ML13354B869
| ML13354B869 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/25/2013 |
| From: | Walton R K NRC/RGN-III/DRS/OLB |
| To: | |
| Walton R K | |
| Shared Package | |
| ML11355A018 | List: |
| References | |
| Download: ML13354B869 (82) | |
Text
Dresden Generating Station ILT-N-1 ESTABLISH PRIMARY CONTAINMENT INERTING WITHDRAW RODS TO OPEN TURBINE BYPASS VALVES CONTROL ROD DRIFTS O UT APRM FAILS UPSCALE WITHOUT HALF SCRAM RFP VENT FAN TRIPS DUE TO OVERCURRENT HPCI SYSTEM SPURIOUS INITIATION LOCA IN DW - MANUAL SCRAM LOSS OF RFPS
- USE HPCI TO RESTORE LEVEL Rev. 00 0 8/13 Developed By:
Exam Author Date Approved By:
Facility Representative Date SCENARIO ILT
-N-1 Page 2 of 28 Rev. 00 (08/13)
Scenario Outline Station: Dresden Generating Station Scenario No.:
ILT-N-1 Class ID:
2013-301 Evaluators Operators / crew position
/ ATC / BOP / CRS Initial Conditions:
~5% Power , steady state, and equilibrium xenon Turnover: 2C RFP OOS Event No. Malf. No. Event Type* Event Description 1 NONE N BOP Establish Primary Containment Inerting Lineup Per D OP 1600-05 2 NONE R ATC Withdraw Rods To Open Turbine Bypass Valves 3 RODH08 DO C/T ATC Control Rod Drifts Out (TS) 4 NIA5POT I/T BOP APRM Fails Upscale Without Half Scram (T S) 5 X10 / X13 C ATC RFP Vent Fan - Trips Due To Overcurrent 6 HPINIT I/T BOP HPCI System Spurious Initiation (T S) 7 F41 M TEAM LOCA In D W - Manual Scram 8 H32 C TEAM Loss Of RFPs
- Use HPCI To Restore Level
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
SCENARIO ILT
-N-1 Page 3 of 28 Rev. 00 (08/13)
Scenario Objective Evaluate the Team's ability to operate the plant with a loss of RFPs requiring use of the HPCI system to restore and maintain RPV level. Scenario Summary
- 1. Unit is at ~
5%. 2. The Primary Containment was deinerted for a Drywell inspection. The Primary Containment is ready to be inerted. 3. The following equipment is OOS:
- a. 2C RFP for bearing replacement. Expected back next shift
. 4. LCOs: a. None Scenario Sequence After completing shift turnover, the BOP will establish Primary Containment Inerting Lineup per DOP 1600
-05, Primary Containment Inerting and Atmosphere Control
. After completing DOP 1600
-05, the Team will raise power to Open Turbine Bypass Valves per procedure DGP 01-01, Unit Startup. After a sufficient change in power has been observed, a CRD failure occurs, causing control rod H-08 to drift out. The crew should take actions per DOA 300
-05, Inoperable or Failed Control Rod Drives. Technical Specifications 3.1.3, Condition C, applies
. After the CRD failure is addressed, APRM 5 fails upscale without a half scram due to an APRM Trip Unit problem. The ATC must manually insert a half scram per DO P 0 5 00-0 7 , Insertion-Reset of Manual Half Scram. Technical Specification 3.3.1.1, Condition A, and TRM 3.3.a, Condition A apply
. After the APRM failure is addressed, the running RFP Vent fan trips. The standby fan does not automatically start as expected. The Team starts the standby fan per DAN 902(3)
-6, RFP Vent Fan Trip and/or DOA 5750-01, Ventilation System Failure.
After the RFP Vent Fan failure is addressed, a HPCI Inadvertent Initiation occurs due to setpoint drift. The Team will shutdown HPCI per DOP 2300
-04, High Pressure Coolant Injection System (HPCI) Shutdown. The CRS will reference Tech Specs and determine that LCOs 3.5.3. Condition A and 3.3.2, Condition A apply
. After the HPCI failure is addressed, a LOCA in the Drywell occurs, causing DW pressure to rise, and requiring a manual scram. The US will enter DGP 02
-03, Reactor Scram
. After the scram, a loss of RFPs occurs, requiring HPCI to be used to restore level per DEOP 100
-00, RPV CONTROL. Completion criteria: When RPV Water Level is being maintained and at the discretion of the Lead Examiner, place the simulator in FREEZE.
SCENARIO ILT
-N-1 Page 4 of 28 Rev. 00 (08/13)
Event One
- Establish Primary Containment Inerting T he BOP will establish Primary Containment inerting lineup. Malfunctions required: 0 (None) Success Path:
Performs DOP 1600-05, Primary Containment Inerting and Atmosphere Control
. Event Two
- Withdraw Rods to Open Turbine Bypass Valves The Team will raise power to Open Turbine Bypass Valves.
Malfunctions required:
0 (None) Success Path:
Performs DGP 01
-01, Unit Startup. Event Three
- Control Rod Drifts Out After a sufficient change in power has been observed, a control rod drifts out
. Malfunctions required:
1 (Control rod drift out
) Success Path:
Performs DOA 0 300-05, Inoperable or Failed Control Rod Drives
. Determines Technical Specifications requirements.
Event Four
- APRM Fails Upscale Without Half Scram APRM 5 fails upscale without a half scram due to an APRM Trip Unit problem.
Malfunctions required: 1 (APRM fails upscale without a half scram
) Success Path:
Inserts a half scram per DO P 0500-0 7 , Insertion-Reset of Manual Half Scram
. Determines Technical Specifications requirements.
Bypasses the APRM and resets the half scram per DOP 0500
-07, Insertion
-Reset of Manual Half Scram.
SCENARIO ILT
-N-1 Page 5 of 28 Rev. 00 (08/13)
Event Five
- RFP Vent Fan Trips Due To Overcurrent 2 A RFP Vent fan trips
. The standby fan fails to auto start.
Malfunctions required: 1 (2A RFP Vent fan trip with failure of standby fan auto start
) Success Path:
The Team manually starts 2B RFP Vent fan.
Event Six
- HPCI System Spurious Initiation A HPCI Inadvertent Initiation occurs due to setpoint drift.
Malfunctions required:
1 (Spurious HPCI initiation
) Success Path:
-04, High Pressure Coolant Injection System (HPCI) Shutdown
. Event Seven
- LOCA in DW - Manual Scram A LOCA in the Drywell occurs, causing DW pressure to rise, and requiring a manual scram.
Malfunctions required:
1 (Recirc loop leak)
Success Path:
Performs DGP 02
-03, Reactor Scram
. Performs DEOP 0100, RPV Control Performs.DEOP 0200-01, Primary Containment Control.
Event Eight
- Loss of RFPs - Use HPCI to Restore Level A loss of RFPs results in RPV level dropping. Malfunctions required:
1 (Loss of RFPs) Success Path:
Performs DOA 2300
-02, HPCI Fast Startup.
SCENARIO ILT
-N-1 Page 6 of 28 Rev. 00 (08/13)
PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre-scenario activities in accordance with TQ
-JA-150-08, 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 DGP 01
-01, Unit Startup.
- c. Provide the Team a Control Rod Sequence Package (CRSP) marked up for the current conditions.
- d. Provide the Team a marked-up copy of DOP 16 00-0 5 , Primary Containment Inerting and Atmosphere Control. 2 Simulator Setup (the following steps can be done in any logical order)
- a. Initialize simulator in an IC with the following:
- 1) Reactor power ~
5%. (IC 159 used for validation, Seq. 2I.0.0, BF78, completed thru step
- 19) 2) The Primary Containment deinerted.
3 Verify the following simulator conditions:
- a. Verify that IRMs are ranged up enough so they are low on scale or the HPCI event will cause a scram.
- b. Verify one FWRV in Master Auto.
- c. Verify 2A & 2C Cond/Boost pumps running with 2B & 2D pumps off.
- d. Verify 2D Cond/Boost pump in STBY.
- e. Verify 2B RFP running.
- f. Verify 2A RFP in STBY.
- g. Verify 3 cond demin beds cut in
. h. Verify the Cond Boost Min Flow open 90
-95%. i. Verify the Turbine is reset.
- k. Verify th at the Primary Containment atmosphere control lineup is as follow s : 1) PIC 2-8540-1, DW PRESS CONTLR, is in MAN and set to zero (0.0) psig.
- 2) PIC 2-1602-14, DW/TORUS DP CONTLR, is in MAN and set to zero (0.0) psid.
- 3) MO 2-1601-57, M-U VLV, closed
- 4) AO 2-1601-58, TORUS M
-U VLV, closed
- 6) AO 2-1601-21, DW PURGE VLV, open 7) AO 2-1601-22, VENT VLV, closed 8) AO 2-1601-55, ISOL VLV, op en 9) AO 2-1601-56, TORUS PURGE VLV, closed
- 12) AO 2-1601-61, TORUS 2
-IN VENT VLV, closed.
- l. Advance the chart recorders.
SCENARIO ILT
-N-1 Page 7 of 28 Rev. 00 (08/13)
NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
4 Run the initial setup CAEP file: ILT
-N-1.cae 5 Place the following equipment out of service:
- a. 2C RFP 6 Run the CAEP file: Pump_Sumps.cae 7 Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Time Critical Tasks PRA Key Operator Actions Required Actions Optional Actions
SCENARIO ILT
-N-1 Page 8 of 28 Rev. 00 (08/13)
Event One
- Establish Primary Containment Inerting Trigger Position Crew Actions or Behavior ROLE PLAY:
NLO in 2/3 EDG room to report :
Oxygen sample
- report "the oxygen level is at 21%".
TR 2/3-8503-1, 2/3 NITROGEN PURGE VAPORIZER OUTLET, reading
- report: If flow has not been started
- "the TR 2/3-8503-1, 2/3 NITROGEN PURGE VAPORIZER OUTLET , reading is 1 8 0 F. If flow has been started
- "the TR 2/3-8503-1, 2/3 NITROGEN PURGE VAPORIZER OUTLET, reading is 150 F. CRS Directs BOP to establish Primary Containment inerting per DOP 16 00-0 5 , Primary Containment Inerting and Atmosphere Control. BOP Establish es Primary Containment inerting per DOP 1600
-05, Primary Containment Inerting and Atmosphere Control, step G.9
- On 2-8540-5, U2 DW & TORUS O2 ANALYZ, select s the percent oxygen range switch to the lowest range that will maintain reading on scale.
(0-25%) On 2-8540-7, U2 DW & TORUS O2 SAMPLE SELECT
- o Place s stream mode switch in MANUAL. o Verifies the TORUS is selected for sampling
. BOP At Panel 902
-3, verifies the following valve lineup:
o MO 2-1601-57, M-U VLV, closed.
o AO 2-1601-58, TORUS M-U VLV, closed.
o AO 2-1601-59, DW M-U VLV, closed.
AO 2-1601-21, DW PURGE VLV, closed.
o AO 2-1601-22, VENT VLV, closed.
o AO 2-1601-55, ISOL VLV, open.
AO 2-1601-56, TORUS PURGE VLV, open.
o AO 2-1601-62, DW 2-IN VENT VLV, closed.
o AO 2-1601-23, DW VENT VLV, closed. o AO 2-1601-61, TORUS 2
-IN VENT VLV, closed.
o AO 2-1601-60, TORUS VENT VLV, closed.
SCENARIO ILT
-N-1 Page 9 of 28 Rev. 00 (08/13)
Event One
- Establish Primary Containment Inerting Trigger Position Crew Actions or Behavior BOP Verifies AO 2-1601-91, VENT TO RX BLDG EXH SYS at Panel 902(3)
-3 is open.
Open s AO 2-1601-60 , TORUS VENT VLV. Open s AO 2-1601-24, VENT TO RX BLDG EXH SYS.
At Panel 902-3, start s nitrogen flow to the torus by opening PCV 2
-8520 using PIC 2
-8540-1, DW PRESS CONTLR. Observes/Confirms Purge Flow by verif ying a temperature decrease on the Nitrogen inerting line in the 2/3 D/G Room.
Event 1 Completion Criteria:
Drywell inerting lineup established
, AND/OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-1 Page 10 of 28 Rev. 00 (08/13)
Event Two
- Withdraw Rods To Open Turbine Bypass Valves Trigger Position Crew Actions or Behavior ROLE PLAY:
At Lead Evaluators direction, inform the Team as the QNE that "I have completed review of core parameters and startup may continue".
CRS Directs pulling control rods:
Reviews REMA.
Designates second verifier.
Directs ATC 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 any control rod:
Control rod selected on the select matrix is correct rod.
Second Verification requirements satisfie
- d. Rod Out Permit light is illuminated.
Withdraws rods as follows
- Moves RONOR Switch to NOTCH OVERRIDE (use of RONOR is optional) and the Rod Movement Control switch to ROD OUT.
Verifies ON light 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.
BOP 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.
Verifies control rod at target position.
Event 2 Completion Criteria:
Sufficient power increase, AND/OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-1 Page 11 of 28 Rev. 00 (08/13)
Event Three
- Control Rod Drifts Out Trigger Position Crew Actions or Behavior 1 Simulator Operator:
At the discretion of the Lead examiner, activate trigger 1, which causes Control Rod H
-08 to drift out.
Role Play: EO to check H
-08 accumulator: Wait 2 min, then report "I see nothing abnormal at H
-08 accumulator.
WEC/EO to disarm H
-08: acknowledge the request. It is not intended to complete the request. QNE to evaluate core limits: Acknowledge the request. Wait 2 min. and report, "core parameters are within limits".
EO to close CRD H-08's 2-0305-102, WITHDRAW VLV: Wait 2 min. and report, "
CRD H-08's 2-0305-102 is closed".
ATC Announces 902
-5 A-3, Rod Drift, alarm.
Notices and announces that Control Rod H
-08 is drifting out.
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.
Subsequent:
Due to the CRD failing to remain at the FULL IN OR OVERTRAVEL IN position, continuously applies an emergency insert signal using EMERG ROD IN on RONOR switch. CRS Enters DOA 0300
-05, Inoperable or Failed Control Rod Drives, and directs actions.
May refer to Tech. Spec 3.3.2.1 Condition C.
BOP At back panel 902-16, places the scram toggle switch for CRD H
-08 to the UP position. ATC Releases RONOR switch.
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.
-08's 2-0305-102, WITHDRAW VLV, to prevent CRD discharge volume from filling.
SCENARIO ILT
-N-1 Page 12 of 28 Rev. 00 (08/13)
Event Three
- Control Rod Drifts Out Trigger Position Crew Actions or Behavior 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 H
-08. CRS Enters DOA 0300
-12, Mispositioned Control Rod.
CRS Directs taking rod H
ATC Takes rod H
Event 3 Completion Criteria:
When Control Rod H
-08 Has Been Inserted To Position 00, AND Tech Specs Have Been Addressed, AND/OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-1 Page 13 of 28 Rev. 00 (08/13)
Event Four
- APRM Fails Upscale Without Half Scram Trigger Position Crew Actions or Behavior 2 3 4 SIMULATOR OPERATOR
- At the discretion of the Lead Examiner, activate trigger 2, which fails APRM channel 5 upscale and defeats the half scram
. When APRM 5 is bypassed, verify the following Triggers automatically activate:
o Trigger 3 - Deletes RPS system fail to scram malfunction.
o Trigger 4 - Restores alarm 902
-5 D-13 to NORMAL.
ROLE PLAY:
IMD to troubleshoot APRM 5: Wait a few minutes and report that "the APRM 5's scram trip unit failed. The problem is isolated to only APRM 5.
ATC Announces the following alarms: o 902-5 A-6 , APRM HI o 902-5 B-4, OPRM TOUBLE/INOP o 902-5 C-3, ROD OUT BLOCK Verifies APRM 5 readings against other APRMs on 902-5 panel. Bypasses APRM 5 after T. S. compliance verified by CRS.
Resets RPS channel A per DOP 0500
-07, Insertion/Reset of Manual Half Scram, as follows: o Verifies half scram no longer required Turns the Scram Reset switch in each direction and verifies all eight white group solenoid lights are lit.
o Verifies alarm 902
-5 A-10, Channel A Manual Trip, resets.
BOP Performs the following actions per DAN 902
-5 A-6: Verifies APRM 5 readings against other APRMs on 902
-3 7 panel. Verifies APRM 5 function switch in operate.
TEAM Determines with the Mode Switch in STARTUP, a Channel B half scram should have occurred. CRS Directs a Channel B half scram be inserted per DOP 0500
-07, Insertion-Reset of Manual Half Scram
.
SCENARIO ILT
-N-1 Page 14 of 28 Rev. 00 (08/13)
Event Four
- APRM Fails Upscale Without Half Scram Trigger Position Crew Actions or Behavior ATC Performs 0500-07, Insertion-Reset of Manual Half Scram, as follows:
o Verifies both RPS Channels are reset AND the attendant annunciators are reset.
Depresses the Manual Scram CH B pushbutton.
o Verifies RED backlighting under Manual Scram pushbutton illuminates.
o Verifies ALL (four) Scram Solenoid Group lights extinguish for the appropriate RPS Channel.
o Verifies Annunciator 902
-5, A-15, (Channel B Manual Trip) alarms as appropriate.
o Verifies NO Control Rod movement has occurred.
o If half scram is to remain up for extended, time notifies BPO.
CRS References TS 3.3.1.1, Condition A
, and determines that sufficient channels are available.
References TS 3.3.1.1, Condition C, and determines that required to 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 />.
References TRM 3.3.a, Condition A, and determines that sufficient channels are available. Event 4 Completion Criteria:
APRM 5 bypassed, Half scram reset, AND Tech Spec determination complete.
AND / OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-1 Page 15 of 28 Rev. 00 (08/13)
Event Five
- RFP Vent Fan Trips Due To Overcurrent Trigger Position Applicant's Actions or Behavior NOTE: Ensure the ATC operator performs this Event 5 Simulator Operator:
At the discretion of the Lead Examiner, activate trigger 5 which causes 2A RFP vent fan to trip. The initial setup prevents 2B RFP vent fan from auto starting.
Role Pla y: NLO to check operation of 2B RFP vent fan: Wait 2 min, and then report that "2B RFP vent fan is operating normally".
NLO to check 2A RFP vent fan breaker: Wait 2 min, and then report "2A RFP vent fan breaker tripped on over current".
Note: Per DOP 57 50-06, Reactor Feed Pump Motor Ventilation System , fan control switches should be held in CLOSE for 45 seconds to allow airflow to develop.
If the Team does not successfully start 2B RFP Vent fan due to not holding the control switch long enough and to avoid RFP high stator temperature computer alarms, provide the following Role Play:
Role Play:
Cue as the Shift Manager to the CRS: "I recommend holding the 2B RFP Vent fan control switch to CLOSE for 45 sec."
ATC Acknowledges and announces alarm 902
-6 F-8, RFP Vent Fan Trip:
Determines 2B RFP Vent Fan did not auto start as expected and manually starts it.
Sends operator to check status of the 2A RFP vent fan breaker at Bus 25.
Sends operator to check operation of the 2B RFP vent fan.
Performs DOP 6700
-20, 480V Circuit Breaker Trip.
CRS Directs starting 2B RFP vent fan.
Enters DOP 6700
-20, 480V Circuit Breaker Trip.
BOP Assists as directed.
TEAM May reference DOP 5750-06, Reactor Feed Pump Motor Ventilation System
. May reference DOA 5750
-01, Ventilation System Failure.
Event 5 Completion Criteria:
2B RFP vent fan is started, AND / OR; At the direction of the Lead Examiner.
SCENARIO ILT
-N-1 Page 16 of 28 Rev. 00 (08/13)
Event Six
- HPCI System Spurious Initiation Trigger Position Applicant's Actions or Behavior 6 SIMULATOR OPERATOR
- At the discretion of the Lead examiner, activate trigger 6, which causes a Spurious HPCI Initiation.
BOP Announces initiation of HPCI.
TEAM Determines and announces HPCI injection not needed.
BOP May place HPCI Flow Controller to MAN and adjust demand to 0 to stop injection.
CRS Directs ANSO to shutdown HPCI either per DOP 2300
-04, High Pressure Coolant Injection System (HPCI) Shutdown, or its Hard Card.
BOP Shuts HPCI down as directed:
Places MO 2
-2301-4 valve control switch in Pull
-To-Lock. Places MO 2-2301-14 valve control switch in Pull
-To-Lock. Places HPCI on the turning gear.
NOTE: If the HPCI Trip push button is used to stop HPCI, releasing the push button allows HPCI to restart.
CRS May enter DGA 07, Unpredicted Reactivity Addition.
Notifies Shift Manager and IMD of Event.
ROLE PLAY: Respond as individual notified.
QNE to evaluate effect of transient on the RX: wait 2 min, and then report "RX parameters are within their limits".
ATC Monitors panels and assists as directed.
CRS References Technical Specifications and determines:
TS 3.5.1 Action G applies. Verify Isolation Condenser is OPERABLE immediately AND restore HPCI System to OPERABLE status within 14 days.
Event 6 Completion Criteria:
Actions taken to shutdown HPCI, Tech Specs addressed, AND / OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-1 Page 17 of 28 Rev. 00 (08/13)
Event Seven
- Manual Scram Trigger Position Applicant's Actions or Behavior 7 SIMULATOR OPERATOR:
At the discretion of the Lead examiner, activate trigger 7, which causes a small Recirc Loop leak to develop in the Drywell.
Role Play:
U-3 NSO to report Drywell pressure status: Report "U
-3 Drywell pressure is 1.2 psig and steady". TEAM Recognizes and announces that Drywell pressure is slowly rising.
May direct an operator to check the Unit 2 Drywell CAM.
May direct operators to search for leaks.
Role Play:
NLO to check Drywell CAM: (wait 2 min.)
Report, "The Drywell CAM is trending up".
NLO to search for leak Report, "I am on my way out to check for leaks".
NLO to check Cribhouse inlet temperature: (wait 5 min.)
Report, "Cribhouse inlet temp is 70 oF". CRS Enters and directs performance of DOA 0040
-01, Slow Leak.
Set Scram contingency of 1.5 psig DW pressure. (Since DW pressure starts much lower than normal, may set a lower pressure Scram contingency 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, Reactor Scram.
ATC Performs the following actions per DOA 0040
-01, Slow Leak, 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
SCENARIO ILT
-N-1 Page 18 of 28 Rev. 00 (08/13)
Event Seven
- Manual Scram Trigger Position Applicant's Actions or Behavior BOP Performs the following actions per DOA 0040
-01 Slow Leak, as directed:
Notifies Shift Supervisor and Rad Protection.
Monitors for EP conditions.
Directs search for leak.
Shutdown H 2 Addition. Makes PA announcement.
Verify Crib House inlet temperature is <95 oF. Initiates Torus cooling per "Hard Card".
o Places 316A/B and 318A/B keylock switches in MANUAL OVERRD.
o Verifies the third circ water pump is secured prior to starting the first CCSW pump. o IF starting torus cooling during a LOCA, THEN verifies RWCU recirc pump is tripped PRIOR to starting the first CCSW pump.
o Starts one CCSW pump in each loop and verifies 3A/B valves open.
o Starts at least one LPCI pump in each loop. (Starts additional LPCI pumps as required.)
o Adjusts CCSW flow controller to approximately 3500 gpm for one pump; > 5000 gpm two pumps. [Maintain LPCI/C 7 psid (1 LPCI Pump/loop)
OR 20 psid (two LPCI Pumps/loop)]
o Momentarily places 11A/B valve control switches to close. (IF 11A/B remain open or re-opened due to LPCI logic, then close valves as soon as possible.)
o IF required, obtains Unit Supervisor permission, THEN places 317 keylock switches to MANUAL OVERRD.
o Opens 21A/B and 20A/B valves in desired loop.
o Throttles open 38A/B valves until >
5000 gpm per LPCI pump is established (maintains LPCI pump discharge pressure >
125 psig). o Starts additional CCSW pumps if desired:
IF TR 86(32) LTC in MANUAL, THEN PRIOR to starting 3rd OR 4th CCSW PP, verifies voltage on applicable ECCS bus >
4000 volts, preferred target 4160V.
(Unit 2 Only) If 2/3 EDG is loaded, then refers to DOP 1500-02 prior to starting additional pumps.
o Adjusts CCSW flow controller to >
5000 gpm for two CCSW pumps [Maintain 7 psid (1 LPCI Pump/loop)
OR 20 psid (two LPCI Pumps/loop)].
ATC / BOP Performs scram preparatory actions per DGP 02
-03, Reactor Scram, as directe
- d. Starts MSP and TGOP.
Trips H 2 addition.
SCENARIO ILT
-N-1 Page 19 of 28 Rev. 00 (08/13)
Event Seven
- Manual Scram Trigger Position Applicant's Actions or Behavior ATC Performs the following actions per DGP 02
-03, Reactor Scram, as directed:
Presses scram pushbuttons Places mode switch in shutdown Check rods inserted.
Verifies Recirc Pumps run back.
Maintains RPV/L between
+25 and +35 inches or as directed by Unit Supervisor.
Inserts SRM/IRMs.
TEAM Verifies the following as time allows:
Group Isolations Automatic start of ECCS systems Automatic start of EDGs.
Event 7 Completion Criteria
SCENARIO ILT
-N-1 Page 20 of 28 Rev. 00 (08/13)
Event Eight - Loss Of RFPs
- Use HPCI To Restore Level Trigger Position Crew Actions or Behavior 8 SIMULATOR OPERATOR
- After the Team has stabilized the plant and at the discretion of the Lead Evaluator, activate trigger 8 , which causes the following:
Increases the size of the recirc leak
. After 1 min, trips the running RFP and prevents the available RFP from starting.
ROLE PLAY:
EO sent to check EDG operation: wait 3 min, then report: "Both EDGs are operating normally".
ROLE PLAY:
Acknowledge other requests; delay as necessary.
TEAM Determines/announces Drywell pressure rapidly rising.
CRS Enters DEOP 100, RPV Control, Directs actions of DEOP 100.
Verification of all isolations, ECCS and EDG starts.
Holding RPV/L +8 to +48 inches.
Maintaining RPV/P <1060 psig using Turbine Bypass valves
. 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 281F: 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 H 2/O 2 monitors.
SCENARIO ILT
-N-1 Page 21 of 28 Rev. 00 (08/13)
Event Eight - Loss Of RFPs
- Use HPCI To Restore Level Trigger Position Crew Actions or Behavior BOP Performs DEOP 0200
-01, Primary Containment Control, actions as directed:
Monitors PC/P and initiates torus sprays as directed:
Opens the 19A/B valve in desired loop.
Opens the 18A/B valve in desired loop.
Initiates drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed:
Opens the 27A/B and 28A/B valves in desired loop.
Adjusts sprays to maintain <
9 psig, but high enough to ensure ECCS NPSH by any combination of the following:
o Open or close 27A/B AND 28A/B valves in the desired containment spray loop.
o Throttling 21A/B OR 38A/B valves in the desired containment spray loop. (Maintain LPCI pump discharge pressure >
125 psig.) Monitors DW/T. Monitors SP/T and initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed.
(May already be initiated for previous Event)
Monitors SP/L.
Verifies initiation of drywell and torus H 2/O 2 monitors. ATC Determines/announces a RFP trip. Attempts to start the available RFP.
Announces loss of RFPs.
CRS Directs starting HPCI to restore and maintain RPV Level at the DEOP directed level band (+8 to +48).
BOP Starts HPCI as directed and restores level to the DEOP directed level band (+8 to
+48): Places the HPCI 14 valve in NORMAL.
Depress es AND hold s the HPCI REMOTE TURBINE TRIP Pushbutton.
Open s the HPCI 4 valve.
WHEN HPCI 4 valve is full open, THEN release HPCI TURBINE TRIP PUSHBUTTON.
Adjust s flow in Auto OR Manual Mode.
Start s HPCI Room Cooler. Event 8 / Scenario Completion Criteria:
Sprays the Drywell; AND, Starts HPCI to restore RPV level to DEOP directed level band
. AND / OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-1 Page 22 of 28 Rev. 00 (08/13)
Critical Tasks With a control rod drifting out to a position where core damage could occur, TAKE ACTION TO PLACE THE CONTROL ROD AT A SAFE POSITION (00). Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with available high
-pressure systems
. (RPV-5.1) When drywell pressure exceeds the suppression chamber spray initiation pressure or before containment pressure exceeds the Pressure Suppression Pressure, INITIATE drywell/containment sprays, while in the safe region of the drywell spray initiation limit or above the containment spray initiation pressure.
SCENARIO ILT
-N-1 Page 23 of 28 Rev. 00 (08/13)
REFERENCES PROCEDURE TITLE DAN 902-5 A-3 ROD DRIFT DAN 902-5 A-6 APRM HI DAN 902-5 A-15 CHANNEL B MANUAL TRIP DAN 902-5 B-4 OPRM TOUBLE/INOP DAN 902-5 C-3 ROD OUT BLOCK DAN 902-6 F-8 RFP VENT FAN TRIP DEOP 0100 RPV CONTROL DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DGA 07 UNPREDICTED REACTIVITY ADDITION DGP 01-01 UNIT STARTUP DGP 02-03 REACTOR SCRAM DGP 03-04 CONTROL ROD MOVEMENTS DOA 0040-01 SLOW LEAK DOA 0300-05 INOPERABLE OR FAILED CONTROL ROD DRIVES DOA 5750-01 VENTILATION SYSTEM FAILURE DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM OPERATION DOP 0500-07 INSERTION/RESET OF MANUAL HALF SCRAM DOP 1600-05 PRIMARY CONTAINMENT INERTING AND ATMOSPHERE CONTROL DOP 2300-04 HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) SHUTDOW N DOP 5750-06 REACTOR FEED PUMP MOTOR VENTILATION SYSTEM DOP 6700-20 480V CIRCUIT BREAKER TRIP TS 3.1.3 CONTROL ROD OPERABILITY TS 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TS 3.6.4.1 SECONDARY CONTAINMENT TRM 3.3.a CONTROL ROD BLOCK INSTRUMENTATION
SCENARIO ILT
-N-1 Page 24 of 28 Rev. 00 (08/13)
Simulator Scenario Review Checklist ILT-N-1 Quantitative Attributes 6 Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 3 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)
SCENARIO ILT
-N-1 Page 25 of 28 Rev. 00 (08/13)
CAEP Files
- ILT-N-1.cae # For ILT Class 12
-1 NRC Exam
- Written by MP
- Rev 00 # Date 08/13
- INITIAL CONDITIONS
- Opens the purge fan dampers to simulate the fan breakers OFF.
irf pcdamper open
- Simulates 2A DRYWELL AND TORUS PURGE EXHAUST FAN breaker OFF.
ior pcdtp57a trip ior pcdcl57a off ior pclof57a off
- Simulates 2B DRYWELL AND TORUS PURGE EXHAUST FAN breaker OFF.
ior pcdtp57b trip ior pcdcl57b off ior pclof57b off
- Ensures 2
-8505-501, U2 DW/TORUS N2 MU PCV 2
-8527 INLET ISOL VLV is closed.
irf p33 falsel2
- Ensures 2
-8503-500, U2 DW/TORUS N2 PURGE PCV 2
-8520 INLET ISOL VLV, is open irf p30 truel2
- Lines up Aux N2 tank to the vaporizer. irf p32 truel2
imf b12l2 # Overrides indications for APRM 5 Hi Hi.
imf ser1099 offl2 imf ser1165 offl2 ior nilaphh5 falsel4 ior nilbaphh5 falsel4 imf pp_w042_2v falsel4
- Inserts failure of 2B RFP Vent fan to auto start. imf x13l4
- EVENT TRIGGERS
- Event Trigger 1 Inserts control rod H
-08 drift out.
trgset 1 "0"l4 imf rodh08do (1)l4
- Event trigger 2 APRM 5 drifts upscale. The half scram is defeated.
Trgset 2 "0"l6 imf nia5pot (2) 30.0 2:00l6
Trgset 3 "rpd301b_drw"l6
SCENARIO ILT
-N-1 Page 26 of 28 Rev. 00 (08/13) trg 3 "dmf b12"l6
- Event trigger 4 Auto activates when APRM 5 is bypassed.
- Restores alarm 902
-5 D-13 to NORMAL.
Trgset 4 "nilapby(5)"l6 trg 4 "mmf ser1165 normal"l6
- Event Trigger 5 Inserts trip of 2A RFP Vent fan.
trgset 5 "0"l8 imf x10 (5)l8
- Event Trigger 6 Inserts a spurious HPCI initiation.
trgset 6 "0"l8 imf hpinit (6)l8 imf hppmpdg (6) 45.0l8
- Event Trigger 7 Inserts a small recirc loop leak.
trgset 7 "0"l8 trg 7"dmf hppmpdg"l8 imf f41 (7) 0.01`l8
- Event Trigger 8 Increases the recirc loop leak.
trgset 8 "0"l10 trg 8 "mmf f41 0.5"l10 imf h32 (8 60)l10 ior fwdsel1 (8 58) offl10 ior fwdrfp1 (8 58) offl10
- END SCENARIO ILT
-N-1 Page 27 of 28 Rev. 00 (08/13)
Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is in Mode 2 at ~
5% power Leading Thermal Limit: NA Action limit: NA Equipment Unavailable:
2C RFP OOS for bearing replacement. Expected back in 2 shifts.
Protected Equipment: None Unit 3 is in Mode 1 at Full Power Leading Thermal Limit: MAPRAT @ 0.819 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started:
LCO Expires:
TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Separator Pit as required. Outside operator monitor and pump as necessary. Today Chem Cleaning ventilation status:
HV-1A/EF-1A are secured due to HV
-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV
-1B throwing its belts. WO 1156150.
HVAC -1 ON. HV-2 running.
Switchyard Status Today TSO notified of oil leaks on 345 Kv BT 2
-3 CB (IR 810135) ComEd WO 6396128 Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area.
Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood.
SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work. Be careful.
SCENARIO ILT
-N-1 Page 28 of 28 Rev. 00 (08/13)
Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
fter assuming the shift, establish Primary Containment inerting per DOP 1600
-05, Primary Containment Inerting and Atmosphere Control. After Drywell inerting is in progress and QNE review is complete , continue Unit Startup by pulling control rods. **** Shift 3 Activities ****
Today **** Unit 2 Procedures In
-Progress **** Do Not Delete ****
-01, Unit Startup DOP 1600-05, Primary Containment Inerting and Atmosphere Control
Dresden Generating Station ILT-N-2 CORE SPRAY TEST WITH MIN FLOW AUTO
-CLOSE FAILURE LOWER POWER USING CONTROL RODS CONTROL ROD STUCK & REQUIRES HIGHER PRESSURE TO MOVE TORUS LEVEL PAM INSTRUMENT NOT QUALIFIED PER IMD SERVICE WATER PUMP DEGRADATION RECIRC RUNBACK DUE TO LOSS OF FW SIGNAL MANUAL SCRAM REQUIRED DUE TO REACTOR CORE INSTABILITIES FAILURE TO SCRAM (SBLC SUCCESSFUL)
Rev. 00 0 8/13 Developed By:
Exam Author Date Approved By:
Facility Representative Date SCENARIO ILT
-N-2 Page 2 of 28 Rev. 00 (08/13)
Scenario Outline Station: Dresden Generating Station Scenario No.:
ILT-N-2 Class ID:
2013-301 Evaluators Operators / crew position
/ ATC / BOP / CRS Initial Conditions:
100% Power , steady state, and equilibrium xenon Turnover: At beginning of shift, perform Core Spray Test Drop power using control rods Event No. Malf. No. Event Type* Event Description 1 AT17 C/T BOP CORE SPRAY TEST per DOS 1400
-05 with Min Flow Auto
-close Failure (TS) 2 NONE R ATC Lower Power Using Control Rods 3 RODD08ST C ATC CRD - Control Rod Stuck & Requires Higher Pressure to Move 4 NONE T SRO Torus Level PAM Instrument Not Qualified per IMD (TS) 5 Q31 / Q21 C BOP Service Water Pump Degradation 6 RLMRFPA(B)(C)
I ATC FW- Recirc Runback Due to Loss of FW Signal 7 RXMLGOSC / A55 M ALL Manual Scram REQUIRED
- Due to Reactor Core Instabilities 8 RDHLVFPA(B) / RDHLDEGA(B) M/C ALL Failure to Scram (SBLC successful) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
SCENARIO ILT
-N-2 Page 3 of 28 Rev. 00 (08/13)
Scenario Objective Evaluate the Team's ability to shutdown the reactor with an ATWS condition
. Scenario Summary
- 1. Unit is at 100%. 2. The following equipment is OOS:
- a. None. 3. LCOs: a. None Scenario Sequence After completing shift turnover, the BOP will perform a Core Spray Test per DOS 1400
-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available. During the test, a Min Flow Auto
-close failure will occur and will need to be addressed. Technical Specification 3.3.5.1, Condition A, applies (Table 3.3.5.1-1 Function 1.d, Core Spray Pump Discharge Flow
- Low (Bypass)
After completing DOS 1400
-05, the Team will lower power with control rods per procedure DGP 0 3-01, Power Changes.
After the required change in power has been observed, a CRD problem occurs causing a rod to stick. The Team should take actions per DOP 0400
-01, Reactor Manual Control System Operation. After the stuck rod is addressed, an IMD Supervisor contacts the CRS to inform him that a recently installed replacement part for Torus Level, LT 2-1641-5A, was found to be UNQUALIFIED. It functioned adequately during testing and calibration, but its performance cannot be assured under accident conditions. Tech Spec Bases and surveillance requirements are referenced to determine the Post Accident Monitoring Requirements. Technical Specification 3.3.3.1, Condition A, applies
. After the Torus Level Tech Spec is addressed, degradation of the 2A Service Water pump is recognized by the BOP. Pump amps are increasing, SW supply pressure is decreasing (if unrecognized initially, U2/3 Diesel Fire Pump Running annunciates, and eventually the 2A SW pump will trip). The failure is expected to be addressed by swapping pumps and investigating the 2A SW pump. After the SW Pump issue is addressed, a Recirc Runback occurs due to loss of FW Signal. The unit enters the unstable region of the Power to Flow Map. The ATC will address the runback per DAN 902
-4 G-4(8), 2A(B) Recirc Loop Lo Flow Limit, and DOA 0202
-03, Reactor Recirculation System Flow Control Failure
. The Team also performs DOA 0500
-01, Inadvertent Entry into the Unstable Power/Flow Region.
After the Recirc Runback is addressed, a Manual Scram is determined to be REQUIRED due to core instabilities per DGA
-02, Reactor Core Instabilities
. After the Instabilities are addressed per DGA
-02, the reactor will not scram as expected due to a hydraulic ATWS. Ultimately, SBLC injection will be successful in shutting down the reactor.
Completion criteria: When the reactor is shutdown, RPV Water Level is being maintained, and at the discretion of the Lead Examiner, Place the simulator in FREEZE.
SCENARIO ILT
-N-2 Page 4 of 28 Rev. 00 (08/13)
Event One
- Core Spray Test With Min Flow Auto
-Close Failure The BOP will perform a Core Spray Test per DOS 1400
-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available. During the test, a Min Flow Auto
-close failure will occur and will need to be addressed.
Malfunctions required:
1 (Core Spray Flow transmitter failure
) Success Path:
Performs DOS 1400-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available. Determines Technical Specifications requirements
. Event Two
- Lower Power Using Control Rods The Team will lower power with control rods per procedure DGP 03
-01, Power Changes
. Malfunctions required:
0 (None) Success Path:
Performs DGP 03-01, Power Changes. Event Three
- Control Rod Stuck & Requires Higher Pressure to Move A CRD problem occurs causing a rod to stick. Malfunctions required:
1 (Control rod stuck) Success Path:
Performs DOP 0400-01, Reactor Manual Control System Operation.
Determines Technical Specifications requirements.
Event Four
- Torus Level PAM Instrument Not Qualified Per IMD An IMD Supervisor contacts the CRS to inform him that a recently installed replacement part for Torus Level Transmitter , LT 2-1641-5A, was found to be UNQUALIFIED
. Malfunctions required:
0 (None) Success Path:
Determines Technical Specifications requirements
.
SCENARIO ILT
-N-2 Page 5 of 28 Rev. 00 (08/13)
Event Five - Service Water Pump Degradation Degradation of the 2A Service Water pump is recognized by the BOP
. Malfunctions required: 1 (Degradation of the 2A Service Water pump
) Success Path:
The Team starts a standby Service Water pump
.
Event Six
- Recirc Runback Due to Loss o f F W Signal Recirc Runback occurs due to loss of FW Signal
. The unit enters the unstable region of the Power to Flow Map. Malfunctions required:
1 (Loss of FW Signal
) Success Path:
Performs DOA 0202-03, Reactor Recirculation System Flow Control Failure
. Performs DOA 0500-01, Inadvertent Entry into the Unstable Power/Flow Region
. Event Seven
- Manual Scram Required Due to Reactor Core Instabilities A Manual Scram is determined to be REQUIRED due to core instabilities.
Malfunctions required:
2 (Core instabilities
) (OPRMs fail to cause a scram)
Success Path:
Performs DGA-02, Reactor Core Instabilities
. Performs DGP 02
-03, Reactor Scram.
Event Eight
- Failure to Scram (SBLC Successful)
A Hydraulic ATWS occurs when the Team attempts a manual scram
. Malfunctions required:
1 (Hydraulic ATWS
) Success Path:
Performs DEOP 0100, RPV Control.
Performs DEOP 0400
-05, Failure to Scram
.
SCENARIO ILT
-N-2 Page 6 of 28 Rev. 00 (08/13)
PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre
-scenario activities in accordance with TQ
-JA-150-08, SIMULATOR EXAMINATION BRIEFING. a. Direct the Team to perform their briefs prior to entering the simulator.
- b. Provide the Team a copy of DGP 0 3-01, Power Changes , marked-up ready to insert control rods
- c. Provide the Team a copy of DOS 1400-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available , marked-up ready to begin step I.5
. d. Provide the Team a marked
-up copy of the CRSP. 2 Simulator Setup (the following steps can be done in any logical order)
- a. Initialize simulator in an IC with the following: 1) Reactor power 100%. (IC 1 60 used for validation, Seq. 2 S.2.0, 7F9C) 3 Verify the following simulator conditions:
- a. Verify 2A and 3B Service Water pumps running with the others OFF
. b. Verify 902
-37 panel OPRM modules are reset.
- c. Start the 2A & 2B LPCI/CS Rm Coolers.
- d. Advance the chart recorders.
NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
4 Run the initial setup CAEP file: ILT-N-2.cae 5 Place the following equipment out of service:
- a. None 6 Run the CAEP file: Pump_Sumps.ca e 7 Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Time Critical Tasks PRA Key Operator Actions Required Actions Optional Actions
SCENARIO ILT
-N-2 Page 7 of 28 Rev. 00 (08/13)
Event One
- Core Spray Test With Min Flow Auto
-Close Failure Trigger Position Crew Actions or Behavior 1 Simulator Operator:
Verify trigger 1 automatically activates when 2A Core Spray PP starts. This fails 2A Core Spray system ATS flow transmitter so M O 2-1402-38A, 2A Min Flow Vlv, fails to close
. ROLE PLAY:
E O at 2A Core Spray pump directed per
- Step I.5.a to verify closed 2-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV, wait 1 min, and then report "the 2-1402-40A-SV, U2 CORE SPRAY PI 2-1402-40A INST SV is closed". Step I.5.b to check 2A Core Spray motor oil level, report Pump Motor Oil level is
+1/8 inches of the Oil Sightglass Standstill Line
. Step I.5.d to open 2-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV , wait 1 min, and then report "the 2-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV is open". Step I.5.e to report the pressure indicated by PI 2
-1402-40A, 2A CORE SPRAY PUMP SUCTION, report "the pressure indicated by PI 2
-1402-40A, 2A CORE SPRAY PUMP SUCTION, is 6.5 psig.
Directed per step I.5.z to close 2-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV, wait 1 min, and then report "the 2
-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV is closed" Directed to check the running pump, report "The 2A Core Spray is operating normally."
Shift Manager: when notified that MO 2-1402-38A, 2A MIN FLOW VLV, did not close as required: direct the Team to "shutdown 2A Core Spray system pending investigation".
CRS Directs BOP to perform DOS 1400-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available
. BOP Performs DOS 1400-05, Core Spray System Pump Operability and Quarterly IST Test with Torus Available, starting at step I.5
- Ensure s the following valves are aligned as stated below:: o MO 2-1402-4A FLOW TEST VLV CLOSED o MO 2-1402-38A 2(3)A MIN FLOW VLV OPEN o 2-1402-6A MANUAL VLV (MCR) OPEN o MO 2-1402-25A PP DISCH VLV CLOSED o MO 2-1402-3A PP SUCT VLV OPEN o 2-1402-40A-SV U2(3) CORE SPRAY o PI 2-1402-40A INST SV CLOSED SCENARIO ILT
-N-2 Page 8 of 28 Rev. 00 (08/13)
Event One
- Core Spray Test With Min Flow Auto
-Close Failure Trigger Position Crew Actions or Behavior BOP Directs EO to check 2A Core Spray motor oil level AND record results on Data Sheet 1. Verifies 2A LPCI/Core Spray Room Cooler is operating properly if available.
Directs EO to open 2-1402-40A-SV, U2 CORE SPRAY PI 2-1402-40A INST SV.
Directs EO to report the pressure indicated by PI 2-1402-40A, 2A CORE SPRAY PUMP SUCTION (Pump Stopped), and record s on Data Sheet 1
.Obtain s 2-1402-8A initial closed dP:
(See procedure)
Notifies CRS that Core Spray System Div 1 is inoperable.
Start s 2A CORE SPRAY PP.
Verifies following annunciators alarm: o 902-3 H-13, LPCI/CS PP AT PRESS. o 902-3 A-5, CORE SPRAY PP RUNNING
. Open s MO 2-1402-4A, FLOW TEST VLV.
Observes and reports to the CRS that MO 2-1402-38A, 2A MIN FLOW VLV, did not close as required.
(Tech Spec SR 3.3.5.1.2, partial)
CRS Declares Core Spray System Div. 1 inoperable for the surveillance. When notified the 2A Core Spray Min Flow valve did not close as expected:
Refers to Tech Spec SR 3.3.5.1.2 and determines Condition E requires restoring to operable status within 7 days.
Refers to Tech Spec 3.5.1 and determines restore low pressure ECC S injection/spray subsystem to OPERABLE status within 7 days.
. May reference Tech Spec 3.6.1.3 (PCIV). The valve will still close with the pump not running.
Notifies Shift Manager and station support groups.
Directs the BOP to shutdown 2A Core Spray System
. BOP Shuts down 2A Core Spray pump starting at step I.5.t:
Closes MO 2
-1402-4A, FLOW TEST VLV.
Stops 2A CORE SPRAY PP.
Directs EO to close 2-1402-40A-SV, U2 CORE SPRAY PI 2
-1402-40A INST SV.
Event 1 Completion Criteria:
Technical Specifications referenced, AND/OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-2 Page 9 of 28 Rev. 00 (08/13)
Event Two
- Lower Power Using Control Rods Trigger Position Crew Actions or Behavior NOTE: The last control rod to be inserted is the stuck rod for the next Event. CRS Directs inserting control rods:
Reviews REMA.
Designates second verifier.
Directs ATC to insert rods. ATC Performs the following actions per DOP 0400
-01, Reactor Manual Control System Operation, and DGP 03
-04, Control Rod Movements, as directe d 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.
Inserts rods as follows
- Moves the Rod Movement Control switch to ROD IN. Verifies ON light and proper Control Rod Timer operation.
Releases switch before target position is reached.
Verifies rod settles to target position and proper response of nuclear instrumentation.
BOP 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.
Verifies control rod at target position.
Event 2 Completion Criteria:
The Team encounters the stuck control rod , AND/OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-2 Page 10 of 28 Rev. 00 (08/13)
Event Three
- Control Rod Stuck & Requires Higher Pressure to Move Trigger Position Crew Actions or Behavior NOTE: The last control rod to be inserted in the previous Event is the stuck rod for this Event. 2 Simulator Operator:
Verify trigger 2 automatically activates when:
-08 is selected
- Drive water pressure is greater than 375 psig; and, E ither the Rod Movement Control switch is placed to the ROD IN position, or the Rod Out Notch Override is placed to the EMERG ROD IN position.
This deletes Control Rod D-08 stuck malfunction
. Role Play:
EO to check D-08 accumulator: Wait 2 min, then report "I see nothing abnormal at D-08 accumulator.
Shift Manager / QNE to concur with raising drive water pressure: advise the CRS that "I concur with raising drive water pressure".
ATC Observes and announces that Control Rod D-08 did not move using normal drive pressure. Requests permission from CRS to raise drive water pressure per DOP 0400-01, Reactor Manual Control System Operation, to attempt to move the control rod.
CRS May contact Shift Manager and/or QNE for concurrence to raise drive water pressur e. Directs ATC to raise drive water pressure per DOP 0400-01, Reactor Manual Control System Operation, to attempt to move the control rod.
NOTE: The pressure is to be raised incrementally to the following ranges for each attempt to move the rod:
280 to 320 psid (~300 psid) 320 to 380 psid
(~350 psid) 380 to 420 psid
(~400 psid; the control rod will move)
ATC Repeats the following until the control rod moves:
Raise s drive water pressure per DOP 0400
-01, Reactor Manual Control System Operation, (Attachment B) as follows:
o May place FIC 2
-340-1, CRD Flow Contlr, in MAN if desired.
Throttl es closed MO 2
-302-8, DRIVE WTR PCV, to establish the desired drive water pressure.
Attempt s to move the control rod.
SCENARIO ILT
-N-2 Page 11 of 28 Rev. 00 (08/13)
Event Three
- Control Rod Stuck & Requires Higher Pressure to Move Trigger Position Crew Actions or Behavior ATC Observes and announces that the stuck control rod moved with ~400 psid.
Returns the drive water pressure to the normal band by throttling open MO 2-302-8, DRIVE WTR PCV.
(250 to 280 psid
) May place FIC 2
-340-1, CRD Flow Contlr, back to AUTO if desired.
Completes moving the rod to its target position.
Event 3 Completion Criteria:
When Control Rod D-08 Has Been moved to its target position , AND/OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-2 Page 12 of 28 Rev. 00 (08/13)
Event Four
- Torus Level PAM Instrument Not Qualified Per IMD Trigger Position Crew Actions or Behavior ROLE PLAY: Call as an IMD Supervisor and report "a recently installed replacement part for Torus Level, LT 2-1641-5A, was found to be UNQUALIFIED. It functioned adequately during testing and calibration, but its performance cannot be assured under accident conditions
". CRS References Licensing documents and determines:
TS 3.3.3.1, Condition A, applies: restore to operable status within 30 days.
Event 4 Completion Criteria:
Tech Spec determination complete.
AND / OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-2 Page 13 of 28 Rev. 00 (08/13)
Event Five
- Service Water Pump Degradation Trigger Position Applicant's Actions or Behavior 3 4 5 SIMULATOR OPERATOR:
At the discretion of the Lead Examiner, activate trigger 3, which simulates degradation of the 2A Service Water Pump.
May take several minutes for the alarm to come in.
Verify trigger 4 automatically activates when a standby service water pump is started.
Verify trigger 5 automatically activates when 2A service water pump is stopped.
FLOOR INSTRUCTOR / EVALUATOR
- When the 2/3 DFP pump starts, announce the XL
-3 is alarming and hand the XL
-3 sheet to the responding operator.
ROLE PLAY: EO at 2A Service Water Pump (wait 2 min.):
Report: "2A Service Water Pump motor is hotter than normal and making an abnormal noise
". EO at Service Water Pump just started (wait 2 min.):
Report: "The Service Water Pump is operating normally".
EO at 2A Service Water Pump breaker at Bus 23 (wait 2 min.):
If stopped by the BOP, then report: "2A Service Water Pump Breaker is open with no targets up".
If tripped by overcurrent malfunction, the report: "2A Service Water Pump Breaker is open and has overcurrent targets up".
EMD: Acknowledges need to go to Bus 23 and troubleshoot. If the 2A Service Water Pump tripped due to the malfunction. Report "an overcurrent flag is up at 2B Service Water Pump breaker".
6 7 SIMULATOR OPERATOR
/ ROLE PLAY
- EO to stop the 2/3 DFP: wait 2 min, then activate trigger 6 which stops the 2/3 DFP. Report to the BOP that "the 2/3 DFP is shutdown".
Verify trigger 7 automatically activates when the 2/3 DFP stops. This returns the Remote for stopping the DFP to normal.
BOP Announces 2/3 DFP started as indicated by alarm 923-1 G-4 , 2/3 DIESEL FIRE PP RUNNING, and its control switch lights.
Dispatches an operator to the Crib House to check 2/3 DFP operation.
Checks Service Water pressure and pump operation.
Announces that 2A Service Water pump amp indication is high and system pressure is low. Directs operator at Crib House to check 2A Service Water Pump.
Starts an available Service Water Pump.
Stops 2A Service Water Pump.
Directs the EO at the Cribhouse to check the Service Water Pump just started
. Direct an EO to check the breaker of 2 A Service Water Pump.
SCENARIO ILT
-N-2 Page 14 of 28 Rev. 00 (08/13)
Event Five
- Service Water Pump Degradation Trigger Position Applicant's Actions or Behavior CRS May enter DOA 3900
-01, Loss of Cooling by Service Water System.
May enter DOA 6500
-10, 4Kv Circuit Breaker Trip.
Directs swapping Service Water pumps.
May direct stopping 2/3 DFP May refer to TRM 3.7.i, Fire Water Supply System , Restore equipment to OPERABLE status within 7 days
. BOP If 2 A Service Water Pump trips, refers to DOA 6500
-10, 4Kv Circuit Breaker Trip and:
Places 2 A Service Water Pump control switch in Pull to Lock.
ATC Assists as directed.
TEAM Notifies Ops Shift Supervisor.
Requests EMD to troubleshoot.
Event 5 Completion Criteria:
Standby Service Water Pump started, AND / OR; At the direction of the Lead Examiner.
SCENARIO ILT
-N-2 Page 15 of 28 Rev. 00 (08/13)
Event Six
- Recirc Runback Due to Loss of FW Signal Trigger Position Applicant's Actions or Behavior 8 9 SIMULATOR OPERATOR
- At the discretion of the Lead examiner, activate trigger 8, which causes all RFP flow transmitters to fail downscale
. Verify trigger 9 automatically activates when the CH A OPRM Enabled light turns ON.
This Manually enables CH B OPRMs. (Necessary since they are bypassed and it is desired to make them appear available)
ATC Announces alarms: o 902-5 G-8, 1-Element FW Control Active at Hi Flow. o 902-6 H-3, FW Control System Panel Trouble Then after a short delay:
o 902-4 G-4(8), 2A(B) Recirc Loop Lo Flow Limit o 902-5 E-8, RPV Lvl Hi Announces Recirc pumps ran back to minimum.
CRS Enters DOA 0600
-01, Transient Level Contro l Enters DOA 0202-03, Reactor Recirculation System Flow Control Failure ATC May attempt to lock out the Recirc MG Set scoop tubes. Will be unsuccessful
. May take manual control of FWLC. This is not necessary.
NOTE: Loss of the FW flow transmitters results in a loss of the core thermal power calculation. The Team must rely on the APRMs and Generator load for estimates of core power.
CRS Analyzes that operation is in the unstable region of the Power to Flow Map.
Enters DOA 0500
-01, Inadvertent Entry Into The Unstable Power
/Flow Region
. Enters DGA
-02, Reactor Core Instabilities May enter DGA
-07, Unpredicted Reactivity Addition.
Notifies Shift Manager and IMD of Event.
ROLE PLAY: Respond as individual notified.
QNE to evaluate core power: wait 2 min, and then report "APRM power indication is accurate". ATC Performs DOA 0500-01, Inadvertent Entry Into The Unstable Power
/Flow Region , actions as directed:
Monitor s APRMs, available LPRMs, AND SRM period meters for Reactor Core instabilities in accordance with DGA
-02, Reactor Core Instabilities.
Reduces FCL to exit the unstable region by inserting CRAM rods per DGP 03
-04. BOP Monitors panels and assists as directed.
SCENARIO ILT
-N-2 Page 16 of 28 Rev. 00 (08/13)
Event Six
- Recirc Runback Due to Loss of FW Signal Trigger Position Applicant's Actions or Behavior Event 6 Completion Criteria
- Actions in progress to exit the unstable region of the Power/Flow Map
, AND / OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-2 Page 17 of 28 Rev. 00 (08/13)
Event Seven
- Manual Scram Required Due to Reactor Core Instabilities Trigger Position Applicant's Actions or Behavior 1 0 11 12 SIMULATOR OPERATOR:
At the discretion of the Lead examiner or if the crew begins inserting cram rods, activate trigger 10, which causes core oscillations to begin
. Verify trigger 11 automatically activates when the Rx is scrammed. This Ramps Core Power oscillations to 0.0 over 1 min. Verify trigger 12 automatically activates when Trigger 11 is active AND core oscillation severity is <0.1. This Changes Core Oscillation Constant back to original value
. NOTE: The oscillations will slowly build in. If the Team does not manually scram, eventually the OPRMs will reach the scram setpoint. The Channel B OPRM scram is defeated, so a manual scram is required to stop the oscillations.
ATC Recognizes and announces that core parameters have begun oscillatin
- g. Announces alarm 902
-5 E-6, OPRM Alarm.
May continue to insert Cram rods.
CRS When core oscillations meet the DGA
-02 criteria, directs insertion of a manual reactor scram.
ATC When core oscillations meet the DGA
-02 criteria, inserts a manual reactor scram. (See next Event for actions)
BOP Monitors panels and assists as directed.
Event 7 Completion Criteria
SCENARIO ILT
-N-2 Page 18 of 28 Rev. 00 (08/13)
Event Eight - Failure to Scram (SBLC Successful)
Tri gger Position Crew Actions or Behavior 13 14 15 16 Simulator Operator / Role Play:
When requested: Wait several minutes and as directed by the Floor Instructor, activate the appropriate trigger and report completed.
Trigger 13: Closes the CRD Charging Water Valve
. Trigger 14:
bypasses MSL GP 1 RPV/L and Offgas High Rad.
Trigger 15: pulls ARI fuses
. Trigger 16: installs scram jumpers ATC Performs the following actions per DGP 02
-03, Reactor Scram, as directed:
Places Mode Switch to Shutdown and depresses the Scram pushbuttons.
Checks rods inserted and observes they are not inserted Initiates ARI.
Announces hydraulic ATWS.
CRS Enters DEOP 100, RPV Control, and directs actions.
Due to report of ATWS condition, exits DEOP 100 AND enters DEOP 0400
-05, Failure to Scram, and directs/performs actions:
Placing ADS to inhibit.
(Conditions are not expected which would cause ADS to initiate. Therefore, this is not a critical task)
Placing Core Spray pumps in PTL.
Inserting control rods using Alternate Rod Insertion. Directs driving control rods.
Verifying required auto actions.
Installing of the jumpers for the MSIV low level isolations and the Off Gas high Rad isolations.
If RX power >6%, and > -35 inches RPV level , terminating and preventing all injection except boron and CRD until RPV level 35 inches.
Holding RPV level between
-164 inches and the level lowered to.
Stabilizing RPV pressure below 1060 psig.
ATC Run s Recirc pumps back to minimum
. Rapidly lower s reactor level by lowering RX LOW FLOW CONTROL STATION 2-640-20 FWLC SETPOINT to
-40 inches. Trip s the recirc pumps
. Initiate s ONLY one train of SBLC. BOP Plac es ADS to inhibit.
(Conditions are not expected which would cause ADS to initiate. Therefore, this is not a critical task)
Places Core Spray pumps in PTL.
SCENARIO ILT
-N-2 Page 19 of 28 Rev. 00 (08/13)
Event Eight - Failure to Scram (SBLC Successful)
Tri gger Position Crew Actions or Behavior ATC / BOP Drives control rods per DEOP 0500-05, Alternate Insertion Of Control Rods, as follows: (RPV
-6.1) Bypasses the RWM.
Maximizes CRD drive water pressure.
Inserts Control Rods by either using the ROD MOVEMENT CONTROL switch or the EMERG ROD IN position of the ROD OUT NOTCH OVERRIDE switch.
Performs Scram/Reset/Scram per DEOP 0500-05, Alternate Insertion Of Control Rods, as follows:
(Will not be successful)
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.
Event 8 / Scenario Completion Criteria:
All control rods inserted, AND / OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-2 Page 20 of 28 Rev. 00 (08/13)
Critical Tasks Given core instabilities where core damage could occur, TAKE ACTION TO SCRAM the reactor (RPV-6.1) 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.
(RPV-6.2) With a reactor scram required, reactor not shutdown, and conditions for AD S blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion.
(Conditions may not occur to cause this to be critical for this scenario)
(RPV-6.3) 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.
(RPV-6.4) When conditions are met to re
-establish injection use available injection systems to MAINTAIN RPV water level above
-164".
SCENARIO ILT
-N-2 Page 21 of 28 Rev. 00 (08/13)
REFERENCES PROCEDURE TITLE DAN 902-3 A-5 CORE SPRAY PP RUNNING DAN 902-3 H-13 LPCI/CS PP AT PRESS DAN 902-4 G-4(8) 2A(B) RECIRC LOOP LO FLOW LIMIT DAN 902-5 E-6 OPRM ALARM DAN 902-5 E-8 RPV LVL HI DAN 902-5 G-8 1-ELEMENT FW CONTROL ACTIVE AT HI FLOW DAN 902-6 H-3 FW CONTROL SYSTEM PANEL TROUBLE DAN 923-1 G-4 2/3 DIESEL FIRE PP RUNNING DEOP 0100 RPV CONTROL DEOP 0400-05 FAILURE TO SCRAM DEOP 0500-05 ALTERNATE INSERTION OF CONTROL RODS DGA-02 REACTOR CORE INSTABILITIES DGA-07 UNPREDICTED REACTIVITY ADDITION DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DGP 03-04 CONTROL ROD MOVEMENTS DOA 0202-03 REACTOR RECIRCULATION SYSTEM FLOW CONTROL FAILURE DOA 0500-01 INADVERTENT ENTRY INTO THE UNSTABLE POWER/FLOW REGION DOA 0600-01 TRANSIENT LEVEL CONTROL DOA 3900-01 LOSS OF COOLING BY SERVICE WATER SYSTEM DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM OPERATION DOS 1400-05 CORE SPRAY SYSTEM PUMP OPERABILITY AND QUARTERLY IST TEST WITH TORUS AVAILABLE TS 3.3.3.1 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TS 3.3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TS 3.6.4.1 SECONDARY CONTAINMENT
SCENARIO ILT
-N-2 Page 22 of 28 Rev. 00 (08/13)
Simulator Scenario Review Checklist ILT-N-2 Quantitative Attributes 7 Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 3 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) 4 Crew critical tasks (2 to 3)
SCENARIO ILT
-N-2 Page 23 of 28 Rev. 00 (08/13)
CAEP Files
- ILT-N-2.cae # For ILT Class 12
-1 NRC Exam
- Written by MP
- Rev 00 # Date 08/13
- INITIAL CONDITIONS
- Inserts SDV Hydraulic Lock imf rdhlvfpa 90.5 imf rdhldega 90.5 imf rdhlvfpb 90.5 imf rdhldegb 90.5
- Sticks control rod D-08 imf rodd08st
ior opdbypsw4 bypassl2 ior opdbypsw5 bypassl2 ior opdbypsw6 bypassl2 ior opdbypsw8 bypassl2 ior opdivbyp2 falsel2
ior rrdaslko offl4 ior rrdbslko offl4
- Changes a Core Oscillation Constant to expand the region oscillation occurs.
set thklapf2 = 1.3l4
- EVENT TRIGGERS
- Event Trigger 1 Activates when 2A Core Spray PP starts.
- Fails 2A Core Spray system ATS flow transmitter so Mo 2
-1402-38A, # 2A Min Flow Vlv, fails to close.
trgset 1 "cssbkppa"l4 imf at17 (1) 100.0l4
- Event Trigger 2 Activates when control rod D
-08 is selected, # drive water pressure is greater than 375 psig and
- when either the Rod Movement Control switch is placed to the ROD IN position, # or the Rod Out Notch Override is placed to the EMERG ROD IN position.
- Deletes the control rod D
-08 stuck rod malfunction to allow the rod to move.
trgset 2 "rdlselw(85) .and. (rddpdriv .gt. 375.0) .and. (rds302in.or. rds303em)"l22 trg 2 "dmf rodd08st"l6
- Event trigger 3 Degrades 2A Service Water PP.
Trgset 3 "0"l6 imf q31 (3) 25.0 10:00 15.0l6 ior wsgip1 (3) 1.0 10:00 0.5l6 imf q21 (3 10:00)l6
- Event trigger 4 Activates when a standby Service Water PP is started.
- Stops the degradation so parameters look normal.
Trgset 4 "wssp(2) .or. wssp(3) .or. wssp(4) .or. wssp(6)"l8
SCENARIO ILT
-N-2 Page 24 of 28 Rev. 00 (08/13) trg 4 "mmf q31 (0 10) 0.0"l8
- Event trigger 5 Activates when 2A Service Water PP breaker opens.
- Stops the degradation so parameters look normal.
Trgset 5 ".not. wssp(1)"l8 trg 5 "dor wsgip1"l8
- Trigger 6 Stops 2/3 DFP.
trgset 6 "0"l8 irf w14 (6) truel8
- Trigger 7 Clears the remote for stopping 2/3 DFP.
trgset 7 "et_array(6) .and. (.not. wssef)"l10 trg 7 "irf w14 false"l10
- Event Trigger 8 Fails RFP flow transmitters downscale.
trgset 8 "0"l10 imf rlmrfpa (8)
-6e+6l10 imf rlmrfpb (8)
-6e+6l10 imf rlmrfpc (8)
-6e+6l10 ior flds302a (8) depressedl12 imf ser1274 (8) onl12
trgset 9 "opdivtrp(1)"l12 ior oprmen4 (9) enablel12 ior oprmen5 (9 2) enablel12
ior oprmen6 (9 2) enablel12 ior oprmen8 (9) enablel14
- Event Trigger 10 Starts core oscillations.
trgset 10 "0"l14 trg 10 "ramp thpcdr 0.03 0.12 6:00"l14 imf rxmlgosc (10) 4.0 2:00 2.0l14 imf a55 (10 2)l14
- Trigger 11 # Activates when the Rx is scrammed.
- Ramps Core Power oscillations to 0.0 over 1 min.
trgset 11 "rpdmode4_drw .or. (rpl301a .and. rpl301b)"l16 trg 11 "imf rxmlgosc 0.0 1:00"l16 # Trigger 12 Activates when Trigger 11 is active AND core oscillation severity is <0.1.
- Changes Core Oscillation Constant back to original value.
trgset 12 "et_array(11) .and. (core_osc .lt. 0.1)"l16 trg 12 "set thklapf2 = 2.0"l16
- Trigger 13 Closes the CRD Charging Water Valve trgset 13 "0"l16 irf rd25pos (13) 0.0l16
- Trigger 14 Installs jumpers to bypass RPV low level MSIV and Off Gas Hi Rad Isolations trgset 14 "0"l18 irf ci59jp (14) inl18 irf ogogjp (14) inl18
- Trigger 15 Pulls ARI fuses.
trgset 15 "0"l18 irf aw4 (15) pulledl18
SCENARIO ILT
-N-2 Page 25 of 28 Rev. 00 (08/13)
- Trigger 16 Installs RPS Jumpers.
trgset 16 "0"l20 irf rpjumpas (16) onl20
- END SCENARIO ILT
-N-2 Page 26 of 28 Rev. 00 (08/13)
Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is 955 MWe Leading Thermal Limit: @ 0.818 Action limit: 0.980 Equipment Unavailable: None. Protected Equipment: None Unit 3 is in Mode 1 at Full Power Leading Thermal Limit: MAPRAT @ 0.819 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started: LCO Expires:
TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Separator Pit as required. Outside operator monitor and pump as necessary. Today Chem Cleaning ventilation status:
HV-1A/EF-1A are secured due to HV
-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV
-1B throwing its belts. WO 1156150.
HVAC -1 ON. HV-2 running.
Switchyard Status Today TSO notified of oil leaks on 345 Kv BT 2
-3 CB (IR 810135) ComEd WO 6396128 Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area.
Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood.
SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work. Be careful.
SCENARIO ILT
-N-2 Page 27 of 28 Rev. 00 (08/13)
Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
fter assuming the shift, perform DOS 1400-05, Core Spray System Pump Operability And Quarterly IST Test With Torus Available, starting at step I.5. After the Core Spray test is completed, reduce power by inserting step 15 of the control rod sequence. Then hold for the QNE to collect data. Next shift will continue the load drop.
- Shift 3 Activities ****
Today **** Unit 2 Procedures In
-Progress **** Do Not Delete ****
-01, Power Changes DOS 1400-05, Core Spray System Pump Operability And Quarterly IST Test With Torus Available
SCENARIO ILT
-N-2 Page 28 of 28 Rev. 00 (08/13)
XL-3 Alarms Sensor 51-20 in alarm 2/3 FIRE PUMP RUNNING
Dresden Generating Station ILT-N-3 LOWER POWER WITH RECIRC BUS DUCT BLOWER TRIP PERFORM MANUAL SCRAM CIRCUIT SENSOR TEST ISOLATION CONDENSER TUBE LEAK RPS MG SET TRIPS / R E-ENERGIZE FROM RESERVE POWER RECIRC MG SET VENT FAN FAILURE LOSS OF STATOR COOLING / MANUAL SCRAM RPV FLOODING Rev. 00 0 8/13 Developed By:
Exam Author Date Approved By:
Facility Representative Date SCENARIO ILT
-N-3 Page 2 of 26 Rev. 00 (08/13)
Scenario Outline Station: Dresden Generating Station Scenario No.:
ILT-N-3 Class ID:
2013-301 Evaluators Operators / crew position
/ ATC / BOP / CRS Initial Conditions:
88% Power , steady state, and equilibrium xenon Turnover: Scheduled load drop at beginning of shift Surveillance DOS 0500-01 Manual Scram Circuit Sensor Test due Event No. Malf. No. Event Type* Event Description 1 NONE R ATC Lower Power with Recirc 2 MGDDBATR C BOP Generator Bus Duct Blower Trip 3 NONE N ATC Perform Manual Scram Circuit Sensor Test on RPS Channel B 4 ICTUBLK I/T BOP Isolation Condenser Tube Leak (TS) 5 B02 C/T ATC RPS - MG Set Trips / Re
-energize from Reserve Power (TS) 6 B02 I ATC Recirc MG Set Vent Fan Failure 7 T50 / T52 C/M ALL Loss of Stator Cooling / Manual Scram 8 AT5 NVM100BP NVML29AP NVML29BP NVML112P M ALL FLOODING - Loss of RPV Level Indication Due to Loss of Inst Power and Transmitter Failures
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
SCENARIO ILT
-N-3 Page 3 of 26 Rev. 00 (08/13)
Scenario Objective Evaluate the Team's ability to operate the plant with a loss of RFPs requiring use of the HPCI system to restore and maintain RPV level. Scenario Summary
- 1. Unit is at 88%. 2. The following equipment is OOS:
- a. None. 3. LCOs: a. None Scenario Sequence After completing shift turnover, the ATC will lower reactor power with Recirc per procedure DGP 03-1, Power Changes. After the change in power has been observed, the crew will respond to a Bus Duct Blower Trip per procedures DAN 902
-8 E-11 and DOP 5370-02, Isolated Phase Bus Duct Cooling System.
After the Bus Duct Blower Trip is addressed, the ATC will perform a Manual Scram Circuit Sensor Test on RPS Channel B per procedure DOS 0500
-01, Manual Scram Circuit Sensor Test.
After the Circuit Test is completed, the BOP will respond to an Isolation Condenser Tube Leak per procedure DOA 1300-01, Isolation Condenser Tube Leak, and DANs 902
-3 B-3, Isol Condr Vent Rad Hi and 902
-3 C-4, Isol Condr Vent Temp Hi. Technical Specification 3.5.3, Conditions A.1 and A.2, apply.
After the Isolation Condenser Tube Leak is addressed, the 2B RPS MG Set Trips on overcurrent. The CRS/ATC will respond per procedure DOA 0500
-05, LOSS OF RPS, and re
-energize 2A RPS from Reserve Power with DOP 0500
-03, RPS Power Supply Operation. The CRS will reference Tech Specs and determine that LCO 3.3.8.2, Condition B applies. After the RPS MG Set Trip is addressed, 2A Recirc MG vent fan degrades causing low ventilation flow. Recirc MG Set temperatures will rise. The Team starts 2B Recirc MG vent fan and secures 2A Recirc MG vent fan After the 2A Recirc MG vent fan failure is addressed, a loss of Stator Cooling Water will lead to a manual scram. After the scram, a loss of RPV level indication occurs due to loss of Instrument Power and transmitter failures, requiring FLOODING per DEOP 0100
-00, R PV Control, and DEOP 0400
-01, R PV Flooding. Completion criteria: When RPV Water Level is being maintained and at the discretion of the Lead Examiner, Place the simulator in FREEZE.
Event One
- Lower Power with Recirc The Team continues reactor power reduction using recirculation flow
. Malfunctions required: 0 (None) Success Path:
Performs DGP 03-01, Power Changes
.
SCENARIO ILT
-N-3 Page 4 of 26 Rev. 00 (08/13)
Event Two
- Bus Duct Blower Trip 2A Bus Duct Blower trips
. Malfunctions required: 0 (None) Success Path:
Performs DAN 902-8 E-11. Event Three
- Perform Manual Scram Circuit Sensor Test
.The Team performs DOS 0500-01, Manual Scram Circuit Sensor Test
. Malfunctions required:
0 (None) Success Path:
Performs DOS 0500
-01, Manual Scram Circuit Sensor Test
.
Event Four
- Isolation Condenser Tube Leak APRM 5 fails upscale without a half scram due to an APRM Trip Unit problem.
Malfunctions required: 1 (APRM fails upscale without a half scram
) Success Path:
Inserts a half scram per DO P 0500-0 7 , Insertion-Reset of Manual Half Scram
. Determines Technical Specifications requirements.
Bypasses the APRM and resets the half scram per DOP 0500
-07, Insertion
-Reset of Manual Half Scram.
Event Five
-energize from Reserve Power 2 A RFP Vent fan trips
. The standby fan fails to auto start.
Malfunctions required: 1 (2A RFP Vent fan trip with failure of standby fan auto start
) Success Path:
The Team manually starts 2B RFP Vent fan.
SCENARIO ILT
-N-3 Page 5 of 26 Rev. 00 (08/13)
Event Six
- Recirc MG Set Vent Fan Failure 2A Recirc MG vent fan degrades causing low ventilation flow. Recirc MG Set temperatures will rise.
Malfunctions required:
1 (Degraded Recirc MG vent fan
) Success Path:
The Team will start 2B Recirc MG Vent Fan and secure 2A Recirc MG vent fan.
Event Seven - Loss of Stator Cooling / Manual Scram A loss of stator cooling occurs resulting in requiring a manual scram.
Malfunctions required:
1 (Recirc loop leak)
Success Path:
Performs DGP 02
-03, Reactor Scram
. Performs DEOP 0100, RPV Control
. Event Eight - RPV Flooding A loss of RFPs results in RPV level dropping. Malfunctions required:
1 (Loss of RFPs) Success Path:
Performs DOA 2300
-02, HPCI Fast Startup.
SCENARIO ILT
-N-3 Page 6 of 26 Rev. 00 (08/13)
PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre
-scenario activities in accordance with TQ-JA-150-08, 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 DO S 0 5 00-0 1 , Manual Scram Circuit Sensor Test
. 2 Simulator Setup (the following steps can be done in any logical order)
- a. Initialize simulator in an IC with the following:
(IC 150 used for validation, Seq. 2S.2.0, 7F9C)
- 1) Reactor power ~90%. 2) Control Rod Sequence 2S.2.0 step 15 inserted.
3 Verify the following simulator conditions:
- a. Verify 2A Recirc MG vent fan running. b. Verify 2A Stator Water Cooling pump operating.
- c. Verify 2A Bus Duct Blower running. d. Cut out one Condensate Demin.
- e. Advance the chart recorders.
NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.
4 Run the initial setup CAEP file: ILT-N-3.cae 5 Place the following equipment out of service:
- a. None 6 Run the CAEP file: Pump_Sumps.cae 7 Complete the Simulator Setup Checklist.
Symbols are used throughout the text to identify specific items as indicated below:
Critical Tasks Time Critical Tasks PRA Key Operator Actions Required Actions Optional Actions
SCENARIO ILT
-N-3 Page 7 of 26 Rev. 00 (08/13)
Event One
- Lower Power with Recirc Trigger Position Crew Actions or Behavior CRS Directs resuming load drop:
Reviews REMA.
Directs ATC to continu e load drop using recirc flow to 800 MWe. ATC Performs the following actions per DGP 03
-01, Power Changes, and DOP 0202
-03, Reactor Recirculation Flow Control System Operation, as directed:
Uses MASTER RECIRC FLOW CONTLR, 2(3)
-262-22, potentiometer to reduce flow AND control reactor power.
Notifies CRS when at 800 M We. BOP Monitors Panels. Event 1 Completion Criteria:
Load dropped to 800 MWe, AND/OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-3 Page 8 of 26 Rev. 00 (08/13)
Event Two
- Bus Duct Blower Trip Trigger Position Crew Actions or Behavior 1 Simulator Operator:
At the discretion of the Lead examiner, activate trigger 1, which causes 2A Bus Duct Blower to trip.
Role Play:
EO to check 2A Bus Duct Blower breaker: wait 2 min, then report "2A Bus Duct Blower breaker is closed and has overcurrent indication".
EO to check 2A Bus Duct Blower: wait 2 min, and then report "there is nothing abnormal at 2A Bus Duct Blower
". EO to check 2 B Bus Duct Blower after starting: wait 1 min, and then report "
2 B Bus Duct Blower is operating normally".
BOP Announces alarm s: o 902-8 E-11, Start Isol Phase Bus Duct Blower
. o 902-8 F-11, Isol Phase Bus Duct Blower Trip. Starts 2B Bus Duct Blower.
CRS Directs starting 2B Bus Duct Blower.
Enter s DOP 6700-20, 480V Circuit Breaker Trip.
BOP Performs DOP 6700-20, 480V Circuit Breaker Trip
Event 2 Completion Criteria:
2B Bus Duct Blower started , AND/OR At the direction of the Lead Examiner.
SCENARIO ILT
-N-3 Page 9 of 26 Rev. 00 (08/13)
Event Three
- Perform Manual Scram Circuit Sensor Test Trigger Position Crew Actions or Behavior ROLE PLAY:
As the Shift Manager, direct the Team to complete DOS 0500-01, Manual Scram Circuit Sensor Test
. CRS Directs ATC to perform DOS 0500-01, Manual Scram Circuit Sensor Test
., for remaining Channel B ATC Performs DOS 0500-01, Manual Scram Circuit Sensor Test as directed:
Verifies Both RPS channels A AND B are reset
. Verifies All RPS Channel manual AND automatic trip alarms are reset:
o Annunciator 902
-5 A-10, CHANNEL A MANUAL TRIP.
o Annunciator 902
-5 A-15, CHANNEL B MANUAL TRIP.
o Annunciator 902
-5 D-10, CHANNEL A RX SCRAM.
o Annunciator 902
-5 D-15, CHANNEL B RX SCRAM.
Verifies computer points W036 and W037 indicate reset.
Momentarily Depress es the Channel B MANUAL SCRAM pushbutton on Panel 902-5. Verifies the RED back lighting under the MANUAL SCRAM pushbutton illuminates.
Verifies all scram pilot solenoid Groups 1 and 4 and Groups 2 and 3 extinguish for the channel B on the vertical section of Panel 902-5. Verifies all operable SDV Vent and drain valves indicate OPEN on panel 902
-5. Verifies computer point W037 for CH B tripped.
Reset the half scram.
(May refer to DOP 0500
-07, Insertion/Reset of Manual Half Scram) Verifies all scram pilot solenoid group lights on Panel 90 2-5 are illuminated.
For RPS Channel B verifies Annunciator 902-5 A-15, CHANNEL B MANUAL TRIP, alarmed. Reset Annunciator 902
-5 A-15, CHANNEL B MANUAL TRIP, on Panel 902
-5. Verifies All RPS Channel manual AND automatic trip alarms are reset:
o Annunciator 90 2-5 A-10, CHANNEL A MANUAL TRIP.
o Annunciator 902
-5 A-15, CHANNEL B MANUAL TRIP.
o Annunciator 902
-5 D-10, CHANNEL A RX SCRAM.
o Annunciator 902
-5 D-15, CHANNEL B RX SCRAM.
Verifies computer points W036 and W037 indicate reset.
BOP Assists as directed.
SCENARIO ILT
-N-3 Page 10 of 26 Rev. 00 (08/13)
Event Three
- Perform Manual Scram Circuit Sensor Test Trigger Position Crew Actions or Behavior Event 3 Completion Criteria:
When DOS 0500-01, Manual Scram Circuit Sensor Test, is completed, AND/OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-3 Page 11 of 26 Rev. 00 (08/13)
Event Four
- Isolation Condenser Tube Leak Trigger Position Crew Actions or Behavior 2 Simulator Operator:
At the discretion of the Floor Instructor/Evaluator, activate trigger 2 which initiates a tube leak in the Isolation Condenser.
ROLE PLAY:
NLO to IC Area: (wait 3 min.) Report, "there is no evidence of steam leakage in the area but the IC is making noises. It sounds like metal parts expanding (creaking)".
ROLE PLAY:
NOTE: (IC temps may be viewed on RNI display IC1, Isolation Condenser)
NLO to check IC Vent outside: (WAIT 3 MIN.)
If IC shell temp is > 190°F, report "some fog/steam exiting from the vent" If IC shell temp is < 190°F, report "NO steam exiting vent".
ROLE PLAY:
Chemistry to sample IC shell side: Report "shell side sample results will take approximately 90 minutes".
ROLE PLAY:
Rad Protection to survey IC Vent outside: Report "the radiological surveys will be initiated".
Security to control access to IC Vent outside: Report "the area will be roped off".
BOP Announces alarms for the Isolation Condenser (IC) and refers to the following DANs:
902-3 B-3, IC Hi Rad 902-3 C-4, IC Hi Temp Monitors temperature and radiation levels for the Isolation Condenser CRS Directs/verifies Operators take action per DAN 902
-3 C-4. After determining there is a leak in the IC, enters DOA 1300-01 , Isolation Condenser Tube Leak. Declares the Isolation Condenser Inoperable.
Requests Chemistry to sample Iso
-Condenser shell side for change in activity.
BOP Performs DOA 1300
-01, Isolation Condenser Tube Leak, as directed and monitors:
IC vent rad levels.
IC shell side water level.
IC temperatures from TR 134 0-1. IC area temperatures from 902
-21 panel. IC area rad levels from 902
-2 panel BOP Reports IC vent rad above 3 mr/hr and IC shell side level and temperatures rising.
SCENARIO ILT
-N-3 Page 12 of 26 Rev. 00 (08/13)
Event Four
- Isolation Condenser Tube Leak Trigger Position Crew Actions or Behavior BOP Isolates the IC by closing the following valves per DAN 902
-3 B-3 or DOA 1300
-01. MO 2-1301-1 MO 2-1301-2 MO 2-1301-3 MO 2-1301-4 AO 2-1301-17 AO 2-1301-20 MO-2-1301-10 MO 2-4399-74 BOP May dispatch an NLO to the Isolation Condenser area.
May bypass the IC area hi rad input to the Rx Bldg Hi Rad alarm.
TEAM Dispatches personnel outside to investigate discharge from the vent.
TEAM Calls Chemistry and requests a sample of the shell side water to analyze for a change in activity.
TEAM Directs Rad Protection to conduct radiological surveys.
TEAM Directs Security to limit access underneath the IC vent.
CRS References Tech Specs and determines:
LCO 3.5.3.A.1: Verify HPCI is OPERABLE immediately.
LCO 3.5.3.A.2: Restore IC System to OPERABLE status within 14 days.
Event 4 Completion Criteria:
DOA 1300-01 is addressed, The IC is isolated, Tech Spec requirements are determined
, AND / OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-3 Page 13 of 26 Rev. 00 (08/13)
Event Five
-energize from Reserve Power Trigger Position Applicant's Actions or Behavior NOTE: Ensure the ATC operator performs this Event ROLE PLAY:
At the discretion of the Floor Instructor/Evaluator, call as the Shift Manager and report:
"Engineering has determined the following equipment inoperable:
-1 EPA BKR 2-500-2B-2, 2B RPS MG SET 2B
-2 EPA BKR ALL other EPA breakers are operable".
3 SIMULATOR OPERATOR ACTIONS:
After The Team has determined the Tech Spec requirements or at the discretion of the Floor Instructor/Evaluator, activate trigger 3, which inserts a 2B RPS MG Set overcurrent trip to simulate trip of 2B RPS MG SET 2B
-1 EPA BKR. NOTE: Communications from the AEER should be over the phone (not the radio)
ROLE PLAY:
EO to check 2B RPS MG set: wait 2 min. and call on the phone and report:
"The 2B RPS MG Set motor is running with normal output of 120 volts".
"The 2A RPS Bus voltage is 0.0".
-1 EPA BKR has tripped but ONLY has the POWER IN, MOTOR GEN red indicating light lit ". (All other lights are NOT lit)
-2 EPA BKR has NO indicating lights lit". 4 NOTE: When the team begins to re
-power 2A RPS bus, report: "Another NSO has completed the steps for bypassing OPRMs".
EO to power the 2A RPS bus from the Reserve source: wait five minutes, call the U2 NSO on the phone and report "I am at step G.3.l.(1) of DOP 0500
-03, for supplying power to RPS 2A bus. The next several steps are yours.
When notified by the NSO to resume at step G.3.
L.(6) then after ~ 1 min, activate trigger 4. Call on the phone and report "I have completed DOP 0500-03 thru st ep G.3.L.9. RPS Bus 2A has been reenergized from the reserve power supply". If asked: "RPS Bus 2A AC voltage is 120".
CRS References Technical Specifications and determines:
TS 3.3.8.2 (RPS Electric Power Monitoring) Condition A: Remove associated in
-service power supply(s) from service within 72 hr.
TS 3.3.8.2 (RPS Electric Power Monitoring) Condition B: Remove associated in
-service power supply(s) from service within 1 hr.
May direct WEC to brief an operator to swap RPS Bus A to the alternate power supply per DOP 0500
-03, RPS Power Supply Operation
. ATC Announces loss of 2A RPS Bus.
Perform actions of DOA 0500
-05, Loss of RPS.
Bypasses APRM 6.
SCENARIO ILT
-N-3 Page 14 of 26 Rev. 00 (08/13)
Event Five
-energize from Reserve Power Trigger Position Applicant's Actions or Behavior CRS Enters DOA 0500-05, Loss of Reactor Protection System Bus, and directs actions.
Directs swapping 2A RPS Bus to Reserve Power per DOP 0500
-03, RPS Power Supply Operation.
ATC Coordinates with an EO to restore power to the 2A RPS Bus per DOP 0500
-03, RPS Power Supply Operation.
Bypasses APRM 6. (May already done per DOA actions)
Resets the RPS CH A half scram per DOP 0500
-07, Insertion/Reset of Manual Half Scram. CRS References Technical Specifications and determines:
TS 3.3.6.2 (Secondary Containment Isolation Instrumentation) Condition A:: Place channel in trip within 1 2 hr. (Failed in trip condition)
TS 3.3.7.1 (TS 3.3.6.2 (Control Room Emergency Ventilation (CREV) System Instrumentation) Condition A 1: Declare CREV System inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of CREV System Instrumentation alarm capability in both trip systems
. Condition A2: Restore CREV instrumentation to operable within 6 hrs.
NOTE: After restoring the RPS Bus, the Team should begin to identify and plan for system restoration back to their normal lineups.
CRS Coordinates restoration of affected plant systems.
May direct shutdown of 2B RPS MG Set.
TEAM Resets the Division 2 Refuel Floor Rad Monitor and Reactor Building Vent Rad Monitor. Restores Reactor Building Ventilation IAW DOP 5750
-02, Reactor Building Ventilation and secures SBGT IAW DOP 7500
-01, SBGT Operation.
Resets ACAD/CAM system per DOP 2400
-01 to reclose the 2
-2499-3B and 4B valves. Restarts RWCU per DOP 1200
-03, RWCU System Operation with the Reactor a t Pressure. Event 5 Completion Criteria:
RPS Bus 2A reenergized and plans for restoration of affected plant systems in progress
, AND / OR; At the direction of the Lead Examiner.
SCENARIO ILT
-N-3 Page 15 of 26 Rev. 00 (08/13)
Event Six
- Recirc MG Set Vent Fan Failure Trigger Position Applicant's Actions or Behavior NOTE: Ensure the ATC operator performs this Event 5 6 7 Simulator Operator:
At the discretion of the Lead Examiner, activate trigger 5 which causes reduced Recirc MG Set ventilation flow.
Verify trigger 6 automatically activates when a Recirc MG Set temperature alarm is received. This adjusts the ventilation flow so temperatures remain below levels requiring speed to be reduced
. After the Team has successfully transferred to 2B Recirc MG Set Vent Fan
, activate trigger 7. This deletes the reduced Recirc MG Set ventilation flow malfunction.
Role Play:
EO to check Recirc MG Set ventilati on: Wait 2 min, and then report that "2A Recirc MG vent fan is making a lot of noise and is severely vibrating".
EO to check operation of 2B Recirc MG vent fan: Wait 2 min, and then report that "2B Recirc MG vent fan is operating normally".
ATC Acknowledges and announces alarms:
902-4 E-4, 2A Recirc M
-G Temp Hi. 902-4 E-9, 2 B Recirc M-G Temp Hi. 902-4 B-9, 2A/B Recirc M
-G M tr/G en Temp H i Sends operator to check status of the Recirc MG ventilation system.
Starts 2B Recirc MG vent fan
. Secures 2A Recirc MG vent fan. Sends operator to check operation of the 2B Recirc MG vent fan.
CRS Directs swapping Recirc MG vent fans.
TEAM May reference DOA 5750
-01, Ventilation System Failure.
BOP Assists as directed.
Event 6 Completion Criteria:
Swapped to 2B Recirc MG vent fan
, AND / OR, At the discretion of the Lead Examiner.
SCENARIO ILT
-N-3 Page 16 of 26 Rev. 00 (08/13)
Event Seven
- Loss of Stator Cooling / Manual Scram Trigger Position Applicant's Actions or Behavior 8 SIMULATOR OPERATOR:
At the discretion of the Lead examiner, activate trigger 8, which causes 2A Stator Cooling Water Pump to trip. 2 B Stator Cooling Water Pump cannot be started.
BOP Announces trip of 2A Stator Cooling Water Pump
. CRS Enters and directs performance of DOA 7400-01, Failure o f the Stator Coolant System. May set a Scram contingency.
Prior to reaching the RPV Pressure scram setpoint, enters DGP 02
-03, Reactor Scram, and directs a manual reactor scram.
BOP Performs DOA 7400-01, Failure of the Stator Coolant System.
Attempts to start the standby Stator Water Cooling Pump. Announces the standby Stator Water Cooling Pump failed to start.
ATC Performs the following actions per DGP 02
-03, Reactor Scram, as directed:
Presses scram pushbuttons Places mode switch in shutdown Check rods inserted.
Verifies Recirc Pumps run back. Maintains RPV/L between +25 and +35 inches or as directed by Unit Supervisor.
Inserts SRM/IRMs.
CRS Enters DEOP 0100, RPV Control and directs. Maintaining RPV level +8 to +48 inches
. Maintaining RPV pressure <1060 using turbine bypass valves.
Verifying automatic actuations TEAM Verifies the following as time allows:
Group Isolations
. Event 7 Completion Criteria
SCENARIO ILT
-N-3 Page 17 of 26 Rev. 00 (08/13)
Event Eight - RPV Flooding Trigger Position Crew Actions or Behavior 9 Simulator Operator:
After the team has stabilized the unit following the reactor scram, and at the discretion of the Lead Evaluator, activate trigger 9, which: Simulates a trip of the MCC 29-1 supply to ATS Panel 2202
-73B which causes loss of MR A and FZ B RPV level instruments.
After 2 min, fails the remaining RPV level instruments in a way that simulates a leak in the common sensing leg for the 2202
-5 instrument rack (MR B, NR A & WR) causing them to ramp downscale. Bailey System NR B circuit card fails causing it to ramp upscale.
Simulator Operator / Role Play:
-0301-25 valve: On Instructor Station drawing RD2, change the CRD 2-0301-25 valve position to the requested position and then report its position.
Role Play:
When dispatched to the ATS Panel, wait a few minutes, and then report that "all instruments in the top row of panel 2202
-73B are downscale and no indicating lights on the top row are lit. All other indications are normal".
-1. Wait two minutes then report from MCC 29
-1 that "the breaker for circuit 4 is tripped".
If sent to 125 VDC Main Bus Dist. Panel 2B
-1 to check breaker 17, report that it is closed. When/if directed to close the ATS Panel supply breaker, wait ~20 seconds, then report that you attempted to reclose the breaker and it immediately tripped again.
BOP Reports annunciator 902
-4 H-20, ATS Div 2 2202
-73B Trouble, in alarm and references DAN.
Sends an EO to inspect ATS panel 2202
-73B. May direct an EO to MCC 29
-1 to check the feed breaker (circuit 4) to ATS.
May direct the closure of the ATS Panel power supply breaker.
TEAM Begins to determine the equipment affected by loss of the ATS feed.
-05, Power Restoration to Analog Trip System Feeds to check for restoration requirements.
TEAM Determines that RPV level indications are diverging.
TEAM May send operators to local instrument panels.
Role Play:
EO to Reactor Bldg to get local RPV level indication: wait 2 min, and then report "there is steam around all the instrument racks and I am unable to get local RPV level readings".
SCENARIO ILT
-N-3 Page 18 of 26 Rev. 00 (08/13)
Event Eight - RPV Flooding Trigger Position Crew Actions or Behavior CRS Based on diverging RPV level indication, exits DEOP 0100 and enters DEOP
0400-01, RPV Flooding, and performs / directs:
Verifying Torus level above 6 feet.
Opening all 5 ADSVs.
Isolating the following steam lines:
MSIVs. Main Steam line drains.
IC. HPCI. Flooding the RPV to the Main Steam lines.
Directs defeating the RFP trips.
Keeping the RPV flooded to the Main Steam lines with injection flow as low as possible. 10 Simulator Operator / Role Play:
Operator to defeat RFP trips: wait 2 min, activate Trigger 10 and then report that "the RFP trips are defeated" ATC / BOP Performs DEOP 0400
-01, RPV Flooding, as directed:
Verifies Torus level above 6 feet.
Opens all 5 ADSVs.
Isolates the following steam lines:
MSIVs. Main Steam line drains.
IC. HPCI. Floods the RPV to the Main Steam lines.
Keeps the RPV flooded to the Main Steam lines with injection flow as low as possible. ATC / BOP Slows down RPV injection once ERV tailpipe temperatures drop below saturation and pressure is steady.
CRS Enters DEOP 2 00-01, Primary Containment Control due to the following: Torus Water Level high.
Torus Temperature high.
Directs starting maximum Torus cooling.
SCENARIO ILT
-N-3 Page 19 of 26 Rev. 00 (08/13)
Event Eight - RPV Flooding Trigger Position Crew Actions or Behavior BOP Initiates Torus cooling per "Hard Card":
Places 316A/B and 318A/B keylock switches in MANUAL OVERRD.
Verifies the third circ water pump is secured prior to starting the first CCSW pump.
IF starting torus cooling during a LOCA, THEN verifies RWCU recirc pump is tripped PRIOR to starting the first CCSW pump.
Starts one CCSW pump in each loop and verifies 3A/B valves open.
Starts at least one LPCI pump in each loop. (Starts additional LPCI pumps as required.)
Adjusts CCSW flow controller to approximately 3500 gpm for one pump; >
5000 gpm 20 psid (two LPCI Pumps/loop)]
Momentarily places 11A/B valve control switches to close. (IF 11A/B remain open or re-opened due to LPCI logic, then close valves as soon as possible.)
IF required, obtains Unit Supervisor permission, THEN places 317 keylock switches to MANUAL OVERRD.
Opens 21A/B and 20A/B valves in desired loop.
Throttles open 38A/B valves until >
5000 gpm per LPCI pump is established (maintains LPCI pump discharge pressure >
125 psig). Starts additional CCSW pumps if desired:
o IF TR 86(32) LTC in MANUAL, THEN PRIOR to starting 3rd OR 4th CCSW PP, verifies voltage on applicable ECCS bus >
4000 volts, preferred target 4160V.
o (Unit 2 Only) If 2/3 EDG is loaded, then refers to DOP 1500-02 prior to starting additional pumps.
Adjusts CCSW flow controller to >
5000 gpm for two CCSW pumps [Maintain 20 psid (two LPCI Pumps/loop)].
CRS Requests IMD to restore RPV level instruments.
Event 8 / Scenario Completion Criteria:
Team has flooded the RPV to the Main Steam Line, AND / OR, At the direction of the Lead Examiner.
SCENARIO ILT
-N-3 Page 20 of 26 Rev. 00 (08/13)
Critical Tasks (RPV 2.1) When RPV water level cannot be determined, INITIATE emergency depressurization.
(RPV 2.2) When reactor water level cannot be determined, INJECT into the RPV to flood up to the Main Steam Lines.
SCENARIO ILT
-N-3 Page 21 of 26 Rev. 00 (08/13)
REFERENCES PROCEDURE TITLE DAN 902-3 B-3 IC HI RAD DAN 902-3 C-4 IC HI TEMP DAN 902-4 B-9 2A/B RECIRC M
-G MTR/G EN TEMP H I DAN 902-4 E-4(9) 2A(B) RECIRC M-G TEMP HI DAN 902-4 F-5 2A-B RECIRC M
-G EXH AIR TEMP HI DAN 902-7 A-5 TURBINE CONTROL MAJOR TROUBLE DAN 902-7 B-10 STATOR CLG PP TRIP DAN 902-7 C-10 STATOR CLG PANEL TROUBLE DAN 902-7 C-3 TURB STATOR COOLANT RUNBACK DAN 902-7 E-11 H2 SEAL OIL & ALTERREX PNL TROUBLE DAN 902-8 E-11 START ISOL PHASE BUS DUCT BLOWER DAN 902-8 F-11 ISOL PHASE BUS DUCT BLOWER TRIP DEOP 0100 RPV CONTROL DEOP 0200-01 PRIMARY CONTAINMENT CONTROL DEOP 0400-01 RPV FLOODING DGA 07 UNPREDICTED REACTIVITY ADDITION DGP 01-01 UNIT STARTUP DGP 02-03 REACTOR SCRAM DGP 03-04 CONTROL ROD MOVEMENTS DOA 0500-05 LOSS OF REACTOR PROTECTION SYSTEM BUS DOA 1300-01 ISOLATION CONDENSER TUBE LEAK DOA 5750-01 VENTILATION SYSTEM FAILURE DOP 0202-03 REACTOR RECIRCULATION FLOW CONTROL SYSTEM OPERATION DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM OPERATION DOP 0500-03 RPS POWER SUPPLY OPERATION DOP 0500-07 INSERTION/RESET OF MANUAL HALF SCRAM DOP 6700-20 480V CIRCUIT BREAKER TRIP DOS 0500-01 MANUAL SCRAM CIRCUIT SENSOR TEST TS 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TS 3.3.6.2 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TS 3.3.7.1 CONTROL ROOM EMERGENCY VENTILATION SYSTEM INSTRUMENTATION TS 3.3.8.2 RPS ELECTRIC POWER MONITORING SCENARIO ILT
-N-3 Page 22 of 26 Rev. 00 (08/13)
Simulator Scenario Review Checklist ILT-N-3 Quantitative Attributes 6 Total malfunctions (5 to 8) 1 Malfunctions after EOP entry (1 to 2) 3 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)
SCENARIO ILT
-N-3 Page 23 of 26 Rev. 00 (08/13)
CAEP Files
- ILT-N-3.cae # For ILT Class 12
-1 NRC Exam
- Written by MP
- Rev 00 # Date 08/13
- INITIAL CONDITIONS
- Prevents 2B Stator Cooling Water Pump from starting.
imf t52 ior mgdscbcl 1
- EVENT TRIGGERS
- Event Trigger 1 Trips 2A Bus Duct Blower.
trgset 1 "0" ior mgddbatr (1) 2 ior mgddbacl (1) 1 ior mgldbaat (1) true imf ser1671 (1) on
- Event Trigger 16 Activates when 2A Bus Duct Blower is placed to PTL.
trgset 16 "mgddbalc_drw(1)"l10 trg 16 "dor mgldbaat"l10
- Event Trigger 17 Activates when 2A Bus Duct Blower is placed to PTL.
trgset 17 "mgddbalc_drw(1)"l10 trg 17 "mmf ser1671 normal"l10
- Event Trigger 2 Iso Cond Tube Leak.
trgset 2 "0"l2 imf ictublk (2) 2.0l2
trgset 3 "0"l2 imf b02 (3)l2
- Trigger 4 Transfers RPS Bus 2A to the normally energized reserve power EPAs trgset 4 "0"l4 irf b03 (4) truel4
- Event Trigger 5 Inserts Recirc MG Set 2A/B Vent Fan Filter Clogged.
Trgset 5 "0"l4 trg 5 "set rrkwvfan = 33.0"l4 imf rrmfaexh (5)l4
- Event Trigger 6 Activates when a Recirc MG Set high temp alarm is received.
- Slows the temperature rise so load drop is not required.
Trgset 6 "sezpoint(341) .or. sezpoint(388)"l6 trg 6 "set rrkwvfan = 20.0"l6
- Event Trigger 7 Deletes Recirc MG Set 2A/B Vent Fan Filter Clogged.
Trgset 7 "0"l6 trg 7 "dmf rrmfaexh"l6
- Event Trigger 8 Trips 2A Stator Cooling Water Pump.
SCENARIO ILT
-N-3 Page 24 of 26 Rev. 00 (08/13) trgset 8 "0"l6 imf t50 (8)l6
- Event Trigger 9 Blows the fuse for the MCC 29
-1 feed to ATS panel 2202
-73B. # This causes a loss of RPV MR A and FZ B.
- After 2 min, fails RPV NR A level instrument to downscale on 5 min. ramp.
- After 2 min, fails RPV NR B level instrument to upscale on 5 min. ramp.
- After 2 min, fails RPV Wide Range level instrument to downscale on 5 min. ramp.
trgset 9 "0"l8 imf at5 (9)l8 imf nvml57ap (9 2:00)
-120.0 5:00l8 imf nvml23ap (9 2:00)
-120.0 5:00l8 imf nvml23cp (9 2:00)
-120.0 5:00l8 imf nvml29ap (9 2:00)
-75.0 5:00l8 imf nvml29bp (9 2:00) 75.0 5:00l10 imf nvml112p (9 2:00)
-400.0 5:00l10
- Event Trigger 10 bypasses the RFP high level trip.
trgset 10 "0"l10 irf fwknife (10) openl10
- END SCENARIO ILT
-N-3 Page 25 of 26 Rev. 00 (08/13)
Unit 2 Risk: GREEN Unit 3 Risk: GREEN Unit 2 is 870 MWe Leading Thermal Limit: 0.802 Action limit: 0.980 Equipment Unavailable:
None Protected Equipment: None Unit 3 is in Mode 1 at Full Power Leading Thermal Limit: MAPRAT @ 0.819 Action Limit: 0.980 Equipment Unavailable: None Protected Equipment: None Current Action Statements None LCO Started:
LCO Expires:
TS Cause: Unit 1 Plant Status Today U1 Diesel Oil Storage Tank Transfer House has grating removed. Currently roped off with pump installed to pump to U1 Oil Separator Pit as required. Outside operator monitor and pump as necessary.
Today Chem Cleaning ventilation status:
HV-1A/EF-1A are secured due to HV
-1A inlet and outlet dampers being shut with fan on, IR# 913157, WO 1239746. HV-1B/EF-1B are secured due to HV
-1B throwing its belts. WO 1156150.
HVAC -1 ON. HV-2 running.
Switchyard Status Today TSO notified of oil leaks on 345 Kv BT 2
-3 CB (IR 810135) ComEd WO 6396128 Today 138 KV Bus 1 Feed To TR 22 Combi Units has low oil in the 'C' phase, ComEd WO #276162 Today HVO: Exercise CAUTION while in the 345 kV Yard due to excavation being performed in the area.
Marv Evans reports holes being dug near manual switch disconnects 345kV Blue Bus. Plywood will be installed over the holes if access is needed, but be aware there are holes under the plywood.
SSC called from the 345Kv yard reporting that the cable trough covers are removed to prep for upcoming work. Be careful.
SCENARIO ILT
-N-3 Page 26 of 26 Rev. 00 (08/13)
Unit 2 Plant Status Today Unit 2 Activities
- Shift 1 Activities ****
- Shift 2 Activities ****
Last shift the Team began a load drop to allow performing a control rod sequence exchange. The load drop was on hold for the QNE to collect data. Immediately after assuming the shift, drop load to 800 MWe. Then hold again for the QNE to collect data.
When directed by the Shift Manager, perform DOS 0500
-01, Manual Scram Circuit Sensor Test. Channel A portion was completed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.
- Shift 3 Activities ****
Today **** Unit 2 Procedures In
-Progress **** Do Not Delete ****
3-01, Power Changes DOS 0500-01, Manual Scram Circuit Sensor Test