Text

2017 Clinton Power Station Initial Licensed Operator Examination As-Administered Scenarios
	ML17116A113
Person / Time
Site:	Clinton
Issue date:	02/09/2017
From:	Chuck Zoia; NRC/RGN-III/DRS/OLB
To:	; Exelon Generation Co
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ML16308A463	List: ML17116A081; ML17116A101; ML17116A113;
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	Download: ML17116A113 (54)
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ILT 15-1 NRC Exam Scenario 1 Rev. 0 Exelon Nuclear ILT 15-1 NRC Exam Scenario Number:

NRC Exam Scenario 1 Revision Number: 0 Date: 10/28/16 Developed By: T. Jennings 10/28/16 Instructor Date Validated By: Michael Antonelli 10/28/16 SME or Instructor Date Reviewed By: Jim Lucas 11/15/16 Operations Representative Date Approved By: T. Jennings 11/15/16 Training Department Date ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 1 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 1 Operating Test No.: 2017-301 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Mode 1 at ~78% power to support performance of CPS 9031.07 Main Turbine Control Valve Tests on the next shift.

Thunderstorms are expected in the area within the next hour.

CY Pump B (0CY01PB) is OOS for maintenance. Not expected back this shift.

CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability is in progress. DG 1C is running in parallel with RAT B.

Turnover:

Priorities for the shift are as follows:

Secure Division 3 Diesel Generator (DG 1C) per CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability, starting at step 8.2.16 - First Priority. CPS 9082.01 Offsite Source Power Verification was completed one (1) hour ago.

Maintain power at 78% throughout the shift.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Secure DG 1C 2 YP_XMFTB_3986 TS-SRO DG 1C Overspeeds When Unloaded A05_A02_A104_3_TVM A05_A02_A105_3_TVM A05_A02_A106_3_TVM 3 A02_A05_01_7_TVM=2 C-ATC CRD high temperature 4 CAM0PR001IA_PUMP to 1 C-BOP Failure of 0RIX-PR001 Ch 15 - Low flow due TS-SRO to sample pump failure CAM0PR001TV_VALUE15 to 0 5 A01_A02_01_8_TVM C-ATC Clogged oil filter Condensate Booster Pump A

6 YPXMALSE_77 to 50 C-BOP Inadvertent opening of a SRV 7 YFFWPPSS_11 R-ATC Loss of CY - Rapid Plant Shutdown YAFWPPDE_9 8 RAT_B_OVERCURRENT M-All LOCA/RAT trip/E51-F013 Failure/Div 3 ERAT YARIMVFP_2 = 0 Feed Breaker Failure/TAF Blowdown ED17B221C1FO YPXMALSE_511 9 LPCS Fails To Auto Start YP_XMFTB_4106 C-BOP LPCS Injection Valve 1E21F005 Fails to Auto lp11acld001fsp=True Open at 472 psig RPV pressure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 2 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 Operating Test No.: 2017-301 Narrative Summary Event # Description

1. Secure DG 1C Division 3 DG is running in parallel with RAT B IAW CPS 9080.03, Diesel Generator 1C Operability -

Manual and Quick Start Operability. Following shift turnover, the SRO will direct the BOP operator to unload and secure DG 1C and place it back in standby.

2. DG 1C Overspeeds When Unloaded When the BOP opens the output breaker for DG 1C in event 1, annunciators 5062-2C TRIP/LOCKOUT DIESEL GEN 1C, 5062-4C OVERSPEED DIESEL GEN 1C, 5062-5C TRIPPED DIESEL GEN 1C ENGINE and 5062-6C TROUBLE DIESEL GEN 1C come in due to an overspeed trip of the Div 3 DG.

The overspeed trip will result in a lockout of the Div 3 DG, rendering the DG inoperable and unavailable.

The field operator stationed in the Div 3 DG Room will confirm MCR indications. Technical Specification 3.8.1 Condition B (one required DG inoperable) will be entered and appropriate actions taken.

3. CRD high temperature Annunciator 5006-1G CRD HYDR TEMP HI is received. The ATC operator will dispatch a field operator to the local recorder on 1H22-P007 to determine rod 52-25 is alarming. The ATC operator will note that rod 52-25 is currently at position 48 and IAW CPS 3304.01 Control Rod Hydraulic & Control (RD) perform an extended coupling check. The annunciator will clear for ~ 30 seconds and then alarm again. The ATC operator will then insert rod 52-25 to position 46 which will clear the high temperature condition.

4. Failure of 0RIX-PR001 Ch 15 - Low flow due to sample pump failure A channel (15) trouble - flow out of limit is received on the MCR AR/PR LAN for 0RIX-PR001 HVAC Exhaust Stack PRM #1. The BOP will identify a low flow condition. The SRO will declare 0RIX-PR001 inoperable and enter ODCM 3.2.2 Conditions A and C. The SRO will direct the BOP to place 0RIX-PR002 in service and exit ODCM actions.

5. Clogged Oil Filter Condensate Booster Pump A Annunciator 5001-1H CLOGGED OIL FILTER CB PUMP 1A will be received. An Equipment Operator will be dispatched to turn the CUNO filter handle several times in an attempt to clear the alarm, but will be unsuccessful. The SRO will direct the ATC to start a non-running Condensate Booster Pump and secure CB Pump 1A per CPS 3104.01 Condensate/Condensate Booster (CD/CB), section 8.2.2 Starting Additional/Shifting Condensate Booster Pumps.

6. Inadvertent opening of a SRV Annunciators 5066-5B ADS OR SAFETY RELIEF VALVE LEAKING and 5067-8L SRV MONITORING SYSTEM TROUBLE come in due to SRV 1B21-F041G failing ~ 50 % open. The BOP operator will diagnose and determine the problem is with 1B21-F041G. The SRO will direct the BOP operator to sound the containment evacuation alarm and coordinate with the ATC and attempt to close the SRV IAW CPS 4009.01 Inadvertent Opening Safety/Relief Valve. The SRO will enter and execute CPS 4005.01 Loss of Feedwater Heating and direct the ATC to restore and maintain reactor power at or below the original power level. SRV 1B21-F041G will shut when the first fuse is simulated removed for the associated A solenoid at 1H13-P661.

7. Loss of CY - Rapid Plant Shutdown The scenario starts with the B CY Pump out of service. In this event the shaft shears on the running CY Pump (0CY01PC). The BOP operator will start the A CY Pump and secure the C CY Pump. However, the A CY pump capacity begins to degrade and annunciator 5014-2B Low Press Cycle Cond Xfer Pump Disch Hdr will be received. Due to the complete loss of CY system pumps, the crew will perform a Rapid Plant Shutdown and attempt to scram the reactor per CPS 3208.01 Cycled / Makeup Condensate (CY/MC).

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 3 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Narrative Summary (cont.)

Event # Description

8. LOCA/RAT Trip/E51-F013 Failure/Div 3 ERAT Feed Breaker Failure/TAF Blowdown When the unit is scrammed in event 7, the Main Generator will trip on reverse power (normal post-scram response). When Generator Output Gas Circuit Breaker (GCB) 4506 opens, a lockout of RAT B results in a loss of non-vital 4160 and 6900 volt power, resulting in a loss of Feedwater and Control Rod Drive as injection sources. Additionally, the ERAT Feed Breaker to 4160V Bus 1C1 fails to close, resulting in de-energization of 4160V Bus 1C1 resulting in loss of HPCS as a feed source, and the RCIC injection valve will fail to open remotely and manually. This will complete the loss of all high pressure feed sources to the RPV. A LOCA will then commence, resulting in a loss of RPV inventory and causing DW pressure to increase. The LOCA will escalate, causing RPV level to fall to TAF, requiring an emergency depressurization to be performed (ADS fails to automatically initiate).

9. LPCS Fails To Auto Start / LPCS Injection Valve 1E21F005 Fails to Auto Open at 472 psig RPV pressure The Low Pressure Core Spray Pump will fail to auto start when DW pressure reaches 1.68 psig and will have to be manually started (critical task). In addition, 1E21-F005 LPCS Injection Valve will fail to automatically open at 472 psig RPV pressure, requiring the injection valve to be manually opened to recover RPV level above TAF.

EOP 1, 3, 6 Critical tasks:

RPV-1.1 Enter EOP-3 and blowdown on a failure of the Automatic Depressurization System to automatically initiate within 17.5 minutes of RPV level reaching -145.5 inches.

RPV-1.2 Maximize injection to restore water level above -162 (TAF) (-160 on Wide Range level indicators). For this scenario, the magnitude of the leak is such that RPV water level will not recover above TAF if LPCS is not manually initiated within 17.5 minutes of RPV level reaching -145.5 inches.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 4 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 1, 2 Page 1 of 2

Description:

Secure DG 1C / DG 1C Overspeeds When Unloaded Initiation: Following shift turnover and when directed by the Lead Examiner. DG 1C will overspeed and trip when the output breaker is opened.

Cues:

Event 1 - Directed by SRO.

Event 2 - Annunciators 5062-2C TRIP/LOCKOUT DIESEL GEN 1C, 5062-4C OVERSPEED DIESEL GEN 1C, 5062-5C TRIPPED DIESEL GEN 1C ENGINE, 5062-6C TROUBLE DIESEL GEN 1C Time Position Applicants Actions or Behavior General Note on Requirements for Expected Annunciator Response - OP-AA-103-102 If this evolution was pre-briefed and Expected Alarms were reviewed, the following expectations apply:

Expected alarms will be flagged

When the annunciator comes in the operator will announce Expected Alarm

The annunciator response procedure (ARP) need not be entered since it has already been reviewed in the pre-brief.

If a pre-brief was not conducted the operator should perform the following:

When an annunciator comes in the ARP should be referred to.

The annunciator may then be identified as an Expected Alarm, flagged, and from that point on the ARP need not be referred to.

Key Parameter Response: None Expected Annunciators: 5062-2C, 5062-4C, 5062-5C, 5062-6C Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Dispatches Equipment Operator to investigate trip of DG 1C.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per CPS 9080.03, performs steps 8.2.16.2 - 8.2.16.4 to unload and secure DG 1C from surveillance (DG 1C will trip when the output breaker is opened in step 8.2.16.4):

Slowly lowers DG 1C load to 100-200 KW using the DG 1C Governor Control Switch.

o Adjusts DG 1C VARs to ~ 0 KVAR using the DG 1C Voltage Regulator Control Switch.

Opens DG 1C Output Bkr, 1E22-S001.

Reports DG 1C tripped to the SRO (annunciators 5062-2C, 4C, 5C, 6C).

Reports receipt of annunciators 5062-2C, 4C, 5C, and 6C to the SRO.

Refers to ARPs for 5062-2C, 4C, 5C, and 6C.

o Informs SRO to refer to CPS 4200.01 Loss of AC Power.

o Informs SRO to refer to ITS 3.8.1, 3.8.2, and 3.8.3.

o Informs SRO of possible need to notify Ameren of Div 3 DG UNAVAILABILITY.

o Dispatches Equipment Operator to investigate.

SRO

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Acknowledges reports from ATC/BOP.

o Enters and executes CPS 4200.01 Loss of AC Power.

Evaluates and re-enters ITS 3.8.1 AC Sources - Operating, Condition B Required Actions B.1, B.2, B.3.1 (or B.3.2), and B.4.

o Informs Shift Manager.

o Contacts Maintenance to investigate.

Conducts a brief.

Terminus: DG 1C unloaded and tripped. ITS 3.8.1 evaluated.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 5 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 NOTES:

Solid bullets are required actions o Hollow bullets are actions that may or may not be performed Operator Actions Event No.(s): 3 Page 1 of 1

Description:

CRD high temperature Initiation: Following Event 2 and upon direction of the Lead Examiner, insert REMOTE 1.

Cues: Annunciator 5006-1G, CRD Hydr Temp Hi Time Position Applicants Actions or Behavior ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 6 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Key Parameter Response: CRD 52-25 operating temperature Expected Annunciators: 5006-1G, CRD Hydr Temp Hi Automatic Actions: None ATC

Reports issue to SRO.

Refers to ARP.

o Directs Field Operator to investigate.

Monitors reactor to ensure operations remain within established bands.

Per 3304.01, Control Rod Hydraulic & Control (RD):

Determines CRD 52-25 is alarming.

Performs extended coupling check of rod 52-25 (10-15 seconds).

Inserts control rod 52-25 to position 46.

BOP

Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

o Initiates an Issue Report and contacts the Reactor Engineer regarding the uncoupled rod event.

SRO

Acknowledges report from ATC.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Informs Shift Manager.

o Contacts Maintenance to investigate.

o Conducts a brief.

Terminus: Control rod 52-25 inserted to position 46. Annunciator 5006-1G clear NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 7 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 4 Page 1 of 1

Description:

Failure of 0RIX-PR001 Ch 15 - Low flow due to sample pump failure Initiation: Following Event 3 and upon direction of the Lead Examiner, insert REMOTE 2 Cues: MCR AR/PR LAN Alarm Time Position Applicants Actions or Behavior Key Parameter Response: 0RIX-PR001 Channel 15 Flow Expected Annunciators: MCR AR/PR LAN Alarm Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP

Reports issue to SRO.

Refers to the ARP.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Determines 0RIX-PR001 sample pump is OFF by observing 0RIX-PR001 Channel 15 Flow and sample pump status.

Per CPS 5140.41, AR/PR Annunciator - HVAC Exhaust PRM #1 - 0RIX-PR001, Operator Actions 2.b, 3.d, and 5:

Dispatches personnel to check sample pump operation and monitor valve lineup.

Determines monitor flow cannot be restored and places 0RIX-PR002 in service.

Per CPS 3315.03, Radiation Monitoring section 8.4, places 0RIX-PR002 in service :

o Directs Chemistry to perform CY-CL-6954-01, HVAC Stack Effluent-Iodine and Particulate.

At Channel Status screen for monitor 0RIX-PR002 ;

Starts the pump by selecting ON under Pump Command.

Verifies Channel 14 pressure is indicating < 14.9 psia AND is not DELETED.

Observes sample flow (Ch 15) stabilizes (53-57 LPM).

Places 0RIX-PR002 in Normal by selecting NRML under Stdby Cmnd.

o At Channel Status screen for monitor to be placed in STANDBY (0RIX-PR001):

Places monitor in STANDBY by selecting STBY under Stdby Cmnd.

o Resets/verifies reset all alarms for 0RIX-PR002.

Performs a channel check of monitor 0RIX-PR002 per CPS 9000.01, Control Room Surveillance Log.

SRO

Acknowledge reports from BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Enters ODCM 3.2.2 Required Actions A.1, C.1, C.2.2.1, C2.2.2, D.1, and D.2 (D.1 and D.2 until 0RIX-PR002 is placed in service).

o Contacts Maintenance to investigate.

o Informs Shift Manager.

o Conducts a brief.

Terminus: 0RIX-PR001 secured, 0RIX-PR002 started, tech specs evaluated.

NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 8 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 5 Page 1 of 1

Description:

Clogged oil filter Condensate Booster (CB) Pump A Initiation: Following Event 4 and upon direction of the Lead Examiner, insert REMOTE 3 Cues: Annunciator 5001-1H Clogged Oil Filter CB Pump 1A Time Position Applicants Actions or Behavior Key Parameter Response:

Expected Annunciators: 5001-1H Clogged Oil Filter CB Pump 1A Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Reports issue to SRO.

Per CPS 5001-1H, Clogged Oil Filter Condensate Booster Pump 1A:

o Directs Equipment Operator to turn CUNO filter handle several turns for the 1A CB Pump.

Per ARP or CPS 3104.01, Condensate/Condensate Booster (CD/CB) step 8.2.2:

Starts CB Pump 1C.

Secures CB Pump 1A.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands o Directs Equipment Operator to turn CUNO filter handle several turns for the 1A CB Pump.

SRO

Acknowledges reports from ATC/BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Informs Shift Manager.

o Conducts a brief.

o Contacts Maintenance to investigate.

Terminus: CB Pumps shifted.

NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 9 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 6 Page 1 of 1

Description:

Inadvertent opening of a SRV Initiation: Following Event 5 and upon direction of the Lead Examiner, insert REMOTE 4 Cues: Annunciators 5067-8L, SRV Monitoring System Trouble and 5066-5B, ADS Or Safety Relief Valve Lifting Time Position Applicants Actions or Behavior Key Parameter Response: Reactor Power, RPV Level Expected Annunciators: 5067-8L, SRV Monitoring System Trouble and 5066-5B, ADS Or Safety Relief Valve Lifting Automatic Actions: None ATC o Reports issue to SRO.

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per CPS 4005.01 Loss Of Feedwater Heating

Reduces RR flow with FCV(s) to restore and maintain power at or below the original power level.

BOP o Reports issue to SRO.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Per CPS 4009.01 Inadvertent Opening Safety/Relief Valves:

Sounds the containment evacuation alarm.

(Attempts) to SHUT open SRV (F041G) by placing control switch to OPEN, and then back to OFF (from 1H13-P601 or P642 control switches as necessary).

Removes fuses for the A and B solenoids (for F041G) at panels 1H13-P661/P662, using Table 1 for fuse location.

SRO

Acknowledges report from ATC/BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Enters CPS 4009.01 Inadvertent Opening Safety/Relief Valves and CPS 4005.01 Loss Of Feedwater Heating.

o May review ITS 3.4.4 Safety/Relief Valves (S/RVs) and verify entry conditions are NOT met.

o Informs Shift Manager.

o Conducts a brief.

Terminus: SRV F041G is SHUT NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 10 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 7 Page 1 of 2

Description:

Loss of CY - Rapid Plant Shutdown Initiation: Following Event 6 and upon direction of the Lead Examiner, insert REMOTE 5 Cues: Annunciator CPS 5014-2B Low Press Cycle Cond Xfer Pump Disch Hdr Time Position Applicants Actions or Behavior Key Parameter Response: None Expected Annunciators: CPS 5014-2D, Low Press Cycled Cond Xfer Pumps Disch Hdr Automatic Actions: None o For the Rapid Plant Shutdown, evacuates the containment and makes a plant ATC announcement, Performing a Rapid Plant Shutdown due to loss of CY Pumps.

When directed by the SRO, performs a Rapid Plant Shutdown IAW CPS 3005.01 Unit Power Changes by lowering core flow using RR FCVs until core flow is ~ 43 mlbm/hr.

Places the mode switch in SHUTDOWN and carries out Scram Choreography by reporting:

Rod status is

Reactor Power is and trend

Reactor pressure is and trend

Reactor level is and trend

Any EOPs with entry conditions (no values required).

o Stops all running condensate pumps 1CD01PA (B) (C) (D).

Performs EOP actions as directed by SRO.

BOP

Reports annunciator 5014-2D Low Press Cycled Cond Xfer Pumps Disch Hdr to the SRO.

Refers to the ARP for 5014-2D.

Per CPS 5014-2D, Low Press Cycled Cond Xfer Pumps Disch Hdr:

Operates CY transfer pumps consistent with system demand to maintain normal header pressure per CPS 3208.01, Cycled/Makeup Condensate (CY/MC) o Operator may go to CPS 3208.01 Section 8.2.2 directly or to 8.3.1 which will then direct him/her to section 8.2.2.

Per CPS 3208.01, Cycled/Makeup Condensate (CY/MC):

Starts the A CY Pump:

Observes an increase in Cyc Cond Xfer Pmp Disch Hdr Pressure followed by a decrease in Cyc Cond Xfer Pmp Disch Hdr Pressure on 1H13-P870-5014.

Reports annunciator 5014-2D Low Press Cycled Cond Xfer Pumps Disch Hdr has been received again.

Reports loss of CY to the SRO.

o For the Rapid Plant Shutdown, evacuates the containment and makes a plant announcement, Performing a Rapid Plant Shutdown due to loss of CY Pumps.

Carries out Scram Choreography by reporting:

Reactor Scram

MDRFP may start

Evacuate the RCIC room

Evacuate the Containment

Determines rod status and reports it to the SRO

Performs EOP actions as directed by SRO.

Acknowledges reports from ATC/BOP.

SRO

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Per CPS 3005.01 Unit Power Changes, directs ATC to perform a Rapid Plant Shutdown or Reactor Scram when it has been determined that CY has been lost.

o Directs ATC to stop all running condensate pumps 1CD01PA (B) (C) (D)

Enters and executes CPS 4100.01 Reactor Scram.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 11 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0

Carries out Scram Choreography by performing an Update:

Update:

Entering EOP-1

Entering the Scram Off-Normal

End of Update Terminus: Reactor has been scrammed and scram actions are in progress.

NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 12 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Operator Actions Event No.(s): 8, 9 Page 1 of 2

Description:

LOCA/RAT trip/E51-F013 Failure/Div 3 ERAT Feed Breaker Failure/TAF Blowdown/LPCS Fails to Auto Start Initiation: Triggered by the Main Generator trip in Event 7.

Cues: Multiple annunciators on 1H13-P680, 1H13-P870, and 1H13-P601, rising DW pressure and temperature indications Time Position Applicants Actions or Behavior Key Parameter Response: Rising DW temperature and pressure, loss of 4160 and 6900 V Non-vital busses.

Expected Annunciators: Multiple annunciators on 1H13-P680, 1H13-P870, and 1H13-P601 Automatic Actions: ECCS systems and DGs start on high DW pressure (1.68 psig)

ATC o Reports trip of the RAT transformers/loss of non-vital AC power.

o Reports that the RCIC Injection valve failed to open remotely and manually.Performs EOP actions as directed by SRO.

Performs EOP actions as directed by SRO.

o Reports that the LPCS Pump failed to automatically start and manually starts the pump.

o Coordinates with BOP operator to monitor and control RPV level and pressure.

o Reports failure of ADS to automatically initiate when RPV level reaches Level 1 (-145.5).

Per EOP-3, Emergency RPV Depressurization (may be performed by BOP):

[CT]

o When TAF (-160 inches on Wide Range level indicators) is reached, initiates ADS to Blowdown the reactor within 17.5 minutes after RPV level reaches -145.5 (Level 1)

[CT]

when directed by the SRO.

o Maximizes ECCS injection (including starting LPCS Pump) to restore RPV water level above TAF within 17.5 minutes after RPV level reaches -145.5 (Level 1).

BOP o Reports trip of the RAT transformers/loss of non-vital AC power.

o Performs a manual Group 1 Isolation.

o Reports that the RCIC Injection valve failed to open remotely and manually.

Performs EOP actions as directed by SRO.

o Reports that the LPCS Pump failed to automatically start and manually starts the pump.

Starts Containment Spray, as directed by the SRO.

Secures Containment Spray when RPV water level is -100 inches WR.

o Reports failure of ADS to automatically initiate when RPV level reaches Level 1 (-145.5).

Per EOP-3, Emergency RPV Depressurization (may be performed by BOP):

[CT] o When TAF (-160 inches on Wide Range level indicators) is reached, initiates ADS to Blowdown the reactor within 17.5 minutes after RPV level reaches -145.5 (Level 1)

[CT] when directed by the SRO.

o Maximizes ECCS injection (including starting LPCS Pump and opening 1E12-F005) to restore RPV water level above TAF within 17.5 minutes after RPV level reaches -

145.5 (Level 1).

Verifies ADS actuation using the following indications:

o SPDS o DCS Display 122 (2H) [Acoustic Monitor Input]

o DCS Display 186 (7B) [A Solenoid Input]

o 1H13-P601/P642 Solenoid Indicator Lights o 1H13-P866, Valve Flow Monitor Control Panel o 1H13-P614, ADS Safety Valve Temperature recorder 1B21-R614 o Indirect indication via changes in RPV pressure, RPV level, MSL flows &

suppression pool temperatures.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 13 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Event No.(s): 8, 9 Page 2 of 2 SRO

Acknowledges reports from ATC/BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Enters and executes the following off-normal procedures:

CPS 4001.01 Reactor Coolant Leakage

CPS 4001.02 Automatic Isolation

Enters and executes EOP-1 RPV Control.

Enters and executes EOP-6 Primary Containment Control

Enters and executes EOP-3 Emergency RPV Depressurization (Blowdown) when RPV Level reaches TAF.

When TAF (-160 inches on Wide Range level indicators) is reached, directs:

[CT]

initiating ADS to Blowdown the reactor within 17.5 minutes after RPV level reaches -145.5 (Level 1).

[CT]

maximizing ECCS injection (including starting LPCS Pump and opening 1E12-F005) to restore RPV water level above TAF within 17.5 minutes after RPV level reaches -145.5 (Level 1).

Terminus: The scenario can be terminated when a blowdown has been initiated, RPV level has being raised above TAF, and containment parameters are being controlled per EOP-6.

NOTES:

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 14 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Simulator Operator Instructions Initial Setup

1. Fill out plant status and have Turnover Sheet ready for the crew.

2. Verify daily lamp test completed.

3. Reset to IC-221 (PW 76319) @ 78% Power. If this is the first reset after swapping simulator loads, reset the IC twice.

4. Load the lesson plan for this scenario.

5. Verify the following commands are active:

A05_A02_A0508 TVM 5066-8A ADS B Out of Service (OFF)

A05_A02_A0608 TVM 5067-8A ADS A Out of Service (OFF)

A05_A02_A13DS47_1 ADS A&E Inhibit Wht Light (OFF)

A05_A02_A13DS48_1 ADS B&F Inhibit Wht Light (OFF)

A05_A02_A13S63 ADS A&E Inhibit PB (Inhibited)

A05_A02_A13S64 ADS B&F Inhibit PB (Inhibited)

YARIMVFP_2 E51F013 (immediate) Fail-To Position (FV = 0)

YP_XMFTB_4106 LPCS Fail to Auto Start

lp11acld001fsp=True (LPCS Injection Valve Auto Open Failure)

6. Place simulator in RUN.

7. Turn on and advance recorders.

8. Verify RCIC Flow Controller is set at 620 gpm.

9. Verify the AR/PR server is running and stabilize AR/PR.

10. Verify Rod Drive pressure is in the expected range of 235-265 psid.

11. Provide pull sheets: Step 29 is in progress - Gang 10A is at Position 10.

12. Make sure Sequence A is selected.

13. Make sure Individual Drive Mode is selected on the OCM.

14. Remove EST Tags from the following control switches:

1H13-P877-5014 - MC Pump B

1H13-P877-5016 - 1TD004A RFPT 1A HP Stop Vlv Before SDV

1H13-P877-5019 - 1B21-BSFV-1 Aux Stm to MSR 1B Inlet Vlv

1H13-P877-5019 - 1GS02CB SPE Blower 1B2

1H13-P800-5042 - 0VQ03CC DW Prg Low Flow Exh Fan

1H13-P801-5050 - 1VY03C RHR Hx Rm A Sply Fan

1H13-P801-5050 - 1VY04C RCIC Pmp Rm Sply Fan

1H13-P801-5050 - 0VC69Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P801-5052 - 0VC70Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P601-5064 - 1SX011A Div 1 Cross Tie Valve

1H13-P601-5065 - 1SX011B Div 2 Cross Tie Valve

1H13-P601-5067 - 1B21-F067B MSL B Outbd MSIV Before Seat Drain Vlv

15. Procedures that are expected to be used during this scenario are:

CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability (provided in the Crew Docs binders)

CPS 5062 Annunciator Response Procedures

CPS 4200.01 Loss of AC Power

ITS 3.8.1 AC Sources - Operating

CPS 5006 Annunciator Response Procedures

CPS 3304.01 Control Rod Hydraulic and Control (RD)

CPS 3304.02 Rod Control and Information System (RC&IS)

CPS 5140 Annunciators (MCR AR/PR LAN)

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 15 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0

CPS 3315.03 Radiation Monitoring (AR/PR)

ODCM 3.9.2 Radioactive Gaseous Effluent Monitoring Instrumentation

CPS 5001 Annunciator Response Procedures

CPS 3104.01 Condensate/Condensate Booster (CD/CB)

CPS 5066 Annunciator Response Procedures

CPS 5067 Annunciator Response Procedures

CPS 4005.01 Loss of Feedwater Heating

CPS 4009.01 Inadvertent Opening Safety/Relief Valves

ITS 3.4.4 Safety/Relief Valves (S/RVs)

CPS 5014 Annunciator Response Procedures

CPS 3208.01 Cycled/Makeup Condensate (CY/MC)

CPS 3005.01 Unit Power Changes

CPS 4100.01 Reactor Scram

EOP-1 RPV Control

CPS 4001.01 Reactor Coolant Leakage

CPS 4001.02 Automatic Isolation

EOP-6 Primary Containment Control

EOP-3 Emergency RPV Depressurization

16. Hang OOS tags on: CY Pump B (0CY01PB)

17. Identify T/S issues associated with OOS and turnover: ITS 3.8.1 AC Sources - Operating, Condition B (with Division 3 DG speed droop set to 50%).

18. Operating Equipment: None

19. Marked up copies: CPS 9080.03 (all step up to and including 8.2.16.1)

20. Verify simulator conditions match the turnover.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 16 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Event Triggers and Role Play Event #

1. Secure DG 1C

a. Event Trigger - None

b. Role Play - Field Operator: If the BOP reports commencing to unload DG 1C, acknowledge the report.

2. DG 1C Overspeeds When Unloaded

a. Event Trigger - None

b. Role Play - Field Operator: If requested to report local panel 1E22-S001B status following the DG 1C trip, report the following:

(1) Annunciator 5286-1B Overspeed locked in (2) Annunciator 5286-2C Engine Tripped locked in (3) Both DG 1C 86 lockout relays tripped

3. CRD high temperature

a. Event Trigger - Following Event 2 and when directed by the Lead Examiner, Activate Remote 1 and verify the following command(s):

(1) A02_A05_01_7_TVM=2 (Annunciator 5006-1G CRD Hydr Temp Hi).

b. Role play:

(1) Field Operator (if requested):

a) Report, CRD 52-25 is alarming at 255°F and trending up at 1°F every five minutes. All other CRD temperatures appear to be normal b) After rod 52-25 has been repositioned to position 46, report CRD 52-25 temperature is ~ 240°F and slowly lowering.

4. Failure of 0RIX-PR001 Ch 15 - Low flow due to sample pump failure

a. Event Trigger - Following Event 3 and when directed by the Lead Examiner, Activate Remote 2 and verify the following command(s):

(1) CAM0PR001IA_PUMP to 1. (PR001 Sample Pump Status)

(2) CAM0PR001TV_VALUE15 to 0. (PR001 Ch 15 input)

b. Role play (1) Field Operator/Chemistry (if directed to check the status of the sample pump for 0RIX-PR001) - The pump is not running. No other abnormalities exist locally at the PRM.

(2) Chemistry (if requested to report filter status for 0RIX-PR002) - 0RIX-PR002 has a fresh filter installed.

5. Clogged oil filter Condensate Booster Pump A

a. Event Trigger - When directed by the Lead Examiner, Activate Remote 3 and verify the following command(s):

(1) A01_A02_01_8_TVM Steady

b. Role play (1) Field Operator (If requested):

a) (when directed to turn the handle on the CB 1A CUNO Filter) - acknowledge request. Wait ~ one minute and report I turned the handle on Condensate Booster Pump 1A CUNO Filter several times".

b) (if asked for CB Pump A oil pressure) - report 13 psig and slowly lowering.

c) (if asked to verify the position of 1CB011C) - report 1CB011C is locked open.

d) (when directed to perform startup checks for the standby CB pump) - report Pre-starts are complete".

e) (when directed for local indications during prestart checks) - report Lube oil pressure is > 8 psi and lube oil temperature is >75°F".

f) (when asked if CB Pump C is operating normally locally) - report CB Pump C is running normally.

ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 17 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0

6. Inadvertent opening of a SRV

a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 4 and verify the following command(s):

(1) YPXMALSE_77 to 50 (F041G MS Relief Failure)

b. Role play (1) Booth Operator (if requested by BOP and not performed at the V-Panel):

a) cycle the Div 2 CS for SRV 41G to Open and then Off - Release 41G P642 CS to Open / Off (YP_HP101_7 Open and YP_HP101_7 Off) b) remove fuses for F041G A Solenoid - Release 41G A Fuse Removed (YP_XREMT_371 = OFF) c) remove fuses for F041G B Solenoid - Release 41G B Fuse Removed (YP_XREMT_387 = OFF)

7. Loss of CY - Rapid Plant Shutdown

a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 5 and verify the following command(s):

(1) YFFWPPSS_11. (CY Pump C Shaft Shear)

(2) YAFWPPDE_9. (CY Pump A Pumping Efficiency)

b. Role play (1) Field Operator:

a) When directed to check operation of CY Pump C - The motor is running, but the pump shaft is not turning, and the motor is making noise and vibrating.

b) When directed to perform CY Pump A prestart checks - CY Pump A prestart checks are complete. When directed to Shut/verify shut 0CY004A CY Pump A Discharge - 0CY004A is Shut. When directed to slowly open 0CY004A CY Pump A Discharge - 0CY004A is Open.

c) When directed to check operation of CY Pump A - CY Pump A discharge pressure indicates 30 psig locally. The pump is not making any unusual noises. There is no evidence of leakage locally.

(2) ROC Operator:

a) When informed that the CY system has been lost (3208.01 step 8.3.1.5 - acknowledge report.

b) If directed to check for indications of CY leakage - There are no indications of increased inleakage in the ROC.

8. LOCA/RAT trip/E51-F013 Failure/Div 3 ERAT Feed Breaker Failure/TAF Blowdown

a. Event Trigger - triggered by GCB 4506 opening during Event 7. Verify the following command(s):

(1) RAT_B_OVERCURRENT (2) ED17B221C1FO 1ETR4C1 Bkr Tripped (3) YPXMALSE_511 RR03C Lower Plenum Leak

b. Role play:

(1) Maintenance (after 2 minutes from scram announcement) - report to the MCR as IMD.

(2) Field Operator:

a) (If requested to check the status of Div 3 ERAT feeder breaker) - The overcurrent relay is tripped.

b) (If requested to manually open the RCIC injection valve) - Heading to WEC for a brief.

9. LPCS Fails to Auto Start / LPCS Injection Valve 1E21F005 Fails to Auto Open at 472 psig RPV pressure

a. Event Trigger - Initial condition

b. Role play - none ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 18 of 19

ILT 15-1 NRC Exam Scenario 1 Rev. 0 Turnover

1. Day of week and shift

Today day shift

2. Weather conditions

Thunderstorms are expected in the area within the next hour.

3. Plant power level

The plant is in Mode 1, operating at ~ 78% power to support performance of CPS 9031.07 Main Turbine Control Valve Tests on the next shift.

RR Pumps A and B are operating in fast speed with FCVs at 53%/54%. 2714 MWt, 872 MWe, 71.02 Mlbm/hr Core Flow.

Control rods - Step 29 / Gang 10A is at position 10.

4. Thermal Limit Problems/Power Evolutions

Power will be maintained at 78% throughout the shift.

CPS 3005.01 Unit Power Changes section 8.2 Power Decrease in progress. Step 8.2.5 is complete.

On Step 2 of ReMA C16-001

RE and Rod Verifier are available on request.

5. LCOs in effect

Appropriate LCOs have been entered for current plant conditions.

6. Surveillances in progress

Div 3 DG has been operating at full load for > 60 minutes IAW CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability step 8.2.16.1.

CPS 9082.01 Offsite Source Power Verification was completed one hour ago.

7. Status of Tagged Out Equipment

CY Pump B (0CY01PB) is OOS for maintenance. Not expected back this shift.

8. Previous Shift Evolutions completed

Power was lowered to 78%. Div 3 DG was started and paralleled to RAT B IAW CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability.

CPS 9082.01 Offsite Source Power Verification was completed one (1) hour ago.

9. Evolutions planned for the shift

Unload DG 1C and complete CPS 9080.03 DG 1C Operability - Manual and Quick Start Operability starting at step 8.2.16.2.

10. Risk Levels

Green

Protected Equipment: FC B

11. Dose equivalent Iodine 131

reading 1.5 E-6 µcuries per gram ILT 15-1 NRC Exam Scenario 1 Rev 0.docx Page 19 of 19

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Exelon Nuclear ILT 15-1 NRC Exam Scenario Number:

NRC Exam Scenario 2 Revision Number: 1 Date: 10/28/16 Developed By: T. Jennings 9/22/16 Instructor Date Validated By: Michael Antonelli 10/28/16 SME or Instructor Date Reviewed By: Jim Lucas 11/15/16 Operations Representative Date Approved By: T. Jennings 11/15/16 Training Department Date ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 1 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 2 Operating Test No.: 2017-301 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Mode 1 Rx Power at 99%.

Weather conditions are calm and clear.

Turnover:

Priorities for the shift are as follows:

Shift Generator Stator Cooling Pumps IAW CPS 3110.01 01Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps (MCR) to support upcoming corrective maintenance on GC Pump B.

Maintain power at 99% throughout the shift.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Shift Generator Stator Cooling (GC) Pumps.

2 YP_XMFTB_4102 I-BOP Spurious HPCS auto initiation TS-SRO 3 A02_A01_02_10_TVM C-ATC RR Pump B high vibration TS-SRO 4 N/A R-ATC Reduce power with Control Rods 5 YP_XMFTB_3917 C-BOP CCW Pump 1A trip 6 YP_XMFTB_4965 C-ATC RR Pump A trip/ATWS YP_XMFTB_4963 7 YPXMALSE_256 0.08% M-All Unisolable MSL D Leak / Multiple Secondary YAMSSIFP_4 Containment Areas above max safe YVMSSILK_8 temperatures requiring blowdown YPXMALSE_256 0.5%

8 YP_XREMT_739 C-All MSIVs fail to close on Group 1 isolation signal

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 2 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 Operating Test No.: 2017-301 Narrative Summary Event # Description

1. Shift Generator Stator Cooling (GC) Pumps The BOP will shift GC Water Pumps IAW CPS 3110.01Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps (MCR) to support upcoming maintenance on 1GC01PB.

2. Spurious HPCS auto initiation High Pressure Core Spray (HPCS) initiates with no operator action. The following annunciators are received: 5062-3C RUNNING DIESEL GEN 1C, 5062-4E HPCS PUMP AUTO START, 5064-1B AUTO START SSW PUMP 1C and 5064-4B AUTO START DG FUEL OIL XFER PUMP 1C. IAW CPS 3309.01 High Pressure Core Spray (HPCS), the crew will verify by at least two independent indications that misoperation in automatic is confirmed or adequate core cooling is assured. Once confirmed, the SRO will direct the BOP operator to secure HPCS. Technical Specification LCO 3.5.1 Actions B.1 and B.2 will be evaluated requiring verification by administrative means that the RCIC system is operable when required AND the HPCS system is restored to operable status within 14 days.

3. RR Pump B high vibration Annunciator 5003-2K RECIRC PMP B MTR VIBR HI is received. BOP will determine B RR Pump vibration levels are 20 mil P-P steady on both probes. ATC will perform RR Loop B Emergency Shutdown. SRO will enter CPS 4008.01 Abnormal Reactor Coolant Flow, CPS 4002.01 Abnormal RPV Level/Loss of Feedwater At Power and ITS LCO 3.4.1 B.1 and C.1.

4. Reduce power with Control Rods Due to the RR Pump B Emergency Loop Shutdown and using CPS 3005.01 Unit Power Changes (Figure 1: Stability Control & Power/Flow Operating Map), the crew will identify a MELLA Limit violation.

Per CPS 3005.01 Unit Power Changes, section 6.5 MELLA Limit Operational Concerns, the SRO will enter Action A.1 for ITS 3.2.1, 3.2.2 and 3.2.3 to restore power distribution limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and direct the ATC to promptly lower power via reverse rod sequence or CRAM RODS. Additionally, the SRO may direct ATC to lower reactor power to 58% RTP IAW TS LCO 3.4.1 B.1 based on having one recirculation loop in operation.

5. CCW Pump 1A trip The following annunciators are received: 5040-1B AUTO TRIP PUMP/MOTOR, 5040-2C LOW PRESS CCW HX OUTLET HEADER and 5003-3D/3K RECIRC MTR A/B WDG CLG WTR FLOW LO are received. BOP will observe that CCW Pump 1A has tripped, review the ARP and start a standby CCW pump.

6. RR Pump A trip/ATWS Annunciator 5003-1F RECIRC PMP A MTR BRKR Trip is received due to a trip of the A RR Pump. With no RR Pumps operating with the mode switch in RUN, the ATC will insert a manual scram (IAW CPS 4008.01 Abnormal Reactor Coolant Flow) and shut 1B33-F023A RR Pmp Suction Vlv. When the mode switch is placed in shutdown, the reactor will fail to scram requiring entry into EOP-1 RPV Control and then transition into EOP-1A ATWS RPV Control. Control Rods will be successfully inserted when ARI is manually initiated. Once shutdown criteria is met, the SRO will exit EOP-1A and re-enter EOP-1 RPV Control.

7. Unisolable MSL D Leak / Multiple Secondary Containment Areas above max safe temperatures requiring blowdown Multiple annunciators are received due to an unisolable MSL D leak into the Aux Building Steam Tunnel (secondary containment). The SRO will enter 4001.01 Reactor Coolant Leakage off-normal and EOP-8 Secondary Containment Control. Temperatures will continue to rise in the Secondary Containment, and when two or more areas exceed max safe temperatures, the SRO will enter EOP-3 Emergency RPV Depressurization and will direct a blowdown to be performed.

8. MSIVs fail to close on Group 1 isolation signal The MSIVs will fail to automatically close when MSL Tunnel Ambient Temperature reaches the Group 1 Isolation setpoint, but can be manually closed from the MCR.

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 3 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 EOP 1, 3, 8 Critical tasks:

RPV-5.1/6.1 ATC/BOP inserts control rods using ARI to shutdown the reactor.

SC-1.2 SRO enters EOP-3 and directs a blowdown when 2 or more areas are above the max safe value of the same parameter (Table T, U, W), and a Primary System is discharging into the Secondary Containment, which cannot be isolated. If the crew Anticipates Blowdown using bypass valves, and in doing so two areas do not reach a max safe condition, then this critical task is considered to be met.

(PRA)

Immediately places the Reactor Mode Switch in Shutdown w/no RR Pumps running with the Reactor Mode Switch in Run. N/A ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 4 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 1 Page 1 of 1

Description:

Shift Generator Stator Cooling (GC) Pumps Initiation: Following shift turnover and when directed by the Lead Examiner Cues: Directed by SRO Time Position Applicants Actions or Behavior General Note on Requirements for Expected Annunciator Response - OP-AA-103-102 If this evolution was pre-briefed and Expected Alarms were reviewed, the following expectations apply:

Expected alarms will be flagged

When the annunciator comes in the operator will announce Expected Alarm

The annunciator response procedure (ARP) need not be entered since it has already been reviewed in the pre-brief.

If a pre-brief was not conducted the operator should perform the following:

When an annunciator comes in the ARP should be referred to.

The annunciator may then be identified as an Expected Alarm, flagged, and from that point on the ARP need not be referred to.

Key Parameter Response: GC Pump indicator lights on 1H13-P870-5017 Expected Annunciators: 5017-5A Auto Start Stator Cooling Water Pump (when the standby pump auto start feature is tested)

Automatic Actions: GC Pump 1B will auto start when the when the standby pump auto start feature is tested.

ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Performs Plant Announcement.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

o Performs Plant Announcement.

IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4:

BOP obtains authorization from the Control Room Supervisor to perform critical steps ({CS})

before performing CPS 3110.01 Section 8.2.4.

{CS} Starts standby GC Pump 1A (1GC01PA).

{CS} Stops GC Pump 1B (1GC01PB). Allows the control switch to spring return to AUTO.

Tests the standby GC pump auto start by:

Depressing the Generator Cooling Water Pump Test push-button.

Verify the AUTO START STATOR COOLING WATER (5017-5A) annunciator illuminates.

{CS} Places control switch for the GC Pump 1B (1GC01PB) in the STOP position, AND lets it spring return to AUTO.

SRO

Acknowledges reports from ATC/BOP.

Authorizes BOP to perform the critical steps contained in CPS 3110.01 Section 8.2.4 (denoted by

{CS}).

Provides direct oversight of the GC Pump shift.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Terminus: GC Pumps shifted and the auto start feature of the standby GC pump has been tested.

NOTES:

Solid bullets are required actions o Hollow bullets are actions that may or may not be performed ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 5 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 2 Page 1 of 1

Description:

Spurious HPCS Auto Initiation Initiation: Following Event 1 and upon direction of the Lead Examiner, insert REMOTE 1.

Cues: Annunciator 5062-4E, HPCS Pump Auto Start Time Position Applicants Actions or Behavior Key Parameter Response: None Expected Annunciators: Multiple annunciators Automatic Actions: DG 1C Auto Starts, HPCS To CNMT Outbd Isln Valve (1E22-F004) OPEN ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Performs Plant Announcements.

o Dispatches an Equipment Operator to investigate.

BOP

Reports issue to SRO.

Refers to ARPs.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Performs Plant Announcements.

o Dispatches an Equipment Operator to investigate.

Per CPS 3309.01 High Pressure Core Spray (HPCS):

Verifies by at least two independent indications that:

Misoperation in automatic is confirmed, or

Adequate core cooling is assured.

Performs shutdown of HPCS (Initiation Signal Present):

Shuts 1E22-F004 HPCS To CNMT Outbd Isln Valve.

Stops HPCS Pump, 1E22-C001.

o Verifies 1E22-F012, HPCS Min Flow To Suppr Pool shuts.

o Verifies HPCS Pmp Rm Sply Fan, 1VY08CA stops.

o Verifies HPCS Pmp Rm Sply Fan, 1VY08CB stops.

SRO

Acknowledges report from BOP.

Directs actions listed above.

Enters and executes CPS 4002.01 Abnormal RPV Level/Loss Of Feedwater At Power o Establishes reactor water level as a critical parameter and directs ATC to scram the reactor if RPV water level reaches 48 inches and rising.

Evaluates and enters TS 3.5.1 Action B.1 and B.2.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Contacts Maintenance to investigate.

o Informs Shift Manager.

Conducts a brief.

Terminus: HPCS is secured and Technical Specifications evaluated.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 6 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 3 Page 1 of 1

Description:

RR Pump B High Vibration Initiation: Following Event 2 and upon direction of the Lead Examiner, insert REMOTE 2.

Cues: Annunciator 5003-2K Recirc Pmp B Mtr Vibr Hi Time Position Applicants Actions or Behavior Key Parameter Response: RR Pump Vibration Indications Expected Annunciators: 5003-2K Recirc Pmp B Mtr Vibr Hi Automatic Actions: None ATC

Reports issue to SRO.

Refers to ARPs.

Per 5003-2K Recirc Pmp B Mtr Vibr Hi and CPS 3302.01 Reactor Recirculation (RR):

Performs emergency loop shutdown of RR Pump B.

o Depresses P680 RR Pump B Vibration reset button.

Per CPS 4008.01 Abnormal Reactor Coolant Flow:

o Monitors RR Pump seal pressure for signs of degradation

Checks operation on the Power to Flow map

Notifies SRO MELLLA limit has being exceeded

Determines flow transient has resulted in entry into the OPRM Enable Region by observing the status of annunciator 5006-3D Per CPS 4002.01 Abnormal RPV Level/Loss of Feedwater at Power:

Per 3302.01 Reactor Recirculation (RR) Appendix A: RR Loop/Pump Shutdown and Isolation Hard Card:

Lowers RPV water level setpoint to ~ 31 inches

Trips RR Pump B by opening RR 3B, 4B, or 5B (any one of the three as a minimum)

Shuts 1B33-F023B, Pmp Suction Vlv o Re-opens 1B33-F023B, Pmp Suction Vlv after 5 minutes.

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP o Monitors reactor to ensure operations remain within established bands.

o Checks RR Vibration Monitor and determines RR Pump B Vibration is 20 mil P-P steady on both probes o Makes plant announcement o Demands an official 3D Monicore Case

Acknowledges report from ATC.

SRO

Directs actions listed above

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Reviews and enters Tech Spec 3.4.1 B.1 and C.1

Enters CPS 4008.01 Abnormal Reactor Coolant Flow

Enters CPS 4100.02 Core Stability Control

Directs ATC to scram the reactor if the restricted zone is entered of if core instabilities are observed.

Enters CPS 4002.01 Abnormal RPV Level / Loss of Feedwater At Power

Directs ATC to monitor RPV Level and to scram if RPV level approaches 52 (Level 8).

o Directs lowering power below the MELLLA limit using reverse rod sequence or CRAM Rods within 15 minutes after plant is stable to be in compliance within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

With the MELLLA Limit exceeded, enters ITS LCOs 3.2.1, 3.2.2, AND 3.2.3

With the RR Loop jet pump flow mismatch not within limits, enters ITS 3.4.1 RA A.1.

o Informs Shift Manager.

o Conducts a brief.

Terminus: RR Pump B secured and Tech Spec review complete.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 7 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 4 Page 1 of 1

Description:

Reduce power with Control Rods Initiation: After RR Pump B has been secured Cues: Directed by SRO Time Position Applicants Actions or Behavior Key Parameter Response: Reactor Power, Rod Drive Parameters (flows, dP), Control Rods move as expected Expected Annunciators: None Automatic Actions: None ATC

Per CPS 3304.02 Rod Control and Information System (RC&IS), NF-CL-721-1002 Control Rod Move Sheets, and CPS 3005.01 Unit Power Changes section 8.2:

Reduces reactor power by inserting control rods to get below the MELLLA limit (<

67%).

o Reduces reactor power to < 58% using control rod insertion when directed by SRO

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

SRO

Directs actions listed above

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Positions himself/herself in proximity of the reactor operator, typically the location from which EOP actions are directed (OP-AA-300) o Notifies Shift Manager o Notifies TSO o Conducts a brief.

Terminus: Clearly observable plant response from change in power level.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 8 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 5 Page 1 of 1

Description:

CCW Pump 1A Trip Initiation: Following Event 4 and upon direction of the Lead Examiner, insert REMOTE 3 Cues: Annunciator 5040-1B Auto Trip Pump/Motor alarm.

Time Position Applicants Actions or Behavior Key Parameter Response: Lowering CCW System Header Pressure Expected Annunciators: 5040-1B Auto Trip Pump/Motor, 5003-3D RECIRC MTR A WDG CLG WTR FLOW LO, 5003-3K RECIRC MTR B WDG CLG WTR FLOW LO Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies SRO of unusual/unexpected conditions.

o Makes plant announcement.

o Dispatches EO to investigate CCW Pump trip.

o Monitors CCW Storage Tank Level.

o Monitors RR Pump motor and seal parameters.

BOP

Reports issue to SRO.

Refers to ARP.

Per 5040-1B Auto Trip Pump/Motor alarm:

Determines CCW Pump A has tripped.

Determines CCW Pump B is running.

Starts CCW Pump C.

o Monitors CCW Storage Tank Level.

o Dispatches EO to investigate.

SRO

Acknowledges reports from BOP.

o Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Informs Shift Manager.

o Contacts Maintenance to investigate.

o Conducts a brief.

Terminus: CCW Pump B running.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 9 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 6 Page 1 of 2

Description:

RR Pump A Trip / ATWS Initiation: Following Event 5 and upon direction of the Lead Examiner, insert REMOTE 4 Cues: Annunciator 5003-1F RECIRC PMP A MTR BRKR TRIP Time Position Applicants Actions or Behavior Key Parameter Response: Reactor Power, RPV Level Expected Annunciators: 5003-1F RECIRC PMP A MTR BRKR TRIP Automatic Actions: None ATC o Reports issue to SRO.

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Determines that no Recirculation Pumps are running with the Reactor Mode Switch in RUN (entry condition for CPS 4008.01 Abnormal Reactor Coolant Flow).

Per CPS 5003-1F RECIRC PMP A MTR BRKR TRIP, CPS 4008.01 Abnormal Reactor Coolant Flow and CPS 4100.01 Reactor Scram:

[CT] * [CT] Places the mode switch in SHUTDOWN.

Determines that Shutdown Criteria is not met.

Arms and depresses Manual Scram Pushbuttons.

[CT] Initiates ARI.

[CT]

Determines Shutdown Criteria is met.

Carries out Scram Choreography by reporting:

Rod status is

Reactor power is and trend

Reactor pressure is and trend

Reactor level is and trend

Manual Scram and ARI have been initiated

Any EOPs with entry conditions (no values required)

IF RPV level is rising with 2 feed pumps operating, THEN Secures/verifies secured 1 Feed Pump and controls RPV water level between Level 3 and Level 8.

o Verifies Turbine and Generator trip when required.

o Shuts 1B33-F023A RR Pump A Suction Valve.

Stabilizes Reactor Pressure 800 to 1065 or per directed band.

Performs EOP actions as directed by SRO.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

Per CPS 4100.01 Reactor Scram:

Carries out Scram Choreography by:

Making an Announcement

§ Reactor Scram

§ Motor Driven Reactor Feed Pump may start

§ Evacuate the RCIC room

§ Evacuate the Containment

§ Determines Rod status and reports shutdown criteria met to the SRO.

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 10 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 SRO

Acknowledges reports from ATC/BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Enters and executes CPS 4008.01 Abnormal Reactor Coolant Flow and CPS 4100.01 Reactor Scram Enters CPS 4100.01 Reactor Scram:

o Directs ATC to scram the reactor.

Carries out Scram Choreography by performing an Update:

Update

Entering EOP-1

Transitioning to EOP-1A

Entering the Scram Off-Normal

End of Update Enters EOP-1A, ATWS RPV Control, and directs the following:

[CT] o Inhibit ADS.

[CT] Verifies ATC manually initiates ARI.

Determines Shutdown Criteria is met when ARI pushbuttons have been armed and depressed and transitions from EOP-1A back to EOP-1.

Directs / Verifies performance of appropriate actions per EOP-1 RPV Control:

Control of RPV pressure between 800 to 1065 psig with Bypass Valves or SRVs.

Control of RPV water level between Level 3 to Level 8 by using Preferred Injection Systems.

o Informs Shift Manager.

o Conducts a brief.

Terminus: Scram choreography complete. Rods manually inserted by initiating ARI.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 11 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Operator Actions Event No.(s): 7, 8 Page 1 of 2

Description:

Unisolable MSL D Leak / Multiple Secondary Containment Areas above max safe temperatures requiring blowdown / MSIVs fail to close on Group 1 Isolation Signal Initiation: Following Event 6 and upon direction of the Lead Examiner, insert REMOTE 5 Cues: Multiple Aux Building Steam Tunnel High Temperature annunciators on 1H13-P601.

Time Position Applicants Actions or Behavior Key Parameter Response: Rising temperatures on 1TR-CM326 & 327 Secondary Containment Temperature Recorder (multiple points).

Expected Annunciators: Multiple annunciators on 1H13-P601 Automatic Actions: CRVICS Group 1, 4, 5, 6 isolations on High MSL Tunnel Ambient Temperature

Monitors reactor to ensure operations remain within established bands.

ATC o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Reports EOP-8 entry on secondary containment area temperature above max normal.

Performs EOP actions as directed by the SRO.

o Reports EOP entry conditions.

o Coordinates with BOP to monitor and control RPV level and pressure.

o Performs a manual Group 1 Isolation of the MSLs and MSL Drains.

o Reports that the MSL leak is unisolable to the SRO.

Per EOP-8, Secondary Containment Control (will probably be BOP):

[CT] o [CT] Initiates ADS when directed by SRO.

Verifies ADS actuation using the following indications:

o SPDS o DCS Display 122 (2H) [Acoustic Monitor Input]

o 1H13-P601/P642 Solenoid Indicator Lights o 1H13-P866 Valve Flow Monitor Control Panel o 1H13-P614 ADS Safety Valve Temperature recorder 1B21-R614 o Indirect indication via changes in RPV pressure, RPV level, MSL flows &

suppression pool temperatures.

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP o Monitors reactor to ensure operations remain within established bands.

o Reports EOP-8 entry on secondary containment area temperature above max normal.

o Monitors and reports secondary containment temperatures on 1H13-P678 recorders 1TR-CM326 and 327 (may be performed by ATC/WEC).

o Determines that Group 1 MSL Isolation Valves failed to isolate on High MSL Tunnel temperature.

o Performs a manual Group 1 Isolation of the MSLs and MSL Drains.

o Reports that the MSL leak is unisolable to the SRO.

o Reports to the SRO when two areas are above Max Safe temperatures per EOP-8, Secondary Containment Control (may be performed by ATC/WEC).

[CT] o [CT] Initiates ADS when directed by the SRO.

Verifies ADS actuation using the following indications:

o SPDS o DCS Display 122 (2H) [Acoustic Monitor Input]

o 1H13-P601/P642 Solenoid Indicator Lights o 1H13-P866 Valve Flow Monitor Control Panel o 1H13-P614 ADS Safety Valve Temperature recorder 1B21-R614 o Indirect indication via changes in RPV pressure, RPV level, MSL flows &

suppression pool temperatures.

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 12 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1

Acknowledges reports from ATC/BOP.

SRO

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations standards and approved procedures.

Enters and executes EOP-8 Secondary Containment Control when ABST Temperatures have exceeded max normal values of EOP-8 Table T Area Temperature Limits.

Directs BOP/ATC to perform a manual Group 1 Isolation

Enters and executes EOP-3 Emergency RPV Depressurization when 2 or more of the following areas have exceeded max safe temperature values of EOP-8 Table T Area Temperature Limits:

Point 14 1TR-CM326 (Upper Recorder) - Aux Bldg Below MS Tunnel > 200°F

Point 18 1TR-CM326 (Upper Recorder) - Aux Bldg Steam Tunnel > 200°F

Point 15 or 16 1TR-CM327 (Lower Recorder) - Aux Bldg MSIV Room A or B >

200°F

[CT]

[CT] Directs initiation of ADS to blowdown the reactor.

o Informs Shift Manager.

o Conducts a brief.

Terminus: The scenario can be terminated when 7 SRVs have been opened and RPV water level is being maintained in accordance with EOP-1.

NOTES:

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 13 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Simulator Operator Instructions Initial Setup

1. Fill out plant status and have Turnover Sheet ready for the crew.

2. Verify daily lamp test completed.

3. Reset to IC-222 (PW 76319) @ 99% Power. If this is the first reset after swapping simulator loads, reset the IC twice.

4. Load the lesson plan for this scenario.

5. Verify the following commands are active:

YP_XMFTB_4963 Auto & Manual Scram Failure

YP_XREMT_739 Defeat Group 1 Interlocks

6. Place simulator in RUN.

7. Turn on and advance recorders.

8. Verify RCIC Flow Controller is set at 620 gpm.

9. Verify the AR/PR server is running and stabilize AR/PR.

10. Verify Rod Drive pressure is in the expected range of 235-265 psid.

11. Provide pull sheets: Step 30 is in progress - Gang 10B is at Position 22.

12. Make sure Sequence A is selected.

13. Make sure Individual Drive Mode is selected on the OCM.

14. Remove EST Tags from the following control switches:

1H13-P877-5014 - MC Pump B

1H13-P877-5016 - 1TD004A RFPT 1A HP Stop Vlv Before SDV

1H13-P877-5019 - 1B21-BSFV-1 Aux Stm to MSR 1B Inlet Vlv

1H13-P877-5019 - 1GS02CB SPE Blower 1B2

1H13-P800-5042 - 0VQ03CC DW Prg Low Flow Exh Fan

1H13-P801-5050 - 1VY03C RHR Hx Rm A Sply Fan

1H13-P801-5050 - 1VY04C RCIC Pmp Rm Sply Fan

1H13-P801-5050 - 0VC69Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P801-5052 - 0VC70Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P601-5064 - 1SX011A Div 1 Cross Tie Valve

1H13-P601-5065 - 1SX011B Div 2 Cross Tie Valve

1H13-P601-5067 - 1B21-F067B MSL B Outbd MSIV Before Seat Drain Vlv

15. Procedures that are expected to be used during this scenario are:

CPS 3110.01 Generator Stator Cooling (GC) (provided in the Crew Docs Notebook)

CPS 3309.01 High Pressure Core Spray (HPCS)

ITS 3.5.1 ECCS - Operating

CPS 4008.01 Abnormal Reactor Coolant Flow

CPS 4002.01 Abnormal RPV Level/Loss of Feedwater At Power

CPS 3302.01 Reactor Recirculation (RR)

ITS 3.4.1 Recirculation Loops Operating

CPS 3005.01 Unit Power Changes

ITS 3.2.1 APLHGR

ITS 3.2.2 MCPR

ITS 3.2.3 LHGR

EOP-1 RPV Control

EOP-1A ATWS RPV Control

EOP-3 Emergency RPV Depressurization (Blowdown)

EOP-8 Secondary Containment Control

CPS 4200.01 Auto Isolation

16. Hang OOS tags on: None ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 14 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1

17. Identify T/S issues associated with OOS and turnover: None

18. Operating Equipment: Make sure CCW Pumps A and B are running

19. Marked up copies: None

20. Verify simulator conditions match the turnover.

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 15 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Event Triggers and Role Play Event #

1. Shift Generator Stator Cooling Pumps (Pull up 1PL10J trouble alarms)

a. Event Trigger - Following shift turnover.

b. Role play :

(1) EO (If requested) a) (when asked to check local panel alarms on 1PL10J ) - acknowledge 1PL10J alarms and provide reports.

b) (when asked to perform prestart checks for GC Pump A) - Prestart checks are complete for GC Pump A. Im standing by for pump start.

c) (when asked to check for GC Pump A locally) - GC Pump A is running normally.

2. Spurious HPCS auto initiation

a. Event Trigger - Following Event 1 and when directed by the Lead Examiner, Activate Remote 1 and verify the following command(s):

(1) YP_XMFTB_4102 (HPCS Spurious Automatic Initiation)

b. Role play (1) Maintenance (if requested) - respond as dispatching personnel to investigate.

(2) EO (when requested to check Div 3 DG and/or SX for proper operation) - wait 5 minutes and report that requested equipment is operating normally.

3. RR Pump B high vibration

a. Event Trigger - Following Event 2 and when directed by the Lead Examiner, Activate Remote 2 and verify the following command(s):

(1) A02_A01_02_10_TVM (5003-2K Recirc Pmp B Mtr Vibr Hi).

b. Role play:

(1) If asked to check RR Pump vibration monitor - RR Vibration Monitoring Computer shows RR Pump B vibration indicates 21 mils and stable.

4. Reduce power with Control Rods

a. Event Trigger - Following Event 3.

b. Role play (1) If RE and/or Rod Verifier are requested - report to the MCR as the RE and/or Rod Verifier.

(2) If Chief Examiner requires additional power reduction, enter MCR as RE and recommend lowering power an additional 5% to provide additional margin to the MELLA Limit.

5. CCW Pump 1A Trip

a. Event Trigger - When directed by the Lead Examiner, Activate Remote 3 and verify the following command(s):

(1) YP_XMFTB_3917 CCW Pump 1A Trip

b. Role play (1) EO a) (when asked to investigate trip of CCW Pump A) - The breaker for CCW Pump A is tripped on overcurrent and the motor is very hot to the touch.

b) (when asked to check for proper operation of CCW Pump C) - The C CCW Pump is operating normally.

ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 16 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1

6. RR Pump A Trip / ATWS

a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 4 and verify the following command(s):

(1) YP_XMFTB_4965 (RR02A-Recirc Pump A Trip)

b. Role play (1) Maintenance (after 2 minutes from scram announcement) - report to the MCR as IMD.

7. Unisolable MSL D Leak into the Aux Building Steam Tunnel requiring blowdown

a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 5 and verify the following command(s):

(1) YPXMALSE_256 0.08%, YVMSSILK_4 100%, YVMSSILK_8 100%, YPXMALSE_256 0.4% (after ATC places the RMS in Shutdown)

b. Role play (1) WEC Supervisor (when requested to monitor secondary containment temperatures on P678 recorders 1TR-CM326 and 327) - report to the MCR and report temperatures as directed by the SRO.

8. MSIVs fail to close on Group 1 isolation signal

a. Event Trigger - Initial condition

b. Role play - none ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 17 of 18

ILT 15-1 NRC Exam Scenario 2 Rev. 1 Turnover

1. Day of week and shift

. Today day shift

2. Weather conditions

. Calm and clear.

3. Plant power level

. The plant is in Mode 1, operating at ~ 99% power.

a. RR Pumps A and B are operating in fast speed with FCVs at 87%/89%. 3436 MWt, 1130 MWe, 83.95 Mlbm/hr Core Flow.

b. Control rods - Step 30 / Gang 10B is at position 22.

4. Thermal Limit Problems/Power Evolutions

Power will be maintained at 99% throughout the shift.

5. LCOs in effect

None

6. Surveillances in progress

None

7. Status of Tagged Out Equipment

None

8. Previous Shift Evolutions completed

None

9. Evolutions planned for the shift

Shift GC Pumps IAW CPS 3110.01 Generator Stator Cooling (GC) section 8.2.4 Shifting GC Water Pumps.

10. Risk Levels

Green

Protected Equipment: FC B

11. Dose equivalent Iodine 131

reading 1.5 E-6 µcuries per gram ILT 15-1 NRC Exam Scenario 2 Rev 1.docx Page 18 of 18

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Exelon Nuclear ILT 15-1 NRC Exam Scenario Number:

NRC Exam Scenario 3 Revision Number: 1 Date: 10/25/16 Developed By: T. Jennings 9/22/16 Instructor Date Validated By: Michael Antonelli 10/28/16 SME or Instructor Date Reviewed By: Jim Lucas 11/15/16 Operations Representative Date Approved By: T. Jennings 11/15/16 Training Department Date ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 1 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 3 Operating Test No.: 2017-301 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

Mode 1 at ~10% power.

Weather conditions are calm and clear.

SF System is secured to support surveillance testing.

Turnover:

CPS 3002.01 Heatup and Pressurization is complete with the exception of placing a TDRFP in rolling standby (to be performed at 15% power).

CPS 3004.01 Turbine Startup and Generator Synchronization is in progress. Section 5.0 Prerequisites are complete. Steps 8.1.1 - 8.1.4 are complete. Step 8.1.5 will be performed after placing a TDRFP in rolling standby.

On Step 12. Gang 3C is at position 48.

Priorities for the shift are as follows:

o Perform CPS 9061.03C012 Week 12 - CM, SF, SM, LD ISOL Valve Operability Checklist sections 8.12.6 and 8.12.7 (Method B). Position indication testing is NOT required. Do NOT restart SF after the completion of 9061.03C012/D012.

o Continue with power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. The RE has requested single rod, single notch rod motion. After reaching 15 % power:

o Place TDRFP A in rolling standby IAW Step 8.6.3 of CPS 3002.01.

o Perform Turbine Roll IAW Step 8.1.8 of CPS 3004.01.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Perform 9061.03C012 Week 12 - SF Valve Operability Checklist 2 NA R-ATC Raise power with rods to 15%.

3 C-ATC ROD1233TFIA5 TS-SRO Uncoupled Rod 4 Rod4433TFIA4 C-ATC Control Rod difficult to withdraw 5 A05_A02_A0204_1_TVM; C-BOP RCIC failure to auto isolate on an isolation A05_A02_A09DS08_1 TS-SRO signal 6 SA01B1SA1CFO C-BOP #1 SA Compressor trips with failure of SA01B0SA1CFTC Standby Compressor to Auto Start 7 Seismic_Value 0.25g M-All Earthquake Multiple Annunciators Loss of Main Condenser vacuum YPXMALSE_239 YP_XMFTB_4963 ATWS 8 ed01LMalfMot(19) C-All CRD Pump B Trips During ATWS

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 2 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 Operating Test No.: 2017-301 Narrative Summary Event # Description

1. Perform 9061.03C012 Week 12 - SF Valve Operability Checklist The SRO directs BOP to perform CPS 9061.03C012 Week 12 - SF Valve Operability Checklist sections 8.12.6 and 8.12.7 (Method B).

2. Raise power with rods to 15%

The crew will continue the power ascension to 15% by withdrawing control rods in accordance with Step 8.1.6 of CPS 3004.01 Turbine Startup and Generator Synchronization.

3. Uncoupled rod When the first in-sequence control rod (12-33) reaches position 48, the ATC will perform a coupling check IAW CPS 3304.02 Rod Control And Information System (RC&IS) section 8.1.10 Coupling Check by applying a continuous withdraw to the rod at position 48. Annunciator 5006-5G Rod Overtravel will be received, indicating that the control rod has become uncoupled from its drive mechanism. The operating crew will attempt to recouple the control rod IAW the annunciator response procedure. The SRO will evaluate and enter ITS 3.1.3 Condition C until the control rod is successfully recoupled.

4. Control Rod difficult to withdraw Control Rod 44-33 will not withdraw when using normal drive differential pressure. The crew will perform actions for a difficult to withdraw control rod IAW CPS 3304.01 Control Rod Hydraulic & Control (RD)

Section 8.3.4 Control Rod Difficult to Withdraw. When drive dP is increased to 300 psid, the control rod withdrawal will be successful, allowing the power ascension to continue.

5. RCIC failure to auto isolate on an isolation signal Annunciator 5063-4A RCIC DIV 2 STEAM LINE DIFF PRESS HIGH is received. BOP will observe that 1E51-F063 and F076 have failed to automatically shut and will manually shut them and trip the RCIC turbine. SRO will enter Tech Spec LCO 3.5.3 RCIC System Action A.1 and A.2, and LCO 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation Action D.1.

6. #1 SA Compressor trips with failure of Standby Compressor to Auto Start Annunciator 5041-1A AUTO TRIP PUMP/MOTOR is received due to a trip of the #1 Service Air Compressor (1SA01C). The SRO will enter CPS 4004.01 Instrument Air Loss and direct the BOP to start the standby Service Air Compressor (0SA01C). If the crew fails to manually start 0SA01C, the air compressor will fail to automatically start to restore air pressure.

7. Earthquake/Loss of Main Condenser Vacuum/ ATWS Annunciators 5009-1A ACCL EXCDED SAFE SHUTDN EARTHQKE, 5009-2A ACCL EXCDED SEIS SW/OPER BAS EARTHQKE, 5009-2B ACCL EXCDED OPER BAS EARTHQKE and 5009-3A ACTIVATED SEIS RCDR are received. SRO enters CPS 4301.01 Earthquake. BOP observes status lights on the Seismic Warning Panel and determines that a Safe Shutdown Earthquake (SSE) has been exceeded. The earthquake causes a vacuum leak in the Main Condenser. The MCR will take actions for degrading vacuum IAW CPS 4004.02 Loss of Vacuum. Efforts to determine the location of the vacuum leak will be unsuccessful. When it is determined that vacuum cannot be controlled above 24 Hg vac, the SRO will direct the ATC to perform a Rapid Plant Shutdown or to scram the reactor. When the ATC places the Reactor Mode Switch in shutdown/attempts manual scram or ARI, control rods fail to insert.

The SRO will enter EOP-1 RPV Control and transition to EOP-1A ATWS RPV Control. The SRO will direct the BOP to start SLC and the ATC to insert control rods per EOP-1A.

8. CRD Pump B trips during ATWS CRD Pump B will trip 15 seconds after the Reactor Mode Switch is placed in Shutdown during Event 7, causing a loss of Control Rod Hydraulic (RD) Drive pressure and inability to insert control rods. The Crew will take actions to restore RD Drive pressure by starting the A RD Pump.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 3 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 EOP 1, 1A Critical tasks:

RPV-6.1 BOP/ATC starts Standby Liquid Control Pumps to shutdown the reactor within 120 seconds of RPV level reaching Level 2 (-45.5 Wide Range).

RPV-6.2 BOP Inhibits ADS within 105 seconds of RPV level reaching Level 1 (-145.5 Wide Range).

RPV-6.3 BOP terminates and prevents injection from HPCS before RPV level reaches Level 2 (-45.5 Wide Range).

RPV-6.4 ATC controls RPV level between TAF and -60 (PRA).

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 4 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Operator Actions Event No.(s): 1 Page 1 of 1

Description:

Perform 9061.03C012 Week 12 - SF Valve Operability Checklist (Method B).

Initiation: Following shift turnover and when directed by the Lead Examiner Cues: Directed by SRO Time Position Applicants Actions or Behavior General Note on Requirements for Expected Annunciator Response - OP-AA-103-102 If this evolution was pre-briefed and Expected Alarms were reviewed, the following expectations apply:

Expected alarms will be flagged

When the annunciator comes in the operator will announce Expected Alarm

The annunciator response procedure (ARP) need not be entered since it has already been reviewed in the pre-brief.

If a pre-brief was not conducted the operator should perform the following:

When an annunciator comes in the ARP should be referred to.

The annunciator may then be identified as an Expected Alarm, flagged, and from that point on the ARP need not be referred to.

Key Parameter Response: 1SF001, 1SF002, and 1SF004 valve position indication.

Expected Annunciators: 5041-7C NOT AVAILABLE SF SYSTEM DIVISION 1, 5041-7F NOT AVAILABLE SF SYSTEM DIVISION 2 Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

IAW CPS 9061.03C012 Week 12 - SF Valve Operability Checklist section 8.12.6:

Places SF SYS DIV 1 IN TEST switch to TEST.

Performs open and close testing of 1SF001 and 1SF004; records data on D001.

Places SF SYS DIV 1 IN TEST switch to NORMAL.

IAW CPS 9061.03C012 Week 12 - SF Valve Operability Checklist section 8.12.7:

Places SF SYS DIV 2 IN TEST switch to TEST.

Performs open and close testing of 1SF002; records data on D001.

Places SF SYS DIV 2 IN TEST switch to NORMAL.

SRO

Acknowledges reports from ATC/BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Terminus: CPS 9061.03C012 Week 12 - SF Valve Operability Checklist sections 8.12.6 and 8.12.7 complete.

NOTES:

Solid bullets are required actions o Hollow bullets are actions that may or may not be performed ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 5 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Operator Actions Event No.(s): 2, 3, 4 Page 1 of 2

Description:

Raise power with rods to 15% / Uncoupled Rod / Control Rod Difficult To Withdraw Initiation: Following Event 1 and upon direction of the SRO Cues: Annunciator 5006-5G Rod Overtravel, Control Rod 44-33 fails to move when withdraw signal is applied.

Time Position Applicants Actions or Behavior Key Parameter Response: Reactor power, Rod drive parameters (flow, dP), control rod position, Bypass Valve Position, rod uncoupled light on P680 OCM for control rod 12-33, Expected Annunciators: 5005-2K SRM Period, 5006-5G Rod Overtravel Automatic Actions: None

Monitors reactor to ensure operations remain within established bands.

ATC o Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

Reactivity Maneuver Per CPS 3004.01 Turbine Startup and Generator Synchronization, NF-CL-721-F-2 Control Rod Move Sheets and CPS 3304.02 RCIS:

Withdraws control rods (beginning with 12-33 from position 12) per the control rod sequence to raise power.

Monitors nuclear instruments during rod movement.

o Monitors the Power to Flow Map during power ascension.

Performs a Coupling Check for any control rod(s) withdrawn to position 48.

Uncoupled Rod Per CPS 3304.02 Rod Control And Information System, section 8.1.10 Coupling Check:

After 12-33 is withdrawn to position 48, applies a continuous withdraw signal to verify rod coupling.

Observes 5006-3G Rod Overtravel is received.

Observes red full-out light for 12-33 goes out.

Determines control rod 12-33 is uncoupled by pressing the ROD UNCOUPLED button on the P680 OCM.

Informs SRO that 12-33 is uncoupled and to refer to ITS 3.1.3.

Per CPS 3304.02 Rod Control And Information System, section 8.2.6:

Verifies that the INDIVID DRIVE light is energized on the OCM. If not, selects individual drive by depressing DRIVE MODE push-button.

Inserts the drive 1 or 2 notches in an attempt to recouple the rod.

Determines if the rod has recoupled by fully withdrawing the drive.

Performs the coupling check and determines that the rod is recoupled.

o Initiates an Issue Report and contacts the Reactor Engineer regarding the uncoupled rod event.

Control Rod Difficult To Withdraw

Determines control rod 44-33 will not withdraw with normal drive water differential pressure.

Informs SRO that 44-33 will not withdraw using normal drive water differential pressure.

Per CPS 3304.01, Control Rod Hydraulic & Control (RD), Section 8.3.4:

Increases Drive Water Diff Press in ~ 50 psid increments to a maximum of 500 psid by throttling closed on C11-F003, CRD Press Control Valve to achieve the desired differential pressure (if BOP attempts to perform, evaluator shall provide a cue to ATC to perform the drive differential pressure adjustment).

Attempts to withdraw rod 44-33 using normal notch withdrawal.

o Logs Drive Water Flow and Drive Water Diff Press.

o Returns Drive Water Diff Press to normal (235 - 265 psid) using C11-F003 (will probably be performed by BOP).

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 6 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

BOP o Monitors reactor to ensure operations remain within established bands.

Reactivity Maneuver o Monitors the Power to Flow Map during power ascension.

Uncoupled Rod o Initiates an Issue Report and contacts the Reactor Engineer regarding the uncoupled rod event.

Control Rod Difficult To Withdraw Evaluator NOTE - If BOP attempts to adjust drive water differential pressure, cue the BOP to allow ATC to perform the drive water differential pressure adjustment.

o Throttles C11-F003 to restore drive water differential pressure to normal (235 - 265 psid) after control rod is successfully withdrawn (may be performed by ATC).

o Logs Drive Water Flow and Drive Water Diff Press.

Acknowledges reports from ATC/BOP.

SRO

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

o Informs Shift Manager.

o Conducts a brief.

Reactivity Maneuver

Directs ATC to raise power to 15%.

Maintains oversight during control rod movement; positioned in proximity to the ATC (typically from the SRO desk).

Uncoupled Rod

Verifies / directs ATC to attempt to recouple rod 12-33.

Enters ITS 3.1.3 Action C.1 and C.2 to fully insert control rod 12-33 within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and disarm 12-33 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Exits ITS 3.1.3 Action C.1 and C.2 when 12-33 is successfully recoupled.

Control Rod Difficult To Withdraw

Verifies / directs ATC to perform CPS 3304.01 Control Rod Hydraulic and Control (RD) section 8.3.4 Control Rod Difficult To Withdraw.

o Directs continuing startup.

Terminus: Clearly observable plant response from change in power level, control rod 12-33 recoupled and returned to position 48, successful withdrawal of control rod 28-33, and rod drive dP restored to normal (235 - 265 psid).

NOTES:

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 7 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Operator Actions Event No.(s): 5 Page 1 of 1

Description:

RCIC failure to auto isolate on an isolation signal Initiation: Following Event 4 and upon direction of the Lead Examiner, insert REMOTE 1.

Cues: Annunciator 5063-4A RCIC Div 2 Steam Line Diff Press High alarm Time Position Applicants Actions or Behavior Key Parameter Response: Annunciator 5063-4A RCIC Div 2 Steam Line Diff Press High alarm Expected Annunciators: 5063-4A RCIC Div 2 Steam Line Diff Press High alarm Automatic Actions: None (automatic isolation fails)

ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels, notifies SRO of unusual/unexpected conditions.

o Makes plant announcement.

BOP

Monitors control room panels, notifies the SRO of unusual/unexpected conditions.

o Monitors reactor to ensure operations remain within established bands. Reports issue to SRO.

Refers to ARP.

Per 5063-4A RCIC Div 2 Steam Line Diff Press High alarm:

o Determines that a Group 5 isolation has not occurred.

Manually initiates a Group 5 isolation by:

Closing 1E51-F063, RHR & RCIC Stm Supp Inbd Isol Valve.

o Verifying closed 1E51-F076, RHR & RCIC Stm Supp Warm Up Isol Valve.

Tripping the RCIC turbine.

SRO

Acknowledges report from BOP.

Directs actions listed above.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Directs performing a Group 5 isolation.

Reviews and enters ITS 3.5.3 A.1 and A.2 (after the RCIC steam supply line is isolated),

and 3.3.6.1 D.1.

o Informs Shift Manager.

o Contacts maintenance to investigate.

o Conducts a brief.

Terminus: Technical Specification review complete.

NOTES:

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 8 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Operator Actions Event No.(s): 6 Page 1 of 2

Description:

Service Air Compressor (SAC) trip / failure of the standby SAC to auto start Initiation: Following Event 5 and upon direction of the Lead Examiner, insert REMOTE 2.

Cues: Annunciator 5041-1A, Auto Trip Pump/Motor Time Position Applicants Actions or Behavior Key Parameter Response: SA header pressure decreases, 1SA01C amber trip light energized Expected Annunciators: 5041-1A Auto Trip Pump/Motor Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

o Dispatches Equipment Operator to investigate.

Per CPS 4004.01 Instrument Air Loss:

o IF air pressure lowers to 60 psig and cannot be restored, or SDV level increases resulting in a rod block, or any control rod begins to drift, THEN turn mode switch to SHUTDOWN.

BOP

Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

Determines that 1SA01C has tripped.

Reports issue to SRO.

Refers to the ARP for 5041-1A.

Per 5041-1A AUTO TRIP SERVICE AIR COMPRESSOR and CPS 4004.01 Instrument Air Loss:

Starts standby Service Air Compressor (0SA01C) (fails to Auto Start).

Monitors SA Header Pressure.

o Dispatches Equipment Operator to investigate cause of trip.

SRO

Acknowledges report from BOP.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards, and approved procedures.

Enters and executes CPS 4004.01 Instrument Air Loss.

Directs actions listed above.

o Informs Shift Manager.

o Contacts Maintenance to investigate.

o Conducts a brief.

Terminus: 0SA01C running and maintaining SA header pressure.

NOTES:

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 9 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Operator Actions Event No.(s): 7, 8 Page 1 of 3

Description:

Earthquake / Loss of Main Condenser vacuum / ATWS / CRD Pump B Trips During ATWS Initiation: Following Event 6 and upon direction of the Lead Examiner, insert REMOTE 3.

Cues: Multiple annunciators on 1H13-P601 and P870 Time Position Applicants Actions or Behavior Key Parameter Response: Lowering (degrading) Main Condenser Vacuum Expected Annunciators: 5009-1A ACCL EXCDED SAFE SHUTDN EARTHQKE, 5009-2A ACCL EXCDED SEIS SW/OPER BAS EARTHQKE, 5009-2B ACCL EXCDED OPER BAS EARTHQKE and 5009-3A ACTIVATED SEIS RCDR Automatic Actions: None ATC

Monitors reactor to ensure operations remain within established bands.

o Monitors control room panels and notifies the SRO of any unusual or unexpected conditions.

Reports receipt of annunciators 5009-1A, 2A, 2B, and 3A to the SRO.

o Recognizes lowering Main Condenser Vacuum and notifies SRO.

Per CPS 4301.01 Earthquake, checks the following parameters:

Reactor power, RPV pressure, RPV level

Feed flow, Steam flow

Generator load, Turbine vibration o Electrical distribution system integrity o Off-Gas, Area Radiation & Process Radiation Monitors o Leak detection systems o Balance of plant annunciators

Reactor Feed Pump vibrations

Reactor Recirculation Pump vibrations o Tank levels (MC, CY, DG Fuel Oil, etc.)

Trip and isolation logic status Per 5007-2B/2D Low Vacuum LP Turb 1A/1B Exh Hood:

o Monitors condenser vacuum.

Scrams the reactor when directed by the SRO.

Carries out ATWS Scram Choreography by reporting the following:

Mode Switch in shutdown, power is

Shutdown Criteria is not met

Reactor Power is and trend

Reactor Pressure is and trend

Reactor Level is and trend

Manual Scram and ARI have been initiated

Any EOPs with entry conditions (EOP-1 on power)

Arms and Depresses manual scram pushbuttons.

Initiates ARI.

[CT] * [CT] Controls level between TAF (-160) and -60.

o Reports critical parameters as required.

o Coordinates with BOP to monitor and control RPV level and pressure.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 10 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 BOP

Monitors control room panels and notifies the SRO of unusual or unexpected conditions.

o Monitors reactor to ensure operations remain within established bands.

o Recognizes lowering Main Condenser Vacuum and notifies SRO.

o Performs a Manual Group 1 Isolation when directed by the SRO.

Per CPS 5009-1A, 2A, 2B and 3A and CPS 4301.01 Earthquake:

Verifies at Seismic Warning Panel 1H13-P865 (NOTE: This panel is only simulated at the simulator V-Panel in the back corner of the simulator):

SAFE SHUTDOWN EARTHQUAKE red light ON.

1VS-EM014 Contmnt 7120 red light ON.

Operating Basis Equake red light ON.

Seismic System Triggered red light ON.

Determines that SSE level earthquake has been exceeded.

Per CPS 4301.01 Earthquake, checks the following parameters:

Electrical distribution system integrity

Off-Gas, Area Radiation & Process Radiation Monitors

Leak detection systems

Balance of plant annunciators o RPV pressure, RPV level, Steam flow o Generator load, Turbine vibration o Reactor Recirculation Pump vibrations

Tank levels (MC, CY, DG Fuel Oil, etc.)

o Trip and isolation logic status

Directs Equipment Operators to perform visual inspection of plant equipment for damage.

Performs ATWS scram choreography actions.

Announces:

Reactor Scram with Failure to Scram

Motor Driven Reactor Feed Pump may start

Evacuate the RCIC room

Evacuate the Containment

Determines rod status and reports Shutdown Criteria is not met to SRO.

Starts Control Rod Drive Pump A.

[CT] * [CT] Inhibits ADS when directed by SRO.

[CT] * [CT] Starts SLC pumps when directed by SRO.

[CT] * [CT] Terminates and prevents injection of HPCS when directed by SRO.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 11 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1

Acknowledges reports from ATC/BOP.

SRO

Determines that a valid seismic event has occurred.

Directs performance of plant and MCR Panel walkdowns.

Enters and executes CPS 4301.01 Earthquake.

Enters and executes CPS 4004.02 Loss of Vacuum.

o Notifies Engineering Duty Director / Manager that a seismic event has occurred and to perform CPS 1337.05 Seismic Response and Reporting.

o Notifies Illinois Department of Natural Resources of the seismic event.

o Notifies Shift Manager of the event.

o Directs performance of CPS 1850.00 Post-Earthquake CPS Organizational Response to verify integrity of buildings systems and components.

o Directs CMO to perform thermography on switchyard components and transformers, including bushings.

o Makes preparations for performing an orderly plant shutdown.

o Enters ORM 2.2.7 Seismic Monitoring Instrumentation Action 3.2.7.a, with one or more of the above seismic monitoring instruments inoperable for more than 30 days, initiate a Condition Report.

Per CPS 4004.02 Loss of Vacuum:

When it is determined that Main Condenser Vacuum cannot be controlled above 24 Hg vacuum, directs ATC to place the Reactor Mode Switch in SHUTDOWN.

o Directs a manual Group 1 Isolation to be performed.

Enters CPS 4100.01 Reactor Scram

Carries out ATWS Scram Choreography by performing an Update:

Entering EOP-1, transitioning to EOP-1A.

Entering the Scram Off-Normal.

End of Update.

Enters EOP-1A, ATWS RPV Control and directs:

Inhibiting ADS.

Initiating ARI.

[CT] Terminate and Prevent injection of HPCS before RPV level reaches Level 2 (-

[CT]

45.5).

[CT] Initiation of SLC per CPS 4411.10 within 120 seconds of RPV level reaching Level

[CT]

2 (-45.5).

Stabilization of RPV Pressure 800 to 1065 psig with Bypass Valves and SRVs.

o Informs the Shift Manager.

o Conducts a brief.

Ensures operations are conducted within the bounds of Tech Specs and IAW Operations expectations, standards and approved procedures.

Terminus: The scenario can be terminated when control rods are being inserted and RPV water level is being maintained in accordance with EOP-1A.

NOTES:

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 12 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Simulator Operator Instructions Initial Setup

1. Fill out plant status and have Turnover Sheet ready for the crew.

2. Verify daily lamp test completed.

3. Reset to IC-223 (PW 76319) @ 10% Power. If this is the first reset after swapping simulator loads, reset the IC twice.

4. Load the lesson plan for this scenario.

5. Verify the following commands are active:

YP_XMFTB_4963 Auto & Manual Scram Failure

ROD4433TFIA4 Rod 44-33 Is Stuck At Present Location

ROD1233TFIA5 Rod 12-33 Rod Uncoupled

6. Place simulator in RUN.

7. Turn on and advance recorders.

8. Verify RCIC Flow Controller is set at 620 gpm.

9. Verify the AR/PR server is running and stabilize AR/PR.

10. Verify Rod Drive pressure is in the expected range of 235-265 psid.

11. Provide pull sheets: On step 12. Gang 3C is at position 48.

12. Make sure Sequence A is selected.

13. Make sure Individual Drive Mode is selected on the OCM.

14. Remove EST Tags from the following control switches:

1H13-P877-5014 - MC Pump B

1H13-P877-5016 - 1TD004A RFPT 1A HP Stop Vlv Before SDV

1H13-P877-5019 - 1B21-BSFV-1 Aux Stm to MSR 1B Inlet Vlv

1H13-P877-5019 - 1GS02CB SPE Blower 1B2

1H13-P800-5042 - 0VQ03CC DW Prg Low Flow Exh Fan

1H13-P801-5050 - 1VY03C RHR Hx Rm A Sply Fan

1H13-P801-5050 - 1VY04C RCIC Pmp Rm Sply Fan

1H13-P801-5050 - 0VC69Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P801-5052 - 0VC70Y Locker Rm Exh Fan 11C Isol Dmpr

1H13-P601-5064 - 1SX011A Div 1 Cross Tie Valve

1H13-P601-5065 - 1SX011B Div 2 Cross Tie Valve

1H13-P601-5067 - 1B21-F067B MSL B Outbd MSIV Before Seat Drain Vlv

15. Procedures that are expected to be used during this scenario are:

CPS 3004.01 Heatup and Presurization

CPS 9061.03C012/D012 Week 12 - CM, SF SM, LD ISOL Valve Operability

CPS 3304.02 Rod Control and Information System (RC&IS)

ITS 3.1.3 Control Rod OPERABILITY

CPS 3304.01 Control Rod Hydraulic & Control (RD)

CPS 4001.02 Automatic Isolation

ITS 3.5.3 RCIC System

ITS 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation

CPS 4004.01 Instrument Air Loss

CPS 4301.01 Earthquake

CPS 4004.02 Loss of Vacuum

EOP-1 RPV Control

EOP-1A ATWS RPV Control

16. Hang OOS tags on: None

17. Identify T/S issues associated with OOS and turnover: None ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 13 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1

18. Operating Equipment:

Verify 1SA01C is running

Verify Suppression Pool Cleanup (SF) is shutdown (pumps secured, SF001/2/4 SHUT)

19. Marked up copies: None

20. Verify simulator conditions match the turnover.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 14 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Event Triggers and Role Play Event #

1. Perform 9061.03C012 Week 12 - SF Valve Operability Checklist

a. Event Trigger - Following shift turnover.

b. Role play - none

2. Raise power with rods to 15%.

a. Event Trigger - Following Event 1 and when directed by the SRO.

b. Role play (1) Booth Operator - (when RE and/or Rod Verifier requested) - report to the MCR as the RE and/or Rod Verifier.

3. Uncoupled Rod

a. Event Trigger - When Rod12-33 is withdrawn to position 48.

b. Role play (1) Booth Operator - When control rod 12-33 is inserted from position 48, verify Delete ROD1233TFIA5 is inserted (Delete Rod 12-33 Malfunction).

4. Control Rod Difficult To Withdraw

a. Event Trigger - Following Event 3 when withdrawal of rod 44-33 is attempted:

(1) Verify ROD4433TFIA4 is inserted (Rod 44-33 Is Stuck At Present Location).

b. Role play (1) System Engineer (if asked about the performance / maintenance history of control rod 44-33) - The seals for rod 44-33 were NOT replaced during the last outage. There are no previous problems noted in the history file for 44-33.

5. RCIC failure to auto isolate on an isolation signal

a. Event Trigger - When directed by the Lead Examiner, Activate Remote 1 and verify the following command(s):

(1) A05_A02_A0204_1_TVM (2) A05_A02_A09DS08_1 On

b. Role play:

(1) Maintenance (if asked to investigate Div 2 Steam Line Diff Press High alarm malfunction) - Well send a technician to the control room to gather information for the troubleshooting plan.

(2) If RCIC Flow ATMs are checked:

ATM Value Trip Status 1E31-N690B 100% (300 H2O) (upscale) Tripped 1E31-N683B 100% (300 H2O) (upscale) Tripped 1E31-N690A 50% (0 H2O) Not tripped 1E31-N683A 50% (0 H2O) Not tripped 1E31-N691B 50% (0 H2O) Not tripped 1E31-N684B 50% (0 H2O) Not tripped 1E31-N691A 50% (0 H2O) Not tripped 1E31-N684A 50% (0 H2O) Not tripped ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 15 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1

6. #1 SA Compressor trips with failure of Standby Compressor to Auto Start

a. Event Trigger - Following Event 5 and when directed by the Lead Examiner, Activate Remote 2 and verify the following command(s):

(1) SA01B1SA1CFO (2) SA01B0SA1CFTC

b. Role play (If requested):

(1) Maintenance (investigate loss of service air pressure or failure of compressor to start) - Report, I will brief and dispatch personnel to investigate.

(2) EO (investigate trip of 1SA01C) - Report, The breaker for 1SA01C is tripped on overcurrent. There are no abnormalities locally. 0SA01C is operating normally.

(3) EO (if directed to support shifting standby Service Air Compressors - acknowledge the order and report, Im on my way up to get a brief.

7. Earthquake / Loss of Main Condenser vacuum / ATWS

a. Event Trigger - Following Event 6 and when directed by the Lead Examiner, Activate Remote 3 and verify the following command(s):

(1) SEISMIC_VALUE 0.25g (2) A04_ A08_02_1_TVM (3) A04_ A05_01_4_TVM (4) A04_ A05_01_3_TVM

b. Role play (1) Security (if asked if ground motion felt): Ive had several security officers report that ground motion was felt.

(2) EO (when directed to investigate loss of condenser vacuum): I will verify Travelling Screens/Screenwash operating properly and verify the Vacuum Breaker Loop Seal is filled.

(3) EO (if asked to check RFP Seal Tank Level) - 1LIC-TD040 is in auto; level is in the green band controlling at 10.

(4) EO (if asked to make preparations to startup a Condenser Vacuum Pump): Im on my way to the WEC office for a brief.

(5) Booth operator (when asked to defeat ATWS interlocks per 4410.00C012 Defeating ATWS Interlocks) - defeat the following isolations (using the ATWS actions in the simulator lesson plan) in the order provided by the ATC:

a) Defeat IA Isolations b) Defeating RPS Logic Trips c) Defeating Rod Pattern Controller d) Defeating ARI Logic Trips (6) Maintenance (after 2 minutes from scram announcement) - report to the MCR as IMD.

8. CRD Pump B Trips During ATWS

a. Event Trigger - Triggered when RMS is placed in shutdown during event 7.

b. Role play (1) EO (when directed to open 1C11-F116, Suct Filt Bypass and 1C11-F117, Suct Filt Bypass for 4411.08):

1C11-F116 and 1C11-F117 are open.)

(2) EO (when directed to shut/verify shut 1C11-F014A, Pump A Stop Chk Discharge Valve for 4411.08): Insert YP_XREMT_697 Normal and report, 1C11-F014A is shut.

(3) EO (when directed to open 1C11-F014A, Pump A Stop Chk Discharge Valve for 4411.08): Insert YP_XREMT_697 Open and report, 1C11-F014A is open.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 16 of 17

ILT 15-1 NRC Exam Scenario 3 Rev. 1 Turnover

1. Day of week and shift

Today day shift

2. Weather conditions

Calm and clear.

3. Plant power level

The plant is in Mode 1, operating at ~ 10% power.

RR Pumps A and B are operating in slow speed with FCVs at 90%/90%. 346 MWt, 0 MWe, 27.3 Mlbm/hr Core Flow.

CPS 3002.01 Heatup and Pressurization is complete with the exception of placing a TDRFP in rolling standby (to be performed at 15% power).

CPS 3004.01 Turbine Startup and Generator Synchronization is in progress. Section 5.0 Prerequisites are complete. Steps 8.1.1 - 8.1.5 are complete.

Control rods - On Step 12. Gang 3C is at position 48.

MDRFP is on the MLC in automatic.

4. Thermal Limit Problems/Power Evolutions

Continue with power ascension to 15% IAW Step 8.1.6 of CPS 3004.01. The RE has requested single rod, single notch rod motion. After reaching 15% power:

Place TDRFP A in rolling standby IAW Step 8.6.3 of CPS 3002.01.

Perform Turbine Roll IAW Step 8.1.8 of CPS 3004.01.

5. LCOs in effect

None

6. Surveillances in progress

CPS 9061.03C012/D012 - Week 12 - SF Valve Operability Checklist

7. Status of Tagged Out Equipment

None

8. Previous Shift Evolutions completed

SF System was secured to support performance of CPS 9061.03C012/D012.

9. Evolutions planned for the shift

Priority 1 - Perform CPS 9061.03C012 Week 12 - CM, SF, SM, LD ISOL Valve Operability Checklist sections 8.12.6 and 8.12.7 (Method B). Position indication testing is NOT required. Do NOT restart SF after the completion of 9061.03C012/D012.

Priority 2 - Continue with power ascension to 15% IAW Step 8.1.6 CPS 3004.01.

10. Risk Levels

Green

Protected Equipment: FC B

11. Dose equivalent Iodine 131

Reading 1.5 E-6 µcuries per gram.

ILT 15-1 NRC Exam Scenario 3 Rev 1.docx Page 17 of 17

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