ML22195A248
| ML22195A248 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/19/2021 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | |
| Baker R | |
| Shared Package | |
| ML21055A859 | List: |
| References | |
| Download: ML22195A248 (75) | |
Text
Dresden Generating Station ILT-N-2 SWAP STATOR WATER COOLING PUMPS CRD PUMP TRIP EMERGENT LOAD DROP HPCI SPURIOUS INITIATION ROD DRIFT BUS DUCT BLOWER TRIP FEEDWATER SYSTEM HIGH VIBES FAILURE OF EDG TO AUTO START LOSS OF FEED - ED ON LEVEL Rev. 00 06/21 Developed By:
Exam Author Date Approved By:
Facility Representative Date
Page 2 of 25 Scenario Outline Facility:
Dresden Generating Station Scenario No.:
2021-302 ILT-N-2 Op-Test No.: 2021-302 Examiners Operators
/ crew position
/ ATC
/ BOP
/ CRS Initial Conditions:
Unit 2 is at 80% Power.
2C Reactor Feed Pump is out of service for motor replacement.
Turnover:
Swap Stator Water Cooling Pumps for maintenance.
Critical Tasks:
RPV-1.1 - If the RPV level trend is not reversible with an RPV injection source lined up with a pump running, initiate emergency depressurization with RPV water level between the Top-of-Active Fuel and the Minimum Steam Cooling RPV Water Level or within two and 1/2 minutes after TAF is reached, whichever is later.
RPV-1.5 - Per DEOP 100, RPV Control, with the automatic ADS timer initiated, inhibit ADS before an automatic actuation occurs.
PC-1.1 - While executing DEOP 200-1, Primary Containment Control, when drywell pressure exceeds 9 psig and only if operating within the safe region of the drywell spray initiation limit (DSIL), initiate drywell sprays.
Event No.
Malf.
No.
Event Type*
Event Description #
1 NONE N
BOP (New) - GENERATOR - SWC Pump Swap for Maintenance 2
RDPPBTRP C
ATC (Pre) - CRD - Pump Swap due to Grinding Noise 3
NONE R
ATC (New) - REACTIVITY - Emergent Load Drop 4
HPINIT I/T BOP CRS (New) - HPCI - Spurious Initiation 5
RODL06DI C/T ATC CRS (New) - CRD - Rod Drift 6
MGDDBTR I
BOP (New) - GENERATOR - Bus Duct Blower Trip 7
SER1363 F43 M
ALL (New) - FEEDWATER - System High Vibes (Manual Scram) with Recirc Leak 8
T13 C
BOP (New) - AUX POWER - Failure of EDG to Auto Start 9
F43 M
ALL (Pre) - EMERGENCY DEPRESSURIZE - On Lowering RPV Water Level Due To Recirc System Leak and Loss of All Reactor Feed Pumps
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams Scenario Objective:
Evaluate the Teams ability to operate the plant with a RCS leak and loss of all feedwater pumps.
Scenario Initial Conditions
- 1. Unit 2 is at ~80% power.
- 2. The following equipment is OOS:
- a.
2C RFP
- 3. LCOs:
- a.
None
Page 3 of 25 Scenario Sequence Event #
Description 1
GENERATOR - SWC Pump Swap for Maintenance:
The BOP will start the standby Stator Water Cooling pump and secure the running pump.
2 CRD - Pump Swap due to Grinding Noise:
While on their round, an EO will report grinding noise in the 2B CRD Pump. The crew will start the standby CRD pump and secure the running CRD Pump. The running CRD pump will trip on its own after 10 minutes if no action is taken.
3 REACTIVITY - Emergent Load Reduction:
The TSO calls and informs the crew that a 75 MWe load reduction is required for grid stability. The ATC lowers power using CRAM rods and/or Recirc flow per DGP 03-01.
4 HPCI - Spurious Initiation:
A spurious initiation of HPCI occurs. The crew will verify HPCI is not needed, then secure and isolate it.
Technical Specification 3.5.1 Condition G applies.
5 CRD - Rod Drift:
Control rod E-06 drifts in. The crew will take actions per DOA 0300-05, Inoperable or Failed Control Rod Drives. Technical Specification 3.1.3 Condition C applies.
6 GENERATOR - Bus Duct Blower Trip:
The running Bus Duct Blower trips on overcurrent. The BOP will start the standby Bus Duct Blower.
7 FEEDWATER - System High Vibes (Manual Scram) with Recirc Leak:
High Feedwater vibrations will come in one at a time until action is taken to insert a Manual Scram and secure all Reactor feed pumps. A recirc leak will also start on the scram causing level to slowly lower.
8 AUX POWER - Failure of EDG to Auto Start:
Once the crew performs a manual SCRAM and level drops to less than -59 inches, the 2/3 EDG will fail to start automatically. The BOP can start the EDG manually by taking the control switch to RUN.
9 EMERGENCY DEPRESSURIZE - On Lowering RPV Water Level Due To Recirc System Leak and Loss of All Reactor Feed Pumps:
Following the scram, water level lowers and HPCI is degraded if the crew attempts to start it. With insufficient HP injection sources available to overcome the leak rate, an ED will be performed on low RPV level. The team will recover RPV level with LP ECCS systems.
Event One - Swap SWC Pumps The BOP will start the oncoming Stator Water Cooling Pump and secure the off going pump for maintenance.
Malfunctions required: 0 None Success Path:
2B SWC Pump running. 2A SWC Pump secured.
Event Two - CRD Pump Failure An EO will report a grinding noise in 2B CRD Pump which will trip after 10 minutes.
Malfunctions required: 1 (CRD Pump overcurrent trip)
Success Path:
2A CRD Pump started and 2B secured or tripped.
Page 4 of 25 Event Three - Emergent Load Drop 75 MWe load drop requested from TSO.
Malfunctions required: 0 None Success Path:
Uses DGP 03-01 to lower power with CRAMs or recirc flow.
Event Four - HPCI Spurious Initiation HPCI will spuriously initiate.
Malfunctions required: 1 (HPCI spurious initiation)
Success Path:
HPCI secured and isolated.
Determines Technical Specifications requirements.
Event Five - Rod Drift Control Rod E-06 drifts in.
Malfunctions required: 1 (E-06 drift in)
Success Path:
Performs DOA 0300-05.
Determines Technical Specifications requirements.
Event Six - Bus Duct Blower Trip 2A Bus Duct Blower trips on overcurrent.
Malfunctions Required: 1 (2A Bus Duct Blower trip)
Success Path:
2B Bus Duct Blower started.
Event Seven - Feedwater System High Vibes with Recirc Leak High Feedwater System vibration alarms come in on at a time. A recirc leak is initiated when the reactor scrams.
Malfunctions required: 2 (Recirc Leak)
(FW System High Vibes)
Success Path:
Feedwater System secure and manual Scram
Page 5 of 25 Event Eight - 2/3 EDG Fails to Auto Start 2/3 EDG fails to start automatically.
Malfunctions required: 1 (Auto Start failure of 2/3 EDG)
Success Path:
Manually starts 2/3 EDG.
Event Nine - Emergency Depressurization on RPV Level Recirc Leak increases causing RPV level to lower rapidly.
Malfunctions required: 1 (Recirc leak increase)
Success Path:
Initiate Emergency Depressurization once TAF is reached.
Page 6 of 25 PRE-SCENARIO ACTIVITIES 1
If applicable, conduct pre-scenario activities in accordance with TQ-AA-155-J040, SIMULATOR EXAMINATION BRIEFING.
- a. Direct the crew to perform their briefs prior to entering the simulator.
- b. Provide the Team a copy of DOP 7400-02, STATOR COOLING WATER SYSTEM PUMP CHANGEOVER.
2 Simulator Setup (the following steps can be done in any logical order)
- a.
Initialize simulator in an ~80% power IC. (IC 301 used for validation)
- b. Cut in/out Cond Demins as needed, to maintain DP within limits.
- c.
Ensure running Condensate pump amps within limits.
3 Verify the following simulator conditions:
- a.
Verify Reactor Power ~80%, adjust rods or Recirc as appropriate.
- b. Ensure 2A SWC Pump is running.
- c.
Ensure 2B CRD Pump is running.
- d. Ensure 2A Bus Duct Blower is running.
- e.
Verify the TR-86 Tap Changer in Manual.
- f.
Delete E208 from alarm processing.
4 Run Pump_Sumps.cae 5
Run the initial setup CAEP file: 20-2 (2021-302) ILT-N-2.cae 6
Place the following equipment out of service:
- c.
2C Aux Oil Pump switch in PTL with OOS tag.
7 Place protected pathways on the following equipment:
- a. 2A & 2B RFPs 8
Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Required Actions o
Optional Actions NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
Page 7 of 25 Event One - Swap SWC Pumps Trigger Position Crew Actions or Behavior 28 SIMULATOR OPERATOR ROLE PLAY:
If requested to set gains to 1, (wait 3 min) activate TRIGGER 28, then report gains set to 1. (This trigger can be triggered OFF, then back ON to adjust gains more than once).
SIMULATOR OPERATOR ROLE PLAY:
EO is on station at the Stator Water Cooling Pumps ready for them to be swapped.
EO to verify operation of 2B SWC Pump, report the following:
2B Stator Water Cooling Pump is operating normally.
EO to check 2A SWC Pump at rest, report the following:
2A Stator Water Cooling Pump is at rest.
EO to verify SWC System parameters, wait 2 minutes and report the following:
All Stator Water Cooling System parameters are normal.
CRS Directs BOP to start 2B Stator Water Cooling Pump and secure 2A Stator Water Cooling Pump per DOP 7400-02, STATOR WATER COOLING WATER SYSTEM PUMP CHANGEOVER.
BOP Swaps Stator Water Cooling Pumps per DOP 7400-02 by performing the following:
Starts 2B SWC Pump by placing the control switch to START.
Verifies NORMAL PRESS light is illuminated.
Direct EO to verify proper operation of 2B SWC Pump.
Stops 2A SWC Pump by placing the control switch to STOP.
Directs EO to verify SWC System parameters.
Notifies CMO to perform vibration monitoring of 2B SWC Pump.
ATC Monitors panels and assists as directed.
Event 1 Completion Criteria:
2B SWC Pump running and 2A SWC Pump secured,
-- AND/OR --
At the discretion of the Lead Examiner.
Page 8 of 25 Event Two - CRD Pump Failure Trigger Position Crew Actions or Behavior 1
SIMULATOR OPERATOR:
At the discretion of the Floor Instructor / Lead Evaluator, activate TRIGGER 1 to cause 2B CRD Pumps amps to rise. 2B CRD Pump will trip after 10 minutes.
After 1 min, call and report the following:
This is the U2 EO, 2B CRD Pump is making a loud grinding noise.
If asked: The grinding noise is getting worse. I am leaving the area.
ROLE PLAY:
EO to verify proper operation of 2A CRD Pump, report the following:
2A CRD Pump is operating normally.
EO at 2B CRD Pump, report the following:
2B CRD Pump is at rest.
ATC Recommends starting 2A CRD Pump and securing 2B CRD Pump.
When directed, enters DOA 0300-01, CONTROL ROD DRIVE SYSTEM FAILURE, and completes the following actions:
o Takes manual control of FIC 2-340-1 CRD FLOW CONTRL (if valve has gone open).
Starts 2A CRD pump.
Stops 2B CRD pump.
Verifies CRD parameters return to previous values.
May take FIC 2-340-1 CRD FLOW CONTRL to open/automatic, if closed previously.
BOP Monitors panels and assists as directed.
CRS Directs entry into DOA 0300-01 and swap CRD Pumps.
Establishes contingency actions if 2nd CRD pump fails.
Contacts outside organizations for assistance.
If 2B CRD Pump trips, enters TRM 3.3.h for loss of RVWLIS, Restore RVWLIS within 7 days.
Event 2 Completion Criteria:
2A CRD Pump is running and 2B CRD Pump is secured,
-- AND/OR--
At the direction of the Lead Examiner.
Page 9 of 25 Event Three - Emergent Load Reduction Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the Floor Instructor / Lead Evaluator, call as the TSO and report the following:
This is the TSO. Due to unstable grid conditions, execute emergent load drop contingencies and immediately drop load 75 MWe on Unit 2 at Dresden Station 12.
CRS Directs 75 MWe emergency power reduction per DGP 03-01, POWER CHANGES.
ATC Performs emergency power reduction per DGP 03-01 Step G.4 by lowering recirc flow as follows:
Presses LOWER HIGH, MED, and/or LOW button on Recirc Master Controller.
BOP Monitors panels and assists as directed.
Event 3 Completion Criteria:
Sufficient Power Decrease,
-- AND/OR --
At the discretion of the Floor Instructor/Lead Evaluator.
Page 10 of 25 Event Four - HPCI Spurious Initiation Trigger Position Crew Actions or Behavior 2
SIMULATOR OPERATOR:
At the discretion of the Floor Instructor / Lead Evaluator, activate TRIGGER 2, which causes HPCI to spuriously initiate.
ROLE PLAY:
EO sent to HPCI, wait 3 min and report the following:
(HPCI secured) The HPCI turbine is at rest and I see no abnormalities.
(HPCI running) U2 HPCI turbine is running. I dont see any other issues.
BOP Reports that HPCI has spuriously initiated.
Checks Reactor level and drywell pressure to validate that it should not be running.
When directed, shuts down HPCI per DOP 2300-04, HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) SHUTDOWN, Hard Card by performing the following:
Places HPCI flow controller in MANUAL and reduce output to zero (0).
OR Places 2-2301-4 and 2-2301-14 in PTL.
CRS Directs BOP to shut down HPCI.
Directs entry into DGA-07, UNEXPECTED REACTIVITY CHANGE.
References Technical Specifications and determines:
TS 3.5.1 Condition G.1 and G.2, Verify Isolation Condenser is OPERABLE immediately AND restore HPCI System to OPERABLE status within 14 days.
o May reference TS 3.3.5.1 A1 & B.3.
ATC When directed, enters and performs actions of DGA-07 as follows:
Contacts QNE.
Generates an OD-20.
Event 4 Completion Criteria:
HPCI shut down AND, Tech Specs have been addressed,
-- AND/OR --
At the discretion of the Floor Instructor/Lead Evaluator.
Page 11 of 25 Event Five - Rod Drift Trigger Position Crew Actions or Behavior 3
SIMULATOR OPERATOR:
When directed, activate TRIGGER 3 which causes control rod E-06 to drift in.
ROLE PLAY:
EO to check E-06 HCU, wait 2min, then report the following:
At the HCU for E-06, the line with the 112 valve is hotter than normal.
EO to close E-06s 2-0305-102, wait 1 min, and report the following:
E-06 2-0305-102 is closed.
WEC/EO to hydraulically and/or electrically disarm E-06: Acknowledge the request. It is not intended to complete field isolation.
QNE to evaluate core limits, wait 2 minutes, and report the following:
Core parameters are within limits.
EO to isolate E-06, wait 2 minutes, activate TRIGGER 12 and report the following:
CRD E-06 is hydraulically and electrically isolated.
ATC Announces 902-5 A-3, ROD DRIFT, alarm.
Notices and announces that Control Rod E-06 is drifting in.
Selects Rod E-06 and receives alarm DAN 902-5 B-3, ROD WORTH MIN BLOCK.
Performs actions of DOA 0300-05, INOPERABLE OR FAILED CONTROL ROD DRIVES, as directed.
Immediate:
Bypasses the Rod Worth Minimizer.
Inserts the CRD to 00 using Emergency Rod In.
CRS Enters DOA 0300-05 and directs actions.
May refer to Tech. Spec 3.3.2.1 Condition C. (Not required with RX power >10%)
Enters DGA 07.
ATC Announces that procedure directs entering DOA 0300-12, MISPOSITIONED CONTROL ROD.
Discontinues ALL non-emergency control rod motion and notifies CRS and QNE to evaluate core parameters.
Directs EO to close CRD E-06s 2-0305-102, WITHDRAW VLV, to prevent CRD discharge volume from filling.
CRS References TS 3.1.3, Condition C, and determines the following actions are required:
C.1 Fully insert inoperable control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. (DOA 0300-05, INOPERABLE OR FAILED CONTROL ROD DRIVES, directs inserting the rod)
C.2 Disarm the associated CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Directs disarming rod E-06.
Enters DOA 0300-12, MISPOSITIONED CONTROL ROD.
Directs taking rod E-06 OOS on the RWM.
Page 12 of 25 Event Five - Rod Drift Trigger Position Crew Actions or Behavior ATC Takes rod E-06 OOS on the RWM.
o Select SECONDARY FUNCTIONS o
Select the Rod to be taken OOS on the select matrix.
o Select the Rod to be taken OOS on the RWM Screen.
o Verify the Rod is enclosed in a blue box.
o Select ROD OUT OF SERVICE and verify message Rod E-06 placed out of service.
Event 5 Completion Criteria:
Control Rod E-06 Has Been Inserted to Position 00, AND Tech Specs Have Been Addressed.
-- AND/OR --
At the direction of the Lead Examiner.
Page 13 of 25 Event Six - Bus Duct Blower Trip Trigger Position Crew Actions or Behavior 4
SIMULATOR OPERATOR:
At the discretion of the Lead Examiner, activate TRIGGER 4, which trips 2A Bus Duct Blower.
ROLE PLAY:
EO to the Bus Duct Blowers, wait 3 min, and then report the following:
2A Bus Duct Blower is at rest and the motor is hot to the touch. 2B Bus Duct Blower is operating normally.
EO to MCC 25-2, wait 3 min, and then report the following:
The breaker for 2A Bus Duct Blower is tripped open and the overloads are tripped as well.
BOP Announces and references DAN 902-8 F-11, ISOL PHASE BUS DUCT BLOWER TRIP.
Starts 2B Bus Duct Blower.
Performs DOP 6700-20, 480V CIRCUIT BREAKER TRIP.
Places Control Switch for 2A Bus Duct Blower in PTL.
CRS Directs starting 2B Bus Duct Blower.
Enters DOP 6700-20.
ATC Monitors panels and assists as directed.
Event 6 Completion Criteria:
2B Bus Duct Blower started,
-- AND/OR --
At the discretion of the Lead Examiner.
Page 14 of 25 Event Seven - Feedwater System High Vibes w/ Recirc Leak Trigger Position Crew Actions or Behavior CAEP 5
SIMULATOR OPERATOR:
At the discretion of the Lead examiner, run CAEP file 20-2 (2021-302) ILT-N-2 SUPPLEMENTAL.cae, which causes a Feedwater System high vibration.
When the crew secures the RFPs, PAUSE and EXIT CAEP file 20-2 (2021-302) ILT-N-2 SUPPLEMENTAL.cae to stop the vibrations.
When the crew performs a manual scram, verify TRIGGER 5 is in to initiate a Recirc leak.
ROLE PLAY:
If RFPs are still operating:
EO sent to Feedwater Regulating Valve station, wait 2 min then report the following:
Feedwater Regulating Valve pipes are swinging.
EO sent to Feedwater Pump room, wait 2 min then report the following:
Feedwater System pipes are swinging outside the RFP room.
If RFPs are secured:
Wait 2 min and report the following:
There is insulation on the floor and a large amount of dust in the air. There is no evidence of a leak.
ATC / BOP Announces following alarms and refers to DANS:
902-6 E-12, FEEDWATER REG STATION VIBRATION HI.
902-6 F-12, 2A RFP VIBRATION HI.
902-6 G-12, 2B RFP VIBRATION HI.
Observes and announces Feedwater parameters are swinging.
May direct EOs to investigate the Feedwater areas.
Performs scram preparatory actions per DGP 02-03, REACTOR SCRAM, as directed.
o Reduces FCL to <93% by inserting control rods.
o Reduce Recirc flow to 56 Mlbm/hr core flow.
o Start the motor suction pump AND turning gear oil pump.
o Trip hydrogen addition.
When directed, enters and performs actions of DOA 3200-01, FEEDWATER SYSTEM HIGH VIBRATION.
Performs manual scram per DGP 02-03.
Depresses BOTH scram buttons.
Places Rx MODE SW in SHUTDOWN.
o Check rods inserted.
o Verifies Recirc Pumps run back.
o Maintains RPV/L between +25 and +35 inches or as directed by Unit Supervisor.
o Verifies turbine tripped.
o Verifies generator tripped.
o Verifies aux power transfers.
Trips RFPs when RPV time/level directions of DOA 3200-01 are met (60 seconds or level restored to > +15 inches)
Page 15 of 25 Event Seven - Feedwater System High Vibes w/ Recirc Leak Trigger Position Crew Actions or Behavior CRS Enters DOA 3200-01, and directs actions.
May enter DGP 02-03, REACTOR SCRAM, and direct taking scram preparatory actions.
Directs manual scram per DGP 02-03 and tripping RFPs when DOA 3200-01 requirements met.
Enters DEOP 100, RPV Control and directs actions.
o Verification of all isolations, ECCS and EDG starts.
o Holding RPV/L +8 to +48 inches.
o Maintaining RPV/P <1060 psig using the BPVs.
8 ROLE PLAY:
EO to close 2-0301-25 valve, wait 2 min and insert TRIGGER 8 and report the following:
The 2-0301-25 valve is closed.
Event 7 Completion Criteria:
Manual Reactor Scram performed,
-- AND / OR --
At the discretion of the Lead Examiner.
Page 16 of 25 Event Eight - 2/3 EDG Fails to Auto Start Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:
Once the crew performs a manual scram and level drops to -59 or drywell pressure rises to +2 psig, the 2/3 EDG will not start automatically. The crew will have to start it manually.
ROLE PLAY:
EO sent to 2/3 EDG, wait 2 minutes, and report the following:
(If 2/3 EDG has not been manually started) 2/3 EDG is not running.
(If 2/3 EDG was manually started) 2/3 EDG is running normally.
BOP Notices 2/3 EDG did not start automatically.
Starts 2/3 EDG manually by placing the control switch to RUN.
Informs supervisor that 2/3 EDG did not start automatically.
Dispatches EO to investigate operation of 2/3 EDG.
CRS Acknowledges report of 2/3 EDG.
Event 8 Completion Criteria:
2/3 EDG is manually started.
-- AND / OR --
At the discretion of the Lead Examiner.
Page 17 of 25 Event Nine - Emergency Depressurization on Level Trigger Position Crew Actions or Behavior 6
7 SIMULATOR OPERATOR:
At the discretion of the Lead examiner, activate TRIGGER 6, which increases the size of the Recirc Loop leak in the Drywell.
At the discretion of the Lead examiner, activate TRIGGER 7, which further increases the size of the Recirc Loop leak in the Drywell.
If the crew decides to start HPCI, it will be degraded.
ROLE PLAY:
EO sent to cutout demin beds, wait 3 min, cutout demin beds as necessary (using Instructor Station) and report the following:
Condensate demin beds have been cutout.
Acknowledge other requests and delay as necessary.
ATC Starts SBLC for level control as directed.
TEAM Determines/announces Drywell pressure rapidly rising.
Determines/announces RPV level is dropping.
CRS Directs starting SBLC for level control Determines insufficient high pressure feed is available, then performs/directs:
Inhibiting ADS before -59 inches. (RPV-1.5)
Verifying at least two low pressure injection systems available.
Waiting until RPV level drops to TAF.
Verifying any low pressure system lined up with a pump running.
BOP Inhibits ADS as directed. (RPV-1.5)
CRS Enters DEOP 0200-01, PRIMARY CONTAINMENT CONTROL, when PC/P reaches 2 psig and performs/directs:
Monitoring of PC/P.
Initiation of torus sprays before PC/P of 9 psig.
When PC/P is above 9 psig or before DW/T reaches 281°F:
Verification of DSIL.
Tripping of Recirc pumps.
Tripping of DW coolers.
Initiation of DW sprays.
Monitoring of DW/T. (D/W sprays may be initiated for temp control)
Monitoring of SP/T and initiation of torus cooling.
Monitors SP/L.
Verifies initiation of drywell and torus H2/O2 monitors.
Orders Torus / DW Spray secured before Torus / DW pressure drops to 0 psig
Page 18 of 25 Event Nine - Emergency Depressurization on Level Trigger Position Crew Actions or Behavior BOP Performs DEOP 0200-01 actions as directed:
Monitors PC/P Initiates torus sprays and drywell sprays per Hard Card as directed.
Monitors DW/T.
Monitors SP/T and initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed.
Monitors SP/L.
Verifies initiation of drywell and torus H2/O2 monitors.
Secures Torus / DW Spray before Torus / DW pressure drops to 0 psig CRS If the RPV level trend is not reversible with an RPV injection source lined up, with a pump running, with RPV level between TAF and the MSCRWL directs entering DEOP 0400-02, Emergency Depressurization, and directs:
Verification that SP/L >6 feet.
Directs Initiation of IC to max flow.
Opening all ADS valves. (RPV-1.1)
Verification all relief valves are open.
Time RPV level reach TAF: __________________
Time entered DEOP 400-2: __________________
Time all 5 ERVs open: __________________
BOP Performs DEOP 0400-02, EMERGENCY DEPRESSURIZATION, as directed:
Verifies SP/L >6 feet.
Initiates IC to max flow by placing the 2-1301-3 to OPEN.
Opens all ADS valves. (RPV-1.1)
Verifies all relief valves are open on back panel.
Reports when RPV level is restored above TAF.
30 SIMULATOR OPERATOR Insert TRIGGER 30 before going to freeze to reset the shielding constant.
Event 9 Completion Criteria:
RPV Water Level above TAF (-170/-143),
-- AND / OR --
At the discretion of the Lead Examiner.
Page 19 of 25 References PROCEDURE TITLE DAN 902-5 A-3 ROD DRIFT DAN 902-6 E-12 FEEDWATER REG STATION VIBRATION HI DAN 902-6 F-12 2A RFP VIBRATION HI DAN 902-8 F-11 ISOL PHASE BUS DUCT BLOWER TRIP DEOP 100 RPV CONTROL DEOP 200-01 PRIMARY CONTAINMENT CONTROL DEOP 400-2 EMERGENCY DEPRESSURIZATION DGA-07 UNEXPECTED REACTIVITY CHANGE DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DOA 0300-05 INOPERABLE OR FAILED CONTROL ROD DRIVES DOA 0300-12 MISPOSITIONED CONTROL ROD DOA 0300-01 CONTROL ROD DRIVE SYSTEM FAILURE DOA 3200-01 FEEDWATER SYSTEM HIGH VIBRATION DOP 2300-04 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM SHUTDOWN DOP 6700-20 480V CIRCUIT BREAKER TRIP DOP 7400-02 STATOR WATER COOLING PUMP CHANGEOVER OP-DR-103-102-1002 STRATEGIES FOR SUCCESSFUL TRANSIENT MITIGATION TS 3.1.3 CONTROL ROD OPERABILITY TS 3.3.6.1 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TS 3.5.1 ECCS - OPERATING OPERATOR AID #158 TECH SPEC / TRM / ODCM IMPLEMENTATION AID
Page 20 of 25 Simulator Scenario Review Checklist ILT-N-2 Quantitative Attributes 5
Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 4 Abnormal events (2 to 4) 2 Major transients (1 to 2) 2 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 3 Crew critical tasks (2 to 3)
Page 21 of 25 CAEP Files
- CAEP file for ILT-N-2
- ILT 2021-302 (20-2)
- Written by ADK
- 06/21
- INITIAL CONDITIONS ####
- Prevents 2/3 EDG from auto starting, can be manually started imf t13 set rmkshldrbvent = 100.0
- EVENT TRIGGERS ####
trgset 1 "0" ior rdipfake2 (1) 50 imf rdppbtrp (1 10:00)
- Event Trigger 2 causes a spurious initiation of HPCI trgset 2 "0"l2 imf hpinit (2)l2
- Event Trigger 3 causes Rod E-06 to drift in trgset 3 "0"l2 imf rode06di (3)l2
- Event Trigger 4 trips the 2A Bus Duct Blower trgset 4 "0"l4 ior mgddbatr (4) tripl4 ior mgldbaat (4) onl4 imf ser1671 (4) onl4
- Event Trigger 5 activates when Mode Switch taken to SHUTDOWN to cause a Recirc leak and degrade HPCI trgset 5 "rpdmode4"l6 imf f41 (5 2:00) 1.0 2:00l6 imf hppmpdg (5) 1.0l6
- Event Trigger 6 will increase the size of the leak to get above 9 psig in the Drywell trgset 6 "0"l6 trg 6 "mmf f41 2.0"l6
- Event Trigger 7 will increase the size of the leak to lower level faster trgset 7 "0"l8 trg 7 "mmf f41 5.0"l8
- Event Trigger 8 closes the 2-0301-25 valve trgset 8 "0"l8 irf rd25pos (8) 0.0l8
- Event Trigger 9 will clear the override for the 2B CRD pump amps trgset 9 "hwrdspmpop(2)"l10 trg 9 "dor rdipfake2"l10
- Event Trigger 10 will clear the Bus Duct Blower overrides when the 2A Bus Duct Blower C/S is taken to PTL trgset 10 "hwmgddbalc(1)"l10 trg 10 "dor mgldbaat"l10
- Event Trigger 11 works with Trigger 10 trgset 11 "et_array(10)"l12 trg 11 "dmf ser1671"l12
- Event Trigger 12 deletes the Rod Drift malfuction
Page 22 of 25 trgset 12 "0"l12 trg 12 "dmf rode06di"l12
- Event Trigger 28 sets gain for all 6 APRMs.
trgset 28 "0"l14 trg 28 "irf niagainf true"l14
- Event Trigger 30 resets shielding constant that was changed before the scenario trgset 30 "0"l14 trg 30 "set rmkshldrbvent = 1300.0"l14
- END ####
- CAEP file for ILT-N-2 SUPPLEMENTAL
- ILT 2021-302 (20-2)
- Written by ADK
- 06/21
- The following drives up the following vibration alarms:
- 2A RFP after 40 seconds
- FRWV Station after 60 seconds
- 2B RFP after 65 seconds imf ser1363 onl40 imf ser1361 onl80 imf ser1397 onl100 ior fwl32061 off ior fwl32062 off
- The following cycles MO 3206A & B valve positions to simulate FW Sys Hi Vibes.
set fwv3206a(1) = 0.4 set fwv3206a(2) = 0.4 set fwv3206a(1) = 0.6l3 set fwv3206a(2) = 0.6l3 set fwv3206a(1) = 0.4l6 set fwv3206a(2) = 0.4l6 set fwv3206a(1) = 0.6l9 set fwv3206a(2) = 0.6l9 set fwv3206a(1) = 0.4l12 set fwv3206a(2) = 0.4l12 set fwv3206a(1) = 0.6l15 set fwv3206a(2) = 0.6l15 set fwv3206a(1) = 0.4l18 set fwv3206a(2) = 0.4l18 set fwv3206a(1) = 0.6l21 set fwv3206a(2) = 0.6l21 set fwv3206a(1) = 0.4l24 set fwv3206a(2) = 0.4l24 set fwv3206a(1) = 0.6l27 set fwv3206a(2) = 0.6l27 set fwv3206a(1) = 0.4l30 set fwv3206a(2) = 0.4l30 set fwv3206a(1) = 0.6l33 set fwv3206a(2) = 0.6l33 set fwv3206a(1) = 0.4l36
Page 23 of 25 set fwv3206a(2) = 0.4l36 set fwv3206a(1) = 0.6l39 set fwv3206a(2) = 0.6l39 set fwv3206a(1) = 0.4l42 set fwv3206a(2) = 0.4l42 set fwv3206a(1) = 0.6l45 set fwv3206a(2) = 0.6l45 set fwv3206a(1) = 0.4l48 set fwv3206a(2) = 0.4l48 set fwv3206a(1) = 0.6l51 set fwv3206a(2) = 0.6l51 set fwv3206a(1) = 0.4l54 set fwv3206a(2) = 0.4l54 set fwv3206a(1) = 0.6l57 set fwv3206a(2) = 0.6l57 set fwv3206a(1) = 0.4l60 set fwv3206a(2) = 0.4l60 set fwv3206a(1) = 0.65l63 set fwv3206a(2) = 0.65l63 set fwv3206a(1) = 0.25l66 set fwv3206a(2) = 0.25l66 set fwv3206a(1) = 0.65l69 set fwv3206a(2) = 0.65l69 set fwv3206a(1) = 0.25l72 set fwv3206a(2) = 0.25l72 set fwv3206a(1) = 0.65l75 set fwv3206a(2) = 0.65l75 set fwv3206a(1) = 0.25l78 set fwv3206a(2) = 0.25l78 set fwv3206a(1) = 0.65l81 set fwv3206a(2) = 0.65l81 set fwv3206a(1) = 0.25l84 set fwv3206a(2) = 0.25l84 set fwv3206a(1) = 0.65l87 set fwv3206a(2) = 0.65l87 set fwv3206a(1) = 0.25l90 set fwv3206a(2) = 0.25l90 set fwv3206a(1) = 0.65l93 set fwv3206a(2) = 0.65l93 set fwv3206a(1) = 0.25l96 set fwv3206a(2) = 0.25l96 set fwv3206a(1) = 0.65l99 set fwv3206a(2) = 0.65l99 set fwv3206a(1) = 0.25l102 set fwv3206a(2) = 0.25l102 set fwv3206a(1) = 0.65l105 set fwv3206a(2) = 0.65l105 set fwv3206a(1) = 0.25l108 set fwv3206a(2) = 0.25l108 set fwv3206a(1) = 0.65l111 set fwv3206a(2) = 0.65l111
Page 24 of 25 set fwv3206a(1) = 0.25l114 set fwv3206a(2) = 0.25l114 set fwv3206a(1) = 0.65l117 set fwv3206a(2) = 0.65l117 set fwv3206a(1) = 0.25l120 set fwv3206a(2) = 0.25l120 set fwv3206a(1) = 0.7l123 set fwv3206a(2) = 0.7l123 set fwv3206a(1) = 0.3l126 set fwv3206a(2) = 0.3l126 set fwv3206a(1) = 0.7l129 set fwv3206a(2) = 0.7l129 set fwv3206a(1) = 0.3l132 set fwv3206a(2) = 0.3l132 set fwv3206a(1) = 0.7l135 set fwv3206a(2) = 0.7l135 set fwv3206a(1) = 0.3l138 set fwv3206a(2) = 0.3l138 set fwv3206a(1) = 0.7l141 set fwv3206a(2) = 0.7l141 set fwv3206a(1) = 0.3l144 set fwv3206a(2) = 0.3l144 set fwv3206a(1) = 0.7l147 set fwv3206a(2) = 0.7l147 set fwv3206a(1) = 0.3l150 set fwv3206a(2) = 0.3l150 set fwv3206a(1) = 0.7l153 set fwv3206a(2) = 0.7l153 set fwv3206a(1) = 0.3l156 set fwv3206a(2) = 0.3l156 set fwv3206a(1) = 0.7l159 set fwv3206a(2) = 0.7l159 set fwv3206a(1) = 0.3l162 set fwv3206a(2) = 0.3l162 set fwv3206a(1) = 0.7l165 set fwv3206a(2) = 0.7l165 set fwv3206a(1) = 0.3l168 set fwv3206a(2) = 0.3l168 set fwv3206a(1) = 0.7l171 set fwv3206a(2) = 0.7l171 set fwv3206a(1) = 0.25l174 set fwv3206a(2) = 0.25l174 set fwv3206a(1) = 0.75l177 set fwv3206a(2) = 0.75l177 set fwv3206a(1) = 0.25l180 set fwv3206a(2) = 0.25l180 set fwv3206a(1) = 0.75l183 set fwv3206a(2) = 0.75l183
- END ####
Page 25 of 25 Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 1 at 80% power, Leading Thermal Limit: MFLCPR @ 0.881 Action limit: 0.980 Equipment Unavailable: 2C RFP Protected Equipment: 2A and 2B RFP, 2A FPC Unit 3 is at 100% power.
Leading Thermal Limit: MFLCPR @ 0.883 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: 3A FPC Current Action Statements None LCO Started: None LCO Expires: None Cause: N/A Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
Swap Stator Water Cooling Pumps
- Shift 3 Activities ****
TURNOVER:
2C RFP is out of service for motor replacement. It is not scheduled to return for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 2A Stator Water Cooling Pump is scheduled for maintenance later in shift. Per DOP 7400-02, STATOR COOLING WATER SYSTEM PUMP CHANGEOVER, swap stator water cooling pumps.
Dresden Generating Station ILT-N-3 TRANSFER MCC 28-7/29-7 FROM BUS 28 TO BUS 29 RAISE POWER WITH RODS CRD FCV FAILS CLOSED CIRC WATER PUMP TRIP RFP SWAP DUE TO OIL LEAK ERV SPURIOUS OPEN LOSS OF ALL SERVICE WATER - MANUAL SCRAM HYDRAULIC ATWS Rev. 00 06/21 Developed By:
Exam Author Date Approved By:
Facility Representative Date
Page 2 of 26 Scenario Outline Facility:
Dresden Generating Station Scenario No.:
2021-302 ILT-N-3 Op-Test No.: 2021-302 Examiners Operators
/ crew position
/ ATC
/ BOP
/ CRS Initial Conditions:
Unit 2 is Mode 2. DGP 01-01 is in progress.
Turnover:
Transfer MCC 28-7/29-7 from Bus 28 to Bus 29.
TS LCO 3.5.1.E - For LPCI Injection valves powered from reserve power supply.
Critical Tasks:
RPV-5.1 - With a reactor scram required and the reactor not shutdown, take action per DEOP 400-5, Failure to Scram, to reduce power by inserting control rods.
RPV-5 Per DEOP 400-5, Failure to Scram, with a reactor scram required, the reactor not shutdown, and the automatic ADS timer initiated, inhibit ADS before an automatic actuation occurs.
Event No.
Malf.
No.
Event Type*
Event Description #
1 NONE N
BOP (Pre) - AUX POWER - Transfer MCC 28-7/29-7 from Bus 28 to Bus 29 2
NONE R
ATC REACTIVITY - Raise Power with Rods 3
RDFCVFCL C/T ATC CRS (New) - CRD - Flow Control valve Fails Closed 4
HP6 HP7 C
BOP (New) - CIRC WATER - Pump Trip on Overcurrent 5
NONE C
ATC (New) - FEEDWATER - RFP Swap due to Oil Leak 6
ADS3ESD C/T BOP CRS (Pre) - MAIN STEAM - ERV Spurious Open 7
Q31 M
ALL (New) - Manual Scram - Loss of all Service Water 8
RDHLVFPA RDHLDEGA RDHLVFPB RDHLDEGB M
ALL (Pre) - ATWS - Hydraulic, ARI Unsuccessful / Team Inserts Rods By Manually Drive Rods
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams Scenario Objective:
Evaluate the Teams ability to operate the plant with a Hydraulic ATWS.
Scenario Initial Conditions
- 1. Unit 2 is at ~8% power.
- 2. The following equipment is OOS:
- a.
None
- 3. LCOs:
- a.
T.S. 3.5.1 Cond E for LPCI components being powered from Bus 28.
Page 3 of 26 Scenario Sequence Event #
Description 1
AUX POWER - Transfer MCC 28-7/29-7 from Bus 28 to Bus 29:
The BOP will transfer power to MCC 28-7/29-7 from Bus 28 to Bus 29 2
REACTIVITY - Raise Power with Rods:
The team will continue raising reactor power by withdrawing control rods until 2 main turbine bypass valves are fully opened.
3 CRD - Flow Control Valve Fails Closed:
The CRD Flow Control Valve fails closed. This causes the controller demand to the CRD FCV to fail high, but all indications are the valve is closed. If the team does not recognize the failure quickly and restore CRD cooling flow, the ROD DRIVE TEMP HI alarm comes up. The Team directs in-plant operators to swap CRD flow control valves and restores CRD flow control to normal.
4 CIRC WATER - Pump Trip on Overcurrent:
The 2A Circulating water pump trips on overload. The Team starts the 2B Circulating water pump.
5 FEEDWATER - RFP Swap due to Oil Leak:
The Team receives a report from the field that 2A RFP has an oil leak. The Team starts 2B or 2C RFP and secures 2A RFP.
6 MAIN STEAM - ERV Spurious Open:
2C ERV setpoint will drift causing 2C ERV to open. The BOP will attempt to close the ERV from the MCR per DOA 0250-01, Relief Valve Failure. The ERV will close after cycling the Inhibit switch.
7 Manual Scram - Loss of all Service Water:
An unisolable Cribhouse Service Water leak downstream of the Service Water strainers occurs. The Team will perform a manual scram due to the loss of cooling to vital plant equipment.
8 ATWS - Hydraulic, ARI Unsuccessful / Team Inserts Rods By Manually Drive Rods:
Following the scram, the control rods will not fully insert. ARI will also fail to insert the control rods due to a hydraulic lock. The team will ultimately be successful in achieving reactor shutdown by driving control rods and performing repeated scram resets.
Event One - Transfer MCC 28-7/29-7 from Bus 28 to Bus 29 The BOP will transfer MCC 28-7/29-7 from Bus 28 to Bus 29.
Malfunctions required: 0 None Success Path:
The team transfers MCC 28-7/29-7 from Bus 28 to Bus 29.
Event Two - Raise Power with Rods The ATC will raise power by withdrawing control rods per DGP 01-01, D0P 0400-01, and DGP 03-04.
Malfunctions required: 0 None Success Path:
Control rods pulled per applicable procedures.
Page 4 of 26 Event Three - CRD Flow Control Fails Closed The CRD Flow Control valve fails closed.
Malfunctions required: 1 (CRD Flow Control Valve fails Closed)
Success Path:
Directs in-plant operators to swap the CRD Flow Control valves.
Determines Technical Specifications requirements.
Event Four - Circulating Water Pump Trip The crew should recognize and respond to Circulating water pump 2A tripping on overload.
Malfunctions required: 1 (Circulating Water Pump trip)
Success Path:
Start 2B Circulating Water Pump.
Event Five - Swap RFP Due to Oil Leak Report from the field of an oil leak on 2B RFP.
Malfunctions required: 1 (2B RFP oil leak)
Success Path:
The Team starts 2C RFP and secures 2B RFP.
Event Six - ERV Spurious Open 2C ERV will spuriously open.
Malfunctions required: 1 (2C ERV Spuriously Opens)
Success Path:
Attempts to close 2C ERV.
Performs actions of DOA 0250-01, Relief Valve Failure to close ERV.
Determines Technical Specifications requirements.
Event Five - Loss of Service Water / Manual Scram Inserts an unisolable Cribhouse Service Water leak downstream of the strainers.
Malfunctions required: 1 (Service Water Leak)
Success Path:
Performs a manual scram per DOA 3900-01, Loss of Cooling by Service Water System, and DGP 02-03, Reactor Scram.
Page 5 of 26 Event Eight - Hydraulic ATWS After the reactor automatically scrams, all rods do not insert. ARI is unsuccessful.
Malfunctions required: 1 (Hydraulic ATWS)
Success Path:
Inserts control rods by manually driving rods and performing repeated scrams.
Page 6 of 26 PRE-SCENARIO ACTIVITIES 1
If applicable, conduct pre-scenario activities in accordance with TQ-AA-155-J040, SIMULATOR EXAMINATION BRIEFING.
- a. Direct the crew to perform their briefs prior to entering the simulator.
- b. Provide the crew with a copy of DGP 01-01, UNIT STARTUP, marked up and completed through G.54, and also step G.58 signed off as complete.
- c.
Provide the crew with a copy of the REMA and Control Rod Move Sheets.
- d. Crew directed to continue with plant startup, per Shift Manager.
- e. Rod moves have been completed up to and including Step 15. Rod J-05 is the next rod to be moved.
- f.
Provide the crew with a marked up partial copy of DOP 6700-18, BUS 28 OUTAGE; only applicable sections of the procedure are provided to the crew with the Prerequisites, Precautions, and Limitations and Actions marked off.
2 Crew directed to return MCC 28-7/29-7 to normal power supply Bus 29 per DOP 6700-18.
3 Simulator Setup (the following steps can be done in any logical order):
- a.
Initialize simulator in an ~7% power IC. (IC 303 used for validation)
- b. Cut in/out Cond Demins as needed, to maintain DP within limits.
- c.
Ensure running Condensate pump amps within limits.
4 Verify the following simulator conditions:
- a.
Verify Reactor Power ~7%, adjust rods or Recirc as appropriate.
- b. Verify MCC 28-7/29-7 is powered from Bus 28.
- c.
Verify 2A and 2C Circ Water Pumps are running.
- d. Verify 2A RFP is running.
- e.
Verify IRMs in FAST Speed.
5 Run Pump_Sumps.cae 6
Run the initial setup CAEP file: 20-1 (2021-302) ILT-N-3.cae 7
Place the following equipment out of service:
- a. 2B RFP
- b. 2C RFP on Bus 21 8
Place protected pathways on the following equipment:
- a. 2A RFP
- b. 2C RFP on Bus 22 9
Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Required Actions o
Optional Actions NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
Page 7 of 26 Event One - Transfer MCC 28-7/29-7 from Bus 28 to Bus 29 Trigger Position Crew Actions or Behavior 28 SIMULATOR OPERATOR ROLE PLAY:
If requested to set gains to 1, (wait 3 min) activate TRIGGER 28, then report gains set to 1. (This trigger can be triggered OFF, then back ON to adjust gains more than once).
SIMULATOR OPERATOR ROLE PLAY:
As Shift Manager:
Acknowledge report that the Team is ready to transfer MCC 28-7/29-7 from Bus 28 to Bus 29.
Acknowledge report that the transfer is complete, and that the Tech Spec LCO has been exited.
CRS Notifies Shift Manager that the Team is ready to transfer MCC 28-7/29-7 from Bus 28 to Bus 29.
Directs NSO to transfer MCC 28-7/29-7 from Bus 28 to Bus 29.
BOP Performs DOP 6700-18, BUS 28 OUTAGE, steps G.5.d through G.5.f:
Hold MCC 29-7/28-7 FEED from BUS 28 in TRIP.
Close MCC 29-7/28-7 FEED from BUS 29.
Release MCC 29-7/28-7 FEED FROM BUS 28.
ATC Assists as directed.
CRS Declares both LPCI subsystems operable and notifies Shift Manager that the Team completed transferring MCC 28-7/29-7 from Bus 28 to Bus 29.
Event 1 Completion Criteria:
MCC 28-7/29-7 transferred from Bus 28 to Bus 29,
-- AND/OR --
At the discretion of the Lead Examiner.
Page 8 of 26 Event Two - Continue raising power by control rod withdrawal Trigger Position Crew Actions or Behavior CRS Directs pulling control rods.
Reviews REMA.
Designates second verifier.
Directs NSO to pulls rods.
ATC Performs the following actions per DOP 0400-01, REACTOR MANUAL CONTROL SYSTEM OPERATION, and DGP 03-04, CONTROL ROD MOVEMENTS, as directed Verifies the following prior to moving first control rod:
Control rod selected on the select matrix is correct rod.
Verifies rod pattern States the following:
Controlling document Step and array RWM status CRD selected Initial position Movement (single or continuous)
Direction Target Position Verifies the following on subsequent control rods:
Control rod selected on the select matrix is correct rod.
States the following:
CRD selected Initial position Movement (single or continuous)
Direction Target Position Second Verification requirements satisfied.
Rod Out Permit light is illuminated.
Drive water pressure at nominal 260 psid.
Withdraws rods as follows:
Moves Rod Out Notch Override (RONOR) Switch to NOTCH OVERRIDE position (use of RONOR switch is optional) and the Rod Movement Control switch to ROD OUT.
Verifies ON light illuminated and proper Control Rod Timer operation.
Releases switches before target position is reached. (If rod is being withdrawn to 48, then switches are held to 48 with coupling check)
Verifies rod settles to target position and proper response of nuclear instrumentation.
Page 9 of 26 Event Two - Continue raising power by control rod withdrawal Trigger Position Crew Actions or Behavior BOP Performs second verification checks.
For first rod in a step:
Verifies correct control rod pattern Verifies correct step and array.
Compares CRD and intended movement with controlling document: point to, touch, or mark controlling document.
State the following:
Repeat back and agree with intended movement For all rods moved:
Verifies correct control rod selected.
Verifies planned control rod motion is correct.
Immediately notify the NSO of errors during rod motion.
Verifies control rod at target position.
Event 2 Completion Criteria:
Sufficient power increase,
-- AND/OR --
At the direction of the Lead Examiner.
Page 10 of 26 Event Three - CRD Flow Control Valve Fails Closed Trigger Position Crew Actions or Behavior 1
2 Simulator Operator:
At the discretion of the Lead Examiner, activate TRIGGER 1, which causes the CRD Flow Control Valve to fail closed.
After CRD FLOW CONTLR FIC 340-1 is in manual mode AND controller demand is set to minimum and at the discretion of the Lead Examiner, activate TRIGGER 2, which simulates swapping CRD FCVs by deleting the failed closed malfunction.
Role Play:
EO to check CRD FCV and/or take local manual control, wait 2 min, then report the following:
AO 2-0302-6B, 2B CRD FCV, is in-service, appears closed and its positioner is leaking air. I cannot control it locally.
EO to check CRD FCV operation: See below for proper response.
EO to check CRD system flow locally (FI 2-302-56), wait 1 min and report the following:
CRD system flow indicates (same as control room meter).
EO to check drive water flow locally (FI 2-302-64), wait 1 min and report the following:
CRD drive water flow indicates (same as control room meter).
EO to check cooling water flow locally (FI 2-302-65), wait 1 min and report the following:
CRD cooling water flow indicates (same as control room meter).
EO to check CRD pumps locally, wait 1 min and report the following:
CRD Pumps appear to be operating normally.
EO to check RVWLIS flow locally, wait 1 min and report the following if FCV open:
RVWLIS Flow is 0.4 gallons/hour.
Respond as groups notified.
ATC From panel monitoring or alarm 902-5 F-3, ROD DRIVE HI TEMP, notices and announces loss of CRD system flow.
Diagnoses failure of the CRD Flow Control Valve.
CRS Directs entering and performing actions of DOA 0300-01, CONTROL ROD DRIVE SYSTEM FAILURE.
Notifies Shift Manager and IMD of CRD Flow Controller failure.
References Technical Specifications and determines the following is required:
TRM 3.3.h, Condition A, restore inoperable RVWLIS Backfill System Lines to OPERABLE status within 7 days. (can be exited when the CRD FCV is restored.)
ATC Performs DOA 0300-01 actions as directed by the CRS:
Attempts to manually control AO 2-0302-6B, 2B CRD FCV, by placing FIC 2-340-1, CRD FLOW CONTROLLER, in MANUAL and adjusting flow to between 40 and 60 gpm.
Continues performing DOA 0300-01 actions as directed by the CRS:
Directs the EO to transfer the CRD FCVs per DOP 0300-03, Control Rod Drive System Flow Control Valve Transfer.
Role Play:
EO performing DOP 0300-03, CONTROL ROD DRIVE SYSTEM FLOW CONTROL VALVE TRANSFER, wait 2 min and report the following:
Im ready for you to perform step G.6 of DOP 0300-03.
Page 11 of 26 Event Three - CRD Flow Control Valve Fails Closed Trigger Position Crew Actions or Behavior ATC At Panel 902-5, verifies CRD FLOW CONTLR FIC 340-1 is in manual mode AND controller demand is set to minimum.
Informs EO step G.6 of DOP 0300-03 is completed.
Role Play:
EO performing DOP 0300-03 wait 2 min and report the following:
Im ready for you to perform step G.10 of DOP 0300-03.
ATC Directs EO to slowly close 2-0301-41B, U2 CRD SYS B FCV OUTLET VLV.
Role Play:
EO to NSO: wait 2 min, and report the following:
2-0301-41B, U2 CRD SYS B FCV OUTLET VLV is closed and the 2A CRD FCV is operating normally.
ATC Raises CRD flow until normal system flow rate is achieved.
Returns CRD Flow Control to AUTOMATIC.
BOP May obtain CRD temperatures on the back panels.
Event 3 Completion Criteria:
Team has transferred CRD Flow Control valves and restored normal flow control,
-- AND/OR --
At the direction of the Lead Examiner.
Page 12 of 26 Event Four - Circulating Water Pump Trip Trigger Position Crew Actions or Behavior 3
Simulator Operator:
At the discretion of the Lead Examiner, activate TRIGGER 3, which trips 2A Circulating Water pump.
Role Play:
EO sent to 2A Circulating Water pump breaker, wait 3 min then report the following 2A Circulating Water pump breaker is open with an overcurrent target up.
EO sent to 2A Circulating Water pump, wait 3 min and then report the following:
2A Circulating Water pump motor is hot to the touch.
If asked about the status of the 2A Circ Water Pump Discharge Valve, report the following:
The 2A Circulating Water pump discharge valve is closed EO sent to check 2B Circulating Water pump operation, wait 2 min and then report the following:
2B Circulating Water pump is operating normally.
EO sent to check Cribhouse bar racks and traveling screens, wait 3 min and then report the following:
The Cribhouse bar racks and traveling screens are clear.
BOP Performs the following actions per DAN 902-7 A-15, CIRC WTR PP TRIP, DOA 4400-01, CIRCULATING WATER SYSTEM FAILURE, and DOA 6500-10, 4KV CIRCUIT BREAKER TRIP, as directed:
Starts 2B Circulating Water pump. (immediate action)
Verifies condenser vacuum returning to normal.
Verifies 2A Circulating Water pump discharge valve closes.
Sends EO to check 2A Circulating Water pump breaker and operation of 2B Circulating Water pump.
Places 2A Circulating Water pump control switch in PTL.
Verifies Circulating Water Flow reversal valves lined up normally.
May send EO to check Cribhouse bar racks and traveling screens.
CRS Enters and directs performance of DOA 4400-01 and DOA 6500-10.
Notifies the Shift Manager and EMD.
ATC Monitors panels and assists as directed.
Event 4 Completion Criteria:
2B Circulating Water pump started,
-- AND/OR --
At the direction of the Lead Examiner.
Page 13 of 26 Event Five - RFP Swap due to Oil Leak Trigger Position Actions or Behavior SIMULATOR OPERATOR:
Call the control room as the U-2 EO and report, While I was on rounds, I found 2A RFP has an oil leak on a line to the speed changer. It cannot be stopped.
If asked the oil is contained on the bed plate and I plugged the drain before the oil reached it.
If asked to quantify the leak, I cant tell.
If asked, The oil level is below the sight glass.
If asked, Zinc injection is lined up to 2A RFP.
If asked, 2C RFP has been checked and is ready to start.
If asked following start, 2C RFP is operating normally.
EO to verify 2A RFP is at rest, wait 1 min and ensure 2A RFP RECIRC VLV PCV 2-3201B is closed, then report the following:
2A RFP is at rest.
Acknowledge request to perform procedural steps for 2C and 2A RFPs. After a two minutes, report that the steps are completed.
If asked after 2A RFP Aux Oil PP is placed in PTL: Report, the oil leak on 2A RFP has stopped.
ATC Acknowledges report from the field and relays it to the CRS.
CRS May enter DOA 0600-01, TRANSIENT LEVEL CONTROL.
Directs ATC to start 2C RFP and secure 2A RFP.
ATC Starts 2C RFP per DOA 0600-01, OR DOP 3200-03, STARTUP OF SECOND OR THIRD REACTOR FEED PUMP OR SHIFTING TO ALTERNATE REACTOR FEED PUMP.
Places RFPs Standby Selector switch, STBY PP SELECT in OFF position.
Closes MO 2-3201C, 2C C PP DISCH VLV.
Opens 2C RFP RECIRC VLV PCV 2-3201C by placing control switch in OPEN.
o Announces 902-6 G-9, RFP RECIRC VLV OPEN Verifies reactor water level is stable.
Verifies sufficient system pressures.
If previously closed, places MO 2-3201C control switch to OPEN position.
Starts 2C RFP.
Verifies reactor water level is stable.
Takes the 2C AUX OIL PP switch to TRIP.
Take the 2C AUX OIL PP switch to CLOSE and verifies amber AUTO TRIP light is lit.
WHEN MO 2-3201C is fully open, THEN places 2C RFP RECIRC VLV PCV 2-3201C control switch in AUTO. (902-6 G-9, RFP RECIRC VLV OPEN, will clear when valve is closed)
Directs EO to perform checks on 2C RFP.
Page 14 of 26 Event Five - RFP Swap due to Oil Leak Trigger Position Actions or Behavior ATC Secures 2A RFP per DOP 3200-05, Reactor Feed Pump Shutdown.
Places RFPs standby selector switch, STBY PP SELECT, in OFF.
Verifies the 2A AUX OIL PP control switch in AUTO.
Opens 2A RFP recirculation valve, by placing 2A RFP RECIRC VLV PCV 2-3201A control switch in OPEN position.
o Announces 902-6 G-9, RFP RECIRC VLV OPEN Verifies reactor water level is stable.
Closes MO 2-3201A, 2A RFP DISCH VLV.
Verifies reactor water level remains stable.
Stops 2A RFP.
As the RFP slows down, verifies the associated auxiliary oil pump automatically starts.
Close 2A RFP recirculation valve, by placing 2A RFP RECIRC VLV control switch in AUTO position.
Direct an EO to verify the 2A RFP has come to rest.
WHEN 2A RFP has come to rest, THEN may open MO 2-3201A, 2A RFP DISCH VLV.
Directs EO to perform remaining in plant steps for securing 2A RFP.
CRS Directs 2A RFP Aux Oil PP secured to stop leak.
ATC Places 2A RFP Aux Oil PP in PTL.
Event 5 Completion Criteria:
2C RFP started and 2A RFP secured
-- AND/OR --
At the direction of the Lead Examiner.
Page 15 of 26 Event Six - ERV Spurious Open Trigger Position Crew Actions or Behavior 4
5 SIMULATOR OPERATOR:
At the discretion of the Floor Instructor / Lead Evaluator, activate TRIGGER 4, which causes 2C ERV to spuriously open due to an electrical failure.
Verify TRIGGER 5 activates when INHIBIT Switch is taken to INHIBIT.
10 ROLE PLAY:
EO to pull control power fuses for 2C ERV, wait 3 min, activate TRIGGER 10 to remove control power fuses, and report the following via phone:
I have pulled the 2C ERV fuses.
QNE to evaluate core parameters, wait 2 min, and report the following:
Core parameters are within limits.
BOP Announces and references DAN 902-3 D-13, 2C ELECTROMATIC RELIEF VALVE OPEN.
Enters DOA 0250-01, RELIEF VALVE FAILURE, and performs the following immediate actions:
Places 2C ERV control switch to OFF.
Verifies Reactor Pressure is not high enough for ERV to be open.
CRS Enters DOA 0250-01 and directs actions.
Enters and directs actions of DGA-7, UNEXPECTED REACTIVITY CHANGE.
ATC Performs a 5 Panel Update and informs the Team of power, pressure, level, & drywell pressure.
Performs actions of DGA-7 as directed:
Contacts QNE Runs OD-20 BOP Determines that 2C ERV is still open and performs subsequent actions of DOA 0250-01:
Cycles 2C ERV control switch to MAN and OFF twice.
Cycles ADS INHIBIT switch from NORMAL to INHIBIT to NORMAL several times (ERV will close).
May Direct 2C ERV control power fuses pulled.
Monitors Turbine Bypass Valve Operation.
May check hydrogen addition operation.
Resets the acoustic monitor (On Back Panels).
May initiate Max Torus Cooling.
CRS May enter DEOP 0200-01, PRIMARY CONTAINMENT CONTROL, due to Torus Temp > 95oF.
Declares 2C ERV inoperable.
Determines following Technical Specifications apply:
3.4.3, Safety and Relief Valves, Condition A.1: Restore the relief valve to OPERABLE status within 14 days.
3.6.1.8, Suppression Chamber-to-Drywell Vacuum Breaker, SR 3.6.1.8.2: Perform a functional test of each required vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.5.1, ECCS, RPV, Water Inventory Control, and IC System, Condition H1: Restore ADS valve to operable status within 14 days.
3.3.6.3, Relief Valve Instrumentation, Function 2, Condition A1: Restore channel to OPERABLE status in 14 days.
3.6.1.6, Condition A.1: Restore low set relief valve to OPERABLE status in 14 days.
Page 16 of 26 Event Six - ERV Spurious Open Trigger Position Crew Actions or Behavior Event 6 Completion Criteria:
2C ERV closed AND, Tech Specs have been addressed,
-- AND/OR --
At the discretion of the Floor Instructor/Lead Evaluator.
Page 17 of 26 Event Seven - Loss of Service Water - Manual Scram Trigger Position Crew Actions or Behavior 6
SIMULATOR OPERATOR:
At the discretion of the Lead Examiner, activate TRIGGER 6, which Inserts an unisolable Cribhouse Service Water leak downstream of the strainers.
FLOOR INSTRUCTOR When 2/3 DFP starts, make an update that the XL3 is alarming and provide the crew a copy of the XL3 handout.
ROLE PLAY EO to Cribhouse, wait 2 min and report the following:
There is a very large leak in the Cribhouse from the Service Water System downstream of the strainers.
If asked, the leak cannot be isolated.
EO to 2/3 Service Water Pump breaker, wait 2 min and report the following:
2/3 Service Water Pump breaker is tripped and has an overcurrent target up.
BOP Announces the following DANs (dependent on how long the crew waits to scram):
o 923-1 G-4, U2/3 DIESEL FIRE PP RUNNING o
923-1 D-3, U2/3 SERV WTR HDR PRESS LO o
902-3 G-2, AREA TEMP HI o
902-7 E-11, H2 SEAL OIL AND ALTERREX PNL TROUBLE o
902-7 A-5, TURBINE CONTROL MAJOR TROUBLE o
902-7 C-3, TURB STATOR COOLANT RUNBACK Dispatches EO to Cribhouse to check the Service Water System.
When directed, enters DOA 3900-01, LOSS OF COOLING BY SERVICE WATER SYSTEM.
Performs the following DAN actions and DOA 3900-01:
Starts 2A and 2/3 Service Water Pumps (2/3 SWP will trip on overcurrent).
If directed, enters DOA 0040-02, LOCALIZED FLOODING IN PLANT.
CRS Enters DOA 3900-01 and directs actions.
May enter DOA 0040-02.
May direct scram preparatory action per DGP 02-03, REACTOR SCRAM.
Determines Service Water System loss cannot be prevented and directs a Manual Scram.
ATC/BOP Performs scram preparatory actions per DGP 02-03 as directed.
o Inserts control rods to reduce FCL to <93%.
o Reduces power with Recirc flow to no lower than 56 Mlbm/hr core flow o
Starts the motor suction pump and turning gear oil pump.
o Trips hydrogen addition.
ATC Performs manual scram per DGP 02-03 as directed.
Event 7 Completion Criteria:
Reactor Scram directed,
-- AND/OR --
At the discretion of the Lead Examiner.
Page 18 of 26 Event Eight - Hydraulic ATWS Trigger Position Crew Actions or Behavior 7
8 9
CAEP SIMULATOR OPERATOR:
When directed to bypass Off Gas High Rad Isolations, wait 3 min, then insert TRIGGER 7, and inform the Floor Instructor.
When directed to pull ARI fuses, wait 3 min, then insert TRIGGER 8, and inform the Floor Instructor.
When directed to install RPS Scram Jumpers, wait 3 min, then insert TRIGGER 9, and inform the Floor Instructor.
When the crew resets the scram or as directed by floor instructor, run ClrHydLk.cae.
ATC Performs the following actions per DGP 02-03 as directed:
Initiates ARI / Determines ARI did not insert control rods.
Announces ATWS condition and RX power.
Places MSIV LO-LO LVL Bypass Keylocks in BYPASS.
Runs recirc pumps back to minimum.
Lowers FWLC setpoint to -40 inches. (not performed if <6%)
Trips recirc pumps. (If not already tripped)
Initiates one train of SBLC. (not performed if <6%)
Maintains RPV/L between -162 inches and the level lowered to. (+8 to +48 inches if < 6%)
If directed and RX power >6%, terminating and preventing all injection except boron and CRD until RPV level 35 inches.
If directed and RX power >6% AND Rx Lvl > TAF AND DW Press > 2 psig or an ERV is open AND Torus Temp > 110oF, terminating and preventing all injection except boron and CRD into the RPV.
o Verify FWRV controllers are in MAN and output is ZERO.
o Verify FWRVs indicate closed CRS Directs/performs actions of DEOP 0400-05, FAILURE TO SCRAM:
Placing ADS to inhibit. (RPV-5.4)
Placing Core Spray pumps in PTL.
Verifying required auto actions.
Placing MSIV LO-LO LVL Bypass Keylocks in BYPASS.
Installing of the jumpers for the Off Gas high Rad isolations.
If RX power >6%, terminating and preventing all injection except boron and CRD until RPV level 35 inches. (Not expected to be a Critical Task unless override conditions are met)
Holding RPV level between -162 inches and the level lowered to.
Stabilizing RPV pressure below 1060 psig.
Inserting control rods using Alternate Rod Insertion. (RPV-5.1)
Directs driving control rods.
Directs repeated scram/resets defeating RPS logic.
BOP Performs the following actions of DEOP 400-5 as directed:
Placing ADS to inhibit. (RPV-5.4)
Place Core Spray Pumps in PTL.
Page 19 of 26 Event Eight - Hydraulic ATWS Trigger Position Crew Actions or Behavior ATC / BOP Inserts control rods per DEOP 500-05, ALTERNATE INSERTION OF CONTROL RODS, as follows: (RPV-5.1)
Drives rods by:
Bypassing the RWM.
Maximizing CRD drive water pressure.
o Start a second CRD pump o
Open the CRD flow control valve (flow controller in manual) o Adjust drive water pressure using MO 2-0302-8 Uses either the ROD MOVEMENT CONTROL switch or the EMERG ROD IN position of the ROD OUT NOTCH OVERRIDE switch.
Performs repeated scram/resets defeating RPS logic:
Directs ARI fuses pulled if RPV level is lowered below - 59 in.
Directs scram jumpers installed.
Places SDV Hi Water Bypass in the BYPASS position.
Closes the SDV vent and drain valves.
Resets the scram.
Opens SDV Vent and Drain valves.
Manually scrams the reactor when the SDV is drained.
Repeats as necessary.
CRS Based on report that all control rods are inserted, exits DEOP 0400-05 and re-enters DEOP 0100.
Event 8 Completion Criteria:
All rods inserted AND, Team re-enters DEOP 100,
-- AND/OR --
At the discretion of the Lead Examiner.
Page 20 of 26 References PROCEDURE TITLE DAN 902-3 D-13 2C ELECTROMATIC RELIEF VLV OPEN DAN 902-5 F-3 ROD DRIVE TEMP HI DAN 902-6 G-9 RFP RECIRC VLV OPEN DAN 902-7 A-5 TURBINE CONTROL MAJOR TROUBLE DAN 902-7 A-15 CIRC WTR PP TRIP DAN 902-7 C-3 TURB STATOR COOLANT RUNBACK DAN 923-1 D-3 U2/3 SERV WTR HDR PRESS LO DAN 923-1 G-4 U2/3 DIESEL FIRE PP RUNNING DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DEOP 0400-05 FAILURE TO SCRAM DEOP 0500-05 ALTERNATE INSERTION OF CONTROL RODS DGA-07 UNEXPECTED REACTIVITY CHANGE DGP 01-01 REACTOR STARTUP DGP 02-03 REACTOR SCRAM DGO 03-04 CONTROL ROD MOVEMENTS DOA 0040-02 LOCALIZED FLOODING IN PLANT DOA 0250-01 RELIEF VALVE FAILURE DOA 0300-01 CONTROL ROD SYSTEM FAILURE DOA 0300-03 CONTROL ROD DRIVE SYSTEM FLOW CONTROL VALVE TRANSFER DOA 0600-01 TRANSIENT LEVEL CONTROL DOA 3900-01 LOSS OF COOLING BY SERVICE WATER SYSTEM DOA 4400-01 CIRCULATING WATER SYSTEM FAILURE DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM OPERATION DOP 3200-03 STARTUP OF SECOND OR THIRD REACTOR FEED PUMP DOP 3200-05 REACTOR FEED PUMP SHUTDOWN DOP 6700-18 BUS 28 OUTAGE TRM 3.3.h REACTOR VESSEL WATER LEVEL INSTRUMENTATION SYSTEM (RVWLIS) BACKFILL SYSTEM TS 3.3.6.3 RELIEF VALVE INSTRUMENTATION TS 3.4.3 SAFETY AND RELIEF VALVES TS 3.5.1 ECCS, RPV, WATER INVENTORY CONTROL, AND IC SYSTEM OPERATOR AID #158 TECH SPEC / TRM / ODCM IMPLEMENTATION AID
Page 21 of 26 Simulator Scenario Review Checklist ILT-N-3 Quantitative Attributes 6
Total malfunctions (5 to 8) 21 Malfunctions after EOP entry (1 to 2) 4 Abnormal events (2 to 4) 2 Major transients (1 to 2) 1 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 2 Crew critical tasks (2 to 3)
Page 22 of 26 CAEP Files
- CAEP file for ILT-N-3
- ILT 2021-302 (20-2)
- Written by ADK
- 06/21
- INITIAL CONDITIONS ####
- Inserts West SDV Hydraulic Lock imf rdhlvfpa 96.0l1 imf rdhldega 96.0l1
- Overrides nuisance alarms imf ser1695 off imf ser1663 off
- Inserts 2/3 Service Water pump overcurrent malfunction.
imf q23l2 imf q33l2
- 2C ERV binding malfunction set to 25%
imf ads3cbn 25.0l2
- EVENT TRIGGERS ####
- Event Trigger 2 deletes the CRD flow control valve fail closed.
trgset 2 "0"l4 trg 2 "dmf rdfcvfcl"l4
- Event Trigger 3 Trips 2A Circ Water pump.
trgset 3 "0"l4 imf hp6 (3)l6
- Event Trigger 4 causes 2C ERV setpoint to drift and fails open trgset 4 "0"l6 imf ads3csd (4) 75.0l6
- Event Trigger 5 deletes 2C ERV binding malfunction so valve will close when the Inhibit switch is taken to Inhibit trgset 5 ".not. hwadd304"l6 trg 5 "dmf ads3cbn"l8
- Event Trigger 6 inserts an unisolable Cribhouse Service Water leak.
trgset 6 "0"l8 imf q31 (6) 95.0 7:00 25.0l8
- Event Trigger 7 lifts Off-gas High Rad isolations trgset 7 "0"l8 irf ogogjp (7) inl10
- Event Trigger 8 pulls the ARI fuses trgset 8 "0"l10 irf aw4 (8) truel10
- Event Trigger 9 inserts the scram jumpers trgset 9 "0"l10 irf rpjumpas (9) truel12
Page 23 of 26
- Event Trigger 10 removes fuses for 2C ERV Trgset 10 "0"l12 irf adsrfc (10) pulledl12
- Event Trigger 28 sets gain for all 6 APRMs.
trgset 28 "0"l12 trg 28 "irf niagainf true"l14
- END ####
Page 24 of 26 Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 2 at 7% power, Leading Thermal Limit: MFLCPR @ 0.881 Action limit: 0.980 Equipment Unavailable: 2B RFP, 2C RFP on Bus 21 Protected Equipment: 2A FPC, 2A RFP, 2C RFP on Bus 22 Unit 3 is at 100% power.
Leading Thermal Limit: MFLCPR @ 0.883 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: 3A FPC Current Action Statements Both LPCI Subdivisions LCO Started: 6 Hour ago LCO Expires: 66 Hours from now TS 3.5.1, Cond E Cause: MCC 28-7/29-7 is not powered from the normal source Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
Transfer MCC 28-7/29-7 from bus 28 to bus 29 Continue Startup
- Shift 3 Activities ****
Turnover:
During initial power ascension following a refuel outage, the 28-7/29-7 breaker on Bus 29 faulted. EMD has replaced the breaker and it is ready to be returned to Bus 29. Once restored, continue on with the reactor startup. 2B RFP is OOS for major overhaul. 2C RFP on Bus 21 is OOS for cubicle damage.
Page 25 of 26 XL-3 Alarms Sensor 51-20 in alarm 2/3 FIRE PUMP RUNNING
Page 26 of 26 LPCI BOTH LPCI SUBSYSTEMS INOPERABLE LCORA:
3.5.1.E Clock Started:
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago Clock Expires:
66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> form now Contingencies / Compensatory Actions:
None Entry Reason:
LPCI swing bus (MCC 28-7/29-7) not on Bus 29.
Dresden Generating Station ILT-N-4 LOAD U2 EDG ON TO BUS 24-1 RAISE POWER WITH FLOW APRM FLOW CONVERTER FAILURE RBCCW PUMP TRIP IRM DOWNSCALE ISO COND SPURIOUS ISOLATION STEAM LEAK IN DRYWELL - MANUAL SCRAM GENERATOR FAILS TO AUTO TRIP ED ON TORUS BOTTOM PRESSURE Rev. 00 06/21 Developed By:
Exam Author Date Approved By:
Facility Representative Date
Page 2 of 24 Scenario Outline Facility:
Dresden Generating Station Scenario No.:
2021-302 ILT-N-4 Op-Test No.: 2021-302 Examiners Operators
/ crew position
/ ATC
/ BOP
/ CRS Initial Conditions:
Unit 2 is at 70% power.
Turnover:
U2 EDG Surveillance Test in progress per DOS 6600-01 and completed up to and including step I.13.
Critical Tasks:
RPV-2.1 - When conditions are met per DEOP 400-2, Emergency Depressurization, the minimum number of available SRVs required for emergency depressurization (MNSRED) are opened.
PC-1.1 - While executing DEOP 200-1, Primary Containment Control, when drywell pressure exceeds 9 psig and only if operating within the safe region of the drywell spray initiation limit (DSIL), initiate drywell sprays.
PC-1.3 - When executing DEOP 200-1, Primary Containment Control, if cannot stay inside the limits of the Pressure Suppression Pressure (PSP) limit, enter DEOP 400-2, Emergency Depressurization and blowdown the reactor.
Event No.
Malf.
No.
Event Type*
Event Description #
1 NONE N
BOP (New) - AUX POWER - Load U2 EDG on to Bus 24-1 2
NONE R
ATC REACTIVITY - Raise Power with Recirc Flow 3
WTNP C/T ATC CRS (New) - APRM - Flow Converter Failure 4
B38 C
BOP (New) - RBCCW - Pump Trip on Overcurrent 5
NII12POT C
ATC (New) - IRM - IRM Downscale 6
CIGP5AP ICGP5SP I/T BOP CRS (New) - ISO COND - Spurious Isolation, Incomplete 7
I21 M
ALL (New) - Manual Scram - Steam Leak in Drywell 8
T45 C
BOP (New) - GENERATOR - Fails to Auto Trip 9
I21 K23 K40 M
ALL (New) - EMERGENCY DEPRESSURIZE - On Exceeding Pressure Suppression Pressure Due To Steam Leak inside the Drywell &
Partial Loss of Ability to Spray the Drywell / Loss of Bus 23-1 and Bus 28
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
- (New) - Event not used on previous 2 NRC Exams, (Pre) - Event used on previous 2 NRC Exams Scenario Objective:
Evaluate the Teams ability to operate the plant with a steam leak in the drywell.
Scenario Initial Conditions
- 1. Unit 2 is at 70% power.
- 2. The following equipment is OOS:
- a.
None
- 3. LCOs:
- a.
Page 3 of 24 Scenario Sequence Event #
Description 1
AUX POWER - Load U2 EDG on to Bus 24-1:
The BOP will parallel the U2 EDG to Bus 24-1 per DOS 6600-01.
2 REACTIVITY - Raise Power with Recirc Flow:
The TSO calls and requests that the team raise load by 75 MWe. The team uses Recirc Flow to raise load per DGP 3-1.
3 APRM - Flow Converter Failure:
An APRM Flow Converter fails. The ATC will insert a Channel A 1/2 Scram as directed. Technical Specifications 3.3.1.1 Condition A, 3.3.1.1 Condition C, and TRM 3.3.a Function 1.a 3.3.1.1 Condition A.1 apply.
4 RBCCW - Pump Trip on Overcurrent:
The running RBCCW Pump trips on overcurrent. The team will start the standby RBCCW Pump.
IRM Channel 12 will fail downscale. The ATC will bypass the failed IRM and the CRS will address technical specifications.
6 ISO COND - Spurious Isolation, Incomplete:
The Isolation Condenser spuriously isolates. The 2-1301-1 valve will not close during the isolation and will have to be manually closed. Technical Specifications 3.5.3 Condition A and 3.6.1.3 Condition A apply.
7 Manual Scram - Steam Leak in Drywell:
A small steam leak in the Drywell begins. The Team manually scrams the Reactor before the automatic Scram occurs.
8 GENERATOR - Fails to Auto Trip Once the reactor is scrammed, the generator will fail to auto trip and the field breaker will open. The team will manually open the Generator GCBs from the 923-2 Panel per DOA 5600-01 or DOA 6000-01.
9 EMERGENCY DEPRESSURIZE - On Exceeding Pressure Suppression Pressure Due To Steam Leak inside the Drywell & Partial Loss of Ability to Spray the Drywell / Loss of Bus 23-1 and Bus 28:
The steam leak worsens causing Drywell pressure to rise rapidly. When the Team attempts to spray the Drywell, Div 2 Drywell Sprays are failed as part of initial setup and Bus 28 trips resulting in a loss of Div 1 Drywell Sprays. Eventually Primary Containment pressure will exceed the PSP limit and require the Team to Emergency Depressurize.
Event One - Load U2 EDG on to Bus 24-1 The BOP will parallel the U2 EDG to Bus 24-1.
Malfunctions required: 0 None Success Path:
U2 EDG loaded on to Bus 24-1.
Event Two - Raise Power with Recirc Flow The Team raises reactor power using recirculation flow as directed by the QNE.
Malfunctions required: 0 None Success Path:
Raises reactor power using recirculation flow.
Page 4 of 24 Event Three - APRM Flow Converter Failure The APRM Flow converter flow input fails high.
Malfunctions required: 1 (Flow input to Channel A flow converter fails high)
Success Path:
The team will insert a half scram on channel A.
Determines Technical Specifications requirements.
Event Four - RBCCW Pump Trip 2A RBCCW Pump trips on overcurrent.
Malfunctions required: 1 (RBCCW Pump trip)
Success Path:
Starts standby RBCCW Pump.
Event Five - IRM Fails Downscale IRM 12 fails downscale.
Malfunctions Required: 1 (IRM 12 fails downscale)
(Partial Half Scram)
Success Path:
IRM 12 placed in bypass.
Determines Technical Specifications requirements.
Event Six - Isolation Condenser Spurious Isolation The Isolation Condenser spuriously isolates and the 2-1301-1 valve does not close.
Malfunctions required: 2 (Isolation Condenser Spurious Isolation)
(Failed Isolation Condenser Isolation)
Success Path:
Completes the IC isolation.
Determines Technical Specifications requirements.
Event Seven - Steam Leak in the Drywell A small steam leak develops in the Drywell causing Drywell Pressure to rise.
Malfunctions required: 1 (Steam Leak in Drywell)
Success Path:
Performs a manual scram.
Page 5 of 24 Event Nine - Generator Fails to Auto Trip The generator fails to auto trip after the manual scram.
Malfunctions required: 1 (Generator Fail to Trip)
Success Path:
Manually trips the generator per DOA 5600-01.
Event Eight - Steam Leak inside the Drywell / Emergency Depressurization The steam leak in the Drywell worsens. When the Team attempts to spray the Drywell, Bus 23-1 trips on overcurrent. The leak worsens and Primary Containment pressure exceeds the PSP limit. The Team performs an Emergency Depressurization.
Malfunctions required: 2 (Steam leak in the Drywell worsens)
(Loss of Drywell Sprays)
Success Path:
Performs DEOP 0400-02, Emergency Depressurization.
Page 6 of 24 PRE-SCENARIO ACTIVITIES 1
If applicable, conduct pre-scenario activities in accordance with TQ-AA-155-J040, SIMULATOR EXAMINATION BRIEFING.
- a. Direct the crew to perform their briefs prior to entering the simulator.
- b. Provide the Team a marked up copy of DOS 6600-01, Diesel Generator Surveillance Tests.
- c.
Provide the Team a copy of DGP 03-01, Power Changes, marked up for load drop through inserting control rods to reduce FCL prior to reducing Recirc flow.
- d. Provide the Team a marked up copy of DOP 0202-03, Reactor Recirculation Flow Control System Operation.
- e. Provide the Team a marked up REMA for power ascension.
2 Simulator Setup (the following steps can be done in any logical order)
- a.
Initialize simulator in a 70% power IC. (IC 302 used for validation)
- b. Cut in/out Cond Demins as needed, to maintain DP within limits.
- c.
Ensure running Condensate pump amps within limits.
3 Verify the following simulator conditions:
- a.
Verify Reactor Power 70%, adjust rods or Recirc as appropriate.
- c.
Verify 2A and 2/3 (on Bus 24-1) RBCCW pumps running. (2B RBCCW pump available) 4 Run Pump_Sumps.cae 5
Run the initial setup CAEP file: 20-2 (2021-302) ILT-N-4.cae 6
Place the following equipment out of service:
- a. None 7
Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Required Actions o
Optional Actions NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
Page 7 of 24 Event One - Load U2 EDG on Bus 24-1 Trigger Position Crew Actions or Behavior 28 SIMULATOR OPERATOR ROLE PLAY:
If requested to set gains to 1, (wait 3 min) activate TRIGGER 28, then report gains set to 1. (This trigger can be triggered OFF, then back ON to adjust gains more than once).
ROLE PLAY:
EO to perform steps in DOS 6600-01, wait 30 secs, then report the required action completed.
FLOOR INSTRUCTOR:
Once the EDG is loaded, inform the BOP that another NSO will finish the surveillance.
CRS Directs DOP to continue DOS 6600-01, DIESEL GENERATOR SURVEILLANCE TESTS.
ATC Assists as directed and monitors the panels.
BOP Loads U2 EDG to Bus 24-1 per DOS 6600-01:
Inserts key AND turns the synchroscope ON between U2 EDG and Bus 24-1.
Adjusts the U2 EDG voltage (using VOLTAGE REG c/s) AND speed (using GOVERNOR c/s) until the U2 EDG output is synchronized with the 4kV system.
Closes the U2 EDG output breaker to 4kV Bus 24-1 AND raises load to 250-500 kW.
Using the GOVERNOR c/s, raises the load on U2 EDG to 2340 to 2600 kW over a period of 30-90 seconds.
Turns off synchroscope AND removes key.
Using the VOLTAGE REG c/s, adjusts U2 EDG excitation to -300 to +300 kVARS.
Event 1 Completion Criteria:
U2 EDG loaded on to Bus 24-1.
-- AND/OR --
At the discretion of the Lead Examiner.
Page 8 of 24 Event Two - Raise Reactor Power using Recirculation Flow Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:
EO to cut in condensate demin beds: Use instructor station drawing FW4 to cut in condensate demin beds and acknowledge the local trouble alarm. Provide appropriate communications.
NOTE:
With 2 RFPs running the maximum allowable feed flow rate is 9.8 mlbm/hr.
CRS Directs ATC to continue power ascension.
ATC Performs the following actions per DGP 03-01, POWER CHANGES, and DOP 0202-03, REACTOR RECIRCULATION FLOW CONTROL SYSTEM OPERATION, as directed:
RAISES Recirc Pump speed using Panel 902-5 Recirc Master Manual Control speed pushbuttons.
BOP Monitors Panels and provides peer check for changing Recirc flow.
Event 2 Completion Criteria:
Sufficient power increase.
-- AND/OR --
At the discretion of the Lead Examiner.
Page 9 of 24 Event Three - APRM Flow Converter Failure Trigger Position Crew Actions or Behavior 1
SIMULATOR OPERATOR:
At the discretion of the Lead Examiner, activate TRIGGER 1, which causes a failure of Div I APRM flow converter.
FLOOR INSTRUCTOR:
If examinee cycles APRM meter function switch between FLOW and AVEARGE more than two times for APRMs 1-3, provide cue that the meter is pegged high when in the FLOW position.
ROLE PLAY:
Respond as groups notified.
ATC Reports and responds to the following DANs:
902-5 D-6, NEUTRON MON FLOW UNIT OFF NORMAL 902-5 C-3, ROD OUT BLOCK Monitors Reactor power, level and pressure.
BOP Checks for abnormal APRM indication on panel 902-37.
Place METER FUNCTION switch to FLOW position for each APRM meter AND verify indication < 110%
Observes APRMs 1, 2 and 3 indicate > 110% (pegged high) in the FLOW position.
Observes RBM 7 Flow pegged high.
Observes Comparator Light lit.
Informs the Unit Supervisor APRMs 1, 2 and 3 indicate failed high in the FLOW position Informs Unit Supervisor of possible Tech Spec applicability from DAN references.
CRS References appropriate plant licensing documents and determines:
TS 3.3.1.1 APRM instrumentation for Function 2.b in Table 3.3.1.1-1 is INOPERABLE.
TS 3.3.1.1, condition A required actions:
A.1 Place Channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. -OR -
A.2 Place associated trip system in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
TS 3.3.1.1, Condition C required actions:
C.1 Restore RPS trip capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
TRM 3.3.a Function 1.a 3.3.1.1, Condition A.1 required actions:
A.1 Restore inoperable channel to OPERABLE status within 7 days.
Directs inserting a Channel A Half Scram to comply with Tech Spec requirements.
ATC Inserts Channel A half scram per DOP 0500-07, INSERTION/RESET OF MANUAL HALF SCRAM, as directed by Unit Supervisor.
Event 3 Completion Criteria:
Technical Specifications have been referenced, Half Scram inserted on Channel A,
-- AND/OR --
At the direction of the Lead Examiner.
Page 10 of 24 Event Four - RBCCW Pump trip Trigger Position Crew Actions or Behavior 2
Simulator Operator:
Shortly after the team has completed the previous Event, activate TRIGGER 2, which trips 2A RBCCW pump.
EO to check 2A RBCCW pump breaker, wait 2 min then report the following:
The 2A RBCCW pump breaker is OPEN and an overcurrent target is up.
EO to check 2A RBCCW pump, wait 2 min then report the following:
The 2A RBCCW pump is at rest and the motor is hot to the touch.
EO to check 2B RBCCW pump, wait 2 min then report the following:
The 2B RBCCW pump is operating normally.
BOP Announces alarm 923-1 C-1, U2 OR U3 RBCCW PP TRIP.
Performs DOA 3700-01, LOSS OF COOLING BY REACTOR BUILDING CLOSED COOLING WATER (RBCCW) System, and / or DAN 923-1 C-1, U2 or U3 RBCCW PP TRIP, as directed:
Starts 2B RBCCW pump. (Immediate action)
Verifies RBCCW system operating normally.
Performs DOA 6500-10, 4KV CIRCUIT BREAKER TRIP, as directed:
Directs EO to check status of 2A RBCCW pump breaker.
Based on breaker report, places 2A RBCCW pump control switch in PTL.
CRS Enters DOA 3700-01.
Enters DOA 6500-10.
ATC Monitors panel, provides assistance as directed.
Event 4 Completion Criteria:
Standby RBCCW pump started
-- OR --
At the discretion of the Floor Instructor/Evaluator
Page 11 of 24 Event Five - IRM Fails Downscale Trigger Position Crew Actions or Behavior 3
SIMULATOR OPERATOR:
At the discretion of the Lead Examiner, activate TRIGGER 3, to fail IRM 12 downscale.
ROLE PLAY:
Respond as groups notified.
ATC Announces and references DAN 902-5 C-5, IRM DOWNSCALE.
Reports IRM 12 failed downscale.
Bypasses IRM 12 per DAN 902-5 C-5 by placing the IRM Bypass Selector Switch to IRM 12, when directed.
CRS Refers to TRM 3.3.a (does not apply).
Directs bypassing IRM 12.
BOP Monitors panels and assists as directed.
Event 5 Completion Criteria:
IRM 12 bypassed,
-- AND/OR --
At the direction of the Lead Examiner.
Page 12 of 24 Event Six - Isolation Condenser Inadvertent Isolation Trigger Position Crew Actions or Behavior 4
SIMULATOR OPERATOR:
At the direction of the Lead Examiner, activate TRIGGER 4, which inserts a spurious Isolation Condenser Isolation (Group 5 Isolation).
ROLE PLAY:
EO to Shutdown Cooling Pump Room, wait 4 min then report the following:
Isolation switches for 2-1301-1 and 2-1301-4 are in NORMAL.
EO to 2/3 EDG Room, wait 4 min then report the following:
The indicating lights for 2-1301-1 and 2-1301-4 are not illuminated.
EO to Iso Condenser Floor, wait 2 min and report the following:
I see nothing abnormal on U2 Isolation Condenser floor.
Respond as Support Groups notified.
BOP Reports and responds to DANs:
902-3 B-4, ISOL CONDR VLVS OFF NORM.
902-3 H-2, ISOL CONDR LINE BREAK (GROUP 5 ISOL).
Determines Isolation Condenser failed to isolate due to MO 2-1301-1 valve open.
Places MO 2-1301-1 close.
When MO 2-1301-1 indicates closed, reports that the Isolation Condenser is isolated.
Informs Security that Isolation Condenser is unavailable.
TEAM Determines Isolation Condenser isolation spurious.
CRS Directs fully isolating the Isolation Condenser.
References appropriate plant licensing documents and determines:
TS 3.5.3, condition A. required actions:
A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE immediately, AND, A.2 Restore IC System to OPERABLE status within 14 days.
TS 3.6.1.3, condition A. required actions:
A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
A.2 Verify the affected penetration flow path is isolated once per 31 days.
TS 3.3.6.1, condition A. required actions:
A.1 Place channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ATC Monitors panels and assist as directed.
Event 6 Completion Criteria:
Isolation Condenser fully isolated, Technical Specifications have been referenced,
-- AND/OR --
At the direction of the Lead Examiner.
Page 13 of 24 Event Seven - Small Steam Leak in Drywell - Manual Scram Trigger Position Crew Actions or Behavior 5
SIMULATOR OPERATOR:
At the discretion of the Lead examiner, activate TRIGGER 5, which causes a small Main Steam line leak to develop in the Drywell.
ROLE PLAY:
U-3 NSO to report Drywell pressure status, report the following:
U-3 Drywell pressure is 1.2 psig and steady.
EO to check Drywell CAM, wait 2 min and report the following:
The Drywell CAM had a step jump to 25K and is trending up.
TEAM Recognizes and announces that Drywell pressure is slowly rising.
CRS Enters and directs performance of DOA 0040-01, SLOW LEAK.
Sets Scram contingency of 1.5 psig DW pressure.
May enter DGP 02-03, REACTOR SCRAM, and direct taking scram preparatory actions.
Prior to reaching the Drywell Pressure scram setpoint, directs a manual reactor scram per DGP 02-03.
ATC Performs the following actions per DOA 0040-01 as directed:
Maintain Level with FWLCS (immediate action).
Monitors leakage rate, reactor water level, and Drywell pressure.
Inserts manual reactor scram prior to 1.5 psig DW pressure BOP Performs the following actions per DOA 0040-01 as directed:
Notifies Shift Supervisor and Rad Protection.
Monitors for EP conditions.
Directs search for leak.
Shutdown H2 Addition.
Makes PA announcement.
Verify Crib House inlet temperature is <95oF.
Initiates Torus cooling per Hard Card.
Place 316A/B AND 318A/B keylock switches in MANUAL (MANUAL OVERRD).
Start one CCSW Pump in each loop AND verify 2(3)A/B valves open. (IF only one CCSW loop available, THEN start second CCSW Pump in same loop.)
Start at least one LPCI pump in each loop. (Start additional LPCI pumps as required.)
Open 21A/B AND 20A/B valves in desired loop.
Throttle open 38A/B valves until > 5000 gpm per LPCI pump is established (maintain LPCI pump discharge pressure > 125 psig OR > 100 psig if ADS is in INHIBIT).
Start additional CCSW Pumps Adjust CCSW flow controller to > 5000 gpm for two CCSW Pumps [Maintain LPCI/CCSW dP 7 psid (1 LPCI Pump/loop) OR 20 psid (two LPCI Pumps/loop)].
Momentarily place 11A/B valve control switches to close.
Page 14 of 24 Event Seven - Small Steam Leak in Drywell - Manual Scram Trigger Position Crew Actions or Behavior ATC /
BOP Performs scram preparatory actions per DGP 02-03 as directed.
Reduces FCL to < 93% by inserting CRAM rods per DGP 03-04, CONTROL ROD MOVEMENTS, OR in-sequence rods per DGP 03-04.
Reduces power with Recirc flow to no lower than 56 Mlbm/hr core flow.
Starts MSP and TGOP.
Trips H2 addition.
ATC Performs the following actions per DGP 02-03 as directed:
Presses scram pushbuttons Places mode switch in shutdown Check rods inserted.
Verifies Recirc Pumps runback to minimum.
Controls RPV water level +25 inches to +35 inches.
TEAM Verifies the following as time allows:
Group Isolations Automatic start of ECCS systems Automatic start of EDGs.
CRS Enters DEOP 100, RPV CONTROL, due to high Drywell Pressure and/or low Reactor water level.
Event 7 Completion Criteria:
Reactor scrammed.
-- AND/OR --
At the discretion of the Lead Examiner.
Page 15 of 24 Event Eight - Steam Leak Inside The Drywell Increases / Emergency Depressurization Trigger Position Applicants Actions or Behavior 6
SIMULATOR OPERATOR:
After the Team has inserted control rods, and at the discretion of the Lead Evaluator, activate TRIGGER 6, which increases the Main Steam line leak enough to require the Team to Emergency Depressurize due to exceeding PSP curve.
TEAM Recognizes and announces that Drywell pressure is rising rapidly.
CRS Enters DEOP 0200-01, PRIMARY CONTAINMENT CONTROL, when Drywell pressure reaches 2 psig and/or Torus bulk temperature reaches 95 deg. F and performs/directs:
Verifying of Torus water level <27.5 ft.
Initiation of Torus sprays.
Monitoring of Drywell temperature (Drywell sprays may be initiated for temperature control)
Initiating Torus cooling per Hard Card. (If not already complete)
Monitors Torus level.
ROLE PLAY:
EO to check operation of the EDGs after auto start, wait 3 minutes and then report the following:
The EDGs are operating normally.
CRS Per DEOP 0200-01 when Drywell pressure reaches 9 psig directs:
Verifying Recirc Pumps and Drywell Coolers tripped.
Verifies the Drywell spray initiation curve prior to the operator manually opening any of the Drywell spray valves. Then directs the Operator to initiate Drywell Sprays.
Initiation of Drywell sprays. (PC-1.1)
BOP Performs DEOP 0200-01 actions as directed:
Initiates Torus Sprays.
Monitors Drywell temperature and pressure and attempts to initiate drywell sprays pre Hard Card LPCI/CCSW OPERATION, as directed.
Initiates Torus cooling per Hard Card. (If not already complete) 7 SIMULATOR OPERATOR:
Verify TRIGGER 7 automatically activates when MO 1501-27A begins to open. This trips Bus 23-1 on overcurrent. As a result, Div. I of Drywell sprays cannot be initiated.
ATC /
BOP Initiates Drywell Sprays. (PC-1.1)
Notices and reports the loss of ECCS equipment powered from Bus 23-1.
Reports the loss of Bus 23-1 and 28.
Reports Drywell Sprays will not initiate, A LOOP has no power and the 2-1501-27B valve will not open.
CRS Directs Operators to investigate the loss of Bus 23-1. Directs entry into DGA-12, LOSS OF OFFSITE POWER, or DOA 6500-01, 4KV BUS FAILURE.
Page 16 of 24 Event Eight - Steam Leak Inside The Drywell Increases / Emergency Depressurization Trigger Position Applicants Actions or Behavior BOP Refers to DAN 902-8 F-5, 4KV BUS 23-1 OVERCURRENT.
As directed, Performs DGA-12 or DOA 6500-01:
Takes actions per DGA 12 for any faulted buses.
Recognizes the loss of Bus 28.
Dispatches EO to Bus 23-1 to investigate the loss of Bus 23-1.
May enter DOA 6500-01.
NOTE:
If team crossties Bus 28 and 29 and Bus 29 trips, allow the team to re-energize Bus 29 from Bus 24-1.
ROLE PLAY:
EO to Bus 23-1, wait 2 min and then report the following:
The feed breaker to Bus 23-1 from Bus 23 has an overcurrent flag up on it and will not reset.
EO to Bus 28, wait 2 min and then report the following:
Bus 28 has an overcurrent flag up and will not reset.
EO to Bus 29, wait 2 min and then report the following:
I see nothing abnormal at Bus 29.
ATC /
BOP May dispatch an Operator to attempt to manually open A LOOP of drywell spray and/or the 2-1501-27B valve.
ROLE PLAY:
DO NOT REPORT BACK ON ATTEMPTS TO OPEN DW SPRAY VALVE TILL after Torus bottom pressure is
> 20 psig.
EO to open A LOOP of drywell spray, wait 2 min and then report the following:
The handwheel for MO 2-1501-28A will not engage.
EO to open the 2-1501-27B valve, wait 2 min and then report the following:
There is equipment in my way to get to the 2-1501-27B. It will take me a little while to get to the valve, I will let you know when I can get to it. (It is not intended for this valve to be opened during the scenario)
CRS Recognizes that Emergency Depressurization per DEOP 0400-02 is necessary due to one of the below:
o Drywell temperature cannot be maintained below 281oF.
o Exceeding the PSP.
May anticipate blowdown per DGP 02-03.
Enters DEOP 400-02 and directs: (PC-1.3)
If Drywell pressure >2 psig, prevention of injection from LPCI/CS pumps not needed for core cooling.
Verification of Torus level > 6ft.
Opening all ADS valves. (RPV-2.1)
Verifying all relief valves open.
Page 17 of 24 Event Eight - Steam Leak Inside The Drywell Increases / Emergency Depressurization Trigger Position Applicants Actions or Behavior BOP Performs DEOP 400-02 as directed. (PC-1.3)
If Drywell pressure is greater than +2 psig, prevents injection from LPCI/CS pumps not needed for Core cooling per Hard Card, LPCI INJ/CC CONTROL/SHUTDOWN.
Verifies Torus level >6 feet.
Open all ADS valves. (RPV-2.1)
Verifies all relief valves open.
Event 8 / Scenario Completion Criteria:
Emergency depressurization in progress; RPV Level is being controlled;
-- AND/OR --
At the discretion of the Lead Evaluator.
Page 18 of 24 Event Nine - Generator Fails to Auto Trip Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:
When the crew scrams the reactor, the generator will not auto trip.
BOP Notices that the generator did not trip and informs the CRS.
Enters and performs the following actions from DOA 5600-01, TURBINE TRIP and/or DOA 6000-01, MAIN GENERATOR TRIP, when directed:
Opens GCB 1-2 and 1-7 from the 923-2 Panel.
CRS Directs BOP to trip the generator per DOA 5600-01 and/or DOA 6000-01.
ATC Monitors panels and assists as directed.
Event 9 Completion Criteria:
GCB 1-2 and 1-7 have been opened from the 923-2 Panel.
-- AND/OR --
At the discretion of the Lead Examiner.
Page 19 of 24 References PROCEDURE TITLE DAN 902-3 B-4 ISOL CONDR VLVS OFF NORM DAN 902-3 H-2 ISOL CONDR LINE BREAK (GROUP 5 ISOL)
DAN 902-5 C-3 ROD OUT BLOCK DAN 902-5 C-5 IRM DOWNSCALE DAN 902-5 D-6 NEUTRON FLOW UNIT OFF NORMAL DAN 902-8 F-5 4KV BUS 23-1 OVERCURRENT DAN 923-1 C-1 U2 OR U3 RBCCW PP TRIP DEOP 0100 RPV CONTROL DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DEOP 0400-02 EMERGENCY DEPRESSURIZATION DGA-12 LOSS OF OFFSITE POWER DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DOA 0040-01 SLOW LEAK DOA 3700-01 LOSS OF COOLING BY REACTOR BUILDING CLOSED COOLING WATER (RBCCW)
DOA 5600-01 TURBINE TRIP DOA 6000-01 MAIN GENERATOR TRIP DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0202-03 REACTOR RECIRCULATION FLOW CONTROL SYSTEM OPERATION DOP 0500-07 INSERT/RESET OF MANUAL HALF SCRAM DOS 6600-01 DIESEL GENERATOR SURVEILLANCE TESTS TRM 3.3.a CONTROL ROD BLOCK INSTRUMENTATION TS 3.3.1.1 APRM INSTRUMENTATION TS 3.5.3 ISOLATION CONDENSER (IC) SYSTEM INSTRUMENTATION TS 3.6.1.3 PRIMARY CONTAINMENT ISOLATION VALVES (PCIVs)
OPERATOR AID #158 TECH SPEC / TRM / ODCM IMPLEMENTATION AID
Page 20 of 24 Simulator Scenario Review Checklist ILT-N-4 Quantitative Attributes 6
Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 4 Abnormal events (2 to 4) 2 Major transients (1 to 2) 2 EOPs entered/requiring substantive actions (1 to 2) 1 EOPs contingency requiring substantive actions (0 to 2) 2 Crew critical tasks (2 to 3)
Page 21 of 24 CAEP Files
- CAEP file for ILT-N-4
- ILT 2021-302 (20-2)
- Written by ADK
- 06/21
- INITIAL CONDITIONS ####
- Prevents 2-1501-27B, Div 2 DW spray valve, from opening ior lpdvlvop18 off
- Prevents the 2-1501-1 valve from closing imf ic1vbn 100.0
- Prevents Generator from tripping on Reverse Power Imf t45
- Prevents Flow Unit 2 Comparator light from turning on imf ser0920 1
- EVENT TRIGGERS ####
- Event Trigger 1 inserts a failure of the Div 1 APRM flow converter trgset 1 "0"l2 imf nvmflwd1 (1) 21.4l2 ior nilblpcm2 (1) offl2
- Event Trigger 2 Trips 2A RBCCW PP.
trgset 2 "0"l2 imf q01 (2)l4
- Event Trigger 3 IRM 12 channel fails downscale.
trgset 3 "0"l4 imf nii12pot (3) 0.0l4
- Event Trigger 4 simulates a spurious Isolation Condensor Isolation.
trgset 4 "0"l4 imf icgp5sp (4) 0.0l6
trgset 5 "0"l6 imf i21 (5) 0.06 25:00 0.005l6
trgset 6 "0"l6 trg 6 "mmf i21 15.0 2:00 2.0"l8 imf p00 (6 30)l8
- Event Trigger 7 activates when DW spray valve mo 1501-27A starts to open.
- Trips Bus 23-1 and Bus 28 on overcurrent.
trgset 7 "lplvlvop(17)"l8 imf k23 (7)l8 imf k40 (7)l10
- Event Trigger 13 closes the 2-0301-25 valve trgset 13 "0"l10 irf rd25pos (13) 0.0l10
- Event Trigger 14 lowers the leak size trgset 14 "(hwpcptr103.gt. 28.0).and. (hwadd303cm)"l10 trg 14 "imf i21 4.0"l12
- Event Trigger 15 allows the 2-1501-1 valve to close trgset 15 "hwicdcl1"
Page 22 of 24 trg 15 "dmf ic1vbn"
- Event Trigger 28 sets gain for all 6 APRMs.
trgset 28 "0"l12 trg 28 "irf niagainf true"l12
- END ####
Page 23 of 24 Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is at 70% power, Leading Thermal Limit: MFLCPR @ 0.881 Action limit: 0.980 Equipment Unavailable: None Protected Equipment: 2A FPC Unit 3 is at 100% power.
Leading Thermal Limit: MFLCPR @ 0.883 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: 3A FPC Current Action Statements AC Sources LCO Started: Today 0600 LCO Expires: 7 days from Today 0600 TS 3.8.1 Condition B Cause: U2 EDG Monthly Surveillance Test Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
Finish Monthly U2 EDG Run DOS 6600-01 complete up to and including Step I.13
- Shift 3 Activities ****
TURNOVER:
U2 EDG Surveillance Test in progress per DOS 6600-01 and completed up to and including step I.13. The Quarterly Fuel Consumption Test is NOT being performed. Attachment A has been briefed. Appendix X due again in 8 hrs. Once the EDG is loaded, continue power ascension.
Page 24 of 24 AC SOURCES ONE REQUIRED DG INOPERABLE LCORA:
3.8.1.B Clock Started:
TODAY 0600 Clock Expires:
7 Days from TODAY 0600 Contingencies / Compensatory Actions:
None 4 days ago 04:30 Entry Reason:
U2 EDG Monthly Surveillance