Text

Initial Submittal of the Scenarios for the Clinton Initial Examination - July 2005
	ML052560368
Person / Time
Site:	Clinton
Issue date:	07/18/2005
From:	Charles Phillips; NRC/RGN-III/DRS/OLB
To:	;
References
	50-461/05-301, ES-D-1 50-461/05-301
	Download: ML052560368 (75)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 1 Operating Test No.: ILT0401-1 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

7% power, normal plant startup is in progress.

Thunderstorm watch is in effect.

Service Air Compressor 1SA01C is OOS for Motor Bearing Replacement.

Turnover:

Continue Power increase to 9% power.

Start RCIC for surveillance 9054.01, and then place mode switch in RUN.

RHR B is in Suppression Pool Cooling to support RCIC surveillance.

Event Malf. No. Event Type* Event No. Description 1 N/A R-ATC/SRO Raise reactor power with rods to 9%.

2 Override C-ATC/SRO Difficult to Withdraw Control Rod 3 N/A N-BOP Start RCIC for Surveillance.

TS-SRO 4 Override I-BOP RCIC Auto Controller fails with low demand.

5 N/A TS-SRO Containment Upper Airlock Outer Door Failure 6 CW06A C-BOP/SRO Auto Trip of B CCW Pump 7 Override I-ATC/SRO Condenser Hotwell Overflow Controller Failure 8 ED04A M-ALL Loss of Power to 4160 V Bus 1A 9 RR03 M-ALL Recirc Loop Rupture 10 HP04 C-BOP/SRO HPCS Injection Valve fails to open, may be manually opened

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 9/13/2005

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 1 Operating Test No.: ILT0401-1 Narrative Summary Event # Description

1. Power will be increased to 9% using rods.

2. While power is being increased rod 32-25 will experience difficulty in being withdrawn requiring the ATC Operator to increase drive water pressure to free the rod.

3. RCIC will be started by the BOP operator for surveillance 9054.01.

4. At the completion of RCIC startup the BOP operator will respond to failure of the RCIC flow controller. This will require evaluation of Technical Specifications LCO 3.5.3, Action A.1 & A.2 which requires within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verifying HPCS is operable and restoring RCIC to operable status within 14 days.

5. A security guard will report that upon exiting the containment upper airlock door he could not get the outer door to shut. The will require the SRO to evaluate Technical Specification 3.6.1.2.a and declare the upper containment airlock Inoperable.

6. A trip of the B Component Cooling Water (CCW) Pump will force the BOP operator to start the standby pump. This sets the stage for a loss of power to trip the other 2 pumps later in the scenario.

7. Condenser Hotwell Overflow Controller failure will require the ATC Operator to take manual control and close the Overflow Valve.

8. A loss of power to 4.16kv bus 1A will cause the remaining CCW Pumps to trip.

This will require the ATC Operator to trip the B Reactor Recirc Pump within 1 minute. The perturbation on the system will cause a Recirc piping rupture.

9. The Recirc Loop Rupture will cause the crew to respond to the LOCA that causes a Scram and RPV Level to decrease. RPV pressure reduction and maximum injection will be required to keep RPV level above TAF.

10. The crew will also need to respond to the failure to open of the HPCS injection valve (1E22-F004). An operator may be dispatched to manually open 1E22-F004.

EOP 1, 6 Critical tasks:

Scram upon the trip of both Reactor Recirc Pumps.

Enters EOP-3, Blowdown, and then maximizes injection to recover level above TAF.

Page 2 of 2 9/13/2005

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Pull rods to raise power (Panel P680, Center Section)

Initiation: Following Turnover Cues: Directed by SRO General Note If this evolution was Prebriefed and Expected Alarms were reviewed, the following may be allowed:

The Expected Alarms will be flagged in some manner.

When the annunciator comes in the operator will announce Expected Alarm

The Annunciator Response Procedure (ARP) need not be entered because it has already been reviewed in the Prebrief.

If a Prebrief 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. (OP-AA-103-102)

Time Position Applicants Actions or Behavior ATC Per, CPS 3002.01, Heatup and Pressurization and NF-CL-721-1002, Control Rod Move Sheets:

Pull rods to raise power to 9%, (step 21 rod 32-33 @ 8)

Performs Rod Coupling checks as rods are positioned to 48.

BOP

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

Positions himself in proximity to the reactor operator, typically the location from which EOP actions are directed. (OP-AA-300).

Directs actions listed above.

Enforces OPS expectations and standards

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

If not discussed in the Prebrief, SRO should discuss REMA Critical Parameters.

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

Page 1 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Difficult to Withdraw Control Rod (Panel P680, Center Section)

Initiation: During withdrawal of rod.

Cues: Control Rod 04-25 does not withdraw.

Time Position Applicants Actions or Behavior ATC

Determine control rod 04-25 will not withdraw

Informs SRO of a difficult to withdraw rod Upon discovery of the difficult to withdraw rod the operator has the following options, all of which add flexibility and are allowed per the procedures:

The operator may be in individual rod mode or gang mode and be notching the rods out or using continuous rod withdraw.

If in gang mode the operator may move the other rods out to 48 before investigating the problem with 04-25.

If in gang mode the operator may stop moving the other rods and correct 04-25 before moving all the rods in the gang to 48.

Note: A sheet from the CR Database is available to present to operator when the operator needs to determine if rod 04-25 has new seals.

Per CPS 3304.01, Control Rod Hydraulic & Contol, Section 8.3.3.3:

Conducts brief on performance of procedure.

Increase Drive Water Diff Press in 50 psid increments to a maximum of 500 psid.

(BOP Operator may perform this action)

Discuss with the CRS how many times to try to move the rod at each pressure.

Throttle C11-F003, CRD Press Control Valve to achieve the desired pressure.

At each 50 psid increment perform the following:

a) While monitoring Drive Water Flow and Drive Water Diff Press, Attempt to withdraw rod using normal notch withdrawal.

b) IF control rod moved; THEN record Drive Water Flow and Drive Water Diff Press in the CPS MCR Autolog.

THEN return Drive Water Diff Press to normal.

BOP

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

Increase Drive Water Diff Press in 50 psid increments to a maximum of 500 psid.

Record Drive Water Flow and Drive Water Diff Press in the CPS MCR Autolog.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Discusses with the ATC Operator how many times to try to move the rod at each pressure.

Conducts brief on performance of procedure.

Contacts Reactor Engineer Terminus: Control Rod has been withdrawn.

Page 2 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 3 Page 1 of 2

==

Description:==

Start RCIC for Surveillance (Panel P601, Section 5063)

Initiation: After Control Rod problem is resolved, and upon direction from Lead Examiner.

Cues: Upon direction of the SRO General Note If this evolution was Prebriefed and Expected Alarms were reviewed, the following may be allowed:

The Expected Alarms will be flagged in some manner.

When the annunciator comes in the operator will announce Expected Alarm

The Annunciator Response Procedure (ARP) need not be entered because it has already been reviewed in the Prebrief.

If a Prebrief 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. (OP-AA-103-102)

Time Position Applicants Actions or Behavior BOP Makes Plant Announcement on start of RCIC.

Enters Short Duration Time Clock when Test Prep Switches are placed in test.

Per CPS 9054.01C002, Steps 8.4.2 through 8.4.12 places RCIC in Operation:

Verifies RCIC Pump Flow Controller, 1E51-R600, set at 620 gpm, and in AUTO.

Places RCIC Div 1 MOV TEST PREP switch in TEST.

Places RCIC DIV 1 OUT OF SERVICE switch in INOP

Drain the RCIC Exhaust Drain Pot.

Start the Gland Seal Air Compressor.

Open 1E51-F046, RCIC Pump Supp To Turb Lube Oil Clr.

Open 1E51-F059, RCIC Pmp Second Test Valve To Stor Tank..

Start CPS 9000.05, Suppression Pool Temperature Log. (In Progress)

Open 1E51-F045, RCIC Turb Stm Supp Shutoff Valve, to start the RCIC turbine, and time the opening of the valve.

Fully open 1E51-F022, RCIC Pmp First Test Valve To Stor Tank.

Verify steam drain pot drain valves automatically close.

Take 1E51-F019, RCIC Pmp Min Flow Recirc To Suppr Pool, switch to OPEN and verify that it cycles OPEN and then CLOSED (RCIC Flow Controller failure will be triggered off of 1E51-F019 opening.)

Verify RCIC Pmp Rm Sply Fan is running.

ATC

Monitors reactor to ensure operations remain within established bands

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

Page 3 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 3 Page 2 of 2

==

Description:==

Start RCIC for Surveillance (Panel P601, Section 5063)

Time Position Applicants Actions or Behavior SRO o Directs actions listed above.

When 1E51-F022 is opened, declares RCIC Inoperable (but still available) per Technical Specification LCO 3.5.3. Addressed in CPS 9054.01, Limitation 6.5.

Enforces OPS expectations and standards

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

Contacts Shift Manager and recommends notifications.

Terminus: RCIC has been started and Technical Specification actions have been identified Page 4 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

RCIC Auto Controller Fails With Low Demand (Panel P601, Section 5063)

Initiation: After RCIC is started, and upon direction from the Lead Examiner.

Cues: Flow Controller fails downscale.

Time Position Applicants Actions or Behavior BOP Observes RCIC flow lower than normal and demand failed.

Notifies SRO of RCIC Flow Controller Problem Should take one of the following actions:

Immediately trips the RCIC Turbine.

Takes manual control of of the flow controller and raises flow/speed.

Depending on what actions have already been taken discusses with SRO to leave RCIC running or, securing RCIC per CPS 9054.01 or 3310.01:

1. Shut 1E51-F022, RCIC Pmp First Test Valve To Stor Tank.

2. Trip RCIC Turbine from 1H13-P601 by depressing the RCIC TURBINE REMOTE TRIP push-button.

3. Shut 1E51-F059, RCIC Pmp Second Test Valve To Stor Tank.

4. Shut 1E51-F045, RCIC Turb Stm Supp Shutoff Valve.

5. After 1E51-F045 closes, verify the following valves open automatically:

1E51-F004, RCIC Turb Exh Drn To RF First Isol Vlv.

1E51-F025, RHR & RCIC Stm Supp First Drn Isol Valve

1E51-F026, RHR & RCIC Stm Supp Second Drn Isol Valve.

6. Verify the following valves shut:

1E51-F013, RCIC Pump Disch To Rx Outbd Isol Valve.

1E51-F019, RCIC Pmp Min Flow Recirc To Suppr Pool.

7. Reset RCIC Turbine Trip & Throttle Valve as follows:

Place 1E51-C002, RCIC Turbine Trip Vlv Opr Switch to CLOSE to reset RCIC Turbine Trip & Throttle Valve.

Open 1E51-C002, RCIC Turbine Trip Vlv Opr (Stem).

8. Stop the Gland Seal Compressor.

9. Shut 1E51-F046, RCIC Pmp Supp To Turb Lube Oil Clr.

Verify RCIC Pump Flow Cont, 1E51-R600 set to 620 gpm/AUTO.

ATC

Monitors reactor to ensure operations remain within established bands

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

Makes Plant Announcement on RCIC condition.

SRO

Directs actions to place RCIC in a stable condition, this may be leaving RCIC running while troubleshooting or securing RCIC.

Enforces OPS expectations and standards Conducts brief on RCIC problem and status.

Terminus: RCIC placed in stable condition.

Page 5 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 5 Page 1 of 1 Description Containment Upper Air Lock Outer Door Failure (Technical Specification Call, No Control Room Action)

Initiation: Following startup of RCIC, and upon direction from the Lead Examiner.

Cues: Report from Security Time Position Applicants Actions or Behavior BOP

Monitors reactor to ensure operations remain within established bands

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

Directs Area Operator to verify the Inner Airlock Door is shut and chain it shut.

Performs Plant Announcement on Inoperability of Upper Airlock Door.

ATC

Monitors reactor to ensure operations remain within established bands

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

Performs Plant Announcement on Inoperability of Upper Airlock Door.

SRO

Receives report from security on the problem with the Containment Upper Airlock Door.

Declares per Technical Specification LCO 3.6.1.2, that the airlock is inoperable and IAW Action A.1, Operable door of the airlock must be verified closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Action A.2, Operable door must be locked closed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and Action A.3, Verify the Operable door is locked closed every 31 days.

Directs a Plant Announcement about restricting access through Upper Airlock.

Contacts Mechanical Maintenance to repair door.

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

Directs that an Area Operator be sent to verify the Inner Airlock Door is shut and chain it shut.

Performs brief on problem and plant status.

Terminus: Technical Specification review complete.

Page 6 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 6 Page 1 of 1

==

Description:==

Auto Trip of B Component Cooling Water (CCW) Pump (Panel P800, Section 5040)

Initiation: Following Technical Specification call, and upon direction of Lead Examiner Cues: Annunciator 5040-1B, Auto Trip Pump/Motor, is received.

Annunciators 5003-3D & 3K, Recirc Mtr A & B Wdg Clg Wtr Flow Lo, is received.

Time Position Applicants Actions or Behavior BOP

Communicates Annunciator 5040-1B

References ARP Per CPS 5040-1B, Auto Trip Component Cooling Water Pump:

IF Only one CCW pump is running,

THEN a) Start the A CCW Pump, 1CC01PA, or b) 1) Shutdown the running FC Pump per CPS 3317.01.

2) Shut 1CC076A & 76B, FC Heat Exchanger Outlet Valves.

Makes Plant Announcement on starting Standby CCW Pump.

Dispatches Area Operator to the pump and breaker.

ATC

Communicates Annunciator 5003-3D & 3K

References ARP

Monitors Reactor Recirc Pumps for elevated temperatures.

Monitors reactor to ensure operations remain within established bands

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

SRO Directs startup of standby pump

Enforces OPS expectations and standards

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

Performs brief on problem and status.

Terminus: A Component Cooling Water Pump has been started.

Page 7 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

Condenser Hotwell Overflow Controller Failure (Panel P680, Section 5001)

Initiation: Following start of A CCW Pump, and upon direction from the Lead Examiner.

Cues: Hotwell Level is increasing, or annunciator 5014-4B, Not Fully Closed Cdsr Emerg O/Flow Vlv 1CD020, is received.

Time Position Applicants Actions or Behavior ATC

Reports problem with Condenser Hotwell Overflow Controller.

Upon identification of problem, may take manual control of controller first and then follow up with Operating Procedure (OP), or may follow through ARP to OP.

Per CPS 3104.01, Condensate/Condensate Booster, Section 8.6.1:

Monitor Hotwell level and conductivity.

Manually control Hotwell level as necessary per 8.3.2

1. Place Condenser Overflow Controller 1LC-CD057A in MANUAL,

2. Control Hotwell level as necessary for plant conditions.

Communicates equipment status to SRO.

BOP Communicates annunciator 5014-4B References ARP, and ensures that the ATC Operator is taking actions per CPS 3104.01, Condensate/Condensate Booster (CD/CB).

SRO

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

Enforces OPS expectations and standards.

Terminus: Hotwell level has been restored to normal band (36-40 inches)

Page 8 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 8 Page 1 of 2

==

Description:==

Loss of Power to 4160 V Bus 1A Initiation: After Hotwell has returned to normal level, and upon direction from the Lead Examiner.

Cues: Loss of power to several major components including A RR Pump, and both running CCW Pumps.

Time Position Applicants Actions or Behavior ATC

Receives report that NO CCW Pumps are running.

Per CPS 5040-1B, Auto Trip Component Cooling Water Pump Critical Task

Initiates a Scram

Carries out Scram Choreography by reporting

1) Mode Switch in Shutdown, Power is

2) Rod status is

3) Reactor Power is and trend

4) Reactor pressure is and trend

5) Reactor level is and trend

6) Any EOPs with entry conditions (EOP-1, 6)

Per CPS 4100.01, Reactor Scram

Turn Mode Switch to SHUTDOWN

1) Verify reactor power is lowering

2) Verify SHUTDOWN CRITERIA met

IF RPV level is rising with 2 feed pumps operating

THEN Secure 1 Feed Pump and control RPV water level Level 3 to Level 8.

Verify Turbine and Generator trip when required

Evacuate the containment.

Per CPS 4008.01, Abnormal Reactor Coolant Flow

Shuts the A RR Pump Discharge Valve, 1B33-F067A

Within 1 minute trips B RR Pump Time RR Pump Tripped: ________

Shuts the B RR Pump Discharge Valve, 1B33-F067B Reports loss of High Pressure Feed.

Directs Area Operator to investigate cause of breaker trip.

BOP

Reports that 4160 V Bus 1A has tripped

Reports that NO CCW Pumps are running.

Carries out Scram Choreography by:

1) Making an Announcement

Reactor Scram

MDRFP may start

Evacuate the RCIC room

Evacuate the Containment

2) Determine Rod status and report to CRS

Monitors panels and reports loss of other equipment due to loss of bus.

Reports Inboard MSIV closure.

Reports Loss of Service Air Compressors Directs Area Operator to investigate cause of breaker trip.

Page 9 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 8 Page 2 of 2

==

Description:==

Loss of Power to 4160 V Bus 1A Time Position Applicants Actions or Behavior SRO

Directs actions of CPS 4008.01, Abnormal Reactor Coolant Flow.

Directs actions for Loss of CCW Critical Task

Directs actions of CPS 4100.01, Reactor Scram upon loss of CCW

Carries out Scram Choreography by performing an Update:

1) Entering EOP-1 and 6

2) Entering Scram Off-Normal

3) Transient Annunciator Response is authorized

Directs a level band of Level 3 to Level 8

Directs stabilization of RPV Pressure 800 to 1065 psig.

Enters CPS 4004.01, Instrument Air Loss.

Enters CPS 4008.01, Abnormal Reactor Coolant Flow.

Directs investigation into cause of breaker trip.

Terminus: Actions related to the bus trip and Reactor Scram have been stabilized.

Page 10 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 9 & 10 Page 1 of 2

==

Description:==

Recirculation Loop Rupture and HPCS Injection Valve Fails to Open Initiation: After actions have been taken for Loss of Power and upon direction of the Lead Examiner.

Cues: Increasing Drywell pressure and temperature, Decreasing RPV Level.

Time Position Applicants Actions or Behavior ATC

Reports Drywell Pressure rising.

Report EOP-1 Entry Condition on High Drywell Pressure and/or Low RPV Water Level.

Report EOP-6 Entry Condition on High Drywell Pressure.

Performs EOP actions as directed by SRO.

Reports loss of High Pressure Feed.

o Initiates ADS BOP

Starts Drywell Mixers, as directed.

Starts Containment Spray, as directed.

Starts both trains of SLC, as directed.

Monitors the start of the ECCS Systems on High Drywell Pressure.

Observes that HPCS Injection Valve, 1E22-F004, has failed to automatically open and reports action to SRO.

o Takes action to have HPCS Injection Valve opened locally.

When TAF is reached, initiates ADS to Blowdown the reactor. (ATC Operator Critical Tasks may initiate ADS)

Maximizes ECCS injection to restore RPV water level above TAF.

Operates ECCS Systems as needed, to control RPV Water Level, Level 3 to Level 8 Attempt restart of Condensate & Condensate Booster.

Page 11 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 9 & 10 Page 2 of 2

==

Description:==

Recirculation Loop Rupture and HPCS Injection Valve Fails to Open Time Position Applicants Actions or Behavior SRO Enters EOP-1, RPV Control, and directs the following:

Determines Mode Switch is in SHUTDOWN.

Determines Shutdown Criteria is met.

Directs control of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs.

Directs maintaining RPV Level, Level 3 to Level 8 by using Preferred Injection Systems.

Directs use of Alternate Level Control Systems Critical Tasks

When TAF is reached, directs initiation of ADS to Blowdown the reactor.

Directs maximizing ECCS injection to restore RPV water level above TAF.

Monitor area temperatures, levels and radiation levels.

Directs making an injection source throttable.

Enters EOP-6, Primary Containment Control, and directs the following:

Starting Mixers

IAW Fig. O, directs the start of Containment Sprays.

If Containment Sprays are running, directs stopping Containment Sprays prior to TAF.

Enters EOP-3, Emergency RPV Depressurization, upon reaching TAF.

Directs initiation of ADS May direct the isolation of RT and/or RR.

Terminus:

Blowdown has been completed

RPV level has been recovered and is being controlled Level 3 to Level 8.

Upon approval of Lead Examiner Page 12 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed

2. Reset to IC #94 for this scenario(Verify/Adjust Power to 7% with rods to match turnover).

3. Load lesson plan #7 for this scenario

4. Place simulator in RUN

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

6. Verify RCIC Flow Controller is set at 620 psig.

7. Ensure the correct number of CPs are in service.

8. Make sure CRD drive water D/P is in the expected range

9. Hotwell levels controllers are set at 50/45

10. Pressure set is at 922 psig.

11. Document rod position is step 19 on a NF-CL-721-1002

12. Turn on and advance recorders

13. Hang OOS tags per turnover

14. Identify T/S issues associated with OOS and turnover

15. Verify simulator conditions match the turnover

16. Provide copies of the following:

CPS 3002.01, Rev. 27a, complete to step 8.7.2. with exception of 8.7.1.2 & 8.7.1.4. Step 8.7.1.1 (Page 25) should have time filled in of 30 minutes prior to start of scenario.

CPS 9054.01, Rev. 42b

CPS 9054.01C002, Rev. 1b, complete through step 8.4.1.

CPS 9054.01D002, Rev. 22a, complete with respect to C002.

CPS 9000.05, Rev. 27 (Have available, but do not provide unless requested)

CPS 9000.05D001 Rev. 27 (Have available, but do not provide unless requested)

Page 13 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1 Event Triggers and Role Play Event #

1. Pull rods to raise power

a. No Trigger

b. Role play: None

2. Difficult to Withdraw Control Rod

a. No Trigger

b. Role play: None

3. Start RCIC for Surveillance.

a. No Trigger

b. Roll play: Area Operator: When requested to verify water has drained from the Exhaust Drain Pot at the drain line report back that no water is visible issuing from the drain.

Area Operator: If RCIC Exhaust Pressure is requested, report that it is 0 psig.

Area Operator: Respond to requests and reports from the MCR.

4. Containment Upper Air Lock Outer Door Failure

a. No Trigger

b. Role play: Security report that as you exited the Upper Airlock Door you could not get the outer door to shut.

Area Operator: If contacted about Upper Airlock Door being shut, respond that it is shut and you will chain lock it shut.

5. RCIC Auto Controller Fails With Low Demand

a. No Trigger

b. Role play: None

6. Auto Trip of B Component Cooling Water (CCW) Pump

a. Remote Trigger 2 on the signal from lead examiner

b. Role Play: Area Operator report that breaker has tripped and will not reset. The pump appears to be fine.

Electrical Maintenance: report that cannot determine cause and it will take some time to troubleshoot.

Area Operator: If requested to check out A CCW Pump report that it appears to operating fine.

7. Condenser Hotwell Overflow Controller Failure

a. Remote Trigger 3 on the signal of lead examiner

b. Role play: None Page 14 of 15

D-2, Dynamic Simulator Scenario 1 EXAM DATE: 7/11/05 ILT0401-1

8. Loss of Power to 4160 V Bus 1A

a. Remote Trigger 4 on the signal of the lead examiner.

b. Role play: Booth Operator: 5 minutes after the scram announcement ensure that dedicated individual reports to MCR as IMD.

Area Operator: if directed to investigate breaker trip, report back that it has tripped on overcurrent.

Electrical Maintenance: If directed to investigate cause of breaker trip, report that it has tripped on overcurrent, further troubleshooting is necessary to determine cause, breaker can not be reset.

9. Recirculation Loop Rupture and HPCS Injection Valve Fails to Open

a. No Trigger

b. Role play: Area Operator: 5 minutes after being sent to open valve report back that valve can not be opened.

Page 15 of 15

Overview Makeup/Reject: CPs A, B, C are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on RAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B, A & B RT F/D, & Aux Stm in service. 1WF Evap is in Hot Stby.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 2 Total Core Flow: _30.0__ mlb/hr FCV Position: A: __94____% B: __93____%

Reactor Power _7 ___% (<=100%) _ __ MWt (<=3473) _0 __ Mwe Xenon: Stable RPV Level _31.3__ in Narrow Range RPV Pressure __926__ psi (< 1045)

In service SDC loop None MODE 2 Containment Suppression Pool Temperature: _74.1_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.6__ psi (0 to 1 psig)

Drywell to Containment dp: _0.6__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _101_ F (<=146.53 F)

Secondary Containment: _0.45_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27.8_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _____ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _92 _ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _ _ MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: If there is protected equipment, it is listed here. If necessary attach the contingency plan.

Comments: This is to be the last page on the approved simulator exercise so that it can be easily torn off and given to the students. Include here the turnover items, weather, time of day, rod positions etc.

From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

Turnover This page contains the Turnover information not found in the Overview page.

1. Power, xenon and time in life Power level is 7% with plant startup in progress. Directions are to continue to pull rods to 9%

power and then perform the RCIC surveillance

2. Status of Tagged Out Equipment Service Air Compressor 1SA01C is OOS for bearing replacement

3. Shift conditions Day Shift Today

4. Weather Conditions Thunderstorm watch is in effect, In CPS 4302.01, Tornado/High Winds, Announcements are not being made.

5. Thermal Limit Problems or concerns

6. LCOs in effect

7. Surveillances in progress

CPS 9054.01C002

RCIC System Operability

RHR B is in Suppression Pool Cooling IAW CPS 3312.01up to Step 8.1.9.4.

PRM 1RIX-PR039 is in service.

Suppression pool Temperature Log is in progress.

8. Evolutions planned for the shift Continue plant startup and place mode switch in RUN.

9. Risk Levels

10. Other CP Outlet Conductivity is > High-High setpoint due to plant startup. All actions for ACTION Level 1 have been taken. Conductivity is slowly tending down and is expected to be in spec within the required time limit.

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 2 Operating Test No.: ILT0401-1 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

73% power, Plant Shutdown in progress.

Thunderstorm Watch is in effect.

Service Air Compressor 1SA01C is OOS for Motor Bearing Replacement.

Turnover:

Continue normal plant shutdown and prepare to downshift RR Pumps after control rod pattern is verified.

Start and run SX Pump C for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to obtain hot oil sample.

Event Malf. No. Event Type* Event No. Description 1 N/A N-BOP/SRO Start SX Pump C 2 Annunc TS-SRO Hydrogen Ignitor Division 1 Power Failure 3 N/A R-ATC/SRO Reduce power with flow 4 EG03 I-ATC/SRO High Generator Field Voltage requiring Manual Control of Voltage Override Regulator.

5 CW04C C-BOP SX Pump C trips requiring manually opening 1SX014C. HPCS Override TS-SRO Inoperable.

6 DC02D C-ATC/SRO DCS Component Failure 7 RM01A C-BOP/SRO Trip of TBCCW Pump 8 ED02A M-ALL Tornado, Loss of RAT & ERAT, Failure of DG Div II Diesel to Auto ED02B Start.

9 Override M-ALL RCIC Line Break & MSL Line Break

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 9/13/2005

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 2 Operating Test No.: ILT0401-1 Narrative Summary Event # Description

1. The BOP operator will start SX 1C Pump IAW CPS No. 3211.01, Section 8.1.2 to perform PMT.

2. Annunciator CPS 5041-5H, Hyd Ignitor Sys Div 1 Trouble, is received. Technical Specifications will be evaluated and LCO 3.6.3.2, Action A1 will require the Hydrogen Ignitor Division to be restored to Operable status within 30 days.

3. Power reduction with flow will commence. Power reduction can be halted upon direction from the Lead Examiner by initiating next event.

4. Generator field voltage will start to increase requiring the ATC Operator to take manual control of the voltage regulator and adjust voltage. Annunciator CPS 5008-3E, Gen/Exciter Field Trouble, will also initiate alerting the operator to the problem.

5. The Shutdown Service Water (SX) pump, which is running for PMT, will trip. The BOP operator will need to open the 1SX014C valve to restore cooling water to the SX components. Technical Specifications LCO 3.7.2, Action A. will be evaluated which will require that HPCS be declared Inoperable immediately.

6. Annunciator 5004-2L, DCS Component Failure, causing a loss of the #4 and #8 DCS screens. This will require the RO to reroute the information by operating the DG 4 Bypass pushbutton on the P680 panel.

7. A trip of TBCCW Pump B will require the BOP Operator to start the standby pump.

8. Security will report that the Thunderstorm Watch has been upgraded to a Tornado Warning and that a Tornado has been sighted on the South edge of Clinton. A Tornado will tear through the RAT and ERAT causing a loss of off-site power. The Div II DG will fail to auto start.

9. A RCIC line break and small MSL break will develop causing entry into EOP-8, Secondary Containment Control as temperatures exceed Max Safe Values.

EOP 1, 8, 3 Critical tasks:

Perform actions to re-energize 4160V Bus 1B1.

Performs Blowdown when two or more areas are above the Max Safe Value.

Page 2 of 2 9/13/2005

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 1 Page 1 of 1

==

Description:==

Start Shutdown Service Water (SX) Pump, 1SX01PC (Panel P601, Section 5062)

Initiation: Following Shift Turnover Cues: Upon direction of the SRO General Note If this evolution was Prebriefed and Expected Alarms were reviewed, the following may be allowed:

The Expected Alarms will be flagged in some manner.

When the annunciator comes in the operator will announce Expected Alarm

The Annunciator Response Procedure (ARP) need not be entered because it has already been reviewed in the Prebrief.

If a Prebrief 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. (OP-AA-103-102)

Time Position Applicants Actions or Behavior BOP Makes plant announcement on start of SX Pump.

Places Test Prep Switch for Div 3 SX in TEST.

Enters Short Duration Time Clock for Test Prep Switches in Test.

Per CPS 3211.01, Shutdown Service Water (SX), place C SX Pump, 1SX01PC in service:

Start SX Pump 1SX01PC.

Verify SX strainer outlet pressure 75 psig.

Verify shut/shut 1SX014C.

Verify running or start 1VH01CC, SX Pump Room Supply Fan.

Verify 1SX006C, DG 1C HX Outlet Vlv opens.

ATC

Monitors reactor to ensure operations remain within established bands

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

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Contacts Chemistry for RWT manipulations.

Terminus: SX Pump C has been started.

Page 1 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 2 Page 1 of 1 Description Hydrogen Ignitor Division 1 Power Failure (P800, Section 5041,Technical Specification Call, No Control Room Action)

Initiation: Following startup of SX and upon direction of the Lead Examiner.

Cues: Annunciator CPS 5041-5H, Hyd Ignitor Sys Div 1 Trouble, is received.

Time Position Applicants Actions or Behavior BOP

Communicates annunciator to SRO

Refers to the ARP.

Dispatches Area Operator to Panel 1HG03JA to investigate cause.

Monitors plant to ensure operations remain within established bands

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

Contacts Electrical Maintenance to investigate breaker.

ATC

Monitors reactor to ensure operations remain within established bands

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

Monitors containment hydrogen concentration.

SRO

Receives report from BOP Operator.

Upon receiving report on system status directs that electrical maintenance be called.

Declares per Technical Specification LCO 3.6.3.2, that division 1 hydrogen ignitors is Inoperable and IAW Action A.1 restore the division to Operable status within 30 days.

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

Conducts Brief on problem and status.

Directs One-Time-Closure-of-Breaker per OP-CL-108-101-1001.

Terminus: Technical Specification review complete.

Page 2 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

Reduce Power With Flow (Panel P680, Section 5003)

Initiation: Following Technical Specification Call Cues: Directed by SRO General Note If this evolution was Prebriefed and Expected Alarms were reviewed, the following may be allowed:

The Expected Alarms will be flagged in some manner.

When the annunciator comes in the operator will announce Expected Alarm

The Annunciator Response Procedure (ARP) need not be entered because it has already been reviewed in the Prebrief.

If a Prebrief 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. (OP-AA-103-102)

Time Position Applicants Actions or Behavior ATC Per, CPS 3005.01, Unit Power Changes reduce reactor power.

Reduces power to 65%

Closes the Flow Control Valves individually while maintaining the mismatch within spec.

Monitors paramaters as flow is reduced. (Power, FCV Position, Flow, MWe)

BOP

Monitors plant to ensure operations remain within established bands

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

Directs actions listed above.

Enforces OPS expectations and standards

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

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

Page 3 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

High Generator Field Voltage (Panel P680, Section 5008)

Initiation: After power reduction, and upon direction from the Lead Examiner.

Cues: Generator Field Voltage increases, #9 Bearing Vibration increases, & Annunciator CPS 5008-3E, Gen/Exciter Field Trouble, is received.

Time Position Applicants Actions or Behavior ATC

Communicates annunciator to SRO.

Refers to the ARP

Investigates cause of annunciator and status of Main Generator.

May attempt to control voltage with the AC Regulator.

Depresses MANUAL on the EXCITER FLD TRANSFER switch.

Reduces Generator Field Voltage to within normal band with the DC Regulator May request a Line-In-The-Sand for tripping the Main Turbine on high vibration.

BOP

Monitors plant to ensure operations remain within established bands.

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

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

May direct that the Main Turbine be tripped at a certain setpoint due to high vibration on #9 bearing.

Conducts brief on problem and status.

Terminus: Generator Field Voltage has been returned to normal.

Page 4 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Auto Trip of C Shutdown Service Water (SX) Pump, 1SX01PC (Panel P601, Section 5062)

Initiation: After Voltage Regulator has been taken to MANUAL, and upon direction of Lead Examiner Cues: Annunciator 5064-1A, Auto Trip SSW Pump 1C is received.

Time Position Applicants Actions or Behavior BOP

Communicates annunciator to SRO

Refers to ARP

Dispatches Area Operator to Pump and Breaker.

Performs Plant Announcement on Pump Trip.

Per CPS 5064-1C, Auto Trip SSW Pump 1C:

Place SSW Pump 1C, 1SX01PC control switch in Pull-To-Lock.

IF An Emergency does not exist,

THEN Refer to CPS 3211.01, Shutdown Service Water (SX) to manually reopen 1SX014C, PSW To SSX 1C Hdr Isol Vlv to provide Plant Service Water to the SSW 1C system.

Per CPS 3211.01, Shutdown Service Water (SX):

Deenergize the breaker for 1SX014C and manually open the valve no more than 25% until SX system pressure approaches WS system pressure.

Open 1SX014C and demonstrate remote valve control per the following:

1) Energize the breaker for 1SX014C.

2) Electrically open 1SX014C to full OPEN.

3) Verify 1SX014C fully open.

4) Verify SX pressure stabilizes near WS pressure.

Shut 1SX006C.

ATC

Monitors reactor to ensure operations remain within established bands

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

Performs Plant Announcement on Pump Trip.

SRO

Directs actions listed above.

Contacts Electrical Maintenance to investigate.

May conduct brief.

Enforces OPS expectations and standards

Declares per Technical Specification LCO 3.7.2, that HPCS is Inoperable immediately, and LCO 3.5.1, verify that RCIC is Operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore HPCS to Operable status within 14 days.

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

Conducts brief on problem and status.

Terminus: C Shutdown Service Water system is being supplied from Plant Service Water.

Page 5 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 6 Page 1 of 1

==

Description:==

DCS Component Failure (Panel P680, Section 5004)

Initiation: After SX problem has been resolved, and upon direction of the Lead Examiner.

Cues: Annunciator CPS 5004-2L, DCS Component Failure, is received.

Time Position Applicants Actions or Behavior ATC

Communicates annunciator to SRO

Refers to the ARP

Investigates annunciator

Identifies that Display Generator #4 has failed resulting in the loss of #4 & #8 DCS Screens.

May attempt to cycle power supplies.

Per CPS 3512.01, DCS & PMS, Step 8.8.4:

Depresses the DG 4 Bypass Pushbutton on P680, Section 5004 to reroute the information and restore the #4 & #8 DCS Screens.

Returns DCS #4 & #8 to original screens.

Re-depresses the DG 4 Bypass Pushbutton to restore it to normal operation.

BOP

Monitors plant to ensure operations remain within established bands.

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

SRO

Directs actions listed above.

Notifies IMD and requests investigation.

Enforces OPS expectations and standards

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

Conducts brief on problem and status.

Terminus: DG 4 has been bypassed and DCS Screens #4 & #8 have been restored.

Page 6 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

Trip of TBCCW Pump B (Panel P870, Section 5017)

Initiation: After DCS Screens have been restored, and upon direction from the Lead Examiner Cues: Following Annunciators are received: CPS 5017-1A, Auto Trip Turbine Auxiliary Pump/Motor, CPS 5017-1B, Low Pressure TBCCW HX Outlet Hdr, CPS 5018-2A, Trouble GC System Local Panel 1PL10J.

Time Position Applicants Actions or Behavior BOP

Communicates annunciators to SRO

Refers to the ARPs.

Performs Plant Announcement on Pump Trip Per CPS 5017-1A & 1B

Immediately take action for Loss of TBCCW per CPS 3304.01, Turbine Building Closed Cooling Water - Loss of TBCCW System: Section 8.3.1.

Per CPS 3204.01, Turbine Building Closed Cooling Water:

Determines that TBCCW Storage Tank Level is >24.

If attempts are made to restart the tripped pump, it will not start.

Starts Standby Pump (1WT001PA) by:

1) Direct Area Operator to shut Pump Discharge Valve, 1WT003A.

2) Starts TBCCW Pump A

3) Directs Area Operator to slowly open Pump Discharge Valve, 1WT003A.

Per CPS 5018-2A, Trouble GC System Local Panel 1PL10J:

Have Area Operator check out Panel 1PL10J.

ATC

Monitors on DCS TBCCW Storage Tank Level, computer points WT-BA401 & 402.

Monitors reactor to ensure operations remain within established bands

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

Monitors CD Pump Temperatures.

Performs plant Announcement on Pump Trip.

SRO

Directs actions listed above.

Directs monitoring CD Pump temperatures.

Directs monitoring TBCCW Storage Tank Level.

Enforces OPS expectations and standards

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

Conducts brief on problem and status.

Terminus: A TBCCW Pump has been started and system pressure has returned to normal.

After Terminus is reached:

Security should call SRO and report that Thunderstorm watch has been upgraded to a Tornado Warning and a tornado was spotted at south edge of Clinton on an Easterly path. Warning should be for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from present time.

Page 7 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 8 Page 1 of 1

==

Description:==

Tornado, Loss of RAT/ERAT, Failure of Div II DG to Auto Start.

Initiation: After TBCCW Pump has been started, Tornado Warning has been reported, and upon direction of the Lead Examiner.

Cues: Loss of power annunciators, no bus voltage, and a loss of lighting.

Time Position Applicants Actions or Behavior ATC

Monitors reactor to ensure operations remain within established bands

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

Reports Drywell pressure increasing due to loss of Drywell Cooling, if BOP Operator has not started the A Drywell Cooling System.

o May dispatch Area Operators due to the BOP Operator workload.

Receives Annunciator 5003-5M, Cnmt/DW IA Isol Vlv Closed.

Notifies SRO and BOP of Isolation Valve closure.

BOP

Reports numerous alarms indicating that power has been lost to the RAT and ERAT.

Determines that Div. II DG has failed to start.

Reports to SRO that Div. II DG has failed to start.

Critical Task

Takes action to start Div. II DG and reenergize the bus.

Dispatches Area Operators to assess damage to RAT and ERAT.

Monitors panels and reports loss of other equipment due to loss of bus.

Identifies that B Drywell Cooling has tripped, and emergency starts the A Drywell Cooling System.

Directs Area Operators to check out Drywell Chillers.

Identifies that Div 3 DG has tripped after scram due to loss of cooling water.

Directs Area Operators to check out various plant equipment.

SRO

Receives report from Security that a Tornado has been sighted coming across the lake, and heading for the Makeup Water Pumphouse

Reenters CPS 4302.01. Tornado/High Winds and directs Plant Announcements.

Receives report from Security that a Tornado has struck the Makeup Water Pumphouse.

Acknowledge that Div. II DG Output Breaker failed to close.

May direct BOP Operator to start Drywell Mixers.

Per CPS 4200.01, Loss of AC Power

Directs actions to reenergize Bus 1B1

Directs stabilization of RPV Pressure 800 to 1065 psig.

Directs actions related to loss of Drywell Cooling and Cnmt/DW IA Isolation.

Terminus: Actions related to the bus trip have been stabilized.

Page 8 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 9 Page 1 of 2

==

Description:==

RCIC Line Break, & Main Steam Line Break Initiation: After actions have been taken for Loss of RAT, & ERAT, and upon direction of Lead Examiner.

Cues: Annunciator CPS 5065-6F, Sec. CNMT. Area High Temp.

Time Position Applicants Actions or Behavior ATC Report EOP-8, Secondary Containment Control, Entry Condition on Area Temperature.

Performs EOP actions as directed by SRO.

Initiates a manual reactor scram before first Max Safe Temperature is exceeded, and performs Scram Choreography.

Carries out Scram Choreography by reporting:

1) Mode Switch in Shutdown, Power is

2) Rod status is

3) Reactor Power is and trend

4) Reactor pressure is and trend

5) Reactor level is and trend

6) Any EOPs with entry conditions Per CPS 4100.01, Reactor Scram

Turn Mode Switch to SHUTDOWN o Verify reactor power is lowering o Verify SHUTDOWN CRITERIA met

IF RPV level is rising with 2 feed pumps operating

THEN Secure 1 Feed Pump and control RPV water level Level 3 to Level 8.

Verify Turbine and Generator trip when required

Evacuate the containment.

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

Coordinates with BOP to monitor and control RPV level and press.

Page 9 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 9 Page 1 of 2

==

Description:==

RCIC Line Break, & Main Steam Line Break Time Position Applicants Actions or Behavior BOP Carries out Scram Choreography by:

Making an Announcement

1) Reactor Scram

2) MDRFP may start

3) Evacuate the RCIC room

4) Evacuate the Containment

DetermineRod status and report to CRS Per CPS 5065-6F, Sec. CNMT. Area High Temp.

At 1H13-P678, monitor temperature recorders 1TR-CM326 and 1TR-CM327 and determine which area(s) is in alarm.

Observes on 1TR-CM326; Point 8, Aux Bldg RCIC Pump Room, & Point 9, Aux Bldg RCIC Instr Pnl Rm are alarming and increasing.

Reports that Point 18, Aux Bldg Steam Tunnel is alarming and increasing.

Dispatches an operator to RCIC room to investigate

Attempts to isolate RCIC

Reports that isolation valves did not close.

Performs EOP actions as directed by SRO.

Verifies status of Fuel Building Ventilation and SGTS.

Critical Task

Performs BLOWDOWN IAW EOP-3 SRO Enters EOP-8, Secondary Containment Control, and directs the following:

Direct a manual reactor scram before first Max Safe Temperature is exceeded.

Directs actions of CPS 4100.01, Reactor Scram.

Carries out Scram Choreography by performing an Update:

1) Entering EOP-1 and 8

2) Entering Scram Off-Normal

3) Transient Annunciator Response is authorized Critical Task

Waits until 2 areas have exceeded Max Safe Values and then performs Blowdown IAW EOP-3 Enters EOP-1, RPV Control, and directs the following:

Directs the stabilization of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs.

Directs maintaining RPV Level, Level 3 to Level 8 by using Preferred Injection Systems.

Expands Level Band to -30 to +40 inches Wide Range.

Terminus:

Reactor has been depressurized through BLOWDOWN.

RPV level stable and under control in required band

Upon approval of lead examiner Page 10 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed

2. Reset to IC #95 for this scenario(Verify/Adjust Power to 73% to match turnover).

3. Place simulator in RUN

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

5. Load lesson plan #8 for this scenario

6. Make sure CRD drive water D/P is in the expected range

7. Hotwell levels controllers are set at 50/45

8. Pressure set is at 922 psig.

9. Document rod position is step 32 complete on a CPS 9000.09D002

10. Turn on and advance recorders

11. Hang OOS tags per turnover

12. Identify T/S issues associated with OOS and turnover

13. Verify simulator conditions match the turnover

14. Provide marked up CPS 3005.01 complete to Step 8.1.3.

Page 11 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Event Triggers and Role Play Event #

1. Start Shutdown Service Water (SX) Pump, 1SX01PC

a. No Trigger

b. Role play: Area Operator: Stationed in the Pump room to respond to requests from the MCR. If asked to perform inspection of SX Pump C report that pump is running normally, and Area Fan is running.

2. Hydrogen Ignitor Division 1 Power Failure

a. Remote Trigger 1 on the signal from the Lead Examiner

b. Role play: Area Operator: report that the 480V breaker for 1HG03JA Transformer is tripped.

1HG03JA appears to be deenergized.

Booth Operator: if directed to attempt One-Time-Breaker-Closure, report that the breaker will not close.

3. Reduce Power With Flow

a. No Trigger

b. Role play: Booth Operator: If RR Vibration Data is rquested report that data is good.

4. High Generator Field Voltage

a. Remote Trigger 2 on the signal from the Lead Examiner

b. Role play: None

5. Auto Trip of C Shutdown Service Water (SX) Pump, 1SX01PC

a. Remote Trigger 3 on the signal from the Lead Examiner

b. Remote Triggers for opening 1SX014C

Remote 8: opens breaker

Remote 9: manually opens valve to 25%

Remote 10: closes breaker.

c. Role play: Area Operator: If sent to Div 3 SX Pump and Breaker, report that Pump appears to be fine but breaker has tripped on overcurrent.

Electrical Maint: If called report that you will investigate, troubleshooting may take time.

6. DCS Component Failure

a. Remote Trigger 4 on the signal from the Lead Examiner

b. Role Play: Booth Operator: BOP Operator may come back to cycle power supplies, report that power supplies hav been cycled.

7. Trip of TBCCW Pump B

a. Remote Trigger 5 on the signal from the Lead Examiner

b. Role play: Area Operator: when directed to check out Local Panel 1PL10J, report that the alarm is Alternator Air Temperature High:

Area Operator: if sent to the B TBCCW Pump Breaker and/or Pump report that breaker is tripped and/or no problem with pump is apparent.

Page 12 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1 Area Operator: respond to requests to shut and open pump discharge valve.

Page 13 of 14

D-2, Dynamic Simulator Scenario 2 EXAM DATE: 7/11/05 ILT0401-1

8. Tornado, Loss of RAT/ERAT, Failure of Div II DG to Auto Start.

a. Role Play: Security: Before initiating Remote Trigger,report that Thunderstorm watch has been upgraded to a Tornado Warning and a tornado was spotted at the south edge of Clinton on an Easterly path. Warning should be for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from present time.

b. Remote Trigger 6 on the signal from the Lead Examiner

c. Malfunction Removal: Make sure the SX Discharge Pressure High is removed before Turbine Trip.

d. Role play: Security: report that a Tornado has been sighted coming across the lake and heading for the Makeup Water Pumphouse.

Security: Within 1 minute after entering loss of RAT and ERAT notify the MCR that a Tornado has struck the Makeup Water Pumphouse and you can see debris on and around the ERAT and RAT.

Area Operator: If directed to check out Drywell Chiller, report that it appears to running fine.

9. RCIC Line Break, & Main Steam Line Break

a. Remote Trigger 7 on the signal from the Lead Examiner

e. Role play: Auxiliary Operator: If requested to go to RCIC room report that as soon as entered the room you heard loud noise and it was very hot, so you backed out and closed the door.

Booth Operator: If operator comes for report on rod status at RACCS, report that the Full In light is on in both cabinets.

Booth Operator: 5 minutes after the scram announcement ensure that dedicated individual reports to MCR as IMD.

Page 14 of 14

Overview Makeup/Reject: All CPs except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: _61.2__ mlb/hr FCV Position: A: __40_____% B: __38____%

Reactor Power _73___% (<=100%) _2593__ MWt (<=3473) _859__ Mwe Xenon: Stable RPV Level _33__ in Narrow Range RPV Pressure _______ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _74.1_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.5__ psi (0 to 1 psig)

Drywell to Containment dp: _0.5__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _101__ F (<=146.53 F)

Secondary Containment: _0.45_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27.1_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _____ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _106_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _264_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: If there is protected equipment, it is listed here. If necessary attach the contingency plan.

Comments: This is to be the last page on the approved simulator exercise so that it can be easily torn off and given to the students. Include here the turnover items, weather, time of day, rod positions etc.

From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

Turnover This page contains the Turnover information not found in the Overview page.

1. Power, xenon and time in life Power has been reduced from 84% with rods to a current power level of 73%. Plant shutdown is in progress.

2. Status of Tagged Out Equipment Service Air Compressor 1SA01C is OOS for bearing replacement

3. Shift conditions Day Shift Today

4. Weather Conditions Thunderstorm watch is in effect, In CPS 4302.01, Tornado/High Winds, Reporting is not being done.

5. Thermal Limit Problems or concerns

6. LCOs in effect

7. Surveillances in progress

8. Evolutions planned for the shift

First: Run SX Pump C for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for EMD to obtain hot oil sample. Chemical Injection has been secured in preparation for starting SX Pump.

Second: Continue power reduction with flow to 65% power. Taking RR Pump vibration data at this flow line.

9. Risk Levels

10. Other

Overview Makeup/Reject: All CPs except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: _61.2__ mlb/hr FCV Position: A: __40____% B: __38____%

Reactor Power _73___% (<=100%) _2593__ MWt (<=3473) _859__ Mwe Xenon: Stable RPV Level _33__ in Narrow Range RPV Pressure _______ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _74.1_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.5__ psi (0 to 1 psig)

Drywell to Containment dp: _0.5__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _____ F (<=146.53 F)

Secondary Containment: _0.45_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _27.1_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _____ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _106_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _264_ MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: If there is protected equipment, it is listed here. If necessary attach the contingency plan.

Comments: This is to be the last page on the approved simulator exercise so that it can be easily torn off and given to the students. Include here the turnover items, weather, time of day, rod positions etc.

From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

Turnover This page contains the Turnover information not found in the Overview page.

1. Power, xenon and time in life Plant startup in progress power level is currently 73%. Holding at this power level.

2. Status of Tagged Out Equipment Service Air Compressor 1SA01C is OOS for bearing replacement.

3. Shift conditions Day Shift Today

4. Weather Conditions Thunderstorm watch is in effect, In CPS 4302.01, Tornado/High Winds, Announcements are not being made.

5. Thermal Limit Problems or concerns

6. LCOs in effect

7. Surveillances in progress

8. Evolutions planned for the shift Shift Plant Service Water (WS) Pumps to A in service and C secured.

Startup will recommence later in shift after engineering resolution of condensate pump vibration issues. All condensate pumps are available.

9. Risk Levels

10. Other

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 3 Operating Test No.: ILT0401-1 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

73% Reactor Power, steady state, waiting on surveillance testing to complete.

Thunderstorm Watch is in effect.

Service Air Compressor 1SA01C is OOS for Motor Bearing Replacement.

Turnover:

Shift Plant Service Water (WS) Pumps to A in service and C secured.

Event Malf. No. Event Type* Event No. Description 1 N/A TS-SRO SLC Pump A Oil Sightglass Empty 2 N/A N-BOP/SRO Shift WS Pumps 3 Annunc C-BOP Low Flow CW Pump 1C Brg Seal Water 4 CU01A C-ATC/SRO Loss of A RT Filter Demin.

5 TU02 I-BOP Turbine LO Temp Controller Failure 6 Annunc C-ATC Low Pressure RFP 1A Seal Water.

7 N/A R-ATC/SRO Power Reduction to remove RFP 1A from service.

8 Override TS-SRO LPCS/RHR A Water Leg Pump trip 9 Annunc M-ALL Seismic Event, Main Turbine High Vibration, with Scram and RP01 ATWS 10 Override C-BOP SLC Squib Valves fail to fire.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 9/13/2005

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 3 Operating Test No.: ILT0401-1 Narrative Summary Event # Description

1. A report will be made by the Area Operator stating that the Oil Sightglass for the A SLC Pump is empty and there is oil on the skid. This will require entry into Technical Specification 3.1.7, Action A.1, which requires restoring the SLC Pump to Operable status within 7 days.

2. The BOP Operator will shift Plant Service Water Pumps, placing A WS Pump in service and securing C WS Pump.

3. Annunciator 5041-3G, Low Flow CW Pump 1C Brg Seal Water, is received.

This will require the BOP operator to secure the 1C CW Pump.

4. Annunciator CPS 5000-2C, F-D System Trouble will be received. The ATC Operator will then need to analyze system conditions and lineup system for 2 pump /1 filter operation.

5. The BOP operator will need to diagnose the problem with the temperature controller and take manual control to stabilize temperature.

6. Annunciator 5002-2A, Low Pressure Reactor Feed Pump 1A Seal Water, will be received. The RO will determine that seal pressure cannot be restored and will remove the RFP from service.

7. A power reduction to <65% will be initiated to allow RFP 1A to be removed from service.

8. Annunciator 5063-3H, LPCS/RHR A Water Leg Pump Auto Trip, is received.

BOP operator will determine that the Water Leg Pump has tripped. This will require entry into Technical Specification 3.5.1, Action A.1, which requires restoring the low pressure subsystem to Operable status within 7 days.

9. A seismic event exceeding an SSE condition will be received. This will require an orderly plant shutdown. The Main Turbine will experience high vibration which will require a manual scram with ATWS.

10. The SLC Squib Valves will not fire preventing SLC Pump B from injecting into the reactor. This will require Alternate Boron Injection.

EOP 6, 1A, (Alternate Boron Injection)

Critical tasks:

Insert Control Rods to Shutdown the Reactor.

Terminate and Prevent Injection to reduce power.

Page 2 of 2 9/13/2005

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 1 Page 1 of 1 Description SLC Pump A Oil Sightglass Empty (Technical Specification Call, No Control Room Action)

Initiation: Completion of turnover.

Cues: Information from turnover.

Time Position Applicants Actions or Behavior BOP

Receives call from Area Operator that the Oil Sightglass for SLC Pump A is empty and there is oil on the skid.

Communicates information to SRO Recommends opening the breaker for SLC Pump A.

Recommends removing the key for SLC Pump A.

Monitors plant to ensure operations remain within established bands

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

ATC

Monitors reactor to ensure operations remain within established bands

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

Recommends opening the breaker for SLC Pump A.

Recommends removing the key for SLC Pump A.

SRO

Receives report from BOP Operator Directs the opening of the breaker for SLC Pump A.

Directs the removal of the key for SLC Pump A.

Reviews Technical Specifications for applicabilty due to isolation of SLC Pump A.

Declares per Technical Specification LCO 3.1.7, that SLC Pump A is inoperable and IAW Action A.1 restore SLC to Operable status within 7 days.

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

Terminus: Technical Specification review complete.

Page 1 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Shift Plant Service Water Pumps (WS)

(Panel P800, Section 5041)

Initiation: Following Shift Turnover Cues: Upon direction of the SRO Time Position Applicants Actions or Behavior BOP Makes a plant announcement for shifting WS pumps as directed.

Per CPS 3212.01, Plant Service Water (WS), Section 8.1.3, shift WS Pumps:

Verifies that a liquid discharge is not in progress.

Notifies Chemistry of pending WS system changes.

Direct an Area Operator to perform prestart checks per step 3.

Start A WS Pump, 1WS01PA.

Verify that 1WS002A, WS Pump A Disch Vlv opens.

Direct an Area Operator to verify proper operation of WS Pump A.

Stop C WS Pump.

Return Control Switch to AUTO.

Verify that 1WS002C, WS Pump C Disch Vlv shuts.

ATC Makes a plant announcement for shifting WS pumps as directed.

Monitors reactor to ensure operations remain within established bands

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

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Conducts an Update on WS Pump shift.

Terminus: A WS Pump has been started and C WS pump has been secured.

Page 2 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

Low Flow CW Pump 1C Brg Seal Water (Panel P800, Section 5041)

Initiation: Following Shift of WS Pumps, and upon direction from the Lead Examiner.

Cues: Annunciator CPS 5041-3G, Low Flow CW Pump 1C Brg Seal Water, is received.

Time Position Applicants Actions or Behavior BOP

Communicates annunciator to SRO

Refers to the ARP.

Per, CPS 5041-3G, Low Flow CW Pump 1C Brg Seal Water:

Directs Area Operator to flush CW Pump C TW supply strainer 1TW01MC.

Monitor CW pump bearing temperatures.

Trips 1C CW Pump.

Makes a plant announcement on shutting down CW Pump 1C as directed.

ATC

Monitors reactor to ensure operations remain within established bands

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

Makes a plant announcement on shutting down CW Pump 1C as directed.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Conducts a brief on shutting down CW Pump 1C.

Enters CPS 4004.02, Loss of Vacuum. (Vacuum should not substantially change)

Directs a followup to complete shutdown of the pump per CPS 3113.01, Circulating Water (CW).

Terminus: CW Pump 1C has been tripped.

Page 3 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

A Reactor Water Cleanup Filter Demin Trips (Panel P680, Section 5000)

Initiation: After Circ Water system has stabilized and upon direction of the Lead Examiner.

Cues: Annunciator CPS 5000-2C, F-D System Trouble Time Position Applicants Actions or Behavior ATC

Communicates Annunciator to SRO.

Refers to the ARP.

Per CPS 5000-2C, F-D System Trouble

Investigate the cause of the alarm at instrument rack 1G36-P001 and control panel 1G36-P002.

Per CPS 3303.01, Reactor Water Cleanup (RT), Section 8.3.2.1 or 8.1.3.

IF RWCU pump(s) did not trip on low flow

THEN Throttle 1G33-F044, RWCU Filter/Demin Bypass to maintain 300 gpm flow with two pumps.

BOP

Monitors plant to ensure operations remain within established bands

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

Dispatches Area Operator to Filter Demin Panel.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: Reactor Water Cleanup has been restored to normal operation.

Page 4 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Turbine LO Temperature Controller Failure (Panel P870, Section 5017 & 5018)

Initiation: After the RT system is restored, and upon direction of the Lead Examiner.

Cues: Annunciator CPS 5018-3A, High Temp Turb-Gen Lube Oil Time Position Applicants Actions or Behavior BOP

Communicates the Annunciator to the SRO.

Refers to the ARP.

Per CPS 5018-3A, High Temp Turb-Gen Lube Oil:

Direct an Area Operator to check the Lube Oil Coolers.

Determines that the Temperature Controller has failed:

a) Place TURB OIL CLG WTR Controller in MANUAL.

b) Adjust (open/close) TCV controller as needed to maintain turbine oil outlet temperature 110°F to 120°F.

ATC

Monitors reactor to ensure operations remain within established bands

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

Checks for excessive temperatures across the turbine bearings.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: Turbine LO Temperature Controller has been placed in MANUAL and temperature has returned to normal.

Page 5 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 6 Page 1 of 2

==

Description:==

Low Pressure Reactor Feed Pump (RFP) 1A Seal Water & Removal of RFP 1A From Service.

(Panel P680, Section 5002)

Initiation: Turbine LO Temperature has been stabilized, and upon direction of Lead Examiner Cues: Annunciator CPS 5002-2A, Low Press RFP 1A Seal Water Time Position Applicants Actions or Behavior ATC

Communicates the Annunciator to the SRO.

Refers to the ARP.

Per CPS 5002-2A, Low Press RFP 1A Seal Water:

Verify condensate booster pump discharge header pressure > 350 psig.

Direct an Area Operator to swap seal water inlet filter to the standby filter.

Determines that seal water pressure is still low after the filter swap and prepares to remove RFP 1A from Service.

See next step for lowering power to remove RFP from service.

Per CPS 3103.01, Feedwater:

Discuss with the SRO the need to lockout the RR FCVs during the TDRFP S/D.

Transfer control of 1A RFP to MANUAL on the RFP A Flow Controller (Preferred).

1) Ensure the non-operating feed pump is selected on the Start Mode Actuator Selector.

2) Depress the RFP Flow Controller MANUAL push-button.

Or

Manual Speed Control Potentiometer (Alternate).

1) Adjust the Manual Speed Control potentiometer until a zero milliamp signal is indicated on the deviation meter.

2) Transfer control to the Manual Speed Control Potentiometer by pressing the MAN XFR push-button.

Reduce off-going turbine speed as necessary, to transfer all flow to the operating feed pump.

Reduce TDRFP speed to minimum. If the Preferred Method was used then before going below 2370 rpm transfer must be made to the Manual Speed Control Potentiometer to reduce speed to minimum.

Press the RFPT 1A trip push-button and verify the HP & LP Stop Valves close.

Shut the RFP 1A Discharge Valve, 1FW002A.

Direct Area Operator to shut CB009A/FW038A Page 6 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 6 Page 2 of 2

==

Description:==

Low Pressure Reactor Feed Pump (RFP) 1A Seal Water & Removal of RFP 1A From Service.

(Panel P680, Section 5002)

Time Position Applicants Actions or Behavior BOP

Monitors plant to ensure operations remain within established bands

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

Verifies the 1A RFP Turning Gear engages when the TDRFP stops.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: A TDRFP has been secured.

Page 7 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 7 Page 1 of 1

==

Description:==

Power Reduction To Remove RFP 1A From Service (Panel P680, Section 5001)

Initiation: Upon direction of the SRO Cues: Upon determination that RFP needs to be removed from service.

Time Position Applicants Actions or Behavior ATC Per, CPS 3005.01, Unit Power Changes.

Reduces power to at least 65% with Recirc Flow.

Closes the Flow Control Valves individually while maintaining the mismatch within spec.

Monitors paramaters as flow is reduced. (Power, FCV Position, Flow, MWe)

Conduct Plant Announcement on power reduction as directed.

Evaluates Power to Flow Map.

BOP

Monitors plant to ensure operations remain within established bands

Monitors control room panels and notifies the SRO of any unusual or unexpected conditions Conduct Plant Announcement on power reduction as directed.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Conducts a brief on the power reduction.

Institutes Transient Annunciator Response during the power reduction.

Calls RP & Chemistry about power reduction.

Contacts Reactor Engineer for concurrence on power reduction.

Terminus: Power reduction to at least 65% has been completed.

Page 8 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 8 Page 1 of 1

==

Description:==

LPCS/RHR A Water Leg Pump Trip Initiation: After A TDRFP has been secured, and upon direction of the Lead Examiner.

Cues: Annunciator 5063-3H, LPCS/RHR A Water Leg Pump Auto Trip Time Position Applicants Actions or Behavior BOP

Communicates annunciators to the SRO.

Refers to ARPs

Determines that LPCS/RHR A Water Leg Pump has tripped.

Dispatches Area Operators to check the pump and breaker.

Dispatches Area Operator to pull control power fuses on LPCS and RHR A Pumps.

ATC

Monitors reactor to ensure operations remain within established bands

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

SRO

Reviews Technical Specifications for applicabilty due to the Water Leg Pump trip.

Declares the following Technical Specification LCOs are affected:

1) 3.5.1, Action A.1, ECCS 1 subsystem inoperable, requires restoring low pressure subsystem to Operable status within 7 days.

2) 3.5.1, Action C.1, ECCS 2 subsystems inoperable, requires restoring one low pressure subsystem to Operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3) 3.6.1.7, Action A.1, Containment Spray, requires restoring subsystem to Operable status within 7 days.

4) 3.6.1.9, Action A.1, FW Leakage Control, requires restoring subsystem to Operable status within 30 days.

5) 3.6.2.3, Action A.1, Suppression Pool Cooling, requires restoring subsystem to Operable status within 7 days.

Directs pulling the control power fuses for LPCS and RHR A.

Pursues 1 time fuse replacement for the Water Leg Pump per OP-CL-108-101-1001,Section 3.8.1.

Conducts a brief on problem and status.

Terminus: Actions related to the Water Leg Pump trip have been completed.

Page 9 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 9, & 10 Page 1 of 3

==

Description:==

Seismic Event, Main Turbine High Vibration, ATWS, and SLC Squib Valves Fail to Fire.

Initiation: After Tech Spec call for Water Leg Pump trip, and upon direction of Lead Examiner.

Cues: Seismic Event Annunciators are received Time Position Applicants Actions or Behavior ATC

Acknowledges Seismic Event Annunciators and reports to the SRO.

Refers to the ARPs

Monitors reactor to ensure operations remain within established bands

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

Upon direction from the SRO checks the following key parameters:

1) Reactor power

2) RPV pressure

3) RPV level

4) Feed flow

5) Steam flow

6) Generator load

7) Turbine vibration Receives annunciator 5007-4D, High Vibr Turb Shaft (Pre Trip), or notices increasing turbine vibrations while monitoring panels.

Refers to CPS 3105.01, Turbine (TG, EHC, TS)

1) If vibration reaches 10 mils, immediately trip the turbine.

2) Verify turbine oil cooler outlet temperature 100°F to 120°F (may not do if decision is made to trip turbine earlier)

3) Places mode switch in shutdown and manually trips the Main Turbine.

Per CPS 4100.01, Reactor Scram:

Performs Scram Choreography

1) Mode Switch in Shutdown, Power is(Still above 5%)

2) Rod status is(rods still out)

3) Reactor power isand trend

4) Reactor pressure isand trend

5) Reactor level isand trend

Stabilize Reactor pressure 800 to 1065 psig or per directed band.

Calls Area Operator to bypass the CRD Pump Suction Filters.

Per EOP-1A, ATWS RPV Control:

Inhibit ADS.

Arm and Depress the Manual Scram Pushbuttons

Initiate ARI Critical Task

Carry out actions to insert control rods per 4411.08

1) Inserts control rods until locked out by Rod Pattern Controller

2) Directs that Rod Pattern Controller be bypassed.

3) Continues rod insertion Critical Task

Terminate and Prevent injection from Condensate/Feedwater.

Holds RPV Level in prescribed band (Band B: -162 in.(TAF) and -60 in.)

Page 10 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 9, & 10 Page 2 of 3

==

Description:==

Seismic Event, Main Turbine High Vibration, ATWS, and SLC Squib Valves Fail to Fire.

Time Position Applicants Actions or Behavior BOP Upon receiving the Seismic Event Annunciators:

Makes Plant Announcement as directed.

Monitors plant to ensure operations remain within established bands

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

Upon direction from the SRO checks the following key parameters:

1) Electrical distribution system integrity

2) Off-gas, Area Radiation & Process Radiation Monitors

3) Leak detection systems

4) Balance of plant annunciators Per CPS 4100.01, Reactor Scram:

Performs Scram Choreography by:

1) Making an announcement

Reactor Scram

MDRFP may start

Evacuate the RCIC room

Evacuate the Containment

2) Determine rod status and report to CRS Per EOP-1A, ATWS RPV Control:

Starts SLC and identifies that squib valves have not fired.

1) Per SRO direction initiates actions for Alternate Boron Injection per CPS 4411.10 Critical Task

Terminate and Prevent injection of HPCS, RCIC, LPCS, & LPCI to lower level

Holds RPV Level in prescribed band (Band B: -162 in.(TAF) and -60 in.)

Page 11 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 9, & 10 Page 3 of 3

==

Description:==

Seismic Event, Main Turbine High Vibration, ATWS, and SLC Squib Valves Fail to Fire.

Time Position Applicants Actions or Behavior SRO Seismic Event Annunciators are received, directing entry into CPS 4301.01, Earthquake Conducts brief on Seismic Event Directs Plant Announcement Enters Transient Annunciator Response Enters CPS 4301.01, Earthquake, and directs the following:

Determines that is is a valid seismic event.

Directs the ATC & BOP Operators to check the parameters IAW procedure.

Receives annunciator 5007-4D, High Vibr Turb Shaft (Pre Trip), or receives report from ATC Operator of increasing turbine vibrations.

Enters CPS 3105.01, Turbine (TG, EHC, TS)

Determines setpoint that turbine will be tripped.

Directs the ATC Operator to scram the reactor and trip the turbine at the determined setpoint.

Enters CPS 4100.01, Reactor Scram

Carries out Scram Choreography by performing an Update:

1) Entering EOP-1 and 8

2) Entering Scram Off-Normal Transient Annunciator Response is authorized Enters EOP-1A, ATWS RPV Control and directs:

Inhibit ADS Critical Task

insertion of control rods per CPS 4411.08

initiation of SLC per CPS 4411.10

initiation of Alternate Boron Injection per CPS 4411.10 Critical Task

terminate & Prevent Injection to lower level to reduce subcooling.

maintain RPV level in prescribed band (Band B: -162 in.(TAF) and -60 in.)

stabilization of RPV Pressure 800 to 1065 psig with Bypass Valves or SRVs.

Directs starting SLC Pump A to fire the Squib Valves.

Terminus:

RPV level stable and under control in required band

Reactor power is below 5%

Upon approval of lead examiner Page 12 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed

2. Reset to IC #95 for this scenario(Verify/Adjust Power to 73% with flow to match turnover).

3. Place simulator in RUN

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

5. Load lesson plan #9 for this scenario

6. Make sure CRD drive water D/P is in the expected range

7. Hotwell levels controllers are set at 50/45

8. Pressure set is at 922 psig.

9. Turn on and advance recorders

10. Hang OOS tags per turnover

11. Identify T/S issues associated with OOS and turnover

12. Verify simulator conditions match the turnover Page 13 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Event Triggers and Role Play Event #

1. SLC Pump A Oil Sightglass Empty

a. No Trigger

b. Roll play: Area Operator: Reports that inspection of A SLC Pump has revealed that the oil sightglass is empty and there is oil on the skid.

Area Operator: Responds to request to de-energize the breaker.

2. Shift Plant Service Water Pumps (WS)

a. No Trigger

b. Role play: Area Operator report Prestarts as being done, and 2 minutes after starting the pump that cooling water and seal water flows, and bearing oil levels are normal.

Area Operator: report 2 minutes after starting the pump that cooling water and seal water flows, and bearing oil levels are normal with normal leakoff.

3. Low Flow CW Pump 1C Brg. Seal Water

a. Remote Trigger 1 on the signal of Lead Examiner

b. Role play: Area Operator: when directed to investigate the problem, report back that the upper and lower motor bearing flow is 0 gpm and 0 psig with a marked vibration increase on CW Pump 1C. Other CW Pumps appear to be fine.

Area Operator: if directed to flush CW Pump C TW supply strainer 1TW01MC, report back in 2 minutes that supply strainer has been flushed, but flows and pressure are still the same.

4. A Reactor Water Cleanup Filter Demin Trips

a. Remote Trigger 2 on the signal of lead examiner

b. Role play: Area Operator: when directed to investigate the cause of the F-D System Trouble report back that the A filter demin is off service and the hold pump did not start.

5. Turbine LO Temperature Controller Failure

a. Remote Trigger 3 on the signal from lead examiner

b. Role play: Area Operator: when directed to check out the Turbine L.O. Coolers report back that everything appears to be fine (if problem has been corrected) or that Temperature Control Valve is closed (if problem has not been corrected).

6. Low Pressure Reactor Feed Pump (RFP) 1A Seal Water

a. Remote Trigger 4 on the signal from lead examiner

b. Role Play: Area Operator: when directed to swap RFP 1A seal water inlet filter to the standby filter report back in 3 minutes that filters have been shifted.

Area Operator: if seal water pressure is requested report that it is 300 psig and filter p is 40 psig, before and after the filters have been shifted.

Page 14 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1

7. Power Reduction To Remove RFP 1B From Service

a. No Trigger

b. Role play: Area Operator: iif directed to close the suction warming valve report that you will enlist support to get the valve shut.

Booth Operator: If contacted, report that CPS 9014.01 was completed 38 days ago.

8. LPCS/RHR A Water Leg Pump Trip

a. Remote Trigger 5 on the signal of the lead examiner.

b. Role play: Area Operator: when directed to check the breaker report back that the control power fuses have blown.

Area Operator: if directed to pull the control power fuses for the LPCS and RHR A Pumps report back after the override is put in that the fuses have been pulled.

Booth Operator: if called about 1 time fuse replacement,report that fuse will be changed.

9. Seismic Event, Main Turbine Trip, ATWS, and SLC Squib Valves Fail to Fire.

a. Remote Trigger 6 on the signal of the lead examiner, for seismic event.

b. Remote Trigger 7 on the signal of the lead examiner, for Main Turbine High Vibration.

c. Role play: Area Operator: if directed to perform a plant walkdown, no damage should be seen.

Booth Operator: if called, report that ground motion has been felt.

Booth Operator: if requested, show the seismic data sheet to the student, but do not allow him to take it. Show the sheet appropriate for the event (OBE, SSE). If they do not request the data until after the SSE then only show the SSE data.

Booth Operator: 5 minutes after the scram announcement ensure that dedicated individual reports to MCR as IMD.

10. Main Turbine High Vibration

a. Remote Trigger 7 on the signal of the lead examiner.

b. Role play: None

11. SLC Squib Valves Fail to Fire.

a. No Trigger.

b. Role play: None Page 15 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Seismic Data for OBE Detector EIN Peak Value 1VT-EM001 Vert 0.1673 E/W 0.1679 N/S 0.1688 1VT-EM002 Vert 0.1543 E/W 0.1567 N/S 0.1603 1VT-EM003 Vert 0.0879 E/W 0.0905 N/S 0.0932 1VT-EM004 Vert 0.0764 E/W 0.0787 N/S 0.0815 1VT-EM005 Vert 0.1625 E/W 0.1631 N/S 0.1634 Page 16 of 17

D-2, Dynamic Simulator Scenario 3 EXAM DATE: 7/11/05 ILT0401-1 Seismic Data for SSE Detector EIN Peak Value 1VT-EM001 Vert 0.2663 E/W 0.2669 N/S 0.2678 1VT-EM002 Vert 0.2543 E/W 0.2567 N/S 0.2603 1VT-EM003 Vert 0.1879 E/W 0.1905 N/S 0.1932 1VT-EM004 Vert 0.1764 E/W 0.1787 N/S 0.1815 1VT-EM005 Vert 0.2635 E/W 0.2641 N/S 0.2644 Page 17 of 17

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: 4 Operating Test No.: ILT0401-1 Examiners: ____________________________ Operators: ____________________

Initial Conditions:

93% power, steady state operation.

Thunderstorm Watch is in effect.

Service Air Compressor 1SA01C is OOS for Motor Bearing Replacement.

Turnover:

Continue steady state operation

Secure DG 1A from CPS 9080.01, DG 1A Operability - Manual and Quick Start Operability, by performing section 8.3.1 through 8.3.7.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Secure DG 1A from surveillance 2 Annunc TS-SRO Low Level DG Fuel Oil Storage Tank TS 3.8.3 3 LC08A C-BOP CRD Pump C001B Seal Leakage High 4 Override C-ATC CRD Accumulator Fault TS-SRO 5 Override C-BOP Auto Trip of C Cycle Condensate Pump 6 Override C-ATC Loss of Feedwater Heating & Recirc Motor B Brg Oil Level Low R-ATC 7 RP03 M-ALL Core Instabilities, Scram, Hydraulic Lock ATWS 8 LC08B C-BOP CRD Pump A will trip (recoverable with delay)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 2 9/13/2005

Appendix D Scenario Outline Form ES-D-1 Scenario No.: 4 Operating Test No.: ILT0401-1 Narrative Summary Event # Description

1. CPS 9080.01, DG 1A Operability - Manual and Quick Start Operability, has been completed. The BOP operator will secure DG 1A and place it back in standby.

2. Annunciator 5060-8B, Low Level DG Fuel Oil Storage Tank, is received requiring entry into Technical Specification 3.8.3, Action A.1, which requires restoring the level within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

3. Annunciator 5068-6C, CRD Pump C001B Seal Leakage High, is received. The BOP operator is required to shift to the A CRD Pump per CPS 3304.01.

4. Two accumulator faults will be received. The RO will have to determine which control rods have the accumulator faults. One fault will make a control rod inoperable requiring entry into Technical Specification 3.1.5, Action A, which requires declaring the control inoperable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

5. A trip of C Cycle Condensate (CY) Pump will be initiated requiring the BOP Operator to start a standby pump and verify that system pressure returns to normal.

6. The #6A FW Heater Inlet Valve will stroke closed. This will require entry into CPS 4005.01, Loss of Feedwater Heating. Reactor power will need to be adjusted to maintain power at or below the original power. Then annunciator 5003-5H, Recirc Mtr B Brg Oil Lvl Lo, is received with a motor bearing temperature increase to 212°F. This will require the RO to stop the RR Pump and enter CPS 4008.01, Abnormal Reactor Coolant Flow.

7. Core Instabilities will be seen requiring a Scram to be initiated and partial rod motion will be seen. Reactor power will still be above 5%.

8. The A CRD Pump will trip, but may be recovered by the BOP operator if attempted.

EOP 1A Critical tasks:

Initiate a scram when core instabilities are identified.

Initiate Standby Liquid Control to shutdown the reactor.

Terminate and Prevent Injection to lower level.

Page 2 of 2 9/13/2005

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 1 Page 1 of 1 Description Secure DG 1A From Surveillance (Panel P877, Section 5060)

Initiation: Completion of turnover.

Cues: Information from turnover.

Time Position Applicants Actions or Behavior BOP Per CPS 9080.01, Steps 8.3.1 through 8.3.9 secures DG 1A from surveillance:

Place/verify DG 1A Output Bkr Sync switch to the ON position.

Adjust DG 1A Output Frequency using the Governor control switch to 60.0 Hz.

Adjust DG 1A output voltage to 4200 V.

Return/Verify DG 1A Output Bkr Sync switch to OFF.

Perform cooldown of the DG.

Notify local operator of impending DG shutdown.

Stop DG 1A with DG 1A control switch.

At local panel 1PL12JA, place/verify Run-Idle switch, 1HS-DG291, to RUN.

Verify the following:

1) DG 1A Fuel Oil Day Tank level is at the overflow level (88.5%)

2) 1DO01PA, DG Fuel Oil Xfer Pmp 1A automatically stops.

3) AUTO START DG FUEL OIL XFER PUMP 1A [5060-4C] annunciator reset.

ATC

Monitors reactor to ensure operations remain within established bands

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

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: DG 1A is secured from the surveillance.

Page 1 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 2 Page 1 of 1

==

Description:==

Low Level DG Fuel Oil Storage Tank (Technical Specification Call, No Control Room Action)

Initiation: Following Shutdown of DG 1A Cues: Identified during securing of Diesel Generator or Annunciator 5060-8B, Low Level DG Fuel Oil Storage Tank, is received.

Time Position Applicants Actions or Behavior BOP

Communicates out of spec reading on DG surveillance or annunciator to SRO

Refers to the ARP if annunciator is received.

Monitors plant to ensure operations remain within established bands

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

ATC

Monitors reactor to ensure operations remain within established bands

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

SRO

Reviews Technical Specifications for applicabilty due to DG Fuel Oil Storage Tank Low Level.

Declares per Technical Specification LCO 3.8.3, Action A.1, that level needs to be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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

Terminus: The Technical Specification call has been made.

Page 2 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 3 Page 1 of 1

==

Description:==

CRD Pump C001B Seal Leakage High (Panel P601, Section 5068)

Initiation: Following resolution of Technical Specification call, and upon direction from the Lead Examiner.

Cues: Annunciator CPS 5068-6C, CRD Pump C001B Seal Leakage High, is received.

Time Position Applicants Actions or Behavior BOP

Communicates annunciator to SRO

Refers to the ARP.

Per CPS 5068-6C, CRD Pump C001B Seal Leakage High:

Swap running CRD Pumps per CPS 3304.01.

Per CPS 3304.01, Control Rod Hydraulic and Control (RD):

Direct Area Operator to Perform prestart local actions.

Direct Area Operator to shut/verify shut 1C11-F014A.

Start standby CRD Aux Oil Pump & allow to run for 1 minute.

Verify oil pressure is 3 psig.

Start standby CRD Pump A, 1C11-C001A.

Verify CRD Pump is running and Aux Oil Pump has auto stopped.

Verify gear increaser oil pressure is between 20 and 30 psig.

Slowly open 1C11-F014A, Pump A Stop Chk Discharge Valve.

Slowly throttle close 1C11-F014B until:

1) On-coming pump A amperage increases to > off-going pumps amperage.

2) 1C11-F014B reaches 25% open.

Stop off-going CRD Pump B, 1C11-C001B

Fully shut the off-going CRD Pump B discharge valve 1C11-F014B.

Direct Area Operator to perform post startup local actions.

Direct Area Operator to close 1C11-F017, Crossconnect valve.

ATC

Monitors reactor to ensure operations remain within established bands

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

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: CRD Pump C001A is in service.

Page 3 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 4 Page 1 of 1

==

Description:==

CRD Accumulator Fault (Panel P680, Center Section)

Initiation: After CRD Pump C001A is started, and upon direction of the Lead Examiner.

Cues: Annunciator CPS 5006-1H, Accumulator Trouble, is received.

Time Position Applicants Actions or Behavior ATC Note: Two accumulator faults will be received. Operator should perform the same actions for both. First rod: 48-21, Second rod: 24-33

Communicates annunciator to the SRO.

Refers to the ARP Per CPS 5006-1H, Accumulator Trouble:

Depress ACCUM FAULT button on P680 Center Section

Identify the associated rod

Acknowledge ACCUM FAULT to clear annunciator.

Direct Area Operator to check accumulator pressure.

When pressure is reported reports pressure to SRO Directs operator to recharge the accumulator to clear the alarm.

BOP

Monitors plant to ensure operations remain within established bands

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

Direct Area Operator to check accumulator pressure.

When pressure is reported reports pressure to SRO Directs operator to recharge the accumulator to clear the alarm.

SRO

Reviews Technical Specifications for applicabilty due to the Accumulator Faults.

Per Technical Specification LCO 3.1.5, Action A.1, declares that rod 24-33 scram time is slow, or declare the rod Inoperable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Refers to ORM 2.1.2, Action 3.1.2.1.a.

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: Accumulator Faults have been corrected.

Page 4 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 5 Page 1 of 1

==

Description:==

Auto Trip of C Cycle Condensate Pump (Panel P870, Section 5014)

Initiation: After Accumulator Faults have been corrected, and upon direction of the lead examiner.

Cues: Annunciator CPS 5014-2D, Low Press Cycled Cond Xfer Pumps Disch Hdr, is received.

Time Position Applicants Actions or Behavior BOP

Communicates annunciator to SRO.

Refers to the ARP.

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

Operate CY transfer pumps consistent with system demand to maintain normal header pressure per CPS 3208.01, Cycled/Makeup Condensate (CY/MC)

Operator may go to Section 8.2.2 directly or to 8.3.1 which will then direct him to 8.2.2.

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

IF Loss of CY was the result of a pump trip

THEN Refer to Section 8.2.2 for starting additional CY pumps

Start the desired standby pump.

Observe an increase in the pump discharge header pressure in the MCR.

ATC

Monitors reactor to ensure operations remain within established bands

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

Checks for excessive temperatures on CD Pumps.

SRO

Directs actions listed above.

Enforces OPS expectations and standards

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

Terminus: A standby CY Pump is running.

Page 5 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 6 Page 1 of 2

==

Description:==

Loss of Feedwater Heating & Recirc Motor B Brg Oil Level Low (Panel P680, Section 5002 & 5003, and Panel P870, Section 5016)

Initiation: After Standby CY has been started, and upon direction of Lead Examiner Cues: Feedwater Heater Level Alarms start being received.

Time Position Applicants Actions or Behavior ATC Per CPS 4005.01, Loss of Feedwater Heating:

Restores and maintains power at or below current power level and Within Figure 1, CPS Stability Control & Power/Flow Map, by adjusting RR flow with FCVs.

Annunciator CPS 5003-5H, Recirc Mtr B Brg Oil Lvl Lo, is received:

Monitors Pump/Motor A & B Temperature Recorder , 1B33-R601 for any increase in bearing temperature. (Bearing temperature on B RR Pump will Increase to >

212°F)

Upon reaching 212°F stops the B RR Pump.

Per CPS 4008.01 Abnormal Reactor Coolant Flow:

Shut 1B33-F067B, B RR Pump Discharge Valve

Review actions for continuing into single loop operation.

BOP Receives alarms associated with closure of 6A FW Heater Inlet Valve.

(CPS 5016-4F, Closed HP Htr 6A ES Chk Vlv, will be first alarm)

Communicates annunciators to SRO.

Refers to the ARP.

Identifies that 6A FW Htr Inlet Valve, 1FW008A, has closed.

Notifies SRO of status of the FW Heaters.

May attempt to open 6A FW Htr Inlet Valve upon SRO direction.

Monitors plant to ensure operations remain within established bands

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

Makes plant announcement on tripping B RR Pump due to High Brg Temps.

Sends Area Operator to 1PL05J Panel.

Page 6 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 6 Page 2 of 2 Time Position Applicants Actions or Behavior SRO Per CPS 4005.01, Loss of Feedwater Heating:

Directs the restoration of power at or below the current level, before the loss.

Verifies the following have not occurred which would necessitate a scram:

1) RESTRICTED ZONE is entered

2) Core instabilities are observed

3) FW drops by >100°F

Determines that following statement is not applicable because FULL FW Heating has not been lost.

IF Reactor power > 21.6% in single loop and Loss of FULL Feedwater Heating.

THEN Enter ITS LCO 3.2.1/3.2.2/3.2.3 actions.

May direct the reopening of 6A FW Htr Inlet Valve Per CPS 4008.01 Abnormal Reactor Coolant Flow:

Demands an official 3D Monicore Case

Lowers reactor power to 40% power using control rods

Reviews CPS 3005.01 for Single Loop Operations.

Calls for Reactor Engineer Enters Transient Annunciator Response Terminus: Initiation of Scram actions.

Page 7 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Operator Actions Event No.(s): 7&8 Page 1 of 3

==

Description:==

Core Instabilities, Scram, Hydraulic Lock ATWS, CRD Pump C001A Trips Initiation: After RR Pump has been tripped, and upon direction of Lead Examiner Cues: Core Instabilities are identified Time Position Applicants Actions or Behavior ATC Identifies that IRMs and APRMs are cycling due to Core Instabilities.

Critical Task

Places Mode Switch in Shutdown Per CPS 4100.01, Reactor Scram:

Performs Scram Choreography

1) Mode Switch in Shutdown, Power is(Still above 5%)

2) Rod status is(rods still out)

3) Reactor power isand trend

4) Reactor pressure isand trend

5) Reactor level isand trend

6) Any EOP Entry Conditions

Stabilize Reactor pressure 800 to 1065 psig or per directed band.

Per EOP-1A, ATWS RPV Control:

Arm and Depress the Manual Scram Pushbuttons

Initiate ARI

Directs performance of CPS 4410.00C012, Defeating ATWS Interlocks.

Carry out actions to insert control rods per 4411.08

1) Identifies that CRD Pump has tripped and rods can not be inserted manually until a CRD pump is regained.

2) If CRD Pump is started directs that Rod Pattern Controller be bypassed.

Critical Task 3) Continues rod insertion Terminate and Prevent injection from Condensate/Feedwater.

Page 8 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 7&8 Page 2 of 3 Time Position Applicants Actions or Behavior BOP Per CPS 4100.01, Reactor Scram:

Performs Scram Choreography by:

1) Making an announcement

Reactor Scram

MDRFP may start

Evacuate the RCIC room

Evacuate the Containment

2) Determine rod status and report to CRS Per EOP-1A, ATWS RPV Control:

Inhibits ADS Critical Tasks

Starts SLC

Terminate and Prevent injection of HPCS, RCIC, LPCS, & LPCI to lower level Identifies that CRD Pump C001A has tripped.

Operator may start CRD Pump per CPS 4411.08 or per CPS 3304.01:

Per CPS 4411.08, Alternate Control Rod Insertion

Close 1C11-F014A, CRD Pump A Disch Chk Vlv.

Start A CRD Aux Oil Pump, 1C11-C001A.

Start CRD Pump A, 1C11-C001A.

Open 1C11-F014A, CRD Pump A Disch Chk Vlv.

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

At 1H13-P601, take manual control of:

1) Adjust 1C11-R600, Flow Controller, to zero output.

2) 1C11-F002A, CRD Flow Control Valve.

Bypass the Suction Filters Isolate RR Pump Seal Filter D/P gauge.

Start A CRD Aux Oil Pump.

Allow Aux Oil Pump to run 1 minute prior to starting CRD Pump.

Close 1C11-F014A, CRD Pump A Disch Chk Vlv.

Verify oil pressure 3 psig.

Start CRD Pump A, 1C11-C001A.

Verify CRD Pump running, Aux Oil Pump has stopped.

Open 1C11-F014A, CRD Pump A Disch Chk Vlv.

Using 1C11-R600, open 1C11-F002A, CRD Flow Control Valve to obtain a flow rate of 41 to 49 gpm as indicated on C11-R606.

Adjust tape setpoint to null out deviation

Place flow controller 1C11-R600 in automatic mode.

Restore RR Seal filter D/P gauge.

Un-bypass the CRD Suction Filters.

Directs Area Operator to DG and ECCS Rooms for inspections.

Page 9 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Event No.(s): 7&8 Page 3 of 3 Time Position Applicants Actions or Behavior SRO Receives report from ATC Operator of Core Instabilities Per CPS 4005.01, Loss of Feedwater Heating:

Any of the following would necessitate a scram:

1) RESTRICTED ZONE is entered

2) Core instabilities are observed

3) FW drops by >100°F Enters CPS 4100.01, Reactor Scram

Carries out Scram Choreography by performing an Update:

1) Entering EOP-1

2) Entering Scram Off-Normal Critical Task Directs the ATC Operator to place mode switch in shutdown if not already completed.

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

Insertion of control rods per CPS 4411.08

Inhibit ADS.

Critical Tasks

Initiation of SLC per CPS 4411.10

Terminate & Prevent Injection to lower level to reduce subcooling. (May direct RCIC & HPCS then FW and then come back to the Low Pressure systems.)

Maintain RPV level in prescribed band (Level Band B: -162 in.(TAF) and -60 in.)

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

Directs the restart of A CRD Pump.

Terminus:

RPV level and pressure are stable

Reactor power is below 5%

Upon approval of lead examiner Page 10 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Simulator Operator Instructions Initial Setup

1. Verify daily lamp test completed

2. Reset to IC #96 for this scenario(Verify/Adjust Power to 93% with flow to match turnover).

3. Place simulator in RUN

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

5. Load lesson plan #10 for this scenario

6. Make sure CRD drive water D/P is in the expected range

7. Hotwell levels controllers are set at 50/45

8. Pressure set is at 926 psig.

9. Turn on and advance recorders

10. Hang OOS tags per turnover

11. Identify T/S issues associated with OOS and turnover

12. Verify simulator conditions match the turnover

13. Provide copies of the following:

CPS 9080.01, Rev 50b, Complete through Step 8.2.15.2

CPS 9080.01D001, Rev 43d, Section A Complete through 8.2.13.8.1 (Fill in a Start time and an End Time to indicate > 60 minute run just before turnover) Section B complete.

CPS 3506.01C005, Rev 1, Completed

CPS 3506.01D001, Rev 0e, (Should be with Area Operator)

Page 11 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1 Event Triggers and Role Play Event #

1. Secure DG 1A From Surveillance

a. Remote Trigger 8 takes diesel to idle.

b. Roll play: Area Operator: When requested to place/verify the Run-Idle switch, 1HS-DG291, after triggering remote, report that it is in RUN.

Area Operator: If requested report the following, oil pumps are running, oil temperature is 145 °F, Day Tank Level is 88.5%. Room temperature is ambient.

2. Low Level DG Fuel Oil Storage Tank

a. Remote Trigger 1 on signal of Lead Examiner

b. Role play: Area Operator if requested to check out DG Fuel Oil Storage Tank, report back that there appears to be no problem with the tank.

3. CRD Pump C001B Seal Leakage High

a. Remote Trigger 2 on the signal of Lead Examiner

b. Role play: Area Operator: if directed to investigate alarm, report that water is spraying around seal.

Area Operator: when directed to perform local actions report back that local actions have been performed and pump is running fine. If directed to shut 1C11-F017 report back that it is shut.

Booth Operator: If information is requested as to how long A CRD Pump has been shutdown report that it was shutdown 2 days ago.

4. CRD Accumulator Fault

a. Remote Trigger 3 on the signal of lead examiner

b. Role play: Area Operator: when directed to verify accumulator pressure on rod 48-21, report back that pressure is 1580 psig.

Area Operator: when directed to verify accumulator pressure on rod 24-33, report back that pressure is 1540 psig.

Surveillance Coord.: If information is requested as to whether rod 24-33 was within the limits during the last scram time surveillance, report that it was.

5. Auto Trip of C Cycle Condensate Pump

a. Remote Trigger 4 on the signal from lead examiner

b. Role play: Area Operator: If directed to check out C Cycle Condensate Pump, report back that the pump has a broken coupling. Responds to MCR directions for starting standby pump.

6. Loss of Feedwater Heating & Recirc Motor B Brg Oil Level Low

a. Remote Trigger 5 on the signal from lead examiner

b. Role Play: Area Operator: If dispatched to 1PL05J respond to requests from MCR. Controllers will be tracking conditions seen in the MCR (Operating as expected).

Page 12 of 13

D-2, Dynamic Simulator Scenario 4 EXAM DATE: 7/11/05 ILT0401-1

7. Recirc Motor B Brg Oil Level Low

a. Remote Trigger 6 on the signal from lead examiner

b. Role Play: None

8. Core Instabilities, Scram, Hydraulic Lock ATWS

a. No Triggers

b. Role play: Booth Operator: 5 minutes after the scram announcement ensure that dedicated individual reports to MCR as IMD.

9. CRD Pump C001A Trips

a. Remote Trigger 7 on the signal from lead examiner

b. Role Play: Area Operator: respond to requests from the MCR.

Page 13 of 13

Overview Makeup/Reject: All CPs except J are in service. RO train #1 & 2 are in-service in auto to WD ECCS: RHR A, B, C, LPCS and HPCS are Operable. RCIC is Operable SDC: N/A Electrical: 6.9 KV 1A & 1B and 4.16 1A &1B on UAT, 4160 Volt Busses 1A1, 1B1 & 1C1 are being supplied by RAT Ventilation:

Radwaste: FP/FP 1B in service. 1WF Evap is in Hot Standby. A and B RT F/D are in service.

Plant Status On Line Risk Green Reactor Operational Condition: Mode 1 Total Core Flow: __61.2___ mlb/hr FCV Position: A: ___40____% B: __38____%

Reactor Power _93___% (<=100%) _3248__ MWt (<=3473) _859__ Mwe Xenon: Stable RPV Level _33.7_ in Narrow Range RPV Pressure _1021__ psi (< 1045)

In service SDC loop None MODE 1 Containment Suppression Pool Temperature: _74.8_ F (<=93.1 F)

Suppression Pool Level _19.2_ ft (19 ft 0 to 19 ft 5 in)

Drywell Pressure _0.5__ psi (0 to 1 psig)

Drywell to Containment dp: _0.5__ psi >=-.02 psid to <=1.0 psid Drywell Avg Air Temperature: _____ F (<=146.53 F)

Secondary Containment: _0.45_ in WG (>= 0.25 in WG vacuum)

BOP Plant Chemistry Condenser Vacuum: _26.1_ in Hg CPI (goal < 1.1): 1.00 Off - Gas Flow: _____ scfm Reactor Sulfates (goal < 2) 1.31 ppb Condensate Temperature: _110_ F Reactor Chlorides: 0.51 ppb Generator Reactive Load: _280_MVARS FW Iron (goal < 2.1) 0.85 ppb Protected Equip: If there is protected equipment, it is listed here. If necessary attach the contingency plan.

Comments: This is to be the last page on the approved simulator exercise so that it can be easily torn off and given to the students. Include here the turnover items, weather, time of day, rod positions etc.

From Excellence in Human Performance Leaders reinforce desired jobsite behaviors (Handbook page 17)

Participate in training program activities.

Leaders monitor and provide feedback to improve training program quality as well as to coach and reinforce individuals who meet or exceed behavior expectations and Standards of performance. During training activities, leaders guide workers on how actions or inactions influence reactor safety and on the potential consequences of mistakes. They give particular attention to recognizing error-likely situations and flawed defenses during tasks important to nuclear safety

Turnover This page contains the Turnover information not found in the Overview page.

1. Power, xenon and time in life Power level is 93% steady state power

2. Status of Tagged Out Equipment Service Air Compressor 1SA01C is OOS for bearing replacement

3. Shift conditions Day Shift Today

4. Weather Conditions Thunderstorm watch is in effect, In CPS 4302.01, Tornado/High Winds, Announcements are not being made.

5. Thermal Limit Problems or concerns

6. LCOs in effect

7. Surveillances in progress CPS 9080.01, DG 1A Operability - Manual and Quick Start Operability

8. Evolutions planned for the shift

9. Risk Levels

10. Other

ML052560368

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