ML030440677
| ML030440677 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/06/2002 |
| From: | Gadbois R, Otten M Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-237/02-302, 50-249/02-302 | |
| Download: ML030440677 (32) | |
Text
Master Copy ML030440677.doc Dresden Generating Station SIMULATOR EXERCISE GUIDE ILT 01-1 NRC RE-EXAM SCENARIO ILT-R-3 Rev. 01 11/02 DEVELOPED BY:
Mark Otten (Original on file) 12/6/02 Exam Author Date APPROVED BY:
Rich Gadbois (Original on file) 12/6/02 Facility Representative Date
Page 2 of 24 NUREG-1021, Revision 8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: Dresden Scenario No: ILT-R-3 Op-Test No: ILT 01-1 Examiners: ___________________________ Operators: __________________________
Initial Conditions: 15% reactor power, IRM channel 15 OOS, Unit 3 is in Mode 1 Turnover: Unit startup in progress; transfer auxiliary power to transformer 21, then continue power ascension Event No.
Malf.
No.
Event Type*
Event Description 1
N/A N
ANSO SRO Synchronize Main Generator to the grid 2
N/A R
NSO SRO Raise reactor power by withdrawing control rods 3
RLMLFBF I
NSO SRO A blown fuse causes a lockup of the LFRV 4
ICSPDFT I
ANSO SRO A setpoint drift causes a spurious Isolation Condenser initiation 5
FWICP1 C
NSO SRO High amps on the 2A Condensate Pump 6
Q21 C
ANSO SRO Trip of the 2A Service Water Pump 7
HPRBBRKP RADFFD ALL Unisolable steam leak in the reactor building from the HPCI line with a fuel element failure 8
RDFHYDK M
NSO SRO Rods fail to insert due to a hydraulic lock
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 3 of 24 Rev. 01 (11/02)
Dresden Generating Station NRC ILT RE-EXAM Scenario ILT-R-3 Scenario Objective Evaluate the operators in using the Failure to Scram contingency procedure.
Scenario Summary Initial Conditions:
15% power, unit startup in progress IRM 15 OOS 2B EHC Pump OOS Unit 3 is in Mode 1 Events:
Synchronize the Main Generator to the Grid.
Raise reactor power by withdrawing control rods A blown fuse causes a lockup of the LFRV A setpoint drift causes a spurious Isolation Condenser initiation High amps on the 2A Condensate Pump Trip of the 2A Service Water Pump Unisolable steam leak in the reactor building from the HPCI line Rods fail to insert due to a hydraulic lock / SBLC failure Scenario Sequence The Team synchronizes the generator to the Grid.
The NSO, as directed by the SRO, then continues the power ascension for unit startup by control rod withdrawal.
During the power ascension, a blown fuse causes a lockup of the LFRV.
A setpoint drift causes a spurious Isolation Condenser initiation.
2D Condensate Pump is drawing excessive current and is reported by an NLO to be running abnormally hot.
2A Service Water Pump trips on overload.
An unisolable steam leak develops in the Reactor Building from the HPCI line.
An ATWS condition results from the failure of all rods to insert due to a hydraulic lock.
SBGT fails to start as expected.
The scenario is terminated when all rods are inserted and the plant stabilized.
Event One - Synchronizes the Main Generator to the Grid The Team synchronizes the generator to the Grid.
Malfunctions required: 0 Success Path:
The Generator is synchronized to the grid IAW DGP 01-01.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 4 of 24 Rev. 01 (11/02)
Event Two - Raise Reactor power by withdrawing control rods.
The Team increases reactor power by withdrawing control rods per DOP 0400-01, and DGP 03-04.
Malfunctions required: 0 Success Path:
Control rods pulled per applicable procedures.
Event Three - A blown fuse causes a lockup of the LFRV A blown fuse causes a lockup of the LFRV.
Malfunctions required: 1 (Blown fuse for LFRV)
Success Path:
Blown fuse replaced and LFRV back in Auto Event Four - A setpoint drift causes a spurious Isolation Condenser initiation Shortly after assuming the shift, the Team should recognize and respond to the Isolation Condenser inadvertent initiation. The team will verify the signal is not valid and secure the Isolation Condenser.
Malfunctions required: 1 (Iso-Condenser Automatic Initiation)
Success Path:
The team isolates the isolation condenser Refers to Technical Specifications.
Event Five - High amps on the 2D Condensate Pump 2D Condensate Pump is drawing high amps and is running abnormally hot.
Malfunctions required: 1 ( High amps on 2D Condensate Pump.)
Success Path:
Start a standby Condensate Pump and secure 2D Condensate Pump.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 5 of 24 Rev. 01 (11/02)
Event Six - Trip of the 2A Service Water Pump.
The Team should recognize and respond to Service Water Pump 2A tripping on overload. The ANSO should manually start the 2/3 Service Water Pump.
Malfunctions required: 1 (Service Water Pump trip)
Success Path:
Start the 2/3 Service Water pump.
Event Seven - Unisolable steam leak in the Reactor Building from the HPCI line.
The Team should recognize and respond to the report of a steam leak in the Reactor Building.
Malfunctions required: 3 (Steam leak from the HPCI line)
(FEF)
(HPCI 4 valve failure to close)
Success Path:
Attempt to manually scram the Reactor.
Event Eight - Rods fail to insert due to a hydraulic lock.
The Team should recognize and respond to the ATWS and the failure of SBLC to start.
Malfunctions required: 2 (Hydraulic lock on SDV)
(SBLC failure to inject)
Success Path:
All rods inserted Scenario Recapitulation Total Malfunctions:
9 Abnormal Events:
4 Major Transients:
1 (ATWS)
EOPs Entered:
1 EOP Contingencies:
1 (ATWS)
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 6 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 1 Page 1 of 1 Event
Description:
Transfer Aux Power from TR-22 to TR-21.
Time Position Applicants Actions or Behavior SRO Directs the ANSO to synchronize the Generator to the Grid IAW DGP 01-01.
ANSO Synchronizes the Generator to the Grid:
Notifies Bulk Power Operations that Unit 2 is ready to parallel to grid.
Check all three phase voltages are approx equal at 18 kv using U2 GENERATOR VOLTS SELECT.
Synchronize Generator to the grid.
Closes OCB 2-3 or 2-7.
Verifies OCB indicates CLOSED.
Place synchroscope switch in OFF.
Raise GOVERNOR to CLOSE all Main Turbine bypass valves.
Adjust LOAD SET to maximum.
Close the Ring Bus.
Place the Voltage Regulator in Auto
Dispatch an Operator to verify MPT cooling fans selected have started and pump flow is normal.
Verify MN BRG OIL PRESS on 902-7 is approximately 35 psig.
Secure:
TGOP MSP Turb Brg Lift PPs
When Load approximately 80 Mwe:
Close MSL drains.
Close Control valve above seat drains.
NSO Monitors panels and assists as directed.
ROLE PLAY:
NLO dispatched to MPT 2 cooling fans (wait 3 mins)
Report: All cooling fans operational and pump flows look good.
Event 1 Completion Criteria:
U2 Generator has been synchronized to the grid.
AND, at the direction of the NRC Chief Examiner.
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 7 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 2 Page 1 of 1 Event
Description:
The NSO, as directed by the SRO, then continues the power ascension for unit startup by control rod withdrawal.
Time Position Applicants Actions or Behavior NSO 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 any control rod:
Control rod selected on the select matrix is correct rod.
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.
Verifies rod settles to target position and proper response of nuclear instrumentation.
ANSO Performs second verification checks.
For first rod in a step:
Verifies correct control rod pattern Verifies correct step and array.
Verifies RWM rod blocks enabled 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.
SRO Directs pulling control rods.
Reviews REMA.
Designates second verifier.
Directs NSO to pulls rods.
Event 2 Completion Criteria:
Sufficient power increase.
AND, at the direction of the NRC Chief Examiner.
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 8 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 3 Page 1 of 1 Event
Description:
A blown fuse causes a lockup of the LFRV.
Time Position Applicants Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 1, which causes Low Flow Reg Valve to lockup.
NSO Reports annunciator DAN 902-6 G-10, LOW FLOW REG VLV LOCKUP and 902-6 H-3, FW CONTROL SYSTEM PANEL TROUBLE, in alarm and refers to DAN:
Determines cause of valve lockup at Operator Interface Station on 902-18 Panel.
Selects F-20 to view alarm summary.
OIS alarm 643 LFRV PLS POS FUSE BAD displayed Requests IMD to replace fuse.
Selects (+) key to acknowledge alarms.
Maintain RPV level IAW DOA 600-1 NSO Monitors Panels and assists as needed.
Acknowledges report of annunciators.
May direct entry into DOA 600-1 SIMULATOR OPERATOR / ROLE PLAY:
IMD to replace LFRV fuse, (wait 5 mins)
Activate trigger 2 to replace blown LFRV fuse.
IMD report LFRV fuse has been replaced.
NSO
Resets LFRV IAW DOP 600-06, FRV Operation step G-10.
When white RESET pushbutton on 902-5 is backlit, depress the RESET pushbutton.
Verify annunciator 902-6 G-10 has cleared.
Returns LFRV to Auto per step G-9 of DOP 600-06.
Place RX LOW FLOW CONTROL STATION in AUTO Event 3 completion criteria:
LFRV is back in auto.
AND, at the discretion of the NRC Chief Examiner
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 9 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 4 Page 1 of 1 Event
Description:
A setpoint drift causes a spurious Isolation Condenser initiation.
Time Position Applicants Actions or Behavior Simulator Operator Actions:
Note: There is a time delay of ~ 15 seconds after activating this trigger.
At the direction of the Lead Evaluator activate trigger 3, which starts the Isolation Condenser inadvertent initiation.
NSO /
ANSO
Recognizes and announces Isolation Condenser initiation.
Verifies IC initiation is not valid.
Announces and refers to DAN 902-4 A-15, ISOL CONDR CH A/B INITIATION.
Places the 2-1301-03 valve in P-T-L per DAN 902-4 A-15.
Contacts RP.
Contacts Security to rope off area under IC vent.
ROLE PLAY:
QNE:
Acknowledge request but do NOT report to the control room.
Contacts maintenance to investigate Isolation Condenser initiation.
ROLE PLAY:
Maintenance:
Acknowledge request but do NOT report to the control room.
Event 4 Completion Criteria:
2-1301-3 valve has been placed in pull to lock.
OR At the discretion of the NRC Chief Examiner
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 10 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 5 Page 1 of 1 Event
Description:
High amps on the 2D Condensate Pump motor.
Time Position Applicants Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 4, which causes the 2D Condensate Pump motor amps to rise from 175 to 300 over 2 mins.
ANSO
Starts 2B or 2C Condensate Pump.
Secures 2D Condensate Pump.
Directs NLO to check 2B or 2C Condensate Pump for proper operation and investigate 2D Condensate Pump.
NSO Monitors panels and assists as directed.
ROLE PLAY:
NLO to check 2B and 2D Condensate Pump (wait 30 secs after trigger 4 inserted).
Report 2B Condensate Pump is running normally and 2D Condensate Pump feels abnormally hot.
SIMULATOR OPERATOR:
After 2D Condensate Pump has been secured, verify trigger 10 has returned 2D Condensate Pump amps to 0. If not, delete override FWICP4.
Event 5 Completion Criteria:
2B Condensate Pump is running.
And at the direction of the NRC Chief Examiner.
Appendix D Operator Actions Form ES-D-2 ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 11 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 6 Page 1 of 1 Event
Description:
Trip of the 2A Service Water Pump on overload.
Time Position Applicants Actions or Behavior Simulator Operator Actions:
At the discretion of the NRC Chief Examiner, activate trigger 5, which trips the 2A Service Water Pump.
ANSO Acknowledges Annunciator and IAW DAN 923-1 C-3:
At Panel 923-1, check which pump has tripped.
Check 90-100 psig on SERV WTR PP DISCH PRESS.
Starts 2/3 Service Water Pump.
Refers to DOA 6500-10, 4Kv Circuit Breaker Trip and:
Directs an NLO to the Cribhouse to check 2/3 Service Water Pump and inspect 2A Service Water Pump.
Direct an NLO to check the breaker of 2A Service Water Pump.
Places control switch in Pull to Lock.
Notifies Ops Shift Supervisor.
Requests EMD to troubleshoot.
SRO Notifies Shift Manager and EMD.
Enters DOA 3900-01 Loss of Cooling by Service Water System.
Role Play:
NLO at 2/3 Service Water Pump (wait 5 mins):
Report: 2/3 Service Water Pump is operating normally and 2A Service Water Pump shows no sign of damage.
NLO at 2A Service Water Pump at Bus 23 (wait 5 mins):
Report: 2A Service Water Pump Breaker has overcurrent targets up.
EMD Acknowledges need to go to Bus 23 and troubleshoot overcurrent flag at 2A Service Water Pump breaker.
Event 6 Completion Criteria:
2/3 Service Water pump is running.
EMD has been dispatched to Bus 23 for troubleshooting.
AND, at the direction of the NRC Chief Examiner.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 12 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 7 & 8 Page 1 of 5 Event
Description:
An unisolable steam leak develops in the Reactor Building from the HPCI line.
Time Position Applicants Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 6, a 2.5% FEF and starts a HPCI line break at the HPCI 5 valve ramping to 100% in 2 mins.
NSO
Announces numerous alarms due to the HPCI steam line break and fuel element failure such as:
- 902-3 A-1, Rx Bldg Hi Rad
- 902-3 B-16, Rx Bldg Vent Ch A/B Rad Hi
- 902-3 A-3, Rx Bldg Vent Ch B Rad Hi Hi
- 902-3 C-12, HPCI Steam Flow Hi ANSO
Checks backpanel ARMs and determines that the areas affected are the torus area (primary) and also the east and west corner rooms/CRD areas.
NSO /
ANSO Performs DEOP 300-1, Secondary Containment Control actions as directed.
Verifies Rx Bldg Vent. isolates and SBGT starts.
Monitors affected areas temperatures and radiation levels
Operates all available area coolers (LPCI/CS and HPCI room coolers)
ANSO
Makes PA and/or plant radio announcements to evacuate the reactor and (maybe) turbine buildings.
May dispatch NLO and/or radiation protection technician to investigate the source of the leakage.
Determines that the leak is from the HPCI steam line either by plant knowledge, reports from the field, or by receiving alarm 902-3 C-12, HPCI Stm Line Flow Hi and reports to US.
Verifies HPCI steam line MOV 2301-5 is closed.
Determines leak is unisolable due to the HPCI MOV 2301-4 valve being unable to close.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 13 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 7 & 8 Page 2 of 5 Event
Description:
An unisolable steam leak develops in the Reactor Building from the HPCI line.
Time Position Applicants Actions or Behavior ROLE PLAY:
Individual to investigate leakage (wait 3 mins):
Report There is steam accumulating on the first floor of the reactor building on the east side, it appears to be coming from the torus access ladder, and that it is getting very hot and humid in the area.
NSO Performs the following actions per DGP 02-03, Reactor Scram:
Presses scram pushbuttons
Places mode switch in shutdown
Checks rods inserted; discovers ATWS condition
Initiates ARI
Verifies recirc pump speed at minimum.
SRO Enters DEOP 0100, RPV Control. When reaches required level of DEOP 300-1 order Reactor scram, exits DEOP 100 and enters DEOP 400-5, Failure to Scram, and directs the following:
Placing ADS to inhibit
Placing both CS pumps in PTL Power Leg
Running back recirc to minimum.
Tripping the recirc pumps
Directing Alternate Rod Insertion per DEOP 500-05:
manually driving rods.
repeated scram/resets.
Initiating SBLC before SP/T of 110°F.
Level Leg
Verification water level instruments are accurate
Verification any required automatic actions have occurred
Directing jumpers installed for MSIV low level and Off Gas high Rad isolations
Terminating and Preventing injection except boron and CRD until RPV/L is -35 inches.
If SP/T is above 110°F, lets level drop until:
Power is below 6%, OR Level drops to -143 in. (TAF), OR All ADSVs stay closed and PC/P stays below 2 psig
Re-establishing injection to MAINTAIN RPV water level above
-164 inches.
Pressure Leg
Maintaining <1060 psig using Bypass Valves.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 14 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 7 & 8 Page 3 of 5 Event
Description:
An unisolable steam leak develops in the Reactor Building from the HPCI line.
Time Position Applicants Actions or Behavior NSO /
ANSO Performs DEOP 400-5, Failure to Scram, actions as directed:
Places ADS to inhibit
Places both CS pumps in PTL Power Leg
Trips recirculation pumps
Performs Alternate Rod Insertion. (see below for specific actions)
Initiates boron injection. Reports SBLC has failed to inject.
Level Leg
Terminates and Prevents injection except boron and CRD until RPV/L is -35 inches.
If SP/T is above 110°F, lets level drop until:
- Power is below 6%, OR
- All ADSVs stay closed and PC/P stays below 2 psig
Re-establishes injection to MAINTAIN RPV water level above
-164 inches.
Pressure Leg
Maintains <1060 psig using Bypass valves.
NSO Performs manual control rod insertion per DEOP 500-05, Alternate Insertion of Control Rods, as directed:
Bypasses the RWM
Starts the second CRD pump
Maximizes drive water pressure using one or more of the methods in DEOP 500-05.
Inserts rods using RONOR in EMERG IN or the normal rod movement control switch NSO Performs repeated scram/resets per DEOP 500-05, Alternate Insertion of Control Rods, as directed:
Depresses close pushbuttons for SDV vent and drain valves
If RPV/L <-59 inches, directs pulling ARI fuses.
Attempts to reset scram
Directs scram jumpers installed.
Resets the scram
Verifies all scram valves closed
Opens the SDV vent and drains
When 902-5 C-1 clears, scrams reactor
Repeats as necessary
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 15 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 7 & 8 Page 4 of 5 Event
Description:
An unisolable steam leak develops in the Reactor Building from the HPCI line.
Time Position Applicants Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:
Operator to jumper the MSIV Group1-59 in. and offgas hi hi radiation isolations (wait 5 min):
Activate trigger 8 and report the MSIV Group1-59 in. and offgas hi hi radiation isolations are jumpered.
SIMULATOR OPERATOR / ROLE PLAY:
Operator to pull ARI fuses (wait 5 min):
Verify trigger 10 activated and report the ARI fuses are pulled.
Operator to install scram jumpers (wait 5 min):
Activate trigger 7 and report the scram jumpers are installed.
Based on failure of SBLC to inject, directs performance of DEOP 0500-01, Alternate Standby Liquid Control Injection.
SIMULATOR OPERATOR / ROLE PLAY:
Operator to install jumpers to defeat DW Cooler trips (wait 5 min):
Activate trigger 9 activated and report the DW Cooler trip jumpers are installed.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 16 of 24 Rev. 01 (11/02)
Op-Test No: ILT 01-1 Scenario No.: ILT-R-3 Event No.: 7 & 8 Page 5 of 5 Event
Description:
An unisolable steam leak develops in the Reactor Building from the HPCI line.
Time Position Applicants Actions or Behavior SIMULATOR OPERATOR:
After the crew has reset the scram and at the discretion of the NRC chief examiner, remove the SDV hydraulic lock.
SRO Based on report that all rods are inserted, exits DEOP 400-05, Failure to Scram, and enters DEOP100, RPV Control and directs:
Securing Boron injection if any was started.
Restoring RPV level to +8 to +48 inches.
NSO Reports that all rods inserted and performs the following as directed:
Restores level to +8 to +48 inches.
Scenario Completion Criteria:
Control Rods Inserted.
RPV level stabilized.
OR, at the direction of the NRC Chief Examiner.
Critical Tasks: Identified by in Guide
With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.
With a reactor scram required, reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion.
During an ATWS with conditions met to perform power/level control TERMINATE AND PREVENT INJECTION, with exception of boron and CRD, into the RPV until conditions are met to re-establish injection.
When conditions are met to re-establish injection use available injection systems to MAINTAIN RPV water level above -164.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 17 of 24 Rev. 01 (11/02)
REFERENCES PROCEDURE TITLE REVISION DAN 902-4 A-15 ISOL CONDR CH A/B INITIATION 14 DAN 902-6 G-10 LOW FLOW REG VLV LOCKUP 4
DAN 902-6 H-3 FW CONTROL SYSTEM PANEL TROUBLE 5
DAN 923-1 C-3 U2 OR U3 SERV WATER PP TRIP 2
DOP 0400-01 Reactor Manual Control System Operation 18 DOP 0600-06 Feedwater Regulating Valve (FRV) Operation 25 DOA 0300-06 RPIS Failure 14 DOA 5750-04 Smoke, Noxious Fumes or Airborne Contaminants In The Control Room 16 DOA 6500-10 4KV Circuit Breaker Trip 03 DGP 01-01 Unit Startup 101 DGP 02-03 Reactor Scram 60 DGP 03-04 Control Rod Movements 43 DGA 07 Unpredicted Reactivity Addition 14 DGA 16 Coolant High Activity/Fuel Element Failure 12 DEOP 0100-00 RPV Control 10 DEOP 0200-01 Primary Containment Control 10 DEOP 0300-01 Secondary Containment Control 07 DEOP 0400-02 Emergency Depressurization 04 DEOP 0400-05 Failure to Scram 12 DEOP 0500-02 Bypassing Interlocks and Isolations 12 DEOP 0500-05 Alternate Insertion of Control Rods 13
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 18 of 24 Rev. 01 (11/02)
PRE-SCENARIO ACTIVITIES
- 1. If applicable, conduct pre-scenario activities in accordance with TQ-AA-106-0107, SIMULATOR EXAMINATION BRIEFING.
- a. Provide the team with a copy of Control Room work request list.
- b. Provide the team with a copy of DGP 01-01, Unit Startup, which is marked up to the point of Step 78, Turbine testing complete and ready to synchronize the Main Generator to the Grid.
- c. If the team inquires about a startup plan, inform then the Shift Manager is maintaining it.
- d. Provide the team with a copy of the REMA.
- e. Inform the team that (select an individual) is the QNE present in the Control Room.
- f.
Direct the team to perform their briefs prior to entering the simulator.
- 2. Simulator Setup (the following steps can be done in any logical order)
- a. Initialize simulator in IC 10 and perform the following prior to proceeding below:
- 1) Bring up Monitor
- 2) At input box, type FLZ1265 and <Enter>.
- 3) At input box, type 1=F and <Enter>.
- 4) Verify variable FLZ1265 is set to FALSE.
- 5) Goto Run and ensure variable stays FALSE.
- 6) Run the Summary program and clear ALL remotes and overrides.
- 7) Verify 2A EHC and 2A Stator Cooling Water pumps running.
- 8) Verify backpanel lights are reset.
- 9) Start 2E Drywell Cooler.
- 10) Open OCB 2-3 and OCB 2-7 at Panel 923-2.
- 11) Open OCBs for Generator at Panel 902-8.
- 12) Close Generator Field Breaker at Panel 902-8.
- 13) Close MPT Disconnect at Panel 902-8.
- b. Run the initial setup caep file: ilt-r-3.cae
- c. Verify the following simulator conditions:
- 1) MWe at ~245.
- 2) Condensate Demin DP between 20 and 45 psid.
- 3) Condensate pump amps between 160 and 255 amps.
- d. Secure the following equipment and tag out of service:
- 1) Place IRM 15 902-5 panel joystick in bypass and place an Equipment Status Tag on it.
- e. Advance the chart recorders.
- f.
Mark up rod sequence for current rod positions.
- g. Complete the Simulator Setup Checklist.
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 19 of 24 Rev. 01 (11/02)
Computer Aided Exercise Programs ILT 01-1 NRC EXAM SCENARIO ILT-R-3 Initial Setup CAEP:
- ilt-r-3.cae
- Setup for ilt-r-3
- Written by MO
- Rev 00
- Date 10/02
- INITIAL CONDITIONS
- Inserts a hydraulic lock of the SDV imf rdhlvfpa 93 imf rdhlvfpb 93 imf rdhldega 95 imf rdhldegb 95
- Sets both SBLC relief valves to 50 psig imf scrlfvad 50 imf scrlfvbd 50
- Prevents an isolation of HPCI imf hp4vlbn
- SETUP EVENT TRIGGERS
- Event Trigger 1 inserts a blown fuse on the LFRV causing it to lock up trgset 1 "0" imf rlmlfbf (1)
- Event Trigger 2 replaces the blown fuse allowing the LFRV lock up to br rest trgset 2 "0"l2 trg 2 "dmf rlmlfbf"
- Event Trigger 3 causes a drift of the isolation condenser setpoint causing a spurious initiation of the isolation condenser trgset 3 "0"l3 imf icspdft (3) 900.0 2:00l3
- Event Trigger 4 ramps up the amps on the 2D condensate pump over two minutes trgset 4 "0"l4 ior fwicp4 (4) 300 2:00l4
- Event Trigger 5 inserts a trip of the 2A service water pump trgset 5 "0" imf q21 (5)l5
- Event Trigger 6 inserts a 2.5% FEF and starts a HPCI line break at the 2301-5 valve ramping to 100% in 2 minutes trgset 6 "0"l2 imf radffd (6) 2.5 imf hprbbrkp (6) 100.0 2:00 l2
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 20 of 24 Rev. 01 (11/02)
- Event Trigger 8 defeats all Group I isolation signals.
trgset 8 "0" irf cigp1jp (8) inl6 irf ci59jp (8) inl6 irf ogogjp (8) inl6
- Event Trigger 9 lifts drywell cooler leads per DEOP 500-2 trgset 9 "0" irf cidw28jp (9) in irf cidw29jp (9) in
- Event Trigger 10 clears the high amps on the condensate pump trgset 10 "fwdcbpn4.ne. 1"l6 trg 10 "dor fwicp4"l6
- Event Trigger 12
- END
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 21 of 24 Rev. 01 (11/02)
Date: TODAY Unit 2 Turnover ECCS Status:
All Online Information Shutdown Information MODE 1 0 MWe Online Risk:
Green CDF:
1.00 Risk Equipment:
Time to Boil: N/A Shutdown Risk: N/A Protected Path: N/A Unit 2 Priorities Station Priorities Continue startup LCORAs LCORA #
Start Title Clock Ends Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Continue Power Ascension Common Unit Activities Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress Unit 2 Conditions, Status, Abnormalities 2 hr ago 0500 IRM 15 OOS due to power supply failure. IMD waiting for replacement power supply to arrive from Quad Cities Station. Placed in DEL for tracking.
6 hr ago 5650 2B EHC pump OOS due to a problem with its pressure compensator. Expected BIS next shift.
Compensatory Actions, Extra Checks
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 22 of 24 Rev. 01 (11/02)
Equipment OOS Service Unit Status 2 hr ago 990045654 IRM 16 6 hr ago 990045652 2B EHC pump 9 days ago 2A Cond Demin Cut In 7 days ago 2B Cond Demin Cut In 16 days ago 2C Cond Demin Cut In 2 days ago 2D Cond Demin Cut Out 11 days ago 2E Cond Demin Cut Out 6 days ago 2F Cond Demin Cut Out 2 days ago 2G Cond Demin Cut Out 376 days ago 2A RWCU Cut In 240 days ago 2B RWCU Cut Out 20 days ago 2C RWCU Cut Out 76 days ago U2 FPC Demin Cut In Unit 2 Abnormal Component Position U2 Open Operability Determinations with Compensatory Actions Events and Misc. Information DGP 01-01 in progress. Continue the startup. Rod moves completed. Ready to increase power with recirculation flow.
The QNE is present in the control room.
DW samples:
Iodine 131 2.5 X 10-13 Beta/Gamma 1.5 X 10-11
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 23 of 24 Rev. 01 (11/02)
Date: TODAY Unit 3 Turnover ECCS Status: All available Online Information Shutdown Information MODE 4 910MWe Online Risk:
GREEN Risk Equipment: None Time to Boil: N/A.
Shutdown Risk: N/A Protected Path: N/A Unit 3 Priorities Station Priorities Continues safe full power ops LCORAs LCORA # None Start Title Clock Ends Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Common Unit Activities Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities IMD taking voltage readings in the EHC Control Panel 903-31.
Compensatory Actions, Extra Checks None Equipment OOS Service Unit Status None 5 days ago 3A Cond Demin Cut In 8 days ago 3B Cond Demin Cut In 10 days ago 3C Cond Demin Cut In 5 days ago 3D Cond Demin Cut In 3 days ago 3E Cond Demin Cut In 15 days ago 3F Cond Demin Cut In 3 days ago 3G Cond Demin Cut In 750 days ago 3A RWCU Cut In 390 days ago 3B RWCU Cut Out 60 days ago 3C RWCU Cut Out 444 days ago U3 FPC Demin Cut In
ILT 01-1 NRC RE-EXAM, Scenario ILT-R-3 Page 24 of 24 Rev. 01 (11/02)
Unit 3 Abnormal Component Position None U3 Open Operability Determinations with Compensatory Actions None Events and Misc. Information None