumps will not automatically start on low system discharge pressure due the 1B CC pump discharge pressure switch being failed high.
The crew will manually start a standby CC pump, either the 1B or 0 CC pump, to restore system flow and dispatch operators to investigate the malfunctions. Technical specification 3.7.7, condition B applies until the U-0 CC pump is racked into bus 141.
After the component cooling water pump trip has been addressed, the rod control summing amplifier will malfunction, resulting in uncontrolled inward rod motion. After checking turbine power stable, the RO will place rod control in Manual to stop the inward rod motion. 1BwOA ROD-1, UNCONTROLLED ROD MOTION, will be implemented. Rods will remain in Manual control for the remainder of the scenario.
After the rod control failure has been addressed, a 1C Steam Generator Tube Leak will be initiated. The crew will implement 1BwOA SEC-8, STEAM GENERATOR TUBE LEAK. The crew should determine from the estimated leak size that a fast ramp to remove the unit from power is required and make preparations to ramp the unit off line using 1BwGP 100-4, POWER DESCENSION.
After the SGTL has been addressed and the crew has ramped the unit sufficient for a reactivity manipulation, the generator voltage regulator output will fail high, causing the main generator to be overexcited. The BOP will turn the voltage regulator to off/test and manually lower main generator excitation using the base adjuster.
After the voltage regulator malfunction has been addressed, the 1C SGTL will worsen to a 300 gpm Steam Generator Tube Rupture. The crew will implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. When SI actuates, a solenoid failure will cause 1IA066 to fail closed, resulting a loss of Instrument Air to containment. IA to containment will remain unavailable for the remainder of the scenario.
1AF013C has failed open and 1AF005C fail open from the MCR and the crew will have to dispatch an operator to locally close 1AF005C. The crew will transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, based on secondary radiation trends on the 1C SG. After determining PZR pressure control is unavailable, the crew will transition to 1BwCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.
The scenario is complete when the crew has terminated high head SI in 1BwCA-3.3.
N142 Page 2 of 75
Critical Tasks
- 1. Isolate feedwater flow into and steam flow from the ruptured SG prior to completing step 4 of 1BwEP-3.
(Westinghouse - CT-18) (K/A number - 000038EA2.01 importance - 4.1/4.7)
(Westinghouse - CT-19) (K/A number - 000038EA1.36 importance - 4.3/4.5)
- 3. Terminate high head SI prior to commencing step 10 of 1BwCA-3.3, and prior to ruptured SG overfill causing water relief from ruptured SG PORV.
(Westinghouse - CT-35) (K/A number - 000038EA1.30 importance - 4.0/3.8)
N142 Page 3 of 75
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap Letdown orifices.
As SM, acknowledge the completion of letdown orifice swap.
Event 2: Master Pressurizer pressure controller fails to 2195 psig (0% demand).
Insert IMF RX15 2195 to fail the master pressurizer pressure controller output low.
Events 3: 1A component cooling pump trip with 1B component cooling pump discharge pressure switch failure.
Insert IMF CC01B to trip the 1A CC pump.
If dispatched as Equipment Operator to 1A CC pump and/or breaker, report phase A overcurrent present at pump breaker/no visible damage to pump locally.
If dispatched as Equipment Operator to 1B or 0 CC pump, report pump parameters normal.
If dispatched as Equipment Operator to 1PS-CC673B, report no visible damage to pressure switch.
Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.
Acknowledge as Shift Manager, to swap power supply of the 0CC pump.
Ensure control rods are in automatic prior to inserting the next event.
Event 4: Uncontrolled inward control rod motion.
If control rods are in manual, as SM direct crew to restore automatic rod control.
Insert IMF RX17 -4.25 to cause uncontrolled inward rod motion.
If dispatched as Equipment Operator to rod control cabinets, report no abnormal indications present.
As SM acknowledge the failure, on line risk assessment, request for maintenance support, and IR requests.
If consulted as SM for status of manual or auto rod control, direct crew to perform actions in accordance with 1BwOA ROD-1.
N142 Page 4 of 75
Event 5: SG tube leak in the 1C SG.
IMF TH03C 20 60 - 1C SGTL at 20 gpm over 60 seconds. (note: 20 gpm is ~ 16 gpm actual)
If called as Chemistry for 1C S/G sample, wait 15 minutes and report the estimated 1C S/G leakrate at 20 gpm.
If called as Chemistry a second time for 1C S/G sample, wait 10 minutes and report the estimated 1C S/G leakrate at 20 gpm.
Acknowledge as SM procedure changes, TS 3.4.13 cond. B entry, E Plan evaluations.
Event 6: Fast ramp of unit off line.
To reset the SG blowdown panel trouble alarm, use the following:
- IRF WD14 RESET As SM acknowledge shutdown required.
Acknowledge as Generation Dispatch initiation of ramp.
Event 7: Main generator voltage regulator failure Insert IMF EG03 90 96 180 (start malfunction at 90 and ramp to 96 in 180 sec.) for main generator voltage regulator failure.
Acknowledge as SM voltage regulator failure, on line risk assessment, requests for maintenance and OAD support, and IR request.
Acknowledge as Generation Dispatch failure of generator voltage regulator and request MVARs be restored to 250 MVARs out.
Events 8 & 9: 1C Steam Generator Tube Rupture, loss of PZR pressure control Run caep N14-2 EVENTS 8 & 9 from disk and verify the following actuate:
- IMF TH11A 0
- IMF TH03C 300 60
- TRGSET 1 "ZLO1IA066(2) == 0"
- IOR ZDI1IA066 (1 0) CLS
- IOR ZAO1PIRY018 (1 60) 0 30
- IMF PN1555 (1 70) ON
- IMF TH11B 0
- IMF FW45C 100 Acknowledge as Shift Manager procedure changes, Emergency Plan evaluations, STA request, and requests for support personnel.
To locally close 1AF005C, use the following:
N142 Page 5 of 75
- IRF FW173 0 20 second ramp After STA requested, as STA report CSF status: Yellow on inventory when pressurizer level < 17%, yellow on heat sink when ruptured SG level > 88%.
Evaluate and monitor to note if crew goes into 1BwFR-P.1.
If containment entry requested to attempt to repair 1IA066, acknowledge request but do not make air available to containment.
As Equipment Operator, acknowledge request to fill 1B AF pump day tank.
As Shift Manager, acknowledge request for environs teams when 1C SG PORV open.
N142 Page 6 of 75
Scenario NRC N142 Event 1 No: No.
Event Swap letdown orifices
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Shift manager requests swapping 75 gpm letdown orifices from 1B to 1C (from turnover).
US
- Directs RO to swap 75 gpm letdown orifices from 1CV8149B to 1CV8149C per BwOP CV-9, step F.3.
- Refers to BwOP CV-9.
- Determine BwOP CV-9, step F.3 to be performed.
- Lower letdown pressure.
- Place 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to MANUAL.
- Raise demand on 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to lower letdown pressure to ~ 180 psig (1PI-131).
- Remove 1B letdown orifice from operation.
- Close 1CV8149B.
- Align 1C letdown orifice (simultaneous operation).
- Open 1CV8149C.
- Restore automatic letdown pressure control.
- Verify letdown pressure stable at ~370 psig (1PI-131).
- Place 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to AUTO.
- Verify letdown temperature 90°F - 115°F (1TI-130).
- Verify PZR level is being maintained at the program value.
- Inform US letdown orifices swapped.
US
- Acknowledge report.
o Notify SM 75 gpm letdown orifices swapped from 1CV8149B to 1CV8149C.
NOTE: After the actions for swapping letdown orifices are complete and with lead examiner concurrence, enter next event.
N142 Page 7 of 75
Scenario NRC N142 Event 2 No: No.
Event Master pressurizer pressure controller fails to 2195 psig
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1).
- PZR pressure indicators 455A/456/457/458 rising.
- Master PZR pressure controller demand at zero.
- Identify/report failure of Master pressurizer pressure controller.
- Take manual control to restore PZR pressure.
- Control PZR pressure manually throughout scenario.
EVALUATOR NOTE: The crew should establish a normal pressure control band to maintain (approximately 2235 psig +/- 15 psig).
CREW o Refer to BwARs as time permits.
US o Notify SM of plant status.
- Check PZR pressure at 1PM05J:
o PZR pressure - normal on 1PI-455, 456, 457, & 458.
- Manually restore PZR pressure using 1PK-455A.
EVALUATOR NOTE: After the actions for the Master pressurizer pressure controller malfunction are complete and with lead examiners concurrence, insert the next event.
N142 Page 8 of 75
Scenario NRC N142 Event 3 No: No.
Event 1A component cooling pump trip with 1B component cooling pump discharge pressure
==
Description:==
switch failure Time Position Applicants Actions or Behavior CUE
- Annunciator 1-2-A4, CC PUMP TRIP
- Annunciator 1-2-A7, SEAL WTR HX CC FLOW LOW
- Annunciator 1-2-B5, CC PUMP DSCH PRESS LOW
- Annunciator 1-2-D7, CNMT PEN CLG FLOW HIGH LOW
- Annunciators 1-7-A4/B4/C4/D4, RCP 1A/B/C/D THERM BARR CC WTR FLOW LOW
- Annunciators 1-7-A5/B5/C5/D5, RCP 1A/B/C/D BRNG CC WTR FLOW LOW
- Annunciator 1-7-E4, RCP THERM BARR CC WTR FLOW HIGH LOW
- 1A CC pump amber trip light lit at 1PM06J.
- Determine 1A CC pump has tripped.
- Report failure to US.
- Determine 1B or 0 CC pump needs to be started.
- Dispatch operator to investigate 1A CC pump trip.
o Refer to BwARs.
US o Direct BOP to start 1B or 0 CC pump.
- Start 1B or 0 CC pump at 1PM06J.
o Refer to BwOP CC-1 and BwOP CC-2 for CC pump start/stop follow up actions.
- Perform the following:
- Assist US by making notifications.
- Refer to BwARs.
US
- Determines TS 3.7.7 condition B is applicable.
- Inform SM/Maint of 1B CC pump pressure switch failure, IR, and contact maintenance to investigate/correct instrument failure.
EVALUATOR NOTE: After the actions for CC pump trip and discharge pressure switch failure are complete and with lead examiners concurrence, enter next event.
EVALUATOR NOTE: The unit supervisor may elect to implement 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION, based on CC system annunciator status.
1BwOA PRI-6 steps are in italics.
CREW o Identify entry conditions for 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION.
US o Notify SM of plant status and procedure entry.
o Request evaluation of Emergency Plan conditions.
o Implement 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION, and direct operator actions of 1BwOA PRI-6 to establish the following conditions:
BOP o Check CC surge tank level at 1PM06J:
o 1LI-670 and 1LI-676 greater than 13% and stable.
o Check CC pumps at 1PM06J:
o CC pumps - NONE running.
o Manually start 1B or 0 CC pump.
o Check annunciator 1-2-B5, CC PUMP DSCH PRESS LOW - NOT LIT.
o Check CC system temperature at 1PM06J:
o Annunciator 1-2-D5, CC PUMP SUCT TEMP HIGH - NOT LIT.
N142 Page 9 of 75
Scenario NRC N142 Event 3 No: No.
Event 1A component cooling pump trip with 1B component cooling pump discharge pressure
==
Description:==
switch failure Time Position Applicants Actions or Behavior o 1TI-674 and 1TI-676 less than 105°F o Check RCP cooling:
o RCPs - ALL running.
o All block 7 annunciators clear.
o 1PR09J and 0PR09J trends normal for plant conditions at RM-11 or PPC.
o 1CC685, RCP thermal barrier isolation valve - OPEN.
o Check RCP temperatures acceptable for RCP operation.
o Check letdown temperature o Letdown in service.
o Annunciator 1-8-C5, LTDWN HX OUTLET TEMP HIGH - NOT LIT.
o Annunciator 1-9-E2, LTDWN TEM HIGH - NOT LIT.
o Check CC surge tank level.
o 1LI-670 and 1LI-676 between 50% and 65%.
US o Determines TS 3.7.7 condition B is applicable (until 0 CC Pump is lined to bus 141).
o Inform SM/Maint of 1B CC pump pressure switch failure, IR, and contact maintenance to investigate/correct instrument failure.
EVALUATOR NOTE: After the actions for CC pump trip and discharge pressure switch failure are complete and with lead examiners concurrence, enter next event.
N142 Page 10 of 75
Scenario NRC N142 Event 4 No: No.
Event Uncontrolled inward control rod motion
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Control rod inward motion.
- RODS IN light lit at 1PM05J.
- 1SI-412, rod speed indicator, indicates approximately 48 steps per minute.
- Identify control rods incorrectly inserting.
- Report failure to US.
- Determine turbine power stable at 1PM02J or OWS drop 210.
- Place rod bank select switch to manual at 1PM05J to stop uncontrolled rod insertion.
CREW
- Identify entry conditions for 1BwOA ROD-1, UNCONTROLLED ROD MOTION.
US
- Notify SM of plant status and procedure entry.
- Enter/implement 1BwOA ROD-1, UNCONTROLLED ROD MOTION " and direct operator actions of 1BwOA ROD-1 to establish the following conditions:
CREW
- Check turbine power stable at 1PM02J or OWS drop 210.
- Check rod control status at 1PM05J:
- Verify/place rod bank select switch in manual.
- Verify rods stopped moving.
- Check for unexplained reactivity addition - none identified.
- Verify manual rod control status by stepping rods in and out 7 steps each.
o Adjust turbine load, boron concentration or rod position to maintain Tave and Tref within 1° F.
US o If pressurizer pressure drops below 2209 psig, then LCO 3.4.1 Cond. A applies.
o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct rod control malfunction.
BOP o Verify turbine is not running back.
o Assist in monitoring reactor power on rod restoration (prevent exceeding 100%).
o Assist RO/US by reviewing BwARs.
EVALUATOR NOTE: After the actions for the rod control malfunction are complete and with lead examiners concurrence, insert the next event.
N142 Page 11 of 75
Scenario NRC N142 Event 5 No: No.
Event 1C SG Tube Leak
==
Description:==
Time Position Applicants Actions or Behavior CUE
- RM-11 Secondary rad monitor alarms/levels rising.
o SG BLDN RAD - 1PR08J.
o SJAE/GLAND STEAM EXHAUST - 1PR027J.
o MAIN STEAM LINE RAD - 1AR022J/23J.
o PZR level dropping.
o PZR pressure dropping.
o Charging/letdown mismatch.
BOP o Refer to BwAR-1-1PR27J for operator actions.
o Refer to BwAR-1-1PR08J for operator actions.
o Refer to BwAR-1-1AR22/23J for operator actions.
CREW
- Identify entry conditions for 1BwOA SEC-8, Steam Generator Tube Leak.
US
- Implement 1BwOA SEC-8, Steam Generator Tube Leak and direct operator action.
o Notify SM of SG leakage and determine leak rate.
o Notify SM to evaluate for Emergency Plan.
- Check SI Status.
o PZR pressure < 1829 psig.
o Steamline pressure < 640 psig.
o CNMT pressure > 3.4 psig.
- Maintain PZR level:
o Throttle 1CV121 & 1CV182 as necessary.
- Check PZR level stable or rising.
o Reduce letdown flow to 75 gpm.
- Monitor VCT level.
- Verify makeup is adequate to maintain VCT level.
US
- Minimize Secondary Contamination.
- Dispatch operators to perform BwOP MS-13, Operation with SG Tube Leakage.
US
- Notify RP to monitor rad levels and quantify release.
CREW
- Identify leaking SG (1C).
o Trend Main Steam Line monitors.
o Dropping Feed Flow with stable SG level.
o Unexpected rise in any NR SG level.
o Chemistry reports high activity via sample or N-16 monitor.
CREW
- Determine SG Tube leak rate.
- Estimate leak rate.
o Computer point on PPC display or SG Leak Tracking PI Display.
o Charging/letdown/RCP leakoff flow balance.
o Change in VCT level.
o Grab sample.
o 1BwOS SG-1 SG Pri to Sec Leakage Estimation.
N142 Page 12 of 75
Scenario NRC N142 Event 5 No: No.
Event 1C SG Tube Leak
==
Description:==
Time Position Applicants Actions or Behavior
- Estimate leak rate > 10 gpm - GO TO STEP 9.
CREW
- Confirm SG leak rate (step 9).
- At least 2 independent indications - TREND in the same direction.
o Main steam line radiation monitors.
o SJAE/GS Exh radiation monitor.
o SG Bldn radiation monitor.
o N-16 radiation monitors.
CREW
- Initiate Unit Shutdown.
- Check leak rate < 100 gpd.
- Reduce power to < 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Rapid Shutdown using 1BwGP 100-4T3).
o Shutdown Unit to MODE 3 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of reaching 50% power. Proceed to continuing shutdown step using 1BwGP 100-4 and 5.
US
- Determines Tech Spec 3.4.13 Condition B applies.
Evaluators Note: At this point the crew should begin preparations for shutting down the unit. The remaining actions of 1BwOA SEC-8 should be performed after the reactor is shutdown.
The fast ramp due to the SG tube leak is event 6. See the following pages.
N142 Page 13 of 75
Scenario NRC N142 Event 6 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Determine from 1BwOA SEC-8, load drop is required.
US o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.
CREW
- Review Operator Aid Book for 1BwOA SEC-8 Fast Ramp reactivity plan.
- Review applicable Precautions, and Limitations and Actions of 1BwGP 100-4.
EVALUATOR NOTE: The following step may be repeated as necessary to borate the RCS during the power descension.
- Verify rod position and boron concentration.
- Initiate boration, if required. (BwOP CV-6) .
- Determine required boric acid volume.
o Refer to operator aid for required boric acid addition.
- Determine desired boric acid flow rate.
- Perform the following at 1PM05J:
- Set 1FK-110 BA Flow Control to desired boration rate.
- Set 1FY-0110 BA Blender Predet Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).
o Turn on PZR backup heaters (as required).
- Batch addition of Boric Acid:
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer pump.
- When desired amount of BA has been added, stop the BA Transfer Pump.
- Close 1CV110A.
- Close 1CV110B.
o Turn on PZR backup heaters (as required).
- Lower turbine load at 1PM02J or OWS drop 210 by performing the following:
- Select SETPOINT.
- Enter desired MW into REF DEMAND window.
- Select ENTER.
- Enter desired MW/min into the RATE window.
- Select ENTER.
- Select EXIT.
o Notify US and ATC of pending ramp.
- Select GO/HOLD.
- Verify GO/HOLD button illuminates.
N142 Page 14 of 75
Scenario NRC N142 Event 6 No: No.
Event 1BwOA SEC-8 Fast Ramp
==
Description:==
Time Position Applicants Actions or Behavior
- Verify HOLD illuminated RED.
- Select GO.
- Verify GO illuminates RED.
- Verify main turbine load begins to lower.
ATC/
- Monitor reactor power and turbine load lowering.
- Monitor NIs, Tave, I, Pzr press/level at 1PM05J.
- Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.
- Manually move rods to maintain Tave-Tref mismatch.
- During boration, monitor the following at 1PM05J and PPC:
o Monitor VCT level.
o Monitor BA predet counter.
o Verify boration auto stops at preset value.
o Return Reactor Makeup System to automatic at current boron concentration.
EVALUATOR NOTE: After measurable change in power (approx. 10 min.) and with lead examiner approval, insert the next event.
N142 Page 15 of 75
Scenario NRC N142 Event 7 No: No.
Event Generator voltage regulator failure
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator 1-19-B6, GENERATOR FIELD FORCING
CREW
- Refer to BwARs.
- Determine generator voltage regulator failing.
US
- Direct/Ensure BOP takes manual control of generator voltage regulator and lowers generator field current.
o Inform SM of voltage regulator failure.
o Direct BOP/RO to stop load ramp/dilution.
- Perform the following at 1PM01J:
- Place voltage regulator to off.
- Place base adjuster to lower.
- Lower exciter field to < 100 amps prior to main generator trip.
CREW
- Maintain exciter field current, generator MW, and generator VARS within limits by operating the base adjuster.
US
- Contact SM to perform risk assessment, initiate IR, and contact additional personnel to investigate/correct instrument failure.
- Inform TSO, NDO, Power team generation dispatcher, OAD of voltage regulator failure.
EVALUATOR NOTE: After the actions for voltage regulator failure are complete and with lead examiner concurrence, enter next event.
N142 Page 16 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of PZR pressure control
==
Description:==
Time Position Applicants Actions or Behavior CUE o Annunciator 1-9-D3, CHARGING LINE FLOW HIGH LOW.
- RM-11 Rad Monitor ALERT/HI RAD Alarms.
o 1PR08J SG Blowdown.
o 1PR27J SJAE/GS.
o 1AR22/23B & 1AR22/23C, 1B & 1C main steam line.
- PZR pressure and PZR level lowering in an uncontrolled manner.
o Level rise/FW flow drop noted on 1C S/G.
CREW Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
- Initiate a manual reactor trip.
- Initiate a manual SI.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Enter/Implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, and direct operator actions of 1BwEP-0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip.
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk):
- Verify Turbine Trip.
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses.
- ESF Buses - BOTH ENERGIZED (141 & 142).
ATC/ Perform immediate operator actions of 1BwEP-0 at 1PM04J, 1PM05J, & 1PM06J:
- Check SI actuated at 1PM05J and 1PM06J:
o Annunciator 1-11-C1, PZR PRESS LO SI/RX TRIP - LIT.
o SI ACTUATED Bypass Permissive - LIT.
o SI equipment automatically actuated:
- 1A and 1B SI pump -RUNNING.
- 1SI8801A and B, CV pump cold leg injection valves - OPEN.
- Manually actuate SI at 1PM05J and 1PM06J.
US
EVALUATOR NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B:
BOP Verify FW isolated at 1PM04J:
N142 Page 17 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of PZR pressure control
==
Description:==
Time Position Applicants Actions or Behavior
- FW pumps - TRIPPED.
- Isolation monitor lights - LIT.
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.
- Verify DGs running at 1PM01J.
- DGs - BOTH RUNNING.
- 1SX169A/B OPEN.
- Dispatch operator locally to check operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.
- Operating VC train equipment - RUNNING.
- 0B Supply fan
- 0B Return fan
- 0B M/U fan
- 0B Chilled water pump
- 0B Chiller
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
- 0VC09Y - OPEN
- 0VC313Y - CLOSED
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED
- 0VC05Y - OPEN
- 0VC06Y - OPEN
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038.
- Verify Auxiliary Building ventilation aligned at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING
- 0VA023Y - OPEN
- 0VA436Y - CLOSED
- Plenum C:
- 0VA03CF RUNNING
- 0VA072Y - OPEN
- 0VA438Y - CLOSED
- Verify FHB ventilation aligned at 0PM02J:
- 0VA04CB - RUNNING
- 0VA055Y - OPEN
- 0VA062Y - OPEN
- 0VA435Y - CLOSED
- Trip all running Heater Drain Pumps.
- Initiate Periodic monitoring of Spent Fuel Cooling (contacts EO to perform locally).
- Notify US Attachment B complete.
N142 Page 18 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of PZR pressure control
==
Description:==
Time Position Applicants Actions or Behavior ATC/
- Verify ECCS pumps running at 1PM05J/1PM06J:
- Both CV pumps - RUNNING.
- Both RH pumps - RUNNING.
- Both SI pumps - RUNNING.
ATC/
- Verify RCFCs running in Accident Mode at 1PM06J:
- Group 2 RCFC Accident Mode lights - ALL LIT.
ATC/
- Verify Phase A isolation at 1PM06J:
- Group 3 Cnmt Isol monitor lights - ALL LIT.
ATC/
- Verify Cnmt Vent isolation at 1PM06J:
- Group 6 Cnmt Vent Isol monitor lights - ALL LIT.
- Verify AF system at 1PM06J:
- AF pumps - BOTH RUNNING.
- AF isolation valves - OPEN:
- AF flow control valves - THROTTLED:
- 1AF005A-H ATC/
- Verify CC pumps at 1PM06J:
- CC pumps - ONE RUNNING.
- Start the 0CC pump.
ATC/
- Verify SX pumps at 1PM06J:
- SX pumps - 1A and 1B RUNNING.
ATC/
- Check if Main Steamline Isolation required at 1PM04J and1PM06J:
- SG pressures - ALL > 640 psig.
- CNMT pressure - < 8.2 psig.
ATC/
- Check if CS is required at 1PM06J:
- CNMT pressure remained < 20 psig.
BOP/
- Verify Total AF flow at 1PM04J and 1PM06J:
- AF flow > 500 gpm.
- SG levels maintained between 10% and 50%.
- Check status of S/G NR levels.
- 1C S/G level rising in an uncontrolled manner.
(CT-18)
- Close 1AF013G.
- 1AF013C will not close and 1AF005C will not close utilizing the pot.
- Dispatch EO to locally close 1AF005C.
- Place 1AF005C and G pots=0.
ATC/
- Verify ECCS valve alignment at 1PM06J:
- Group 2 Cold Leg Injection monitor lights required for injection - LIT.
N142 Page 19 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of PZR pressure control
==
Description:==
Time Position Applicants Actions or Behavior
- Verify ECCS flow at 1PM05J:
- RCS pressure > 1700 psig.
- Check PZR PORVs and spray valves at 1PM05J:
- PORV isolation valves:
- 1RY8000A & B - ENERGIZED.
- PORV relief paths:
- 1RY455A & 456- C/S in AUTO.
- 1RY8000A & B - OPEN.
- 1RY455B & 1RY455C - CLOSED.
- Maintain RCS temperature control at 1PM05J:
- RCPs - ALL RUNNING:
- Verify RCS average temperature stable at or trending to 557oF.
o Throttle AF flow.
- Check status of RCPs at 1PM05J:
- All RCPs - RUNNING.
- Check RCP trip criteria:
BOP/
- Check if SG secondary pressure boundaries are intact at 1PM04J:
- Check pressure in all SGs:
- None dropping in an uncontrolled manner.
- None completely depressurized.
CREW
- Determine 1C S/G tubes are NOT intact:
- RM-11 ALERT/HI RAD Alarms:
o 1PR08J SG Blowdown o 1PR27J SJAE/GS o 1AR22/23C 1C Main Steam Line CREW Transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.
N142 Page 20 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of RCS pressure control
==
Description:==
Time Position Applicants Actions or Behavior US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
- Enter/Implement 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, and direct operator actions of 1BwEP-3 to establish the following conditions:
BOP/
- Check status of RCPs at 1PM05J:
- All RCPs - RUNNING.
- Check RCP trip criteria at 1PM05J:
- High head ECCS flow > 100 gpm.
o RCS pressure > 1425 psig - continue on in 1BwEP-3.
BOP/
- Identify ruptured SG 1C:
ATC Abnormal level rise.
1C Main steam line rad monitor ABNORMAL for plant conditions.
- Isolate ruptured SG at 1PM04J & 1PM06J:
- Verify 1MS018C in AUTO.
o Check 1MS018C CLOSED.
o Verify closed when SG pressure < 1115 psig.
o Notify SM to dispatch Environmental Monitoring Teams.
o Announce condition on plant page.
- Verify 1SD002G & H CLOSED.
[CT-18]
- Place 1MS001C, Loop 1C MSIV, C/S to CLOSE.
- Verify 1MS101C, 1C MSIV Bypass Valves - CLOSED.
BOP/
- Perform the following at 1PM04J:
- Check 1C SG level - Narrow Range > 10%.
(CT-18)
- Close 1AF013G.
- 1AF013C will not close and 1AF005C will not close utilizing the pot.
- Dispatch EO to locally close 1AF005C.
- Close 1AF005G with pot.
- Check 1C SG pressure > 320 psig.
CREW
- Initiate RCS cooldown:
- Determine required core exit temperature:
- 1C SG pressure at 1PM04J.
- Average of 10 highest CETCs at 1PM05J.
- Check P-11 status at 1PM05J:
o RCS pressure < 1930 psig:
- Verify P-11 Bypass Permissive light - LIT.
- Place BOTH Steam Line SI Reset/Block C/S to BLOCK.
o RCS pressure > 1930 psig:
- Continue RCS cooldown and block steamline SI in accordance with above steps when RCS pressure < 1930 psig.
- Dump steam to condenser at maximum rate:
- Check C-9 Bypass Permissive - NOT LIT at 1PM05J.
N142 Page 21 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of RCS pressure control
==
Description:==
Time Position Applicants Actions or Behavior
- Check 1A, 1B, & 1D MSIVs - OPEN at 1PM06J.
- Perform the following at 1PM04J:
- Place Steam Dump Mode Selector C/S to STM PRESS.
- When P-12 permissive is LIT, bypass P-12 interlock to continue cool down by placing steam dump switches to BYP-INTLK.
- Dispatch EOs with keys to 1SI101A and 1SI101B.
- Check average of 10 highest CETCs:
[CT-19]
o CETC < required temperature determined in step 6a - stop RCS cooldown by lowering demand on MS Header Pressure Controller and throttling AF flow. (Cooldown must be stopped prior to forcing entry into 1BwFR-P.1) o CETC > required temperature determined in step 6a - continue with 1BwEP-3 steps 7-13 and stop RCS cooldown when CETC < required temperature.
- Check 1A, 1B, & 1D SG levels at 1PM04J:
- Control SG levels between 30% - 50%.
ATC Note: RO may note a depressurized PZR PORV accumulator and report that a PZR PORV (1RY455A) is unavailable.
- Check PZR PORVs and isolation valves at 1PM05J:
- PORV isolation valves:
- 1RY8000A/B - ENERGIZED.
- 1RY455A/456 - CLOSED.
- PORV isolation valves:
- 1RY8000A/B - OPEN.
BOP/
- Reset SI at 1PM06J:
- Depress both SI reset pushbuttons.
- Verify SI actuated permissive light - NOT LIT.
- Verify auto SI blocked permissive light - LIT.
- Reset CNMT isolations at 1PM06J:
- Reset phase A isolation.
- Check Station Air Compressors - one running.
- Open 1IA065, Instrument Air Outside Isolation Valve.
- 1IA066, Instrument Air Inside Isolation Valve, will NOT open.
- Check if RH pumps should be stopped at 1PM06J:
- 1SI8812A & B open.
- RCS pressure > 325 psig.
- Stop both RH pumps and place in standby.
- Check average of 10 highest CETCs:
o CETC < required temperature determined in step 6a - stop RCS cooldown by
[CT-19] lowering demand on MS Header Pressure Controller. (Cooldown must be N142 Page 22 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of RCS pressure control
==
Description:==
Time Position Applicants Actions or Behavior stopped prior to forcing entry into 1BwFR-P.1) o CETC > required temperature determined in step 6a - continue cooldown and DO NOT proceed further in with 1BwEP-3 until CETC < required temperature.
- Maintain CETC < required temperature.
- Check 1C SG pressure at 1PM04J - stable or rising.
- Check RCS subcooling acceptable per Figure 1BwEP 3-2.
- Attempt to depressurize RCS:
- Determine normal PZR spray at 1PM05J - NOT available (1IA066 will not open).
- Check PZR PORVs at 1PM05J:
- 1RY455A is unavailable (air accumulator de-pressurized).
- Attempt to open 1RY456.
- Determine 1RY456 will not open.
ATC/
- Try to establish aux spray:
BOP o Verify at least one SI and one CV pump running.
o Terminate Hi Head ECCS:
- Verify CV pump miniflow valves OPEN - 1CV8110, 1CV8111, 1CV8114, &
1CV8116.
[CT-35]
- Close CV pump cold leg injection valves - 1SI8801A & B (this critical task may be performed later in 1BwCA-3.3).
- Place 1CV182 at 0%.
- Open 1CV8105 & 1CV8106.
o Determine aux spray unavailable without IA to CNMT.
CREW Transition to 1BwCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.
N142 Page 23 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of RCS pressure control
==
Description:==
Time Position Applicants Actions or Behavior US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Enter/Implement 1BwCA-3.3 and direct operator actions of 1BwCA-3.3 to establish the following conditions:
EVALUATOR NOTE: If 1C SG level is > 88% in the next step, the crew will proceed to 1BwCA-3.3, step 7. 1BwCA-3.3 step 7 actions begin at next evaluators note.
- Check 1C SG NR level:
o Greater than 88%, GO TO Step 7 (CHECK IF ECCS FLOW CAN BE TERMINATED). (On next page) o Less than 88% NR, continue with next step.
CREW
CREW o Attempt to restore PZR PORV:
o Open PORV isol valves (already open).
o Open PORV(s) as necessary (neither PORV will open).
o Go to step 4.
- Try to Establish Auxiliary Spray.
- > 1 SI pump running.
- > 1 CV pump running.
- Terminate High-Head ECCS:
- Reset Cent CHG pump miniflow isol valves.
- Verify CENT CHG pump miniflow isol valves OPEN:
1CV8110 1CV8111 1CV8114 1CV8116
[CT-35]
- Close CENT CHG pumps to cold legs injection isol valves:
1SI8801A 1SI8801B
- Place 1CV182 at 0%.
- Open 1CV8105 & 1CV8106.
- Check intact SG levels - Narrow range levels > 10%:
- Maintain narrow range levels between 30% and 50%.
- Check PZR level:
o Less than 14%, return to step 1 of 1BwCA-3.3.
o Greater than 14%, continue to next procedure step.
EVALUATOR NOTE: At this point the scenario is terminated since all critical tasks are met and the crew will end up cycling back through step 1 of the procedure until SG water level reaches 88% and then continuing in the procedure.
N142 Page 24 of 75
Scenario NRC N142 Event 8&9 No: No.
Event 1C Steam Generator Tube Rupture/loss of RCS pressure control
==
Description:==
Time Position Applicants Actions or Behavior CREW
- Check if ECCS flow can be terminated: (Step 7)
- Subcooling - acceptable per Iconics or Attachment A and Fig 1BwCA-3.3-1.
- Secondary heat sink established.
- RVLIS Plenum 15% or greater.
- Ruptured SG 1C rising in an uncontrolled manner or off scale high.
- Stop BOTH SI pumps.
- Stop 1 CV pump.
CREW
- Terminate high head ECCS:
- Reset SI CV pump miniflow isolation valves: 1CV8114 and 1CV8116
[CT-35]
- Verify CV pump miniflow valves OPEN-1CV8110, 1CV8111, 1CV8114, & 1CV8116.
- Close CV pump cold leg injection valves - 1SI8801A & B. (critical task may have been performed earlier in 1BwEP-3 or earlier in 1BwCA-3.3 if the SG level was less than 88%).
N142 Page 25 of 75
Simulation Facility Braidwood Scenario No.: Operating Test No.: 2014 301 NRC 14-3 Examiners: ______________________ Applicant: _____________________ SRO
______________________ _____________________ ATC
______________________ _____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover the shift manager requests the BOP to swap GC pumps per BwOP GC-5, in preparation for an OOS on 1GC01PA next shift. When GC pumps have been swapped, Generation Dispatch has requested Unit 1 to reduce power by 125 MW at 3 MW/min due to grid demand.
Event Malf. No. Event Event No. Type* Description Preload IMF ED06A Breaker 1562 ABT failure IMF FW44 1B AF Pp Trip IMF FW48A 1A AF Pp fails to auto start 1 None N-BOP, Swap stator cooling pumps.
US 2 None R-ATC, Lower power by 125 MW @ 3 MW/minute US 3 IMF RX06K 0 15 I-BOP, US 1C SG NR level transmitter 1LT-539 fails low TS-US 4 IMF CV05 600 5 I-ATC, Letdown line pressure controller 1PK-131 output TS-US fails low 5 IMF RH05A 0 5 TS-US RWST level channel failure 6 IMF FW35C C-BOP 1C HD Pump Trip (standby pump available) 7 IMF RD02H08 C-ATC, Single Dropped Rod (H-8)
TS-US 8 IMF RD02D04 M-All Multiple Dropped Rods (H-8 and D-4) 9 IMF TH03D 550 M-ALL 1D SGTR 10 Preload C-ATC/ 1A AF Pp auto start failure, 1B AF Pp trip BOP (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 26
SCENARIO OVERVIEW Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. Following completion of turnover, Generation Dispatch has requested Unit 1 to reduce power by 125 MW at 3 MW/min due to grid demand.
The shift manager requests the BOP to swap GC pumps per BwOP GC-5, in preparation for an OOS on 1GC01PA next shift.
After completing shift turnover and relief, the BOP will swap stator cooling pumps per BwOP GC-5.
After swapping GC pumps, the US will direct the crew to reduce power by 125 MW at 3 MW/min due to grid demand. The crew will commence a power reduction at 3 MW/min.
After a measurable change in power, 1C SG NR level transmitter 1LT-539 will fail low. 1FW530, Feedwater Regulating Valve, will open fully and 1C SG level will rise. The BOP will take manual control of 1C SG level and stabilize 1C SG level. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment E, will be implemented. The BOP will restore 1C SG level control to automatic after 1C SG level is restored to normal and an operable 1C SG NR level controlling channel is selected.
Technical specifications 3.3.1, conditions A and E and 3.3.2, conditions A and D are applicable.
After the 1LT-539 failure has been addressed, letdown pressure controller 1PK-131 output will fail low.
The letdown PCV will close and letdown pressure will rise lifting the letdown line relief valve. The ATC will take manual control of letdown pressure controller and restore letdown pressure. The crew may isolate letdown due to the lifting letdown relief valve. If letdown is isolated, it will be restored per BwOP CV-17.
After the 1PK-131 controller failure is addressed, RWST level channel 1LT930 will fail low. The crew will enter 1BwOA INST-2 Attachment S. Technical Specifications 3.3.2 conditions A and K apply.
After the RWST level channel failure is addressed, the 1C Heater Drain pump will trip due to overcurrent.
The crew will implement 1BwOA SEC-1, SECONDARY PUMP TRIP, and start the 1B Heater Drain pump.
Technical Specifications do not apply. The 1C Heater Drain pump will remain unavailable for the rest of the scenario.
After the 1C Heater Drain pump has been addressed, Rod H-8 will drop into the core causing Tave to drop and reactor power to further drop. The crew will implement 1BwOA ROD-3, DROPPED OR MISALIGNED ROD. After the crew has made sufficient reactivity manipulation to stabilize plant conditions, either by adjusting Tave to within 3oF of Tref, or commencing a load reduction to reduce power to within the range allowable for the dropped rod recovery, a second rod (D-4) will drop into the core. The crew should identify that two rods have dropped into the core and trip the reactor. The crew will take immediate actions per 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
After the transition to 1BwEP ES-0.1, the thermal hydraulic shock from the reactor trip results in a SGTR.
When the main generator trips, an ABT failure of breaker 1562 results in the 1B RCP being de-energized.
The crew will manually actuate safety injection and return to 1BwEP-0. The 1B AF pump will not start. The 1A AF pump fails to auto-start. The crew will manually start the 1A AF pump.
The scenario is complete when the crew has terminated high head injection and established normal charging flow in 1BwEP-3.
N143 Page 27
Critical Tasks
- 1. Manually trip the reactor upon discovery of multiple dropped control rods prior to completion of step 4 in 1BwOA ROD-3 (if crew re-enters the procedure at step 1) upon second dropped rod, or upon verification that the DRPI indication for the second dropped rod is valid. (per INPO SER 15-90 & SER 19-89) (K/A number - APE003A2.01 importance - 3.7/3.9)
- 2. Identify the 1D SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required.
(Westinghouse - CT-18) (K/A number - EPE038EA1.32 importance 4.6/4.7)
(Westinghouse - CT-20) (K/A number EPE038EA1.09 importance 3.2/3.3)
(Westinghouse - CT-4) (K/A number - 061000A2.05 importance - 3.1/3.4)
N143 Page 28
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap stator cooling pumps.
If dispatched as EO to observe stator cooling pump swap, report 1B stator cooling pump is ready for start, the pump has stable operating parameters once running, and no signs of leakage at the stator water skid.
If dispatched as EO to acknowledge stator panel alarm, insert the following:
- MRF TP15 ACK to acknowledge 1PL01J.
Acknowledge as SM commencement and completion of procedure.
Event 2: Lower power by 125 MW at 3 MW/min Acknowledge as chemistry/rad protection requests for RCS samples (if required).
Acknowledge as Generation Dispatch the initiation of ramp.
Event 3: 1C SG NR level transmitter 1LT-539 fails low.
- Insert IMF RX06K 0 15 to fail 1LT-539 low over a 15 second period.
Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.
Acknowledge as Shift Manager reactor overpower condition, on line risk assessment, request for IR, evaluation for reactivity screening, QNE and personnel notifications, and evaluation of return to full power operation.
If lead examiner desires the bistable bypassed, participate in brief and perform the following:
To bypass the required bistables, participate in brief and perform the following (Sim Drawing RX19):
- As extra NSO contact Unit 1 (X-2209).
- Insert the following:
- MRF RP20 OPEN (open protection cabinet #1 door).
- IRF RX063A BYPASS (Bypass LB 539A).
- IRF RX063B BYPASS (Bypass LB 539B).
- MRF RP20 CLOSE (close protection cabinet #1 door).
N143 Page 29
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: Letdown line pressure controller 1PK-131 output fails low.
Insert IMF CV05 600 5 for 1PK-131 failure.
If dispatched as EO to investigate 1PT-131, wait three minutes and report no visible damage to 1PT-131.
If dispatched as EO to align excess letdown to the top of the VCT, insert the following:
- MRF CV26remf 100 to open 1CV8482.
- MRF CV27 0 to close 1CV8484.
Acknowledge as SM the1PK-131 failure, on line risk assessment, requests for maintenance support, and IR requests.
Event 5: RWST Level Channel Failure 1LT-930.
Insert IMF RH05A 0 5 Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.
As SM, if requested support for bypassing the bistables, report that bistables are not to be bypassed until work analyst/NSO support can be obtained (i.e. not at this time) and that the abnormal operating procedure should be continued. Bistable bypassing will be conducted later.
Event 6: 1C Heater Drain Pump Trip.
Insert IMF FW35C to trip 1C HD Pump.
As SM acknowledge the failure, on line risk assessment, request for maintenance support, IR request, evaluation for reactivity screening, request for personnel notifications, and evaluation for restoration of full power operation.
If dispatched as Equipment Operator, report 1C HD pump ground overcurrent flag at breaker cubicle.
If dispatched as Equipment Operator, report you will complete pump vent alignment per BwOP HD-2 for tripped pump.
If dispatched as Equipment Operator, report standby pump start was successful and you will complete BwOP HD-1 for started pump.
N143 Page 30
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7: Single Dropped Rod (H-8).
Single Dropped Rod (H-8): With lead examiner approval, initiate the dropped rod (H-8).
Insert IMF RD02H08 to cause rod H8 to drop into the core.
As SM, acknowledge entry into 1BwOA ROD-3, requests for on line risk assessment, notification of Station Duty Manager, Station Duty Officer, Nuclear Duty Officer, Work Week Manager, and IR initiation As Reactor Engineering acknowledge receipt of Attachment A information.
As SM offer that an extra NSO will perform 1BwOSR 3.1.1.1-2, SHUTDOWN MARGIN SURVEILLANCE DURING OPERATION if asked.
When notified of need to ramp to less than 70% power, as QNE or SM the QNE has recommended use of the Operator Aid for a 350 Mwe Load Swing for the ramp.
As SM, acknowledge entry into 1BwOA ROD-3, requests for on line risk assessment, notification of Station Duty Manager, Station Duty Officer, Nuclear Duty Officer, Work Week Manager, and IR initiation.
If contacted as Generation Dispatch acknowledge about continued need for load drop.
Event 8: Multiple Dropped Rods.
When directed by the lead examiner, insert the following:
After STA requested, as STA report CSF status.
Event 9: 1D SGTR.
After the crew enters 1BwEP ES-0.1, insert IMF TH03D 550 to initiate a 550 gpm tube rupture in the 1D SG.
Acknowledge as SM procedure changes, E Plan evaluations, and STA request.
Bus 156 status: no breaker targets are present.
1B AF pump: tripped on overcrank.
N143 Page 31
Scenario N143 Event 1 No: No.
Event Swap stator cooling pumps
==
Description:==
Time Position Applicants Actions or Behavior CUE
- From turnover, swap stator cooling pumps per BwOP GC-5, SWITCHING STANDBY AND OPERATING GC PUMPS.
US Directs BOP to perform BwOP GC-5.
- Peer check actions of BOP operator.
- Refer to BwOP GC-5.
- Start 1B stator water pump at 1PM02J.
- Allow both pumps to run in parallel for 5 minutes (per step D.1).
Note: When examinee indicates that a 5 minute parallel run is required, evaluator may time compress parallel run and give cue that 5 minutes has elapsed.
o Notify EO to perform leak check at skid and acknowledge local alarm.
- Stop 1A stator water pump at 1PM02J.
- Inform US BwOP GC-5 complete.
US
- Acknowledge report.
o Notify SM BwOP GC-5 is complete.
ATC o Peer check actions of BOP operator.
o Monitor remainder of MCB.
NOTE: After BwOP GC-5 is complete and with lead examiners concurrence, enter next event.
N143 Page 32
Scenario N143 Event 2 No: No.
Event Lower power 125 MW at 3 MW/min
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Turnover.
US
- Implement actions of 1BwGP 100-4, POWER DESCENSION or 1BwGP 100-8, GENERIC REACTOR CONTROL GUIDANCE Attachment B, RAMPING HARD CARD.
o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.
CREW o Review Precautions, and Limitations and Actions, if not already performed during pre-job brief.
- Verify rod position and boron concentration.
- Initiate boration, if required. (BwOP CV-6)
- Determine required boric acid volume (per Operator Aid Book ___ to ___ gal.)
o Refer to operator aid for reactivity guidelines.
o Auto addition of Boric Acid:
- Determine desired boric acid flow rate.
- Perform the following at 1PM05J:
- Set 1FK-110 BA Flow Control to desired boration rate.
- Set 1FY-0110 BA Blender Predet Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).
o Turn on PZR backup heaters (As required).
OR o Batch addition of Boric Acid:
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer pump.
- When desired amount of BA has been added, stop the BA Transfer Pump.
- Close 1CV110A.
- Close 1CV110B.
o Turn on PZR backup heaters (As required).
- Lower turbine load at 1PM02J or OWS drop 210 by performing the following::
- Select SETPOINT.
- Enter desired MW into REF DEMAND window
- Select ENTER.
- Enter 3 MW/min into the RATE window.
- Select ENTER.
- Select EXIT.
o Notify US and RO of pending ramp.
N143 Page 33
Scenario N143 Event 2 No: No.
Event Lower power 125 MW at 3 MW/min
==
Description:==
Time Position Applicants Actions or Behavior
- Select GO/HOLD.
- Verify GO/HOLD button illuminates.
- Verify HOLD illuminated RED.
- Select GO.
- Verify GO illuminates RED.
- Verify main turbine load begins to lower.
ATC/
- Monitor reactor power and turbine load lowering:
- Monitor NIs, Tave, I, Pzr press/level at 1PM05J.
- Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.
- During boration, monitor the following at 1PM05J and PPC:
o Monitor VCT level.
o Monitor BA predet counter.
o Verify boration auto stops at preset value.
o Return Reactor Makeup System to automatic at current boron concentration.
After measurable change in power and lead examiner concurrence, insert the next event.
N143 Page 34
Scenario N143 Event 3 No: No.
Event 1C SG NR level transmitter 1LT-539 fails low
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator 1-15-C9, S/G 1C LEVEL DEVIATION HIGH LOW
- Annunciator 1-15-C5, S/G 1C LVL LO-2 RX TRIP ALERT
- SG 1C feed flow and NR level rising.
- Determine SG 1C feed flow and/or NR level rising at 1PM04J.
- Reference BwARs 1-15-C5 & 1-15-C9.
CREW
- Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US
- Notify Shift Manager of SG level channel failure.
o Orders ramp placed on hold (per OP-AA-300 step 4.6.12).
- Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment E, NARROW RANGE SG LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:
- Stabilize 1C SG level at 1PM04J.
- Establish automatic level control by placing 1FK-530 in auto when SG level restored to program level.
- Perform the following:
- Monitor reactor power at 1PM05J.
- Assist US by making notifications.
- Refer to BwARs.
The following steps will be performed if the lead examiner wants to observe bypassing bistables.
US o Perform pre-job brief per HU-AA-1211 for bistable bypassing.
o Complete 1BwOL 3.3.1/3.3.2, Attachment A, INSTRUMENT CONDITION TRACKING LOG.
Extra o Locally bypass bistables for 1C steam generator level by placing in BYPASS/ BOP NSO/ verifies correct bistable operation:
BOP o P-14/Lo-2 Rx Trip/AF Pump Start US
- Determine AMS channel NOT affected.
- Determine TS 3.3.1 conditions A and E are applicable.
- Determine TS 3.3.2 conditions A and D are applicable.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to N143 Page 35
Scenario N143 Event 3 No: No.
Event 1C SG NR level transmitter 1LT-539 fails low
==
Description:==
Time Position Applicants Actions or Behavior investigate/correct instrument failure, and make other notifications.
The next event is to be inserted following the above actions by the US and Lead Examiner concurrence.
N143 Page 36
Scenario N143 Event 4 No: No.
Event 1PK-131 output fails low
==
Description:==
Time Position Applicants Actions or Behavior CUE o Annunciator LP LTDWN RLF TEMP HIGH (1-9-B1)
- Annunciator LTDWN HX OUTLT PRESS HIGH (1-8-B5)
- 1FI-132, letdown line flow, lowering.
- 1PI-131, letdown line pressure, rising.
CREW
- Refer to BwARs.
- Recognize 1PK-131 failed.
US o Direct/Ensure RO takes manual control of 1PK-131 and returns letdown pressure to normal.
o Direct RO to isolate letdown.
- Perform the following at 1PM05J:
- Place 1PK-131, letdown line pressure control valve, in manual.
- Raise demand on 1PK-131.
- Lower letdown line pressure sufficiently to close letdown line relief valve and restore letdown flow to normal.
- Maintain letdown flow and pressure by operating 1PK-131 in manual.
o May take manual control of 1TK-130.
NOTE: ATC may respond so that the letdown relief valve will not lift.
US
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
o May enter tech spec 3.4.13 and then exit when relief resets.
EVALUATORS NOTE: The crew may elect to isolate letdown based on letdown relief valve lifting. Following letdown isolation the crew may elect to establish excess letdown or re-establish normal letdown. The steps for restoring normal letdown are in italics below.
ATC o Establish normal letdown per BwOP CV-17:
/BOP o Verify/close 1CV8149A/B/C.
o Verify CC aligned to letdown Hx (was previously aligned).
o Place 1CV131 manual at 30% demand.
o Place 1CC130 in manual at 60% demand.
o Open 1CV8152/8160.
o Open 1CV459/460.
o Verify open 1CV8324A & 1CV8389A.
o Verify/open 1CV381B.
o Verify/close 1CV381A.
o Verify/open 1CV8401A.
o Verify/close 1CV8145.
o Verify/open 1CV8146/8147.
o Open 1CV8105/8106.
o Adjust charging flow to approx. 100 gpm w/seal injection 8-10 gpm per RCP.
o Open 1CV8149A/B/C and control 1CV131 to maintain letdown pressure 360-380 psig.
o Control 1CC130 to maintain letdown temperature 90-115°F.
N143 Page 37
Scenario N143 Event 4 No: No.
Event 1PK-131 output fails low
==
Description:==
Time Position Applicants Actions or Behavior o Place controllers in auto.
o Verify 1PR06J in service.
o Verify proper operation of RMCS during VCT makeup.
o Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).
o Restore PZR level to program.
The steps establishing excess letdown are in italics below.
ATC o Establish excess letdown per BwOP CV-15.
/BOP o Prerequisite if excess letdown is placed online reactor power is maintained less than or equal to 99.8%.
o Verify Open 1CV8100/8112.
o Open 1CC9437A/B.
o Verify Closed 1CV123.
o Verify 1CV8143 C/S in VCT position.
o Open 1RC8037A/B/C/D.
o Open 1CV8153A(B).
o Slowly Open 1CV123 while monitoring excess letdown outlet temperature.
Initiate the next event when the lead examiner approves.
N143 Page 38
Scenario N143 Event 5 No: No.
Event RWST level channel failure 1LT-930
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator RWST LEVEL LO-3 (1-6-A7)
- Annunciator RWST LEVEL LO-2 (1-6-B7)
- Annunciator RWST LEVEL LOW (1-6-C7)
- Level Indicator 1LI-930 Failed Low.
ATC/
- Determine 1LI-930 failed low.
- Reference BwARs as time permits.
CREW
- Identify entry conditions for 1BwOA INST-2, OPERATION WITH FAILED INSTRUMENT CHANNEL.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Enter/Implement 1BwOA INST-2, OPERATION WITH FAILED INSTRUMENT CHANNEL, Attachment S, RWST LEVEL LOW LOW COINCIDENCE WITH SI.
- Determines TS 3.3.2 condition A and K are applicable.
- Contact SM to perform risk assessment, initiate IR, and contact additional personnel to investigate/correct instrument failure.
EVALUATOR NOTE: After the actions for the 1LT-930 failure are complete and with lead examiner concurrence, insert the next event.
N143 Page 39
Scenario N143 Event 6 No: No.
Event 1C Heater Drain Pump Trip
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator HD PUMP TRIP (1-17-D2)
- Annunciator HD PUMP DSCH FLOW HIGH (1-17-D3)
- HDT level indicator 1LI-HD009 rising at 1PM03J.
- 1C HD Pump flow indication 1FI-HD006 drops at 1PM03J.
- 1A HD Pump flow indication 1FI-HD004 rises at 1PM03J.
ATC/
- Recognize 1C HD pump has tripped.
- Report pump trip to US.
- Reference BwARs.
o Dispatch operators to investigate.
CREW
- Identify entry conditions for 1BwOA SEC-1, SECONDARY PUMP TRIP.
US
- Acknowledge 1C HD pump trip.
- Contact Shift Manager to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
- Implement 1BwOA SEC-1, SECONDARY PUMP TRIP Attachment C, HD PUMP TRIP, and direct operator actions of 1BwOA SEC-1 to establish the following conditions:
- Start the 1B HD Pump (may have been done per BwAR actions).
- Recognize two HD pumps running again.
- Monitor HD tank level at 1PM03J.
- Restore Plant Conditions
- 1HD117 in auto and closed.
- Running HD pumps current acceptable.
- HD Flow acceptable.
- Check PDMS operable:
- 1-10-E8 NOT lit.
- 1-10-D7 NOT lit.
ATC/
- Dispatch EO to perform BwOP HD-1 on standby pump that was started and BwOP BOP HD-2 on tripped pump.
EVALUATOR NOTE: After the actions for the HD Pump trip are complete and with lead examiners concurrence, insert the next event.
EVALUATOR NOTE: In order for the ATC to receive credit for the next event for the component failure the ATC must either switch rod control from auto to manual or dilute to adjust reactivity.
N143 Page 40
Scenario N143 Event 7 No: No.
Event Single Dropped Rod (H-8)
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Tave dropping.
- PZR pressure dropping.
- Rod Bottom light for rod H-8 LIT.
- Annunciator ROD AT BOTTOM (1-10-E6) o Annunciator TAVE CONT DEV LOW (1-14-E1)
ATC o Determine Rod H-8 has dropped.
o Reference BwARs.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
o Implement 1BwOA ROD-3, DROPPED OR MISALIGNED ROD, and direct operator actions of 1BwOA ROD-3.
CREW
- Stop Reactivity Changes:
- Rods in Manual.
- Stop unnecessary turbine load changes.
- Stop unnecessary boration or dilution.
ATC/
- As directed by US:
- Check DRPI not failed:
- ROD CONTROL URGENT FAILURE alarm (1-10-C6) - NOT LIT.
- ROD CONTROL NON-URGENT FAILURE alarm (1-10-D6) - NOT LIT.
- URGENT ALARM light (s) on DRPI panel - NOT LIT.
- Check Reactor power: Greater than 5%.
- Power - Less than 100%.
- Check for dropped rod:
- DRPI Rod Bottom Light LIT.
- Tave dropping.
- Stabilize RCS Temperature:
- Check Tave greater than 550oF.
- Maintain Tave - Tref deviation - within 3oF: Crew may adjust turbine load or dilute to restore Tave to within 3oF of Tref.
US
- Direct ATC/BOP to perform actions listed:
- Check DRPI not failed:
- ROD CONTROL URGENT FAILURE alarm (1-10-C6) - NOT LIT.
- ROD CONTROL NON-URGENT FAILURE alarm (1-10-D6) - NOT LIT.
- URGENT ALARM light (s) on DRPI panel - NOT LIT.
- Check Reactor power: Greater than 5%.
- Power - Less than 100%.
- Check for dropped rod:
- DRPI Rod Bottom Light LIT.
- Tave dropping.
- Stabilize RCS Temperature:
- Check Tave greater than 550oF.
- Maintain Tave - Tref deviation - within 3oF: Crew may adjust turbine load or dilute to N143 Page 41
Scenario N143 Event 7 No: No.
Event Single Dropped Rod (H-8)
==
Description:==
Time Position Applicants Actions or Behavior restore Tave to within 3oF of Tref.
- Notify the Shift Manager to perform risk evaluation, notify appropriate personnel (Station Duty Manager, Station Duty Officer, Nuclear Duty Officer, Work Week Manager) and initiate IR.
- Check Flux Rate Trip Alarm 1-10-C3 PWR RNG FLUX RATE RX TRIP ALERT - NOT LIT.
- RECORD DATA ON ATTACHMENT A:
- Check Core Power Distribution:
- PDMS INOPERABLE (1-10-E8) NOT LIT.
- 1BwOS PDMS-1a, AAR POWER DISTRIBUTION MONIORING SYSTEM NOT IMPLEMENTED.
- PDMS LIMIT EXCEEDED (1-10-D7) NOT LIT.
- Refer to Tech Specs: Identify LCO 3.1.4 Condition B applies (action B.2 does NOT apply) and 3.4.1 Condition A.
EVALUATOR NOTE: After the actions for the dropped rod are complete and with lead examiners concurrence, insert the next event.
N143 Page 42
Scenario N143 Event 8 No: No.
Event Multiple Dropped Rods (H-8 and D-4)
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator 1-10-C4, PWR RNG CHANNEL DEV
- DRPI Rod at Bottom lights for rod H-8 and D-4 LIT ATC
- Identify/report multiple alarms with indications of dropped rods.
CREW
- Identify conditions requiring reactor trip.
US/
- Direct/Initiate a manual reactor trip (and transition to 1BwEP-0).
[CT]
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
ATC Perform immediate operator actions of 1BwEP-0:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk):
- Verify Turbine Trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF Buses - BOTH ENERGIZED (141 & 142).
NOTE: BUS 156 ABT failure following the reactor trip will cause a loss of the 1B RCP.
ATC/ Perform immediate operator actions of 1BwEP-0 at 1PM04J, 1PM05J, & 1PM06J:
- Check if SI actuated at 1PM05J and 1PM06J:
- Any SI first out Annunciator - NONE LIT.
- SI ACTUATED Bypass Permissive - NOT LIT.
- SI equipment automatically actuated:
1A or 1B SI pump - NOT RUNNING.
1SI8801A or B, CV pump cold leg injection valve - CLOSED.
- Check if SI required:
- PZR pressure > 1829 psig.
- Steamline pressure > 640 psig.
- Containment pressure < 3.4 psig.
- Determine SI not required.
N143 Page 43
Scenario N143 Event 8 No: No.
Event Multiple Dropped Rods (H-8 and D-4)
==
Description:==
Time Position Applicants Actions or Behavior CREW
- Transition to 1BwEP ES-0.1.
N143 Page 44
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior CUE
- RM-11 Secondary rad monitor alarms/levels rising.
o SJAE/GLAND STEAM EXHAUSTER HIGH - 1PR027J.
o MAIN STEAM LINE RAD HIGH - 1AR022J/23J.
o PZR level dropping.
o PZR pressure dropping.
o Charging/letdown mismatch.
US
o RCS subcooling not acceptable, or o PZR level cannot be maintained > 4%.
NOTE: The crew may identify the failure of AF to start on LO-2 SG level at this point and attempt to start manually start AF pumps now.
CREW Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
- Manually actuate SI as directed.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Enter/Implement 1BwEP-0 and direct operator actions of 1BwEP-0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:
- Verify reactor trip:
- Rod bottom lights - ALL LIT.
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J:
- Verify Turbine Trip:
- All Turbine throttle valves -CLOSED.
- All Turbine governor valves -CLOSED.
BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:
- Verify power to 4KV busses:
- ESF bus 141 - ENERGIZED.
- ESF bus 142 - ENERGIZED.
CREW
- Check SI Status at 1PM05J:
- SI First OUT annunciator - LIT.
- SI ACTUATED Permissive Light - LIT.
- SI Equipment - AUTOMATICALLY ACTUATED.
- Manually actuate SI at 1PM05J & 1PM06J.
EVALUATOR NOTE: US and RO will continue in 1BwEP-0 while BOP is performing Attachment B.
- Verify FW isolated at 1PM04J.
N143 Page 45
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior
- FW pumps - TRIPPED.
- Isolation monitor lights - LIT.
- FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.
- Verify DGs running at 1PM01J:
- DGs - BOTH RUNNING.
- 1SX169A/B OPEN.
- Dispatch operator locally to check operation.
- Verify Generator Trip at 1PM01J:
- OCB 1-8 and 7-8 open.
- PMG output breaker open.
- Verify Control Room ventilation aligned for emergency operations at 0PM02J:
- VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.
- Operating VC train equipment - RUNNING.
- 0B Supply fan
- 0B Return fan
- 0B M/U fan
- 0B Chilled water pump
- 0B Chiller
- M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.
- 0B VC train M/U filter light - LIT.
- 0VC09Y - OPEN
- 0VC313Y - CLOSED
- Operating VC train Charcoal Absorber aligned for train B.
- 0VC44Y - CLOSED
- 0VC05Y - OPEN
- 0VC06Y - OPEN
- Control Room pressure greater than +0.125 inches water on 0PDI-VC038.
- Verify Auxiliary Building ventilation aligned at 0PM02J:
- Two inaccessible filter plenums aligned.
- Plenum A:
- 0VA03CB - RUNNING
- 0VA023Y - OPEN
- 0VA436Y - CLOSED
- Plenum C:
- 0VA03CF - RUNNING
- 0VA072Y - OPEN
- 0VA438Y - CLOSED
- Verify FHB ventilation aligned at 0PM02J:
- 0VA04CB - RUNNING
- 0VA055Y - OPEN
- 0VA062Y - OPEN
- 0VA435Y - CLOSED
- Trip all running HD pumps.
- Initiate monitoring of SFP cooling.
- Notify US Attachment B complete.
N143 Page 46
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior ATC /
- Verify ECCS pumps running at 1PM05J/1PM06J:
- BOTH CV pumps - RUNNING.
- BOTH RH pumps - RUNNING.
- BOTH SI pumps - RUNNING.
ATC /
- Perform the following at 1PM06J:
- RCFCs running in accident mode.
- RCFC accident mode status light lit.
- Perform the following at 1PM06J:
- Verify Cnmt Vent isolation:
- Group 6 Cnmt Vent Isol monitor lights - LIT.
- Verify AF system:
- AF pumps - NEITHER RUNNING.
[CT-4]
- Manually Start 1A AF pump. (may have been performed earlier)
- AF flow control valves - 1AF005A-D are throttled OPEN. 1AF005E-H are OPEN (no flow).
- Verify CC pumps running:
- Both CC pumps - RUNNING.
- Verify SX pumps running:
- BOTH SX pumps - RUNNING.
ATC /
- Check if Main Steamline Isolation required:
BOP o S/G pressures > 640 psig at 1PM04J.
o CNMT pressure < 8.2 psig at 1PM06J.
ATC /
- Check CS not required:
- CNMT pressure remained < 20 psig.
ATC /
- Verify Total AF flow:
- AF flow > 500 gpm.
o If 1D SG level > 10% and tube rupture is recognized then:
o CLOSE 1AF013D.
o CLOSE 1AF013H.
o AF pots - 1AF005D and 1AF005H pot demand = 0%.
NOTE: The crew may also isolate the 1B SG AF lines by closing 1AF013B and F.
Level will be rising in this SG due to the loss of power to the 1B RCP from ABT failure of breaker 1562. Eventually, the crew should recognize that this SG is not ruptured (once they have throttled AF flow to it and the SG level stops rising).
ATC /
- Verify ECCS valves aligned.
- Group 2 cold leg injection monitor lights lit.
- Verify ECCS FLOW.
- > 100 gpm on indicator 1FI-917.
- Check PZR PORVs and SPRAYs:
- PORVs CLOSED.
- PORV isolation valves - BOTH ENERGIZED.
- Normal Spray valves CLOSED.
N143 Page 47
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior ATC /
- Check RCS Temperature.
- Tave at or trending to 557°F.
o RCPs NOT running.
- Tcold at or trending to 557°F.
o Throttle AF to control cooldown.
ATC /
- Verify RCP trip criteria NOT met.
ATC /
- Check if SG secondary boundaries are intact.
- Verify NO SG depressurizing uncontrollably or completely depressurized.
ATC /
- Check if SG tubes are intact.
- Recognize 1PR27J and 1D MS line indicate ABNORMAL rads.
CREW Identify entry conditions for 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Request STA evaluation of status trees.
US
- Enter/Implement 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, and direct operator actions of 1BwEP-3 to establish the following conditions:
ATC /
- Check Status of RCPs:
- Identify ruptured SG 1D.
ATC / 1D Main steam line rad monitor ABNORMAL for plant conditions.
BOP 1D SG level rising uncontrollably.
- Isolate ruptured SG.
- Verify 1MS018D CLOSED.
- Verify 1SD002C & D CLOSED.
[CT-18]
- Check ruptured SG level - Narrow Range > 10%.
- Verify/close 1AF013D&H - may have already been closed in 1BwEP-0.
ATC /
- Check ruptured SG pressure > 320 psig.
BOP US
- Specify RCS temperature to which the RCS must be cooled down to allow depressurization of the RCS to ruptured SG pressure.
ATC /
- Dump steam at maximum rate via:
BOP o Steam dumps in steam pressure mode.
- Block MS Isolation after P-11 reached.
- Bypass Steam Dump P-12 interlock when setpoint is reached by holding steam dump off/reset switches in bypass.
ATC /
- Check intact SG levels.
- Control Aux feed flow to maintain intact SG levels between 30% and 50%.
ATC /
- Check PZR PORVs and ISOL Valves:
N143 Page 48
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior BOP
- PORVs CLOSED.
- PORV isolation valves - Both ENERGIZED.
- PORV isolation valves OPEN.
ATC /
- Depress BOTH SI Reset Pushbuttons at 1PM06J.
- Verify SI ACTUATED BP light NOT lit at 1PM05J.
- Verify AUTO SI BLOCKED BP light lit at 1PM05J.
ATC /
- Reset Phase A.
- Depress BOTH Phase A Reset Pushbuttons at 1PM06J.
ATC /
- Restore IA to Cnmt.
- Verify a station air compressor is running at 0PM01J.
- OPEN 1IA065 and 1IA066 at 1PM11J.
ATC /
- Check if RH pumps should be stopped.
- Check RCS pressure > 325 psig.
- Stop BOTH RH pumps.
ATC /
- Check if RCS cooldown should be stopped.
- Check CETCs < required temperature.
- Maintain CETCs < required temperature.
- Check ruptured SG pressure stable or rising.
- Check RCS subcooling acceptable.
ATC /
- Depressurize RCS to refill Pzr.
- OPEN PZR sprays/1 PZR PORV at 1PM05J until any of the following are met:
[CT-20] o RCS press < ruptured SG press and PZR level > 14%.
o PZR level > 68%.
o RCS subcooling is unacceptable.
- CLOSE PZR sprays/1 PZR PORV at 1PM05J.
- Check RCS pressure rising.
ATC /
- Check if ECCS flow should be terminated.
- Check subcooling acceptable.
- Check RCS pressure rising.
- Check Pzr level >14%.
- Stop ECCS pumps.
- Stop Both SI pumps and 1 CV pump.
ATC /
- Terminate high-head ECCS & establish charging flow.
- Depress BOTH CV pump recirc valve reset pushbuttons at 1PM05J.
- Verify CV pump recirc valves OPEN at 1PM05J:
- 1CV8110, 1CV8111, 1CV8114, 1CV8116.
ATC /
- CLOSE 1SI8801A & B at 1PM05J.
- Place 1CV182 controller demand at 0%.
- OPEN 1CV8105 & 1CV8106 at 1PM05J.
- Adjust 1CV121 and 1CV182 to maintain desired charging and seal injection flow.
NOTE: All critical tasks are complete at this point. The following steps address the second depressurization.
N143 Page 49
Scenario N143 Event 9 & 10 No: No.
Event 1D SGTR, 1A AF Pp auto start failure, 1B AF Pp trip
==
Description:==
Time Position Applicants Actions or Behavior ATC /
- Control charging to maintain PZR Level stable.
- Verify ECCS flow not required:
o Subcooling acceptable.
o PZR level > 14%.
- Check RMCS:
- Makeup set for automatic control.
- Check if Letdown can be established:
- PZR level > 27%.
- Adjust charging and letdown to maintain subcooling and avoid SG overfill.
ATC / Align cent chg pump suction to VCT:
- Check VCT pressure 15-65 psig.
- Open 1CV112B and 1CV112C.
- Close 1CV112D and 1CV112E.
- Check 1CV8804A - closed.
o 1SI8807A and B - closed; or o 1SI8924 - closed
- Check if SI Accumulators should be isolated:
- RCS pressure < 800 psig - not met continue to step 29.
o PZR level < 27% and 1D SG level rising: raise charging flow and depressurize RCS using available PZR spray.
o PZR level 27-50% and 1D SG level rising: depressurize RCS using available PZR spray.
o PZR level 50-68% and 1D SG level rising: depressurize RCS using available PZR spray and reduce charging flow.
o PZR level >68% and 1D SG level rising: reduce charging flow.
Terminate the scenario at examiners discretion.
N143 Page 50
Simulation Facility Braidwood Scenario No.: Operating Test No.: 2014 301 NRC 14-4 Examiners: ______________________ Applicant: _____________________ SRO
______________________ _____________________ ATC
______________________ _____________________ BOP Initial Conditions: IC-18 Turnover: Unit 1 is operating at 75% power, steady state, equilibrium xenon. Online risk is yellow. 1B RH pump has been OOS for breaker work for the past 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. LCO 3.5.2 has been entered. Expect 1B RH pump back in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Following completion of turnover, the shift manager requests the BOP to start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the 0C WS pump. Align the 0C WS pump for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump swap.
Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1RH01PB PTL 1B RH pump OOS IMF RP01 Failure of Rx to auto trip IOR ZDIRT2 NORMAL Failure of Rx Trip switch on 1PM05J IMF RD05G13 15 stuck rod IMF RD05H12 15 stuck rod IMF RD05H14 8 stuck rod IMF RD05J13 25 stuck rod 1 None N-BOP Swap WS pumps 2 None US Determine containment spray additive tank Tech TS-US Spec requirements 3 IMF RX13B 0 C-ATC, US 1LT-460 fails low TS-US 4 IMF FW16 1500 30 I-BOP, US 1PT-508 FW Htr Dsch Press fails high 5 TRGSET 1 C-BOP, US Degraded bus voltage with a loss of bus 142 EDE142==0 TS-US TRG 1 IMF ED07B IRF EP09 325 IRF EP09 348 390 6 None R-ATC, US Rapid down power of Unit-1 due to aircraft threat 7 IRF TC03remf TRIP M-ALL Inadvertent turbine trip with failure of Rx to trip 8 Preload C-ATC, US Failure of auto Rx trip 9 Preload C- ATC, Four stuck rods US 10 IMF ED15C M-ALL Loss of Offsite Power IMF EG08A 1A DG Failure
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 51
SCENARIO OVERVIEW Unit 1 is operating at 75% power, steady state, equilibrium xenon. Online risk is yellow. 1B RH pump has been OOS for breaker work for the past 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. LCO 3.5.2 has been entered. Expect 1B RH pump back in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Following completion of turnover, the shift manager requests the BOP to start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the 0C WS pump. Align the 0C WS pump for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump swap.
After completing shift turnover and relief, the BOP will swap WS pumps in accordance with BwOP WS-1 and BwOP WS-3. The Unit will get a phone call from chemistry stating the spray additive tank sodium hydroxide solution concentration is 28%. The US will address the Tech Spec requirements and determine that TS 3.6.7 condition A will be entered.
After swapping WS pumps and spray additive TS, 1LT-460 will fail low. The crew will implement 1BwOA INST-2 and take actions to restore PZR level control and stabilize plant conditions by restoring letdown. TS 3.3.1 conditions A and K apply (LCO 3.3.3 and 3.3.4 for Accident Monitoring and Remote Shutdown Panel minimum channel requirements are still met).
After the PZR level channel failure, feedwater line pressure detector 1PT-508 will fail high over a 30 second period. Both main feedwater pumps speed will lower, reducing feedwater flow and causing all steam generator levels to begin lowering. The crew will take actions to stabilize the plant by taking manual control of the main feedwater pumps or the Manual FW Pump Speed controller. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment J, will be implemented. 1PT-508 will remain unavailable for the remainder of the scenario.
After the 1PT-508 failure has been addressed,a degraded bus voltage will occur. Bus 141 and 142 voltage will drop to 3900 volts and will bring in annunciator 1-21/22-C7 and require the operator to open breakers 1412/1422. Per BwAR 1-21/22-C7 with voltage below 3990 volts the operator is required to open the SAT feed breakers to the ESF busses, if no operator action occurs the bus voltage remains at 3900 volts for 310 seconds and then the SAT feed breakers will automatically open. When the 4 KV ESF busses are de-energized the 1A DG will pick up bus 141. The 1B DG will start, but bus 142 will be faulted. TS 3.8.1 condition A and 3.8.9 condition A applies.
After the degraded bus voltage has been addressed, the NRC phone will ring and the crew will be notified of an aircraft heading toward Braidwood Station and will arrive in the next 20 minutes. The crew will initiate a rapid reactor downpower.
Once the above actions have been taken to initiate a rapid downpower, a trip of the main turbine will occur. The reactor does not automatically trip and the manual trip switch at 1PM05J is disabled. The crew should trip the reactor from 1PM06J and complete immediate actions of 1BwEP-0. When the reactor trips, one control bank rod and three shutdown bank rods will not fully insert. The crew will transition to 1BwEP ES-0.1 and initiate emergency boration for the stuck rods.
Once the crew has initiated emergency boration, a loss of all offsite power will occur and the 1A DG will trip resulting in a loss of all AC power to the unit. The crew will transition to 1BwCA-0.0. The crew must restore power to Unit 1 within 10 minutes. After power is restored to Bus 141, a transition will be made to either 1BwCA-0.1 or 1BwCA-0.2.
N144 Page 52
Completion criteria The scenario ends following transition to 1BwCA-0.1 or 1BwCA-0.2.
Critical Tasks
- 1. Perform a manual reactor trip at 1PM06J before transition out of 1BwEP-0.
(Westinghouse - CT-1) (K/A number - 000029EA1.08 importance - 4.5/4.5)
(Westinghouse - CT-24) (K/A number - 000055EA2.03 importance - 3.9/4.7)
- 3. Isolate RCP seal injection before a CV pump is started.
(Westinghouse - CT-27) (K/A number - 003000A4.01 importance - 3.3/3.2)
N144 Page 53
INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1 and 2: Swap WS pumps and determine containment spray additive tank Tech Spec requirements.
Call Unit 1 as chemistry and inform them that the Unit 1 containment spray additive tank sodium hydroxide solution concentration is 28% by weight.
If contacted as Equipment Operator for WS pump swap, report 0WS002B is open, 0B WS pump is aligned for start, and you are ready for the control room to start 0B WS pump in accordance with BwOP WS-1, step F.3.c.
If contacted as Equipment Operator for WS pump swap, report 0B WS pump has stable operating parameters once running, and no signs of reverse rotation from the 0C WS pump when the 0C WS pump is stopped.
If contacted as Equipment Operator chem. feed to WS is not available currently.
Acknowledge as Shift Manager at the start and completion of procedure.
Event 3: PZR level channel 1LT-460 fails low.
Insert IMF RX13B 0 to fail 1LT-460 low.
As SM, if requested support for bypassing bistables in AEER, report that AEER bistable is not to be bypassed until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and that the abnormal operating procedure should be continued. AEER bistable bypassing will be conducted later.
Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.
Event 4: Feed line pressure detector 1PT-508 fails high.
Insert IMF FW16 1500 30 for 1PT-508 failed high.
If dispatched as EO to investigate 1PT-508, wait two minutes report no visible damage to 1PT-508.
Acknowledge as SM 1PT-508 failure, on line risk assessment, request for maintenance support, and IR requests.
Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.
N144 Page 54
Event 5: Degraded bus voltage with a loss of bus 142.
Insert CAEP N144 Event 5
- TRGSET 1 EDE142==0
- TRG 1 IMF ED07B
- IRF EP09 325
- IRF EP09 348 400 If breaker 1412 and 1422 are manually opened, insert the following IRF EP09 348 Acknowledge as generation dispatch that low grid voltage occurred.
If dispatched to the bus 142, report Ground overcurrent flag on breaker 1412.
Acknowledge request for U-2 admin NSO to perform 1/2BwOSR 3.8.1.1.
Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, request for maintenance support, and IR request.
If requested as FS/EO to cross-tie 125 VDC bus 112 to 125 VDC bus 212 wait five minutes and insert the following:
MRF ED112 CLOSE If dispatched as EO to depress 1B DG emergency stop push button insert the following:
MRF EG20 TRIP After breakers 1412 and 1422 are open, generation dispatch reports the grid is normal.
If asked, report as EO good start on 1A and 1B DG, 1SX169B is open if asked.
Event 6: Rapid downpower of Unit-1 due to aircraft threat.
Contact Unit 1 on the NRC red phone with the following information This is the NRC Operations Center.
Authentication Code is A1BY. A 767 aircraft flying from Indianapolis has deviated from its planned course, turned off its transponder and is not responding to attempts to contact it. It is currently approximately 20 minutes from Braidwood. The NRC believes that the aircraft has been commandeered and that a significant threat exists to Braidwood Station.
Acknowledge as Shift Manager to implement the Operational Contingency Action Guideline (OCAG),
implement the security plan, and evaluate onsite protective actions using the OCAG.
N144 Page 55
Acknowledge as Shift Manager initiation of load reduction.
Acknowledge as Security the status of the threat.
Acknowledge as Generation Dispatch initiation of ramp.
Acknowledge as chemistry/rad protection requests for RCS samples (if required).
Acknowledge as fire brigade to relocate and assemble.
Acknowledge as radiation protection responder to relocate to the main control room.
Acknowledge as reactor services that no fuel movement is in progress and dry cask activities are not in progress.
Acknowledge as operator to perform BwOP VC-16 to isolate MCR ventilation.
IRF HV07remf ISOLATE to isolate VC train A.
Acknowledge as security to maintain communications, state that security will contact the control room as necessary.
Acknowledge as the Shift Manager that EAL will be evaluated, proper people will be notified, and the TSC will be activated.
Events 7, 8 & 9: Inadvertent turbine trip/auto reactor trip failure with four stuck rods NOTE: This needs to occur before power goes below 30%.
Insert: IRF TC03remf TRIP for inadvertent turbine trip.
Acknowledge as SM procedure changes, E Plan evaluations, request for SDM calculation, and STA request.
Events 10: Loss of offsite power/loss of all AC power and EDG trip.
Verify the crew has initiated emergency boration prior to initiating the next event.
Run caep N144 Event 10 from disk and verify the following actuate:
- IMF ED15C
- IMF EG08A Record time loss of all AC power occurred: ______:______:______
Record time AC power restored to Unit 1: ______:______:______
Calculate time to restore AC power: ______:______:______
Record time bus 142 restored ______:______:______
N144 Page 56
Acknowledge as SM procedure changes, E Plan evaluations, request for SDM calculation, and STA request.
After STA requested, as STA report CSF status - Yellow on inventory if pressurizer level < 17%.
When requested as EO to start the U1 D/Gs, report that 1A D/G and is tripped and seized, 1B D/G was previously emergency tripped.
Acknowledge as EO request to depress 1A DG emergency stop push button and insert the following:
- MRF EG19 TRIP As Unit 2 operator, acknowledge request to perform 2BwCA-0.3, report both Unit 2 4KV ESF buses powered from Unit 2 SATs, and acknowledge request to monitor crosstie current as loads are started.
After being notified to perform 2BwCA-0.3, wait 4 minutes 19 seconds then: Insert the following to perform crosstie:
- MRF ED006 CLOSE (closes 2414 brk)
- MRF ED007 CLOSE (closes 2424 brk)
Acknowledge as EO request to close 1CV8384A & B and insert the following to isolate the seal injection filters:
- MRF CV41 0
- MRF CV42 0 Acknowledge as EO request to isolate CC surge tank auto makeup and insert the following to isolate CC surge tank makeup:
- MRF CC51 0
- MRF CC52 0 Acknowledge as EO request to drain CC surge tank to normal level and insert the following as needed to initiate CC surge tank drain:
- MRF CC15 100
- MRF CC16 100 N144 Page 57
Scenario N144 Event No. 1 No:
Event Swap WS pumps
==
Description:==
Time Position Applicants Actions or Behavior CUE
- From turnover, start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP.
US
- Direct BOP to perform BwOP WS-1 and BwOP WS-3.
- Refer to BwOP WS-1.
- Contact Equipment Operator at 0B WS pump to verify 0B WS pump is ready for start.
- Start 0B WS pump at 0PM01J.
- Check 0B WS pump amps and WS system pressure normal.
o Contact Equipment Operator at 0B WS pump to verify normal pump parameters.
- Contact Equipment Operator at 0B WS pump to align chemical feed to 0B WS pump.
- Refer to BwOP WS-3.
- Contact Equipment Operator at 0C WS pump to isolate chemical feed to 0C WS pump.
- Place 0C WS pump C/S to PULL OUT.
- Contact Equipment Operator at 0C WS pump to determine if 0C WS pump shaft is not rotating backwards.
- Verify WS header pressure is stable.
- Place 0C WS pump C/S in AFTER TRIP.
- Contact Equipment Operator at 0C WS pump to complete 0C WS pump shutdown.
- Inform US WS pumps have been swapped.
US
- Acknowledge report.
o Notify SM WS pump swap is complete.
NOTE: Chemistry will call the US and give them chemistry results for the Spray additive tank while WS swap is in progress.
N144 Page 58
Scenario N144 Event No. 2 No:
Event Determine containment spray additive tank Tech Spec requirements
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Call from chemistry to inform them that the Unit 1 containment spray additive tank sodium hydroxide solution concentration is 28% by weight.
US
- Identify that TS 3.6.7 condition A is applicable for the spray additive tank.
- Contact SM about TS condition.
NOTE: After WS pump swap are complete and Spray additive tank TS are complete with lead examiner concurrence, enter next event.
N144 Page 59
Scenario N144 Event 3 No: No.
Event PZR level channel 1LT-460 fails low
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator 1-12-A4, PZR LVL LOW HTRS OFF LTDWN SECURED
- Annunciator 1-12-A5, PZR HTR TRIP
- Letdown isolated.
- PZR level rising.
- Determine PZR level rising and letdown is isolated at 1PM05J.
- Identify 1LI-460 is failed low.
- Report failure to US.
- Perform the following at 1PM05J:
- Verify automatic actions occurred (letdown isolated, heaters tripped off).
- Operate 1LK-459 OR 1FK-121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow.
- Isolate charging - close 1CV8105/8106.
- Reference BwARs 1-12-A4/1-12-A5/1-9-D3.
CREW
- Reference BwARs 1-12-A4/1-12-A5.
- Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.
US o Notify Shift Manager of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment C, PRESSURIZER LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:
- Check PZR level at 1PM05J:
- Select operable PZR level control channel:
- Place PZR level control select C/S to CH 459/461.
- Select operable PZR level channel for PZR level recorder at 1PM05J:
- Verify PZR level channel to recorder select switch in 459 or 461.
- Check letdown and PZR heaters at 1PM05J:
- Check letdown flow established: report to US that letdown is isolated.
o Check valve alignment.
- Check PZR heaters:
- PZR heaters available in auto.
- Check PZR level control in auto at 1PM05J:
- Verify/place the following components in AUTO:
- 1LK-459, master PZR level controller.
- 1FK-121, CV pumps flow control valve.
- Perform the following:
- Perform 1BwOA ESP-2 REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS by performing the following:
N144 Page 60
Scenario N144 Event 3 No: No.
Event PZR level channel 1LT-460 fails low
==
Description:==
Time Position Applicants Actions or Behavior
- Close letdown orifice isolation valves (1CV8149A-C).
- Close letdown isolation valves (1CV459 and 1CV460).
- Verify either 1CV8401A or B open.
- Open 1CV8324A/B and 1CV8389A/B (A with A, B with B).
- Confirm Letdown CNMT isolation valves 1CV8152 and 1CV8160 open.
- Place 1CV131 controller in manual at 40% demand.
- Place 1CC130 controller in manual at 60% demand.
- Open 1CV8105/8106
- Adjust 1CV121 and 1CV182 to attain at least 100 gpm charging with seal injection 8-13 gpm per RCP (coordinate with ATC).
- Open 1CV459 and 1CV460.
- Re-establish 120 gpm letdown flow by opening appropriate orifice isolation valves (1CV8149A and either 1CV8149B or C).
- Adjust 1CV131 and 1CC130 to restore letdown to 360 psig and 90-115oF.
- Place controllers in auto when desired (1CV131 and 1CC130).
- Verify 1PR06J restored.
US
- Determine TS 3.3.1, conditions A and K are applicable.
o Determine TS 3.3.3 and 3.3.4 are NOT applicable - minimum channels operable requirement is met.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
EVALUATOR NOTE: After the actions for the pressurizer level channel failure are complete and with lead examiners concurrence, insert the next event.
N144 Page 61
Scenario N144 Event 4 No: No.
Event FW Htr Dsch Press 1PT-508 fails high
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciators (1-15-A9 thru D9) "S/G 1_ LEVEL DEVIATION HIGH LOW"
- Annunciators (1-15-A4 thru B4) S/G 1_ FLOW MISMATCH FW FLOW LOW
- 1B MFP speed lowering
- 1C MFP speed lowering
- Master, 1B and 1C MFP speed controllers demand lowering
- 1PI-508 meter indication rising.
- 1PI-509 meter indication rising.
CREW
- Refer to BwARs.
- Determine 1PT-508 failing high at 1PM04J.
- Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.
- Dispatch operators to investigate 1PT-508 failure.
US o Notify SM of plant status and procedure entry.
o Request evaluation of Emergency Plan conditions.
- Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL", Attachment J "FW PUMP SPEED CONTROL MALFUNCTION" and direct operator actions of 1BwOA INST -2 to establish the following conditions.
- Perform the following at 1PM04J:
- Raise demand on 1SK-509A.
- Check reactor power less than 100%.
- Align steam dumps (not required. go to step 6).
o Crew may intermittently place each FRV in manual (then return to auto) to clear integral signal.
- Perform the following:
US
- Contact SM to perform risk assessment, initiate IR, evaluate reactivity screening, overpower assessment, QNE notification, duty personnel (WW Manager, Station Duty Manager, SDO, NDO) and evaluate for restoration to full power (as stated in step 6 of 1BwOA INST-2, Attachment J).
o IF PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 condition A.
N144 Page 62
Scenario N144 Event 5 No: No.
Event Degraded bus voltage with a loss of bus 142
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator 1-22-C7, BUS 142 OVERLOAD OR VOLT LOW
- Annunciator 1-21-C7, BUS 141 OVERLOAD OR VOLT LOW
- Low voltage on all three phases on bus 141 and 142.
- Determine there is low voltage on bus 141 and 142 at 1PM01J.
o Report failure to US.
- Reference BwARs 1-21-C7/1-12-C7.
- Verify voltage on ALL 3 phases of 4KV Bus are less than 4100 volts, and then OPEN the affected bus SAT Feed Breaker.
- Verify the DG start and power bus 141/142.
- 1B DG will start.
- Determine bus 142 is de-energized.
o Inform the US of entry into LCO 3.8.1.
- Monitor Bus 141 voltage.
CREW
- Monitor equipment ESF equipment starting.
CUE
- Annunciator 1-22-A7 BUS 142 FD BRKR 1422 TRIP
- Annunciator 1-22-C7 BUS 142 OVERLOAD OR VOLT LOW
- Annunciator 1-22-C8 DG 1B TROUBLE/FAIL TO START
- Bus 142 bus alive light not lit CREW
- Determine Bus 142 De-energized.
- Reference BwARs.
US o Notify SM of plant status and procedure entry.
- Request evaluation of Emergency Plan conditions.
- Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.
ATC/
- Ensure the following A train equipment started/running:
- Bus 131X
- 1A CV pump.
- 1A CC pump.
- 1A SX pump.
- 1A/C RCFCs.
- 0A VC train.
- Isolate bus 142 by placing the following breakers in PTL:
- ACB 1423 FIRST, then:
- ACB 1421, 1422, 1424.
- Bus 142 lockout alarm (1-22-A7) LIT.
- 112 Batt Chgr trouble alarm (1-22-E8) LIT.
- Refer to Tech Specs (US) and determines:
- TS 3.8.9 condition A (applicable since Bus 142 is faulted).
N144 Page 63
Scenario N144 Event 5 No: No.
Event Degraded bus voltage with a loss of bus 142
==
Description:==
Time Position Applicants Actions or Behavior
- Per 1BwOA ELEC-3:
- Perform 1BwOSR 3.8.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- Unit 2 contacted to perform 2BwOSR 3.8.1.1 w/i 1 hr.
- Review Tech Spec 3.8.4.
- Operator dispatched to emergency trip 1B D/G.
- Dispatch operators to locally investigate bus 142.
EVALUATOR NOTE: After the actions for the degraded bus voltage and loss of bus 142 are complete and with lead examiners concurrence, insert the next event.
N144 Page 64
Scenario N144 Event 6 No: No.
Event Rapid down power of Unit 1 due to aircraft threat
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Call from NRC that an aircraft is 20 minutes out.
US o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.
- Enter/Implement 0BwOA Security-1 and direct operator actions the following conditions:
CREW
- Check Braidwood Station Target of threat.
- Notify Shift Manager to implement the Operational Contingency Action Guideline (OCAG), implement the security plan, and evaluate onsite protective actions using the OCAG.
- Implement Attachment A of 0BwOA Security-1 Airborne.
- Validate threat came from NRC red phone and authentication code is correct.
- Identify that threat of Aircraft is probable and to initiate a rapid downpower of the unit(s).
EVALUATOR NOTE: The crew may perform the italic steps below as time permits.
- Make plant notifications; plant page, radio announcement, notify security, direct fire brigade, radiation protection.
- Check if fuel movement or dry cask activities in progress.
- Check reactor is critical.
- Place control room ventilation in emergency mode of operation.
- Monitor security radio communications.
- Make emergency classification determination and notification.
- Check plant status to:
o Coordinate plant access with security.
o Secure all surveillances, unless authorized.
o Terminate any releases in progress.
o Restore inoperable ECCS/RPS/ESF/ATWS or decay heat removal equipment.
o Expedite return of all other systems or equipment.
o Check fire header pressurized.
o Evaluate available staffing.
o Maximize makeup water systems inventory.
o Check unit shutdown.
o CREW
- Review applicable Precautions, and Limitations and Actions of 1BwGP 100-4.
EVALUATOR NOTE: The following step may be repeated as necessary to borate the RCS during the power descension.
- Verify rod position and boron concentration.
- Initiate boration. (BwOP CV-6).
- Determine required boric acid volume.
o Perform boration boundary calculation per 1BwGP 100-4T2.
o Refer to operator aid for ramp.
- Determine desired boric acid flow rate.
NOTE: The next 2 blocks outline the optional methods of boration, only ONE of which must be performed:
N144 Page 65
Scenario N144 Event 6 No: No.
Event Rapid down power of Unit 1 due to aircraft threat
==
Description:==
Time Position Applicants Actions or Behavior ATC * (BwOP CV-6 step 2 borate in automatic via procedure step or hard card Att. A)
Perform the following at 1PM05J:
o Turn on PZR backup heaters in accordance with BwOP RY-13, PRESSURIZER BACKUP HEATER OPERATION.
- Set 1FK-110 BA Flow Control to desired boration rate.
- Set 1FY-0110 BA Blender Predet Counter to desired volume.
- Place MAKE-UP MODE CONT SWITCH to STOP position.
- Place MODE SELECT SWITCH to BORATE position.
- Place MAKE-UP MODE CONT SWITCH to START.
- Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).
OR ATC * (BwOP CV-6 step 4 or hard card Att. A batch addition) Batch addition of Boric Acid:
o Turn on PZR backup heaters in accordance with BwOP RY-13, PRESSURIZER BACKUP HEATER OPERATION.
- Open 1CV110B.
- Open 1CV110A.
- Start the BA Transfer pump.
o Adjust M/A station setpoint on 1LK-112 if desired.
- When desired amount of BA has been added, stop the BA Transfer Pump.
- Close 1CV110A.
- Close 1CV110B.
o Adjust M/A station setpoint on 1LK-112 if desired.
- Place 1CV110A in AUTO.
- Place 1CV110B in AUTO.
- Lower turbine load at 1PM02J or OWS drop 210 by performing the following:
- Select SETPOINT.
- Enter desired MW into REF DEMAND window.
- Select ENTER.
- Enter desired MW/min into the RATE window.
- Select ENTER.
- Select EXIT.
o Notify US and ATC of pending ramp.
- Select GO/HOLD.
- Verify GO/HOLD button illuminates.
- Verify HOLD illuminated RED.
- Select GO.
- Verify GO illuminates RED.
- Verify main turbine load begins to lower.
ATC/
- Monitor reactor power and turbine load lowering.
- Monitor NIs, Tave, I, Pzr press/level at 1PM05J.
- Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.
- During boration, monitor the following at 1PM05J and PPC:
o Monitor VCT level.
o Monitor BA predet counter.
N144 Page 66
Scenario N144 Event 6 No: No.
Event Rapid down power of Unit 1 due to aircraft threat
==
Description:==
Time Position Applicants Actions or Behavior o Verify boration auto stops at preset value.
o Return Reactor Makeup System to automatic at current boron concentration.
EVALUATOR NOTE: The TURBINE TRIP needs to occur >30% power. After measurable change in power and with lead examiner approval, insert the next event.
N144 Page 67
Scenario N144 Event 7, 8, & 9 No: No.
Event Inadvertent turbine trip/auto reactor trip failure with four stuck rods
==
Description:==
Time Position Applicants Actions or Behavior CUE
- Annunciator TURB TRIP ABOVE P8 RX TRIP (1-11-A9)
- Annunciator TURB STOP VLV CLOSED ALERT (1-18-A4)
US
- Enter/Implement 1BwEP-0 and direct operator actions of 1BwEP-0 "REACTOR TRIP OR SI" and direct operator actions to establish the following conditions:
ATC Perform immediate operator actions of 1BwEP-0:
- Verify reactor trip :
- Rod bottom lights - NOT ALL LIT.
[CT-1]
- Manually trip the reactor (1PM06J) (1PM05J RX trip switch will not work).
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
- PR channels < 5%.
- IR SUR is negative.
BOP Perform immediate operator actions of 1BwEP-0:
- Verify Turbine Trip:
- All Turbine throttle valves - CLOSED.
- All Turbine governor valves - CLOSED.
BOP Perform immediate operator actions of 1BwEP-0:
- Verify power to 4KV busses bus 141:
- ESF Buses - ENERGIZED, BUS 142 DEAD.
CREW Determine SI NOT actuated/required.
- Check SI status:
- SI First OUT annunciators NOT lit (1-11-B1, 1-11-C1, 1-11-D1, 1-11-E1).
- SI ACTUATED permissive light NOT lit (1-BP-4.1).
- Check if SI is required:
- PZR pressure > 1829 psig.
- Steamline pressure > 640 psig.
- CNMT pressure <3.4 psig.
US
- Review immediate operator actions and determine SI not required.
o Notify SM of plant status (auto reactor trip failure) and procedure entry.
o Request evaluation of Emergency Plan conditions.
- Transition to 1BwEP ES-0.1 "REACTOR TRIP RESPONSE".
o Request STA evaluation of status trees.
- Maintain RCS temperature control.
- Check RCPs - RUNNING.
- Verify RCS average temperature stable at or trending to 557o.
- Verify ALL control rods fully inserted.
- Rod at bottom lights - NOT ALL LIT.
N144 Page 68
Scenario N144 Event 7, 8, & 9 No: No.
Event Inadvertent turbine trip/auto reactor trip failure with four stuck rods
==
Description:==
Time Position Applicants Actions or Behavior
- Initiate emergency boration of 5280 gallons per 1BwOA PRI-2, EMERGENCY BORATION.
- Calculate shutdown margin within one hour (request U-2 operator to perform SDM calculation).
- Initiate emergency boration per 1BwOA PRI-2 EMERGENCY BORATION:
/BOP
- Check CV pump status.
- 1A CV pump running.
- Emergency borate RCS.
- Establish boration flow from BAT.
o Open 1CV8104 (de-energized).
- Open 1CV110A & 1CV110B.
- Start boric acid transfer pump.
- Verify CV pump discharge flow path aligned with proper flow.
- Verify PZR backup heaters energized.
- Continue boration until required gallons of boron added.
Once the crew has initiated emergency boration, initiate the next event. (event 10)
ATC o Check PZR level control:
/BOP
- Level > 17% and trending to 25%.
- Charging and letdown - IN Service.
ATC o Check PZR pressure control:
/BOP
- Pressure > 1829 psig and trending to 2235 psig.
/BOP
- Isolation monitor lights - LIT.
- Trip FW pumps.
o Check total feed flow to SGs - GREATER THAN 500 GPM:
o Start 1A FW Pump.
o Start AF pump(s).
/BOP
- Levels maintained between 10% and 50%.
ATC o Verify generator trip.
/BOP
- Main transformer output breakers - OPEN:
- OCB 1-8.
- OCB 7-8.
- PMG output breaker - OPEN.
- Verify ALL AC busses energized.
N144 Page 69
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior CUE
- A Loss of Offsite power is indicated by lights going out.
- Annunciator LOSS OF OFFSITE POWER (1-20-A1).
CREW
- Identify Loss of Offsite Power.
ATC o Determine emergency boration stopped.
US
- Direct operator actions of 1BwCA-0.0.
- Notifies SM of plant status and procedure entry.
o Requests evaluation of Emergency Plan conditions.
NOTE: For evaluation of critical task, Record time loss of all AC power occurred.
ATC Perform immediate operator actions of 1BwCA-0.0:
- Verify reactor trip:
- Reactor trip & Bypass breakers - OPEN.
- Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwCA-0.0:
- Isolate Steamlines:
- Actuate main steamline isolation.
- Verify AF flow:
- >500 gpm (1B AF only).
N144 Page 70
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior
- Verify RCS isolated:
- 1RY455A and 1RY456 closed.
- 1CV8149A, B & C closed.
- 1CV459 and 1CV460 closed.
- 1CV8153A & B closed.
- Identify/report neither DG running.
- Actuate SI from 1PM05J and 1PM06J.
BOP/
- Prepare for Unit 2 crosstie:
US
- Dispatch operator to depress emergency stop push buttons on both U1 DGs.
- Reset SI.
US
- Check status of Unit 2 ESF buses:
- Notify Unit 2 to implement 2BwCA-0.3.
BOP/
- Crosstie bus 141 to Unit 2:
US
- Bus 241 energized from SAT.
- Check Bus 141 - NOT FAULTED.
- ACB 1413 (DG feed) in PULL OUT.
- ACB 1411 (Non-ESF bus tie) in PULL OUT.
- ACB 1412 (SAT feed) in PULL OUT.
- ACB 1414 (Reserve feed) in PULL OUT.
- Verify Bus 141 alarms NOT LIT:
- Annunciator BUS 141 FD BRKR ACB 1412 TRIP (1-21-A7)
- Annunciator BRKR 1414 CROSS-TIE OVERCURRENT (1-21-B8)
- Annunciator DG 1A OVERLOAD (1-21-B9)
- Crosstie bus 141 to Unit 2 (Contd)
- Verify loads fed from Bus 141 available:
- Bus 131X
- CENT CHG pump 1A
- CC pump 1A or 0
- SX pump 1A
- MCR chiller 0A
- Place ESF loads in PULL OUT:
- CENT CHG pumps
- RH pumps
- SI pumps
- AF pump 1A
- CS pumps
- CC pumps (1A, 1B, and 0)
- SX pumps
- MCR chillers N144 Page 71
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior
- Check ACB 2414 closed (reserve feed light lit.).
[CT-24]
- Synch and Close Bus 141/241 reserve feeder breaker.
- Close ACB 1414.
- Check Bus 141 energized.
- Check Bus 131X energized.
[CT-24] NOTE: For evaluation of critical task, CT-24, record time AC power restored:
Time power restored - time power lost = ______:______:______ (<10 minutes).
- Restore Unit 1 SX cooling.
- Check valves for available SX pump - OPEN.
- 1SX001A
- 1SX016A
- 1SX027A
- Start SX pump 1A.
- Check open SX crosstie valves - 1SX033 and 1SX034.
N144 Page 72
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior ATC
/BOP
- Annunciator 125V DC BATT CHGR 111 TROUBLE NOT LIT (1-21-E8)
- Dispatch operator to instrument bus 111 and 113.
BOP/
- Align equipment for Unit 1 restoration.
- Verify 1B AF pump - RUNNING.
- Check Bus 142 - NOT FAULTED:
- ACB 1423 (DG feed) in PULL OUT.
- ACB 1421 (Non-ESF bus tie) in PULL OUT.
- ACB 1422 (SAT feed) in PULL OUT.
- ACB 1424 (Reserve feed) in PULL OUT.
- Verify Bus 142 alarms status:
- Annunciator BUS 142 FD BRKR ACB 1422 TRIP LIT (1-22-A7)
- Annunciator BRKR 1424 CROSS-TIE OVERCURRENT NOT LIT (1-22-B8)
- Annunciator DG 1B OVERLOAD NOT LIT (1-22-B9)
[CT-27]
- Dispatch EOs to close 1CV8384A & B.
- Close RCP seal water return isol valves - 1CV8100.
Place S/G PORVs in Auto.
- Check VC fans - ONE TRAIN RUNNING:
- Start makeup fan (will not start if VC isolation switch is in isolate event 6).
N144 Page 73
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior CREW
- Select proper recovery procedure.
- Check RCS subcooling acceptable per ICONIC DISPLAY or attachment A.
- Check PZR level > 14% (28% ADVERSE).
- Determine proper recovery procedure:
- 1BwCA-0.1 if all the following satisfied:
- RCS subcooling acceptable.
Iconic Display.
OR Attachment A.
- Pzr level > 14% (28% ADVERSE).
- 1BwCA-0.2 if ANY of the above conditions NOT satisfied.
US o Transition to 1BwCA-0.1 "Loss of All AC Power Recovery without SI Required.
o Transition to 1BwCA-0.2 "Loss of All AC Power Recovery with SI Required.
NOTE: All critical tasks are complete at this point.
- Direct operator actions of 1BwCA-0.1.
- Notifies SM of plant status and procedure entry.
o Requests evaluation of Emergency Plan conditions.
- Check RCP seal isolation status:
- Dispatch EOs to close 1CV8384A & B.
- Check CNMT isolation status:
- CNMT isolation phase A - ACTUATED.
- Reset Phase A and B.
- Manually load following equipment on 4KV bus(es):
- Check SACs - any running.
- Open 1IA065 1IA066.
- Start 1A CC pump.
- Check CV pump suction alignment.
o Boric acid transfer - pump available.
o Rx makeup control system.
o VCT outlet isol valves - both open.
- Check CV pump miniflow alignment.
- Reset SI CV pump miniflow valves.
- Verify available 1A CV pump isolation valves - open.
- 1CV8111 and 1CV8114 open.
- Check CV pump discharge alignment.
- Close 1CV8106.
- Check 1SI8801A closed.
- Start 1A CV pump.
N144 Page 74
Scenario N144 Event 10 No: No.
Event Loss of all AC power
==
Description:==
Time Position Applicants Actions or Behavior Note: The scenario may be terminated at this point.
N144 Page 75