Text

Initial Exam - 07/2002 - Operating Exam
	ML030140496
Person / Time
Site:	Callaway
Issue date:	07/29/2002
From:	Gody A; Operations Branch IV
To:	Randolph A; Union Electric Co
References
	50-483/02-301 50-483/02-301
	Download: ML030140496 (217)
	v • d • e

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A1 RO/SRO K/A NO: G 2.1.7 COMPLETION TIME: 10 MINUTES K/A RATING: 3.7/4.4 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE IF ROD INSERTION LIMIT HAS BEEN EXCEEDED The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

OSP-ZZ-00001, Control Room Shift and Daily Log Readings and Channel Checks, Rev 37 CURVE BOOK, COLR, Figure 2, Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation, Rev 0 TOOLS/EQUIPMENT: Attachment 3 of OSP-ZZ-00001 Calculator FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A1 RO/SRO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. A FAILURE IN THE MAIN GENERATOR PROTECTION CIRCUIT HAS CAUSED A TURBINE RUNBACK. REACTOR POWER HAS BEEN STABILIZED AT APPROXIMATELY 50%. THE ROD INSERTION LIMIT MONITOR WAS DECLARED INOPERABLE 30 MINUTES AGO.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO PERFORM OSP-ZZ-00001, CONTROL ROOM SHIFT AND DAILY LOG READINGS AND CHANNEL CHECKS, ATTACHMENT 3, INOPERABLE ROD INSERTION LIMIT MONITOR.

NI READINGS ARE AS FOLLOWS:

SE NI-41B 50.0% SE NI-42B 49.9%

SE NI-43B 49.8% SE NI-44B 50.3%

DRPI READINGS ARE AS FOLLOWS:

CB "A" CB "B" CB "C" CB "D" Group 1 Rods 226 226 155 40 Group 2 Rods 226 226 155 40 TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL DETERMINE THAT CONTROL BANKS "C" & "D" ARE BELOW THE REQUIRED ROD INSERTION LIMITS.

START TIME:

STOP TIME:

PAGE 1 of 4

ADMIN JPM NO: ILE-2002-A1 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED STEPS MAY BE PREFORMED IN ANY ORDER S U

2. CANDIDATE OBTAINS CANDIDATE SHOULD OBTAIN CORRECT CURVE BOOK CURVE BOOK COLR FIGURE 2 Comments:

FIGURE HAND CANDIDATE COPY OF CURVE BOOK COLR FIGURE 2 AFTER THEY DEMONSTRATE THE ABILITY TO LOCATE (GREEN SHEET)

S U

3. DETERMINE REACTOR CANDIDATE SHOULD POWER LEVEL DETERMINE REACTOR Comments:

POWER TO BE 50%

CRITICAL STEP PAGE 2 of 4

ADMIN JPM NO: ILE-2002-A1 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. DETERMINE ROD CANDIDATE SHOULD INSERTION LIMIT FOR DETERMINE ROD INSERTION Comments:

CONTROL BANK "A" LIMIT FOR CONTROL BANK "A" IS >225 STEPS AND RECORD AS SAT ON ATTACHMENT 3 S U

5. DETERMINE ROD CANDIDATE SHOULD INSERTION LIMIT FOR DETERMINE ROD INSERTION Comments:

CONTROL BANK "B" LIMIT FOR CONTROL BANK "B" IS >225 STEPS AND RECORD AS SAT ON ATTACHMENT 3 S U

6. DETERMINE ROD CANDIDATE SHOULD INSERTION LIMIT FOR DETERMINE ROD INSERTION Comments:

CONTROL BANK "C" LIMIT FOR CONTROL BANK "C" IS >160 STEPS AND RECORD AS UNSAT ON ATTACHMENT 3

CRITICAL STEP PAGE 3 of 4

ADMIN JPM NO: ILE-2002-A1 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

7. DETERMINE ROD CANDIDATE SHOULD INSERTION LIMIT FOR DETERMINE ROD INSERTION Comments:

CONTROL BANK "D" LIMIT FOR CONTROL BANK "D" IS >45 STEPS AND RECORD AS UNSAT ON ATTACHMENT 3 S U

8. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 4

EXAM KEY OSP-ZZ-00001 Rev. 6 INOPERABLE ROD INSERTION LIMIT MONITOR PERSON PERFORMING (PRINT) INITIALS TIME / DATE PERSON PERFORMING (PRINT) INITIALS TIME / DATE PERSON PERFORMING (PRINT) INITIALS TIME / DATE PERSON PERFORMING (PRINT) INITIALS TIME / DATE THE POSITION OF EACH CONTROL BANK SHALL BE DETERMINED TO BE WITHIN THE INSERTION LIMIT AT LEAST ONCE PER FOUR HOURS WHEN THE ROD INSERTION LIMIT MONITOR IS INOPERABLE. FSAR 16.1.3.4 NOTE: INCLUDE THIS ATTACHMENT WITH ATTACHMENT 1 WHEN REQUIRED ROD INSERTION LIMIT MONITOR DETERMINED TO BE TIME / DATE INOPERABLE:

VERIFY DRPI ABOVE INSERTION LIMITS PER COLR FIG. 2 AND RECORD SAT OR UNSAT FOR EACH CONTROL BANK.

Reference Time Bank A Bank B Bank C Bank D Initials Time SAT SAT UNSAT UNSAT T + 4 hrs T + 8 hrs T + 12 hrs T + 16 hrs T + 20 hrs ROD INSERTION LIMIT MONITOR ¨ NO, MONITOR RETURNED TO SERVICE: CONTINUED

¨ YES DATE / TIME / INITIALS File Code O120.0054 Page 1 of 1 ATTACHMENT 3 EXAM KEY

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. A FAILURE IN THE MAIN GENERATOR PROTECTION CIRCUIT HAS CAUSED A TURBINE RUNBACK. REACTOR POWER HAS BEEN STABILIZED AT APPROXIMATELY 50%. THE ROD INSERTION LIMIT MONITOR WAS DECLARED INOPERABLE 30 MINUTES AGO.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO PERFORM OSP-ZZ-00001, CONTROL ROOM SHIFT AND DAILY LOG READINGS AND CHANNEL CHECKS, ATTACHMENT 3, INOPERABLE ROD INSERTION LIMIT MONITOR.

NI READINGS ARE AS FOLLOWS:

SE NI-41B 50.0% SE NI-42B 49.9%

SE NI-43B 49.8% SE NI-44B 50.3%

DRPI READINGS ARE AS FOLLOWS:

CB "A" CB "B" CB "C" CB "D" Group 1 Rods 226 226 155 40 Group 2 Rods 226 226 155 40

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A2 RO/SRO K/A NO: G 2.1.25 COMPLETION TIME: 15 MINUTES K/A RATING: 2.8/3.1 JOB TITLE: URO/SRO REVISION: APRIL 30, 2002 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE DILUTION REQUIREMENTS The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

Curve Book, Figure 5-2, Differential Boron Worth (HZP) Callaway Nuclear Plant Cycle 12 ,

Rev 12 Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs (Boron Dilution),

Rev 01 TOOLS/EQUIPMENT: Calculator FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A2 RO/SRO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3, 557°F, CYCLE 12 WITH CORE AGE AT MOL (BURNUP OF 10,000 MWD/MTU). THE SHUTDOWN BANKS HAVE BEEN PULLED AND THE ESTIMATED CRITICAL POSITION (ECP) HAS BEEN CALCULATED.

THE ECP ASSUMED XENON FREE CONDITION WITH A CRITICAL ROD HEIGHT OF 100 STEPS ON CONTROL BANK "D". THE ECP REQUIRES A POSITIVE REACTIVITY ADDITION OF 2,800 PCM BY DILUTION TO ACHIEVE THE REQUIRED CRITICAL BORON CONCENTRATION. PRESENT RCS BORON CONCENTRATION IS 1600 PPM. PRESSURIZER LEVEL IS AT 25%.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO CALCULATE THE DILUTION VOLUME REQUIRED (GALLONS)

TO ACHIEVE THE REQUIRED CRITICAL BORON CONCENTRATION. THE DILUTION SHOULD BE CALCULATED USING THE DILUTION EQUATION INSTEAD OF USING THE DILUTION NOMOGRAPH TO ENSURE GREATER ACCURACY.

Notes: THE USE OF THE PC NUCLEAR DESIGN REPORT IS NOT ALLOWED.

TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL HAVE CALCULATED THE REQUIRED DILUTION VOLUME OF 15,069 + 430 GALLONS (14,639 - 15,499 GALLONS).

START TIME:

STOP TIME:

PAGE 1 of 4

ADMIN JPM NO: ILE-2002-A2 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED S U

2. CANDIDATE OBTAINS CANDIDATE SHOULD OBTAIN CORRECT CURVE BOOK CURVE BOOK FIGURES 5-2 Comments:

FIGURES AND 7-5 HAND CANDIDATE COPY OF CURVE BOOK FIGURES AFTER THEY DEMONSTRATE THE ABILITY TO LOCATE (GREEN SHEETS)

S U

3. CANDIDATE SHOULD CANDIDATE SHOULD REFER DETERMINE THE TO CURVE BOOK FIGURE 5-2, Comments:

DIFFERENTIAL BORON DIFFERENTIAL BORON WORTH (DBW) FOR HOT WORTH (HZP) AND ZERO POWER (HZP) DETERMINE THE DBW TO BE

-8.1 + 0.2 PCM/PPM

CRITICAL STEP PAGE 2 of 4

ADMIN JPM NO: ILE-2002-A2 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. CANDIDATE SHOULD PPMBoron = Reactivity ÷ DBW CALCULATE THE = +2,800 PCM ÷ -8.1 PCM/PPM Comments:

REQUIRED BORON = -345.7 + 8.7 PPM CONCENTRATION CHANGE S U

5. CANDIDATE SHOULD PPMBoronFinal = PPMBoronInitial +

DETERMINE THE FINAL PPMBoron Comments:

BORON CONCENTRATION PPMBoronFinal = 1600 PPM - 345.7 PPM PPMBoronFinal = 1254.3 + 8.7 PPM S U

6. CANDIDATE SHOULD V = (M ÷ 8.33) [ln (Ci ÷ Cf)]

DETERMINE THE Comments:

REQUIRED DILUTION V = (515676 ÷ 8.33) [ln (1600 ÷ VOLUME USING 1254.3)]

EQUATION ON FIGURE 7-5 V = 61905.9 [ln 1.2756]

V = 15,069 + 430 GALLONS V = 14,639 - 15,499 GALLONS

CRITICAL STEP PAGE 3 of 4

ADMIN JPM NO: ILE-2002-A2 RO/SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

7. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3, 557°F, CYCLE 12 WITH CORE AGE AT MOL (BURNUP OF 10,000 MWD/MTU). THE SHUTDOWN BANKS HAVE BEEN PULLED AND THE ESTIMATED CRITICAL POSITION (ECP) HAS BEEN CALCULATED.

THE ECP ASSUMED XENON FREE CONDITION WITH A CRITICAL ROD HEIGHT OF 100 STEPS ON CONTROL BANK "D". THE ECP REQUIRES A POSITIVE REACTIVITY ADDITION OF 2,800 PCM BY DILUTION TO ACHIEVE THE REQUIRED CRITICAL BORON CONCENTRATION. PRESENT RCS BORON CONCENTRATION IS 1600 PPM. PRESSURIZER LEVEL IS AT 25%.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO CALCULATE THE DILUTION VOLUME REQUIRED (GALLONS)

TO ACHIEVE THE REQUIRED CRITICAL BORON CONCENTRATION. THE DILUTION SHOULD BE CALCULATED USING THE DILUTION EQUATION INSTEAD OF USING THE DILUTION NOMOGRAPH TO ENSURE GREATER ACCURACY.

Notes: THE USE OF THE PC NUCLEAR DESIGN REPORT IS NOT ALLOWED.

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A3 RO K/A NO: G 2.2.27 COMPLETION TIME: 15 MINUTES K/A RATING: 2.6 JOB TITLE: URO REVISION: MAY 14, 2002 DUTY: ADMINISTRATIVE TASK TITLE: CALCULATE RHR PUMP RUN TIME FOR FLOOD UP The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

OTS-KE-00017, FILLING THE REFUELING POOL, REV 11 TANK DATA BOOK, TDB-001 PAGE 74, REV 36 FSAR 16.1.2.5, BORATED WATER SOURCES - SHUTDOWN TOOLS/EQUIPMENT: CALCULATOR FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A3 RO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 6. THE CREW IS PREPARING TO FILL THE REFUELING POOL FROM THE RWST USING THE "A" RHR PUMP PER OTS-KE-00017, FILLING THE REFUELING POOL. THE RWST LEVEL IS CURRENTLY AT 93.6%.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO CALCULATE THE MAXIMUM TIME THE "A" RHR PUMP CAN BE RUN FOR FILLING THE REFUELING POOL BEFORE THE RWST WILL BE AT THE MINIMUM VOLUME REQUIRED BY FSAR 16.1.2.5. ASSUME THAT THE "A" RHR PUMP FLOW REMAINS CONSTANT AT 2,100 GPM THROUGHOUT THE FILLING EVOLUTION AND THAT NO MAKEUP IS PERFORMED ON THE RWST.

Notes:

TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL HAVE CALCULATED THE MAXIMUM RUN TIME FOR THE "A" RHR PUMP IS 161.2 MINUTES WITHIN A TOLERANCE OF -5% (153.1 - 161.2 MINUTES).

START TIME:

STOP TIME:

PAGE 1 of 4

ADMIN JPM NO: ILE-2002-A3 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED S U

2. CANDIDATE SHOULD CANDIDATE SHOULD REFER REFER TO FSAR 16.1.2.5 TO FSAR 16.1.2.5 AND TANK Comments:

AND TANK DATA BOOK DATA BOOK PAGE 74 FOR PAGE 74 FOR RWST RWST VOLUMES VOLUMES HAND CANDIDATE COPY OF FSAR 16.1.2.5 AND TANK DATA BOOK PAGE 74 AFTER THEY DEMONSTRATE THE ABILITY TO LOCATE (GREEN SHEETS)

S U

3. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE THE DETERMINE FROM PAGE 74 Comments:

CURRENT RWST VOLUME OF THE TANK DATA BOOK IN GALLONS USING THE THAT 93.6% IS EQUIVALENT TANK DATA BOOK TO 394,000 GALLONS

CRITICAL STEP PAGE 2 of 4

ADMIN JPM NO: ILE-2002-A3 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE THE DETERMINE THE MINIMUM Comments:

MINIMUM RWST VOLUME RWST VOLUME FROM FSAR IN GALLONS FROM FSAR 16.1.2.5 IS 55,416 GALLONS 16.1.2.5 S U

5. CANDIDATE SHOULD Volume = VolumeInitial - VolumeFinal DETERMINE HOW MUCH Comments:

BORATED WATER CAN Volume = 394,000 - 55,416 BE PUMPED FROM THE RWST TO THE Volume = 338,584 GALLONS REFUELING POOL S U

6. CANDIDATE SHOULD Time = Volume ÷ Pump Flowrate DETERMINE HOW LONG Comments:

THE "A" RHR PUMP CAN Time = 338,584 ÷ 2,100 BE RUN PRIOR TO REACHING THE FSAR Time = 161.2 MINUTES MINIMUM LIMIT FOR RWST VOLUME Tolerance Of -5% = -8.1 Time = 161.2 - 8.1 = 153.1 Time = 153.1 - 161.2 MINUTES

CRITICAL STEP PAGE 3 of 4

ADMIN JPM NO: ILE-2002-A3 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

7. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 6. THE CREW IS PREPARING TO FILL THE REFUELING POOL FROM THE RWST USING THE "A" RHR PUMP PER OTS-KE-00017, FILLING THE REFUELING POOL. THE RWST LEVEL IS CURRENTLY AT 93.6%.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO CALCULATE THE MAXIMUM TIME THE "A" RHR PUMP CAN BE RUN FOR FILLING THE REFUELING POOL BEFORE THE RWST WILL BE AT THE MINIMUM VOLUME REQUIRED BY FSAR 16.1.2.5. ASSUME THAT THE "A" RHR PUMP FLOW REMAINS CONSTANT AT 2,100 GPM THROUGHOUT THE FILLING EVOLUTION AND THAT NO MAKEUP IS PERFORMED ON THE RWST.

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A3 SRO K/A NO: G 2.2.12 COMPLETION TIME: 15 MINUTES K/A RATING: 3.4 JOB TITLE: SRO REVISION: MAY 1, 2002 DUTY: ADMINISTRATIVE TASK TITLE: DETERMINE ACTIONS FOR VALVE STROKE TEST The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

OSP-EC-V001A, FUEL POOL HEAT EXCHANGER "A" SHELL SIDE OUT ISO VALVE INSERVICE TEST, REV 4 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A3 SRO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. OSP-EC-V001A, FUEL POOL HEAT EXCHANGER "A" SHELL SIDE OUT ISO VALVE INSERVICE TEST HAS BEEN PERFORMED. THE TEST RESULTS WERE OUTSIDE THE NORMAL RANGE. THE SHIFT SUPERVISOR DIRECTED THE IMMEDIATE RETEST OF THE VALVE. THE RESULTS WERE THE SAME FOR THE SECOND TEST.

Initiating Cues: YOU ARE THE CONTROL ROOM SUPERVISOR AND HAVE BEEN GIVEN ATTACHMENT 1 FOR REVIEW. YOU ARE TO DETERMINE WHAT ACTIONS SHOULD BE TAKEN BASED ON THE RESULTS OF THIS SURVEILLANCE.

TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL DETERMINE THAT THE DATA IS TO BE ANALYZED WITHIN 96 HOURS TO VERIFY THAT THE NEW STROKE TIME REPRESENTS ACCEPTABLE VALVE OPERATION OR THE VALVE SHALL BE DECLARED INOPERABLE.

START TIME:

STOP TIME:

PAGE 1 of 3

ADMIN JPM NO: ILE-2002-A3 SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED S U

2. CANDIDATE SHOULD CANDIDATE SHOULD REVIEW THE TEST REVIEW THE TEST RESULTS Comments:

RESULTS ON ON ATTACHMENT 1 ATTACHMENT 1 S U

3. CANDIDATE SHOULD CANDIDATE SHOULD OBTAIN A COPY OF DETERMINE THAT THE OPEN Comments:

OSP-EC-V001A, FUEL STROKE TIME IS LESS THAN POOL HEAT EXCHANGER THE MAXIMUM ALLOWED "A" SHELL SIDE OUT ISO STROKE TIME, BUT OUTSIDE VALVE INSERVICE TEST THE NORMAL RANGE FOR AND REVIEW THE BOTH THE 1ST AND 2ND TESTS ACCEPTANCE CRITERIA

CRITICAL STEP PAGE 2 of 3

ADMIN JPM NO: ILE-2002-A3 SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE WHAT DETERMINE THE Comments:

ACTIONS SHOULD BE FOLLOWING:

TAKEN BASED ON THE RESULTS OF THIS THE DATA IS TO BE SURVEILLANCE ANALYZED WITHIN 96 HOURS TO VERIFY THAT THE NEW STROKE TIME REPRESENTS ACCEPTABLE VALVE OPERATION OR THE VALVE SHALL BE DECLARED INOPERABLE S U

5. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. OSP-EC-V001A, FUEL POOL HEAT EXCHANGER "A" SHELL SIDE OUT ISO VALVE INSERVICE TEST HAS BEEN PERFORMED. THE TEST RESULTS WERE OUTSIDE THE NORMAL RANGE. THE SHIFT SUPERVISOR DIRECTED THE IMMEDIATE RETEST OF THE VALVE. THE RESULTS WERE THE SAME FOR THE SECOND TEST.

Initiating Cues: YOU ARE THE CONTROL ROOM SUPERVISOR AND HAVE BEEN GIVEN ATTACHMENT 1 FOR REVIEW. YOU ARE TO DETERMINE WHAT ACTIONS SHOULD BE TAKEN BASED ON THE RESULTS OF THIS SURVEILLANCE.

OSP-EC-V001A Rev. 004 VALVE TEST DATA SHEET PERSON PERFORMING INITIAL REACTOR OPERATOR RO DATE STARTED JULY 31, 2002 BALANCE OF PLANT OPERATOR BOP DATE COMPLETED JULY 31, 2002 MAX MAX FULL FULL AS INIT INIT OBSERVED NORMAL STROKE OPEN CLOSE STROKE STROKE RESTOR VALVE FOUND REM LOCAL STROKE TIME(S) TIME RANGE (S) STR STR REM LOCAL RESTOR RESTOR INDEP POS POS POS O C O C TIME(S) TIME(S) POS POS POS VERIF VERIF ECHV0011 OPEN OPEN OPEN 46.1 56.1 49.3-62.9 49.3-62.9 62.9 62.9 CLOSED CLOSED OPEN RO BOP 46.1* 56.1*

Indicates data from second test.

M&TE ID NUMBERS RECORDED ON STS COMPLETION FORMS SW-2001-OP Page 1 of 1 ATTACHMENT 1

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A4 RO K/A NO: G 2.3.10 COMPLETION TIME: 15 MINUTES K/A RATING: 2.9 JOB TITLE: URO REVISION: MAY 1, 2002 DUTY: ADMINISTRATIVE TASK TITLE: CALCULATE STAY TIME The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

APA-ZZ-01000, CALLAWAY PLANT HEALTH PHYSICS PROGRAM, REV 16 TOOLS/EQUIPMENT: CALCULATOR FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A4 RO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: THE CONTROL ROOM SUPERVISOR HAS REQUESTED YOU TO HANG WPA IN AN AREA WHERE THE KNOWN RADIATION DOSE RATE IS 425 mrem/hr. YOUR CURRENT YEAR EXPOSURE HISTORY ACCORDING TO YOUR NRC FORM 4 IS AS FOLLOWS:

COMMITTED DOSE EQUIVALENT (CDE) 20 mrem

COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) 100 mrem

DEEP-DOSE EQUIVALENT (DDE) 200 mrem

EYE DOSE EQUIVALENT (LDE) 15 mrem

SHALLOW DOSE EQUIVALENT (SDE) 10 mrem Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO DETERMINE YOUR MAXIMUM STAY TIME IN THE CAUTION HIGH RADIATION AREA WHILE HANGING THE WPA BEFORE EXCEEDING THE CALLAWAY PLANT ADMINISTRATIVE DOSE LIMIT FOR WHOLE BODY TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE).

Notes:

TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL HAVE CALCULATED THE MAXIMUM STAY TIME FOR HANGING THE WPA IS 4.0 HOURS WITHIN A TOLERANCE OF -5% (3.8 - 4.0 HOURS).

START TIME:

STOP TIME:

PAGE 1 of 4

ADMIN JPM NO: ILE-2002-A4 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED S U

2. CANDIDATE SHOULD CANDIDATE SHOULD REFER REFER TO APA-ZZ-01000, TO APA-ZZ-01000, CALLAWAY Comments:

CALLAWAY PLANT PLANT HEALTH PHYSICS HEALTH PHYSICS PROGRAM PROGRAM S U

3. CANDIDATE SHOULD TEDE = DDE + CEDE DETERMINE THEIR Comments:

CURRENT TOTAL TEDE = 200 mrem + 100 mrem EFFECTIVE DOSE EQUIVALENT (TEDE) TEDE = 300 mrem

CRITICAL STEP PAGE 2 of 4

ADMIN JPM NO: ILE-2002-A4 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE THE DETERMINE THE CALLAWAY Comments:

CALLAWAY PLANT PLANT ADMINISTRATIVE ADMINISTRATIVE DOSE DOSE LIMIT FOR WHOLE LIMIT FOR WHOLE BODY BODY TEDE IS 2,000 mrem TEDE S U

5. CANDIDATE SHOULD EXPOSURE MARGIN =

DETERMINE THEIR CALLAWAY PLANT Comments:

EXPOSURE MARGIN ADMINISTRATIVE DOSE LIMIT FOR WHOLE BODY TEDE MINUS THEIR CURRENT TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)

Margin = 2,000 mrem - 300 mrem Margin = 1,700 mrem S U

6. CANDIDATE SHOULD Stay Time = Margin ÷ Dose Rate DETERMINE THEIR Comments:

MAXIMUM STAY TIME IN Stay Time = 1,700 mrem ÷ 425 THE CAUTION HIGH mrem/hr RADIATION AREA Stay Time = 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Tolerance Of -5% = -0.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Stay Time = 3.8 - 4.0 hours0 days 0 hours 0 weeks 0 months

CRITICAL STEP PAGE 3 of 4

ADMIN JPM NO: ILE-2002-A4 RO TASK NUMBER - ELEMENT STANDARD SCORE S U

7. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 4

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: THE CONTROL ROOM SUPERVISOR HAS REQUESTED YOU TO HANG WPA IN AN AREA WHERE THE KNOWN RADIATION DOSE RATE IS 425 mrem/hr. YOUR CURRENT YEAR EXPOSURE HISTORY ACCORDING TO YOUR NRC FORM 4 IS AS FOLLOWS:

COMMITTED DOSE EQUIVALENT (CDE) 20 mrem

COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) 100 mrem

DEEP-DOSE EQUIVALENT (DDE) 200 mrem

EYE DOSE EQUIVALENT (LDE) 15 mrem

SHALLOW DOSE EQUIVALENT (SDE) 10 mrem Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO DETERMINE YOUR MAXIMUM STAY TIME IN THE CAUTION HIGH RADIATION AREA WHILE HANGING THE WPA BEFORE EXCEEDING THE CALLAWAY PLANT ADMINISTRATIVE DOSE LIMIT FOR WHOLE BODY TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE).

CALLAWAY PLANT ADMINISTRATIVE JOB PERFORMANCE MEASURE ADMIN JPM NO: ILE-2002-A4 SRO K/A NO: G 2.3.4 COMPLETION TIME: 15 MINUTES K/A RATING: 3.1 JOB TITLE: SRO REVISION: MAY 1, 2002 DUTY: ADMINISTRATIVE TASK TITLE: REPORTABILITY FOR EXCEEDING EXPOSURE LIMITS The performance of this task was evaluated against the standards contained in this Admin JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

REFERENCES:

APA-ZZ-00520, REPORTING REQUIREMENTS AND RESPONSIBILITIES, REV 16 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

ADMIN JPM NO: ILE-2002-A4 SRO Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 6. REFUELING ACTIVITIES ARE IN PROGRESS.

AN EQUIPMENT OPERATOR WAS SENT INSIDE THE INCORE INSTRUMENT TUNNEL TO HANG WPA. DUE TO AN INCORE INSTRUMENT THIMBLE BEING RETRACTED, THE EQUIPMENT OPERATOR RECEIVED AN OVEREXPOSURE OF 30 REM TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE).

Initiating Cues: YOU ARE THE CONTROL ROOM SUPERVISOR. YOU HAVE BEEN DIRECTED TO DETERMINE THE FOLLOWING ITEMS:

1. IS THIS OVEREXPOSURE REPORTABLE

2. IF YES, WHO IS THE PRIMARY RECIPIENT OF THE REPORT

3. IF YES, WHAT IS THE TIME LIMIT FOR THE REPORT TASK STANDARD: UPON COMPLETION OF THE TASK, THE CANDIDATE WILL HAVE DETERMINED THE FOLLOWING:

1. THE OVEREXPOSURE IS REPORTABLE

2. THE PRIMARY RECIPIENT IS THE NRC OPERATIONS CENTER

3. THE TIME LIMIT FOR THE REPORT IS ONE HOUR START TIME:

STOP TIME:

PAGE 1 of 3

ADMIN JPM NO: ILE-2002-A4 SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

1. PROVIDE CANDIDATE CANDIDATE SHOULD WITH MATERIAL AND REVIEW ADMIN JPM INITIAL Comments:

ALLOW TIME FOR CONDITIONS AND INITIATING REVIEW OF WORK TO BE CUES PERFORMED S U

2. CANDIDATE SHOULD CANDIDATE SHOULD REFER REFER TO APA-ZZ-00520, TO APA-ZZ-00520, REPORTING Comments:

REPORTING REQUIREMENTS AND REQUIREMENTS AND RESPONSIBILITIES RESPONSIBILITIES ATTACHMENT 1 SECTION 3.3 OR ATTACHMENT 2 ITEM 11 CONTAIN THE REPORTING CRITERIA FOR THIS EVENT S U

3. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE WHETHER DETERMINE THE Comments:

THE OVEREXPOSURE IS OVEREXPOSURE IS REPORTABLE REPORTABLE

CRITICAL STEP PAGE 2 of 3

ADMIN JPM NO: ILE-2002-A4 SRO TASK NUMBER - ELEMENT STANDARD SCORE S U

4. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE WHO IS THE DETERMINE THE NRC Comments:

PRIMARY RECIPIENT OF OPERATIONS CENTER IS THE REPORT THE PRIMARY RECIPIENT OF THE REPORT NRC ENS LINE (RED PHONE)

IS ALSO AN ACCEPTABLE ANSWER S U

5. CANDIDATE SHOULD CANDIDATE SHOULD DETERMINE THE TIME DETERMINE THE TIME LIMIT Comments:

LIMIT FOR THE REPORT FOR THE REPORT IS ONE HOUR S U

6. THIS ADMIN JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 3 of 3

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. You may use any approved reference materials normally available to you, unless directed otherwise. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Administrative Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 6. REFUELING ACTIVITIES ARE IN PROGRESS.

AN EQUIPMENT OPERATOR WAS SENT INSIDE THE INCORE INSTRUMENT TUNNEL TO HANG WPA. DUE TO AN INCORE INSTRUMENT THIMBLE BEING RETRACTED, THE EQUIPMENT OPERATOR RECEIVED AN OVEREXPOSURE OF 30 REM TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE).

Initiating Cues: YOU ARE THE CONTROL ROOM SUPERVISOR. YOU HAVE BEEN DIRECTED TO DETERMINE THE FOLLOWING ITEMS:

1. IS THIS OVEREXPOSURE REPORTABLE

2. IF YES, WHO IS THE PRIMARY RECIPIENT OF THE REPORT

3. IF YES, WHAT IS THE TIME LIMIT FOR THE REPORT

REFERENCE USE CALLAWAY PLANT WAS IN MODE 1 WHEN A TRANSIENT OCCURRED WHICH RESULTED IN AN EMERGENCY EVENT DECLARATION. WHICH "ON-SHIFT" POSITION INITIALLY ASSUMES THE ROLE OF THE EMERGENCY COORDINATOR (EC) FOLLOWING THE DECLARATION OF AN ALERT?

REFERENCE USE CALLAWAY PLANT WAS IN MODE 1 WHEN A TRANSIENT OCCURRED WHICH RESULTED IN AN EMERGENCY EVENT DECLARATION. WHAT IS THE PRIMARY MEANS OF COMMUNICATIONS USED TO MAKE INITIAL NOTIFICATIONS TO THE STATE EMERGENCY MANAGEMENT AGENCY (SEMA) AND THE FOUR COUNTIES IN THE EMERGENCY PLANNING ZONE?

RCP Shaft Vibration 15.1 mils RCP Frame Vibration 1.5 mils RCP Shaft Vibration is @ 1.8 mils/hr

RCP Frame Vibration is @ .2 mils/hr *

, C, & D RCP Shaft Vibrations are 1.4 mils

, C, & D RCP Frame Vibrations are 0.5 mils

These rates have been determined using time compression. These values indicate a rate of increase over a period of one hour.

CALLAWAY PLANT TRAINING DEPARTMENT DYNAMIC SIMULATOR SCENARIO SIMULATOR SCENARIO: ILE2002DS1 REVISION NUMBER: REV. 0 REVISION DATE: April 5, 2002 Page 1 of 20

SCENARIO TITLE: EXAM #:

LARGE BREAK LOCA ILE2002DS1 INITIAL CONDITIONS:

The plant is operating at 100% steady state power with 'B' RHR Pump tagged out.

Event - TITLE KSA # (RATING)

A) Increase Letdown Flow From 75 GPM to 120 GPM 004A4.06 3.6/3.1 B) B S/G Level Channel 529 Fails High 016K3.12 3.4/3.6 C) VCT Level Channel 149 Fails High 004A2.18 3.1/3.1 D) B Circulating Water Pump Trip 075A2.02 2.5/2.7 E) Turbine Setback to 75% Power 045K4.12 3.3/3.6 F) Hotwell Instrumentation Leak - Loss of Feed 054AA2.01 4.3/4.4 G) Turbine Automatic Trip Failure 007EA1.07 4.3/4.3 H) Large Break LOCA 011EK3.12 4.4/4.6 I) ESF Bus NB01 Lockout (IPE/PRA) 062A2.04 3.1/3.4 SCENARIO LENGTH:

Approximately 65 minutes.

SCENARIO COMPLETION CRITERIA:

This scenario is complete when the crew transitions to ECA-1.1, Loss of Emergency Coolant Recirculation.

Page 2 of 20

SCENARIO OVERVIEW EXAM #:

ILE2002DS1 The plant is at 100% steady state power with the 'B' RHR Pump tagged out for a breaker inspection. The 'B' RHR Pump should be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This is a 'B' train week for maintenance.

The crew will be directed to increase CVCS letdown flow from 75 gpm to 120 gpm for chemistry control.

Steam Generator Level Channel AE LT-529 fails high. The crew should respond per OTO-AE-00003, "Steam Generator Level Channel Failure" and stabilize B S/G level. Technical Specifications 3.3.1 and 3.3.2 actions should be applied.

VCT Level Channel BG LT-149 fails high causing CVCS Letdown to be diverted to the Recycle Holdup Tank. The crew should respond per OTO-BG-00004, VCT Level Channel Failure, and redirect letdown to the Volume Control Tank to terminate the RCS inventory loss.

A lockout on B Circulating Water Pump initiates a Turbine Setback. The crew should respond per OTO-MA-00007, Turbine Setback, to reduce Tavg and stabilize the plant.

A leak on the Condenser Hotwell Level Indicator causes indicated level to fail low. This results in a trip of all Condensate Pumps and both Main Feedwater Pumps. The reactor will trip on S/G Low Low Level unless the crew manually initiates a reactor trip. The crew should respond per E-0, Reactor Trip or Safety Injection. The main turbine fails to automatically trip and must be manually tripped by the Balance of Plant Operator.

A large break LOCA develops on the 'B' RCS Hot Leg. A lockout occurs on 4160V bus NB01 when the 'A' RHR Pump attempts to start. The crew should perform the required actions of E-0 then transition to E-1, "Loss of Reactor or Secondary Coolant". At step 12 of E-1, the crew should transition to ECA-1.1, "Loss of Emergency Coolant Recirculation".

Page 3 of 20

SCENARIO SETUP GUIDE EXAM #:

ILE2002DS1

1) Initialize at IC-20, 100% steady state power, BOL. (For 2002 ILE, this will be IC-167 and the password is 'gary')

2) Run Batch File DS1ILE.TXT.

Runs Batch File EJ01B. TXT (B RHR OOS)

Preloads Events B, C, D, F-I

This will prevent auto turbine trip.

imf tur08b

3) Set Conditionals for Triggers.

Trigger 5 - sac.le.100 (when turbine load is < 100 MWe)

Trigger 6 - x17o154r (when 'A' RHR Pump attempts to start)

4) Ensure letdown flow rate is 75 gpm.

5) Ensure the Immediate Boration Timer is reset.

6) Ensure NIS indicates 100% power.

7) Ensure step counters for Control Bank D are set to 215 steps and all other steps counters are at 228 steps.

8) Check Rx Trip Switch has a RED Flag.

9) Ensure the digital display is selected to PZR Pressure and Auctioneered HI Tave.

10) Ensure Decrease Loading Rate Button is ON.

11) Update status board to a B Train Week.

Page 4 of 20

SCENARIO SETUP GUIDE EXAM #:

ILE2002DS1

12) Update Status Board T/S LCO 3.5.2, Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

13) Update status board to show CCP suction boron concentration:

A 1015 ppm, 5 days ago B 1050 ppm, 2 weeks ago

14) Ensure the following is indicated on the "white board" 50 sec Imm Borate Per 10% PWR Reduction 1/2 Boron 1/2 Rods 8 Gal/% 3 Steps/%

15) Hold Off Tag on B RHR Pump Handswitch and place in PTL.

16) Turnover sheets and log sheets are on the desks.

17) Ensure RM-11 is on the Training System.

18) Ensure chart recorders are rolled forward.

19) Ensure alarm printer is "ON".

Page 5 of 20

SCENARIO SEQUENCE OF EVENTS GUIDE EXAM #:

ILE2002DS1 INSERT TIME EVENT MALF DESCRIPTION N/A A n/a Increase Letdown Flow 10 B fwm02b (1) 100 20 S/G Level Channel Failure 20 C cvc22 (2) 100 VCT Level Channel Failure 25 D,E cnd04b (3) Circ Pump Trip - Turbine Setback 35 F adl003 (4,15) 0 Hotwell Instrumentation Leak - Loss of Feed P G tur08b Turbine Auto Trip Failure P H rcs05b (5) 2000 30 Large Break LOCA P I nbs004 (6) trip ESF Bus NB01 Lockout EVENT INITIATING CUE (Instructor enters times ACTUATED)

START Time Completion Of Shift Turnover A Time Increase Letdown Flow B Time S/G Level Channel Failure C Time VCT Level Channel Failure D,E Time Circ Pump Trip - Turbine Setback F Time Hotwell Instrumentation Leak - Loss of Feed End Time Completion Of Scenario Page 6 of 20

INSTRUCTOR TURNOVER INFORMATION EXAM #:

ILE2002DS1 PRESENT CONDITIONS:

Mode 1 100% BOL Bank 'D' @ 215 steps CB= 996 ppm MWe= 1215 Circ Water pump setback - Enabled Cooling Tower B/D = 1K AEHV0038 22% open (3650 klbm/hr)

POWER HISTORY:

Steady state for 87 days.

EQUIPMENT STATUS:

'B' RHR Pump OOS for breaker inspection (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration remaining)

T/S LCO 3.5.2 Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

ABNORMAL CONDITIONS:

None SURVEILLANCES DUE/IN PROGRESS:

None ADDITIONAL INSTRUCTIONS:

Chemistry requests that we increase CVCS letdown flow to 120 gpm.

Page 7 of 20

SIMULATOR INSTRUCTOR RUN AID EXAM ILE2002DS1 EVENT ADDITIONAL INFORMATION B Respond as I&C to troubleshoot failed channel.

To trip S/G Level Channel Bistables bat ae03_07.txt bat doorshut.txt C Respond as I&C to troubleshoot failed channel D Respond as Electrical Maintenance to troubleshoot Circ Pump Trip F Respond as Secondary Operator and report pipe break on Condenser Hotwell Instrument Tree.

I Report lockout on bus NB01 with overcurrent relays actuated and a smell of burnt insulation.

If requested to secure the A Emergency DG (NE01), use the following:

Remote kjs001 Local/Manual Remote kjs007 Stop If requested to secure the B Emergency DG (NE02), use the following:

Remote kjs002 Local/Manual Remote kjs008 Stop If secured from the MCB respond as the SEO and report the amber Exciter Shutdown light extinguished after 130 seconds.

If asked to close bkrs per E-1 att. 4 the following information is for repeat-back to the caller; BGHIS8104 =>NG04CPF2

'B' BAT Pump =>NG02AAF4

'B' CRDM Cooling Fan =>NG02BJF5 COMMENTS:

T61.0810.8 Page 8 of 20

EVENT: A EXAM # ILE2002DS1 BRIEF DESCRIPTION: Increase Letdown Flow EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

NONE

1) Increase CVCS Letdown Flow to 120 gpm IAW _______

OTN-BG-00001, "Chemical and Volume Control System".

Inform Chemistry _______ _______

Place BG PK-131 in MANUAL and set to control _______

pressure at 190 psig

Open BG HV-8149AA _______

Manually control BG PK-131 at approximately 350 psig _______

When flow and pressure have stabilized, place BG PK- _______

131 in AUTO

Monitor BG TI-130 to control Letdown HX Disch Temp _______

at 95 - 115°F

Close BG HV-8109 _______

Ensure charging flow is maintaining PZR level _______

COMMENTS:

Denotes Critical Task Page 9 of 20

EVENT: B EXAM # ILE2002DS1 BRIEF DESCRIPTION: S/G Level Channel Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

S/G B LEV DEV 109C S/G B FLOW MISMATCH 109D REACTOR PARTIAL TRIP 83C

1) Implement OTO-AE-00003, "S/G Level Channel Failure". _______

Identify AE LT-529 as the failed channel _______ _______

Select the alternate level channel _______ _______

Stabilize B S/G level _______ _______

2) Refer to Technical Specification _______

T/S 3.3.1 Condition E 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months T/S 3.3.2 Condition D, I 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (T/S 3.3.3 Min Channels SAT INFO only EOSL)

3) Contact I&C to troubleshoot and trip bistables. _______

4) Notify the EDO of entry into an Off-Normal Procedure. _______

COMMENTS:

Denotes Critical Task Page 10 of 20

EVENT: C EXAM # ILE2002DS1 BRIEF DESCRIPTION: VCT Level Channel Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

VCT LEVEL HI LO 42B VCT DIVERT TO RHT 42D

1) Implement OTO-BG-00004, "VCT Level Channel Failure". _______

Identify BGLT0149 as the failure _______

Determine BGLT0149 has failed HIGH _______

2) Place BG HIS-112 in the VCT position _______ _______

Contact I&C to troubleshoot. _______

3) Notify EDO of entry into an Off-Normal Procedure. _______

COMMENTS:

Denotes Critical Task Page 11 of 20

EVENT: D/E EXAM # ILE2002DS1 BRIEF DESCRIPTION: Circ Pump Trip - Turbine Setback EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

CIRC WTR PMP LOCKOUT 13A

1) Implement OTO-MA-00007, Turbine Setback. _______

Verify Generator Load decreasing _______ _______

Verify that a Circ Water Pump tripped _______ _______

Drive Control Rods IN using manual control _______ _______

When ANN 65E is received, shift Rod Control to AUTO _______ _______

Ensure Control Rods stepping IN at 72 steps/min. _______ _______

Initiate Immediate Boration as required _______

Verify S/G levels are returning to 50% _______ _______

Ensure Tavg is being reduced to match Tref _______ _______ _______

Ensure PZR Pressure and Level are returning to normal _______ _______

programmed values

When Tavg is restored to program value, reset the steam _______ _______

dump arming signal COMMENTS:

Denotes Critical Task Page 12 of 20

EVENT: D/E EXAM # ILE2002DS1 BRIEF DESCRIPTION: Circ Pump Trip - Turbine Setback EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Adjust RCS boron to maintain Control Rods within their _______ _______

insertion / withdrawal limits.

Notify Chemistry and Health Physics of power _______

change > 15%.

Reset the load limiter. _______ _______

2) Notify EDO of entry into an Off-Normal Procedure. _______

COMMENTS:

Denotes Critical Task Page 13 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

COND HOTWELL LEV LO 106B S/G LEV LO LO 108-111A

1) Implement E-0, Reactor Trip or Safety Injection. _______

Verify Reactor Trip _______ _______

Verify Turbine Trip _______ _______

Identify failure of the main turbine to trip and _______ _______ _______

manually trip the turbine before a severe challenge develops to either the Subcriticality or the Integrity CSF or before transition to ECA-2.1.

Verify Power to NB01 AND NB02 _______ _______

Identify lockout on NB01 and investigate _______ _______ _______

Check if SI is actuated _______ _______ _______

Verify SI is actuated and continue in E-0. _______

COMMENTS:

Denotes Critical Task Page 14 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS Assign an RO to perform Attachment 12 _______

Ensure ESW pumps are running. _______ _______

Ensure at least One CCW pump running in each train _______ _______

Ensure Feedwater Isolation _______ _______

Ensure CISA _______ _______

Ensure AFW Actuation _______ _______

Ensure SI initiation. _______ _______

Check CTMT Coolers _______ _______

Ensure CPIS _______ _______

Check if Main Steam lines should be isolated _______ _______

Check if CTMT Spray is required _______ _______

Ensure CRVIS _______ _______

COMMENTS:

Denotes Critical Task Page 15 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Notify the CRS that 'A" Train ECCS equipment failed to _______ _______

actuate as a result of the NB01 Lockout COMMENTS:

Denotes Critical Task Page 16 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS Continue in E-0 _______

Ensure ECCS flow _______ _______ _______

Ensure total AFW flow greater than 300,000 lbm/hr _______ _______ _______

Ensure AFW valve alignment _______ _______ _______

Ensure SI valve alignment. _______ _______ _______

Check RCS Temperatures _______ _______ _______

Check PZR PORV and PZR Spray valves _______ _______ _______

Check if RCPs should be stopped _______ _______ _______

Check if S/Gs are NOT faulted _______ _______ _______

Check if S/G tubes are NOT ruptured _______ _______ _______

Check if RCS is in intact _______ _______ _______

COMMENTS:

Denotes Critical Task Page 17 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS Transition to E-1, Loss of Reactor or Secondary Coolant. _______

Implement CSF-1, "Critical Safety Function Status Trees". _______

COMMENTS:

Denotes Critical Task Page 18 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

2) Implement E-1, Loss of Reactor or Secondary Coolant. _______

Check if RCPs should be stopped _______ _______ _______

a. at least one ECCS pump is running

b. RCS press less than 1400 psig

c. Stop all RCP's. This critical task could be _______ _______ _______

accomplished earlier at either of the following:

E Foldout Page E Step 12.c

Check if S/Gs are NOT faulted _______ _______ _______

Check Intact S/G levels _______ _______ _______

Check Secondary Radiation normal _______ _______ _______

Check PZR PORV and PZR PORV Block Valve _______ _______ _______

Check if SI flow should be reduced _______ _______ _______

COMMENTS:

Denotes Critical Task Page 19 of 20

EVENT: F/G/H/I EXAM # ILE2002DS1 BRIEF DESCRIPTION: Hotwell Instrumentation Leak -Loss of Feed / Reactor Trip /

Turbine Auto Trip Failure / Large Break LOCA / NB01 Bus Lockout EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Check if CTMT Spray should be stopped _______ _______ _______

Check if RHR pumps should be stopped _______ _______ _______

Check RCS and S/G pressures _______ _______ _______

Check if Diesel Generators should be stopped _______ _______ _______

Initiate evaluation of plant status _______ _______ _______

Verify cold recirculation capability does NOT exist per _______ _______ _______

Attachment 5, Verifying Cold Leg Recirculation Capability Transition to ECA-1.1, Loss of Emergency Coolant _______

Recirculation.

COMMENTS:

Denotes Critical Task Page 20 of 20

CALLAWAY PLANT TRAINING DEPARTMENT DYNAMIC SIMULATOR SCENARIO SIMULATOR SCENARIO: ILE2002DS2 REVISION NUMBER: REV. 0 REVISION DATE: April 5, 2002 Page 1 of 24

SCENARIO TITLE: EXAM #: ILE2002DS2 FAULTED/RUPTURED STEAM GENERATOR INITIAL CONDITIONS:

The plant is stable at 30% reactor power ready to increase load at 3%/hr with 'B' RHR Pump tagged out.

Event TITLE KSA # (RATING)

A) Swap Charging From NCP To CCP 004A4.08 3.8 / 3.4 B) Pressurizer Pressure Channel 455 Fails High 027AA2.15 3.7 / 4.0 C) Steam Flow Channel 542 Fails High On 'D' S/G 059A2.11 3.0 / 3.3 D) Steam Generator Tube Leak On 'D' S/G 037AK3.05 3.7 / 4.0 E) Plant Shutdown Due To S/G Tube Leak 004A4.01 3.8 / 3.9 F) Steam Generator Tube Rupture On 'D' S/G 038EA2.02 4.5 / 4.8 G) Failure Of 'D' FWIV To Automatically Close 013A4.01 4.5 / 4.8 H) S/G Safety Stuck Open On 'D' S/G 035A2.01 4.5 / 4.6 SCENARIO LENGTH:

Approximately 85 minutes.

SCENARIO COMPLETION CRITERIA:

This scenario is complete when the crew transitions to ECA-3.1, "SGTR With Loss of Reactor Coolant Subcooled Recovery Desired" or FR-P.1, "Response to Imminent Pressurized Thermal Shock Condition".

Page 2 of 24

SCENARIO OVERVIEW EXAM #: ILE2002DS2 The plant is stable at 30% power ready to increase load at 3%/hr with the 'B' RHR Pump tagged out for a breaker inspection. The 'B' RHR Pump should be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This is a 'B' train week for maintenance.

The NCP is required to be tagged out for an oil change. The crew will start the 'B' CCP and secure the NCP.

Pressurizer Pressure Channel BB PT-455 fails high, causing spray valves to open and pressurizer heaters to turn off. The crew should respond per OTO-BB-00006, Pressurizer Pressure Channel Failure, and stabilize pressurizer pressure.

Controlling Steam Flow Channel AB FT-542 fails high, causing a level perturbation on 'D' S/G and an increase in the speed of the MFP in automatic. This will also cause a steam generator tube leak to develop. The crew should respond per OTO-AB-00002, Steam Flow Channel Failure, and stabilize 'D' S/G level.

A 5 gpm steam generator tube leak develops on 'D' S/G. This will place the crew in Action Level 3 in APA-ZZ-01023, Primary to Secondary Leakage Program, and enter OTO-BB-00001, Steam Generator Tube Leak. The crew should commence a controlled shutdown to Mode 3 at a rate to be in Mode 3 within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Once the crew has commenced the power reduction, the steam generator tube leak in 'D' S/G will increase to 150 gpm. This will cause a reactor trip and safety injection. The crew should enter E-0, Reactor Trip or Safety Injection.

'D' Feedwater Isolation Valve, AE HV-42, fails to close on the FWIS. The crew must fast close feedwater isolation valves with push-button AE HS-80 or AE HS-81.

When steam pressure increases Safety Valve, ABV045, on 'D' S/G will open and remain open causing a faulted/ruptured steam generator.

The crew should enter E-2, Faulted Steam Generator Isolation, then transition to E-3, Steam Generator Tube Rupture.

The scenario is complete with the transition to ECA-3.1, "SGTR With Loss of Reactor Coolant Subcooled Recovery Desired" or FR-P.1, "Response to Imminent Pressurized Thermal Shock Condition".

Page 3 of 24

SCENARIO SETUP GUIDE EXAM #: ILE2002DS2

1) Initialize at IC-16, 30% power ready to increase power at 3%/hr, BOL. (For 2002 ILE, this will be IC-168 and the password is 'gary')

2) Run Batch File DS2ILE.TXT.

Runs Batch File EJ01B.TXT ('B' RHR Pump OOS).

Preloads Events B, C, D, F-H

VERIFY REMOTE SAS010d FAIL IS ACTIVE

3) Set Conditionals for Triggers.

Trigger 4 - "0" mmf rcs02d 150 30 15 (manual trigger to start SGTR)

Trigger 5 - "sac.le.100" (fails open S/G safety after the turbine trip)

4) Ensure the Immediate Boration Timer is reset.

5) Ensure NIS indicates 30% power.

6) Check Rx Trip Switch has a RED Flag.

7) Ensure step counters for Control Bank 'D' are set to 130 steps and all other steps counters are at 228 steps.

8) Ensure the digital display is selected to PZR Pressure and Auctioneered HI Tave.

9) Place Hold Off Tag on 'B' RHR Pump Handswitch and place in PTL.

10) Ensure 'B' Train CCW is in service.

11) Ensure Decrease Loading Rate Button is ON.

Page 4 of 24

SCENARIO SETUP GUIDE EXAM #: ILE2002DS2

12) Update status board to a 'B' Train Week.

13) Update Status Board T/S LCO 3.5.2, Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

14) Update status board to show CCP suction boron concentration:

'A' 1204 ppm, 5 days ago

'B' 1200 ppm, 2 weeks ago (ensure this is within 300 ppm of BCMS)

15) Ensure the following is indicated on the "white board" 50 sec Imm Borate Per 10% PWR Reduction 1/2 Boron 1/2 Rods 8 Gal/% 3 Steps/%

16) Ensure alarm printer is "ON".

17) Ensure RM-11 is on the Training System.

18) Turnover sheets and log sheets are on the desks.

19) Ensure chart recorders are rolled forward.

Page 5 of 24

SCENARIO SEQUENCE OF EVENTS GUIDE EXAM #: ILE2002DS2 INSERT TIME EVENT MALF DESCRIPTION N/A A n/a Swap Charging From NCP To CCP 10 B prs01a (1) 2500 5 Pressurizer Pressure Channel 455 Fails High 20 C mss02d (2) 4.8 20 Steam Flow Channel 542 Fails High On

'D' S/G 25 D rcs02d (3) 5 1800 0 Steam Generator Tube Leak On 'D' S/G 25 E n/a Plant Shutdown Due To S/G Tube Leak 40 F rcs02d (4) 150 30 15 Steam Generator Tube Rupture On 'D' S/G P G sas010d fail Failure Of 'D' FWIV To Automatically Close 42 H mss14d (5) 200 30 S/G Safety Stuck Open On 'D' S/G EVENT INITIATING CUE (Instructor enters times ACTUATED)

Start Time Completion Of Shift Turnover A Time Swap Charging From NCP To CCP B Time Pressurizer Pressure Channel 455 Fails High C Time Steam Flow Channel 542 Fails High On 'D' S/G Steam Generator Tube Leak On 'D' S/G / Plant Shutdown Due D/E Time To S/G Tube Leak F Time Steam Generator Tube Rupture On 'D' S/G H Time S/G Safety Stuck Open On 'D' S/G End Time Completion Of Scenario Page 6 of 24

INSTRUCTOR TURNOVER INFORMATION EXAM #: ILE2002DS2 PRESENT CONDITIONS:

Mode 1 30% BOL stable, ready to increase power at 3%/hr Bank 'D' @ 130 steps CB= 1195 ppm MWe= 360 At Step 5.1.7 of OTG-ZZ-00004, Power Operations AEHIS0038 closed (0% open)

POWER HISTORY:

30% following a reactor startup from an unexpected plant trip due to loss of off site power.

EQUIPMENT STATUS:

'B' RHR Pump OOS for breaker inspection (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration remaining)

T/S LCO 3.5.2 Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

ABNORMAL CONDITIONS:

None.

SURVEILLANCES DUE/IN PROGRESS:

None.

ADDITIONAL INSTRUCTIONS:

Maintenance request to have NCP removed from service for oil change.

Place the 'B' CCP in service.

Page 7 of 24

SIMULATOR INSTRUCTOR SCENARIO RUN EXAM #: ILE2002DS2 AID EVENT ADDITIONAL INFORMATION A When contacted as HP, acknowledge that 'B' CCP is to be started.

NOTE: Time Compression - Inform the RO that 'B' CCP Aux L. O. Pump has run for 5 minutes.

B Act as I&C, acknowledge the failure of BB PT-455 and trip bistables if requested:

BAT dooropen.txt BAT bb012.txt BAT doorshut.txt Inform crew that troubleshooting/repair will be pursued.

C Act as I&C, acknowledge the failure of AB FT-542, and inform the crew that the troubleshooting/repair will begin.

D/E Act as Chemistry and begin to sample steam generators. Open Blowdown Sample Valves using Remote Mode to open BMHV5-8.

REMOTE BMHV5 = BMV020 BMHV6 = BMV021 BMHV7 = BMV022 BMHV8 = BMV023 45 minutes later inform the crew that 'D' S/G has a leak indication of 8 gpm.

Act as HP and acknowledge direction to survey main steam lines and inform operator later that 'D' steam line is much higher (15 mr on contact).

Act as EDO and inform the CRS to shutdown the plant as per the most conservative action in OTO-BB-00001. Call back if necessary.

Act as Power Supervisor and acknowledge plant shutdown.

F Act as Chemistry and inform crew you will take more S/G samples.

Page 8 of 24

SIMULATOR INSTRUCTOR SCENARIO RUN EXAM #: ILE2002DS2 AID H Act as Insides Equipment Operator and inform crew steam is coming from Area 5 roof.

Act as Primary Equipment Operator and inform crew 'D' S/G Safety ABV045 has failed open and you cannot close it.

Page 9 of 24

EVENT: A EXAM # ILE2002DS2 BRIEF DESCRIPTION: Swap Charging From NCP To CCP EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

NONE

1) Refer to OTN-BG-00001, Chemical and Volume Control System, and perform the following:

Notify HP of which CCP is to be started. _______

Verify CCW is aligned to the 'B' CCP. _______

Place CCP Flow Controller, BG FK-121 in manual and _______

set to minimum.

Ensure 'B' CCP Recirc Valve, BG HIS-8111 is open. _______

Place 'B' CCP Aux L. O. Pump HS, BG HIS-2AX in _______

AUTO and verify the Run Light is lit.

NOTE: Time Compression - The RO will be informed that 'B' CCP Aux L. O. Pump has run for 5 minutes.

Start 'B' CCP with BG HIS-2A. _______

Verify the 'B' CCP Aux L. O. Pump stops. _______

COMMENTS:

Denotes Critical Task Page 10 of 24

EVENT: A EXAM # ILE2002DS2 BRIEF DESCRIPTION: Swap Charging From NCP To CCP EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Place NCP Flow Controller, BG FK-124 in manual. _______

Open NCP Recirc Valve with BG HIS-8109 when NCP _______

flow <100 gpm. (when annunciator 41F alarms)

Increase CCP flow / decrease NCP flow. _______

When BG FK-124 indicates 0%, stop the NCP using _______

BG HIS-3.

Verify that RCP Seal Injection is 8 gpm per pump. _______

Verify PZR level is stable and place BG FK-121 in auto. _______

COMMENTS:

Denotes Critical Task Page 11 of 24

EVENT: B EXAM # ILE2002DS2 BRIEF DESCRIPTION: Pressurizer Pressure Channel 455 Fails High EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

PZR HI PRESS DEV 33B RX PARTIAL TRIP 83C

1) Implement OTO-BB-00006, Pressurizer Pressure Channel _______

Failure.

Identify the failed channel. (BBPT455) _______ _______

Select away from the failed channel. _______ _______

(Select BBPT457/456)

Terminate any pressure transient and ensure the plant is _______ _______

in a stable condition.

2) Ensure PORVs, spray valves, and heaters return to normal. _______ _______ _______

3) Select a valid input to the Pressurizer Pressure (Channel _______ _______ _______

456, 457 or 458) and OPT / OTT (Loop 2, 3 or 4) recorders.

4) Select a valid input to the Plant Computer for the digital _______ _______ _______

display. (Channel 456, 457 or 458)

COMMENTS:

Denotes Critical Task Page 12 of 24

EVENT: B EXAM # ILE2002DS2 BRIEF DESCRIPTION: Pressurizer Pressure Channel 455 Fails High EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

5) Refer to Technical Specifications _______

T/S 3.3.1 Condition E, M 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months T/S 3.3.2 Condition L 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Condition D 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months T/S 3.3.4 Condition A 30 days

6) Consult with the LD and EDO to evaluate RX power _______

reduction prior to troubleshooting, tripping bistables, and/or repairing the channel.

7) Contact I&C to trip bistables per Attachment 1. _______

COMMENTS:

Denotes Critical Task Page 13 of 24

EVENT: C EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Flow Channel 542 Fails High On 'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

SG D LEV DEV 111C SG D FLOW MISMATCH 111D

1) Implement OTO-AB-00002, Steam Flow Channel Failure. _______

Identify the failed channel. (Channel F542) _______ _______

Select the alternate steam flow channel. (Channel F543) _______ _______

Stabilize S/G level at 50%. _______ _______

2) Contact I&C to troubleshoot/repair channel. _______

3) Notify EDO of OTO procedure entry. _______

COMMENTS:

Denotes Critical Task Page 14 of 24

EVENT: D/E EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Leak On 'D' S/G, Plant Shutdown Due To S/G Tube Leak EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

PROCESS RAD HI 61B PROCESS RAD HIHI 61A

1) Implement OTO-BB-00001, Steam Generator Tube Leak. _______

2) Determine size and location of leak. _______ _______

Utilize N16 monitors on RM11. _______ _______ _______

Trends on GERE0092, SJRE0002, or BMRE0025. _______ _______ _______

Utilize computer points GEF0092, GEF0092A, and _______ _______ _______

GEF0792.

3) Use trends of VCT Level and/or Pressurizer Level. _______ _______

4) Compare Charging and Letdown flow rates. _______ _______

5) Ensure SG B/D sampling is in operation. _______ _______ _______

Utilize computer points GEF0092, GEF0092A, and _______

GEF0792.

COMMENTS:

Denotes Critical Task Page 15 of 24

EVENT: D/E EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Leak On 'D' S/G, Plant Shutdown Due To S/G Tube Leak EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

6) If required, reduce letdown flow to 75 gpm. _______ _______

Contact HP to survey the Main Steam Lines. _______

7) If leakage rate is > 75 gpd and primary to secondary leakage _______

rate of change is > to 30 gpd/hr, go to Attachment 1 and commence a rapid load decrease to 50% in one hour, followed by a controlled shutdown to Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Note: After crew has reduced power by at least 2%, initiate Event F, Steam Generator Tube Rupture On 'D' S/G.

Shutdown plant to be in Mode 3 in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . _______ _______ _______

8) Refer to APA-ZZ-01023, S/G Tube Leak Contingency _______

Guidelines.

9) Refer to Technical Specification LCO 3.4.13. _______

COMMENTS:

Denotes Critical Task Page 16 of 24

EVENT: D/E EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Leak On 'D' S/G, Plant Shutdown Due To S/G Tube Leak EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

10) Attachment 1

Discuss shutdown with EDO. _______

Notify Power Supervisor of plant S/D. _______ _______

Perform OTG-ZZ-00004, Power Operations, may use _______

Attachment 1 for rapid shutdown.

COMMENTS:

Denotes Critical Task Page 17 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

PROCESS RAD HIHI 61A PROCESS RAD HI 61B

1) Identify S/G Tube Leak exceeds 50 gpm and trip reactor per _______ _______ _______

OTO-BB-00001, Steam Generator Tube Leak, Attachment 2.

2) Implement E-0, Reactor Trip or Safety Injection. _______

Verify Reactor Trip. _______ _______

Verify Turbine Trip. _______ _______

Verify Power to NB01 AND NB02. _______ _______

Check if SI is actuated. _______ _______ _______

Verify SI is actuated and continue in E-0. _______

COMMENTS:

Denotes Critical Task Page 18 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS Assign an RO to perform Attachment 12. _______

Ensure ESW pumps are running. _______ _______

Ensure at least One CCW pump running in each train. _______ _______

Ensure Feedwater Isolation. _______ _______

Identify failure of 'D' FWIV to close and fast close _______ _______ _______

FWIV with AE-HS-80 or AE-HS-81 before a transition to ECA-3.1 occurs.

Ensure CISA. _______ _______

Ensure AFW Actuation. _______ _______

Ensure SI initiation. _______ _______

Check CTMT Coolers. _______ _______

Ensure CPIS. _______ _______

COMMENTS:

Denotes Critical Task Page 19 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Check if main steam lines should be isolated. _______ _______

Check if CTMT Spray is required. _______ _______

Ensure CRVIS. _______ _______

Notify the CRS that 'D" FWIV failed to close and was fast _______ _______

closed (if applicable) per Attachment 12.

COMMENTS:

Denotes Critical Task Page 20 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS Continue in E-0. _______

Ensure ECCS flow. _______ _______ _______

Ensure total AFW flow greater than 300,000 lbm/hr. _______ _______ _______

Ensure AFW valve alignment. _______ _______ _______

Ensure SI valve alignment. _______ _______ _______

Check RCS Temperatures. (Crew may fast close MSIV's per _______ _______ _______

RNO)

Check PZR PORV and PZR Spray valves. _______ _______ _______

Check if RCPs should be stopped. _______ _______ _______

Check if S/Gs are NOT faulted. _______ _______ _______

Crew should determine a S/G is faulted and transition to _______ _______ _______

E-2, Faulted Steam Generator Isolation.

Implement CSF-1, "Critical Safety Function Status Trees". _______

COMMENTS:

Denotes Critical Task Page 21 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

3) Implement E-2, Faulted Steam Generator Isolation. _______

Check MSIVs and MSIV Bypass Valves closed. _______ _______

Check if any S/G is intact. _______ _______

Identify Faulted S/G. _______ _______

Isolate Faulted S/G. _______ _______

AFW should be isolated to the 'D' S/G before _______ _______ _______

transition out of E-2.

Check CST Level greater than 18%. _______ _______

Check Secondary Radiation normal. _______ _______ _______

Transition to E-3, Steam Generator Tube Rupture. _______

COMMENTS:

Denotes Critical Task Page 22 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

4) Implement E-3, Steam Generator Tube Rupture. _______

Check if RCPs should be stopped. _______ _______ _______

Identify ruptured S/G. _______ _______

Isolate flow from ruptured S/G. _______ _______

Check ruptured S/G level. _______ _______

Check PZR PORV and PZR PORV block valves. _______ _______ _______

Check if S/Gs are not faulted. _______ _______

Check intact S/G levels. _______ _______

Reset SI. _______ _______

Reset CIS 'A'. _______ _______ _______

Establish Instrument Air to Containment. _______ _______ _______

COMMENTS:

Denotes Critical Task Page 23 of 24

EVENT: F/G/H EXAM # ILE2002DS2 BRIEF DESCRIPTION: Steam Generator Tube Rupture on 'D' S/G, Failure Of 'D' FWIV To Automatically Close, and S/G Safety Stuck Open on

'D' S/G EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Verify All AC Service Buses energized by OFFSITE _______ _______ _______

power.

Check if RHR pumps should be stopped. _______ _______ _______

Check ruptured S/G pressure > 430 psig. _______ _______

5) Transition to ECA-3.1, "SGTR With Loss of Reactor _______ _______ _______

Coolant Subcooled Recovery Desired" or FR-P.1, "Response to Imminent Pressurized Thermal Shock Condition" if required per the CSF Status Trees.

COMMENTS:

Denotes Critical Task Page 24 of 24

CALLAWAY PLANT TRAINING DEPARTMENT DYNAMIC SIMULATOR SCENARIO SIMULATOR SCENARIO: ILE2002DSBU REVISION NUMBER: REV. 0 REVISION DATE: April 19, 2002 Page 1 of 19

SCENARIO TITLE: EXAM #: ILE2002DSBU EARTHQUAKE CAUSES LOSS OF SITE POWER AND NE01 FAILURE CAUSES LOSS OF ALL AC INITIAL CONDITIONS:

The plant is operating at 80% steady state power with B RHR pump tagged out.

Event TITLE KSA # (RATING)

A) Pressurizer Level Channel 459 Failure 011A2.11 3.4 / 3.6 B) Letdown Isolation Valve Failure 004A2.07 3.4/3.7 C) Place Excess Letdown In Service 028AA1.05 2.8 / 2.9 D) A RCP High Vibration Requiring Power Reduction 015AA1.23 3.1 / 3.2 E) Plant Shutdown due to RCP High Vibration 004A4.01 3.8/3.9 F) A S/G PORV Failure 041A4.06 2.9 / 3.1 G) Loss of Off-Site Power and NB02 056AA2.44 4.3 / 4.5 H) Automatic Reactor Trip Failure 029EA1.12 4.1 / 4.0 I) Turbine Driven Aux. Feed Pump Fails To Auto Start 061A2.04 3.4 / 3.8 J) Loss of All AC due to NE01 Failure 055EA2.02 4.4 / 4.6 SCENARIO LENGTH:

Approximately 70 minutes.

SCENARIO COMPLETION CRITERIA:

This scenario is complete when the crew initiates ECA-0.0 step 16, Depressurize Intact SGs to 220 PSIG.

Page 2 of 19

SCENARIO OVERVIEW EXAM #: ILE2002DSBU The plant is at 80% power with 'B' RHR Pump tagged out for a breaker inspection. The 'B' RHR Pump should be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This is a 'B' train week for maintenance.

Pressurizer Level Channel BB LT-459 fails low, causing a loss of CVCS Letdown. The crew should respond per OTO-BB-00007, Pressurizer Level Channel Failure, and refer to Technical Specification 3.3.1. When letdown restoration is attempted, BG LCV-0459 will not open. The crew should place excess letdown in service per OTN-BG-00001, Chemical and Volume Control System.

An RCP Vibration annunciator is received and A RCP is indicating just over 15 mils on the shaft. The crew should reduce reactor power in preparation for securing the A RCP.

During the power reduction, the A S/G Atmospheric PORV fails open. The crew should respond per OTO-AB-00001, Steam Dump Malfunction, and manually close the failed PORV.

Technical Specification 3.7.4 should be reviewed.

A major earthquake causes a loss of off-site power and a lockout on 4160V bus NB02. The crew should respond to the reactor trip per E-0, Reactor Trip or Safety Injection. The reactor fails to automatically trip. The crew must manually trip the reactor.

The TDAFP fails to automatically start. The crew must to manually start the TDAFP.

At the completion of Step 3 of ES-0.1, Reactor Trip Response, the 'A' diesel generator will trip causing a Loss of All AC Power. The crew will transition to ECA-0.0, Loss of All AC Power.

The scenario is complete when the crew initiates ECA-0.0 step 16, Depressurize Intact SGs to 220 PSIG.

Page 3 of 19

SCENARIO SETUP GUIDE EXAM #: ILE2002DSBU

1) Initialize at IC-19, 80% steady state power, BOL. (For 2002 ILE, this will be IC-169 and the password is 'gary')

2) Run Batch File DSBUILE.TXT.

Runs batch file EJ01B.txt ('B' RHR pump OOS)

Preloads events A, B, D, F-G

VERIFY REMOTE SBI006 INHIBIT IS ACTIVE

3) Set Conditionals for Triggers.

Trigger 2 - Event Action - 0 Command - SET CRCPV2(1)=17

3) Ensure that an easel is set up around back of the simulator with the following information:

A RCP Shaft Vibration 15.1 mils

A RCP Frame Vibration 1.5 mils

A RCP Shaft Vibration is @ 1.8 mils/hr.

A RCP Frame Vibration is @ .2 mils/hr.

B, C, & D RCP Shaft Vibration is 1.4 mils

B, C, & D RCP Frame Vibration is .5 mils

4) Ensure the Immediate Boration Timer is reset.

4) Ensure NIS indicates 80% power.

5) Ensure step counters for Control Bank D are set to 180 steps and all other steps counters are at 228 steps.

6) Check Rx Trip Switch has a RED Flag.

Page 4 of 19

SCENARIO SETUP GUIDE EXAM #: ILE2002DSBU

7) Ensure the digital display is selected to PZR Pressure and Auctioneered HI Tave.

8) Ensure Decrease Loading Rate Button is ON.

9) Update status board to a B Train Week.

10) Update Status Board T/S LCO 3.5.2, Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

11) Update status board to show CCP suction boron concentration:

A 1042 ppm, 5 days ago B 1046 ppm, 2 weeks ago

12) Ensure the following is indicated on the "white board" 50 sec Imm Borate Per 10% PWR Reduction 1/2 Boron 1/2 Rods 8 Gal/% 3 Steps/%

13) Hold Off Tag on B RHR Pump Handswitch and place in PTL.

14) Turnover sheets and log sheets are on the desks.

15) Ensure RM-11 is on the Training System.

16) Ensure chart recorders are rolled forward.

17) Ensure alarm printer is "ON".

Page 5 of 19

SCENARIO SEQUENCE OF EVENTS GUIDE EXAM #: ILE-7/2000-DSBU INSERT TIME EVENT MALF DESCRIPTION 0 A prs02a (1) 0 10 PZR Level Channel Failure N/A B bghis459_IC (1 5) ON LTDN Iso Vlv 459 Fails Closed bghis459_IO (1 5) OFF 20 D Trigger 2 'A' RCP High Vibration 35 F mss07a (3) 100 10 S/G PORV Failure 40 G Seismic EPS03 Loss of Off-Site Power and NB02 P H crf13 0 RX Auto Trip Failure P I sbi006 inhibit TDAFW Pump Auto Start Failure P J eps06a (5) NE01 Failure EVENT INITIATING CUE (Instructor enters times ACTUATED)

Start Time Completion Of Shift Turnover A Time PZR Level Channel Failure C Time Place Excess Letdown In Service D Time RCP High Vibration F Time S/G PORV Failure G, H Time Loss of Off-Site Power and NB02, Auto RX Trip Failure I Time TDAFW Pump Auto Start Failure J Time Loss of All AC End Time Completion Of Scenario Page 6 of 19

INSTRUCTOR TURNOVER INFORMATION EXAM #: ILE-7/2000-DSBU PRESENT CONDITIONS:

Mode 1 80% BOL Bank 'D' @ 180 steps CB = 1041 ppm MWe = 972 Circ Water pump setback - Enabled Cooling Tower B/D = 1K AEHV0038 20% open (2615 klbm/hr)

POWER HISTORY:

80% following an outage to repair a leak in Main Generator Stator Cooling Water.

EQUIPMENT STATUS:

'B' RHR Pump OOS for breaker inspection (8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration remaining)

T/S LCO 3.5.2 Condition A (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

ABNORMAL CONDITIONS:

None.

SURVEILLANCES DUE/IN PROGRESS:

None.

ADDITIONAL INSTRUCTIONS:

None.

Page 7 of 19

SIMULATOR INSTRUCTOR SCENARIO EXAM #: ILE2002DSBU RUN AID EVENT ADDITIONAL INFORMATION A Respond as I&C to trip bistables BAT dooropen.txt BAT bb052.txt BAT doorclosed.txt If contacted as EDO acknowledge the OTO entry B Respond as Work Control if requested to investigate the failure of BGLV0459.

D If called, answer as the RCP and Vibration Engineers and recommend securing the RCP as soon as possible.

E If the EDO is contacted, answer and agree the plant should be shutdown.

F Respond as I&C to troubleshoot failed ASD G Respond as Secondary EO and report that NB0209 breaker has a 186 lockout relay dropped, but there are no other flags dropped.

Respond as Electrical Maintenance if requested to investigate the trip of NB0209 Respond as Secondary EO and secure 'B' DG, use the following Remote kjs002 Local/Manual Remote kjs008 Stop J Respond as an Equipment Operator and report that 'A" DG annunciator panel KJ121 has the following alarms 1A Fuel Oil Pressure Low 1B Fuel Filter Differential Pressure High Respond as I&C to perform OTO-GK-00001, Loss of Control Room HVAC.

Respond as HP to take radiation readings in Area 5.

Page 8 of 19

EVENT: A EXAM # ILE2002DSBU BRIEF DESCRIPTION: Pressurizer Level Channel Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

PZR 17% HTRS OFF LTDN ISO 32B PZR LO LVL DEV 32C

1) Implement OTO-BB-00007, Pressurizer Level Channel _______

Failure.

Identify pressurizer level channel BB LT-459 failure _______ _______

Select away from the failed channel using switch BB _______ _______

LS-459D. (Channel 461/460)

If letdown has isolated, within two minutes align _______ _______

charging only to the RCP seals.

2) Restore PZR level to program level (See Events B & C) _______ _______

If required, restart the variable heaters using BB HIS-50 _______ _______

Select a valid level channel (Channel 460 or 461) for the _______ _______

Pressurizer Program Level Recorder using switch BB LS-459E

Verify pressurizer level control is normal _______ _______

If letdown has isolated, restore per OTN-BG-00001, _______

Chemical and Volume Control System Refer to Technical Specifications and ensure compliance with minimum channel requirements and action statements T/S 3.3.1 Condition M (6 hrs to trip bistables)

COMMENTS:

Denotes Critical Task Page 9 of 19

EVENT: A EXAM # ILE2002DSBU BRIEF DESCRIPTION: Pressurizer Level Channel Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Contact I&C to have the instrument failure investigated, _______

and request tripping of bistables.

3) Notify EDO upon entering off-normal procedure. _______

COMMENTS:

Denotes Critical Task Page 10 of 19

EVENT: B/C EXAM # ILE2002DSBU BRIEF DESCRIPTION: Place Excess Letdown In Service Due To A Normal Letdown Isolation Valve Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

NONE

1) When attempts to restore normal letdown are unsuccessful, _______

place excess letdown in service per OTN-BG-00001.

Inform H.P. that excess letdown is to be placed in _______ _______

service.

Inform Chemistry that excess letdown is to be placed in _______ _______

service.

Notify Radwaste that excess letdown is being directed to _______ _______

the RCDT.

Verify that the Excess Letdown Heat Exchanger is _______ _______

supplied with CCW.

Ensure BG HC-123, the Excess Letdown HX Outlet _______ _______

Flow Hand Switch, is in the closed position.

Place BG HIS-8143, in the RCDT position. _______ _______

Open either set of Reactor Coolant To Excess Letdown _______ _______

HX valves with the applicable control switches:

Train A BG HIS-8153A & BG HIS-8154A Train B BG HIS-8153B & BG HIS-8154B COMMENTS:

Denotes Critical Task Page 11 of 19

EVENT: B/C EXAM # ILE2002DSBU BRIEF DESCRIPTION: Place Excess Letdown In Service Due To A Normal Letdown Isolation Valve Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Slowly turn BG HC-123, EX LTDN EX OUT FLOW _______ _______

HAND CTRL, to the open position to establish excess letdown flow.

Ensure Excess Letdown HX Outlet temperature using _______ _______

BG TI-122 on panel RL002; does not exceed 175°F.

Verify RCP seal water leak-off flow is 1-5 gpm with _______ _______

normal RCS operating pressure as indicated on BG FR-154 through BG FR-157 on panel RL022.

After approximately 2 minutes, direct excess letdown _______ _______

flow to the VCT as follows

Slowly turn BG HC-123 to the closed position to secure _______ _______

excess letdown flow.

Ensure BG HC-123 in the closed position and select _______ _______

BGHV8143 to the VCT position using BG HIS-8143.

Ensure open either set of Excess Letdown HX Valves _______ _______

Slowly turn BG HC-123 to the open position to _______ _______

re-establish excess letdown flow.

Notify Radwaste that excess letdown flow is now _______ _______

directed to the VCT.

Ensure Excess Letdown HX Outlet temperature, using _______ _______

BG TI-122 on panel RL002, does not exceed 175°F.

COMMENTS:

Denotes Critical Task Page 12 of 19

EVENT: B/C EXAM # ILE2002DSBU BRIEF DESCRIPTION: Place Excess Letdown In Service Due To A Normal Letdown Isolation Valve Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Verify RCP seal water leak-off is 1-5 gpm with normal _______ _______

operating pressure as indicated on BG FR-154 through BG FR-157 on panel RL022.

Notify H.P. that excess letdown is in service. Identify _______ _______

the flowpath for excess letdown so that H.P. can monitor rooms and components in the flowpath for increased radiation levels.

COMMENTS:

Denotes Critical Task Page 13 of 19

EVENT: D/E EXAM # ILE2002DSBU BRIEF DESCRIPTION: RCP Vibration Requiring Power Reduction EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

RCP VIB / SYS ALERT 70B

1) Implement OTO-BB-00002, Reactor Coolant Pump _______

Off-Normal, Attachment 1.

Check RCP Vibrations. _______ _______ _______

Continue monitoring RCP vibration _______ _______ _______

Contact the RCP and Vibration System Engineers to _______

determine if securing the RCP is required.

If the RCP is to be secured perform the following: _______

Reduce reactor power to less than 48% (P-8 _______ _______ _______

extinguished on SB069) IAW OTG-ZZ-00004, Power Operations.

Begin the load decrease at a rate directed by the _______ _______

Control Room Supervisor using the EHC LOAD DECREASE pushbutton.

Maintain Tavg with Tref with control rods and/or _______ _______

boron concentration adjustments.

2) Notify EDO of OTO procedure entry. _______

Note: After crew has reduced power by at least 2%, initiate Event F, 'A' S/G PORV fails open.

COMMENTS:

Denotes Critical Task Page 14 of 19

EVENT: F EXAM # ILE2002DSBU BRIEF DESCRIPTION: A S/G PORV Fails Open EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

S/G PORV OPEN 109F

1) Identify AB-PV-1 failure. _______

2) Implement OTO-AB-00001, Steam Dump Malfunction. _______

Place the controller for the failed valve in manual and _______ _______

close.

If at high load, ensure reactor power is less than 3565 _______ _______ _______

MWth.

3) Ensure rod control is in manual to prevent rod movement _______ _______

Notify the Count Room Tech of the valve opening and _______ _______

provide open/close times.

For an inoperable Atmospheric Steam Dump refer to _______

Technical Specification 3.7.4

Contact I&C to have the failure investigated and or _______

repaired.

4) Notify EDO of OTO procedure entry. _______

COMMENTS:

Denotes Critical Task Page 15 of 19

EVENT: G/H/I EXAM # ILE2002DSBU BRIEF DESCRIPTION: Loss of Site Power and NB02, RX Auto Trip Failure, TDAFP Auto Start Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

CA-BL-1 PCB V45 TRIP 03A TIE BKR PCB V43 TRIP 03C S/U XFMR PCB V41 TRIP 03E MT-CA-8 PCB V51 TRIP 04E MT-CA-7 PCB V85 TRIP 05E NB02 BUS LOCKOUT 21A R SPCTRM SSE EXCEEDED 98A SSE 98B

1) Recognize reactor trip from loss of off-site power and _______

implement E-0, Reactor Trip or Safety Injection.

Verify reactor trip _______ _______ _______

Manually trip reactor _______ _______ _______

Verify turbine trip

Verify power to NB01 and NB02 - recognize NB02 lockout

Check if SI is actuated Transition to ES-0.1, Reactor Trip Response and implement _______

CSF-1, Critical Safety Function Status Trees.

COMMENTS:

Denotes Critical Task Page 16 of 19

EVENT: G/H/I EXAM # ILE2002DSBU BRIEF DESCRIPTION: Loss of Site Power and NB02, RX Auto Trip Failure, TDAFP Auto Start Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

2) Perform actions of ES-0.1 _______

Check PZR PORV and Block Valve Status _______ _______ _______

Check RCS temperature _______ _______ _______

Check feedwater status _______ _______

Establish feed flow to SGs to obtain greater than 300,000 LBM/HR (manually start the TDAFP)

Recognize NE01 failure and transition to ECA-0.0, Loss Of _______

All AC Power.

COMMENTS:

Denotes Critical Task Page 17 of 19

EVENT: J EXAM # ILE2002DSBU BRIEF DESCRIPTION: Loss of All AC due to NE01 Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS ANNUNCIATORS:

NB01 BUS UV 18B DG NE01 TROUBLE 20D

1) Recognize NE01failure and implement ECA-0.0, Loss Of _______

All AC Power.

Ensure reactor trip

Verify turbine trip

Check if RCS is isolated Isolate Excess Letdown

Ensure AFW flow greater than 300,000 lbm/hr

Manually start the TDAFP _______ _______ _______

Try to restore power to either NB01 or NB02

Place Following Equipment in pull-to-lock position

Dispatch personnel to locally restore AC power using Attachment 9, Restoration of Offsite Power

Dispatch personnel to locally open breakers and close valves to isolate RCP seals

Check CST isolated from Hotwell

Check S/G status

Check if S/Gs are not faulted COMMENTS:

Denotes Critical Task Page 18 of 19

EVENT: J EXAM # ILE2002DSBU BRIEF DESCRIPTION: Loss of All AC due to NE01 Failure EXPECTED OPERATOR / PLANT RESPONSE RO BOP CRS

Check if S/G tubes are not ruptured

Check intact S/G levels

Check DC bus loads

Check CST to AFP suction header pressure - Greater than 7 PSIG

Depressurize Intact SGs to 220 PSIG COMMENTS:

Denotes Critical Task Page 19 of 19

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-B/U K/A NO: 022A4.01 COMPLETION TIME: 8 MINUTES K/A RATING: 3.6/3.6 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: CONTAINMENT COOLING SYSTEM TASK TITLE: START "A" CTMT COOLER FAN The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTN-GN-00001, CONTAINMENT COOLING AND CRDM COOLING, REVISION 11 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-B/U Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: "A" CONTAINMENT COOLER FAN WAS SECURED FOR ROUTINE MAINTENANCE. ONE (1) CAVITY COOLING FAN IS RUNNING, THREE (3) CRDM COOLING FANS ARE RUNNING, AND THE PZR COOLING FAN IS SECURED.

Initiating Cues: THE MAINTENANCE ON "A" CONTAINMENT COOLER FAN HAS BEEN COMPLETED. YOU HAVE BEEN DIRECTED TO START THE "A" CONTAINMENT COOLER FAN USING SECTION 4.2 OF OTN-GN-00001, CONTAINMENT COOLING AND CRDM COOLING. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-170 OR IC-166. STOP "A" CONTAINMENT COOLER WITH GN HIS-5 AND PLACE HANDSWITCH GN-HS-5 IN SLOW. PARAMETER, GNS001, HI VIB, DELAY 31 SECONDS, EVENT TRIGGER = 10, INSERT. EVENT, TRIGGER #10, TYPE "x20i64r.eq.true", ACCEPT NEW EVENT.

Task Standard: UPON COMPLETION OF THIS JPM, THE "A" CONTAINMENT COOLER FAN WILL HAVE BEEN STARTED AND SECURED DUE TO HIGH VIBRATIONS.

START TIME:

STOP TIME:

PAGE 1 of 6

JPM NO: ILE-2002-B/U TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTN-GN-00001, OPERATOR WITH OBTAIN A COPY OF Comments:

CONTAINMENT PROCEDURE COPY OTN-GN-00001, COOLING AND (GREEN SHEETS) CONTAINMENT CRDM COOLING COOLING AND CRDM COOLING S U

2. REVIEW IF ASKED, ALL OPERATOR SHOULD PRECAUTIONS AND PRECAUTIONS AND REVIEW THE Comments:

LIMITATIONS OF LIMITATIONS ARE PRECAUTIONS AND OTN-GN-00001, SATISFIED LIMITATIONS OF CONTAINMENT OTN-GN-00001, COOLING AND CONTAINMENT CRDM COOLING COOLING AND CRDM COOLING STEP 2.0 S U

3. REVIEW INITIAL IF ASKED, ALL OPERATOR SHOULD CONDITIONS OF INITIAL REVIEW THE INITIAL Comments:

OTN-GN-00001, CONDITIONS ARE CONDITIONS OF CONTAINMENT SATISFIED OTN-GN-00001, COOLING AND CONTAINMENT CRDM COOLING COOLING AND CRDM COOLING STEP 3.0

CRITICAL STEP PAGE 2 of 6

JPM NO: ILE-2002-B/U TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. PLACE SELECTOR GN HS-5 IS IN THE OPERATOR SHOULD SWITCH GN HS-5 FAST POSITION PLACE SELECTOR Comments:

FOR SGN01A IN THE SWITCH GN HS-5 FOR FAST POSITION SGN01A IN THE FAST POSITION STEP 4.2.1 LOCATED ON RL020 S U

5. VIBRATION ON OPERATOR SHOULD CONTAINMENT MONITOR Comments:

COOLERS MAY BE VIBRATION OF MONITORED AT SGN01A AT THE FOLLOWING COMPUTER POINT COMPUTER POINT GNY0007 FOR "A" CONTAINMENT SGN01A: GNY0007 COOLER FAN STEP 4.2.2 S U

6. START GN HIS-5 RED SLOW OPERATOR SHOULD CONTAINMENT AIR LIGHT IS LIT AND SELECT "RUN" ON Comments:

COOLER "A", THE GREEN LIGHT IS GN HIS-5, SGN01A, WITH OUT CONTAINMENT HANDSWITCH COOLER FAN "A" GN HIS-5 LOCATED ON RL020 STEP 4.2.3

CRITICAL STEP PAGE 3 of 6

JPM NO: ILE-2002-B/U TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. SGN01A WILL SHIFT 30 SECONDS AFTER OPERATOR SHOULD TO FAST AFTER 30 SELECTING RUN, THE OBSERVE THE RED Comments:

SECONDS RED FAST LIGHT IS FAST LIGHT LIT AND THE RED ILLUMINATE AND NOTE PRIOR TO SLOW LIGHT IS OUT THE RED SLOW STEP 4.2.4 LIGHT GO OUT LOCATED ON RL020 S U

8. IF ANY VIBRATION GNY0007 INDICATES OPERATOR SHOULD ALARM OCCURS, "A" CONTAINMENT DETERMINE "A" Comments:

CONSULT THE COOLER FAN HAS CONTAINMENT CONTROL ROOM HIGH VIBRATION COOLER HAS HIGH SUPERVISOR TO VIBRATION AND DETERMINE IF FAN THE CONTROL INFORM CONTROL SHOULD BE ROOM SUPERVISOR ROOM SUPERVISOR STOPPED, OR TO ACKNOWLEDGES RESET THE ALARM THE HIGH ON RP312 VIBRATION ON THE "A" CONTAINMENT STEP 4.2.4 COOLER S U

9. THE CONTROL ROOM SUPERVISOR Comments:

DIRECTS "A" CONTAINMENT COOLER FAN BE SECURED PER SECTION 4.3 OF OTN-GN-00001 NOTE: HAND APPLICANT SECTION 4.3 OF OTN-GN-00001 (PINK SHEET)

CRITICAL STEP PAGE 4 of 6

JPM NO: ILE-2002-B/U TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. STOP "A" GN HIS-5 GREEN OPERATOR SHOULD CONTAINMENT LIGHT IS LIT AND STOP "A" Comments:

COOLER FAN, RED LIGHT IS OUT CONTAINMENT SGN01A, WITH COOLER WITH HANDSWITCH HANDSWITCH GN HIS-5 GN HIS-5 STEP 4.3.1 S U

11. IF CONTAINMENT OPERATOR SHOULD COOLER 1D HAS REALIZE "A" Comments:

BEEN SECURED CONTAINMENT AND RCS COOLER FAN WAS TEMPERATURE IS SECURED

>120°F START THE PZR COOLING FAN STEP 4.3.2 S U

12. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM THE "A" THE TASK IS SUPERVISOR THAT CONTAINMENT COMPLETE THE "A" COOLER HAS BEEN CONTAINMENT SECURED COOLER HAS BEEN SECURED

CRITICAL STEP PAGE 5 of 6

JPM NO: ILE-2002-B/U TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 6 of 6

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: "A" CONTAINMENT COOLER FAN WAS SECURED FOR ROUTINE MAINTENANCE. ONE (1) CAVITY COOLING FAN IS RUNNING, THREE (3) CRDM COOLING FANS ARE RUNNING, AND THE PZR COOLING FAN IS SECURED.

Initiating Cues: THE MAINTENANCE ON "A" CONTAINMENT COOLER FAN HAS BEEN COMPLETED. YOU HAVE BEEN DIRECTED TO START THE "A" CONTAINMENT COOLER FAN USING SECTION 4.2 OF OTN-GN-00001, CONTAINMENT COOLING AND CRDM COOLING. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-C1 K/A NO: 013A4.01 COMPLETION TIME: 6 MINUTES K/A RATING: 4.5/4.8 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: ENGINEERED SAFETY FEATURES ACTUATION SYSTEM TASK TITLE: MANUALLY OPERATE MSIVs WHICH FAIL TO ACTUATE The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM X SIMULATOR/LAB PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

E-0, REACTOR TRIP OR SAFETY INJECTION, REVISION 1B5 OOA-SA-0001A, SA075A EMERGENCY OVERRIDE PANEL OPERATION, REVISION 2 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-C1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE CONTROL ROOM CREW IS RESPONDING TO A SAFETY INJECTION PER E-0, REACTOR TRIP OR SAFETY INJECTION.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED PER STEP 9 OF ATTACHMENT 12 OF E-0, REACTOR TRIP OR SAFETY INJECTION AND PERFORM ALL ACTIONS AND RESPONSE NOT OBTAINED ACTIONS PER STEP 9. INFORM THE CONTROL ROOM SUPERVISOR WHEN STEP 9 HAS BEEN COMPLETED.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Task Standard: UPON COMPLETION OF THIS JPM, ALL MSIVs WILL HAVE BEEN FAST CLOSED FROM SA075A.

START TIME:

STOP TIME:

PAGE 1 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD E-0, REACTOR TRIP OPERATOR WITH OBTAIN A COPY OF Comments:

OR SAFETY COPY OF E-0, REACTOR TRIP INJECTION, ATTACHMENT 12, OR SAFETY ATTACHMENT 12, STEP 9 INJECTION, STEP 9 (GREEN SHEET) ATTACHMENT 12, STEP 9 S U

2. CHECK IF SG ALL STEAM OPERATOR SHOULD PRESSURES ARE GENERATOR CHECK STEAM Comments:

LESS THAN OR PRESSURES ARE AT GENERATOR EQUAL TO 615 PSIG 590 PSIG PRESSURES ON RL026 STEP 9a S U

3. ENSURE MSIVs AND ALL MSIVs RED OPERATOR SHOULD MSIV BYPASS LIGHTS ARE LIT CHECK MSIV AND Comments:

VALVES - CLOSED AND GREEN LIGHTS BYPASS POSITIONS ARE OUT ON RL027 STEP 9b ALL MSIV BYPASSES GREEN LIGHTS ARE LIT AND RED LIGHTS ARE OUT

CRITICAL STEP PAGE 2 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. FAST CLOSE MSIV ALL MSIVs RED OPERATOR SHOULD AND BYPASS LIGHTS ARE LIT DEPRESS EITHER Comments:

VALVES USING AND GREEN LIGHTS AB-HS-79 AB-HS-79 OR ARE OUT OR AB-HS-80 AB-HS-80 ALL MSIV BYPASSES STEP 9b RNO GREEN LIGHTS ARE NOTE: OPERATOR LIT AND RED MAY USE BOTH LIGHTS ARE OUT S U

5. IF THE MSIVs DID CONTROL ROOM OPERATOR SHOULD NOT FAST CLOSE, SUPERVISOR LOCATE OPERATOR Comments:

THEN USE THE DIRECTS USE OF AID OOA-SA-0001A OPERATOR AIDS OOA-SA-0001A FOR AT SA075A OOA-SA-0001A OR SA075A OOA-SA-0001B TO FAST CLOSE MSIVs NOTE: HAND APPLICANT STEP 9b RNO OOA-SA-0001A (PINK SHEET)

S U

6. SECURE POWER TO OPERATOR SHOULD THE 3 PLC LOGIC LOCATE THE 3 LOGIC Comments:

CHANNELS AS CHANNEL POWER FOLLOWS: SWITCHES LOCATED ABOVE THE STEP 1.1 EMERGENCY OVERRIDE PANEL

CRITICAL STEP PAGE 3 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. SECURE POWER TO LOGIC CH. 1 POWER OPERATOR SHOULD THE LOGIC SWITCH IS IN OFF SECURE POWER TO Comments:

CHANNEL 1 BY LOGIC CHANNEL 1 PLACING LOGIC BY PLACING LOGIC CH. 1 SWITCH TO CH. 1 TO THE OFF THE OFF POSITION POSITION STEP 1.1 S U

8. SECURE POWER TO LOGIC CH. 2 POWER OPERATOR SHOULD THE LOGIC SWITCH IS IN OFF SECURE POWER TO Comments:

CHANNEL 2 BY LOGIC CHANNEL 2 PLACING LOGIC BY PLACING LOGIC CH. 2 SWITCH TO CH. 2 TO THE OFF THE OFF POSITION POSITION STEP 1.1 S U

9. SECURE POWER TO LOGIC CH. 3 POWER OPERATOR SHOULD THE LOGIC SWITCH IS IN OFF SECURE POWER TO Comments:

CHANNEL 3 BY LOGIC CHANNEL 3 PLACING LOGIC BY PLACING LOGIC CH. 3 SWITCH TO CH. 3 TO THE OFF THE OFF POSITION POSITION STEP 1.1

CRITICAL STEP PAGE 4 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. PLACE THE MSIV MSIV ENABLE OPERATOR SHOULD ENABLE SWITCH TO SWITCH IS IN THE PLACE THE MSIV Comments:

ENABLE ENABLE POSITION ENABLE SWITCH (S99) TO ENABLE ON STEP 1.2 THE EMERGENCY OVERRIDE PANEL S U

11. FAST CLOSE A MSIV A TOGGLE OPERATOR SHOULD MSIV (AB-HV-14) BY SWITCH IS IN THE PLACE MSIV A Comments:

PLACING AB-HV-14 (FC) FAST CLOSE TOGGLE SWITCH MSIV TOGGLE POSITION (S95) TO THE (FC)

SWITCH TO THE FAST CLOSE FC POSITION POSITION STEP 1.3 S U

12. FAST CLOSE B MSIV B TOGGLE OPERATOR SHOULD MSIV (AB-HV-17) BY SWITCH IS IN THE PLACE MSIV B Comments:

PLACING AB-HV-17 (FC) FAST CLOSE TOGGLE SWITCH MSIV TOGGLE POSITION (S96) TO THE (FC)

SWITCH TO THE FAST CLOSE FC POSITION POSITION STEP 1.3

CRITICAL STEP PAGE 5 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. FAST CLOSE C MSIV C TOGGLE OPERATOR SHOULD MSIV (AB-HV-20) BY SWITCH IS IN THE PLACE MSIV C Comments:

PLACING AB-HV-20 (FC) FAST CLOSE TOGGLE SWITCH MSIV TOGGLE POSITION (S97) TO THE (FC)

SWITCH TO THE FAST CLOSE FC POSITION POSITION STEP 1.3 S U

14. FAST CLOSE D MSIV D TOGGLE OPERATOR SHOULD MSIV (AB-HV-11) BY SWITCH IS IN THE PLACE MSIV D Comments:

PLACING AB-HV-11 (FC) FAST CLOSE TOGGLE SWITCH MSIV TOGGLE POSITION (S98) TO THE (FC)

SWITCH TO THE FAST CLOSE FC POSITION POSITION STEP 1.3 S U

15. IF THE MSIV DID ALL MSIVs GREEN OPERATOR SHOULD NOT CLOSE, GO TO LIGHTS ARE LIT CHECK MSIV Comments:

THE OTHER TRAIN AND RED LIGHTS POSITIONS ON RL027 MSFIS CABINET, ARE OUT SA075B AND PERFORM THE FAST CLOSURE OPERATION STEP 1.4

CRITICAL STEP PAGE 6 of 7

JPM NO: ILE-2002-C1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM STEP 9 IS COMPLETE THE TASK IS SUPERVISOR THAT AND ALL MSIVs COMPLETE STEP 9 IS COMPLETE HAVE BEEN AND ALL MSIVs CLOSED HAVE BEEN CLOSED S U

17. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 7 of 7

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE CONTROL ROOM CREW IS RESPONDING TO A SAFETY INJECTION PER E-0, REACTOR TRIP OR SAFETY INJECTION.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED PER STEP 9 OF ATTACHMENT 12 OF E-0, REACTOR TRIP OR SAFETY INJECTION AND PERFORM ALL ACTIONS AND RESPONSE NOT OBTAINED ACTIONS PER STEP 9. INFORM THE CONTROL ROOM SUPERVISOR WHEN STEP 9 HAS BEEN COMPLETED.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-P1 K/A NO: 004A2.14 COMPLETION TIME: 11 MINUTES K/A RATING: 3.8/3.9 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: CHEMICAL AND VOLUME CONTROL SYSTEM TASK TITLE: EMERGENCY BORATION PER FR-S.1 The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION, REVISION 1B3 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-P1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THE "A" S/G LEVEL HAS DECREASED BELOW THE LO LO LEVEL REACTOR TRIP SETPOINT AND THE REACTOR HAS FAILED TO TRIP. THE CREW HAS ATTEMPTED TO MANUALLY TRIP THE REACTOR. THE ATTEMPT WAS UNSUCCESSFUL.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO INITIATE IMMEDIATE BORATION OF THE RCS AT STEP 4 OF FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL BE BORATING THE RCS THROUGH BGV0177.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: ILE-2002-P1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD FR-S.1, RESPONSE OPERATOR WITH OBTAIN A COPY OF Comments:

TO NUCLEAR PROCEDURE COPY FR-S.1, RESPONSE TO POWER (GREEN SHEET) NUCLEAR POWER GENERATION GENERATION S U

2. ENSURE AT LEAST BG-HIS-1A, CCP "A" OPERATOR SHOULD ONE (1) CCP OR NCP RED LIGHT IS LIT LOOK FOR A RED Comments:

IS RUNNING AND GREEN LIGHT LIGHT LIT ON ANY IS OUT OF THE FOLLOWING STEP 4.a PUMPS:

CCP "A" BG-HIS-1A CCP "B" BG-HIS-2A NCP BG HIS-3 LOCATED ON RL001 S U

3. OPEN EMERGENCY BG-HIS-8104 GREEN OPERATOR SHOULD BORATE TO LIGHT REMAINS LIT ATTEMPT TO OPEN Comments:

CHARGING PUMPS AND RED LIGHT EMERGENCY SUCTION VALVE DOES NOT COME ON BORATE TO BG-HIS-8104 CHARGING PUMPS SUCTION VALVE STEP 4.b.(1) BG-HIS-8104 LOCATED ON RL001

CRITICAL STEP PAGE 2 of 5

JPM NO: ILE-2002-P1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. INITIATE PROVIDE OPERATOR SHOULD IMMEDIATE OPERATOR WITH A REALIZE THAT Comments:

BORATION OF RCS COPY OF BGHV8104 DID NOT BY PERFORMING ATTACHMENT 1 OPEN AND GO TO ATTACHMENT 1, (PINK SHEET) ATTACHMENT 1 IMMEDIATE RCS BORATION STEP 4.b RNO S U

5. ENSURE A CCP OR BG-HIS-1A, CCP "A" OPERATOR SHOULD THE NCP IS RED LIGHT IS LIT LOOK FOR A RED Comments:

RUNNING AND GREEN LIGHT LIGHT LIT ON ANY IS OUT OF THE FOLLOWING STEP 1.a.(1) PUMPS:

CCP "A" BG-HIS-1A CCP "B" BG-HIS-2A NCP BG HIS-3 LOCATED ON RL001 S U

6. OPEN CCP BN-HIS-112D GREEN OPERATOR SHOULD SUCTIONS FROM LIGHT REMAINS LIT ATTEMPT TO OPEN Comments:

RWST, BN-HIS-112D AND RED LIGHT CCP SUCTIONS FROM AND BN-HIS-112E DOES NOT COME ON RWST, BN-HIS-112D AND BN-HIS-112E STEP 1.a.(2) BN-HIS-112E GREEN LIGHT REMAINS LIT LOCATED ON RL001 AND RED LIGHT DOES NOT COME ON

CRITICAL STEP PAGE 3 of 5

JPM NO: ILE-2002-P1 TASK NUMBER - ELEMENT CUE STANDARD SCORE

7. DIRECT AN YOU ARE NOW THE OPERATOR SHOULD EQUIPMENT PRIMARY EO AND DIRECT AN OPERATOR (EO) TO THE REACTOR EQUIPMENT OPEN ALTERNATE OPERATOR HAS OPERATOR (EO) TO IMMEDIATE DIRECTED YOU TO OPEN ALTERNATE BORATION VALVE LOCALLY OPEN IMMEDIATE BGV0177 ALTERNATE BORATION VALVE IMMEDIATE BGV0177 STEP 1.b.(1) BORATION VALVE BGV0177 LOCATED IN AB 1974, "A" SI PUMP ROOM S U

8. PROCEED TO "A" OPERATOR SHOULD SAFETY INJECTION GO TO HP ACCESS, Comments:

PUMP ROOM THEN PROCEED TO THE AUX BLDG 1974' STEP 1.b.(1) LEVEL, "A" SI PUMP ROOM S U

9. LOCATE OPERATOR SHOULD ALTERNATE LOCATE ALTERNATE Comments:

IMMEDIATE IMMEDIATE BORATION VALVE BORATION VALVE, BGV0177 BGV0177, ALONG THE NORTH WALL IN THE STEP 1.b.(1) "A" SI PUMP ROOM

CRITICAL STEP PAGE 4 of 5

JPM NO: ILE-2002-P1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. OPEN ALTERNATE BGV0177 IS OPEN OPERATOR SHOULD IMMEDIATE TURN THE Comments:

BORATION VALVE HANDWHEEL FOR BGV0177 ALTERNATE IMMEDIATE STEP 1.b.(1) BORATION VALVE BGV0177, IN THE COUNTER-CLOCKWISE DIRECTION UNTIL OPEN S U

11. INFORM THE THE REACTOR OPERATOR SHOULD REACTOR OPERATOR INFORM THE Comments:

OPERATOR THAT ACKNOWLEDGES REACTOR OPERATOR BGV0177 IS OPEN THE TASK IS THAT BGV0177 IS COMPLETE OPEN S U

12. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 5 of 5

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THE "A" S/G LEVEL HAS DECREASED BELOW THE LO LO LEVEL REACTOR TRIP SETPOINT AND THE REACTOR HAS FAILED TO TRIP. THE CREW HAS ATTEMPTED TO MANUALLY TRIP THE REACTOR. THE ATTEMPT WAS UNSUCCESSFUL.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (REACTOR OPERATOR) TO INITIATE IMMEDIATE BORATION OF THE RCS AT STEP 4 OF FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-P2 K/A NO: 103A2.03 COMPLETION TIME: 11 MINUTES K/A RATING: 3.5/3.8 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: CONTAINMENT SYSTEM TASK TITLE: LOCALLY CLOSE VALVES FOR CIS A The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

ECA-0.0, LOSS OF ALL AC POWER, REVISION 1B2 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-P2 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THERE HAS BEEN A LOSS OF ALL AC POWER AT THE CALLAWAY PLANT.

THE CONTROL ROOM HAS ENTERED EMERGENCY PROCEDURE, ECA-0.0, LOSS OF ALL AC POWER.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO PERFORM ATTACHMENT 3 (CISA-CONTINGENCY ACTIONS) OF ECA-0.0, LOSS OF ALL AC POWER. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Task Standard: UPON COMPLETION OF THIS JPM, VALVES ASSOCIATED WITH PENETRATIONS 23, 24, 25, 26, 32 AND 65 WILL BE CLOSED.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: ILE-2002-P2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD ATTACHMENT 3 OF OPERATOR WITH A OBTAIN A COPY OF Comments:

ECA-0.0, LOSS OF COPY OF ATTACHMENT 3 OF ALL AC POWER ATTACHMENT 3 ECA-0.0, LOSS OF ALL (GREEN SHEET) AC POWER S U

2. GO TO THE AUX OPERATOR SHOULD BUILDING SOUTH GO TO HP ACCESS, Comments:

PIPING THEN PROCEED TO PENETRATION THE SOUTH PIPING ROOM 1322 PENETRATION ROOM 1322 STEP 1.0 S U

3. ENSURE CLOSED BG-HV-8100 IS OPEN OPERATOR SHOULD BG-HV-8100, SEAL ENSURE CLOSED Comments:

WTR RTN OUTER OPERATOR SHOULD BG-HV-8100, SEAL CTMT ISO VLV DEMONSTRATE WTR RTN OUTER KNOWLEDGE OF CTMT ISO VLV STEP 1.a HOW TO CLOSE A MOTOR OPERATED NOTE: BG-HV-8100 IS VALVE (DECLUTCH A MOTOR OPERATED AND ROTATE THE VALVE @ PEN 24 HANDWHEEL IN THE CLOSED DIRECTION)

BG-HV-8100 IS NOW CLOSED

CRITICAL STEP PAGE 2 of 5

JPM NO: ILE-2002-P2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. ENSURE CLOSED BG-HV-8152 IS OPEN OPERATOR SHOULD BG-HV-8152, CVCS ENSURE CLOSED Comments:

LTDN SYS OUT OPERATOR SHOULD BG-HV-8152, CVCS CTMT ISO DEMONSTRATE LTDN SYS OUT CTMT KNOWLEDGE OF ISO STEP 1.b HOW TO CLOSE AN AIR OPERATED NOTE: BG-HV-8152 IS VALVE (VALVE WILL AN AIR OPERATED FAIL CLOSED ON VALVE @ PEN 23 LOSS OF AIR)

BG-HV-8152 IS NOW CLOSED S U

5. ENSURE CLOSED BL-HV-8047 IS OPERATOR SHOULD BL-HV-8047, RX M/U CLOSED ENSURE CLOSED Comments:

WTR OUTER CTMT BL-HV-8047, RX M/U ISO WTR OUTER CTMT ISO STEP 1.c NOTE: BL-HV-8047 IS AN AIR OPERATED VALVE @ PEN 25 S U

6. ENSURE CLOSED HB-HV-7136 IS OPERATOR SHOULD HB-HV-7136, RCDT CLOSED ENSURE CLOSED Comments:

HX OUT HDR OUTER HB-HV-7136, RCDT CTMT ISO HX OUT HDR OUTER CTMT ISO STEP 1.d NOTE: HB-HV-7136 IS AN AIR OPERATED VALVE @ PEN 26

CRITICAL STEP PAGE 3 of 5

JPM NO: ILE-2002-P2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. ENSURE CLOSED LF-FV-0096 IS OPERATOR SHOULD LF-FV-0096, CTMT CLOSED ENSURE CLOSED Comments:

NORM SUMP PMPS LF-FV-0096, CTMT DISCH HDR AUX NORM SUMP PMPS BLDG FCV DISCH HDR AUX BLDG FCV STEP 1.e NOTE: LF-FV-0096 IS AN AIR OPERATED VALVE @ PEN 32 S U

8. ENSURE CLOSED GS-HV-21 IS CLOSED OPERATOR SHOULD GS-HV-21, H2 PURGE ENSURE CLOSED Comments:

OUTER CTMT ISO GS-HV-21, H2 PURGE OUTER CTMT ISO STEP 1.f NOTE: GS-HV-21 IS A MOTOR OPERATED VALVE @ PEN 65 S U

9. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM ATTACHMENT 3 OF THE TASK IS SUPERVISOR THAT ECA-0.0 IS COMPLETE ATTACHMENT 3 OF COMPLETE ECA-0.0 IS COMPLETE

CRITICAL STEP PAGE 4 of 5

JPM NO: ILE-2002-P2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 5 of 5

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THERE HAS BEEN A LOSS OF ALL AC POWER AT THE CALLAWAY PLANT.

THE CONTROL ROOM HAS ENTERED EMERGENCY PROCEDURE, ECA-0.0, LOSS OF ALL AC POWER.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO PERFORM ATTACHMENT 3 (CISA-CONTINGENCY ACTIONS) OF ECA-0.0, LOSS OF ALL AC POWER. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-P3 K/A NO: 064A4.01 COMPLETION TIME: 11 MINUTES K/A RATING: 4.0/4.3 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: EMERGENCY DIESEL GENERATOR SYSTEM TASK TITLE: LOCALLY START NE01 EMERGENCY DG The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

ECA-0.0, LOSS OF ALL AC POWER, REVISION 1B2 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-P3 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THERE HAS BEEN A LOSS OF ALL AC POWER AT THE CALLAWAY PLANT.

THE CONTROL ROOM HAS ENTERED EMERGENCY PROCEDURE, ECA-0.0, LOSS OF ALL AC POWER. THE CONTROL ROOM SUPERVISOR IS AT STEP 5.a OF ECA-0.0, LOSS OF ALL AC POWER, AND DETERMINED THAT NEITHER EMERGENCY DIESEL GENERATOR (NE01 OR NE02) HAS STARTED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR DIRECTS YOU TO LOCALLY START NE01 PER ATTACHMENT 2 (LOCALLY STARTING EMERGENCY DIESEL GENERATOR) OF ECA-0.0, LOSS OF ALL AC POWER. THE CAUSE FOR THE FAILURE TO START IS UNKNOWN. INFORM THE CONTROL ROOM SUPERVISOR WHEN NE01 IS STARTED AND THE MASTER TRANSFER SWITCH IS IN "AUTO".

ALL OPERATOR ACTIONS ARE TO BE SIMULATED ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes:

Task Standard: UPON COMPLETION OF THIS JPM, EMERGENCY DIESEL GENERATOR NE01 WILL BE RUNNING WITH ITS MASTER TRANSFER SWITCH (KJ-HS-9) IN "AUTO".

START TIME:

STOP TIME:

PAGE 1 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD ATTACHMENT 2 OF OPERATOR WITH A OBTAIN A COPY OF Comments:

ECA-0.0, LOSS OF COPY OF ATTACHMENT 2 OF ALL AC POWER ATTACHMENT 2 ECA-0.0, LOSS OF ALL (GREEN SHEETS) AC POWER S U

2. REVIEW NOTES ON OPERATOR SHOULD ENGINE SHUTDOWN REVIEW NOTES Comments:

RELAY AND START FAILURE NOTES PRIOR TO STEP A S U

3. DETERMINE AND NO ANNUNCIATORS OPERATOR SHOULD CORRECT CAUSE OF ARE IN ALARM ON ATTEMPT TO Comments:

THE DIESEL PANEL KJ-121 DETERMINE CAUSE GENERATORS OF FAILURE FAILURE TO START NOTE: THE CAUSE STEP A FOR THE FAILURE TO START IS UNKNOWN (GIVEN IN INITIATING CUES)

CRITICAL STEP PAGE 2 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. PERFORM PART D OPERATOR SHOULD FOR UNKNOWN DETERMINE PART D Comments:

FAILURES TO START SHOULD BE PERFORMED STEP A S U

5. PERFORM A THERE ARE NO OPERATOR SHOULD WALKDOWN OF OBVIOUS ADVERSE PERFORM A Comments:

NE01 TO ENSURE CONDITIONS WALKDOWN OF NE01 THAT NO OBVIOUS TO ENSURE THAT NO ADVERSE OBVIOUS ADVERSE CONDITIONS EXIST CONDITIONS EXIST PRIOR TO STARTING PRIOR TO STARTING THE DIESEL THE DIESEL STEP D.2.a S U

6. ON PANEL NE107, NE01 DID NOT OPERATOR SHOULD BREAK THE GLASS START USE THE ATTACHED Comments:

ON THE HAMMER TO BREAK EMERGENCY START THE GLASS ON THE POP-OUT BUTTON EMERGENCY START (KJ-HS-1D) POP-OUT BUTTON (KJ-HS-1D)

STEP D.2.b NOTE: THIS CAN ALSO BE PERFORMED BY UNSCREWING THE GLASS COVER

CRITICAL STEP PAGE 3 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. PLACE THE MASTER KJ-HS-9 IS IN OPERATOR SHOULD TRANSFER SWITCH LOC/MAN PLACE THE MASTER Comments:

(KJ-HS-9) IN TRANSFER SWITCH LOC/MAN AUDIBLE ALARM (KJ-HS-9) IN ON PANEL KJ-121 LOC/MAN STEP D.2.d "SWITCH NOT IN OPERATOR SHOULD AUTO" ACKNOWLEDGE ANNUNCIATOR IS IN ALARM ALARM ALARM IS SILENCED S U

8. PRESS AND HOLD NE01 DID NOT OPERATOR SHOULD THE LOCAL START START PRESS AND HOLD Comments:

PUSHBUTTON THE LOCAL START (KJ-HS-1C) PUSHBUTTON (KJ-HS-1C)

STEP D.2.e S U

9. PLACE THE MASTER WHEN KJ-HS-9 IS OPERATOR SHOULD TRANSFER SWITCH PLACED IN AUTO, PLACE THE MASTER Comments:

(KJ-HS-9) IN AUTO THE "SWITCH NOT TRANSFER SWITCH IN AUTO" (KJ-HS-9) IN AUTO STEP D.2.f ANNUNCIATOR CLEARS ON PANEL KJ-121 NE01 DID NOT START

CRITICAL STEP PAGE 4 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. PLACE THE MASTER KJ-HS-9 IS IN OPERATOR SHOULD TRANSFER SWITCH LOC/MAN PLACE THE MASTER Comments:

KJ-HS-9 IN LOC/MAN TRANSFER SWITCH AUDIBLE ALARM KJ-HS-9 IN LOC/MAN STEP D.2.h ON PANEL KJ-121 OPERATOR SHOULD "SWITCH NOT IN ACKNOWLEDGE AUTO" ALARM ANNUNCIATOR IS IN ALARM ALARM IS SILENCED S U

11. LOCATE THE OPERATOR SHOULD MANUAL AIR START GO TO THE SOUTH Comments:

CONTROL VALVE END OF THE D/G AND ON THE UPPER GO UP THE LADDER GENERATOR END TO CLIMB ON TOP OF OF THE DIESEL THE DIESEL AT THE GENERATOR END STEP D.2.h S U

12. REMOVE THE CAP CAP IS REMOVED OPERATOR SHOULD ON TOP OF THE REMOVE THE CAP Comments:

MANUAL AIR START ON TOP OF THE CONTROL VALVE MANUAL AIR START HOUSING CONTROL VALVE HOUSING STEP D.2.h.(1)

CRITICAL STEP PAGE 5 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. REMOVE THE HANDLE IS IN THE OPERATOR SHOULD HANDLE ATTACHED SLOT ON TOP OF REMOVE THE Comments:

TO THE SIDE OF THE THE AIR START HANDLE ATTACHED AIR START CONTROL VALVE TO THE SIDE OF THE CONTROL VALVE AIR START CONTROL AND PLACE THE VALVE AND PLACE HANDLE IN THE THE HANDLE IN THE SLOT ON TOP OF SLOT ON TOP OF THE THE AIR START AIR START CONTROL CONTROL VALVE VALVE STEP D.2.h.(2)

S U

14. PUSH THE HANDLE THE HANDLE HAS OPERATOR SHOULD DOWN TO START BEEN PUSHED PUSH THE HANDLE Comments:

THE ENGINE DOWN DOWN TO START THE ENGINE STEP D.2.h.(3) NE01 HAS STARTED S U

15. PLACE THE MASTER WHEN KJ-HS-9 IS OPERATOR SHOULD TRANSFER SWITCH PLACED IN AUTO, PLACE THE MASTER Comments:

KJ-HS-9 IN AUTO THE "SWITCH NOT TRANSFER SWITCH IN AUTO" KJ-HS-9 IN AUTO STEP D.2.i ANNUNCIATOR CLEARS ON PANEL KJ-121

CRITICAL STEP PAGE 6 of 7

JPM NO: ILE-2002-P3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM NE01 HAS STARTED THE TASK IS SUPERVISOR THAT AND THE MASTER COMPLETE NE01 HAS STARTED TRANSFER SWITCH AND THE MASTER IS IN "AUTO" TRANSFER SWITCH IS IN "AUTO" S U

17. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 7 of 7

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: THERE HAS BEEN A LOSS OF ALL AC POWER AT THE CALLAWAY PLANT.

THE CONTROL ROOM HAS ENTERED EMERGENCY PROCEDURE, ECA-0.0, LOSS OF ALL AC POWER. THE CONTROL ROOM SUPERVISOR IS AT STEP 5.a OF ECA-0.0, LOSS OF ALL AC POWER, AND DETERMINED THAT NEITHER EMERGENCY DIESEL GENERATOR (NE01 OR NE02) HAS STARTED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR DIRECTS YOU TO LOCALLY START NE01 PER ATTACHMENT 2 (LOCALLY STARTING EMERGENCY DIESEL GENERATOR) OF ECA-0.0, LOSS OF ALL AC POWER. THE CAUSE FOR THE FAILURE TO START IS UNKNOWN. INFORM THE CONTROL ROOM SUPERVISOR WHEN NE01 IS STARTED AND THE MASTER TRANSFER SWITCH IS IN "AUTO".

ALL OPERATOR ACTIONS ARE TO BE SIMULATED

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S1 K/A NO: 001A4.06 COMPLETION TIME: 15 MINUTES K/A RATING: 2.9/3.2 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: CONTROL ROD DRIVE SYSTEM TASK TITLE: RECOVER A DROPPED CONTROL ROD The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTO-SF-00003, DROPPED CONTROL ROD, REVISION 8 TOOLS/EQUIPMENT: REACTOR OPERATOR LOG SHEET FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-S1 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THIRTY MINUTES AGO, CONTROL ROD H-8 DROPPED INTO THE CORE. ALL IMMEDIATE ACTIONS HAVE BEEN PERFORMED. THE PLANT HAS BEEN STABILIZED WITH TAVG AND TREF T

<3°F. THE EDO AND REACTOR ENGINEER HAVE AGREED THE PROBLEM IS CORRECTED AND THE PLANT IS READY FOR RECOVERY. CURRENTLY IN T/S LCO 3.1.4, CONDITION "B".

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO RECOVER THE DROPPED ROD (H-8) BY PERFORMING STEPS 6.1 THROUGH 6.3.11 OF OTO-SF-00003, DROPPED CONTROL ROD. THE PRIMARY EO IS STATIONED AT THE ROD CONTROL CABINETS IF YOU NEED HIS ASSISTANCE. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-170. (MALFUNCTION CRF4_53 IS USED TO DROP ROD H-8)

Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL HAVE ALIGNED CONTROL ROD H-8 WITH ITS GROUP + 4 STEPS.

START TIME:

STOP TIME:

PAGE 1 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTO-SF-00003, OPERATOR WITH OBTAIN A COPY OF Comments:

DROPPED CONTROL PROCEDURE COPY OTO-SF-00003, ROD (GREEN SHEETS) DROPPED CONTROL ROD S U

2. DETERMINE THE OPERATOR SHOULD NEED TO PERFORM DETERMINE A QPTR Comments:

A QPTR IS NOT REQUIRED STEP 6.1 S U

3. IF ANNUNCIATOR ANNUNCIATORS 78B, OPERATOR SHOULD 78B OR 78C OR 78F 78C AND 78F NOT LIT. RECOGNIZE Comments:

IS IN ALARM, ANNUNCIATORS 78B, CHECK COMPUTER ALL ALARMS ARE 78C AND 78F ARE POINTS REU1151 OPERABLE IF NOT IN ALARM THRU REU1162 TO CHECKED DETERMINE QUADRANT POWER ALL COMPUTER TILT RATIO POINTS INDICATE

< 1.02 STEP 6.1.1

CRITICAL STEP PAGE 2 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. IF QPTR IS GREATER ALL COMPUTER OPERATOR SHOULD THAN 1.02, REFER POINTS INDICATE DETERMINE QPTR IS Comments:

TO T/S LCO 3.2.4 QPTR < 1.02 NOT REQUIRED STEP 6.1.1.1 S U

5. REFER TO NOTE: GIVEN IN THE OPERATOR MAY T/S LCO 3.1.4 INITIAL CONDITIONS REFER TO T/S LCO Comments:

3.1.4 STEP 6.2 S U

6. IF DROPPED ROD REACTOR POWER IS OPERATOR SHOULD OCCURS DURING A APPROXIMATELY RECOGNIZE THAT Comments:

STARTUP OR AT A 99% THE REACTOR HAS LOW ENOUGH NOT GONE POWER SUCH THAT SUBCRITICAL THE REACTOR GOES SUBCRITICAL, THE REACTOR SHOULD BE SHUTDOWN TO MODE 3 STEP 6.2.1

CRITICAL STEP PAGE 3 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. IF DROPPED ROD ROD DROPPED 30 OPERATOR SHOULD RECOVERY IS NOT MINUTES AGO RECOGNIZE THE Comments:

GOING TO BE DROPPED ROD WILL COMPLETED PRIOR NOTE: GIVEN IN BE RECOVERED TO EXCEEDING INITIAL CONDITIONS WITHIN 1 HOUR 1 HOUR, REACTOR ENGINEERING MUST BE CONTACTED TO DETERMINE GUIDELINES FOR RECOVERY STEP 6.2.2 S U

8. REACTOR IF ASKED, REACTOR THE OPERATOR MAY ENGINEERING AND ENGINEERING AND ASK IF REACTOR Comments:

THE EDO MUST BE EDO HAVE BEEN ENGINEERING OR NOTIFIED OF A ROD NOTIFIED THAT THE EDO ARE DROP PRIOR TO THE DROPPED ROD AWARE THAT THE RECOVERY IS READY TO BE DROPPED ROD IS RECOVERED READY TO BE STEP 6.2.4 RECOVERED NOTE: GIVEN IN INITIAL CONDITIONS S U

9. PLACE THE ROD CB "D" IS SELECTED OPERATOR SHOULD BANK AUTO/MAN WITH SE-HS-9 SELECT CB "D" ON Comments:

SEL SWITCH, THE ROD BANK SE HS-9, TO THE AUTO/MAN SEL AFFECTED BANK SWITCH, SE-HS-9 ON POSITION RL003 STEP 6.3.1

CRITICAL STEP PAGE 4 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. ENSURE THAT THE PRIMARY EO THE OPERATOR PROPER GROUP REPORTS THAT SHOULD CONTACT Comments:

SELECT LIGHT IS LIT GROUP SELECT THE PRIMARY EO ON THE POWER LIGHT "B" IS LIT ON AND ASK WHICH CABINETS WITH POWER CABINETS GROUP SELECT SELECTED RODS 1 BD AND 2 BD LIGHT IS ON POWER PRIOR TO MOVING CABINETS 1 BD AND ROD BANKS 2 BD STEP 6.3.1.1 S U

11. LOCATE CONTROL OPERATOR SHOULD ROD DISCONNECT GO TO THE CONTROL Comments:

SWITCH BOX ROD DISCONNECT SWITCH BOX IN THE STEP 6.3.2 BACK OF THE CONTROL ROOM (IN THE NIS CABINET IN SIMULATOR)

S U

12. PLACE CONTROL D-4 IS OPERATOR SHOULD ROD D-4 IN THE DISCONNECTED TAKE THE TOGGLE Comments:

DISCONNECTED SWITCH FOR D-4 AND POSITION MOVE IT UP TO THE ROD DISCONNECTED STEP 6.3.2 POSITION NOTE: STEPS 12, 13, 14 AND 15 MAY BE ACCOMPLISHED IN ANY ORDER

CRITICAL STEP PAGE 5 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. PLACE CONTROL M-12 IS OPERATOR SHOULD ROD M-12 IN THE DISCONNECTED TAKE THE TOGGLE Comments:

DISCONNECTED SWITCH FOR M-12 POSITION AND MOVE IT UP TO THE ROD STEP 6.3.2 DISCONNECT POSITION NOTE: STEPS 12, 13, 14 AND 15 MAY BE ACCOMPLISHED IN ANY ORDER S U

14. PLACE CONTROL D-12 IS OPERATOR SHOULD ROD D-12 IN THE DISCONNECTED TAKE THE TOGGLE Comments:

DISCONNECTED SWITCH FOR D-12 POSITION AND MOVE IT UP TO THE ROD STEP 6.3.2 DISCONNECT POSITION NOTE: STEPS 12, 13, 14 AND 15 MAY BE ACCOMPLISHED IN ANY ORDER S U

15. PLACE CONTROL M-4 IS OPERATOR SHOULD ROD M-4 IN THE DISCONNECTED TAKE THE TOGGLE Comments:

DISCONNECTED SWITCH FOR M-4 POSITION AND MOVE IT UP TO THE ROD STEP 6.3.2 DISCONNECT POSITION NOTE: STEPS 12, 13, 14 AND 15 MAY BE ACCOMPLISHED IN ANY ORDER

CRITICAL STEP PAGE 6 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. INDEPENDENTLY INDEPENDENT OPERATOR SHOULD VERIFY ALL LIFT VERIFICATION HAS REQUEST THAT AN Comments:

COIL DISCONNECT BEEN PERFORMED INDEPENDENT SWITCHES FOR THE VERIFICATION BE AFFECTED BANK, PERFORMED EXCEPT THE DROPPED ROD, ARE IN THE DISCONNECTED POSITION STEP 6.3.2.1 S U

17. RECORD IN THE RO NOTE: SEE STEP OPERATOR SHOULD LOG THE POSITION COUNTER FOR RECORD READING Comments:

OF THE "GROUP" CONTROL BANK D-2 FROM SC CB-D2, STEP COUNTER FOR FOR READING CTRL BANK D2 STEP THE GROUP COUNTER, ON RL003 CONTAINING THE DROPPED ROD STEP 6.3.3 S U

18. MANUALLY RESET SC CB-D2 IS RESET OPERATOR SHOULD TO ZERO (0) THE TO ZERO (0) OPEN WINDOW AND Comments:

STEP COUNTER FOR RESET THE STEP THE AFFECTED COUNTER TO ZERO GROUP (0) BY HAND FOR CONTROL BANK D STEP 6.3.4 GROUP 2

CRITICAL STEP PAGE 7 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. AT THE PULSE-TO- PRIMARY EO HAS OPERATOR SHOULD ANALOG BEEN CONTACTED CONTACT PRIMARY Comments:

CONVERTER AND IS HOLDING THE EO TO HOLD THE CABINET, HOLD AUTO-MANUAL SWITCH IN THE THE AUTO-MANUAL SWITCH IN MANUAL POSITION SWITCH IN THE "MANUAL" MANUAL POSITION NOTE:

REMOTE, SFS001, STEP 6.3.5.1 DE-ENERGIZE, INSERT S U

20. BEGIN ANNUNCIATOR 79A, OPERATOR SHOULD WITHDRAWING THE ROD CTRL URG FAIL, PLACE IN-HOLD-OUT Comments:

DROPPED ROD TO HAS LIT SWITCH IN THE OUT THE GROUP STEP POSITION AND COUNTER POSITION ONLY H-8 IS MOVING VERIFY THAT ONLY RECORDED IN STEP H-8 IS MOVING 6.3.3 ANNUNCIATOR IS ACKNOWLEDGED OPERATOR SHOULD STEP 6.3.6 ACKNOWLEDGE ANNUNCIATOR 79A S U

21. BORATE OR ADJUST OPERATOR SHOULD TURBINE LOAD AS BORATE THE RCS OR Comments:

REQUIRED TO ADJUST TURBINE MAINTAIN TAVE - LOAD AS REQUIRED TREF T < 3°F TO MAINTAIN THE TAVE - TREF T < 3°F STEP 6.3.6.2

CRITICAL STEP PAGE 8 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

22. WITHDRAW ROD TO ROD H-8 IS NOW AT OPERATOR SHOULD INITIAL STEP THE DESIRED STEP WITHDRAW ROD TO Comments:

COUNTER READING COUNTER POSITION INITIAL STEP

+/- 4 STEPS COUNTER READING

+/-4 STEPS STEP 6.3.6 S U

23. COMPARE THE DRPI THE DROPPED ROD IS OPERATOR SHOULD ASSOCIATED WITH AT THE SAME EXAMINE ROD POS Comments:

THE BANK OF THE HEIGHT AS ITS BANK INDICATION, SF074, DROPPED ROD ON PANEL RL022 TO WITH THE DROPPED ENSURE THE ROD DRPI TO DROPPED ROD ENSURE THEY POSITION AGREES AGREE WITH ITS ASSOCIATED BANK STEP 6.3.7 POSITION S U

24. RELEASE THE "AUTO-MANUAL" OPERATOR SHOULD "AUTO-MANUAL" SWITCH IS IN CONTACT THE Comments:

SWITCH AT THE AUTOMATIC PRIMARY EO AND PULSE-TO-ANALOG INSTRUCT HIM TO CONVERTER RELEASE THE CABINET "AUTO-MANUAL" SWITCH STEP 6.3.8

CRITICAL STEP PAGE 9 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

25. RESET THE ROD ROD CONTROL OPERATOR SHOULD CTRL URG FAIL URGENT FAILURE IS DEPRESS SF HS-4, Comments:

ALARM USING RESET ROD CTRL ALARM SF HS-4, ROD RESET, ON PANEL CONTROL ALARM RL003 RESET PUSHBUTTON ON PANEL RL003 STEP 6.3.9 S U

26. LOCATE ROD OPERATOR SHOULD DISCONNECT RETURN TO THE Comments:

SWITCH BOX CONTROL ROD DISCONNECT STEP 6.3.10 SWITCH BOX S U

27. PLACE CONTROL D-4 IS CONNECTED OPERATOR SHOULD ROD D-4 IN THE TAKE THE TOGGLE Comments:

CONNECTED SWITCH FOR D-4 AND POSITION MOVE IT DOWN TO THE ROD STEP 6.3.10 CONNECTED POSITION NOTE: STEPS 27, 28, 29 AND 30 MAY BE ACCOMPLISHED IN ANY ORDER

CRITICAL STEP PAGE 10 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

28. PLACE CONTROL M-12 IS CONNECTED OPERATOR SHOULD ROD M-12 IN THE TAKE THE TOGGLE Comments:

CONNECTED SWITCH FOR M-12 POSITION AND MOVE IT DOWN TO THE ROD STEP 6.3.10 CONNECTED POSITION NOTE: STEPS 27, 28, 29 AND 30 MAY BE ACCOMPLISHED IN ANY ORDER S U

29. PLACE CONTROL D-12 IS CONNECTED OPERATOR SHOULD ROD D-12 IN THE TAKE THE TOGGLE Comments:

CONNECTED SWITCH FOR D-12 POSITION AND MOVE IT DOWN TO THE ROD STEP 6.3.10 CONNECTED POSITION NOTE: STEPS 27, 28, 29 AND 30 MAY BE ACCOMPLISHED IN ANY ORDER S U

30. PLACE CONTROL M-4 IS CONNECTED OPERATOR SHOULD ROD M-4 IN THE TAKE THE TOGGLE Comments:

CONNECTED SWITCH FOR M-4 POSITION AND MOVE IT DOWN TO THE ROD STEP 6.3.10 CONNECTED POSITION NOTE: STEPS 27, 28, 29 AND 30 MAY BE ACCOMPLISHED IN ANY ORDER

CRITICAL STEP PAGE 11 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

31. INDEPENDENTLY INDEPENDENT OPERATOR SHOULD VERIFY VERIFICATION HAS REQUEST THAT AN Comments:

DISCONNECT BEEN PERFORMED INDEPENDENT SWITCHES TO THE VERIFICATION BE ROD CONNECTED PERFORMED POSITION STEP 6.3.10.1 S U

32. RETURN THE ROD THE SS DIRECTS OPERATOR SHOULD AUTO/MAN YOU TO RETURN PUT THE BANK Comments:

SELECTOR SWITCH ROD CONTROL TO SELECTOR SWITCH SE HS-9 TO THE MANUAL ON RL003 IN THE AUTO OR MANUAL MANUAL POSITION POSITION AS REQUIRED BY THE SS STEP 6.3.11 S U

33. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM DROPPED ROD, H-8, THE TASK IS SUPERVISOR THAT HAS BEEN COMPLETE DROPPED ROD, H-8, RESTORED HAS BEEN RESTORED

CRITICAL STEP PAGE 12 of 13

JPM NO: ILE-2002-S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

34. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 13 of 13

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THIRTY MINUTES AGO, CONTROL ROD H-8 DROPPED INTO THE CORE. ALL IMMEDIATE ACTIONS HAVE BEEN PERFORMED. THE PLANT HAS BEEN STABILIZED WITH TAVG AND TREF T

<3°F. THE EDO AND REACTOR ENGINEER HAVE AGREED THE PROBLEM IS CORRECTED AND THE PLANT IS READY FOR RECOVERY. CURRENTLY IN T/S LCO 3.1.4, CONDITION "B".

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO RECOVER THE DROPPED ROD (H-8) BY PERFORMING STEPS 6.1 THROUGH 6.3.11 OF OTO-SF-00003, DROPPED CONTROL ROD. THE PRIMARY EO IS STATIONED AT THE ROD CONTROL CABINETS IF YOU NEED HIS ASSISTANCE. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S2 K/A NO: 005A4.01 COMPLETION TIME: 12 MINUTES K/A RATING: 3.6/3.4 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: RESIDUAL HEAT REMOVAL SYSTEM TASK TITLE: PERFORM 'B' RHR PUMP NON-SURVEILLANCE RUN The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTS-EJ-0004B, RHR PUMP 'B' NON-SURVEILLANCE RUN, REVISION 2 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-7/2000-JPM4 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THE 'B' RHR PUMP CIRCUIT BREAKER WAS RACKED OUT FOR AN ENGINEERING INSPECTION. THE INSPECTION HAS BEEN COMPLETED AND THE CIRCUIT BREAKER HAS BEEN RACKED IN. THE

'A' RHR TRAIN IS OPERABLE AND BOTH RHR TRAINS ARE IN THEIR NORMAL STANDBY ALIGNMENT.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO START THE 'B' RHR PUMP PER OTS-EJ-0004B, RHR PUMP 'B' NON-SURVEILLANCE RUN.

INFORM THE CONTROL ROOM SUPERVISOR WHEN THE 'B' RHR PUMP IS RUNNING.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-170. ENSURE 'B' CCW TRAIN IS IN SERVICE.

Task Standard: UPON COMPLETION OF THIS JPM, THE 'B' RHR PUMP WILL HAVE BEEN STARTED PER OTS-EJ-0004B.

START TIME:

STOP TIME:

PAGE 1 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTS-EJ-0004B, RHR OPERATOR WITH OBTAIN A COPY OF Comments:

PUMP 'B' NON- PROCEDURE COPY OTS-EJ-0004B, RHR SURVEILLANCE (GREEN SHEETS) PUMP 'B' NON-RUN SURVEILLANCE RUN S U

2. REVIEW IF ASKED, ALL OPERATOR SHOULD PRECAUTIONS AND PRECAUTIONS AND REVIEW THE Comments:

LIMITATIONS OF LIMITATIONS ARE PRECAUTIONS AND OTS-EJ-0004B, RHR SATISFIED LIMITATIONS OF PUMP 'B' NON- OTS-EJ-0004B, RHR SURVEILLANCE PUMP 'B' NON-RUN SURVEILLANCE RUN STEP 2.0 S U

3. REVIEW INITIAL IF ASKED, ALL OPERATOR SHOULD CONDITIONS OF INITIAL REVIEW THE INITIAL Comments:

OTS-EJ-0004B, RHR CONDITIONS ARE CONDITIONS OF PUMP 'B' NON- SATISFIED OTS-EJ-0004B, RHR SURVEILLANCE PUMP 'B' NON-RUN SURVEILLANCE RUN STEP 3.0

CRITICAL STEP PAGE 2 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. ENSURE EJ HIS-8701B GREEN OPERATOR SHOULD EJ HIS-8701B, RHR LIGHT IS OUT AND VERIFY EJ HIS-8701B, Comments:

PMP B SUCT IS RED LIGHT IS OUT RHR PMP B SUCT IS CLOSED CLOSED.

NOTE: EJHIS8701B IS STEP 4.1 NORMALLY CLOSED LOCATED ON RL017 AND DE-ENERGIZED S U

5. ENSURE EJ HIS-8811B GREEN OPERATOR SHOULD EJ HIS- 8811B, CTMT LIGHT IS LIT AND VERIFY EJ HIS- 8811B, Comments:

RECIRC SUMP B TO RED LIGHT IS OUT CTMT RECIRC SUMP RHR PMP B SUCT IS B TO RHR PMP B CLOSED SUCT IS CLOSED STEP 4.1 LOCATED ON RL017 S U

6. ENSURE BN HIS-8812B RED OPERATOR SHOULD BN HIS-8812B, B RHR LIGHT IS LIT AND VERIFY Comments:

SUCT FROM RWST GREEN LIGHT IS OUT BN HIS-8812B, B RHR IS OPEN SUCT FROM RWST IS OPEN STEP 4.1 LOCATED ON RL017

CRITICAL STEP PAGE 3 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. ENSURE EJ HIS-611, EJ HIS-611 RED LIGHT OPERATOR SHOULD B RHR PMP MINI IS LIT AND GREEN VERIFY EJ HIS-611, B Comments:

FCV IS OPEN LIGHT IS OUT RHR PMP MINI FCV IS OPEN STEP 4.1 LOCATED ON RL017 S U

8. ENSURE EJ HIS-8840A ISO OPERATOR SHOULD EJ HIS-8840A, PWR WHITE LIGHT IS OUT VERIFY EJ HIS-8840A, Comments:

LOCKOUT SWITCH PWR LOCKOUT FOR EJ-HV-8840 IS IN SWITCH FOR THE ISO POSITION EJ-HV-8840 IS IN THE ISO POSITION STEP 4.1 LOCATED ON RL017 S U

9. ENSURE EJ HIS-8840, EJ HIS-8840 GREEN OPERATOR SHOULD RHR TRNS A&B SI LIGHT IS LIT AND VERIFY EJ HIS-8840, Comments:

SYS HOT LEG RED LIGHT IS OUT RHR TRNS A&B SI RECIRC IS CLOSED SYS HOT LEG RECIRC IS CLOSED STEP 4.1 LOCATED ON RL017

CRITICAL STEP PAGE 4 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. ENSURE EJ HIC-607, AFTER EJ HIC-607 OPERATOR SHOULD RHR HX B OUTLET POTENTIOMETER IS CLOSE EJ HIC-607, Comments:

FCV IS CLOSED TURNED FULLY RHR HX B OUTLET CLOCKWISE THE FCV BY TURNING STEP 4.1 METER INDICATES EJ HIC-607 ZERO PERCENT OPEN POTENTIOMETER FULLY CLOCKWISE LOCATED ON RL017 S U

11. ENSURE EJ FK-619, EJ FK-619 IS IN OPERATOR SHOULD RHR HX B BYPASS MANUAL AND HAS A VERIFY EJ FK-619, Comments:

FLOW CTRL M/A ZERO DEMAND RHR HX B BYPASS STATION IS CLOSED FLOW CTRL M/A STATION IS CLOSED STEP 4.1 LOCATED ON RL017 S U

12. ENSURE EJ HIS-8804B GREEN OPERATOR SHOULD EJ HIS-8804B, B RHR LIGHT IS LIT AND VERIFY EJ HIS-8804B, Comments:

PMP TO SI PMPS RED LIGHT IS OUT B RHR PMP TO SI SUCT IS CLOSED PMPS SUCT IS CLOSED STEP 4.1 LOCATED ON RL017

CRITICAL STEP PAGE 5 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. ENSURE EJ HIS-8890A GREEN OPERATOR SHOULD EJ HIS-8890A, RHR LIGHT IS LIT AND VERIFY EJ HIS-8890A, Comments:

TRN A ACC INJ SIS RED LIGHT IS OUT RHR TRN A ACC INJ TEST LINE IS SIS TEST LINE IS CLOSED CLOSED STEP 4.1 LOCATED ON RL017 S U

14. ENSURE EJ HIS-8890B GREEN OPERATOR SHOULD EJ HIS-8890B, RHR LIGHT IS LIT AND VERIFY EJ HIS-8890B, Comments:

TRN B ACC INJ SIS RED LIGHT IS OUT RHR TRN B ACC INJ TEST LINE IS SIS TEST LINE IS CLOSED CLOSED STEP 4.1 LOCATED ON RL017 S U

15. IF IN MODES 5 OR 6, OPERATOR SHOULD PERFORM THIS STEP DETERMINE THIS Comments:

STEP IS NOT STEP 4.2 APPLICABLE SINCE THE PLANT IS IN MODE 1.

GIVEN IN INITIAL CONDITIONS

CRITICAL STEP PAGE 6 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. ENSURE SW/ESW IS EF HIS-52 RED LIGHT OPERATOR SHOULD ALIGNED TO THE 'B' IS LIT AND GREEN VERIFY SW/ESW IS Comments:

CCW HX LIGHT IS OUT ALIGNED TO THE 'B' CCW HX STEP 4.3.1 NOTE: THIS IS ACCOMPLISHED BY VERIFYING EF HIS-52 IS OPEN LOCATED ON RL019 S U

17. ENSURE 'B' TRAIN 'B' CCW PUMP IS OPERATOR SHOULD CCW IS IN RUNNING VERIFY THAT Comments:

OPERATION EITHER THE 'B' OR 'D' CCW PUMP IS STEP 4.3.2 RUNNING LOCATED ON RL019 S U

18. ENSURE EGHV0102, AFTER EG HIS-102 OPERATOR SHOULD CCW TO RHR HX B OPEN PUSHBUTTON OPEN EGHV0102 BY Comments:

IS OPEN USING HAS BEEN DEPRESSING THE EG HIS-102 DEPRESSED, OPEN PUSHBUTTON EG HIS-102 RED ON EG HIS-102 STEP 4.3.3 LIGHT WILL ILLUMINATE AND LOCATED ON RL017 GREEN LIGHT WILL EXTINGUISH

CRITICAL STEP PAGE 7 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. IF MCB ALARM 53A MCB ALARM 53A OPERATOR SHOULD IS LIT, THEN WILL CLEAR, IF CCW THROTTLE EC HIS-12 Comments:

THROTTLE CLOSED FLOW HAS BEEN AS REQUIRED TO ECHV0012, FUEL PROPERLY ENSURE THAT MCB POOL HX B SHELL ADJUSTED ALARM 53A IS NOT IN SIDE CCW OUTLET, ALARM USING EC HIS-12, UNTIL ALARM 53A LOCATED ON RL019 CLEARS STEP 4.3.4 S U

20. ENSURE CCW FLOW IF REQUESTED, THE OPERATOR SHOULD TO THE RHR HX B PRIMARY EO CONTACT THE Comments:

AS INDICATED BY REPORTS THAT PRIMARY EO TO EGFI0064 IS EGFI0064 INDICATES VERIFY THAT GREATER THAN 4.2E+6 LBM/HR EGFI0064 IS GREATER 3.8E+6 LBM/HR THAN 3.8E+6 LBM/HR IF EGF0702 IS USED, STEP 4.3.5 TELL THE OPERATOR MAY USE OPERATOR IT COMPUTER POINT READS 4.2E+6 EGF0702 TO VERIFY LBM/HR THIS FLOW S U

21. ENSURE CCW FLOW IF REQUESTED, THE OPERATOR SHOULD TO THE PUMP SEAL PRIMARY EO CONTACT THE Comments:

COOLER AS REPORTS THAT PRIMARY EO TO INDICATED BY EGFI0092 INDICATES VERIFY THAT EGFI0092 IS > 3000 3400 LBM/HR EGFI0092 IS > 3000 LBM/HR LBM/HR IF EGF0712 IS USED, STEP 4.3.6 TELL THE OPERATOR MAY USE OPERATOR IT COMPUTER POINT READS 3400 LBM/HR EGF0712 TO VERIFY THIS FLOW

CRITICAL STEP PAGE 8 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

22. NOTIFY HEALTH IF CONTACTED, OPERATOR SHOULD PHYSICS THAT THE ACKNOWLEDGE CONTACT HP Comments:

RHR PUMP IS GOING THAT THE 'B' RHR PERSONNEL AND TO BE STARTED PUMP WILL BE INFORM THEM THAT STARTED THE 'B' RHR PUMP STEP 4.4 WILL BE STARTED S U

23. USING EJ HIS-2, AFTER THE PUMP OPERATOR SHOULD START RHR PUMP 'B' HANDSWITCH IS START THE 'B' RHR Comments:

TAKEN TO RUN, PUMP USING EJ HIS-2 STEP 4.5 EJ HIS-2 RED LIGHT WILL ILLUMINATE LOCATED ON RL017 AND GREEN LIGHT WILL EXTINGUISH S U

24. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM THE 'B' RHR PUMP IS THE TASK IS SUPERVISOR THAT RUNNING COMPLETE THE 'B' RHR PUMP IS RUNNING

CRITICAL STEP PAGE 9 of 10

JPM NO: ILE-7/2000-JPM4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

25. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 10 of 10

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THE 'B' RHR PUMP CIRCUIT BREAKER WAS RACKED OUT FOR AN ENGINEERING INSPECTION. THE INSPECTION HAS BEEN COMPLETED AND THE CIRCUIT BREAKER HAS BEEN RACKED IN. THE

'A' RHR TRAIN IS OPERABLE AND BOTH RHR TRAINS ARE IN THEIR NORMAL STANDBY ALIGNMENT.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO START THE 'B' RHR PUMP PER OTS-EJ-0004B, RHR PUMP 'B' NON-SURVEILLANCE RUN.

INFORM THE CONTROL ROOM SUPERVISOR WHEN THE 'B' RHR PUMP IS RUNNING.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S3 K/A NO: 045A2.17 COMPLETION TIME: 15 MINUTES K/A RATING: 2.7/2.9 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: MAIN TURBINE TASK TITLE: MAIN TURBINE MECHANICAL O/S TRIP TEST The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OSP-AC-00004, MAIN TURBINE TRIP TEST, REVISION 13 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-S3 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THE MECHANICAL OVERSPEED TRIP TEST IS REQUIRED TO BE PERFORMED PER SECTION 6.3 OF OSP-AC-00004, MAIN TURBINE TRIP TEST. A PRE-JOB BRIEF HAS BEEN PERFORMED AND THE SECONDARY EQUIPMENT OPERATOR (EO) HAS OBTAINED KEY 91 FROM THE SHIFT SUPERVISOR. THE SHIFT SUPERVISOR HAS GIVEN PERMISSION TO PERFORM THE MECHANICAL OVERSPEED TRIP TEST. YOU ARE THE BOP REACTOR OPERATOR.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO PERFORM THE MECHANICAL OVERSPEED TRIP TEST ON THE MAIN TURBINE PER SECTION 6.3 OF OSP-AC-00004, MAIN TURBINE TRIP TEST. SECTIONS 6.1 AND 6.2 HAVE BEEN COMPLETED. INFORM THE CONTROL ROOM SUPERVISOR WHEN SECTION 6.3 HAS BEEN COMPLETED.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-170.

ENSURE A LAMP TEST HAS BEEN PERFORMED ON THE EHC CONTROL PANEL.

STEPS 7 AND 11 WILL REQUIRE THE USE OF REMOTE CHS005.

Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL HAVE DETERMINED THAT ACHS0001 WAS PLACED IN THE INCORRECT POSITION, HALTED THE TEST, CORRECTED THE POSITION OF ACHS0001, AND COMPLETED THE PERFORMANCE OF THE MECHANICAL OVERSPEED TRIP TEST.

START TIME:

STOP TIME:

PAGE 1 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OSP-AC-00004, MAIN OPERATOR WITH OBTAIN A COPY OF Comments:

TURBINE TRIP PROCEDURE COPY OSP-AC-00004, MAIN TESTS (GREEN SHEETS) TURBINE TRIP TESTS S U

2. REVIEW OPERATOR SHOULD ACCEPTANCE REVIEW THE Comments:

CRITERIA OF ACCEPTANCE OSP-AC-00004, MAIN CRITERIA OF TURBINE TRIP OSP-AC-00004, MAIN TESTS TURBINE TRIP TESTS STEP 2.0 S U

3. REVIEW IF ASKED, ALL OPERATOR SHOULD PRECAUTIONS AND PRECAUTIONS AND REVIEW THE Comments:

LIMITATIONS OF LIMITATIONS ARE PRECAUTIONS AND OSP-AC-00004, MAIN SATISFIED LIMITATIONS OF TURBINE TRIP OSP-AC-00004, MAIN TESTS TURBINE TRIP TESTS STEP 3.0

CRITICAL STEP PAGE 2 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. REVIEW INITIAL IF ASKED, ALL OPERATOR SHOULD CONDITIONS OF INITIAL REVIEW THE INITIAL Comments:

OSP-AC-00004, MAIN CONDITIONS ARE CONDITIONS OF TURBINE TRIP SATISFIED OSP-AC-00004, MAIN TESTS TURBINE TRIP TESTS STEP 4.0 S U

5. REVIEW NOTES, OPERATOR SHOULD CAUTIONS, AND REVIEW THE NOTES, Comments:

MECHANICAL CAUTIONS, AND OVERSPEED TRIP MECHANICAL TEST PROCEDURE OVERSPEED TRIP TEST PROCEDURE STEP 6.3 S U

6. OBTAIN THE SHIFT IF ASKED, THE OPERATOR MAY SUPERVISOR'S SHIFT SUPERVISOR OBTAIN THE SHIFT Comments:

PERMISSION TO HAS GIVEN SUPERVISOR'S OPERATE THE PERMISSION TO PERMISSION TO BYPASS SWITCH OPERATE THE OPERATE THE BYPASS SWITCH BYPASS SWITCH STEP 6.3.1 NOTE: GIVEN IN THE INITIAL CONDITIONS

CRITICAL STEP PAGE 3 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. OBTAIN KEY 91 SECONDARY EO OPERATOR SHOULD FROM THE SS AND REPORTS THAT KEY DIRECT THE Comments:

INSERT KEY IN THE 91 HAS BEEN SECONDARY EO TO BYPASS SWITCH INSERTED INTO INSERT KEY 91 INTO ACHS0001. TURN ACHS0001 AND ACHS0001 AND TURN THE KEY TO THE TURNED TO THE THE SWITCH TO THE MECHANICAL TRIP MECHANICAL TRIP MECHANICAL TRIP TEST BYPASS TEST BYPASS TEST BYPASS POSITION POSITION POSITION STEP 6.3.2 SET REMOTE CHS005 TO "ETT BYPASS" S U

8. VERIFY THAT THE "LOCKED OUT" OPERATOR SHOULD "LOCKED OUT" LIGHT IS NOT DETERMINE THAT Comments:

LIGHT IS ENERGIZED THE "LOCKED OUT" ENERGIZED IS NOT ENERGIZED, AFTER THE SS/CRS STOP THE TEST, AND STEP 6.3.2.1 IS INFORMED OF INFORM THE SS/CRS THE INCORRECT RESPONSE, THE SS/CRS DIRECTS THE OPERATOR TO RE-VERIFY STEP 6.3.2 S U

9. OPERATOR SHOULD SECONDARY EO OPERATOR SHOULD RE-VERIFY THE REPORTS THAT HE DIRECT THE Comments:

POSITION OF INCORRECTLY SECONDARY EO TO ACHS0001 PLACED ACHS0001 IN RE-VERIFY THE THE ELECTRICAL POSITION OF STEP 6.3.2 TRIP TEST BYPASS ACHS0001 POSITION

CRITICAL STEP PAGE 4 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. OPERATOR SHOULD THE SS/CRS OPERATOR SHOULD INFORM THE SS/CRS DIRECTS THE INFORM THE SS/CRS Comments:

THAT ACHS0001 OPERATOR TO RE- OF THE INCORRECT WAS INCORRECTLY PERFORM STEP 6.3.2 OPERATION OF PLACED IN THE AND CONTINUE THE SWITCH ACHS0001 ELECTRICAL TRIP TEST TEST BYPASS POSITION STEP 6.3.2 S U

11. OBTAIN KEY 91 SECONDARY EO OPERATOR SHOULD FROM THE SS AND REPORTS THAT KEY DIRECT THE Comments:

INSERT KEY IN THE 91 HAS BEEN SECONDARY EO TO BYPASS SWITCH INSERTED INTO INSERT KEY 91 INTO ACHS0001. TURN ACHS0001 AND ACHS0001 AND TURN THE KEY TO THE TURNED TO THE THE SWITCH TO THE MECHANICAL TRIP MECHANICAL TRIP MECHANICAL TRIP TEST BYPASS TEST BYPASS TEST BYPASS POSITION POSITION POSITION STEP 6.3.2 SET REMOTE CHS005 TO "NORMAL" THEN TO "MTT BYPASS" S U

12. VERIFY THAT THE "LOCKED OUT" OPERATOR SHOULD "LOCKED OUT" LIGHT IS ENERGIZED DETERMINE THAT Comments:

LIGHT IS THE "LOCKED OUT" ENERGIZED IS ENERGIZED STEP 6.3.2.1

CRITICAL STEP PAGE 5 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. VERIFY THAT THE "NORMAL" LIGHT IS OPERATOR SHOULD "NORMAL" LIGHT IS DEENERGIZED DETERMINE THAT Comments:

DEENERGIZED THE "NORMAL" LIGHT IS STEP 6.3.2.2 DEENERGIZED S U

14. OBSERVE THAT THE "MECHANICAL O/S OPERATOR SHOULD "MECHANICAL O/S RESET" LIGHT IS VERIFY THAT THE Comments:

RESET" AND THE ENERGIZED "MECHANICAL O/S "TRIP PISTON RESET" AND THE RESET" LIGHTS ARE "TRIP PISTON RESET" "TRIP PISTON RESET" ENERGIZED LIGHT IS ENERGIZED LIGHTS ARE ENERGIZED STEP 6.3.3 S U

15. VERIFY THAT ALL "LOCKED OUT" OPERATOR SHOULD OTHER LIGHTS IN LIGHT IS THE ONLY VERIFY THAT ONLY Comments:

THIS GROUP LIGHT ENERGIZED IN THE "LOCKED OUT" EXCEPT THE THIS GROUP LIGHT IS ENERGIZED "LOCKED OUT" IN THIS GROUP LIGHT ARE DEENERGIZED STEP 6.3.4

CRITICAL STEP PAGE 6 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. DEPRESS AND HOLD "START MECH O/S OPERATOR SHOULD THE "START MECH TRIP TEST" DEPRESS AND HOLD Comments:

O/S TRIP TEST" PUSHBUTTON IS THE "START MECH PUSHBUTTON AND DEPRESSED AND THE O/S TRIP TEST" VERIFY THAT THE PUSHBUTTON LIGHT PUSHBUTTON AND PUSHBUTTON IS ENERGIZED VERIFY THAT THE LIGHT ENERGIZES PUSHBUTTON LIGHT ENERGIZES STEP 6.3.5 S U

17. RELEASE THE "START MECH O/S OPERATOR SHOULD "START MECH O/S TRIP TEST" RELEASE THE Comments:

TRIP TEST" PUSHBUTTON HAS "START MECH O/S PUSHBUTTON BEEN RELEASED TRIP TEST" PUSHBUTTON STEP 6.3.6 S U

18. OBSERVE THAT THE "MECH O/S RESET" OPERATOR SHOULD "MECH O/S RESET" LIGHT DEENERGIZES VERIFY THAT THE Comments:

LIGHT "MECH O/S RESET" DEENERGIZES AND "TRIPPED" LIGHT LIGHT DEENERGIZES THAT THE ENERGIZES AND THAT THE "TRIPPED" LIGHT "TRIPPED" LIGHT ENERGIZES ENERGIZES STEP 6.3.6.1

CRITICAL STEP PAGE 7 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. VERIFY THAT THE ANNUNCIATOR, 112B, OPERATOR SHOULD ANNUNCIATOR, MECH O/S TURB TRIP VERIFY THAT THE Comments:

112B, MECH O/S HAS ALARMED ANNUNCIATOR, 112B, TURB TRIP ALARMS MECH O/S TURB TRIP ALARMS STEP 6.3.6.2 S U

20. VERIFY THAT THE ANNUNCIATOR, 122F, OPERATOR SHOULD ANNUNCIATOR, TURB ELEC MALF VERIFY THAT THE Comments:

122F, TURB ELEC HAS ALARMED ANNUNCIATOR, 122F, MALF ALARMS TURB ELEC MALF ALARMS STEP 6.3.6.3 S U

21. OBSERVE THAT THE "RESETTING" LIGHT OPERATOR SHOULD "RESETTING" LIGHT IS ENERGIZED OBSERVE THAT THE Comments:

ENERGIZES "RESETTING" LIGHT ENERGIZES STEP 6.3.6.4

CRITICAL STEP PAGE 8 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

22. OBSERVE THAT THE "MECH O/S TRIPPED" OPERATOR SHOULD "MECH O/S LIGHT IS OBSERVE THAT THE Comments:

TRIPPED" LIGHT DEENERGIZED "MECH O/S TRIPPED" DEENERGIZES AND LIGHT DEENERGIZES THE "RESET" LIGHT "RESET" LIGHT IS AND THE "RESET" ENERGIZES ENERGIZED LIGHT ENERGIZES STEP 6.3.6.5 S U

23. OBSERVE THAT THE "START MECH O/S OPERATOR SHOULD "START MECH O/S TRIP TEST" LIGHT IS OBSERVE THAT THE Comments:

TRIP TEST" LIGHT DEENERGIZED "START MECH O/S DEENERGIZES TRIP TEST" LIGHT DEENERGIZES STEP 6.3.6.6 S U

24. OBSERVE THAT THE "RESETTING" LIGHT OPERATOR SHOULD "RESETTING" LIGHT IS DEENERGIZED OBSERVE THAT THE Comments:

IS DEENERGIZED "RESETTING" LIGHT IS DEENERGIZED STEP 6.3.6.7

CRITICAL STEP PAGE 9 of 10

JPM NO: ILE-2002-S3 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

25. RESET ANNUNCIATOR 112B, OPERATOR SHOULD ANNUNCIATOR MECH O/S TURB TRIP, RESET Comments:

112B, MECH O/S CLEARS AFTER THE ANNUNCIATOR 112B, TURB TRIP ANNUNCIATOR MECH O/S TURB TRIP, RESET PUSHBUTTON WITH THE STEP 6.3.12 HAS BEEN PRESSED ANNUNCIATOR RESET PUSHBUTTON S U

26. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM SECTION 6.3 OF THE TASK IS SUPERVISOR THAT OSP-AC-00004 HAS COMPLETED SECTION 6.3 OF BEEN COMPLETED OSP-AC-00004 HAS BEEN COMPLETED S U

27. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 10 of 10

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 1. THE MECHANICAL OVERSPEED TRIP TEST IS REQUIRED TO BE PERFORMED PER SECTION 6.3 OF OSP-AC-00004, MAIN TURBINE TRIP TEST. A PRE-JOB BRIEF HAS BEEN PERFORMED AND THE SECONDARY EQUIPMENT OPERATOR (EO) HAS OBTAINED KEY 91 FROM THE SHIFT SUPERVISOR. THE SHIFT SUPERVISOR HAS GIVEN PERMISSION TO PERFORM THE MECHANICAL OVERSPEED TRIP TEST. YOU ARE THE BOP REACTOR OPERATOR.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO PERFORM THE MECHANICAL OVERSPEED TRIP TEST ON THE MAIN TURBINE PER SECTION 6.3 OF OSP-AC-00004, MAIN TURBINE TRIP TEST. SECTIONS 6.1 AND 6.2 HAVE BEEN COMPLETED. INFORM THE CONTROL ROOM SUPERVISOR WHEN SECTION 6.3 HAS BEEN COMPLETED.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S4 K/A NO: 010A4.01 COMPLETION TIME: 15 MINUTES K/A RATING: 3.7/3.5 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: PRESSURIZER PRESSURE CONTROL TASK TITLE: DEPRESSURIZE AND BLOCK SAFETY INJECTION The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTG-ZZ-00006, PLANT COOLDOWN HOT STANDBY TO COLD SHUTDOWN, REVISION 23 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-S4 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3, WITH RCS TAVG AT 557°F AND RCS PRESSURE AT 2050 PSIG. A AND D RCPs ARE IN OPERATION.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO DEPRESSURIZE THE RCS TO LESS THAN 1970 PSIG AND BLOCK SAFETY INJECTION PER OTG-ZZ-00006, STEPS 5.2.13 THROUGH 5.2.14.5. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

Notes: USE IC-166. (THIS IC WAS BUILT FROM IC-7 STARTING POINT)

Task Standard: UPON COMPLETION OF THIS JPM, THE OPERATOR WILL HAVE BLOCKED BOTH TRAINS OF PRESSURIZER PRESSURE AND STEAM LINE PRESSURE SAFETY INJECTION.

START TIME:

STOP TIME:

PAGE 1 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTG-ZZ-00006, OPERATOR WITH OBTAIN A COPY OF Comments:

PLANT COOLDOWN PROCEDURE COPY OTG-ZZ-00006, PLANT HOT STANDBY TO (GREEN SHEETS) COOLDOWN HOT COLD SHUTDOWN STANDBY TO COLD SHUTDOWN S U

2. REVIEW GENERAL IF ASKED, ALL OPERATOR SHOULD NOTES OF GENERAL NOTES REVIEW GENERAL Comments:

OTG-ZZ-00006, ARE SATISFIED NOTES OF PLANT COOLDOWN OTG-ZZ-00006, PLANT HOT STANDBY TO COOLDOWN HOT COLD SHUTDOWN STANDBY TO COLD SHUTDOWN STEP 2.0 S U

3. REVIEW IF ASKED, ALL OPERATOR SHOULD PRECAUTIONS AND PRECAUTIONS AND REVIEW Comments:

LIMITATIONS OF LIMITATIONS ARE PRECAUTIONS AND OTG-ZZ-00006, SATISFIED LIMITATIONS OF PLANT COOLDOWN OTG-ZZ-00006, PLANT HOT STANDBY TO COOLDOWN HOT COLD SHUTDOWN STANDBY TO COLD SHUTDOWN STEP 3.0

CRITICAL STEP PAGE 2 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. REVIEW INITIAL IF ASKED, ALL OPERATOR SHOULD CONDITIONS OF INITIAL REVIEW INITIAL Comments:

OTG-ZZ-00006, CONDITIONS ARE CONDITIONS OF PLANT COOLDOWN SATISFIED OTG-ZZ-00006, PLANT HOT STANDBY TO COOLDOWN HOT COLD SHUTDOWN STANDBY TO COLD SHUTDOWN STEP 4.0 S U

5. START TO DEPRESSURIZE THE Comments:

RCS AS FOLLOWS:

STEP 5.2.13 S U

6. ENSURE ALL PZR ALL PZR HEATERS OPERATOR SHOULD HEATERS ARE ON ARE ON ENSURE ALL PZR Comments:

TO MAXIMIZE HEATERS ARE ON TO SPRAY FLOW MAXIMIZE SPRAY FLOW STEP 5.2.13.1

CRITICAL STEP PAGE 3 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. NOTE: AUTO PZR OPERATOR MAY USE PRESSURE AUTO PZR PRESSURE Comments:

CONTROL MAY BE CONTROL INSTEAD USED UNTIL OF MANUAL PRESSURE HAS DECREASED TO 1700 PSIG BY ADJUSTING THE POTENTIOMETER ON BB PK-455A INSTEAD OF USING MANUAL CONTROL S U

8. SET THE SPRAY THE SPRAY VALVE THE OPERATOR VALVE IN THE IN THE A RCS LOOP SHOULD OPEN THE Comments:

OPERATING RCS HAS BEEN OPENED SPRAY VALVE IN LOOP IN MANUAL AND RCS PRESSURE THE A RCS LOOP TO AND SLOWLY OPEN IS DECREASING BEGIN RCS (OR ADJUST DEPRESSURIZATION BB PK-455A) TO BEGIN DE-PRESSURIZATION STEP 5.2.13.2 S U

9. MAINTAIN THE RCS PRESSURE AND OPERATOR SHOULD IN ACCORDANCE TEMPERATURE ARE ENSURE THAT RCS Comments:

WITH THE WITHIN THE LIMITS PRESSURE AND PRESSURE AND OF FIGURE 8-6 OF TEMPERATURE ARE TEMPERATURE THE CURVE BOOK WITHIN THE LIMITS BAND AS OF FIGURE 8-6 OF DELINEATED ON THE CURVE BOOK CURVE BOOK FIGURE 8-6 STEP 5.2.13.3

CRITICAL STEP PAGE 4 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. MAINTAIN AT RCS SUBCOOLING IS OPERATOR SHOULD LEAST 50°F GREATER THAN 50°F MAINTAIN AT LEAST Comments:

SUBCOOLING 50°F SUBCOOLING DURING THE DURING THE DEPRESSURIZATION DEPRESSURIZATION AND COOLDOWN AND COOLDOWN STEP 5.2.13.4 S U

11. PRIOR TO OPERATOR SHOULD REACHING MAINTAIN RCS Comments:

1900 PSIG, ENSURE PRESSURE GREATER STEP 5.2.14 IS THAN 1849 PSIG (SI COMPLETED SETPOINT) UNTIL STEP 5.2.14 IS STEP 5.2.13.5 COMPLETE S U

12. WHEN RCS PRESSURE Comments:

DECREASES BELOW 1970 PSIG AND PRIOR TO 1900 PSIG, COMPLETE THE FOLLOWING:

STEP 5.2.14

CRITICAL STEP PAGE 5 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. CAUTION: IF RCS OPERATOR SHOULD PRESSURE RISES READ CAUTION. Comments:

ABOVE 1970 PSIG AFTER BLOCKING, THEN THE SAFETY INJECTION BLOCK SIGNALS WILL AUTOMATICALLY RESET. IT WILL BE NECESSARY TO REBLOCK WHEN PRESSURE AGAIN DECREASES.

S U

14. VERIFY THAT THE PERMISSIVE P-11 OPERATOR SHOULD PERMISSIVE P-11 STATUS LIGHT IS LIT VERIFY THAT THE Comments:

STATUS LIGHT IS ON SB069 PERMISSIVE P-11 LIT ON SB069 STATUS LIGHT IS LIT ON SB069 STEP 5.2.14.1 S U

15. BLOCK THE SB-HS-7 AND SB-HS-8 OPERATOR SHOULD PRESSURIZER HAVE BEEN DEPRESS SB-HS-7 Comments:

PRESSURE SAFETY DEPRESSED AND SB-HS-8 INJECTION TRAIN A AND TRAIN B SIGNALS WITH SB-HS-7 AND SB-HS-8 ON RL002 STEP 5.2.14.2

CRITICAL STEP PAGE 6 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. VERIFY THAT BOTH BOTH PRESSURIZER OPERATOR SHOULD PRESSURIZER SAFETY INJECTION VERIFY THAT BOTH Comments:

SAFETY INJECTION TRAINS A AND B PRESSURIZER TRAINS A AND B BLOCKED STATUS SAFETY INJECTION BLOCKED STATUS LIGHTS ARE LIT ON TRAINS A AND B LIGHTS ARE LIT ON SB069 BLOCKED STATUS SB069 LIGHTS ARE LIT ON SB069 STEP 5.2.14.3 S U

17. BLOCK THE STEAM SB-HS-9 AND SB-HS- OPERATOR SHOULD LINE ISOLATION/ 10 HAVE BEEN DEPRESS SB-HS-9 Comments:

SAFETY INJECTION DEPRESSED AND SB-HS-10 TRAINA AND TRAIN B SIGNALS WITH SB-HS-9 AND SB-HS-10 ON RL002 STEP 5.2.14.4 S U

18. VERIFY THAT THE THE STEAM LINE OPERATOR SHOULD STEAM LINE ISOLATION/SAFETY VERIFY THAT THE Comments:

ISOLATION/SAFETY INJECTION TRAINS STEAM LINE INJECTION TRAINS A AND B ISOLATION/SAFETY A AND B BLOCKED STATUS INJECTION TRAINS BLOCKED STATUS LIGHTS ARE LIT ON A AND B LIGHTS ARE LIT ON SB069 BLOCKED STATUS SB069 LIGHTS ARE LIT ON SB069 STEP 5.2.14.5

CRITICAL STEP PAGE 7 of 8

JPM NO: ILE-2002-S4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM THE RCS HAS BEEN THE TASK IS SUPERVISOR THAT DEPRESSURIZED TO COMPLETE THE RCS HAS BEEN

< 1970 PSIG AND DEPRESSURIZED TO SAFETY INJECTION < 1970 PSIG AND HAS BEEN SAFETY INJECTION BLOCKED HAS BEEN BLOCKED S U

20. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 8 of 8

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3, WITH RCS TAVG AT 557°F AND RCS PRESSURE AT 2050 PSIG. A AND D RCPs ARE IN OPERATION.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU TO DEPRESSURIZE THE RCS TO LESS THAN 1970 PSIG AND BLOCK SAFETY INJECTION PER OTG-ZZ-00006, STEPS 5.2.13 THROUGH 5.2.14.5. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S5 K/A NO: 015A2.02 COMPLETION TIME: 15 MINUTES K/A RATING: 3.1/3.5 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: NUCLEAR INSTRUMENTATION SYSTEM TASK TITLE: RESPOND TO A FAILED POWER RANGE INSTRUMENT The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTO-SE-00003, POWER RANGE NUCLEAR CHANNEL FAILURE, REVISION 9 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-S5 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE PLANT HAS EXPERIENCED A FAILURE OF POWER RANGE CHANNEL N42. ALL IMMEDIATE OPERATOR ACTIONS HAVE BEEN COMPLETED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO PERFORM POWER RANGE CHANNEL N42 TRIP INITIATION USING ATTACHMENT 2 OF OTO-SE-00003, POWER RANGE NUCLEAR CHANNEL FAILURE. INFORM THE CONTROL ROOM SUPERVISOR WHEN YOU HAVE VERIFIED THE PROPER BISTABLE LIGHTS ARE LIT ON SC066W.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-166. (MALFUNCTION NIS03B IS USED TO FAIL THE CHANNEL TO 200% POWER)

ENSURE THE REACTOR TRIP BREAKERS ARE CLOSED.

Task Standard: UPON COMPLETION OF THIS JPM, POWER RANGE NUCLEAR INSTRUMENT CHANNEL N42 WILL HAVE ITS INPUTS TO CHANNEL COMPARATORS AND ROD STOP DEFEATED, INSTRUMENT POWER FUSES REMOVED, P-10 JUMPER INSTALLED, AND REACTOR PROTECTION BISTABLES TRIPPED.

START TIME:

STOP TIME:

PAGE 1 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTO-SE-00003, OPERATOR WITH OBTAIN A COPY OF Comments:

POWER RANGE COPY OF OTO-SE-00003, NUCLEAR CHANNEL ATTACHMENT 2 POWER RANGE FAILURE, (GREEN SHEETS) NUCLEAR CHANNEL ATTACHMENT 2 FAILURE, ATTACHMENT 2 S U

2. SS AUTHORIZATION OPERATOR SHOULD TO REMOVE THE DETERMINE SS Comments:

CONTROL POWER AUTHORIZATION IS FUSES, (IF REACTOR NOT REQUIRED POWER LEVEL IS SINCE POWER LEVEL BELOW P-10, IS BELOW P-10 CONTROL POWER FUSES REMAIN CONTROL POWER INSTALLED) TO FUSES WILL REMAIN BYPASS N42 AND INSTALLED TRIP THE REACTOR PROTECTION B/S S U

3. PLACE THE "UPPER "UPPER SECTION" OPERATOR SHOULD SECTION" SWITCH SWITCH IS IN THE PR PLACE THE "UPPER Comments:

TO THE PR N42 N42 POSITION SECTION" SWITCH TO POSITION AND THE PR N42 POSITION VERIFY THAT THE UPPER "CHANNEL AND VERIFY THAT UPPER "CHANNEL DEFEAT" LIGHT IS THE UPPER DEFEAT" LIGHT IS LIT "CHANNEL DEFEAT" LIT AND THAT ANN LIGHT IS LIT AND 78B, PR UPPER ANN 78B, PR UPPER THAT ANN 78B, PR DETECTOR FLUX DETECTOR FLUX UPPER DETECTOR DEV IS CLEAR DEV IS CLEAR FLUX DEV IS CLEAR

CRITICAL STEP PAGE 2 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. PLACE THE "LOWER " LOWER SECTION" OPERATOR SHOULD SECTION" SWITCH SWITCH IS IN THE PR PLACE THE " LOWER Comments:

TO THE PR N42 N42 POSITION SECTION" SWITCH TO POSITION AND THE PR N42 POSITION VERIFY THAT THE LOWER "CHANNEL AND VERIFY THAT LOWER "CHANNEL DEFEAT" LIGHT IS THE LOWER DEFEAT" LIGHT IS LIT "CHANNEL DEFEAT" LIT AND THAT ANN LIGHT IS LIT AND 78C, PR LOWER ANN 78C, PR LOWER THAT ANN 78C, PR DETECTOR FLUX DETECTOR FLUX LOWER DETECTOR DEV IS CLEAR DEV IS CLEAR FLUX DEV IS CLEAR S U

5. PLACE THE ROD ROD STOP BYPASS OPERATOR SHOULD STOP BYPASS SWITCH IS IN THE PLACE THE ROD Comments:

SWITCH TO THE BYPASS PR N42 STOP BYPASS BYPASS PR N42 POSITION SWITCH TO THE POSITION AND BYPASS PR N42 VERIFY THAT ANN ANN 82A, PR OVER POSITION AND 82A, PR OVER PWR PWR ROD STOP IS VERIFY THAT ANN ROD STOP IS CLEAR CLEAR 82A, PR OVER PWR ROD STOP IS CLEAR S U

6. PLACE THE POWER POWER MISMATCH OPERATOR SHOULD MISMATCH BYPASS BYPASS SWITCH IS IN PLACE THE POWER Comments:

SWITCH TO THE THE BYPASS PR N42 MISMATCH BYPASS BYPASS PR N42 POSITION SWITCH TO THE POSITION BYPASS PR N42 POSITION

CRITICAL STEP PAGE 3 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. PLACE THE COMPARATOR OPERATOR SHOULD COMPARATOR CHANNEL DEFEAT PLACE THE Comments:

CHANNEL DEFEAT SWITCH IS IN THE COMPARATOR SWITCH TO THE N42 N42 POSITION CHANNEL DEFEAT POSITION AND SWITCH TO THE N42 VERIFY THAT THE COMPARATOR POSITION AND COMPARATOR DEFEAT LIGHT IS LIT VERIFY THAT THE DEFEAT LIGHT IS COMPARATOR LIT AND THAT ANN ANN 78A, PR DEFEAT LIGHT IS LIT 78A, PR CHANNEL CHANNEL DEV IS AND THAT ANN 78A, DEV IS CLEAR CLEAR PR CHANNEL DEV IS CLEAR S U

8. IF REACTOR POWER AFTER OPERATOR OPERATOR SHOULD LEVEL IS BELOW DETERMINES DETERMINE THE Comments:

P-10, SKIP THE NEXT ATTACHMENT 9 IS NEXT 2 STEPS 2 STEPS AND REQUIRED, SHOULD BE SKIPPED PERFORM PROVIDE AND PERFORM ATTACHMENT 9 OPERATOR WITH ATTACHMENT 9 COPY OF ATTACHMENT 9 (PINK SHEETS)

S U

9. REMOVE THE N42 INSTRUMENT OPERATOR SHOULD INSTRUMENT POWER FUSES ARE REMOVE THE Comments:

POWER FUSES FOR REMOVED INSTRUMENT POWER N42 FUSES FOR N42

CRITICAL STEP PAGE 4 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. INSTALL THE OPERATOR SHOULD CONTROL POWER REALIZE THE Comments:

FUSES (IF REMOVED CONTROL POWER EARLIER) FOR N42 FUSES FOR N42 WERE NOT REMOVED EARLIER S U

11. INFORM THE SS SS WILL ENTER OPERATOR SHOULD AND URO THAT THE FUSE REMOVAL IN INFORM THE SS AND Comments:

INSTRUMENT THE SS LOG URO THAT THE POWER FUSES FOR INSTRUMENT POWER N42 HAVE BEEN URO WILL ENTER FUSES FOR N42 HAVE REMOVED AND FUSE REMOVAL IN BEEN REMOVED AND ENTER IN THE SS THE URO LOG ENTER IN THE SS AND URO LOG AND URO LOG S U

12. SLIDE OUT THE I&C TECHS HAVE OPERATOR SHOULD APPROPRIATE "A" COMPLETED DIRECT I&C TECHS Comments:

DRAWER ON IT'S INSTALLATION OF TO SLIDE OUT THE TRACK, REMOVE P-10 JUMPER FOR N42 APPROPRIATE "A" THE BOTTOM DRAWER ON IT'S SHIELD PLATE, TRACK, REMOVE INSTALL P-10 THE BOTTOM SHIELD JUMPER, REPLACE PLATE, INSTALL P-10 SHIELD PLATE, AND JUMPER, REPLACE SLIDE DRAWER SHIELD PLATE, AND BACK IN SLIDE DRAWER BACK IN INSERT REMOTE SES010 INSTALLED

CRITICAL STEP PAGE 5 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. VERIFY ON SB069 PR P-10 NC_M OPERATOR SHOULD THAT THE PR P-10 PARTIAL TRIP LIGHT VERIFY ON SB069 Comments:

NC_M PARTIAL TRIP FOR N42 IS NOT LIT THAT THE PR P-10 LIGHT FOR N42 IS NC_M PARTIAL TRIP NOT LIT LIGHT FOR N42 IS NOT LIT S U

14. PLACE THE OS/STA WILL OPERATOR SHOULD CHANNEL JUMPED GENERATE AN EOSL INFORM THE OS/STA Comments:

IN THE EOSL AND AND ATTACH THE OF THE NEED TO ATTACH THIS COMPLETED GENERATE AN EOSL COMPLETED ATTACHMENT TO FOR THE JUMPED ATTACHMENT TO THE EOSL CHANNEL AND THE EOSL ATTACH THE COMPLETED ATTACHMENT WITH THE EOSL S U

15. IF THIS OPERATOR SHOULD ATTACHMENT WAS RETURN TO Comments:

PERFORMED IN ATTACHMENT 2 CONJUNCTION WITH ATTACHMENT 1-4, RETURN TO THE APPROPRIATE ATTACHMENT

CRITICAL STEP PAGE 6 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. IN SB042, ON BS-3 AND BS-4 IN OPERATOR SHOULD CHANNEL TEST SB042, ON CHANNEL DIRECT I&C TECHS Comments:

CARD TS/421C/D (8- TEST CARD TO PLACE BS-3 AND 22), PLACE BS-3 AND TS/421C/D (8-22) ARE BS-4 IN THE TEST BS-4 IN THE TEST IN THE TEST POSITION IN SB042, POSITION POSITION ON CHANNEL TEST CARD TS/421C/D (8-22)

USE BATCH FILE BAT SE022.TXT S U

17. VERIFY ON SB069 OTT L2 TB421C OPERATOR SHOULD THAT THE PR HI SETPT NC42R VERIFY ON SB069 Comments:

FOLLOWING PR HI FLUX NC42U THAT THE STATUS LIGHTS PR LO SETPT NC42P FOLLOWING STATUS ARE LIT: STATUS LIGHTS ARE LIGHTS ARE LIT:

LIT ON SB069 OTT L2 TB421C OTT L2 TB421C PR HI SETPT NC42R PR HI SETPT NC42R PR HI FLUX NC42U PR HI FLUX NC42U PR LO SETPT NC42P PR LO SETPT NC42P S U

18. VERIFY ON SC066W CHAN II INPUT TO C-3 OPERATOR SHOULD THAT THE AND N42 BYP C-2 VERIFY ON SC066W Comments:

FOLLOWING OVER PWR ROD STOP THAT THE STATUS LIGHTS STATUS LIGHTS ARE FOLLOWING STATUS ARE LIT: LIT ON SC066W LIGHTS ARE LIT:

CHAN II INPUT TO C- CHAN II INPUT TO C-3 3 AND N42 BYP C-2 AND N42 BYP C-2 OVER PWR ROD OVER PWR ROD STOP STOP

CRITICAL STEP PAGE 7 of 8

JPM NO: ILE-2002-S5 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR YOU ACKNOWLEDGES CONTROL ROOM HAVE VERIFIED THE THE TASK IS SUPERVISOR HE HAS PROPER BISTABLE COMPLETED VERIFIED THE LIGHTS ARE LIT ON PROPER BISTABLE SC066W LIGHTS ARE LIT ON SC066W S U

20. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 8 of 8

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE PLANT HAS EXPERIENCED A FAILURE OF POWER RANGE CHANNEL N42. ALL IMMEDIATE OPERATOR ACTIONS HAVE BEEN COMPLETED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO PERFORM POWER RANGE CHANNEL N42 TRIP INITIATION USING ATTACHMENT 2 OF OTO-SE-00003, POWER RANGE NUCLEAR CHANNEL FAILURE. INFORM THE CONTROL ROOM SUPERVISOR WHEN YOU HAVE VERIFIED THE PROPER BISTABLE LIGHTS ARE LIT ON SC066W.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM NO: ILE-2002-S6 K/A NO: 008A4.01 COMPLETION TIME: 12 MINUTES K/A RATING: 3.3/3.1 JOB TITLE: URO/SRO REVISION: APRIL 29, 2002 DUTY: COMPONENT COOLING WATER SYSTEM TASK TITLE: RESTORATION OF CCW FROM INADVERTENT CIS B The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY, REVISION 2 TOOLS/EQUIPMENT: NONE FACILITY REPRESENTATIVE: DATE:

CHIEF EXAMINER: DATE:

JPM NO: ILE-2002-S6 Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE PLANT HAS EXPERIENCED AN INADVERTENT CIS B ISOLATION. THE CREW IS RESPONDING PER OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY. ALL CCW CONTAINMENT BYPASS ISOLATION VALVES HAVE BEEN SUCCESSFULLY OPENED. THE CAUSE OF THE INADVERTENT CIS B ISOLATION HAS BEEN CORRECTED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO RESTORE NORMAL CCW FLOW ALIGNMENT TO/FROM CONTAINMENT BY PERFORMING STEPS 6.3 THROUGH 6.5.1.1 OF OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: USE IC-166.

OPEN ALL CCW CTMT BYPASS VALVES, THEN ACTUATE CIS B ENSURE THE STATUS BOARD REFLECTS THE CCW CTMT BYPASS VALVES ARE OPEN.

Task Standard: UPON COMPLETION OF THIS JPM, NORMAL CCW FLOW ALIGNMENT TO/FROM CONTAINMENT WILL HAVE BEEN ESTABLISHED PER OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY.

START TIME:

STOP TIME:

PAGE 1 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. OBTAIN A COPY OF PROVIDE OPERATOR SHOULD OTO-SA-00002, OPERATOR WITH OBTAIN A COPY OF Comments:

SPURIOUS PROCEDURE COPY OTO-SA-00002, CONTAINMENT (GREEN SHEETS) SPURIOUS SPRAY AND CONTAINMENT CONTAINMENT SPRAY AND PHASE B ISOLATION CONTAINMENT RECOVERY PHASE B ISOLATION RECOVERY S U

2. RESET CIS B USING SB HS-52 AND OPERATOR SHOULD SB HS-52 AND SB HS-55 HAVE BEEN RESET CIS B USING Comments:

SB HS-55 ON RL018 RESET SB HS-52 AND SB HS-55 ON RL018 STEP 6.3 S U

3. VERIFY THAT ANNUNCIATOR 59B OPERATOR SHOULD ANNUNCIATOR 59B IS NOT LIT VERIFY THAT Comments:

IS NOT LIT ANNUNCIATOR 59B IS NOT LIT STEP 6.3.1

CRITICAL STEP PAGE 2 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. RESTORE NORMAL NOTE: CCW FLOW OPERATOR SHOULD CCW FLOW FROM RCPs WILL PERFORM THE Comments:

ALIGNMENT AUTO CLOSE FOLLOWING VALVE TO/FROM DURING THESE ALIGNMENTS:

CONTAINMENT BY RESTORATION PERFORMING THE STEPS, THE FOLLOWING VALVE SIMULATOR ALIGNMENT IN OPERATOR WILL SEQUENCE: ACKNOWLEDGE THESE ALARMS AND STEP 6.4 TAKE THE APPROPRIATE ACTIONS S U

5. OPEN CTMT SUPPLY EG HIS-58 RED LIGHT OPERATOR SHOULD EG HIS-58 ON RL019 IS LIT AND GREEN OPEN CTMT SUPPLY Comments:

LIGHT IS OUT EG HIS-58 ON RL019 STEP 6.4 S U

6. OPEN CTMT EG HIS-59 RED LIGHT OPERATOR SHOULD RETURN EG HIS-59 IS LIT AND GREEN OPEN CTMT RETURN Comments:

ON RL019 LIGHT IS OUT EG HIS-59 ON RL019 STEP 6.4

CRITICAL STEP PAGE 3 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. OPEN THERMAL EG HIS-61 RED LIGHT OPERATOR SHOULD BARRIER EG HIS-61 IS LIT AND GREEN OPEN THERMAL Comments:

ON RL019 LIGHT IS OUT BARRIER EG HIS-61 ON RL019 STEP 6.4 S U

8. OPEN CTMT EG HIS-60 RED LIGHT OPERATOR SHOULD RETURN EG HIS-60 IS LIT AND GREEN OPEN CTMT RETURN Comments:

ON RL019 LIGHT IS OUT EG HIS-60 ON RL019 STEP 6.4 S U

9. OPEN THERMAL EG HIS-62 RED LIGHT OPERATOR SHOULD BARRIER EG HIS-62 IS LIT AND GREEN OPEN THERMAL Comments:

ON RL019 LIGHT IS OUT BARRIER EG HIS-62 ON RL019 STEP 6.4

CRITICAL STEP PAGE 4 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. OPEN CTMT SUPPLY EG HIS-71 RED LIGHT OPERATOR SHOULD EG HIS-71 ON RL019 IS LIT AND GREEN OPEN CTMT SUPPLY Comments:

LIGHT IS OUT EG HIS-71 ON RL019 STEP 6.4 S U

11. CAUTION: IF ANY OPERATOR SHOULD CCW REVIEW CAUTION Comments:

CONTAINMENT ISOLATION VALVE FAILED TO OPEN IN STEP 6.4, THEN THE RESPECTIVE CCW CONTAINMENT BYPASS ISOLATION VALVE MUST REMAIN OPEN S U

12. CLOSE THE CCW OPERATOR SHOULD CTMT BYPASS PERFORM THE Comments:

ISOLATION VALVES FOLLOWING VALVE AND PLACE THE ALIGNMENTS:

POWER LOCKOUT SWITCHES IN ISO, UNLESS THE VALVE(S) ARE OPEN DUE TO A FAILURE IN STEP 6.4 STEP 6.5

CRITICAL STEP PAGE 5 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. CLOSE EGHV0071 EG HIS-126 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0071 Comments:

EG HIS-126 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-126 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER S U

14. PLACE THE POWER EG HIS-126A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-126A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-126A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER S U

15. CLOSE EGHV0058 EG HIS-127 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0058 Comments:

EG HIS-127 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-127 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER

CRITICAL STEP PAGE 6 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

16. PLACE THE POWER EG HIS-127A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-127A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-127A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER S U

17. CLOSE EGHV0060 EG HIS-130 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0060 Comments:

EG HIS-130 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-130 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER S U

18. PLACE THE POWER EG HIS-130A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-130A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-130A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER

CRITICAL STEP PAGE 7 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. CLOSE EGHV0059 EG HIS-131 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0059 Comments:

EG HIS-131 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-131 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER S U

20. PLACE THE POWER EG HIS-131A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-131A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-131A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER S U

21. CLOSE EGHV0062 EG HIS-132 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0062 Comments:

EG HIS-132 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-132 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER

CRITICAL STEP PAGE 8 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

22. PLACE THE POWER EG HIS-132A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-132A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-132A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER S U

23. CLOSE EGHV0061 EG HIS-133 GREEN OPERATOR SHOULD BYPASS USING LIGHT IS LIT AND CLOSE EGHV0061 Comments:

EG HIS-133 ON RL020 RED LIGHT IS OUT BYPASS USING EG HIS-133 ON RL020 STEP 6.5 STEPS 13, 15, 17, 19, 21, & 23 MAY BE PERFORMED IN ANY ORDER S U

24. PLACE THE POWER EG HIS-133A IS IN OPERATOR SHOULD LOCKOUT SWITCH THE ISO POSITION PLACE THE POWER Comments:

EG HIS-133A IN THE LOCKOUT SWITCH ISO POSITION ON EG HIS-133A IN THE RL020 ISO POSITION ON RL020 STEP 6.5 STEPS 14, 16, 18, 20, 22, & 24 MAY BE PERFORMED IN ANY ORDER

CRITICAL STEP PAGE 9 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

25. IF ANY CCW ALL CCW CONTAINMENT CONTAINMENT Comments:

BYPASS ISOLATION BYPASS ISOLATION VALVE(S) IS OPEN, VALVES SHOULD BE ENSURE THE CLOSED APPROPRIATE ADMINISTRATIVE CONTROLS ARE IMPLEMENTED IN THE CAUTIONS PRIOR TO STEP 6.5 STEP 6.5.1 S U

26. THE CONTROL OPERATOR SHOULD ROOM OPERATOR IS UPDATE THE STATUS Comments:

ALSO REQUIRED TO BOARD UPDATE THE CONTROL ROOM STATUS BOARD AS TO THE POSITION OF THE VALVES STEP 6.5.1.1 S U

27. INFORM THE THE CONTROL OPERATOR SHOULD CONTROL ROOM ROOM SUPERVISOR INFORM THE Comments:

SUPERVISOR THAT ACKNOWLEDGES CONTROL ROOM NORMAL CCW THE TASK IS SUPERVISOR THAT FLOW ALIGNMENT COMPLETE NORMAL CCW FLOW TO/FROM ALIGNMENT CONTAINMENT HAS TO/FROM BEEN RESTORED CONTAINMENT HAS BEEN RESTORED

CRITICAL STEP PAGE 10 of 11

JPM NO: ILE-2002-S6 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

28. THE JPM IS COMPLETE Comments:

RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 11 of 11

Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: CALLAWAY PLANT IS IN MODE 3. THE PLANT HAS EXPERIENCED AN INADVERTENT CIS B ISOLATION. THE CREW IS RESPONDING PER OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY. ALL CCW CONTAINMENT BYPASS ISOLATION VALVES HAVE BEEN SUCCESSFULLY OPENED. THE CAUSE OF THE INADVERTENT CIS B ISOLATION HAS BEEN CORRECTED.

Initiating Cues: THE CONTROL ROOM SUPERVISOR HAS DIRECTED YOU (BOP REACTOR OPERATOR) TO RESTORE NORMAL CCW FLOW ALIGNMENT TO/FROM CONTAINMENT BY PERFORMING STEPS 6.3 THROUGH 6.5.1.1 OF OTO-SA-00002, SPURIOUS CONTAINMENT SPRAY AND CONTAINMENT PHASE B ISOLATION RECOVERY. INFORM THE CONTROL ROOM SUPERVISOR WHEN COMPLETE.

ML030140496

Contents

Text

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

ML030140496

Text

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

Search