ML22199A189
| ML22199A189 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/18/2022 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co LLC |
| Baker R | |
| Shared Package | |
| ML20140A271 | List: |
| References | |
| Download: ML22199A189 (85) | |
Text
20-1 NRC 1 Page 1 of 23 Simulation Facility Braidwood Scenario No.:
NRC 1 Operating Test No.: 20-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-31 Turnover Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). FIN is currently troubleshooting loop 1B OTDT setpoint circuitry. Tech Spec 3.3.1 Conditions A and E have been entered (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago). Following turnover, perform 1BwOSR 3.6.6.2, sections 1 & 3 for the 1B RCFC, as a PMT for an EMD breaker swap completed last shift. Tech Spec 3.6.6 Condition C has been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). FIN is troubleshooting the 1RE01PA and 1RE01PB, RCDT Pumps 1A & 1B, auto start feature (pumps started at lower than expected RCDT level).
Both pumps are available for manual operation, if required, and their control switches are in STOP at 1PM05J.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS IMF RX24B 0 IRF RX018A BYPASS IRF RX018C BYPASS IMF SI12A IMF SI01B Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start Fail loop 1B OTDT setpoint low Bypass loop 1B OTDT trip Bypass loop 1B OTDT runback 1A SI pump auto start failure 1B SI pump fails to start/run 1
None N-BOP N-SRO 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 2
IMF RM02N C-BOP C, T-SRO VC rad monitor, 0PR33J, operate failure 3
IMF FW35A C-BOP C-SRO 1A HD pump trip 4
IOR ZDI1CV181 OPEN SSF Gate GFXDI1CV181==1 DOR ZDI1CV181 C-ATC C-SRO RCP 1A Standpipe PW supply valve, 1CV181, fails open (manual closure available) 5 IMF RX18K 530 IMF RX18O 530 I, T-SRO I-BOP Loop 1C Tave channel fails low 6
None R-ATC R-BOP R-SRO Tech Spec LCO 3.0.3 ramp 7
IMF CV28B C-ATC C-SRO 1B RCP #2 seal failure 8
IMF TH06A 2000 M-ALL Small Break LOCA 9
Preload C-ATC C-SRO 1A SI pump fails to auto start, manual start is successful
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient
20-1 NRC 1 Page 2 of 23 SCENARIO OVERVIEW Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). FIN is currently troubleshooting loop 1B OTDT setpoint circuitry. Tech Spec 3.3.1 Conditions A and E have been entered (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago). Following turnover, perform 1BwOSR 3.6.6.2, sections 1 & 3 for the 1B RCFC, as a PMT for an EMD breaker swap completed last shift. Tech Spec 3.6.6 Condition C has been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). FIN is troubleshooting the 1RE01PA and 1RE01PB, RCDT Pumps 1A & 1B, auto start feature (pumps started at lower than expected RCDT level). Both pumps are available for manual operation, if required, and their control switches are in STOP at 1PM05J.
After completing shift turnover, the crew will perform 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3. The BOP will perform sections 1 and 3 of 1BwOSR 3.6.6.2 for the 1B RCFC.
Once the crew has completed the RCFC surveillance, rad monitor 0PR33J will go into operate failure. The crew will respond to the VC rad monitor failure per BwAR 2-0PR33J. The BOP will reference BwOP AR/PR-11. The SRO will enter Tech Spec 3.3.7 Condition A. The SRO will direct the BOP to place the 0B VC train in emergency mode per BwOP VC-5.
Following the completion of BwOP VC-5 to place MCR ventilation in emergency mode, the 1A HD pump will trip. The BOP will respond utilizing BwAR 1-17-D2 and start the standby 1B HD pump. The crew will respond using 1BwOA SEC-1.
Following the 1A HD pump trip, the 1A RCP Standpipe PW supply valve, 1CV181, fails open (manual closure available). The ATC will respond per BwAR 1-7-A6 and will close 1CV181 to stop filling the 1A RCP standpipe.
After 1CV181 is manually closed, loop 1C Tave channel will fail low. The crew will enter 1BwOA INST-2, Attachment A. The crew will perform 1BwOA INST-2 actions. The SRO will enter Tech Spec 3.3.1 Conditions A and E and Tech Spec 3.0.3 (2 failed OTDT channels).
After the Tave failure Tech Specs are determined, the crew will brief a Tech Spec LCO 3.0.3 plant shutdown. The crew will begin shutting down Unit 1 per 1BwGP 100-4 and will utilize 1BwGP 100-4T1/3.
Once sufficient reactivity controls have been observed, the 1B RCP #2 seal will fail open. The crew will enter 1BwOA RCP-1, determine that continued RCP operation is allowed, and manually control RCDT level at 1PM05J by manual operation of a RCDT pump.
After the crew has manually started an RCDT pump, a small break LOCA will occur. The ATC will determine that PZR level is lowering greater than 2% per minute and recommend to the SRO that a reactor trip and SI are required. The SRO will order a manual reactor trip and SI and order the crew to perform the immediate actions of 1BwEP-0. The 1A SI pump will not auto start, and the ATC will manually start the pump. The 1B SI pump will trip on starting. The crew will dispatch an EO to investigate the failure of the 1B SI pump.
Scenario completion criteria is the transition to 1BwEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
Critical Tasks:
- 1. Manually start the 1A SI pump prior to transitioning out of 1BwEP-0. (Westinghouse - CT-7) (K/A number - EPE009EA1.13, Importance - 4.4/4.4)
- 2. Trip RCPs when RCP trip criteria are met (RCS pressure < 1425 psig and high head SI flow > 100 gpm or 1A SI pump discharge flow > 200 gpm) prior to transition out of 1BwEP-1. (Westinghouse - CT-16)
(K/A Number - EPE009EA1.09, Importance - 3.6/3.6)
20-1 NRC 1 Page 3 of 23 SIMULATOR SETUP GUIDE Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
Reset to IC-31, 90%, steady state, Equilibrium Xenon, BOL OR equivalent IC.
Open SmartScenario file 20-1 NRC 1.ssf from the thumb drive and place the ssf in run.
Complete items on Simulator Ready for Training Checklist.
Release the SETUP command box.
Verify page 1 PRELOAD items are inserted:
IMF RX06C 0 Fail 1LT-519, 1A SG NR level channel, low IRF RX051A BYPASS Bypass 1LT-519 SG HI-2 level (P-14) turbine trip IRF RX051B BYPASS Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start IMF RX24B 0 Fail loop 1B OTDT setpoint low IRF RX018A BYPASS Bypass loop 1B OTDT trip IRF RX018C BYPASS Bypass loop 1B OTDT runback IMF SI12A 1A SI pump auto start failure IMF SI01B 1B SI pump fails to start/run Ensure 1A and 1C HD pumps are RUNNING.
Perform 1BwOA INST-2, Attachment E, actions for removing 1LT-519 from service in Ovation.
Perform 1BwOA INST-2, Attachment A, actions for removing loop 1B OTDT from service in Ovation.
Place flags on TSLBs and annunciators associated with 1LT-519 and loop 1B OTDT setpoint failure.
Select Loop 1C for OTDT recorder.
Place both RCDT pump control switches in STOP at 1PM05J and place flags on BOTH pump switches.
Ensure the simulator is in RUN (allow simulator to run during board walk down and turnover).
Verify 0A & 0C VA plenums in-service, 0B VA plenum in standby.
Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
Verify SER printer is clear of data.
If desired, write an IC after all the set-up actions are completed (snap to 0). This IC may be used for running the scenario on additional simulator groups.
Provide examinees with turnover sheets and a marked-up copy of 1BwOSR 3.6.6.2.
Provide turnover of unit status to oncoming crew.
20-1 NRC 1 Page 4 of 23 INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 As SM, if asked, permission is granted to perform this surveillance and EOs are briefed IAW Attachment C.
If needed, prompt Examiner to inform examinees that 15 minutes have elapsed once the 1B RCFC was started in LO speed.
As SM, acknowledge completion of 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3.
If contacted as RP, acknowledge BwOP VP-5 and VP-6 performance.
Event 2: VC rad monitor, 0PR33J, operate failure Release SSF EVENT 2 and verify the following actuates:
IMF RM02N causes 0PR33J to go into operate failure.
If dispatched as EO to investigate 0PR33J, report that the skid is in operate failure locally and no other issues exist, the sample pump appears to be running but there doesnt seem to be flow.
If called as Chemistry/RP, acknowledge request to replace filters. Wait 5 minutes and report filters have been replaced.
If dispatched as EO, acknowledge request to verify VL, VW, VV fans are tripped.
If asked, as SM, report no extra NSOs are available, and all actions will have to be performed by the on-shift crew.
If asked, as SM, extra EOs are not available to align the 0A VC train for operation at this time.
As SM, acknowledge the failure, request for maintenance support, and IR request.
Event 3: 1A HD pump trip Release SSF EVENT 3 and verify the following actuates:
IMF FW35A trips the 1A HD pump.
As SM, acknowledge the failure, 1BwOA SEC-1 entry, request for Emergency Plan evaluation, and requests for online risk assessment, maintenance support, and IR initiation.
If dispatched as EO, wait 2 minutes, then report 1A HD pump has a ground overcurrent flag at its breaker cubicle. If asked, the recently started 1B HD pump has no issues locally, and BwOP HD-2 has been completed for the 1A HD pump.
If dispatched to the 1B HD pump, report a good start. BwOP HD-1 has been completed for the 1B HD pump.
Event 4: RCP 1A Standpipe PW supply valve, 1CV181, fails open (manual closure available)
Release SSF EVENT 4 and verify the following actuates:
IOR ZDI1CV181 OPEN causes 1CV181 to fail open.
20-1 NRC 1 Page 5 of 23 SSF Gate GFXDI1CV181==1 DOR ZDI1CV181 deletes the1CV181 override when the 1CV181 C/S is placed in CLOSE.
As SM, acknowledge the failure and requests for risk evaluation, IR initiation and notification request.
Event 5: Loop 1C Tave channel failure low Release SSF EVENT 5 and verify the following actuates:
IMF RX18K 530 fails loop 1C Tave channel low.
IMF RX18O 530 fails loop 1C Tave channel low.
As SM, acknowledge entry into 1BwOA INST-2 and emergency plan evaluation request.
As SM, acknowledge entry into Tech Spec 3.3.1 Conditions A & E and Tech Spec 3.0.3 (2 OTDT channels inoperable).
As SM, acknowledge request for writing IR, performing on-line risk assessment, and making appropriate notifications.
As SM, if requested for support for bypassing bistables in AEER, report that AEER bistables are not to be bypassed until IMD 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.
Event 6: Tech Spec LCO 3.0.3 ramp As SM, acknowledge the reactivity plan and concur with the ramp.
As Chemistry/RP, acknowledge the unit ramp down.
As Generation Dispatch/TSO, acknowledge the initiation of ramp.
Event 7: 1B RCP #2 seal failure Release SSF EVENT 7 and verify the following actuates:
IMF CV28B causes the 1B RCP #2 seal to fail open.
As SM, acknowledge entry into 1BwOA RCP-1 and request to evaluate emergency plan.
As EO, acknowledge request to locally check seal return filter DP. Wait 5 minutes and report DP is 15 psid.
As Radwaste Operator, report RCDT pump switches are in remote and 1RE1003 switch is in AUTO. If requested to open 1RE9163, report that 1RE9163 will NOT open.
If asked, as FIN Supervisor, inform shift that RCDT pumps may be run as required.
As Engineering, acknowledge request to evaluate RCP vibration and seal performance.
As SM, acknowledge request to perform risk evaluation, initiate IR and conduct notifications.
Events 8 & 9: Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start
20-1 NRC 1 Page 6 of 23 Release SSF EVENT 8 and verify the following actuates:
IMF TH06A 2000 causes a SBLOCA.
Acknowledge as SM procedure changes and E Plan evaluations as requested.
After STA requested, as STA report CSF status.
As EO, acknowledge request to investigate 1B SI pump failure. After 5 minutes, report the 1B SI pump breaker has a phase A overcurrent flag dropped, no issues found at the pump.
As EO, acknowledge the request to monitor the 1A & 1B DG operation per BwOP DG-11 & 11T2 and release the DG Panel Reset ssf command box.
As EO, when requested, open 0/1SX007 valves to obtain 8000 gpm by releasing the Throttle SX to CC ssf command box.
As EO, acknowledge the request to monitor the SFP level greater than 420 and the SFP temperature stable and periodically report the results to the STA.
As TSC, acknowledge request for RCS boron, containment sump pH, containment sump activity, and additionally fuel damage assessment samples.
As U2, acknowledge request to place hydrogen monitors in service per BwOP PS-9.
20-1 NRC 1 Page 7 of 23 Scenario No:
20-1 NRC 1 Event No.
1 Event
Description:
1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 Time Position Applicants Actions or Behavior CUE Turnover item to perform 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3.
SRO Brief BOP to perform 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 (may have been previously performed).
BOP Refer to 1BwOSR 3.6.6.2, REACTOR CONTAINMENT FAN COOLER SURVEILLANCE:
Complete section 1:
Verify all Prerequisites, Precautions, Limitations and Actions are addressed.
Complete AS FOUND equipment status.
Complete section 3:
Verify/stop 1B RCFC per BwOP VP-6.
Start 1B RCFC in LO speed per BwOP VP-5.
Record 15-minute run time for 1B RCFC.
Return RCFCs to AS FOUND status (HI speed) using BwOP VP-5 and BwOP VP-6.
Record AS LEFT equipment status.
Notify SRO that 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 are complete.
CUE EXAMINERS NOTE: Cue the examinee that 15 minutes have elapsed since the 1B RCFC was started in LO speed.
ATC Monitor remainder of MCBs.
SRO Acknowledge report that 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 are complete.
o Notify SM that 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 are complete.
EXAMINERS NOTE: After the actions for the RCFC surveillance are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 8 of 23 Scenario No:
20-1 NRC 1 Event No.
2 Event
Description:
VC rad monitor, 0PR33J, operate failure Time Position Applicants Actions or Behavior CUE RMS alarm.
0PR33J indicators turn blue (operate failure).
BOP Recognize 0PR33J operate failure.
Refer to BwAR 2-0PR33J.
Notify SRO to refer to TLCO 3.3.p and Tech Spec 3.3.7.
Refer to BwOP AR/PR-11A5.
o Notify Chemistry and Rad Protection of rad monitor status.
o Dispatch EO to 0PR33J.
SRO Direct BOP to address RMS alarm.
Enter LCO 3.3.7 Condition A.
Direct the BOP to place 0B VC train into emergency mode per BwOP VC-5.
Notify SM of Tech Spec 3.3.7 entry and VC train status.
ATC Monitor remainder of MCBs.
BOP Refer to BwOP VC-5, PLACING THE CONTROL ROOM HVAC SYSTEM MAKEUP FILTER TRAIN AND RECIRCULATION CHARCOAL ABSORBER IN OPERATION.
Determine steps F.1 and F.3 apply.
Verify Train 0B M/U Fltr Inlet sel switch is in AUTO at 0PM02J.
START 0VC03CB (0B M/U Fan) using the control switch on 0PM02J.
Check alignment of the Makeup Air Filter Unit Dampers at 0PM02J:
VERIFY 0VC08Y indicates open/throttled.
VERIFY 0VC282Y indicates closed.
VERIFY 0VC16Y indicates closed.
VERIFY 0VC313Y indicates closed.
VERIFY 0VC09Y indicates open.
Line-up 0VC02FB as follows:
PLACE the Recirculation Charcoal Absorber 0B Control Selector Switch in the ABSORB position on 0PM02J.
CHECK the alignment of Recirculation Charcoal Absorber 0B dampers on 0PM02J as follows:
VERIFY 0VC44Y, RECIRC CHAR ABSORB BYP DAMPER, indicates CLOSED.
VERIFY 0VC05Y, RECIRC CHAR ABSORB INLET DAMPER, indicates OPEN.
VERIFY 0VC06Y, RECIRC CHAR ABSORB OUTLET DAMPER, indicates OPEN.
VERIFY 0VC03Y, MCR RETURN AIR FAN OUTLET DAMPER, indicates OPEN on 0PM02J.
VERIFY 0VC04Y, MCR MAX OUTSIDE AIR DAMPER, indicates CLOSED on 0PM02J.
VERIFY 0VC02Y, MCR EXH DAMPER TO TURB BLDG, indicates CLOSED on 0PM02J.
EXAMINERS NOTE: If the crew asks, no extra EOs are available to swap trains.
20-1 NRC 1 Page 9 of 23 Scenario No:
20-1 NRC 1 Event No.
2 Event
Description:
VC rad monitor, 0PR33J, operate failure Time Position Applicants Actions or Behavior EXAMINERS NOTE: After the applicable VC system Tech Spec has been determined and the 0B VC train is placed in the emergency mode, and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 10 of 23 Scenario No:
20-1 NRC 1 Event No.
3 Event
Description:
1A HD Pump Trip Time Position Applicants Actions or Behavior CUE
- Annunciator 1-17-D2, HD PUMP TRIP, LIT.
- Annunciator 1-17-D3, HD PUMP DSCHG FLOW HIGH, LIT.
- HD tank level rising.
- HD pump discharge valves opening.
- Recognize 1A HD pump tripped.
- Report failure to SRO.
- Refer to BwAR 1-17-D2.
Start a standby HD pump (1B).
Verify 2 HD pumps are running.
Place 1A HD pump to PULLOUT.
- Acknowledge 1A HD pump trip.
- Enter 1BwOA SEC-1, SECONDARY PUMP TRIP, ATTACHMENT D, HD PUMP TRIP MODE 1 OR 2, and direct operator actions of 1BwOA SEC-1.
- Contact SM to perform risk assessment and to initiate IR.
- Restore HD flow.
Start 1B HD pump (previously performed).
- Check HD pump status:
HD pumps - At least one running.
HD pumps - Two running (YES).
- Check HD tank level:
Level - STABLE OR DROPPING.
Level < 76%.
- Check 1HD117, HD TANK OVERFLOW VALVE - in auto and closed.
Running HD pumps amps < 168 amps - 1C HD pump, 176 amps -1B HD pump.
Running HD pump flows < 2950 KLB/HR per pump.
o Deactivate turbine runback (NOT used).
ATC Check Delta I within limits of BwCB-1 Figure 19.
Check PDMS operable:
Annunciator PDMS INOPERABLE not lit (1-10-E8).
1BwOS PDMS-1A not implemented.
Annunciator PDMS LIMIT EXCEEDED not lit (1-10-D7).
Control Delta I near target.
o Adjust RCS boron concentration as necessary.
BOP Verify running CB pump recirc valves in auto:
1CB113A-D on running pumps.
Dispatch operators to perform BwOP HD-2 for 1A HD pump.
Dispatch operators to perform BwOP HD-1 for 1B HD pump.
Shutdown CD/CB pump (if started during procedure performance).
Adjust SG blowdown flows and calorimetric inputs as necessary.
o Complete applicable actions of 1BwGP 100-4, POWER DESCENSION.
SRO o Enter Tech Spec 3.4.1 Condition A if PZR pressure drops below 2209 psig.
Check reactor power change GREATER THAN 15% IN ONE HOUR (NO).
Notify SM of plant status, need for maintenance assistance and perform required notifications.
EXAMINERS NOTE: After the actions for the 1A HD Pump trip are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 11 of 23 Scenario No:
20-1 NRC 1 Event No.
3 Event
Description:
1A HD Pump Trip Time Position Applicants Actions or Behavior Scenario No:
20-1 NRC 1 Event No.
4 Event
Description:
RCP 1A Standpipe PW supply valve, 1CV181, fails open (manual closure available)
Time Position Applicants Actions or Behavior CUE Annunciator 1-7-A6, RCP 1A STANDPIPE LEVEL HIGH, lit.
1CV181, RCP 1A STANDPIPE PW SUPPLY VALVE, is open.
ATC Perform the following actions per BwAR 1-7-A6:
CLOSE 1CV181.
o Notify SRO to refer to 1BwOA RCP-1, RCP SEAL FAILURE.
BOP Monitor remainder of MCBs.
SRO Acknowledge report from ATC.
Refer to 1BwOA RCP-1 (no actions are required).
SRO Notify SM to perform risk evaluation, initiate IR and make notifications as appropriate.
EXAMINERS NOTE: After the actions for the 1CV181 failure are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 12 of 23 Scenario No:
20-1 NRC 1 Event No.
5 Event
Description:
Loop 1C Tave channel fails low Time Position Applicants Actions or Behavior CUE Annunciator 1-14-C3, LOOP 1C TAVE DEV LOW, lit.
Annunciator 1-14-C5, LOOP 1C DT DEV LOW, lit.
Loop 1C Tave lowers.
Loop 1C T fails low.
ATC Determine loop 1C Tave has failed.
Report failure to SRO.
BOP Reference BwARs as time permits.
SRO Notify SM of plant status and procedure entry.
Request SM to evaluate Emergency Plan conditions.
Enter 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, ATTACHMENT A, RCS NARROW RANGE RTD CHANNEL FAILURE, and direct the following operator actions:
ATC Check rod control status (rods NOT moving).
Check reactor power < 100%.
Check PZR level normal & stable.
Check P-12 interlock.
LO-2 TAVE STM DUMP INTLK P12 (1-BP-4.5) - NOT LIT.
BOP Remove the failed Tave and DT channels from service:
On OWS graphic 6020:
Select T-AVG in the signal selectors box.
Select the T-AVG MASTER header to enable the window.
Select place out of service for RC-TY-0432C.
Exit the window.
Select DELTA-T in the signal selectors box.
Select the DELTA-T MASTER header to enable the window.
Select place out of service for RC-TY-0431D.
Exit the window.
Select OP DELTA-T in the signal selectors box.
Select the OP DELTA T SETPOINT header to enable the window.
Select place out of service for RC-TY-0431F.
Exit the window.
Select OT DELTA-T in the signal selectors box.
Select the OT DELTA T SETPOINT header to enable the window.
Select place out of service for RC-TY-0431G (CANNOT perform, ONLY 1 channel can be OOS).
Exit the window.
ATC Check if rod control can be placed in auto (rods remained in AUTO).
BOP Select an operable RTD channel to the T recorder.
On OWS graphic 6020:
Select the DELTA-T, OPDT, OTDT RECORDER.
20-1 NRC 1 Page 13 of 23 Scenario No:
20-1 NRC 1 Event No.
5 Event
Description:
Loop 1C Tave channel fails low Time Position Applicants Actions or Behavior BOP Select the DELTA-T, OPDT, OTDT CHANNEL SELECT header to enable the window.
Select an operable channel (A or D).
Exit the window.
Remove SPDS inputs using the PPC PDMS Test Mode page:
Place PPC point T0442A IN TEST.
DELETE FROM SCAN PPC point T0440.
SRO Bypass loop 1C Tave channel bistables (will be delayed).
EXAMINERS NOTE: Tech Spec 3.3.1 was previously entered for the failed loop 1B OTDT setpoint circuitry (turnover item). However, Tech Spec 3.0.3 must now be entered with 2 failed OTDT setpoint channel failures in addition to Tech Spec 3.3.1 (separate entry).
SRO Enter Tech Spec 3.0.3 (2 failed OTDT channels).
Enter Tech Spec 3.3.1 Conditions A and E (separate entry).
SRO Notify SM/maintenance of loop 1C Tave channel failure.
Notify SM of unit status, emergency plan notification and Tech Spec status.
Notify SM of the required Tech Spec LCO 3.0.3 ramp.
Notify SM to perform risk assessment, initiate IR, evaluate reactivity screening, notify QNE and contact personnel to investigate/correct instrument failure.
EXAMINERS NOTE: After the actions for the Tave channel failure are complete, the crew will perform actions to initiate the Tech Spec LCO 3.0.3 ramp (event 6).
20-1 NRC 1 Page 14 of 23 Scenario No:
20-1 NRC 1 Event No.
6 Event
Description:
Tech Spec LCO 3.0.3 ramp Time Position Applicants Actions or Behavior CUE Determine from Tech Spec LCO 3.0.3 that a unit shutdown is required.
SRO o Perform pre-job brief per HU-AA-1211, PRE-JOB BRIEFINGS, for load ramp.
o Perform pre-job brief using the Emergent Ramp Reactivity Summary Sheet (OP-BR-108-101-1002) (under the NSO desk glass) for load ramp.
CREW Review Operator Aid for LCO 3.0.3 reactivity plan.
Review applicable Prerequisites, Precautions, and Limitations and Actions of 1BwGP 100-4.
Notify TSO/Constellation of starting the ramp.
EXAMINERS NOTE: The following step may be repeated as necessary to borate the RCS during the power descension.
ATC Initiate boration per BwOP CV-6.
BwOP CV-6 Attachment A, borate in automatic, via hard card (if authorized) or procedure. Perform the following at 1PM05J:
Determine required boric acid volume.
o Refer to operator aid for required boric acid addition.
Determine desired boric acid flow rate.
o Turn on PZR backup heaters (as desired).
- Set BA totalizer to desired value.
- Set BA controller setpoint to desired BA flowrate.
- 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 If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
- When desired boration achieved, place RMCS M/U CONT switch to STOP.
- Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped.
Record boration in Unit log.
Perform BwOP CV-7 to return RMCS to automatic.
- OR -
BwOP CV-6 Attachment A, batch boration, via hard card (if authorized) or procedure. Perform the following at 1PM05J:
o Turn on PZR backup heaters (as required).
o If desired, reset the BA blender predetermined setpoint.
Open 1CV110B.
Open 1CV110A.
Start the BA Transfer pump.
o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
When desired amount of BA has been added, stop the BA Transfer Pump.
Close 1CV110A.
20-1 NRC 1 Page 15 of 23 Scenario No:
20-1 NRC 1 Event No.
6 Event
Description:
Tech Spec LCO 3.0.3 ramp Time Position Applicants Actions or Behavior ATC Close 1CV110B.
o Adjust 1LK-112, VCT level controller, setpoint to desired value.
Place 1CV110A/B to AUTO.
Record boration in Unit log.
Perform BwOP CV-7 to return RMCS to automatic.
BOP Lower turbine load at 1PM02J or OWS drop 210 by performing the following:
Select SETPOINT.
Enter desired MWs into REF DEMAND window.
Select LEFT ENTER.
Verify correct value in REFERENCE DEMAND window.
Enter desired MW/min into the RATE window.
Select RIGHT ENTER.
Verify correct value in RATE window.
Select EXIT.
Inform crew of pending ramp with an UPDATE.
Select GO/HOLD.
Verify GO/HOLD button illuminates orange.
Verify HOLD illuminated RED.
Select GO.
Verify GO illuminates RED.
Verify main turbine load begins to lower.
Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.
ATC Perform periodic control rod steps/boron concentration adjustment to maintain Tave and Delta I within limits.
Monitor NIs, Tave, I, PZR pressure/level at 1PM05J or PPC.
Monitor MWe and DEHC system response on Ovation.
During boration, monitor the following at 1PM05J, PPC and/or Ovation:
VCT level.
RCS Tave.
o Refer to 1BwGP 100-4 for additional guidance as necessary.
EXAMINERS NOTE: After sufficient reactivity control is evaluated and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 16 of 23 Scenario No:
20-1 NRC 1 Event No.
7 Event
Description:
1B RCP #2 Seal Failure Time Position Applicants Actions or Behavior CUE Annunciator 1-7-B3, RCP SEAL LEAKOFF FLOW HIGH, lit.
Annunciator 1-7-C3, RCP SEAL LEAKOFF FLOW LOW, lit.
1B RCP seal leakoff flow lowering.
ATC Determine 1B RCP #2 seal has failed open by SER point 1660 being printed.
CREW Refer to BwARs as time permits.
Identify entry conditions for 1BwOA RCP-1, RCP SEAL FAILURE.
SRO Notify Shift Manager of 1B RCP seal failure.
Direct the BOP to hold the load ramp.
Direct actions per 1BwOA RCP-1:
ATC/
BOP Check NO.1 seal DP. (>200 psid)
Check NO. 1 seal leakoff flow. (GO TO step 3 for low flow)
Verify NO. 1 seal leakoff flow path:
Check No. 1 seal leakoff isolation valves (1CV8141A-D) open.
Check No. 1 seal leakoff cnmt isolation valves (1CV8100/8112) open.
Check VCT pressure <65 psig.
Dispatch operator to check seal return filter DP <20psid.
Check for failed leakoff flow instrument. (NO)
Check Seal injection flow path:
Check RCP seal injection valves (1CV8355A-D) open.
Check seal injection flow between 8-13 gpm.
Check Annunciator 1-7-A2 NOT LIT.
Check No. 1 seal leakoff flow still low.
Determine if affected RCP may continue to run. (YES, #2 Seal leakoff flow high, GO TO step 15).
EXAMINERS NOTE: The crew may also use BwOP RE-1, step F.2 to manually start a RCDT pump.
ATC/
Either RCDT pump available.
RCDT pump switch at Radwaste Panel in remote (YES).
RCDT pump switch at 1PM05J in AUTO (NO - ATC), contacts FIN and place RCDT pump switch to ON or AUTO.
1RE1003 switch at Radwaste Panel in auto (YES).
1RE1003 switch at 1PM11J in local (YES).
1RE9170 at 1PM11J - OPEN (YES).
Monitor RCDT level and control by manually operating RCDT pumps.
Check No. 3 seal operating conditions.
Check RCS leak rate (SRO refers to Tech Specs 3.4.13 and 3.5.5).
SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
o May establish a critical parameter for RCDT level.
o Notify FIN of RCDT pump manual control.
Notify Engineering to evaluate RCP performance.
EXAMINERS NOTE: After the actions for 1B RCP #2 seal failure are complete including manually starting an RCDT pump and with Lead Examiners concurrence, insert next event.
20-1 NRC 1 Page 17 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior CUE Pressurizer pressure lowering Pressurizer level lowering Annunciator 1-12-C1, PZR PRESS CONT DEV LOW HTRS ON, lit.
Annunciator 1-12-B4, PZR LEVEL CONT DEV LOW, lit.
Containment pressure rising ATC Identify/report pressurizer level/pressure trend and recommend reactor trip and SI.
SRO Direct ATC to trip reactor, verify the reactor is tripped and then SI.
CREW Initiate a manual reactor trip and SI, transition to 1BwEP-0, and perform immediate actions from memory.
SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
Enter 1BwEP-0 and direct operator actions of 1BwEP-0.
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/Ovation graphics:
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/BOP Check SI status at 1PM05J/1PM06J:
SI First OUT annunciator - LIT.
SI ACTUATED Permissive Light - LIT.
SI Equipment - AUTOMATICALLY ACTUATED.
Either SI pump - RUNNING (NO - 1A SI pump can be manually started).
Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
Manually actuate SI from 1PM05J and 1PM06J.
EXAMINERS NOTE: SRO and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
Verify FW isolated at 1PM04J:
FW pumps - TRIPPED.
Isolation monitor lights - LIT.
FW pump discharge valves (1FW002A-C) - CLOSED (or going closed).
20-1 NRC 1 Page 18 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior Verify DGs running at 1PM01J:
DGs - BOTH RUNNING.
1SX169A/B OPEN.
Dispatch operator to monitor DGs operation.
Verify Generator trip at 1PM01J:
OCB 1-8 and 7-8 open.
PMG output breaker open.
Verify SX pumps running.
Check U-0 CC Heat Exchanger aligned to U-1:
1CC9473A - OPEN.
1CC9473B - OPEN.
Unit 1 SX pumps - BOTH running.
Dispatch an operator to energize the 0SX007 & 1SX007 valves.
Adjust flow to 8000 gpm to U-1 & U-0 CC HX.
Deenergize the 0SX007 & 1SX007 valves.
BOP Verify Control Room ventilation aligned for emergency operation at 0PM02J:
VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT (0PR33J operate failure).
Operating VC train equipment - RUNNING.
0B Supply fan 0B Return fan 0B M/U fan 0B Chilled water pump 0B Chiller Operating VC train dampers - ALIGNED.
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 > +0.125 inches water on 0PDI-VC038.
Verify Auxiliary Building ventilation aligned for emergency operation at 0PM02J:
Two inaccessible filter plenums aligned.
Plenum A:
- 0VA03CB - RUNNING.
- 0VA023Y - OPEN.
- 0VA436Y - CLOSED.
Plenum C:
- 0VA03CF - RUNNING.
- 0VA072Y - OPEN.
- 0VA438Y - CLOSED.
20-1 NRC 1 Page 19 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior Verify FHB ventilation aligned for emergency operation at 0PM02J:
0VA04CB - RUNNING.
0VA055Y - OPEN.
0VA062Y - OPEN.
0VA435Y - CLOSED.
Secure HD pumps.
Shutdown FW pumps as necessary.
Shutdown all unnecessary CD/CB pumps - Leave as is.
Shutdown all unnecessary CW pumps - Leave as is.
Notify Equipment Operator to initiate periodic checking of Spent Fuel Pool level and temperature and notify STA of results.
Notify SRO Attachment B is complete.
ATC/
[CT-7]
Verify ECCS pumps running:
BOTH CV pumps - RUNNING.
BOTH RH pumps - RUNNING.
SI pumps - NONE RUNNING (1B SI pump will NOT start).
Manually start the 1A SI pump prior to transitioning out of 1BwEP-0.
(Westinghouse - CT-7) (K/A number - EPE009EA1.13, Importance -
4.4/4.4)
Manually start 1A SI pump.
ATC Perform the following at 1PM06J:
Verify RCFCs running in Accident Mode:
Group 2 RCFC Accident Mode lights - LIT.
Verify Phase A isolation:
Group 3 Cnmt Isol monitor lights - LIT.
Verify Cnmt Vent isolation:
Group 6 Cnmt Vent Isol monitor lights - LIT.
Verify AF system:
AF pumps - BOTH RUNNING.
AF isolation valves - 1AF13A-H OPEN.
AF flow control valves - 1AF005A-H THROTTLED.
Verify CC pumps - BOTH RUNNING.
Verify SX pumps - BOTH RUNNING.
Check if Main Steamline Isolation is required:
All S/G pressures >640 psig (at 1PM04J).
CNMT pressure <8.2 psig (at 1PM06J).
When CNMT pressure is >8.2 psig, then verify MSIVs & MSIV bypass valves - CLOSED.
Check if CS is required:
CNMT pressure has remained <20 psig.
AF flow > 500 GPM.
Check SG narrow range levels not rising in an uncontrolled manner.
20-1 NRC 1 Page 20 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior ATC Verify ECCS valve alignment at 1PM06J:
Group 2 Cold Leg Injection monitor lights required for injection - LIT.
Verify ECCS flow:
High Head SI flow >100 gpm (1FI-917).
RCS pressure <1700 psig.
1A SI pump discharge flow (1FI-918) >200 gpm.
ATC Check PZR PORVs and SPRAY VALVES at 1PM05J:
PORVs CLOSED.
PORV isol valves - BOTH ENERGIZED.
PORV relief path - BOTH available.
Normal PZR spray valves - CLOSED.
ATC/BOP Check RCS temperatures at 1PM05J:
If RCPs running, RCS Tave stable at or trending to 557oF.
If RCPs not running, RCS Cold leg temperatures stable at or trending to 557oF.
Throttle AF flow if temperature is low.
[CT-16]
Check status of RCPs at 1PM05J:
RCPs - ANY RUNNING.
ECCS flow:
High head SI flow (1FI-917) >100 gpm.
1A SI pump discharge flow (1FI-918) >200 gpm.
RCS pressure <1425 psig.
Trip RCPs when RCP trip criteria are met (RCS pressure < 1425 psig and high head SI flow > 100 gpm or 1A SI pump discharge flow > 200 gpm) prior to transition out of 1BwEP-1. (Westinghouse - CT-16) (K/A Number
- EPE009EA1.09, Importance - 3.6/3.6)
Trip all RCPs.
CREW Check if SG secondary pressure boundaries are intact at 1PM04J:
- Check pressure in all SGs:
No SG pressure dropping in an uncontrolled manner.
No SG completely depressurized.
BOP Check if SG tubes are intact:
- SG NR levels - NOT RISING IN AN UNCONTROLLED MANNER.
- Check the following have remained < alert alarm setpoint at RMS:
1PR08J, SG Blowdown.
1PR27J, SJAE/GS.
1AR22/23A-D, 1A-D Main Steam Line.
- Check if RCS is intact:
- CNMT area rad monitors > alert alarm setpoint.
- CNMT pressure >3.4 psig (1PI-CS934-937).
CREW Transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.
20-1 NRC 1 Page 21 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
Request STA evaluation of status trees.
Enter 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, and direct operator actions of 1BwEP-1:
CREW Determine and announce containment is adverse when containment pressure rises above 5 psig.
ATC/BOP Check status of RCPs at 1PM05J:
o RCPs - ANY RUNNING (if NO, GO TO next step below). If YES, continue with this step.
o ECCS flow:
o High head SI flow (1FI-917) >100 gpm.
o 1A SI pump discharge flow (1FI-918) >200 gpm.
o RCS pressure <1425 psig.
o Trip all RCPs when RCS pressure is <1425 psig.
ATC/BOP Check if SG secondary pressure boundaries are intact at 1PM04J:
- Check pressure in all SGs:
No SG pressure dropping in an uncontrolled manner.
No SG completely depressurized.
ATC/BOP Check intact SG levels at 1PM04J:
- Narrow range levels - greater than 10% (31% adverse cnmt).
- Control feed flow to maintain narrow range levels - between 10% (31%
adverse CNMT) and 50%.
ATC/BOP Check secondary radiation normal:
- Reset CNMT isolation phase A if necessary.
- Sample all SGs for activity:
Open SG Blowdown Sample Isol valves:
1SD005A (SG 1A) 1SD005C (SG 1B) 1SD005D (SG 1C) 1SD005B (SG 1D)
Request Chem Dept to sample all SGs for activity.
- Check for secondary radiation trends - Normal for plant conditions:
SJAE/Gland Steam Exhaust Gas radiation, 1PR27J.
SG Blowdown Liquid radiation, 1PR08J.
1A MS line, 1AR22/1AR23.
1B MS line, 1AR22/1AR23.
1C MS line, 1AR22/1AR23.
1D MS line, 1AR22/1AR23.
Secondary activity samples normal (when available).
ATC/BOP Check PZR PORVs and ISOLATION VALVES at 1PM05J:
PORV isol valves - BOTH energized.
PORVS - BOTH closed.
PORV isol valves - BOTH open.
20-1 NRC 1 Page 22 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior ATC/BOP Check if ECCS flow should be reduced:
RCS subcooling acceptable (NO).
Secondary heat sink >500 gpm or SG level NR >10% (31%).
RCS pressure stable or rising.
PZR level >14% (28%) (NO).
ECCS flow is required.
ATC/BOP Check if CS should be stopped:
CS pumps - ANY RUNNING (NO).
ATC/BOP Check if RH pumps should be stopped:
Reset SI if necessary:
Depress both SI reset pushbuttons.
Verify SI ACTUATED permissive light - NOT LIT.
Verify AUTO SI BLOCKED permissive light - LIT.
Check RCS pressure:
Pressure - Greater than 325 psig.
Pressure stable or rising.
RH pumps - Any running with suction aligned to RWST.
Stop RH pumps and place in standby (if conditions are met).
Examiner Note: If the crew has secured RCPs, all critical tasks have been completed and the scenario may be terminated. If not the scenario must continue until the crew transitions to 1BwEP ES-1.2.
ATC/BOP Check RCS and SG pressures for faulted SG indications:
Check pressure in all SGs - STABLE or RISING.
Check RCS pressure - STABLE or DROPPING.
ATC/BOP Check if DGs should be stopped:
4KV busses - energized by offsite power:
Bus 141 Bus 142 Bus 143 Bus 144 Stop any unloaded DG and place in standby per BwOP DG-12, DIESEL GENERATOR SHUTDOWN.
ATC/BOP Initiate evaluation of plant status:
Check cold leg recirculation capability (Both Trains Available)
Check Aux Building radiation trends (PPC or RMS) normal for plant conditions (ALL normal)
Obtain Samples:
Request U2 admin place hydrogen monitors in service per BwOP PS-9.
Consult TSC for obtaining RCS boron, containment sump pH, containment sump activity, and additional samples required for fuel damage assessments.
Evaluate plant equipment of long term recovery:
ESF Equipment Post accident monitoring instrumentation
20-1 NRC 1 Page 23 of 23 Scenario No:
20-1 NRC 1 Event No.
8 & 9 Event
Description:
Small Break LOCA with 1A SI pump failing to start in auto, 1B SI pump trips on start Time Position Applicants Actions or Behavior Radiation monitoring Other equipment as necessary Shutdown chiller on non-operating VC train Start additional equipment as directed by unit supervisor (NONE)
Check if source range detectors should be energized:
Place boron dilution alert alarm switches to normal.
Place scaler timer power switch - on.
Check IR current - less than 5x10-11 amps (YES).
Verify SR detectors - Energized (YES).
Verify count rate - audible.
ATC/SRO Check if RCS cooldown and depressurization is required:
RCS pressure - greater than 325 PSIG (YES).
GO TO 1BwEP ES-1.2, Post LOCA cooldown and Depressurization, Step 1.
CREW Transition to 1BwEP ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
EXAMINERS NOTE: At this point in the scenario, all Critical Tasks are complete and the scenario stop criteria has been reached, with Lead Examiners concurrence, STOP the scenario.
20-1 NRC 2 Page 1 of 18 Enter Simulation Facility Braidwood Scenario No.:
NRC 2 Operating Test No.: 20-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-18 Turnover Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following completion of turnover, the crew is to perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF FW43 IMF FW44 IMF RD05G13 15 IMF RD05H12 15 IMF RD05H10 24 IMF RD05J13 25 IMF TC03 IMF MS01A 100 IMF MS01B 100 IMF MS01C 100 IMF MS01D 100 IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS SSF Gate RP:52HRTA==
FALSE IMF RP09A 1A AF pump fails to start 1B AF pump fails to start Stuck rod G13 Stuck rod H12 Stuck rod H10 Stuck rod J13 Main turbine auto trip failure 1A-1D MSIVs failed open Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start Inadvertent FWI on reactor trip 1
None N-BOP N-SRO 1BwOS FW-M2 FW pump oil reservoir Hi/Lo alarm surveillance 2
IMF CH03A C-BOP C-SRO 1A CRDM Exhaust Fan trip 3
IMF RD02H08 C-ATC C, T-SRO Dropped rod H-8 4
None R-ATC N-BOP R-SRO Power reduction for dropped rod recovery
20-1 NRC 2 Page 2 of 18 5
IMF SLIM12ManPB PRESSED IMF SLIM12OutDecPB PRESSED IRF OV12 TRUE I-ATC I-SRO Master Pressurizer Level Controller (1LK-0459) output fails LOW Loss of power to 1LK-0459 6
IOR ZDI0VC01CA TRIP DOR ZDI0VC01CA C-BOP C, T-SRO 0A MCR Supply Fan trip 7
IMF RD02M04 Preload M-ALL Dropped rod M-4 Inadvertent FWI on reactor trip 8
Preload C-BOP C-SRO Main Turbine Auto Trip failure 9
Preload C-ATC C-SRO Four stuck rods requiring emergency boration 10 IMF FW19B 3.5 M-ALL 1B SG feedline break / loss of heat sink
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
20-1 NRC 2 Page 3 of 18 SCENARIO OVERVIEW Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following completion of turnover, the crew is to perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.
After completing shift turnover and relief, the crew will perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.
Once the crew completes the 1B TDFWP surveillance, the 1A CRDM exhaust fan will trip. This will require the BOP to respond using BwARs 0-33-A5/B5. The BOP will send an operator to the breaker to investigate, and the BOP will swap the CRDM exhaust fans per BwOP VP-9/10.
Following the restoration of CRDM exhaust fans, rod H-8 will drop. Rods will initially step out to respond to the transient. The ATC will receive numerous alarms related to the dropped rod and will place rod control in manual. The SRO will enter 1BwOA ROD-3, RESPONSE TO A DROPPED OR MISALIGNED ROD, and enter Tech Spec 3.1.4 Condition B. 1BwOA ROD-3 will require power to be reduced to < 70% to recover the dropped rod. The crew will brief and begin to ramp to < 70%.
After sufficient reactivity controls have been observed, the Master Pressurizer Level Controller (1LK-0459) output will fail low prior to losing power. The crew will take manual control of the 1CV121 controller and manually control charging flow to restore PZR level.
When the crew has completed taking the actions for the Master Pressurizer Level Controller failure, the 0A MCR Supply Fan will trip. The crew will send an EO to investigate the cause. Upon receiving the report that local indications include motor damage, the crew will start the 0B VC train as directed by BwAR 0-33-A8, MCR SUP FAN 0A TRIP DP HIGH LOW, and BwOP VC-1. The SRO will enter Tech Spec 3.7.10 Condition A.
After the 0A MCR Supply Fan failure is addressed, rod M-4 will drop. The ATC will diagnose the dropped rod and corresponding change in Tave and recommend a reactor trip the SRO. The SRO will order the ATC to trip the reactor and verify reactor trip. The SRO will enter 1BwEP-0 and direct the performance of immediate actions. When the reactor trips, one control bank rod and three shutdown bank rods will not fully insert.
Feedwater will isolate immediately on the reactor trip vs. on low Tave due to a SSPS card failure. The turbine will fail to automatically trip, requiring a manual trip. Both AF pumps will fail to start and cannot be manually started. The crew will transition to 1BwEP ES-0.1, REACTOR TRIP RESPONSE, and initiate emergency boration for the 4 stuck rods. An automatic SI signal may be generated if the main turbine is not manually tripped expeditiously.
Once the crew has established emergency boration or after an SI actuates, a 1B SG feedline break inside Cnmt will occur. The MSIVs will fail to close automatically or on manual steamline isolation signals.
The crew will transition to 1BwFR-H.1 due to a loss of heat sink at step 15 of 1BwEP-0 or based on STA status tree results. When Wide Range SG levels are < 43% (adverse Cnmt), the crew will initiate RCS bleed and feed.
Scenario completion criteria is establishing RCS Bleed and Feed.
Critical Tasks:
- 1. Manually trip the main turbine before a severe challenge (ORANGE path) develops to either subcriticality or integrity critical safety function or before transition to 1BwCA-2.1, whichever happens first. (Westinghouse -
CT-13) (K/A Number - EPE007EA1.07, Importance - 4.3/4.3)
- 2. Establish RCS bleed and feed before either PZR PORV opens automatically as a result of a loss of heat sink. (Westinghouse - CT-44) (K/A Number - EPE05EA1.1, Importance - 4.1/4.0)
20-1 NRC 2 Page 4 of 18 SIMULATOR SETUP GUIDE Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
Reset to IC-18, 75% power, steady state, equilibrium Xenon, BOL OR equivalent IC.
Open SmartScenario file 20-1 NRC 2.ssf from the thumb drive and place the ssf in run.
Complete items on Simulator Ready for Training Checklist.
Release the SETUP command box.
Verify page 1 PRELOAD items are inserted:
IMF FW43 1A AF pump fails to start IMF FW44 1B AF pump fails to start IMF RD05G13 15 Stuck Rods IMF RD05H12 15 IMF RD05H10 24 IMF RD05J13 25 IMF TC03 Turbine auto trip failure IMF MS01A 100 1A-1D MSIVs failed open IMF MS01B 100 IMF MS01C 100 IMF MS01D 100 IMF RX06C 0 Fail 1LT-519, 1A SG NR level channel, low IRF RX051A BYPASS Bypass 1LT-519 SG HI-2 level (P-14) turbine trip IRF RX051B BYPASS Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start Ensure command block with the following is ACTIVE:
SSF Gate RP:52HRTA==FALSE Inadvertent FWI on reactor trip IMF RP09A Ensure the simulator is in RUN (allow simulator to run during board walk down and turnover).
Verify 0A & 0C VA plenums in-service, 0B VA plenum in standby.
Place flags on TSLBs and annunciators associated with 1LT-519.
Perform 1BwOA INST-2, Attachment E, actions for removing 1LT-519 from service in Ovation.
Verify 1A & 1C CRDM exhaust fans are running.
Verify 0A MCR ventilation train is in service, 0B VC train in standby.
Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
Verify SER printer is clear of data.
If desired, write an IC after all the set-up actions are completed (snap to 0). This IC may be used for running the scenario on additional simulator groups.
Provide examinees with turnover sheets and copy of 1BwOS FW-M2.
Provide turnover of unit status to oncoming crew.
20-1 NRC 2 Page 5 of 18 INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1BwOS FW-M2 FW pump oil reservoir Hi/Lo level alarm surveillance As EO, observe 1B FW pump during surveillance performance, report all system parameters are normal throughout the surveillance.
As SM, acknowledge completion of procedure.
Event 2: 1A CRDM Exhaust Fan trip Release SSF EVENT 2 and verify the following actuates:
IMF CH03A to trip the 1A CRDM Exhaust Fan.
If asked to investigate as an EO, after 2 minutes, report that the MCC breaker for the 1A CRDM Exhaust Fan (133X6 A3) is closed with no apparent cause for the fan trip.
As SM, acknowledge the fan failure and IR request.
Event 3: Dropped rod H-8 Release SSF EVENT 3 and verify the following actuates:
IMF RD02H08 to drop control rod H-8.
If dispatched as EO to investigate the dropped rod, wait 3 minutes, then report that at 1RD03J, stationary gripper fuses FU27 & 31 are blown for rod H-8, no other abnormalities were noted in the panel.
If asked to replace fuses, report supply has been contacted and it will be 30 minutes before the fuses are obtained.
If called as Engineering, IMD or EMD to troubleshoot rod control blown fuse, acknowledge request and state a troubleshooter will be developed.
As SM, acknowledge the failure and requests for on-line risk assessment, Tech Spec call, E-Plan evaluation, maintenance support and IR initiation. Acknowledge the load ramp.
As U-2 NSO, acknowledge the request to perform 1BwOSR 3.1.1.1-2, SHUTDOWN MARGIN SURVEILLANCE DURING OPERATION.
Event 4: Power reduction to recover rod As SM, acknowledge reactivity plan for required rod recovery ramp.
Event 5: Master Pressurizer Level Controller (1LK-0459) output fails LOW Release SSF EVENT 5 and verify the following actuates:
IMF SLIM12ManPB PRESSED places 1LK-0459 in manual.
IMF SLIM12OutDecPB PRESSED fails 1LK-0459 output LOW IRF OV12 TRUE 1LK-0459 loses power.
20-1 NRC 2 Page 6 of 18 As SM, acknowledge the Master Pressurizer Level Controller failure & manual control of charging.
As SM, acknowledge the IR request, on-line risk assessment and making appropriate notifications.
Event 6: 0A MCR Supply Fan Trip Release SSF EVENT 6 and verify the following actuates:
IOR ZDI0VC01CA TRIP to trip the 0A VC Supply Fan.
One second delay, DOR ZDI0VC01CA.
If dispatched as EO to investigate 0A VC Supply Fan trip, report that the motor for the fan is charred with light smoke in the area (no fire).
If the crew directs you to locally start the standby VC train (supply and return fans), acknowledge and then 1 minute later call back and report that the local/remote transfer switch for Supply Fan 0VC01CB is stuck in the REMOTE position and recommend that the crew start the 0B VC train from the MCR.
If directed as EO to locally shutdown the 0A VC Chiller per BwOP VC-11, then use the following remote functions:
MRF HV03 LOCAL MCR Chiller 0A Remote/Local SW to LOCAL MRF HV05 OFF MCR Chiller 0A LOCAL ON/OFF SW to OFF Notify the crew that you are ready for them to place the 0A VC Chiller Unit Control Switch to AFTER TRIP at 0PM02J.
MRF HV03 REMOTE MCR Chiller 0A Remote/Local SW to REMOTE In support of starting the 0B VC Chiller provide the following information (BwOP VC-10):
Steps F 1 and 2 complete (Chilled pump suction pressure 30 psig; WO Expansion Tank level 55%,
oil level 77%).
You are ready for the crew to perform step F.3 (start of 0WO01PB Chilled Water pump at 0PM02J)
After the 0B Chilled Water pump is running:
If directed to locally start the chiller:
o MRF HV06 OFF MCR Chiller 0B LOCAL ON/OFF SW to OFF o MRF HV04 LOCAL MCR Chiller 0B Remote/Local SW to LOCAL o Contact the MCR to perform steps F.10.c and d (place the 0B MCR Chiller 0B C/S to AFTER TRIP at 0PM02J, followed by AFTER CLOSE) o MRF HV06 ON MCR Chiller 0B LOCAL ON/OFF SW to ON o MRF HV04 REMOTE to restore control of MCR Chiller 0B to the MCR o Notify the MCR that you will complete the local steps If the crew remotely starts the 0B MCR Chiller, provide reports that you will/have completed local actions as requested As SM, acknowledge failure, request for maintenance support, Tech Spec call and IR request.
Event 7, 8 & 9: Dropped rod M-4 with Inadvertent FWI on reactor trip / Main Turbine Auto Trip Failure / Four stuck rods requiring emergency boration Release SSF EVENT 7 and verify the following actuates:
IMF RD02M04 to cause a 2nd dropped rod (M-4).
20-1 NRC 2 Page 7 of 18 As SM, acknowledge procedure changes, E Plan evaluations, and STA request.
As STA, when conditions are met and an emergency boration is in progress OR an SI has occurred, notify the SRO that a Red Path in heat sink exists from the latest status tree scan.
As U-2 NSO, acknowledge the request to perform 1BwOSR 3.1.1.1-2, SHUTDOWN MARGIN SURVEILLANCE DURING OPERATION.
As EO, acknowledge request to investigate 1A AF pump failure to start. After 5 minutes, report that a phase C overcurrent flag is dropped, there is a light haze at the pump with an acrid odor, and NO fire.
Event 10: 1B SG feedline break / loss of heat sink Release SSF EVENT 10 and verify the following actuates:
IMF FW19B 3.5 to cause the feedline break.
As STA, when conditions are met, notify the SRO that a Red Path in heat sink exists from the latest status tree scan.
As EO, acknowledge request to investigate 1B AF pump trip. Wait 5 minutes and report the 1B AF pump has large lube oil leak and engine damage.
As EO, acknowledge request to start the S/U FW pump aux oil pump. Wait 3 minutes and release ssf command box Event 10 S/U FW Pump AOP.
IRF FW149 to start the S/U FW Pump AOP.
20-1 NRC 2 Page 8 of 18 Scenario No:
20-1 NRC 2 Event No.
1 Event
Description:
1BwOS FW-M2 FW pump oil reservoir Hi/Lo level alarm surveillance Time Position Applicants Actions or Behavior CUE
- From turnover, perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE.
- Brief BOP to perform 1BwOS FW-M2 for the 1B TDFWP (may have been previously performed).
- Refer to 1BwOS FW-M2.
- Perform the following for 1B FW pump at 1PM04J:
PLACE/HOLD the Lube Oil Reservoir Level Test C/S in the LOW LEVEL position on 1PM04J.
Verify the LEVEL LOW light above the C/S is LIT.
Verify annunciator 1-16-D3, FW PUMP TURB BRNG OIL LEVEL HIGH LOW, is LIT.
Release the test switch.
Record YES if the low level alarm operated correctly.
PLACE/HOLD the Lube Oil Reservoir Level Test C/S in the HIGH LEVEL position on 1PM04J.
Verify the LEVEL LOW light above the C/S is NOT LIT.
Verify annunciator 1-16-D3, FW PUMP TURB BRNG OIL LEVEL HIGH LOW, is NOT LIT.
Verify the LEVEL HIGH light above the C/S is LIT.
Verify annunciator 1-16-D3, FW PUMP TURB BRNG OIL LEVEL HIGH LOW, is LIT.
Release the test switch.
Verify the LEVEL HIGH light above the C/S is NOT LIT.
Verify annunciator 1-16-D3, FW PUMP TURB BRNG OIL LEVEL HIGH LOW, is NOT LIT.
Record YES if the high level alarm operated correctly.
- Notify SRO that 1BwOS FW-M2 is complete.
- Acknowledge report of 1BwOS FW-M2 completion.
- Notify SM that 1BwOS FW-M2 is complete.
EVALUATOR NOTE: After 1BwOS FW-M2 is complete and with lead examiners concurrence, insert next event.
20-1 NRC 2 Page 9 of 18 Scenario No:
20-1 NRC 2 Event No.
2 Event
Description:
1A CRDM Exhaust Fan Trip Time Position Applicants Actions or Behavior CUE Annunciator 0-33-A5, CRDM EXH FAN TRIP, lit.
Annunciator 0-33-B5, CRDM EXH FLOW LOW, lit.
BOP Determine the 1A CRDM Exhaust Fan has tripped and notify the crew.
Refer to associated BwARs.
Refer to BwOP VP-9 & 10.
o Dispatch operator to MCC 133X6 Cub A3 to investigate fan trip.
SRO Notify Shift Manager of 1A CRDM Exhaust Fan (1VP03CA) trip.
Direct BOP to take actions per BwOP VP-9 and BwOP VP-10.
EXAMINERS NOTE: Per BwOP VP-9/10 Limitations and Actions step E.2, it is preferable, but not required to run fan 1VP03CA with 1VP03CC and 1VP03CB with 1VP03CD. In this event, the examinee may start only 1VP03CB or 1VP03CD.
BOP Trend PDMA01 on the Plant Process Computer.
Start 1VP03CB and 1VP03CD (1B & 1D CRDM Exhaust Fans).
Secure 1VP03CC (1C CRDM Exhaust Fan).
o Place 1VP03CA C/S to PULL OUT.
Inform SRO when CRDM exhaust fan swap is complete.
ATC Monitor remainder of MCBs.
SRO Inform SM of successful CRDM exhaust fan swap.
o Inform the SM to contact Reactor Engineering to determine if a flux map per BwOP IC-9 will be necessary, 1 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the fan swap.
EXAMINERS NOTE: After the actions for the 1A CRDM Exhaust Fan Trip are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 2 Page 10 of 18 Scenario No:
20-1 NRC 2 Event No.
3 & 4 Event
Description:
Dropped rod H-8 / Power reduction for dropped rod recovery Time Position Applicants Actions or Behavior CUE Annunciator 1-10-E6, ROD AT BOTTOM, lit.
Annunciator 1-10-A7, ROD DEV POWER RNG TILT, lit.
DRPI position for rod H-8 = 0 steps.
Tave dropping.
SRO Enter 1BwOA ROD-3, DROPPED OR MISALIGNED ROD.
Notify SM to evaluate for Emergency Plan.
Direct operator actions of 1BwOA ROD-3 to establish the following conditions:
ATC Identify rod H-8 dropped and notify SRO.
Place rod control in manual.
Stop unnecessary turbine load changes.
Stop unnecessary boration or dilution.
ATC Check DRPI not failed.
ROD CONT 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 level > 5% and < 100%.
Check for dropped rod(s).
Check DRPI rod bottom lights - ONLY ONE LIT.
Stabilize RCS temperature (adjust turbine load to maintain Tave within 3°F of Tref - 1BwOA PWR-1).
EXAMINERS NOTE: The crew may use 1BwOA PWR-1 to lower turbine load.
SRO Notify SM to make notifications, perform risk evaluation and write IR.
Enter Tech Spec 3.4.1 Condition A if PZR pressure <2209 psig.
ATC/
BOP Check flux rate trip alarm (1-10-C3) - NOT LIT.
Record data and report to Reactor Engineering.
Check core power distribution.
SRO Enter Tech Spec 3.1.4 Condition B.
Request U-2 NSO to perform 1BwOSR 3.1.1.1-2, SHUTDOWN MARGIN SURVEILLANCE DURING OPERATION.
ATC Verify reactor power proper for rod recovery - reduce Rx power < 70%.
SRO Perform pre-job brief using the Emergent Ramp Reactivity Summary Sheet (OP-BR-108-101-1002) (under the NSO desk glass) for load ramp.
ATC Initiate boration per BwOP CV-6.
BwOP CV-6 Attachment A, borate in automatic, via hard card. Perform the following at 1PM05J:
Determine required boric acid volume.
o Refer to operator aid for required boric acid addition.
Determine desired boric acid flow rate.
20-1 NRC 2 Page 11 of 18 Scenario No:
20-1 NRC 2 Event No.
3 & 4 Event
Description:
Dropped rod H-8 / Power reduction for dropped rod recovery Time Position Applicants Actions or Behavior o Turn on PZR backup heaters (as desired).
- Set BA totalizer to desired value.
- Set BA controller setpoint to desired BA flowrate.
- 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 If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
- When desired boration achieved, place RMCS M/U CONT switch to STOP.
- Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped.
Record boration in Unit log.
o Perform BwOP CV-7 to return RMCS to automatic.
- OR -
BwOP CV-6 Attachment A, batch boration, via hard card. Perform the following at 1PM05J:
o Turn on PZR backup heaters (as required).
o If desired, reset the BA blender predetermined setpoint.
Open 1CV110B.
Open 1CV110A.
Start the BA Transfer pump.
o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
When desired amount of BA has been added, stop the BA Transfer Pump.
Close 1CV110A.
Close 1CV110B.
o Adjust 1LK-112, VCT level controller, setpoint to desired value.
Place 1CV110A/B to AUTO.
Record boration in Unit log.
o Perform BwOP CV-7 to return RMCS to automatic.
BOP Lower turbine load at 1PM02J or OWS drop 210 by performing the following:
- Select SETPOINT.
- Enter desired MWs into REF DEMAND window.
- Select LEFT ENTER.
- Verify correct value in REFERENCE DEMAND window.
- Enter desired MW/min into the RATE window.
- Select RIGHT ENTER.
- Verify correct value in RATE window.
- Select EXIT.
- Inform crew of pending ramp with an UPDATE.
- Select GO/HOLD.
- Verify GO/HOLD button illuminates orange.
- Verify HOLD illuminated RED.
- Select GO.
- Verify GO illuminates RED.
20-1 NRC 2 Page 12 of 18 Scenario No:
20-1 NRC 2 Event No.
3 & 4 Event
Description:
Dropped rod H-8 / Power reduction for dropped rod recovery Time Position Applicants Actions or Behavior
- Verify main turbine load begins to lower.
ATC/
BOP Dispatch EO to check affected rod(s) for blown fuses (replace blown fuses, fuses blow on insertion).
Record affected rod position.
Record Master Cycler status.
Prepare affected rod bank for rod recovery.
ATC Perform periodic control rod steps/boron concentration adjustment to maintain Tave and Delta I within limits.
Monitor NIs, Tave, I, PZR pressure/level at 1PM05J or PPC.
Monitor MWe and DEHC system response on Ovation.
During boration, monitor the following at 1PM05J, PPC and/or Ovation:
VCT level.
RCS Tave.
o Refer to 1BwGP 100-4 for additional guidance as necessary.
SRO Notify Engineering and/or IMD to investigate cause of rod malfunction.
EXAMINERS NOTE: After sufficient reactivity control is evaluated and with Lead Examiners concurrence, insert next event.
20-1 NRC 2 Page 13 of 18 Scenario No:
20-1 NRC 2 Event No.
5 Event
Description:
Master Pressurizer Level Controller (1LK-0459) output fails LOW Time Position Applicants Actions or Behavior CUE Annunciator 1-9-D3, CHG LINE FLOW HIGH LOW, lit.
1LK-0459 controller loss of power.
Charging flow, 1FI-121A, lowering.
ATC Perform the following at 1PM05J:
Determine charging flow lowering.
Identify 1FK-0121 controller output is low.
Identify 1LK-0459 controller loss of power.
Report failure(s) to SRO.
ATC Reference BwAR 1-9-D3 and perform the following at 1PM05J:
Determine that charging flow is low.
Place 1FK-0121 controller in manual.
Raise demand on 1FK-0121.
Monitor charging flow and pressurizer level and restore PZR level to normal band.
BOP Monitor remainder of MCBs.
o Refer to BwARs as time permits.
SRO Notify SM of 1LK-0459 failure/manual control of charging flow.
o May establish a critical parameter for PZR level.
Notify SM to evaluate for Emergency Plan conditions.
Notify SM to perform risk assessment, initiate IR and contact maintenance to investigate/correct the controller failure.
EXAMINERS NOTE: After the actions for Master Pressurizer Level Controller failure are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 2 Page 14 of 18 Scenario No:
20-1 NRC 2 Event No.
6 Event
Description:
0A MCR Supply Fan Trip Time Position Applicants Actions or Behavior CUE Annunciator 0-33-A8, MCR SUP FAN 0A TRIP P HIGH LOW, lit.
Annunciator 0-33-A9, MCR RTRN FAN 0A TRIP P HIGH LOW, lit.
BOP Recognize 0A VC Supply Fan and Return Fan tripped.
Refer to associated BwARs.
Send EO to locally investigate.
Start standby VC train per BwAR and SRO direction.
SRO Direct BOP to address annunciators.
o Check SER for cause.
Enter Tech Spec 3.7.10 Condition A.
Enter Tech Spec 3.7.11 Condition A.
Direct BOP to start standby train of VC (and associated VC Chiller) per BwOP VC-10 and BwOP VC-1 (secure the 0A VC Chiller per BwOP VC-11).
o Notify SM of Tech Spec entry and request for maintenance assistance.
EXAMINERS NOTE: BwOP VC-1 allows for locally starting the standby VC train. If directed as such, the EO will report back that the local/remote transfer switch is stuck in remote so the crew MUST start the standby train from the MCR.
EXAMINERS NOTE: If/when the BOP addresses completing a shutdown of the tripped VC train, see steps on the next page.
BOP Refer to BwOP VC-1 STARTUP OF CONTROL ROOM HVAC SYSTEM PRESS both Train A and B MCR Isol Reset switches at 1PM06J.
Check status of 0RT-PR033/34.
Ensure Makeup Filter Fan Isolation and Bypass Dampers Control Switch in AUTO position on 0PM02J.
START 0VC01CB, MCR Supply Fan 0B.
START 0VC02CB, MCR Return Fan 0B.
Examiner Note: Once 0VC01CB and 0VC02CB are running the lead examiner may continue with the next event.
BOP Refer to BwOP VC-1 STARTUP OF CONTROL ROOM HVAC SYSTEM Verify 0VC282Y and 0VC16Y, MCR Outside Air Dampers, are OPEN.
Verify 0VC172Y, MCR Supply Air Damper, is OPEN.
Verify 0VC01Y, MCR Return Air Fan Inlet Damper, is OPEN.
Verify MCR differential pressure is > 0.125 inches water.
Refer to BwOP VC-11 to shut down the 0A VC Chiller.
Places Control Room Chiller 0A Control switch to AFTER TRIP.
Refer to BwOP VC-10 to start the OB Chiller.
After directing EO to perform local checks, STARTS 0WO01PB, MCR Chilled Water Pump at 0PM02J.
IF the BOP starts the chiller from the MCR, the BOP will place the OB VC Chiller Control Switch to AFTER CLOSE at 0PM02J and direct the EO to perform the rest of the local verifications in the procedure.
IF the BOP directs the EO to locally start the OB VC Chiller, then the EO will take local control of the Chiller, the BOP will cycle the OB VC Chiller switch to AFTER TRIP, then to AFTER CLOSE. The EO will then LOCALLY initiate the Chiller start sequence and transfer control back to
20-1 NRC 2 Page 15 of 18 Scenario No:
20-1 NRC 2 Event No.
6 Event
Description:
0A MCR Supply Fan Trip Time Position Applicants Actions or Behavior the MCR.
The 0B Chiller will start approximately a minute after the start signal is initiated.
BOP o Refer to BwOP VC-2, SHUTDOWN OF CONTROL ROOM HVAC SYSTEM for Train A (tripped) VC. (NOTE: this procedure allows two different combinations of steps to perform this: F.1 through F.10, then F.13 and F.14 to remotely shutdown the train. Otherwise, steps F.1 through F.4, then F.11 through F.14).
(F.1) Direct EO to shutdown Electrical SG 0A per BwOP VC-9.
(F.2) Direct EO to place C/S to OFF at 0VC13J for CR Heating Coil 0A.
(F.3) Depress Train A and B MCR Isol Reset switches on 1PM06J.
(F.4) Check status of 0RT-PR031/32 (Train A) and 0RT-PR033/34 (Train B).
(F.5) Place C/S for 0VC03CA in AFTER STOP at 0PM02J (NOT running).
(F.6) Verify intake dampers 0VC025Y/09Y, 0VC312Y/313Y and 0VC24Y/08Y indicate CLOSED.
(F.7) STOP MCR Return Fan 0A (tripped) at 0PM02J by placing the C/S in AFTER STOP.
(F.8) STOP MCR Supply Fan 0A (tripped) at 0PM02J by placing the C/S in AFTER STOP.
(F.9) Verify 0VC017Y, MCR Return Fan Inlet Damper, indicates CLOSED.
(F.10) Verify MCR Outside Air Dampers, 0VC32Y and 0VC281Y, and MCR Supply Air Damper, 0VC033Y, indicate CLOSED.
(F.11) Direct EO to shutdown M/U Filter Fan, 0VC03CA, locally.
(F.12) Direct EO to shutdown MCR HVAC Supply and Return fans locally.
(F.13) Coordinate with EO to shutdown VC Chilled Water per BwOP VC-
- 11.
(F.14) N/A (applies if BOTH VC trains are to remain shutdown).
EXAMINERS NOTE: After the actions for the 0A MCR Supply Fan Trip are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 2 Page 16 of 18 Scenario No:
20-1 NRC 2 Event No.
7, 8 & 9 Event
Description:
Dropped rod M-4 with Inadvertent FWI on reactor trip / Main Turbine Auto Trip Failure / Four stuck rods requiring emergency boration Time Position Applicants Actions or Behavior CUE Annunciator 1-10-C4, PWR RNG CHANNEL DEV, lit.
DRPI Rod at Bottom lights for rod H-8 and M-4 LIT.
ATC Identify/report multiple alarms with indications of 2 dropped rods.
CREW Identify conditions requiring reactor trip.
SRO/
ATC Direct/Initiate a manual reactor trip (and transition to 1BwEP-0).
SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
Enter 1BwEP-0 and direct operator actions of 1BwEP-0.
ATC Perform immediate operator actions of 1BwEP-0 at 1PM01J:
Verify reactor trip:
Rod bottom lights - LIT (4 rods NOT fully inserted).
Reactor trip & Bypass breakers - OPEN.
Neutron flux - DROPPING.
[CT-13]
Perform immediate operator actions of 1BwEP-0 at 1PM02J/Ovation graphics:
Verify Turbine Trip - (NO).
Manually trip the main turbine before a severe challenge (ORANGE path) develops to either subcriticality or integrity critical safety function or before transition to 1BwCA-2.1, whichever happens first. (Westinghouse -
CT-13) (K/A Number - EPE007EA1.07, Importance - 4.3/4.3)
Manually trip the main turbine and verify:
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/BOP Perform immediate operator actions of 1BwEP-0 at 1PM04J, 1PM05J &
1PM06J:
Check if SI actuated at 1PM05J and 1PM06J:
Any SI first out Annunciator - NOT 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.
SRO Determine SI not required.
Notify SM of plant status (auto turbine trip failure) and procedure entry.
Request evaluation of Emergency Plan conditions.
Transition to 1BwEP ES-0.1, REACTOR TRIP RESPONSE.
Request STA evaluation of status trees.
20-1 NRC 2 Page 17 of 18 Scenario No:
20-1 NRC 2 Event No.
7, 8 & 9 Event
Description:
Dropped rod M-4 with Inadvertent FWI on reactor trip / Main Turbine Auto Trip Failure / Four stuck rods requiring emergency boration Time Position Applicants Actions or Behavior ATC Check RCS temperature.
Check RCPs - RUNNING.
Verify RCS average temperature stable at or trending to 557oF.
ATC Verify ALL control rods fully inserted.
Rod at bottom lights - NOT ALL LIT.
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).
ATC /BOP Initiate emergency boration per 1BwOA PRI-2, EMERGENCY BORATION:
Check CV pump status:
1A CV pump running.
Emergency borate RCS.
Establish boration flow from BAT.
- Open 1CV8104.
- OR -
- Open 1CV110A & 1CV110B.
Start boric acid transfer pump.
Check emergency boration flow >30 gpm (1FT-0110 or 1FI-183A).
Verify CV pump discharge flow path aligned with proper flow.
Verify PZR backup heaters energized.
Continue boration until required gallons of boron added.
EXAMINERS NOTE: (1) If an SI occurs, 1BwEP ES-0.1 will NOT be entered.
(2) After emergency boration is initiated or an SI occurs and with Lead Examiners concurrence, insert next event.
(3) The following steps from 1BwEP ES-0.1 are included in italics since the length of time for the crew diagnosing the feedline break is uncertain.
ATC /BOP o Check PZR level control:
Level > 17% and trending to 25%. (Letdown may isolate due to low Tave)
Charging and letdown - IN Service. (1BwOA ESP-2 will be required if letdown is isolated)
ATC /BOP o Check PZR pressure control:
Pressure > 1829 psig and trending to 2235 psig.
ATC /BOP o Check FW isolation:
Isolation monitor lights - LIT.
Trip running FW pumps.
o Check total feed flow to SGs - GREATER THAN 500 GPM:
o Start AF pump(s) - (1A & 1B AF pumps will NOT start).
Levels maintained between 10% and 50%.
20-1 NRC 2 Page 18 of 18 Scenario No:
20-1 NRC 2 Event No.
10 Event
Description:
1B SG feedline break/loss of heat sink Time Position Applicants Actions or Behavior CUE 1A and 1B AF pumps NOT running.
Cue from STA status tree scan.
CREW Identify entry conditions for 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
SRO Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Request STA evaluation of status trees.
Enter 1BwFR-H.1 and direct operator actions of 1BwFR-H.1.
CREW Determine and announce containment is adverse when containment pressure rises above 5 psig.
ATC Check if secondary heat sink is required:
RCS pressure > intact SG pressure.
RCS temperature > 350°F.
ATC Check if bleed and feed is required:
WR SG level in any three SGs < 27%(43% adverse) - YES.
STOP all RCPs.
GO TO step 15 (bleed and feed).
EXAMINERS NOTE: If an auto SI occurred, ONLY opening BOTH PZR PORVs is the critical action for CT-44.
[CT-44]
Establish RCS feed path:
Establish RCS bleed and feed before either PZR PORV opens automatically as a result of a loss of heat sink. (Westinghouse - CT-44)
(K/A Number - EPEE05EA1.1, Importance - 4.1/4.0)
Actuate SI.
ATC/BOP Verify RCS feed path:
BOTH CV pumps - RUNNING.
Group 2 cold leg injection monitor lights required for operating ECCS pumps - LIT.
[CT-44]
Establish RCS bleed path:
PORV isolation valves - 1RY8000A & 1RY8000B energized & open.
Open BOTH PZR PORVs (1RY455A & 1RY456).
ATC Verify adequate RCS bleed path:
PZR PORVs - BOTH OPEN.
PORV isolation valves - BOTH OPEN.
EXAMINERS NOTE: At this point in the scenario, all Critical Tasks are complete and the scenario stop criteria has been reached, with Lead Examiners concurrence, STOP the scenario.
20-1 NRC 3 Page 1 of 23 Simulation Facility Braidwood Scenario No.:
NRC 3 Operating Test No.: 20-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-22 Turnover Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following turnover, perform 1BwOS TRM 3.3.g.3 (section 2.2) as a PMT for repairs conducted by the FIN team to fix an indication issue on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve). The SM has determined that main turbine load does not have to be reduced.
EOs are briefed and standing by at 1HD06J and at 1MS5001B to conduct a local observation.
Event No.
Malf. No.
Event Type*
Event Description Preload IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start 1
None N-BOP N-SRO Perform 1BwOS TRM 3.3.g.3 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve))
2 None R-ATC N-BOP R-SRO Load Dispatcher orders a 100 MWe emergency load drop due to a grid disturbance 3
IOR ZDI1CV8324A CLS C-ATC C-BOP C-SRO 1CV8324A, Charging to 1A Regen HX Isol Valve, fails closed (loss of normal charging and letdown) 4 IMF RX06A 0 (30 min ramp)
I-BOP I, T-SRO 1A SG NR level channel, 1LT-517, fails low 5
IMF ED04A C-ATC C-BOP C, T-SRO Unit 1 Loss of Offsite Power 6
IMF RX15dec LOWER I-ATC I, T-SRO Master Pressurizer Pressure controller, 1PK-0455A, setpoint fails low 7
IMF EG08A IMF ED07B M-ALL Loss of All AC Power - 1A DG failure / Bus 142 fault 8
IMF TH04D 225 C-ATC C-SRO Small RCS leak
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
20-1 NRC 3 Page 2 of 23 SCENARIO OVERVIEW Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently surveillance testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E
& 3.3.2 Conditions A and D have been entered. Following turnover, perform 1BwOS TRM 3.3.g.3 (section 2.2) as a PMT for repairs conducted by the FIN team to fix an indication issue on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve). The SM has determined that main turbine load does not have to be reduced. EOs are briefed and standing by at 1HD06J and at 1MS5001B to conduct a local observation.
After completing shift turnover, the crew will perform 1BwOS TRM 3.3.g.3 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve)). The BOP will perform a left side RSV L2 (1MS5001B) PMT per 1BwOS TRM 3.3.g.3.
After the crew has completed 1BwOS TRM 3.3.g.3, the Load Dispatcher will call and order a 100 MWe emergency load drop. The crew will take prompt action per 1BwGP 100-4T6/1BwOA PWR-1 to lower main generator load by 100 MWe at 6.7 MWe/minute. The ATC will borate the RCS. The crew has 15 minutes to begin the ramp and 15 minutes to complete the ramp.
After sufficient reactivity controls are observed, 1CV8324A, Charging to 1A Regen HX Isol Valve, will fail closed. The ATC will notify the SRO of a loss of normal charging and will isolate letdown per 1BwPR 1-9-LD since 1CV8389A closed on interlock when 1CV8324A closed. The crew will use either BwOP CV-22 or 1BwOA PRI-15 to restore normal charging. Letdown will be restored per 1BwOA ESP-2 with the 1B Regen HX on-line.
After normal charging and letdown have been restored, 1A SG NR level channel, 1LT-517, will fail low. Ovation will detect the second 1A SG NR level channel failure causing an OVATION ALTERNATE ACTION that will swap the 1A FRV and bypass valve controllers to manual. The BOP will respond per 1BwPR 1-15-FRV and will manually adjust the 1A FRV controller to restore 1A SG NR level to normal. The SRO will enter 1BwOA INST-2. The SRO will enter Tech Spec 3.0.3, 3.3.1 Conditions A and E and 3.3.2 Conditions A and D. NOTE: If the crew takes no action for this failure, an automatic reactor trip will occur.
After the plant is stable from the 2nd 1A SG NR level channel failure, a Unit 1 Loss of Offsite Power (LOOP) will occur. The crew will respond utilizing 1BwOA ELEC-4, request Unit 2 to perform 1/2BwOSR 3.8.1.1 and restore ESF equipment to standby. The SRO will enter Tech Spec 3.8.1 Condition A on Unit 1.
After the LOOP Tech Specs are determined, the Master Pressurizer Pressure controller (1PK-0455A) setpoint will fail low. Both PZR spray valves, 1RY455B/C, will open and PZR pressure will drop. The ATC will take manual control of 1PK-0455A or both PZR spray valve controllers per 1BwPR 1-12-RY and lower demand to close the PZR spray valves and energize the PZR heaters. The SRO will enter Tech Spec 3.4.1 Condition A when PZR pressure drops below 2209 psig. NOTE: If the crew takes no action for this failure, a reactor trip and SI will occur.
After the SRO has evaluated Tech Specs for the Master PZR Pressure controller failure and PZR pressure is stable, a Loss of All AC Power will occur. The 1A DG will seize and bus 142 will fault causing a Loss of All AC Power. The SRO will enter 1BwCA-0.0 and direct crew actions to restore power to Bus 141. The SRO will transition to 1BwCA-0.2 due to a small RCS leak and restore vital equipment including at least one CV pump.
Scenario completion criteria is starting 1A CV pump in 1BwCA-0.2.
20-1 NRC 3 Page 3 of 23 Critical Tasks:
- 1. Energize ESF bus 141 from Unit 2 within 10 minutes of the Loss of All AC Power. (Westinghouse -
CT-24) (K/A number - EPE055EA1.07, Importance - 4.3/4.5)
- 2. Isolate RCP seal injection before a CV pump is started. (Westinghouse - CT-27)
(K/A number - 003A4.01, Importance - 3.3/3.2)
Potential Critical Tasks:
- 1. Manually control 1A SG NR level to prevent a reactor trip. (K/A number - 059A4.08, Importance -
3.0/2.9)
- 2. Manually control PZR pressure to prevent a reactor trip. (K/A number - 010A4.01, Importance -
3.7/3.5)
20-1 NRC 3 Page 4 of 23 SIMULATOR SETUP GUIDE Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
Reset to IC-22, 100% power, steady state, equilibrium Xenon, MOL OR equivalent IC.
Open SmartScenario file 20-1 NRC 3.ssf from the thumb drive and place the ssf in run.
Complete items on Simulator Ready for Training Checklist.
Release the SETUP command box.
Verify page 1 PRELOAD items are inserted:
IMF RX06C 0 Fail 1LT-519, 1A SG NR level channel, low IRF RX051A BYPASS Bypass 1LT-519 SG HI-2 level (P-14) turbine trip IRF RX051B BYPASS Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start Ensure the simulator is in RUN (allow simulator to run during board walk down and turnover).
Perform 1BwOA INST-2, Attachment E, actions for removing 1LT-519 from service in Ovation.
Verify 1CV8324A is OPEN.
Verify 0A & 0C VA plenums in-service, 0B VA plenum in standby.
Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
Verify SER printer is clear of data.
If desired, write an IC after all the set-up actions are completed (snap to 0). This IC may be used for running the scenario on additional simulator groups.
Mark up a copy of 1BwOS TRM 3.3.g.3 with section 1, precautions/limitations/actions complete, steps not to be performed marked N/A.
Provide examinees with turnover sheets and a marked-up copy of 1BwOS TRM 3.3.g.3.
Provide turnover of unit status to oncoming crew.
20-1 NRC 3 Page 5 of 23 INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS TRM 3.3.g.3 section 2.2 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve))
As an EO, report EH system flow is 6 gpm.
As an EO, report 1MS5001B moves as expected locally. When 1MS5001B re-opens, report all valves are approximately at their original position.
As SM, acknowledge the completion of 1BwOS TRM 3.3.g.3 PMT.
Event 2: Load Dispatcher orders a 100 MWe emergency load drop Call Unit 1 on the TSO phone as Brett Warren and direct Unit 1 to complete an emergency load reduction of 100 MWe within 30 minutes due to an grid overload condition. Inform Unit 1 that Unit 2 has been contacted and Unit 2 is also initiating a 100 MWe load drop in response to the grid emergency.
As SM, acknowledge the initiation and completion of load reduction.
As TSO/Constellation, acknowledge completion of load ramp.
Event 3: 1CV8324A, Charging to 1A Regen HX Isol Valve, fails closed (loss of normal charging and letdown)
Release SSF EVENT 3 and verify the following actuates:
IOR ZDI1CV8324A CLS closes 1CV8324A.
If dispatched as an EO to check the fuses for the 1CV8324A, report that the voltage readings indicate that the fuses are good (6 minute delay).
If dispatched as an EO to monitor RCP seal filter DP, open jade drawing CV6. Wait 5 minutes and report the following.
CV6 -> RCP SEAL INJ FILT DP = CVPFCV121 - CVPISL1.
If contacted as Chemistry, report that the 1B CV Regen HX was on-line one week ago and the boron concentration is the same as the current RCS boron concentration.
If contacted as Radiation Protection, report that RP has NO concerns about the swap of the Regen HXs.
As SM, acknowledge the 1CV8324A failure and that the Regen HXs will be swapped to 1B Regen HX on-line, request for risk evaluation, IR initiation and notification request.
Event 4: 1A SG NR level channel, 1LT-517, fails low Release SSF EVENT 4 and verify the following actuates:
IMF RX06A 0 30:00 fails 1A SG NR level,1LT-517, low over 30 minutes.
As SM, acknowledge the failure, request for risk evaluation, IR initiation and notification request. If asked for personnel to bypass bistables, inform the SRO that 2 NSOs will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The SRO will enter Tech Spec 3.0.3 and make separate entries for Tech Spec 3.3.1 Conditions A and E and 3.3.2 Conditions A and D.
20-1 NRC 3 Page 6 of 23 Event 5: Unit 1 Loss of Offsite Power Release SSF EVENT 5 and verify the following actuates:
IMF ED04A causes a loss of offsite power.
If dispatched to the DGs, report a good start on 1A DG and 1B DG. Release ssf command box DG Panel Reset and verify the following are inserted:
IRF EG06 for 1A D/G.
IRF EG12 for 1B D/G.
If dispatched as EO or FS to investigate SAT 142-1, report back after 2 minutes that the SAT is bulging but there is no fire present and no oil is leaking.
If asked as TSO for grid restrictions, report that no grid restrictions currently exist. The cause of the LOOP is being investigated.
As U-2 Admin NSO, acknowledge the request to perform 1/2BwOSR 3.8.1.1.
If asked as U-2 NSO, report Unit 2 busses are energized from their respective SATs & their cross-tie breakers (ACB 2414/2424) are open.
As an EO, acknowledge shutdown of the 1A AF pump per BwOP AF-6.
If requested to reset inverter alarms, release ssf command box Reset Inverters and ensure the following are inserted:
IRF ED125-128 RESET resets inverter alarms.
If contacted as Chemistry to determine if the mixed bed demins can be placed in service, inform the crew that sampling to confirm demin status will take approx. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
As an EO, acknowledge request for Cnmt chiller start preps per BwOP VP-1.
As the SM, acknowledge the LOOP, LCO entry, on-line risk assessment, request for maintenance support, IR request, EAL evaluation and notification request.
Event 6: Master Pressurizer Pressure controller, 1PK-0455A, setpoint fails low Release SSF EVENT 6 and verify the following actuates:
IMF RX15dec LOWER fails the Master Pressurizer Pressure controller, 1PK-0455A, setpoint low.
As SM, acknowledge the failure and requests for risk evaluation, IR initiation and notification request. The SRO will enter Tech Spec 3.4.1 Condition A.
Event 7 & 8: Loss of All AC Power - 1A DG failure / small RCS leak Release SSF EVENT 7 and verify the following actuates:
IMF EG07B, IMF ED08A and IMF TH04D 225 cause a bus 142 fault, 1A DG seizure and a small RCS leak.
As SM, acknowledge procedure transitions, EAL evaluation request and STA request.
Calculate the time to restore power to Bus 141:
20-1 NRC 3 Page 7 of 23 Record time Loss of All AC power occurred: ______:______:______
Record time power restored to Bus 141:
Calculate time to restore AC power:
When requested as EO for the U-1 DGs status, report that 1A DG tripped, the cause cannot be determined, 1B DG is running.
As an EO, if dispatched to investigate loss of ESF bus 142, wait 1 minute and report that breaker 1422 has a lockout relay actuated.
After the STA is requested, as STA report CSF status - Yellow on inventory when PZR level is < 17%.
As an EO, acknowledge the request to depress the 1A & 1B DG emergency stop pushbuttons, then release ssf command box DGs EMERGENCY TRIP.
IRF EG19 TRIP emergency trips the 1A DG.
IRF EG20 TRIP emergency trips the 1B DG.
As Unit 2 NSO, acknowledge the request to perform 2BwCA-0.3. Report both Unit 2 4KV ESF busses are powered from the Unit 2 SATs. Acknowledge request to monitor crosstie current as U-1 loads are started.
After being notified to perform 2BwCA-0.3, wait 3 minutes 19 seconds (time delay in command box), then insert the following:
Release ssf command box CROSSTIE UNIT 1/2 BUSSES.
IRF ED006 CLOSE closes ACB 2414.
IRF ED007 CLOSE closes ACB 2424.
As an EO, report the status of all inverters is normal (3 minute delay).
As an EO, acknowledge the request to close 1CV8384A & B, then insert the following to isolate the seal injection filters (3 minute delay):
When ordered to isolate seal injection, release ssf command box ISOLATE SEAL INJECTION.
IRF CV41 0 closes 1CV8384A.
IRF CV42 0 closes 1CV8384B.
If ordered as an EO to isolate CC surge tank makeup, release ssf command box ISOLATE CC MAKEUP, then release each valve from SmartSummary as directed (3 minute delay):
IRF CC51 0 isolates CC surge tank makeup.
IRF CC52 0 isolates CC surge tank makeup.
If ordered as an EO to drain the CC surge tank, release ssf command box CC Tank Lvl, (5 minute delay and the drain will automatically stop when level is at 56%):
IRF CC15 100 (0 after desired level reached) - drains CC surge tank (1CC2020B).
IRF CC16 100 (0 after desired level reached) - drains CC surge tank (1CC2020A).
If ordered as an EO to reset inverters, release ssf command box RESET INVERTERS and ensure the following is entered:
IRF ED125-128 RESET resets inverter alarms.
If asked to crosstie DC 112 to DC 212, as EO or FS, release ssf command box DC Crosstie and ensure the following is entered after a five minute delay:
IRF ED144 OPEN IRF ED112 CLOSE
20-1 NRC 3 Page 8 of 23 Scenario No:
20-1 NRC 3 Event No.
1 Event
Description:
Perform 1BwOS TRM 3.3.g.3 section 2.2 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve))
Time Position Applicants Actions or Behavior CUE
- From turnover, perform 1BwOS TRM 3.3.g.3 section 2.2.
- EOs are briefed and standing by at 1HD06J and at 1MS5001B to conduct a local observation.
- Perform 1BwOS TRM 3.3.g.3 section F.2.0/2.2/G.2:
- Record EH fluid pressure and flow.
- VERIFY at least 5 minutes has elapsed since the performance of the last RV/IV test.
- On OWS graphic 5501, VERIFY:
RSV L2 OPEN indicator is illuminated.
IV L2 OPEN indicator is illuminated.
RSV L2 CLOSED indicator is NOT illuminated, and IV L2 CLOSED indicator is NOT illuminated.
- SELECT VALVE TEST on graphic 5501.
- SELECT RSV/IV Left 2.
- SELECT EXECUTE.
- Communicate with EO to observe local valve movement.
- On OWS graphic 5501, VERIFY:
RSV L2 CLOSED indicator is illuminated.
IV L2 CLOSED indicator is illuminated.
RSV L2 OPEN indicator is NOT illuminated, and IV L2 OPEN indicator is NOT illuminated.
- On OWS graphic 5501, VERIFY:
RSV L2 OPEN indicator is illuminated.
IV L2 OPEN indicator is illuminated.
RSV L2 CLOSED indicator is NOT illuminated, and IV L2 CLOSED indicator is NOT illuminated.
- Verify with EO that RSV L2 & IV L2 have returned to ~ their original position.
- VERIFY/OPEN Extraction Steam to 1st Stg MSR 1A/1B:
1ES056A/B/C/D
- SELECT EXIT on the popup labeled RSV & IV LH. 2.
- Section 2.7 (N/A - main turbine load was not reduced).
- Verify Acceptance Criteria, section G.2, are met.
o Notify SM that 1BwOS TRM 3.3.g.3 PMT is complete.
- Monitor remainder of MCBs.
EXAMINERS NOTE: After the actions for 1BwOS TRM 3.3.g.3 are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 3 Page 9 of 23 Scenario No:
20-1 NRC 3 Event No.
2 Event
Description:
Load Dispatcher orders a 100 MWe emergency load drop Time Position Applicants Actions or Behavior CUE Call from TSO to perform an emergency load drop of 100 MWe.
SRO Acknowledge request from TSO to lower load 100 MWe.
o Initiate 1BwGP 100-4T6, LOAD CHANGE INSTRUCTION SHEET FOR POWER REDUCTION.
Perform pre-job brief using the Emergent Ramp Reactivity Summary Sheet (OP-BR-108-101-1002) (under the NSO desk glass) for load ramp (may be delayed until after load ramp is started).
o Enter 1BwOA PWR-1, POWER REDUCTION and direct operator actions of 1BwOA PWR-1 (may be used in conjunction with 1BwGP 100-4T6).
SRO Notify SM of plant status and required load ramp.
Notify Chemistry and RP of power reduction and to monitor affected parameters.
Brief ATC concerning ramp parameters and primary plant control.
CREW Review Prerequisites, Precautions, and Limitations and Actions of 1BwGP 100-4, POWER DESCENSION (may be performed after ramp is initiated).
ATC Initiate boration per BwOP CV-6.
BwOP CV-6 Attachment A, borate in automatic, via hard card. Perform the following at 1PM05J:
Determine required boric acid volume.
o Refer to operator aid for required boric acid addition.
Determine desired boric acid flow rate.
o Turn on PZR backup heaters (as desired).
- Set BA totalizer to desired value.
- Set BA controller setpoint to desired BA flowrate.
- 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 If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
- When desired boration achieved, place RMCS M/U CONT switch to STOP.
- Verify 1CV110B closed, 1CV110A closed and Boric Acid Transfer Pump stopped.
Record boration in Unit log.
o Perform BwOP CV-7 to return RMCS to automatic.
- OR -
BwOP CV-6 Attachment A, batch boration, via hard card. Perform the following at 1PM05J:
o Turn on PZR backup heaters (as required).
o If desired, reset the BA blender predetermined setpoint.
Open 1CV110B.
Open 1CV110A.
Start the BA Transfer pump.
o If desired, adjust 1LK-112, VCT level controller, setpoint to control VCT level.
When desired amount of BA has been added, stop the BA Transfer Pump.
Close 1CV110A.
20-1 NRC 3 Page 10 of 23 Scenario No:
20-1 NRC 3 Event No.
2 Event
Description:
Load Dispatcher orders a 100 MWe emergency load drop Time Position Applicants Actions or Behavior Close 1CV110B.
o Adjust 1LK-112, VCT level controller, setpoint to desired value.
Place 1CV110A/B to AUTO.
Record boration in Unit log.
o Perform BwOP CV-7 to return RMCS to automatic.
BOP Lower turbine load at Ovation Graphic 5501 by performing the following:
Select SETPOINT.
Enter desired MWs into REF DEMAND window.
Select LEFT ENTER.
Verify correct value in REFERENCE DEMAND window.
Enter desired MW/min into the RATE window.
Select RIGHT ENTER.
Verify correct value in RATE window.
Select EXIT.
Notify crew of pending ramp with an UPDATE.
Select GO/HOLD.
Verify GO/HOLD button illuminates orange.
Verify HOLD indicator illuminates RED.
Select GO.
Verify GO indicator illuminates RED while the main turbine ramps.
Verify main turbine load begins to drop.
ATC/BOP Perform periodic control rod steps/boron concentration adjustment to maintain Tave and Delta I within limits.
Monitor NIs, Tave, I, PZR pressure/level at 1PM05J or PPC.
Monitor MWe and DEHC system response on Ovation.
During boration, monitor the following at 1PM05J, PPC and/or Ovation:
VCT level.
RCS Tave.
o Refer to 1BwGP 100-4 for additional guidance as necessary.
SRO Notify Constellation and TSO of load ramp completion.
EXAMINERS NOTE: After the emergency load ramp reactivity change is adequately evaluated and with Lead Examiners concurrence, insert next event.
20-1 NRC 3 Page 11 of 23 Scenario No:
20-1 NRC 3 Event No.
3 Event
Description:
1CV8324A, CHARGING TO 1A REGEN HX ISOL VALVE, fails closed (loss of normal charging and letdown)
Time Position Applicants Actions or Behavior CUE Annunciator 1-7-A2, RCP SEAL WTR INJ FLTR P HIGH, lit.
1CV8324A, CHG TO 1A REGEN HX ISOL VALVE, closes with its control switch in the open position.
Charging flow, 1FI-121A, lowers.
Letdown line flow, 1FI-132, drops to zero.
RCP seal injection flows, 1FI-142A-145A, rise.
ATC/BOP Perform actions per 1BwPR 1-9-LD, LETDOWN MALFUNCTION PROMPT RESPONSE, at 1PM05J:
Verify 1PK-0131 proper operation.
Isolate letdown by:
Close 1CV8149A/B/C, Letdown orifice valves.
Close 1CV459 and 1CV460, Letdown isolation valves.
Adjust charging flow to minimum required for seal injection flow:
Throttle 1CV121.
Close 1CV182.
o Isolate charging (if crew utilizes BwAR 1-1PR06J):
o Close 1CV8106.
o Close 1CV8105.
BOP Refer to BwAR 1-7-A2, RCP SEAL WTR INJ FLTR DP HIGH:
Monitor RC Pumps seal injection flow and RCS charging flow.
If flow is excessive, REFER to 1BwOA RCP-1, RCP SEAL FAILURE.
If flow is low, REFER to 1BwOA RCP-2, LOSS OF SEAL COOLING.
EXAMINERS NOTE: Annunciator 1-7-A2 should clear when 1CV121 is throttled per 1BwPR 1-9-LD.
EXAMINERS NOTE: Actions to align the standby REGEN HX can be performed in either 1BwOA PRI-15 or BwOP CV-22.
SRO Identify entry conditions for 1BwOA PRI-15, LOSS OF NORMAL CHARGING.
Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Enter 1BwOA PRI-15 and direct operator actions of 1BwOA PRI-15 to establish the following conditions:
Seal injection flow to all RCPs - IN SERVICE.
RCP THERM BARR CC WTR FLOW LOW alarms (1-7-_4) - NOT LIT.
Check status of CENT CHG pumps:
CENT CHG pumps - AT LEAST ONE RUNNING.
Check CENT CHG pump parameters - ANY FLUCTUATING:
- 1. Motor amps.
- 2. Charging header pressure.
- 3. Charging flow.
With CV pump discharge pressure > RCS pressure, GO TO step 8 (next page).
20-1 NRC 3 Page 12 of 23 Scenario No:
20-1 NRC 3 Event No.
3 Event
Description:
1CV8324A, CHARGING TO 1A REGEN HX ISOL VALVE, fails closed (loss of normal charging and letdown)
Time Position Applicants Actions or Behavior Check CV system alignment (step 8):
Either charging to RC loop isolation valve - OPEN:
o 1CV8146.
o 1CV8147.
In-service charging to REGEN HX isolation valve - OPEN:
o 1CV8324A - Closed with switch in open position. (may place 1CV8324A C/S to close)
Open 1CV8324B.
Charging line Cnmt isolation valves - OPEN.
1CV8105.
1CV8106.
Check charging flow - ESTABLISHED.
Check normal letdown - ISOLATED.
Restore letdown per 1BwOA ESP-2, REESTABLISHING CV LETDWON DURING ABNORMAL CONDITIONS (see below).
Notify SM to perform a risk evaluation, initiate IR and notify the appropriate personnel.
Refer to Tech Specs (none are applicable).
o Monitor RMCS during VCT auto makeup:
o Proper flow indicated for PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110) on recorder 1FR-0110.
ATC o Perform the following actions at 1PM05J per step F.6 of BwOP CV-22, OPERATION OF LETDOWN AND REGEN HEAT EXCHANGERS:
o Open 1CV8324B, CHARGING TO 1B REGEN HX ISOL VALVE.
o Open 1CV8389B, LETDOWN TO 1B REGEN HX ISOL VALVE.
o Close 1CV8389A, LETDOWN TO 1A REGEN HX ISOL VALVE.
o Close 1CV8324A, CHARGING TO 1A REGEN HX ISOL VALVE (failed closed).
SRO Identify entry conditions for 1BwOA ESP-2, REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS.
SRO Notify Shift Manager of plant status and procedure entry.
Direct BOP/ATC to perform 1BwOA ESP-2.
BOP/ATC Perform the following at 1PM05J (1BwOA ESP-2):
Check letdown isolated:
1CV8149A, B, & C, LETDOWN ORIFICE ISOLATION VALVES -
CLOSED.
1CV459 & 1CV460, LETDOWN LINE ISOLATION VALVES - CLOSED.
Check letdown flow path:
1CV8401A, LETDOWN HX 1A ISOLATION VALVE - OPEN.
1CV8324B, CHARGING TO REGEN HX 1B ISOLATION VALVE -
OPEN.
1CV8389B, LETDOWN TO REGEN HX 1A ISOLATION VALVE - OPEN.
1CV8152 & 1CV8160, LETDOWN LINE CNMT ISOLATION VALVES -
OPEN.
BTRS mode selector switch OFF light - LIT.
20-1 NRC 3 Page 13 of 23 Scenario No:
20-1 NRC 3 Event No.
3 Event
Description:
1CV8324A, CHARGING TO 1A REGEN HX ISOL VALVE, fails closed (loss of normal charging and letdown)
Time Position Applicants Actions or Behavior Align letdown controllers:
Place 1PK-0131, Letdown Line Pressure Controller, in MANUAL and raise demand to 40%.
Place 1TK-0130, Letdown HX Outlet Temperature Controller, in MANUAL and raise demand to 60%.
Verify charging flow established:
Check 1CV8105 and 1CV8106, Charging Line CNMT Isolation Valves -
OPEN (if closed, place 1CV182 controller = 0% demand, then open 1CV8105/8106).
Throttle 1CV182, Charging Header Backpressure Control Valve, to establish 8-13 gpm RCP seal injection flow per RCP.
Place 1FK-0121 in manual and establish 100 gpm charging flow on 1FI-121A.
Establish letdown flow:
OPEN 1CV459 & 1CV460.
OPEN 1CV8149A & B or C to establish 120 gpm letdown flow.
Lower demand on 1PK-0131 to raise letdown pressure to ~ 360 psig on 1PI-131.
Operate 1FK-0121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow per RCP.
Lower demand on 1TK-0130 to control letdown temperature between 90°F to 115°F on 1TI-130.
Place 1PK-0131 controller in AUTO.
Place 1TK-0130 controller in AUTO.
At RMS, verify 1PR06J cursor is GREEN (in-service).
EXAMINERS NOTE: After the actions for the 1CV8324A failure are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 3 Page 14 of 23 Scenario No:
20-1 NRC 3 Event No.
4 Event
Description:
1A SG NR level channel, 1LT-517, fails low Time Position Applicants Actions or Behavior CUE Annunciator 1-10-E4, OVATION SYSTEM TROUBLE, lit.
1A SG feed flow/NR level slowly rising.
Annunciator 1-10-E5, OVATION ALTERNATE ACTION, lit.
BOP Determine 1A SG feed flow and NR level rising at 1PM04J.
Identify 1LI-517, 1A SG NR level, lowering at 1PM04J.
BOP Potential CT Report failure of 1LT-517 to the SRO.
Perform actions per 1BwPR 1-15-FRV, FRV MANUAL CONTROL MALFUNCTION PROMPT RESPONSE (crew may enter 1BwOA INST-2 directly, see below):
Steam Generator level LOW (NO).
o Place 1A FRV in MANUAL (ALTERNATE ACTION places 1A FRV controller and 1A FRV bypass valve controller in MANUAL control).
Manually control 1A SG NR level to prevent a reactor trip. (K/A number -
059A4.08, Importance - 3.0/2.9)
Operate 1FK-0510 (1A FRV) in MANUAL to restore/maintain 1A SG NR level.
Verify/close 1A FRV bypass valve.
1A FRV controlling in MANUAL (YES).
Manually control 1A FRV bypass valve as necessary to maintain NORMAL SG level.
GO TO 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.
SRO Identify entry conditions for 1BwOA INST-2.
SRO Notify Shift Manager of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Enter 1BwOA INST-2 ATTACHMENT E, NARROW RANGE SG LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:
BOP Potential CT SG levels - NORMAL (NO).
Perform the following for the 1A SG:
o Place 1FK-0510, FW Reg Valve 1FW510 controller, in MANUAL (ALTERNATE ACTION automatically places 1A FRV controller and 1A FRV bypass valve controller in MANUAL control)
Manually control 1A SG NR level to prevent a reactor trip. (K/A number -
059A4.08, Importance - 3.0/2.9)
Operate 1FK-0510 (1A FRV) in MANUAL to restore/maintain 1A SG NR level.
ATC Check Rx power < 100% - monitor reactor power at 1PM05J/PPC.
If calorimetric power exceeds 100%, lower load 5 MW at 5 MW/min.
Refer to BwARs as time permits.
20-1 NRC 3 Page 15 of 23 Scenario No:
20-1 NRC 3 Event No.
4 Event
Description:
1A SG NR level channel, 1LT-517, fails low Time Position Applicants Actions or Behavior BOP Remove the failed NR SG level channel from service:
Select OWS graphic SG A Level (6041).
In Signal Selectors box, select NR LEVEL and enable the window.
o Select PLACE OUT OF SERVICE for channel 517 (CANNOT remove channel from service - 2 failed channels).
Exit window.
o Restore 1A SG level control to auto (ALTERNATE ACTION prevents restoring 1A FRV to auto).
SRO Bypass SG level channel 1LT-517 bistables (will be delayed).
o May establish a critical parameter for 1A SG NR level.
EXAMINERS NOTE: Tech Specs 3.3.1 & 3.3.2 were previously entered for the failed SG NR level channel 1LT-519 (turnover item). However, Tech Spec 3.0.3 must now be entered with 2 failed SG NR level channel failures in addition to Tech Spec 3.3.1 & 3.3.2 (separate entries).
SRO Determine AMS channel - NOT FAILED.
Enter Tech Spec 3.0.3 (2 SG NR level channels failed).
Enter Tech Spec 3.3.1 Conditions A and E (separate entry).
Enter Tech Spec 3.3.2 Conditions A and D (separate entry).
Notify SM of unit status, emergency plan notification and Tech Spec status.
Notify SM of the Tech Spec LCO 3.0.3 ramp.
Notify SM to perform risk assessment, initiate IR, evaluate reactivity screening, notify QNE and notify personnel to investigate/correct instrument failure.
EXAMINERS NOTE: After the SG NR level channel failure Tech Specs are determined and with Lead Examiners concurrence, insert next event.
20-1 NRC 3 Page 16 of 23 Scenario No:
20-1 NRC 3 Event No.
5 Event
Description:
Unit 1 Loss of Offsite Power (LOOP)
Time Position Applicants Actions or Behavior CUE Annunciator 1-20-A1, LOSS OF OFFSITE POWER, lit.
Annunciator 1-21-A7, BUS 141 FD BRKR 1412 TRIP, lit.
Annunciator 1-22-A7, BUS 142 FD BRKR 1422 TRIP, lit.
BOP Determine a Loss of Offsite Power has occurred.
Report failure to SRO.
CREW Determine bus 141 and 142 have been energized by their respective DGs.
Monitor bus 141 and 142 ESF equipment sequencing on.
Reference BwARs as time permits.
Identify entry conditions for 1BwOA ELEC-4, LOSS OF OFFSITE POWER.
SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
Enter 1BwOA ELEC-4 and direct operator actions to establish the following conditions:
BOP/ATC Verify power to 4KV ESF buses - BOTH ENERGIZED.
1SX169A 1SX169B Dispatch EOs to monitor DGs operation.
Check reactor power < 100%.
Check safe shutdown loads - ENERGIZED (bus 141/142):
480 volt ESF busses CV pumps 1A AF pump CC pumps SX pumps MCR chillers Check RCS cold leg temperature - GREATER THAN 350°F.
Check Cnmt Vent Isolation valves - CLOSED (Group 6 monitor lights).
Restore plant systems:
Check SG PORV controllers in - AUTO.
Reset RVLIS if necessary.
Reset Cnmt Vent Isolation.
Notify TSO of existing conditions.
BOP Check status of non-ESF buses:
Bus 143/144 - DEAD (NO), GO TO Attachment B.
BOP Perform Tech Spec required actions:
Check VC rad monitors 0PR31J through 0PR34J - OPERATING (NO, restart rad monitors).
Contact Unit 2 to perform 1/2BwOSR 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 />.
Restore train A ESF equipment to standby:
Check bus 141 - ENERGIZED BY DG 1A.
Check bus 241 - ENERGIZED BY SAT.
Check bus 241 reserve feed breaker (ACB 2414) - OPEN.
Sync and close ACB 1414 (to defeat sequencer).
20-1 NRC 3 Page 17 of 23 Scenario No:
20-1 NRC 3 Event No.
5 Event
Description:
Unit 1 Loss of Offsite Power (LOOP)
Time Position Applicants Actions or Behavior Place 1A AF pump in - AFTER TRIP.
Shutdown 1A AF pump per BwOP AF-6 while continuing with the procedure.
Shutdown unnecessary ESF equipment on bus 141 by placing in -
AFTER TRIP (1A CV/CC/SX pumps, may leave running).
Check 0A VC train - IN SERVICE (NO).
Place 0A MCR Chiller control switch in AFTER TRIP.
BOP Restore train B ESF equipment to standby:
Check bus 142 - ENERGIZED BY DG 1B.
Check bus 242 - ENERGIZED BY SAT.
Check bus 242 reserve feed breaker (ACB 2424) - OPEN.
Sync and close ACB 1424 (to defeat sequencer).
Shutdown unnecessary ESF equipment on bus 142 by placing in -
AFTER TRIP (1B CV/CC/SX pumps).
Check 0B VC train - IN SERVICE (YES).
Supply Fan 0B - RUNNING.
Return Fan 0B - RUNNING.
ATC/BOP Restore systems to normal status:
Check 1CV129 - IN DEMIN POSITION (NO, restore demin flow if desired).
Check at least ONE VA supply and exhaust fan - RUNNING.
Restart Cnmt Chiller per BwOP VP-1, RCFC REFRIGERATION UNIT AND CHILLED WATER SYSTEM STARTUP.
Check CNMT PEN CLG FLOW HIGH/LOW (1-2-D7) - NOT LIT.
Restore remaining ventilation systems as necessary.
SRO Refer to Tech Specs:
Enter Tech Spec 3.8.1 Condition A.
o Enter Tech Spec 3.6.5 Condition A (if Cnmt temp exceeds 120°F).
Notify SM to perform risk assessment, initiate IR and notify maintenance to investigate/correct failure.
EXAMINERS NOTE: (1) After the Tech Specs are determined for the LOOP and with Lead Examiners concurrence, insert next event.
(2) The actions in 1BwOA ELEC-4 for the crosstie of the U-2 ESF buses (241/242) to the U-1 ESF buses (141/142) will NOT be evaluated in this event since the crosstie of bus 241 to bus 141 is evaluated in the Loss of All AC Power event.
20-1 NRC 3 Page 18 of 23 Scenario No:
20-1 NRC 3 Event No.
6 Event
Description:
Master Pressurizer Pressure controller, 1PK-0455A, setpoint fails low Time Position Applicants Actions or Behavior CUE Annunciator 1-12-D2, PZR PRESS CONT DEV HIGH, lit.
BOTH PZR spray valves open.
PZR pressure lowers.
Master PZR Pressure controller, 1PK-0455A, demand rises.
ATC Potential CT Report failure of Master Pressurizer Pressure Controller to SRO.
Perform actions per 1BwPR 1-12-RY, PZR CONTROL MALFUNCTION PROMPT RESPONSE:
Manually control PZR pressure to prevent a reactor trip. (K/A number -
010A4.01, Importance - 3.7/3.5)
Place Master PZR Pressure controller (or both spray valve controllers) in MANUAL and control PZR pressure.
EXAMINERS NOTES: (1) Manual control of either the Master PZR Pressure Controller or the PZR spray valve controllers will be used to control PZR pressure for the remainder of the scenario.
(2) If the PZR spray valve controllers are used, manual PZR heater operation will also be required.
BOP Monitor remainder of MCBs.
Refer to BwARs as time permits.
SRO Enter Tech Spec 3.4.1 Condition A when PZR pressure drops below 2209 psig.
Notify SM to perform risk evaluation, initiate IR and notify maintenance to investigate/correct failure.
o May establish a critical parameter for PZR pressure.
EXAMINERS NOTE: After the actions for the Master Pressurizer Pressure Controller failure are complete and PZR pressure is stable, with Lead Examiners concurrence, insert next event.
20-1 NRC 3 Page 19 of 23 Scenario No:
20-1 NRC 3 Event No.
7 & 8 Event
Description:
Loss of All AC Power - 1A DG failure / bus 142 fault / small RCS leak Time Position Applicants Actions or Behavior CUE BOTH ESF busses 141 and 142 are DEENERGIZED.
Annunciator 1-21-C7, BUS 141 OVERLOAD OR VOLT LOW, lit.
Annunciator 1-22-C7, BUS 142 OVERLOAD OR VOLT LOW, lit.
EXAMINERS NOTE: For evaluation of critical task CT-24, record the time the Loss of All AC Power occurred: ______:______:______
CREW Identify loss of power to busses 141 and 142.
SRO Identify entry conditions for 1BwCA-0.0, LOSS OF ALL AC POWER.
SRO Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Enter 1BwCA-0.0 and direct operator actions of 1BwCA-0.0 to establish the following conditions:
ATC Perform immediate operator actions of 1BwCA-0.0 at 1PM05J:
Verify reactor trip:
Reactor trip & bypass breakers - OPEN (NO).
Manually trip reactor from 1PM05J/1PM06J.
Neutron flux - DROPPING.
BOP Perform immediate operator actions of 1BwCA-0.0 at 1PM05J/1PM06J:
- Isolate Steamlines:
Actuate main steamline isolation.
Verify all MSIVs and MSIV bypass valves - CLOSED.
- Verify AF flow:
1B AF pump - RUNNING.
Total AF flow - GREATER THAN 500 GPM.
- Verify RCS isolated:
Close letdown isolation valves:
1CV8149A-C.
1CV459/460.
PZR PORVs - CLOSED:
1RY455A.
1RY456.
Excess letdown isol valves - CLOSED:
1CV8153A/B.
RCPs - NOT RUNNING.
BOP Try to restore power to any/both Unit 1 4 KV ESF busses:
Attempt to manually start both DGs (1A DG seized, 1B DG running).
Actuate SI from 1PM05J and 1PM06J.
4KV busses - AUTOMATICALLY ENERGIZE (NO).
Manually energize bus 142 (NO, bus 142 fault present).
Dispatch EOs to depress emergency stop pushbuttons on 1A & 1B DGs.
4KV busses - AT LEAST ONE ENERGIZED (NO).
20-1 NRC 3 Page 20 of 23 Scenario No:
20-1 NRC 3 Event No.
7 & 8 Event
Description:
Loss of All AC Power - 1A DG failure / bus 142 fault / small RCS leak Time Position Applicants Actions or Behavior BOP/SRO Prepare for ESF bus crosstie:
Dispatch EOs to depress emergency stop pushbuttons on 1A & 1B DGs (previously performed).
Reset SI.
SRO Check status of Unit 2 ESF busses:
Both Unit 2 4 KV ESF busses - ENERGIZED (from SATs).
Notify Unit 2 to enter 2BwCA-0.3, RESPONSE TO OPPOSITE UNIT LOSS OF ALL AC POWER.
Both U-2 4 KV ESF busses - ENERGIZED.
BOP Crosstie bus 141 to Unit 2:
Check bus 241 - ENERGIZED (from SAT).
Check bus 141 - NOT FAULTED:
Place ACB 1413 (DG feed) in - PULL OUT.
Place ACB 1411 (Non-ESF bus tie) in - PULL OUT.
Place ACB 1412 (SAT feed) in - PULL OUT.
Place ACB 1414 (Reserve feed) in - PULL OUT.
Check bus 141 alarms - NOT LIT:
Annunciator 1-21-A7, BUS 141 FD BRKR 1412 TRIP.
Annunciator 1-21-B8, BRKR 1414 CROSS-TIE OVERCURRENT.
Annunciator 1-21-B9, DG 1A OVERLOAD.
BOP/ATC
[CT-24]
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 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.
Check ACB 2414 (reserve feed) - CLOSED.
Energize ESF bus 141 from Unit 2 within 10 minutes of the Loss of All AC Power. (Westinghouse - CT-24) (K/A number - EPE055EA1.07, Importance - 4.3/4.5)
Sync and close Bus 141 reserve feeder breaker.
Close ACB 1414.
EXAMINERS NOTE: For evaluation of critical task CT-24, record time Bus 141 power restored: ______:______:______
20-1 NRC 3 Page 21 of 23 Scenario No:
20-1 NRC 3 Event No.
7 & 8 Event
Description:
Loss of All AC Power - 1A DG failure / bus 142 fault / small RCS leak Time Position Applicants Actions or Behavior
[CT-24]
Time power restored - time power lost = _______-________=_______ (< 10 minutes).
BOP Check bus 141 energized.
Check bus 131X energized.
BOP Restore Unit 1 SX cooling:
Check valves for 1A SX pump - OPEN.
1SX001A.
1SX016A.
1SX027A.
Start 1A SX pump.
Check SX crosstie valves - OPEN.
1SX033 and 1SX034.
Monitor crosstied power source load capacity.
ATC/BOP Verify following equipment loaded on energized 4 KV ESF bus:
Check Battery Charger 111 - ENERGIZED:
Annunciator 1-21-E8, 125V DC BATT CHGR 111 TROUBLE - NOT LIT.
Dispatch EO to check instrument inverter status.
BOP/ATC
[CT-27]
Align equipment for Unit 1 restoration.
Verify 1B AF pump - RUNNING.
Check both Unit 2 ESF buses - ENERGIZED FROM SAT.
Check bus 142 - NOT FAULTED:
Place ACB 1423 (DG feed) in - PULL OUT.
Place ACB 1421 (Non-ESF bus tie) in - PULL OUT.
Place ACB 1422 (SAT feed) in - PULL OUT.
Place ACB 1424 (Reserve feed) in - PULL OUT.
Check bus 142 alarms:
Annunciator 1-22-A7, BUS 142 FD BRKR 1422 TRIP - LIT.
Annunciator 1-22-B8, BRKR 1424 CROSS-TIE OVERCURRENT -
NOT LIT.
Annunciator 1-22-B9, DG 1B OVERLOAD - NOT LIT.
Dispatch EOs to start DGs per 1BwOA ELEC-3, ATTACHMENT D.
Isolate RCP seal injection before a CV pump is started. (Westinghouse -
CT-27) (K/A number - 003A4.01, Importance - 3.3/3.2)
Dispatch EOs to close 1CV8384A & B (isolate RCP seals).
Close CC from RCP Thermal Barrier isol valve - 1CC9438.
Close RCP seal water return isol valve - 1CV8100 (closed on Phase A).
Check energized S/G PORVs in - AUTO.
Check VC fans - ONE TRAIN RUNNING (NO - manually start 0A VC Supply, Return and Makeup fans).
SRO Select proper recovery procedure.
Check RCS subcooling acceptable.
Check PZR Level greater than 14% (NO).
20-1 NRC 3 Page 22 of 23 Scenario No:
20-1 NRC 3 Event No.
7 & 8 Event
Description:
Loss of All AC Power - 1A DG failure / bus 142 fault / small RCS leak Time Position Applicants Actions or Behavior SRO GO TO 1BwCA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED.
SRO Transition to 1BwCA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED.
1BwCA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED SRO Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Enter 1BwCA-0.2 and direct operator actions of 1BwCA-0.2 to establish the following conditions:
SI signal - RESET.
RWST level - GREATER THAN 46%.
BOP Manually establish ECCS injection alignment on energized train(s):
Verify RH miniflow valve (1RH610) - OPEN.
Verify RH HX bypass flow control valve (1RH618) - IN MANUAL WITH ZERO DEMAND.
ATC Open 1SI8801A.
Open 1CV112D.
Close 1CV112B.
Close 1CV8106.
BOP Check RCP thermal barrier CC isolation status:
Check CC pumps - ALL STOPPED.
Close 1CC9438 (previously performed).
BOP/ATC Manually load the following safeguards equipment on bus 141:
Check 1CC9438 closed.
Start 1A CC pump.
Start 1A RH pump.
Start 1A SI pump.
o Start 1A & 1C RCFCs in LO speed.
o Start 1A SX pump (previously started).
Start 0A VC chilled water pump and chiller (operating VC train).
[CT-27]
Check if CV pumps should be started:
Check CV pumps - ALL STOPPED.
Isolate RCP seal injection before a CV pump is started. (Westinghouse -
CT-27) (K/A number - 003A4.01, Importance - 3.3/3.2)
Check 1CV8384A/B - CLOSED.
Start 1A CV pump.
EXAMINERS NOTE: At this point in the scenario, all Critical Tasks are complete and the scenario stop criteria has been reached, with Lead Examiners concurrence, STOP the scenario.
20-1 NRC 3 Page 23 of 23 Scenario No:
20-1 NRC 3 Event No.
7 & 8 Event
Description:
Loss of All AC Power - 1A DG failure / bus 142 fault / small RCS leak Time Position Applicants Actions or Behavior
20-1 NRC 4 Page 1 of 21 Simulation Facility Braidwood Scenario No.:
NRC 4 Operating Test No.: 20-1 NRC Examiners:
Applicant:
SRO ATC BOP Initial Conditions:
IC-46 Turnover Unit 1 is at 1x10-8 amps, steady state, Xenon free, BOL. On-line risk is Green. Following turnover, the crew will raise reactor power to 2-3% per 1BwGP 100-2 step 27 and then prepare for rolling the main turbine per 1BwGP 100-2 step 33. Another NSO is assigned to commence the step F.33.e surveillances.
Event No.
Malf. No.
Event Type*
Event Description Preload SSF Gate RP:52HRTA==FALSE IMF ED04B Loss of offsite power on reactor trip (30 seconds delay) 1 None R-ATC R-SRO Withdraw control rods to 2%-3% power 2
None N-BOP N-SRO Perform preparations for rolling the main turbine 3
IMF CV02A C-BOP C-SRO 0A PW pump trip 4
IMF TH08.01 T-SRO High RCS activity 5
IOR ZDI1VP05CA STOP DOR ZDI1VP05CA C-BOP C-SRO 1A Reactor Cavity vent fan trip 6
IRF OV06 TRUE IMF CV45 OPEN I-ATC I-SRO Spurious automatic make-up relay actuation with Boric Acid flow controller power failure 7
TH03B 30 60 C-ATC T-SRO 1B SG tube leak 8
IMF TH03B 420 M-ALL 1B SGTR 9
Preload C-ALL LOOP on main generator trip
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
20-1 NRC 4 Page 2 of 21 SCENARIO OVERVIEW Unit 1 is at 1x10-8 amps, steady state, Xenon free, BOL. On-line risk is Green. Following turnover, the crew will raise reactor power to 2-3% per 1BwGP 100-2 step 27 and then prepare for rolling the main turbine per 1BwGP 100-2 step 33. Another NSO is assigned to commence the step F.33.e surveillances.
After completing shift turnover, the crew will raise reactor power to 2%-3%. The ATC will use 1BwGP 100-2 step 27 to withdraw rods with the BOP providing peer checks and the SRO providing oversight. Reactor power will be slowly raised by withdrawing rods. Reactor power will be stabilized at 2%-3%.
Once the crew has stabilized reactor power at 2%-3%, the crew will perform turbine roll preps. The BOP will perform 1BwGP 100-2 step 33 to prepare for rolling the main turbine.
After 1BwGP 100-2 step 33 is completed, the 0A PW pump will trip. The BOP will respond and start the 0B PW pump per BwAR 0-38-A5. The 0B PW pump will be required for reactivity control during the plant startup.
After the 0A PW pump failure is addressed, high RCS activity will occur. The crew will enter 1BwOA PRI-4 to address the high RCS activity. The SRO will enter Tech Spec 3.4.16 Condition A.
After the SRO has evaluated Tech Specs for the high RCS activity, the 1A Reactor Cavity Vent Fan will trip. The BOP will respond utilizing BwAR 0-33-C5 and BwOP VP-7 to start the 1B Reactor Cavity Vent Fan.
After the 1B Reactor Cavity Vent Fan is started, a 1B SG tube leak will occur. The crew will enter 1BwOA SEC-8, STEAM GENERATOR TUBE LEAK. The crew will determine the estimated leak size and determine that a unit shutdown is required using 1BwGP 100-4, POWER DESCENSION. The SRO will enter Tech Spec 3.4.13 Condition B.
After the SGTL has been addressed, the Boric Acid flow controller, 1FK-0110, will fail and a spurious automatic make-up will start due to a failure in the Ovation logic and relaying. This will require the ATC to stop the automatic makeup by placing the makeup control system to stop.
After the spurious auto makeup action is completed, the 1B SG tube leak will worsen to a 420 GPM tube rupture. The crew should note that pressurizer level is dropping at greater than 2% per minute and perform a reactor trip and SI. The crew will enter 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
When the reactor is tripped, a loss of offsite power (LOOP) will occur 30 seconds later. The crew will transition to 1BwEP-3, SGTR. The crew will utilize the SG PORVs to conduct the RCS cooldown and RCS depressurization will occur via the PZR PORVs due to the LOOP.
Scenario completion criteria is completion of the first RCS depressurization in 1BwEP-3.
Critical Tasks:
- 1.
Isolate feedwater flow into and steam flow from the 1B SG before transition to 1BwCA 3.1 occurs.
(Westinghouse - CT-18) (K/A number - EPE038EA1.32, importance - 4.6/4.7)
- 2.
Establish/maintain RCS temperature so that transition from 1BwEP-3 does not occur because the RCS temperature is too high (1BwCA-3.1) or too low (1BwFR-P.1).
(Westinghouse - CT-19) (K/A number - EPE038EA1.36, importance - 4.3/4.5)
- 3.
Depressurize RCS to meet SI termination criteria prior to water release from the 1B SG PORV or safety valve.
(Westinghouse - CT-20) (K/A number - EPE038EA1.04, importance - 4.3/4.1)
20-1 NRC 4 Page 3 of 21 SIMULATOR SETUP GUIDE Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.
Reset to IC-46, 1x10-8 amps, steady state, Xenon free, BOL OR equivalent IC. (Password =
2022NRC4)
Open SmartScenario file 20-1 NRC 4.ssf from the thumb drive and place the ssf in run.
Complete items on Simulator Ready for Training Checklist.
Release the SETUP command box.
Verify page 1 PRELOAD items are active.
SSF Gate - RP:52HRTA==FALSE IMF ED04B (30 seconds delay)
Ensure the simulator is in RUN (allow simulator to run during board walk down and turnover).
Verify 0A & 0C VA plenums in-service, 0B VA plenum in standby.
Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.
Verify SER printer is clear of data.
If desired, write an IC after all the set-up actions are completed (snap to 0). This IC may be used for running the scenario on additional simulator groups.
Provide examinees with turnover sheets, 1BwGP 100-2 and the in-progress 1BwGP 100-2T1.
Provide turnover of unit status to oncoming crew.
20-1 NRC 4 Page 4 of 21 INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Withdraw control rods to 2%-3% power If requested, provide Reactor Engineering oversight for raising power.
As SM, acknowledge commencement and completion of the power change/rod withdrawal.
As directed by the Lead examiner, call as SM and ask what are causing the delays in the startup. This should be done if SUR is low (<.3 DPM) from 10-8 amps to 2-3% power.
If asked, the SM is performing the final review of the Mode 2 to Mode 1 checklist.
Event 2: Perform preparations for rolling the main turbine If asked, another NSO has commenced the step F.33.e surveillances (1BwOS TRM 3.3.g.3/3.3.g.4).
As SM, acknowledge completion of 1BwGP 100-2 step 33.
If called as SM, acknowledge completion of 1BwGP 100-2 and report that 1BwGP 100-3 should not be initiated until the SM review of the Mode 2 to Mode 1 checklist is completed.
Event 3: 0A PW pump trip NOTE: Releasing event 3 will also cause event 4 to release. See note below on time delay.
Release SSF EVENT 3 and verify the following actuates:
IMF CV02A trips the 0A PW pump.
When dispatched as the EO, report the 0A PW pump is hot to the touch, no issues at its breaker.
If asked as the EO, the 0B PW pump is ready for a start and report a good start when started.
As SM, acknowledge the failure and requests for on-line risk assessment, maintenance support and IR initiation.
Event 4: High RCS activity NOTE: From malfunction insertion until the 1st RMS alarm is ~6-7 minutes.
Release SSF EVENT 4 and verify the following actuates:
IMF TH08.01 causes a small RCS fuel failure.
As SM, acknowledge high RCS activity, procedure entry, EAL review, Tech Spec entry and request for Nuclear Engineer. The SRO will enter Tech Spec 3.4.16 Condition A.
As Chemistry, acknowledge RCS sample requests. Five (5) minutes after sample request, give the following results: DE I-131 = 50 µCi/gm, DE Xe-133 = 425 µCi/gm and mixed bed decon factor is 65 (acceptable).
If asked as Chemistry, confirmed sample results are being analyzed to determine if the parameters are outside CY-AP-120-110 limits.
If asked, acknowledge that Chemistry has made all required notifications.
20-1 NRC 4 Page 5 of 21 If called as an EO, acknowledge request to check Reactor Coolant filter DP and periodically monitor/trend Reactor Coolant filter DP.
20-1 NRC 4 Page 6 of 21 Event 5: 1A Reactor Cavity Vent Fan trip Release SSF EVENT 5 and verify the following actuates:
IOR ZDI1VP05CA STOP trips the 1A Rx Cavity Vent fan.
DOR ZDI1VP05CA As SM, acknowledge the failure and requests for maintenance support and IR initiation.
If dispatched as EO, wait 2 minutes, then report the 1A Rx Cavity vent fan has no issues at its breaker (MCC 133X4 C1).
Event 6: 1B SG Tube Leak Release SSF EVENT 6 and verify the following actuates:
IMF TH03B 30 60 inserts a tube leak on the 1B SG, ramps to 30 gpm over 1 minute.
If called as Chemistry for 1B S/G sample, wait 15 minutes and report the estimated 1B S/G leakrate at 25 gpm.
As SM, acknowledge procedure entry, Tech Spec 3.4.13 Condition B entry and request for E Plan evaluation.
Event 7: Spurious automatic make-up relay actuation with Boric Acid flow controller power failure Release SSF EVENT 7 and verify the following actuates:
IRF OV06 TRUE fails power to the 1FK-0110 SLIM controller.
IMF CV45 OPEN starts a continuous VCT auto makeup.
If dispatched as the EO to investigate the spurious auto makeup, report that no abnormal conditions found.
As SM, acknowledge the failure and requests for on-line risk assessment, maintenance support and IR initiation.
Event 8: 1B SGTR Release SSF EVENT 8 and verify the following actuates:
IMF TH03B 420 causes the SG tube leak to worsen to a 420 gpm tube rupture in the 1B SG.
As SM, acknowledge procedure transitions and E Plan evaluation requests.
As Chemistry, acknowledge request to sample SGs.
After STA requested, as STA report CSF status.
As an EO, acknowledge the request to monitor the 1A & 1B DG operation per BwOP DG-11 & 11T2 and release the DG Panel Reset ssf command box.
As an EO, when requested, open 0/1SX007 valves to obtain 8000 gpm by releasing the Throttle SX to CC ssf command box.
As an EO, acknowledge request to trip the VV, VL and VW fans.
20-1 NRC 4 Page 7 of 21 As an EO, acknowledge the request to monitor the SFP level greater than 420 and the SFP temperature stable and periodically report the results to the STA.
Event 9: LOOP on main generator trip Verify SSF Gate 1 has auto released after the reactor trips and verify the following actuates on a 30 seconds time delay:
IMF ED04B causes a LOOP.
As an EO, if dispatched, wait 3 minutes & report SAT 142-2 appears to be damaged, no fire or oil leaks exist.
20-1 NRC 4 Page 8 of 21 Scenario No:
20-1 NRC 4 Event No.
1 Event
Description:
Withdraw control rods to 2%-3% power Time Position Applicants Actions or Behavior CUE
- From turnover, perform step 27 of 1BwGP 100-2.
- Direct ATC to withdraw rods to raise reactor power to 2%-3% per step 27 of 1BwGP 100-2.
EXAMINERS NOTE: Per 1BwGP 100-8, step F.10.3, the Shift Manager/Unit Supervisor may suspend the three-step pull-and-wait when the reactivity computer is in service during the performance of physics testing or during a reactor start-up when reactor power is below the point of adding heat or during rod recovery of a dropped or misaligned rod.
- Communicate with the BOP to obtain peer checks and withdraw rods (a maximum of 3 steps at a time unless the 3 step requirement is waived, see NOTE above).
- Monitor reactor power and slowly raise reactor power to 2%-3%.
- Additional rod withdrawals will be necessary to bring power into the desired range.
- Stabilize reactor power at 2%-3% (will insert rods to stabilize power).
- Notify the SRO when reactor power is in the 2%-3% range.
- Initiate 1BwOS NR-1 or core burnup computer program.
- Provide peer checks for the ATC.
- Monitor the remainder of the MCBs.
- Provide oversight of the rod withdrawals.
o May establish a critical parameter for reactor power.
o Notify SM when reactor power is in the 2%-3% range.
EXAMINERS NOTE: After the crew stabilizes reactor power at 2%-3%, the crew should perform step 33 of 1BwGP 100-2 (event 2) per their turnover.
20-1 NRC 4 Page 9 of 21 Scenario No:
20-1 NRC 4 Event No.
2 Event
Description:
Perform preparations for rolling the main turbine Time Position Applicants Actions or Behavior CUE From turnover, perform step 33 of 1BwGP 100-2.
SRO Direct BOP to perform step 33 of 1BwGP 100-2.
BOP Verify that all Turbine Drain Valves indicate OPEN at 1ZL-MS083.
Verify Turbine Main Steam Drain Valve Control Switch is in the AUTO position.
Verify that all Extraction Steam Spill Valves indicate OPEN.
Verify Condenser pressure is < 5 inches Hg absolute (OWS graphic 5515, 1PI-ES043/046/049 or computer points 2205/2206/2207).
Commence the following surveillances while continuing with the procedure:
1BwOS TRM 3.3.g.3.
1BwOS TRM 3.3.g.4.
EXAMINERS NOTE: If the BOP commences 1BwOS TRM 3.3.g.3/3.3.g.4, CUE the examinee that another NSO has been assigned to commence the surveillances.
BOP Verify TURBINE TRIPPED indicator on graphic 5512 is ILLUMINATED.
Verify the following are ILLUMINATED on graphic 5501:
IMP PRESS OUT MW OUT Verify/place the main turbine in MANUAL on graphic 5501:
SELECT MANUAL turbine control.
SELECT EXECUTE.
VERIFY TURBINE MANUAL pushbutton is ILLUMINATED.
BOP Verify the OPC STATUS ENABLED light is ILLUMINATED on graphic 5509.
Verify the following CLOSED lights are ILLUMINATED on graphic 5501:
Throttle valves (TV1-TV4).
Governor valves (GV1-GV4).
Intercept valves (IV R1-R3, IV L1-L3).
Reheat valves (RV R1-R3, RV L1-L3).
Perform the following to place DEHC in AUTO on graphic 5501:
Select AUTO field.
Select OPER AUTO mode of operation.
Verify the OPER AUTO indicator is ILLUMINATED.
Verify MANUAL indicator is OFF.
Perform the following to set the VPL limit on graphic 5501:
Select LIMITERS field.
Verify/select VPL up/down arrow until display indicates 0%.
Select EXIT.
If necessary, ZERO the GV positions (NOT required).
ATC Maintain reactor power at 2%-3%.
SRO Acknowledge completion of 1BwGP 100-2 step 33.
o Inform SM of completion of 1BwGP 100-2 step 33.
EXAMINERS NOTE: After 1BwGP 100-2 step 33 is complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 4 Page 10 of 21 Scenario No:
20-1 NRC 4 Event No.
2 Event
Description:
Perform preparations for rolling the main turbine Time Position Applicants Actions or Behavior Scenario No:
20-1 NRC 4 Event No.
3 Event
Description:
0A PW pump trip Time Position Applicants Actions or Behavior CUE Annunciator 0-38-A5, PW PUMP TRIP OR AUTO START, lit.
Annunciator 0-38-C5, PW PUMP DSCH PRESS LOW, lit.
EXAMINERS NOTE: The high RCS activity malfunction is inserted with this malfunction and (event 4) will take ~ 6-7 minutes to cause the 1st RMS alarm.
SRO Acknowledge annunciator 0-38-A5 and 0-38-C5 alarms.
Report failure to the SM.
BOP Refer to BwAR 0-38-A5/C5.
Determine 0A PW pump is tripped.
Start the 0B PW pump.
Dispatch EO to investigate the tripped 0A PW pump.
Place the 0A PW pump in PULLOUT.
O Dispatch EO to verify 0B PW pump proper operation.
ATC Monitor remainder of MCBs.
SRO Acknowledge PW pump status.
Notify SM of 0A PW pump trip and subsequent start of 0B PW pump.
Notify SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
EXAMINERS NOTE: (1) After the actions for starting the 0B PW pump are complete and with Lead Examiners concurrence, insert next event.
(2) The high RCS activity malfunction (event 4) will take ~ 6-7 minutes to cause the 1st RMS alarm.
20-1 NRC 4 Page 11 of 21 Scenario No:
20-1 NRC 4 Event No.
4 Event
Description:
High RCS activity Time Position Applicants Actions or Behavior CUE RMS alarm.
Gross failed fuel rad monitor, 1PR06J > alert/alarm setpoint.
CREW Identify entry conditions for 1BwOA PRI-4, HIGH REACTOR COOLANT ACTIVITY.
SRO Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Enter 1BwOA PRI-4 and direct the following operator actions of 1BwOA PRI-4:
Notify Chemistry to calculate DF for letdown mixed bed demineralizer and to sample for dose equivalent I-131 and noble gas activity.
Notify Rad Protection to monitor Aux Building radiation.
ATC Maximize letdown (verify 120 gpm letdown flow).
SRO Consult with Reactor Engineering for operational guidance.
Enter Tech Spec 3.4.16 Condition A.
Check letdown mixed bed demin DF acceptable per Chemistry Procedure.
Check RCS Chemistry.
Refer to TRM 3.4.b (NO actions required).
Verify Chemistry has made all required notifications.
Notify SM to perform risk evaluation, initiate IR, notify QNE and notify appropriate personnel.
BOP Monitor remainder of MCBs.
o Dispatch an EO to check Reactor Coolant filter DP and periodically monitor/trend Reactor Coolant filter DP.
EXAMINERS NOTE: After the high RCS activity Tech Spec is determined and with Lead Examiners concurrence, enter next event.
20-1 NRC 4 Page 12 of 21 Scenario No:
20-1 NRC 4 Event No.
5 Event
Description:
1A Reactor Cavity vent fan trip Time Position Applicants Actions or Behavior CUE Annunciator 0-33-C5, RX CAV FAN 1A TRIP DP LOW, lit.
1A Reactor Cavity vent fan trip light lit.
BOP Determine that the 1A Reactor Cavity vent fan is tripped.
Report failure to SRO.
Refer to BwAR 0-33-C5.
Start the standby 1B Reactor Cavity vent fan per BwOP VP-7, REACTOR CAVITY VENT FAN STARTUP.
Dispatch an EO to the 1A Reactor Cavity vent fan breaker.
o Place 1A Reactor Cavity vent fan to PULLOUT.
o Notify the ATC that shifting of the Reactor Cavity vent fans may cause a change in Core Exit Thermocouple (CETC) temperatures (BwOP VP-7).
ATC Monitor remainder of MCBs.
SRO Acknowledge 1A Reactor Cavity vent fan trip.
Notify SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
EXAMINERS NOTE: After the actions for the 1A Reactor Cavity vent fan trip are complete and with Lead Examiners concurrence, insert next event.
20-1 NRC 4 Page 13 of 21 Scenario No:
20-1 NRC 4 Event No.
6 Event
Description:
Spurious automatic make-up relay actuation with Boric Acid flow controller power failure Time Position Applicants Actions or Behavior CUE Boric Acid pump starts.
1CV110A and 1CV111A throttle open, 1CV110B opens.
VCT level rises (initial level above auto-start setpoint of 37%).
1FK-0110, Boric Acid flow controller, loses power.
ATC Determine that VCT auto make-up has occurred with normal VCT level.
Place Makeup Control switch to STOP or Mode Select switch to OFF to stop the auto make-up (may wait for 55% VCT level prior to stopping the auto make-up).
Determine 1FK-0110, Boric Acid flow controller, has lost power.
o Dispatch an NSO to the AEER to investigate the spurious automatic make-up relay actuation with Boric Acid flow controller power failure.
SRO Acknowledge the spurious automatic make-up relay actuation with Boric Acid flow controller power failure.
Notify SM of spurious auto make-up and status of RMCS.
Notify SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.
o May establish a critical parameter for VCT level.
EXAMINERS NOTE: After the actions for stopping the auto make-up are complete and with Lead Examiners concurrence, enter next event.
20-1 NRC 4 Page 14 of 21 Scenario No:
20-1 NRC 4 Event No.
7 Event
Description:
1B SG Tube Leak Time Position Applicants Actions or Behavior CUE RMS Secondary rad monitor alarms/levels rising:
o SJAE/GLAND STEAM EXHAUST - 1PR027J.
o 1B MAIN STEAM LINE - 1AR022J/23J.
PZR level dropping.
PZR pressure dropping.
Charging/letdown mismatch.
BOP o Refer to BwAR 1-1PR27J for operator actions.
o Refer to BwAR 1-1AR22/23J for operator actions.
SRO Enter 1BwOA SEC-8, SG TUBE LEAKAGE, and direct operator actions.
Request SM evaluation of Emergency Plan conditions.
o PZR pressure < 1829 psig (NO).
o Steamline pressure < 640 psig (NO).
o CNMT pressure > 3.4 psig (NO).
Maintain PZR level stable:
Throttle 1CV121 & 1CV182.
Check PZR level stable or rising.
Reduce letdown flow to 75 gpm.
Verify makeup is adequate to maintain VCT level.
SRO Minimize secondary contamination.
Dispatch operators to perform BwOP MS-13, OPERATION WITH SG TUBE LEAKAGE.
Notify RP to monitor rad levels and quantify release.
CREW Identify leaking SG (1B).
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.
ATC Determine SG tube leak rate.
Estimate leak rate.
o Computer point U9052 or SG Leak Tracker Program on PPC.
Charging/letdown/RCP leakoff flow balance.
o Change in VCT level.
o 1BwOS SG-1, SG PRI TO SEC LEAKAGE ESTIMATION.
o Grab sample.
Check total RCS to secondary leak rate < 10 gpm - NO (GO TO step 9).
ATC Confirm SG leak rate (step 9).
At least 2 independent indications - TREND in the same direction.
o Main steam line radiation monitors (1AR22/23).
o SJAE/GS Exhaust radiation monitor (1PR27J).
o SG Blowdown radiation monitor (1PR08J).
o N-16 radiation monitors.
20-1 NRC 4 Page 15 of 21 Scenario No:
20-1 NRC 4 Event No.
7 Event
Description:
1B SG Tube Leak Time Position Applicants Actions or Behavior CREW Initiate Unit Shutdown.
Check leak rate < 100 gpd - NO.
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 /> (current power ~3%).
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 />. Continue shutdown using 1BwGP 100-4 and 5.
- Enter Tech Spec 3.4.13 Condition B.
EXAMINERS NOTE: (1) After the actions for the 1B SG tube leak are complete and with Lead Examiners concurrence, insert next event.
(2) At this point, the crew should begin preparations for shutting down the unit. The remaining actions of 1BwOA SEC-8 would be performed after the reactor is shutdown, if an SI does NOT actuate.
20-1 NRC 4 Page 16 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior CUE RMS Secondary rad monitor alarms/levels rising.
o SJAE/GLAND STEAM EXHAUSTER - 1PR027J.
o 1B/1C MAIN STEAM LINE - 1AR022J/23J.
PZR level dropping.
PZR pressure dropping.
Charging/letdown mismatch.
CREW Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.
SRO Notify SM of plant status and procedure entry.
Request evaluation of Emergency Plan conditions.
Enter 1BwEP-0 and direct operator actions of 1BwEP-0.
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/Ovation graphics:
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).
EXAMINERS NOTE: ~30 Seconds after the reactor trip a loss of offsite power (LOOP) will occur causing ESF busses to be powered by the DGs.
ATC/BOP Perform immediate operator actions of 1BwEP-0 at 1PM05J/1PM06J:
Check SI Status:
SI First OUT annunciator - LIT.
SI ACTUATED Permissive Light - LIT.
SI Equipment - AUTOMATICALLY ACTUATED:
o Either SI pump - RUNNING.
o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B.
Manually actuate SI at 1PM05J & 1PM06J.
SRO Direct BOP to perform Attachment B of 1BwEP-0.
EXAMINERS NOTE: SRO and ATC will continue in 1BwEP-0 (page 17) while BOP is performing Attachment B.
Verify FW isolated at 1PM04J.
FW pumps - TRIPPED.
FW isolation monitor lights - LIT.
FW pumps discharge valves (1FW002A-C) - CLOSED (NO - power to valves lost).
20-1 NRC 4 Page 17 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior Verify DGs running at 1PM01J:
DGs - BOTH RUNNING.
1SX169A/B OPEN.
Dispatch operator to monitor DGs operation.
Verify Generator Trip at 1PM01J:
OCB 1-8 and 7 OPEN.
PMG output breaker - OPEN.
Verify SX pumps running.
Check U-0 CC Heat Exchanger aligned to U-1:
1CC9473A - OPEN.
1CC9473B - OPEN.
Unit 1 SX pumps - BOTH running.
Dispatch an operator to energize the 0SX007 & 1SX007 valves.
Adjust flow to 8000 gpm to U-1 & U-0 CC HX.
Deenergize the 0SX007 & 1SX007 valves.
Verify Control Room ventilation aligned for emergency operations at 0PM02J:
o VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT (Operate failure exists on all VC rad monitors - Verify VV, VL and VW fans tripped).
o Restart VC Rad monitors (student may elect to restart monitors)
Operating VC train equipment - RUNNING.
0B Supply fan 0B Return fan 0B M/U fan 0B Chilled water pump 0B Chiller Operating VC train dampers - ALIGNED.
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 > +0.125 inches water on 0PDI-VC038.
Verify Auxiliary Building ventilation aligned for emergency operation at 0PM02J:
Two inaccessible filter plenums aligned.
Plenum A:
0VA03CB - RUNNING.
0VA023Y - OPEN.
0VA436Y - CLOSED.
Plenum C:
0VA03CF - RUNNING.
0VA072Y - OPEN.
20-1 NRC 4 Page 18 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior 0VA438Y - CLOSED.
Verify FHB ventilation aligned for emergency operation at 0PM02J:
- 0VA04CB - RUNNING.
- 0VA055Y - OPEN.
- 0VA062Y - OPEN.
- 0VA435Y - CLOSED.
Trip all running HD pumps (None running - LOOP).
Shutdown FW pumps as necessary (None running - LOOP).
Shutdown all unnecessary CD/CB pumps (None running - LOOP).
Shutdown all unnecessary CW pumps (None running - LOOP).
Notify Equipment Operator to initiate periodic checking of Spent Fuel Pool level and temperature and notify STA of results.
Notify SRO Attachment B is complete.
EXAMINERS NOTE: SRO and ATC will continue in 1BwEP-0 while BOP is performing Attachment B.
ATC Verify ECCS pumps running at 1PM05J/1PM06J:
BOTH CV pumps - RUNNING.
BOTH RH pumps - RUNNING.
BOTH SI pumps - RUNNING.
ATC Verify the following at 1PM06J:
RCFCs running in accident mode.
Group 2 RCFC accident mode status lights - LIT.
CNMT Phase A valves closed.
Group 3 Cnmt Isol monitor lights - LIT.
ATC Perform the following at 1PM06J:
Verify Cnmt Vent isolation:
Group 6 Cnmt Vent Isol monitor lights - LIT.
Verify AF system:
BOTH AF pumps - RUNNING.
AF isolation valves - 1AF13A-H OPEN.
AF flow control valves - 1AF005A-H throttled OPEN.
Verify CC pumps running:
BOTH CC pumps - RUNNING.
Verify SX pumps running:
BOTH SX pumps - RUNNING.
ATC Check if Main Steamline isolation is required (NO):
S/G pressures > 640 psig at 1PM04J.
CNMT pressure < 8.2 psig at 1PM06J.
CNMT pressure remained < 20 psig.
20-1 NRC 4 Page 19 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior ATC
[CT-18]
Verify total AF flow:
AF flow > 500 gpm.
If 1B SG NR level > 10% and rising in an uncontrolled manner, then:
CLOSE 1AF013B.
CLOSE 1AF013F.
Set 1AF005B and 1AF005F pot demand = 0%.
ATC Verify ECCS valve alignment at 1PM06J:
Group 2 Cold Leg Injection monitor lights required for injection - LIT.
Verify ECCS flow:
High head SI flow >100 gpm (1FI-917).
RCS pressure >1700 psig.
ATC Check PZR PORVs and spray valves at 1PM05J:
PORVs CLOSED.
PORV isolation valves - BOTH ENERGIZED.
PORV relief paths - PORVs in AUTO, PORV isolation valves OPEN.
Normal PZR spray valves - CLOSED.
ATC Check RCS temperatures at 1PM05J:
RCPs - ANY RUNNING (NO).
- RCS cold leg temperature - STABLE AT OR TRENDING TO 557°F (NO - reduce AF flow to minimize RCS cooldown).
o Actuate main steamline isolation.
Examiner Note: The crew may determine that a main steamline isolation is required at the prior step. The combination of a loss of offsite power, with a reactor trip, will cause MSR drain valves to remain open resulting in an uncontrolled cooldown.
ATC Check if RCPS should be stopped:
RCPS - ANY RUNNING (NO).
BOP Check if SG secondary boundaries are intact:
Verify NO SG depressurizing in an uncontrolled manner or completely depressurized.
BOP Check if SG tubes are intact:
1B MS lines > ALERT ALARM SETPOINT.
CREW Identify entry conditions for 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.
SRO Notify SM of plant status and procedure entry.
Request SM evaluation of Emergency Plan conditions.
Request STA evaluation of status trees.
SRO Enter 1BwEP-3 and direct operator actions of 1BwEP-3 to establish the following conditions:
ATC Check if RCPS should be stopped:
RCPS - ANY RUNNING (NO).
1B Main steam line rad monitor ABNORMAL for plant conditions.
20-1 NRC 4 Page 20 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior
[CT-18]
1B SG level rising uncontrollably.
Isolate flow from ruptured SG.
Verify 1MS018B in AUTO and CLOSED.
Verify 1SD002E & F CLOSED.
Isolate feedwater flow into and steam flow from the 1B SG before transition to 1BwCA 3.1 occurs. (Westinghouse - CT-18) (K/A number -
EPE038EA1.32, importance - 4.6/4.7)
CLOSE MSIV and MSIV bypass valve for 1B SG.
Check ruptured SG level - Narrow Range > 10%.
CLOSE 1AF013B & F (previously performed in 1BwEP-0).
Set demand for 1AF005B and F to 0% (previously performed in 1BwEP-0).
BOP Check ruptured SG pressure > 330 psig.
SRO Determine the RCS temperature to which the RCS must be cooled down to allow depressurization of the RCS to ruptured SG pressure.
BOP/
[CT-19]
Block MS Isolation SI after P-11 reached.
Establish/maintain RCS temperature so that transition from 1BwEP-3 does not occur because the RCS temperature is too high (1BwCA-3.1) or too low (1BwFR-P.1). (Westinghouse - CT-19) (K/A number - EPE038EA1.36, importance - 4.3/4.5)
Dump steam at maximum rate using intact SG PORVs.
Dispatch an operator with keys to standby 1SI101A & B.
Control Aux feed flow to maintain intact SG levels between 30% and 50%.
ATC Check PZR PORVs and ISOL Valves:
PORV isolation valves - BOTH ENERGIZED.
PORVs - CLOSED.
PORV isolation valves - BOTH OPEN.
BOP Reset SI:
Depress BOTH SI Reset pushbuttons at 1PM06J.
Verify SI ACTUATED PERMISSIVE light NOT lit at 1PM05J (no power).
Verify AUTO SI BLOCKED PERMISSIVE light lit at 1PM05J (no power).
BOP Reset Phase A:
Depress BOTH Phase A Reset Pushbuttons at 1PM06J.
Check a station air compressor is running at 0PM01J.
OPEN 1IA065 and 1IA066 at 1PM11J.
BOP Check if RH pumps should be stopped:
20-1 NRC 4 Page 21 of 21 Scenario No: 20-1 NRC 4 Event No.
8 & 9 Event
Description:
1B SGTR / LOOP on reactor trip Time Position Applicants Actions or Behavior RH pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST.
Check RCS pressure > 325 psig.
Stop BOTH RH pumps and place in standby.
BOP Check if RCS cooldown should be stopped.
Check CETCs < required temperature.
Reduce steam flow from intact SG PORVs.
Maintain CETCs < required temperature.
SRO Establish a critical parameter for RCS temperature.
BOP Check ruptured SG pressure stable or rising.
Check RCS subcooling acceptable per figure 1BwEP 3-2 (+20°F).
[CT-20]
Depressurize RCS to refill PZR.
Normal Spray available (NO) - GO TO step 17.
PZR PORV - AT LEAST ONE AVAILABLE (YES).
Depressurize RCS to meet SI termination criteria prior to water release from the 1B SG PORV or safety valve. (Westinghouse - CT-20) (K/A number - EPE038EA1.04, importance - 4.3/4.1)
OPEN ONE PZR PORV at 1PM05J until any of the following are met:
o RCS pressure - Less than ruptured SG pressure and PZR level > 14%.
o PZR level - Greater than 68%.
o RCS subcooling - not acceptable.
CLOSE PZR PORVs at 1PM05J.
Check normal and aux spray valves - CLOSED.
Check RCS pressure - RISING.
EXAMINERS NOTE: At this point in the scenario, all Critical Tasks are complete, and the scenario stop criteria has been reached, with Lead Examiners concurrence, STOP the scenario.