ML20207L567

JOB PERFORMANCE MEASURE )

i Step 5: Throttle open HCV-3615 and HCV-3625, LPSI header isolation Critical Step valves (step 1F)

Sat Standard: Operator opens HCV-3615 and HCV-3625 to throttled position Unsat Cue: (RTGG 206)

HCV-3615 and HCV-3625 Indicate red and green lights illuminated

Comments: ,

Steo 6: Ensure V3480, V3481, and V3664 are open (step 1G)

Standard: Operator observes V3480, V3481, are open and places the Sat keyswitch for V3664 in the OPEN position.

Unsat Cue: (RTGB 206)

V3480, V3481, and V3664 Indicate red lights illuminated

Comments:

Step 7: Open FCV-3306, SDC flow control valve (step 1 H) Critical Step i Standard: Operator places the keyswitch for FCV-3306 to locked open position Sat Cue: (RTGB 206) Unsat ,

FCV-3306 Indicates red light lliuminated*

Comments:

I Steo 8: Ensure open V 3517 to HX 2A valve (temporary step 11) Critical Step Standard: Operator places the control switch for V3517 in the OPEN position Sat Cue: (RTGB 206) Unsat i V3517 Indicates red light illuminated

1 NOTE: This step is a temporary change to the procedure !

Comments: ;

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ST. LUCIE TRAINING CEPT.

JOB PERFORMANCE MEASURE PAGE5 1

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I 31ep_9; 9 Ensure open HCV-14-3A, CCW to SDC HX (temporary step 1J )

i Standard: Operator observes HCV-14-3A indicates open . Sat Cue: (RTGB 206) Unsat HCV 14-3A indicates red light illuminated

Comments:

i Stoo 10: Start 2A LPSI pump (temporary step 1K) Critical Step ,

Standard: Operator announces and places 2A LPSI pump control switch to Sat ,

Start while observing light indication and pump amps Unsst Cue: (RTGB 206) 2A LPSI pump indicates red light illuminated, amps stable

Comments:

Step 11: Slowly close V-3444,2A LPSI pump suction valve (temporary step Critical Step 1N1)

Sat Standard: Operator notifies SNPO and directs him to slowly close V-3444 Unsat Cue: SNPO Informs control room V-3444 is closed

Comments:

Step 12: Verify suction form RCS is adequate by observing stable flow on FRC-3306 (temporary step 1N2) !

Sat ,

Standard: Operator observes FRC-3306 and verifies flow Unsat I

Cue: (RTGB 206)

FRC-3306 Indicates flow

Comments: :

$ I ST. LUCIE TRAINING DEPT, JOB PERFORMANCE MEASURE i PAGE 6 l

Step 13: Open HCV-3615 and HCV-3625, LPSI header isolation valve to Critical Step

desired position (temporary step 1N3)

Sat Standard: Operator places control switches for HCV-3615 and HCV-3625 to open and observes red light indication (MAY ALREADY BE OPEN) Unsat gu_ej u (RTGB 206)

HCV-3615 and HCV-3625 indicate red lights illuminated *

lF NOT OPEN Comments:

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly Step 14: When temperature stabilizes, adjust FCV 3306 to the desired flow Critical Step ,

rate as indicated on FR-3306 (temporary step 1N4)

Sat Standard: Operator places keyswitch for FCV-3306 to the Modulate position, then, using the control switch for FCV-3306, throttles flow to Unsat approximately 1800-2000 gpm Qug (RTGB 206)

FCV 3306 Indicates red and green lights illuminated, FRC-3306 Indicates 1800-2000 gpm' Comments:

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i Step 15: Close V3536, SDC warmup valve (temporary step 1N5) Critical So y Standard: Operator pla.:es the keyswitch for V3536 in the Locked Closed or Sat .

Modulate position (if in modulate, then places the control switch for V3536 to the closed position) l Unsat .

Cue: (RTGB 206)

V3536 Indicates green light illuminated

Comments:

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ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE l PAGE 7 1 l

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._ . -. _. . . . . . . .. . .. _ . _ . _ ._ __ _ ~-. . . _ . . - . -

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Sten 16: Throttio open HCV-3657 to obtain desired RCS cooldown rate Critical Step (temporary step 1N6)

Sat Standard: Operator places the keyswitch for HCV-3657 to the Modulate position, then places the control switch for HCV-3657 to the open Unsat 1 position until cooldown rate is observed on TR-3303Z

]

Cue: (RTGB 206) -

HCV-3657 Indicates red and green light indication, cooldown rate observed

Comments:

END OF TASK

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly

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i Stop Time i

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ST. LUCIE TRAINING DEPT.

, JOB PERFORMANCE MEASURE PAGE 8 l

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JPM QUESTION # 1 REFERENCE ALLOWED: X YES' NO Quention: Describe the major difference in the Unit 1 and Unit 2 Shutdown Cooling Purification systems and the advantages or disadvantages of each.

Expected Response: Unit 1 SDC purification inlet to the CVCS enters the system upstream of the Letdown heat exchanger. This allows SDC ,

purification to be placed in service much earlier than Unit 2, I which enters the CVC'i downstream of the Letdown heat exchanger.

CANDIDATES RESPONSE ,

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i K/A: 005K1.04 Importance: 2.9 / 3.1

References:

P&lD 8770-G-078, sheet 120A,2998-G-078, sheet 120 I ST. LUCIE TRAINING DEPT. l job PERFORMANCE MEASURE !

PAGE9 I l

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JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: Unit 1 is in mode 5, the15th day of a refueling outage, nozzle dam installation is in progress. RCS temperature is 130 F, RCS level is 31'4" as indicated on LI-1117-1. All shutdown cooling flow has been lost.

Assuming shutdown cooling cannot be restored, when will the RCS boil?

Expected Response: 40 minutes (+ /-2 minutes) ,

CANDl DATES RESPONSE K/A: 005G2.1.25 l

1 Importance: 2.8 / 3.1 !

References:

P&lD 2998-G-087, sheet 131 l l

ST. LUCIE TRAINING DEPT.

JOD PERTORMANCE MEASURE PAGE 10 i

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JPM QUESTION # 1 CANDIDATE COPY d

REFERENCE ALLOWED: X-YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Describe the major difference in the Unit 1 and Unit 2 Shutdown Cooling Purification systems and the advantages or disadvantages of each.

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ST. LUCIE TRAINING DEPT. )

i JOB PERFORMANCE MEASURE l PAGE 11 j l

JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Unit 1 is in mode 5, the 15th day of a refueling outage, nozzle dam ,

installation is in progress. RCS temperature is 130 F, RCS level is 31'4" ;

as indicated on LI-1117-1. All shutdown cooling flow has been lost. l Assuming shutdown cooling cannot be restored, when will the RCS boil?

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i ST. LUCIE TRAINING DEPT. l JOB PERFORMANCE MEASURE PAGE 12 i

CANDIDATE CUE SHEET (TO BE RETURNED TO r ?!i EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 2 was on Shutdown Cooling, making preparations for nozzle dam installation. The RCS level had been at hot leg centerline when valve leakage resulted in a level decrease below hot leg centerline requiring 2B LPSI pump to be stopped. The valve leakage has been isolated and the RCS level has been raised to 35'1" using the charging pump. The RCS has not heated up appreciably.

INITIATING CUE: ,

The ANPS has directed that shutdown cooling be re-established using the 2A LPSI pump IAW ONP 2-0440030, Appendix E. '

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ST. LUCtE TRAINING DEPT.

PAGE 13 '

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REGION 11 INITIAL LICENSE EXAMINATION l

JOB PERFORMANCE MEASURE ,

! ST. LUCIE NUCLEAR PLANT DEPRESSURIZE THE RCS l l

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CANDIDATE j EXAMINER l

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REGION 11 -

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST LUCIE NUCLEAR PLANT Task: Control Pressurizer Pressure in individual manual mode !

Alternate Path; Yes No X Facility JPM #: New i

Task Standard: Successfully depressurize the RCS to 1850 psia Preferred Evaluation Location:

Simulator X Control Room In-Plant Preferred Evaluation Mathod:

Perform X Simulate

References:

None Validation Time 15 minutes Time Critical No Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade Examiner: Signature:

Name sT. LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE '

-I a i Tools / Equipment / Procedures Needed:

4 None i

Road to Candidate 4:

Directions to s.-d!-tt for in-Plant or Control Room JPMs:

i

. I will explain the initial conditions and state the task to be performed. All in-plant or I control room JPM steps, including any communications, shall be simulated for this JPM. 1 i

Under no circumstances,' unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by retuming the i i handout sheet i provided you. J

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Directions to candidate for Simulator JPMs: l I _will explain the initial conditions and state the task to be performed. All simulator JPM j steps, including any communications, shall be performed for this JPM. You are you to j operate any plant equipment that is necessary for the completion of this JPM. The ;

simulator will provide the cues as you' perform this JPM. Ensure you indicate to me 1; when you finish your assigned task by retuming the handout sheet I provided you.

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Initial Conditions: Unit 2 is currently in mode 3. The 2B1 RCP has developed i

. an oil leak and the unit was removed from service to !

facilitate repairs.: The NPS has made the decision to remain ,

in hot standby while repairs are made. j l

initiating Cues: The ANPS has directed you to depressurize the RCS to 1850 psia.

using aux spray, i i

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PAGE 3 {

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Start Time Sten 1: Obtain two auxiliary spray keys from the ANPS key locker Standard: Operator obtains and signs out keys #76 & 77 from the ANPS key Sat locker Unsat .l hg Keys 76 and 77 signed out* >

Comments: ;

SigLt Close SE-02-1 and SE-02-2, Charging header isolation valves Standard: Operator places control switch for SE-02-1 and SE-02-2 in the Sat CLOSED position Unsat Cue: (RTGB 205) l SE42-1 and SE-02-2 indicate green lights illuminated * '

NOTE: if these valves are not closed, depressurization will be VERY slow, ;

candidate may perform step 3 prior to step 2 - OK 3 Comments: !

Sten 3: Open SE-02-3 and SE-02-4, Auxiliary spray isolation valves Critical Step Standard: Operator places the keyswitches for SE-02-3 and SE-02-4 in the . Sat OPEN position Unsat

@g (RTGB 203)

SE-02-3 and SE-02-4 Indicate red lights illuminated * ,

l Commants: ,

Step 4: Depressurize the RCS to 1850 psia Standard: Operator observes RCS pressure indications on the OSPDS, Sat PI-1108-1 or PR-1100. Operator should also observe RCS .

subcooling on the QSPDS and ensure subor ating remains above Unsat !

20 F j

@g (RTGB 203) ,

RCS pressure and subcooled margin decreasing

l Comments: j

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to

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verify the JPM is being performed correctly '

, ST. LUCIE TRAINING DEPT. l JOB PERFORMANCE MEAsVRE PAGE 4 i,

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Step 5: Secure auxiliary spray when RCS pressure is 1850 psia (+/- 20 psia) Critical Step Standard: Operator places keyswitches for SE-02-3 and SE-02-4 to the Sat -

CLOSED position Unsat l u

Q.ue.; (RTGB 203) !

RCS pressure indicates 1830-1870 pala* -

Comments:

Step 6: Open f!E-02-1 and SE-02-2. <.arging header isolation valves i

Standard: Operator places co601 switches for SE-02-1 and SE-02 2 to the Sat '

OPEN position j Unsat i Cue: SE-02-1 and SE-02 2 indicate red lights illuminated * ,

Comments: ,

END OF TASK !

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If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to ,

verify the JPM is being performed correctly Stop Time f

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i ST. LUCIE TRAINING DEPT.

' JOB PERFORMANCE MEASURE !

PAGE5 d l

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JPM QUESTION # 1 l

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REFERENCE ALLOWED: X l

YES NO ;

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Question: Explain two ways the pressurizer main sprays are protected against damage due to thermal shock. !

I Expected Response: The seats of the main spray valves are notched to allow a small amount of flow (.26 gpm) at all times. (.5) The main spray valves also have a bypass needle valve that is '

adjusted to allow a continuous amount of flow designed to keep the spray lines warm.(adjusted so spray line maintains within 20 F of Tcold) (.5) i CANDIDATES RESPONSE l

K/A: 010K4.01 Importance: 2.7 / 2.9 l

References:

0711206, " Pressurizer Pressure and Level Control", P&lD 2998-G-078, i sheet 109 !

ST. LUCIE TRAINING DEPT. !

JOB PERFORMANCE MEASURE PAGE 6 l

I JPM QUESTION # 2 REFERENCE ALLOWED: X YES- NO i Question: Assuming the initial conditions of this JPM, what method would be used to depressurize the RCS if Main and Aux spray were not available?

Expected Response: Performance of an RCS cooldown using steam generator heat removal or manual operation of the letdown system. ,

(Full credit for either answer) ;

CANDIDATES RESPONSE 1

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K/A: 010A1.07 Importance: 3.7 / 3.7

References:

2-EOP-15., " Functional Recovery" l

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ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE ,

PAGE 7 i i

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JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Explain two ways the pressurizer main sprays are protected against damage due to thermal shock.

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ST. LUCIE TRAINING DEPT. i JOB PERFORMANCE MEASURE PAGE8

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JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Assuming the initial conditions of this JPM, what method would be used to depressurize the RCS if Main and Aux spray were not available?

ST LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE PAGE 9

1 CANDIDATE CUE SHEET :

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 2 is currently in mode 3. The 2B1 RCP has developed an oilleak and the unit was removed from service to facilitate repairs. The NPS has made the decision to remain in hot standby while repairs are made.

INITIATING CUE:

The ANPS has directed you to depressurize the RCS to 1850 psia. using aux spray. .

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sT. LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE PAGE 10

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REGION 11 4 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l ST. LUCIE NUCLEAR PLANT ;

COOL THE QUENCH TANK UNIT 2 !

CANDIDATE EXAMINER ll l

i REGION ll lNITIAL LICENSE EXAMINATION !

JOB PERFORMANCE MEASURE i ST LUCIE NUCLEAR PLANT l

Task: Fill the PRT, Monitor the PRT Alternate Path: Yes X No Facility JPM #: New Task Standard: Perform a cooling evolution on the Quench tank, trip the reactor Preferred Evaluation Location:

Simulator X Control Room _ in-Plant Preferred Evaluation Method:

Perform X Simi,.ote

References:

OP 2-0120025, " Quench Tank Operation" ,

Validat!on Time 10 minutes Time Critical No Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade Examiner: Signature:

Name a

ST LUclE TRAINING DEPT.

Tools / Equipment / Procedures Needed:

Read to Candidate )

l Directions to candidate for in-Plant or Control Room JPMs: '

I will explain the initial conditions and state the task to be performed. All in-plant or control room JPM steps, including any communications, shall be simulated for this JPM. ;

Under no circumstances, unless directed by the examiner, are you to operate any plant 1

equipment. I will provide initiating cues and reports on other actions when directed by l you. Ensure you indicate to me when you finish your assigned task by retuming the l handcut sheet I provided you. j l

Directions to candidate for Simulator JPMs:

I will explain the initial conditions and state the task to be performed. All simulator JPM steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The -

simulator will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you, initial Conditions: V 1201, Pressurizer Code Safety Valve has been identified to be leaking approximately .05 gpm. Quench tank temperature has increased significantly.

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Initiatina Cues: The ANPS has directed you to cool the quench tank using the continuous fill and drain method IAW OP 2-0120025.

ST. LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE PAGE 3 l

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Start Time ,

$tep 1: Redice Quench tank fevel to approximately 60% (step 8.4.1) Critical Step ;

Standard: Operator opens V1401 and monitors quench tank level until 60% Sat level is reached (Candidate has the option of leaving V1401 open or cycling V1401) Unsat l Cue: (RTGB 203)

V1401 indicates red light illuminate ( level at 60%*

Comments:

Step 2: Open SE-15-2 to begin filling the quench tank (step 8.5.2) Critical Step Standard: Operator opens SE-15-2 Sat Cue: (RTGB 203) Unsat SE-15-2 indicates red light liluminated*

Comments: ;

Step 3: Continue filling quench tank until level reaches approximately 70%

(step 8.5.3) Sat Standard: Operator monitors quench tank level and temperature until 70% Unsat levells reached Cqe; (RTGB 203)

Quench tank level is 70%* ,

Comments:

1 Stepdi Close SE-15-2 (step 8.5.4)

)

Critical Step ,

i Standard: Operator places control switch for SE-15-2 to Closed Sat l Cue: (RTGB 203) Unsat SE-15 2 indicates red light illuminated

Comments:

If JPM is performed on tne simulator, cues will not be verbalized by the examiner, but will be used to verity the JPM is being performed correctly.

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 4 4

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Step 5: Repeat steps 1-4 until quench tank temperature is reduced less than 120"F (step 8.5.5)

Sat Stanclard: Operator monitors quench tank temperature and level Unsat l Cue: (RTGB 203)

I Quent i tank pressure, temperature and level are increasing dramatically as V1201 Code Safety fully opens

I Comments:

Step 6: Trip the reactor and turbine as Pressurizer level and pressure are Critical Step decreasing rapidly. (Step not proceduralized)

Sat Standerd: Operator may refer to ONOP 2-0120036, " Pressurizer Relief /

Safety Valve", but trips the reactor and turbine on decreasing RCS Unsat level and pressure indications.

Cue: Reactor and turbine tripped *

(Automatic reactor trip will NOT occur, canc'idate must recognize and manually trip the reactor if not already tripped)

Comments:

End of Task

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly.

Stop Time i

ST. LUCIE TRAINING DLPT.

JOB PERFORMANCE MEASURE PAGE5

JPM QUESTION # 1 REFERENCE ALLOWED: X YES NO Question: Assuming V-1201 failed to close post trip, describe RCS response.

Expected Response: RCS pressure will decrease (.3)

Saturation conditions wil develop in the upper head and a void will form (.4)

Pressurizer level will increase to 100% (.3)

CANDIDATES RESPONSE 1

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i K/A: 007A2.01 1 Importance: 3.9 / 4.2

References:

0711824," Loss of Coolant Accident Event and Procedure" l

ST. LtlCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 6 i

m :_,Aa JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: State two major differences between Unit 1 and Unit 2 quench tanks.

Expected Response: Unit 1 quench tank has a CCW supplied cooling blanket, Unit 2 does not. (.5) Unit 2 has an RTGB controlled primary makeup water isolation valve, on Unit 1, primary makeup water to containment must be opened to fill the quench tank and is normally kept isolated. (.5)

CANDIDATES RESPONSE i

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w K/A: 007K4.01 Importance: 2.6 / 2.9 l

References:

0711206, " Pressurizer Pressure and Level Control" ST. LUCIE TRAINING DEPT.

l JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) i l

Question: Assuming V-1201 failed to close post trip, describe RCS response.

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l ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGEB

JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: State two major differences between Unit 1 and Unit 2 quench tanks.

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JOB PERFORMANCE MEASURE PAGE 9 i

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CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

V 1201, Pressurizer Code Safety Valve has been identified to be leaking approximately

.05 gpm. Quench tank temperature has increased significantly.

INITIATING CUE:

The ANPS has directed you to cool the quench tank using the continuous fill and drain method IAW OP 2-0120025.

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I ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 10 i

REGION ll lNITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE :

ST. LUCIE NUCLEAR PLANT '

RESTORE OFFSITE POWER TO 2A3 4.16KV BUS CANDIDATE EXAMINER l

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REGION 11 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST LUClE NUCLEAR PLANT '

Task: Unload the 'EDG, Shutdown the EDG '

Alternate Path: Yes No X F_acility JPM #: New i

J Task Standard: Restore offsite power to the 2A3 4.16KV bus and unload and shutdown the 2A EDG Preferred Evaluation Location:

Simulator X Control Room In-Plant Preferred Evaluation Method:

Pedorm X Simulate

References:

2-EOP-99, Appendix D Validation Time 20 minutes Time Critical No Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade Examiner: Signature: !

Name l

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE j PAGE 2 l

l Tools / Equipment / P ocedures Needed:

2-EOP-99, Appendix D Read to Candidate Directions to candidate for in-Plant or Control Room JPMs:

I will explain the initial conditions and state the task to be performed. All in-plant or control room JPM steps, including any communications, shall be simulated for this JPM l

~ Under no circumstances, unless directed by the examiner, are you to operate any plart !

equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet i provided you.

Directions to candidate for Simulator JPMs:

I will explain the initial conditions and state the task to be performed. All simulator JPM ,

steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The simulator will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Initial.Qonditions: A loss of offs!te power has occurred on Unit 2. Both Emergency Diesel Generators are running and carrying their respective 4.16KV !

busses. Offsite power has been restored and is now available and !

2-EOP-99, Table 6 has been completed. j Initiatina Cues: The ANPS has directed you to restore offsite power to the 2A3 ;

4.18KV bus IAW 2-EOP-99, Appendix D l

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sT. LUCIE TRAINING DEPT.

JoD PERFORMANCE MEASURE PAGE 3 i

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Start Time t

Step 1; insert the sync plug and turn to position ST-2A2 (step 28) Critical Step Standard: Operator obtains sync plug, inserts it and places it to ST-2A2 Sat ,

position j Unsat '

Cue: (RTGB 201)

Sync plug in ST-2A2 position * )

i Comments:

l Step 2: Close breaker 2-20102, "Startup transformer 2A" (step 2C) Critical Step j Standard: Operator places breaker 2-20102 to the CLOSE position and Sat observes red light indication Unsat Cue: (RTGB 201)

Breaker 2-20102 indicates red light illuminated

Comments; Step 3: Close breaker 2-20109, *4.16 KV bus Tie 2A2 - 2A3" (step 2D) Critical Step Standard: Operator places breaker 2-20109 to the CLOSE position and Sat observes red light indication Unsat Cyel (RTGB 201)

Breaker 2-20109 indicates red light illuminated

Comments:

Step 4: Verify the amber light on the 2A EDG govemor control is lit (step 2J) I Standard: Operator observes the 2A EDG governor control and verifies the Sat amber light is lit Cue: (RTGB 201)

Amber light illuminated

Comments:

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly.

I ST. LUCtE TRAINING DEPT. l JOB PERFORMANCE MEASURE I PAGE 4

Step 5: Insert the sync plug in the 2A EDG control panel, and turn to the TIE- Critical Step 2A3 position (step 2K)

Sat i Standard: Operator inserts the sync plug and places it to the TIE-2A3 position Unsat

.Qgd (RTGB 201) !

Sync plug in TIE 2A3 psoltion*

Comments:

Step 6: Match voltage using DG voltage control (step 2L) Critical Step Standard: Operator observes incoming and outgoing voltage indication and Sat adjusts voltage control switch until voltages are matched !

Unsat l Qug; (RTGB 201) ;

incoming and outgoing voltages matched

Comments:

Step 7: Using DG governor control, adjust synchroscope to slow in the Critical Step )

counterclockwise direction (step 2M) j Sat i S_tyndard: Operator observes the synchroscope and adjusts governor control i switch until indicator is moving slow in the counterclockwise direction Unsat 1 Qug; (RTGB 201)

Synchroscope indicates slow in the counterclockwise direction

l Comments: i Step 8: When synchroscope is in the 12 O' CLOCK position, then close Critical Step breaker 2 20209,"4.16 KV bus Tie 2A3 2A2* (step 2N)

Sat Standard: Operator observes the synchroscope to be in the 12 O' CLOCK l position, then places the control switch for breaker 2-20209 in the Unsat 1 CLOSED position Cue: (RTGB 201)

Breaker 2 20209 indicates red light 11luminated*

Comments:

If JPM is performed on the simulator, cues will not be verbalized by the :

examiner, but will be used to verify the JPM is being performed correctly.

ST. LUCIE TRAINING DEPT. l JOB PERFORMANCE MEASURE PAGE5 I

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Step 9: Hold DG govemor controlin the RAISE position untilload is greater Critical Step than 100 KW to avoid a reverse power trip (step 20) After load is greater than 100 KW, release the governor control switch (step 2P) Sat Standard: Operator positions the governor control switch to RAISE and Unsat -

observes the KW recorder to ensure load is greater than 100 KW at which time, he releases the governor control switch Cue: (RTGB 201) 2A EDG load greater than 100 KW*

t Comments:

Sten 10: Unload 2A EDG to 100 KW, then open breaker 2-20211, *2A D/G Critical Step 4.16 KV Breaker"(step 2O)

Sat Standard: Operator positions the governor control switch to LOWER and observes the KW recorder to ensure load is less than 100 KW at Unsat which time, he opens breaker 2-20211 Cue: (RTGB 201)

?A EDG load less than 100 KW, breaker 2-20211 Indicates green light illuminated

Cornments:

Sten 11: Remove the sync plug (step 2R)

Standard: Operator removes the sync plug and places it back in the holder Sat behind the DDPS console Unsat Cue: (RTGB 201)

Syne plug removed

Comments:

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly.

4 sT. LUCIE TRAINING DEPT.

Sten 12: If no ESFAS signal present, then stop the 2A Diesel Generator. The Critical Step diesel engine will automatically go to 450 rpm, remain there to 10 minutes and then stop (step 2S) Sat _ _ _

Standard: Operator places the control switch for 2A EDG to the STOP position Unsat and observes the red light above the control switch goes out Cue: (RTGB 201) 2A EDG red light Indication estinguished*

Comments; Sten 13: Verify proper restart condition by amber light indication on voltage Critical Step regulator and governor controls (step 2T)

Sat Standard; Operator observes voltage and governor controls and verifies amber light indication illuminated Unsat Cue: (RTGB 201)

Voltage regulator and governor controls indicate amber light llluminated*

Comments:

END OF TASK

If JPM is performed on the simulator, cues will not be verbalized by the examiner, but will be used to verify the JPM is being performed correctly.

Stop Time ST. LUCIE TRAINING DEPT.

i JPM QUESTION # 1 <

REFERENCE ALLOWED: X YES NO Question: . Explain the difference between Unit 1 and Unit 2 Emergency Diesel Generator starting air system and the reason for the difference.

1 i

Expected Response: Unit 1 has an air dryer system installed between the outlet of )

the air compressors and the air receivers. The reason for this system is to protect the air receivers, which are carbon 9 steel, from moisture damage. Unit 2 has stainless steel l tanks and does not require an air dryer system. 1 i

CANDIDATES RESPONSE )

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K/A: 064K1.05

)

importance: 3.4 / 3.9

References:

0711501, " Emergency Diesel Generators", P&lDs 2998-G-096 sheet 1C,8770-G-096 sheet 1C ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 8 ;

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JPM QUESTION # 2 REFERENCE' ALLOWED: X i YES NO Question: List the eight conditions that will trip a running Emergency Diesel Generator. In your list, denote which trips are in effect when the EDG was started by a safeguards signal.

Expected Response: 1. Low engine oil pressure (.1)

2. High engine water temperature (.1)

3. Engine overspeed* (.2)

4. Generator differential current * (.2)

5. Generator overcurrent (.1)

6. Generator reverse power flow (.1)

7. Loss of generator excitation (.1)

8. High crankcase pressure at (.1)

not bypassed on safeguards signal l

CANDIDATES RESPONSE l

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K/A: 064K4.02 l

Importance: 3.5 / 4.0

References:

0711501, " Emergency Diesel Generators" 1

ST. LUCIE TRANNG DEPT.

job PERFORMANCE MEASURE PAGE 9 ,

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JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Explain the difference between Unit 1 and Unit 2 Emergency Diesel i

Generator starting air system and the reason for the difference.

}

i ST, LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 10 s

1 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X ~

YES NO j (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) '

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Question: List the eight conditions that will trip a running Emergency Diesel I Generator. In your list, denote which trips are in effect when the EDG was {

started by a safeguards signal. )

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ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 11

l CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A loss of offsite power has occurred on Unit 2. Both Emergency Diesel Generators are running and carrying their respective 4.16KV busses. Offsite power has been restored i and is now available and 2-EOP-99, Table 6 has been completed.

i INITIATING CUgl The ANPS has directed you to restore offsite power to the 2A3 4.16KV bus IAW 2-EOP-99, Appendix D t l

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 12 l

I REGION 11

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT l

ESTABLISH AN ALTERNATE CHARGING FLOWPATH THROUGH THE AUX HPSI HEADER UNIT 1 l

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EXAMINER l

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R E GIO N ll INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST LUCIE NUCLEAR PLANT Task: Perform lineup of the CVCS l Alternate Path _; Yes No X Facility JPM #: 0821115 Task Standard: Establish a charging flowpath through the Aux HPSI header .

Preferred Evaluation Location:

Simulator Control Room X In-Plant Preferred Evaluation Method:

Perform Simulate X

References:

1-EOP-99, Appendix T Validation Time 20 minutes Time Critical No Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade Examiner: Signature: ,

Name ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE l PAGE 2

h 9

Tools / Equipment / Procedures Needed:

1-EOP-99, Appendix T Read to Candidate Directions to candidate for in-Plant or Control Room JPMs: !

I will explain the initial conditions and state the task to be performed. All in-plant or

- control room JPM steps, including any communications, shall be simulated for this JPM. .

Under no circumstances, unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Directions to candidate for Simulator dPMs:

I will. explain the initial conditions and state the task to be performed. All simulator JPM steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The -

simulator will provide the cues as you perform this JPM. Ensure you indicate to me ,

when you finish your assigned task by retuming the handout sheet I provided you.

initial Conditions: Unit 1 was tripped from 100% power (MOL) due to a problem with the Feedwater Regulating System. Subsequent to the trip it was discovered that two CEAs had stuck out and emergency boration was begun. The SNPO reported a pipe break in the charging header between V2429 and the containment penetration. The .

emergency boration line-up was secured. With the loss of the Reactivity Control safety function, it was decided to enter 1-EOP-15.

Initiatina Cues: LAW Reactivity Control Success Path 2: Emergency Boration CVCS, the ANPS has requested that you emergency borate using Aux HPSI header per Appendix T of 1-EOP-99.

ST. LUclE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 3

s Start Time r

Step 1: Close V3656, "HPSI 1 A discharge valve" (step 1 A) Critical Step Standard: Operator simulates obtaining key #54 and positioning V3656 to Sat Closed .

Unsat

_Qu!!; (RTGB 106)

V3656 Indicates red light illuminated Comments:

Step 2: Place all charging pump control switches to Stop while realigning system (step 1B) l Sat t Standard: Operator simulates placing 1 A,1B and 1C charging pump control switches to STOP Unsat ,

Cue: (RTGB 106)

All charging pump control switches in hard stop Comments:

Step 3: Locally close V2429, " Charging pump discharge isolation" (step 1C) Critical Step ;

Standa_rd; Operator contacts SNPO to locally close V2429 Sat Cug; SNPO reports V2429 is closed Unsat Comments: '

r Step 4: Open png of the following HPSI header isolation valves: HCV-3617, Critical Step HCV-3627, HCV-3637, HCV-3647 (step 1D)

Sat ,

Standard: Operator positions any one of the HPSI header isolation valves to f OPEN Unsat. __.

{

Cue: (RTGB 106)

Red light indication for selected valve Comments:.

ST. LUCIE TRAINING DEPT.

r Step 5: Locally open V2340," Charging pump discharge to Aux HPSI header Critical Step isolation (step 1E)

Sat Standard: Operator contacts SNPO to locally open V2340 Unsat Cue: SNPO reports V2340 open Comments:

Ele _g_6; 9 Start 2A or 2B BAM pump and open V2514 (step 1F) Critical Step Standard: Operator starts 2A or 28 BAM pump and positions V2514 to OPEN Sat Cys; (RTGB 105) Unsat BAM pump red light illuminated and V2514 red light illuminated Comments: l Step 7: Start desired charging pump and borate to maintain shutdown Critical Step margin greater than or equal to 3600 pcm (step 1G)

Sat Standard: Operator starts either 1 A,1B or 1C charging pump ;

Unsat Cue: (RTGB 105) ;

Red light illuminated on selected charging pump Comments:

Step 8: Verify charging flow to the RCS by observing pressurizer level ,

increase and applicable HPSI loop flow indication: F1-3311, F1-3321, F1-3331, F1-3341 (step 1H) Sat Standard: Operator observes pressurizer level and HPSI flow indications Unsat Cue: (RTGB 105,106)

Pressurizer level increasing, HPSI header flow indicated * ,

Comments: l l

ST. LUClE TRAINING DEPT, !

JOB PERFORMANCE MEASURE PAGE5

Step 9; Record all charging pump cycles using AP0010134 and forward to Tech Staff for review (step 11)

Sat Standard: Operator completes data sheet or contacts STA to complete data sheet s Unsat Qigt; AP 0010134 requirements completed Comments:

END OF TASK Stop Time ST. LUCIE TRAINING DEPT.

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1 JPM QUESTION # 1' l l

l REFERENCE ALLOWED: X l

YES NO !

i Question: How could this method of boration be accomplished if a loss of offsite !

power occurred with failure of the 1 A EDG prior to making the alignment? ;

l i

Expected ResDonse: (Although not proceduralized), the gravity feed valves j (V2508 and V2509) (.5) supplying 2B charging pump and !

local manual operation of the HPSI header isolation valves (HCV-3617, HCV-3627, HCV3637, HCV-3647) (.5) could ,

accomplish this method of boration. )

l CANDIDATES RESPONSE j l

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K/A: 004K2.01 l

Importance: 2.9 / 3.1

References:

0711205, " Chemical and Volume Control System" ST. LUCIE TRAINING DEPT. l job PERFORMANCE MEASURE PAGE 7

JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: Assuming initial RCS boron concentration was 650 ppm and had to be increased to 1060 ppm to meet shutdown margin requirements, how much would the boron added equalin terms of reactivity? (Assume Unit 1, hot standby,7000 EFPH)

Expected Response: (7000 EFPH Hot Standby boron worth is 9.14)

(410 PPM X 9.14 PPM /PCM = 3747.4 PCM) 3747.4 PCM (+0,-10)

CANDIDATES RESPONSE b

K/A: 004K5.06 Importance: 3.0 / 3.3 l

References:

St. Lucie Unit 1 Plant Physics Curves I

ST. LUCIE TRAINING DEPT, JOB PERFORMANCE MEASURE PAGE 8 l l

JPM QUESTION # 1

CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: How could this method of boration be accomplished if a loss of offsite power occurred with failure of the 1 A EDG prior to making the alignment?

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l ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE ,

4 JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO ,

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) i, l Question: Assuming initial RCS boron concentration was 650 ppm and had to be j increased to 1060 ppm to meet shutdown margin requirements, how much would the boron added equalin terms of reactivity? (Assume Unit 1, hot standby,7000 EFPH)

ST. LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE PAGE 10 j

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l CANDIDATE CUE SHEET l (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

I I

INITIAL CONDITIONS:

Unit 1 was tripped from 100% power (MOL) due to a problem with the Feedwater j Regulating System. Subsequent to the trip it was discovered that two CEAs had stuck ;

out and emergency boration was begun. The SNPO reported a pipe break in the l charging header between V2429 and the containment penetration. The emergency :

boration line-up was secured. With the loss of the Reactivity Control safety function, it )

was decided to enter 1-EOP-15.

INITIATING CUEl i

)

LAW Reactivity Control Success Path 2: Emergency Boration CVCS, the ANPS has requested that you emergency borate using Aux HPSI header per Appendix T of 1- )

EOP-99.

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ST. LUC'E TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 11 i

l

-. s..a:aa

-.4 ~ .a.,e -..as -as a

aaw s - -a- . - _aa-.a. +, s..-r-n-..xaa.s .-.-....as REGION ll INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT MANUALLY ACTUATE AFAS UNIT 1 CANDIDATE 4

E EXAMINER 4

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REGION 11 ,

INITIAL LICENSE EXAMINATION ;

ST LUCIE NUCLEAR PLANT- t Task: Start the AFW system Alternate Path: Yes X No ;

Facility JPM #: 0821075 / modified Task Standard: Successfully actuate AFAS and feed the 1 A steam generator i i

Preferred Evaluation Location:

Simulator Control Room X In-Plant Preferred Evaluation Method- I l

Perform Simulate X ll I

References:

1-EOP-4, "Stearn Generator Tube Rupture" Validation Time 10 minutes Time Critical No Candidats: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade I l

Examiner: _ Signature: __

Name ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE 4

PAGE 2

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Tools / Equipment / Procedures Needed: I None Read to Candidate l Directions to candidate for in-Plant or Control Room JPMs: t

ill explain the initial cenditions and state the task to be performed. All in-plant or control room JPM steps, including any communications, shall be simulated for this JPM.

Under no circumstances, unless directed by the examiner, are you to operate any plant :

equipment. I will provide initiating cues and reports on other actions when directed by !

you. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Qirm i tions to candidate for Simulator JPMs: ,

I will explain the initial conditions and state the task to be performed. All simulator JPM I steps, including any communications, shall be performed for this JPM. You are you to ;

operate any plant equipment that is necessary for the completion of this JPM. The i simulator will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you, Initial Conditions: A steam generator tube rupture has occurred in 1B steam s generator. The 1B steam generator has been isolated and the RCS is being cooled down and depressurized. AFW to the 1 A ,

steam generator has just isolated due to the DP between the steam .

generators.

Initiatina Cues: The ANPS has directed you to manually actuate AFAS-1 and :

restore 1 A steam generator to the normal band (60-70% NR) using i only the 1 A AFW pump.

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sT. LUclE TRAINING DEPT. .

JOB PERFORMANCE MEASURE l PAGE3

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Start Time 1 1

)

Stop1: Manually actuate AFAS-1 Critical Step Standard: Operator simulates opening each AFAS cabinet using key # 192 and Sat turns the AFAS-1 Actuation Switch to the "ACT" position on all four channels Unsat

.Q.yg; (Control room behind RTGB 101) -

All four AFAS-1 actuation switches positioned to "ACT" Comments:

]

)

i Step 2: Observe AFW valves MV-09-9 and MV-09-11 stroke full open and flow increases on F1-09-2A and F1-09-2C Sat Standard: Operator observes MV-09-9 (1 A AFW header isolation valve) and MV-09-11 (1C AFW to 1 A steam generator header isolation valve) Unsat stroke full open and flow indication on F1-09-2A and FI-09-2C :

Cue; (RTGB 103)

MV-09-9 indicates green light lliuminated, MV-0911 indicates red light illuminated, F1-09-2A Indicates low scale, and Fi-09-2C indicates full scale Comments:

Step 3: Open MV-09-9 Critical Step Standard: Operator simulates placing and holding control switch for MV-09-9 to Sat :

the OPEN position until 150 gpm of flow is observed l Unsat !

Cue: (RTGB 103)

MV-09-9 indicates red and green light illuminated, FI-09-2A indicates 150 gpm i Comments:

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l ST. LUCIE TRAINING DEPT. j JOB PERFORMANCE MEAsVRE i PAGE 4 l 1

r Step 4: Secure flow to the 1 A S/G from the 1C AFW pump Critical Step Standard: Operator simulates placing and holding control switch for MV-09-11 Sat to the CLOSED position until green light indication and no flow is observed Unsat Cue: (RTGB 103)

MV-09-11 indicates green light illuminated, F1-09-2C Indicates low scale Comments:

Step 5: Restc,re 1 A steam generator level to 60-70% NR using the 1 A AFW Critical Step pump Sat Standard: Operator observes level indications for 1 A steam generator Unsat !

Cue: (RTGB 103) 1 A steam generator level indicates 65% NR Comments:

END CF TASK Stop Time ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEAsVRE PAGE5

JPM QUESTION # 1 REFERENCE ALLOWED: X YES NO Question: Describe the response of the AFAS system upon the loss of the 1 A safety related DC bus. Include in your answer the effect of this transient on AFAS actuation logic.

Expected Response: The loss of the 1 A DC bus results in the "A" AFAS channel going to bypass (.35) and the "C" AFAS channel going to trip. (.35) This places the AFAS logic in a one out of two logic.(.3)

CANDIDATES RESPONSE K/A: 061 A?.02 importance: 3.1 / 3.4

References:

0711412, " Auxiliary Fet 1 water and AFAS" ST. LUCIE TRAINING DEPT.

?

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JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: Unit 1 has tripped from 100% power. The operators have throttled AFW so that flow from the 1C AFW pump is secured and each steam generator is being fed by its respective AFW pump at 150 gpm. Describe the response of the AFW system to a loss of offsite power with no operator action. (Assume all equipment operates properly)

Expected Response: After the EDGs load on their respective busses, all AFW header isolation valves will stroke to their full open position.

(15 second time delay) after the EDG breaker closes in (.5),

the respective AFW pump will start and feed the steam generator with full flow.(.5)

CANDIDATES RESPONSE r

i K/A: 061K4.02 Importance: 4.5 / 4.6

References:

0711412, " Auxiliary Feedwater and AFAS" ST. LUclE TRAINING DEPT.

[

0.

JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

I Question: Describe the response of the AFAS system upon the loss of the 1 A safety l related DC bus. Include in your answer the effect of this transient on ;

AFAS actuation logic. '

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i ST. LUCIE TRAINING DEPT.

JOB PERFORMANOE MEASURE PAGEB l

1 J

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JPM QUESTION # 2 CANDIDATE COPY 1 1

REFERENCE ALLOWED: .X l YES NO )

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Unit 1 has tripped from 100% power. The operators have throttled AFW so that flow from the 1C AFW pump is secured and each steam generator i is being fed by its respective AFW pump at 150 gpm. Describe the s

response of the AFW system to a loss of offsite power with no operator action. (Assume all equipment operates properly) ;

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ST. LUCIE TRAINING DEPT.

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l CANDIDATE CUE SHEET I

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A steam generator tube rupture has occurred in 1B steam generator. The 1B steam gerator has been isolated and the RCS is being cold down and depressurized. AFW to the 1 A steam generator has just isolated due to the DP between the steam generators.

I INITIATING CUE:

The ANPS has directed you to manually actuate AFAS-1 and restore 1 A steam i

generator to the normal band (60-70% NR) using only the 1 A AFW pump.

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sT. LUCIE TRAINING DEPT. ;

JOB PERFORMANCE MEASURE PAGE 10 u.. .-

y 't

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i REGION ll l

INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE i ST. LUCIE NUCLEAR PLANT PERFORM A CONTAINMENT PURGE UNIT 1 l

i 4

l CANDIDATE jY EXAMINER l

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REGION 11 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST LUCIE NUCLEAR PLANT Task: Start up the CPS Alternate Path: Yes X No Facility JPM #: New 1

Task Standard: Initiate a containment purge on Unit 1 Preferred Evaluation Location:

Simulator Control Room X In-Plant 4

Preferred Evaluation Method:

Perform Simuiat0 X

References:

Validation Time 15 minutes Time Critical No Candidate: Time Start Name Time Finish 1

Performance Rating: Sat Unsat Question Grade 1

Examiner: Signature:

Name

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l ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 2 J

Tools / Equipment / Procedures Needed:

OP 1-0530021," Controlled Gaseous Batch Release to Atmosphere" Read to Candidate pirections to candidr .e for In-Plant or Control Room JPMs:

I will explain the initir.1 conditions and state the task to be perfonned. All in-plant or control room JPf/s steps, including any communications, shall be simulated for this JPM.

Under no circumstances, unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Directions to candidate for Simulator JPMs:

I will explain the initial conditions and state the task to be performed. All simulator JPM steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The simulator will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Initial Conditions: Unit 1 is in Mode 5, entering a refueling outage. Preparations are being made to open containment to allow personnel access. An approved gaseous batch release permit has been issued and approved by the ANPS. !

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initiatina Cues: The ANPS has directed that you perform a containment purge l using HVE-8A LAW OP 1-0530021.

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ST. LUCIE TRAINING DEPT. j job PERFORMANCE MEASURE i PAGE 3 I

Start Time Step 1: Notify security of the intent to conduct a containment purge and the approximate length of time. (Step 8.2.1)

Sat Standard: Operator should simulate notifying security Unsat Cue: Security acknowledges Comments:

Step 2: Check the following valves to be closed: FCV-25-1, FCV-25-2,

, FCV-25-3, FCV-25-4, FCV-25-5, FCV-25-6 (step 8.2.2)

Sat s Standard: _ Operator verifies all purge valves are closed.

Unsat Cue: (RTGB 106)

FCV-25-1 through FCV-25-6 Indicate green lights illuminated Comments:

Step 3: Check to be closed containment vacuum relief valves FCV 25-7 and FCV-25-8 (step 8.2.3) ,

Sat Standard: Operator verifies containment vacuum relief valves closed Unsat Cue: (RTGB 106)

FCV 25-7 and FCV-25-8 indicate green lights illuminated Comments:-

Step 4; Check that the containment purge refueling damper is in the

" Purge" pos) tion (Step 8.2.4)

Sat Standard: Operator verifies that the containment purge refueling damper is in the " Purge" position Unsat Cue: (RTGB 106)

Containment purge refueling damper is in the " Refueling" position Comments:

sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEAsVRE PAGE4

.- - . = . - - . - - . _. _ . . _ .

Step 5: Have an approved Gaseous Release Permit (step 8.2.6) Critical Step Standard: Operator should ask if gas release permit is issued Sat Cue: Gas release permit # 1-98-45 has been approved and issued Unsat Comments: l Step 6: At the start of the release, record the date and time (step 8.2,7) i Standard: Operator should record current date and time in procedure Sat Cue: Date and time recorded Unsat l

Comments:

f Step 7: Ensure proper flow to plant vent sampler prior to start of purge by verifying T-SH26002 is closed and T-SH26001 is open (step 8.2.8)

Sat Standard: Operator simulates contacting SNPO to verify T SH26002 is closed ,

and T-SH26001 is open Unsat ;

Cue: SNPO reports T-SH26002 is closed and T-SH26001 is open Comments:

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I ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE s I

l Step 9; Start HVE-8A. Observe FCV-25-4, FCV 25-5 and FCV-25-6 open Critical Step before the fan starts. Observe PDIS-25-1 A and PDIS-25-1B. (Step 8.2.8A) Sat Standard: Operator simulates starting HVE-8A and observes PDIS-25-1 A and Unsat PDIS-25-1B on RTGB 106. ;

Cue: (RTGB 106)

FCV-25-4, FCV-25-5 and FCV-25 6 Indicate red lights illuminated, HVE-8A indicates red 81ght illuminated, PDIS-25-1 A and PDIS-25-1B indicate -1.2"H20.

Comments:

i Stoo 10: Verify FCV-25-1, FCV-25-2 and FCV-25-3 open after containment Critical Step to outside differential reaches . 5"H20. (Step 8.2.8B)

Sat Standard: Operator verifies FCV-25-1, FCV 25-2 and FCV-25-3 open Unsat Quej FCV 25-1, FCV-25-2 and FCV-25-3 Indicate green lights illuminated Comments:

Sten 11: If FCV-25-1, FCV-25-2 and FCV 25-3 do not open before Critical Step containment to olutside differential reaches -1.0"H20, stop purge fan and notify I&C. (Step 8.2.SB continued) Sat Standard: Operator simulates stopping HVE-8A with control s~witch on RTGB Unsat 106 Qp.ej HVE-8A indicates green light illuminated Comments:

Sten 12: Notify l&C Standard: Operator simulates calling l&C and notifying them Sat Cue: I&C acknowledges Unsat Comments:

End of Task ST. Lt>CIE TRAINING DEPT. ,

1 Stop Time JPM QUESTION # 1 REFERENCE ALLOWED: X YES NO Question:

, Unit 2 is in a refueling outage with the Containment Purge System in operation. An l&C spec inadvertently initiates an A train SIAS. What is the status of the Containment Purge System after this event occurs?

i Expected Response: Since SIAS also generates a CIAS, the running containment purge fan will stop and all purge valves will close.

CANDIDATES RESPONSE i

K/A: 029K4.03 Importance: 3.2 / 3.5

References:

0711602, " Containment Ventilation System",2-EOP-99 Table 2 ST. LUCIE TRAINING DEPT.

%, -=

i JPM QUESTION # 2 i REFERENCE ALLOWED: X YES NO l

Question: If the plant vent monitor became inoperable during this evolution, could I the containment purge continue? Explain why or why not. (Assume initiating cue plant conditions) l l

Expected Response: The release can continue (.5) because the plant vent monitor is not required to be operable in mode 5 (.5) J (St. Lucie Unit 1 Tech Spec table 3.3-6)

CANDIDATES RESPONSE i

K/A: 029G2.1.12 Importance: 2.9 / 4.0

References:

St. Lucie Unit 1 Tech Spec table 3.3-6 ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE8

JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Unit 2 is in a refueling outage with the Containment Purge System in operation. An l&C spec inadvertently initiates an A train SlAS. What is the status of the Containment Purge System after this event occurs?

ST. LUCIE TRAINING DEPT.

JPM QUESTION # 2 CANDIDATE COPY l REFERENCE ALLOWED: X i YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: If the plant vent monitor became inoperable during this evolution, could the containment purge continue? Explain why or why not. (Assume initiating cue plant conditions)

F ST. LUClE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 10

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CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS: ;

Unit 1 is in Mode 5, entering a refueling outage. Preparations are being made to open containment to allow personnel access. An approved gaseous batch release permit has been issued and approved by the ANPS.

i INITIATING CUE:

The ANPS has directed that you perform a containment purge using HVE-8A LAW OP 1-0530021.

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sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 11 i

. . _ . . .- . _ . . _ . . . - ... .. - _-. _= -

i REGION 11 INITIAL LICENSE EXAMINATION ,

JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT DISCONNECT INSTRUMENT INVERTER 1B FOR PREVENTATIVE MAINTENANCE UNIT 1 CANDIDATE EXAMINER i

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REGION 11 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

, ST LUCIE NUCLEAR PLANT Task: Transfer a vital (120V) instrument power supply Alternate Path: Yes No X Facility JPM #: 0821067 Task Standard: Remove the 1B instrument Inverter from service Preferred Evaluation Location:

Simulator Control Room In-Plant X Preferred Evaluation Method:

Perform Simulate X

References:

OP 1-0970020," Operation of the 120V instrument AC System" Validation Time 10 minutes Time Critical No Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat Question Grade Examiner: Signature:

Name l

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ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 2 J

Tools / Equipment / Procedures Needed:

OP 1-0970020," Operation of the 120V instrument AC System" Read to Candidate Directions to candidate for in-Plant or Control Room JPMs:

I will explain the initial conditions and state the task to be performed. All in-plant or +

control room JPM steps, including any communications, shall be simulated for this JPM.

Under no circumstances, unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by retuming the

- handout sheet I provided you.

Directions to candidate for Simulator JPMs:

I will explain the initial conditions and state the task to be performed. All simulator JPM steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The simulator will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by returning the handout sheet I provided you.

Initial Conditions: Unit 1 is at 100% power and stable with each instrument bus aligned to receive power from its respective inverter.

Initiatina Cues: The ANPS has directed you to take the 1B 120 volt instrument inverter out of service for preveniative maintenance IAW OP 1-0970020.

sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 3 J

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Start Time 1

Step 1: ' Close the bypass bus breaker on the bypass bus for ALTERNATE Critical Step 1 feed: Transfer switch 1 B, CKT #13 (step 8.2.1) l Sat i Standard; Operator simulates placing 1B CKT # 13 to the CLOSED position Unsat Cue: (B battery charger room,1B bypass bus cabinet) I Circuit 13 in the CLOSED position i

Comments: '

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Step 2: Verify power available light in transfer panel is energized. (step ,

8.2.2) i Sat E,andard:

t Check Inverter 18 to Bypass Bus 1B U1010-2 is illuminated ' Unsat Cue: (B battery charger room,1B transfer panel cabinet) ,

Light U1010 2 is liluminated Comments:

Step 3 Verify the synchronizing (SYNC) signal breaker, CKT #3 on the bypass bus is closed. (Step 8.2.3) :

Standard: Venfy IN SYNC light is illuminated prior to operation of transfer !

switch if IN SYNC light is not illuminated, close SYNC signal Unsat breaker, CKT #3 Cue: (B battery charger room,1B bypass bus cabinet)

SYNC breaker, CKT #3 closed, IN SYNC light illuminated Comments:

ST. LUCIE TRAINING DEPT.

Step 4: Place the transfer switch in the maintenance bypass bus critical Step position (step 8.2.4)

Sat Standard: Operator simulates positioning transfer switch to MAINTENANCE BYPASS BUS 1B Unsat Cue: (B battery charger room,1B transfer panel cabinet)

Transfer switch in the Maintenance Bypass Bus 1B position Comments:

Step 5: Notify control room the 1 B lnstrument bus is now being powered from the Maintenance Bypass Bus (step 8.2.5)

Sat Standard: Operator simulates notifying the control room Unsat Cue: Control room acknowledges Comments:

Step 6: Open the Inverter supply breakers on the front of the 1B inverter in the following order: CB-6, CB-4, CB-2, CB-1 (step 8.2.6)

Sat Standard: Operator simulates opening CB-6, CB-4, CB-2, CB-1 Unsat Cue: (B battery charger room,1B inverter)

CB-6, CB-4, CB-2, CB-1 Indicate open Comments:

Step 7: Open 1-60224,1B inverter supply breaker (step 8.2.7)

Standard: Operator simulates opening 1-60224,1B inverter supply breaker Sat Cue: (B battery charger room,1B 125 VDC bus) Unsat 1-60224 Indicates open Comments:

sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 5 s

Step 8: Open CKT #3 on the 1B Maintenance Bypass bus, sync signal breaker (step 8.2.8)

Sat Standard: Operator simulates opening maintenanca bypass bus circuit #3 Unsat Cue: . (B battery charger room,18 Maintenance bypass bus)

Circuit #3 indicates open Comments:

Step _9; Notify the control room the 1 B Instrument Inverter is out of service (step 8.2.9)

Sat _

Standard: Operator simulates contacting coritrol room had notifies them that 1B instrument inverter is out of se / ice Unsat Cpug; Control room acknowledges Comments:

i END OF TASK Stop Time l

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 6 I

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- . = . . . . ._- - - - .

t JPM QUESTION # 1 REFERENCE ALLOWED: X YES NO Question: A. ' What is the purpose of the mechanicalinterlock located on the ,

instrument bus breakers in the Maintenance Bypass bus?

B. What would be the plant response of the loss of 1B Instrument Bus while at power?

Expected Response: A. The mechanical interlock ensures that only one instrument bus is being powered by the Maintenance Bypass bus at any one time. (.5)

B. One channel of RPS would be de-energized (.2), 4 TCBs would open (.2) and the reactor would not trip

(.1)

CANDIDATES RESPONSE i

K/A: 062K4.03, 062K3.01 ,

t

'Anportance: 2.8 / 3.1, 3.5 / 3.9

References:

0711503, "..120V inshument AC System" l

ST. LUCIE TRAINING DEPT.

JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: Describe the Unit differences in the 120V instrument AC System concerning attemate power sources.

Expected Response: Unit 2 has a separate bypass bus for each inverter for a total of four. (.5) Unit 1 has two bypass busses, (one feeds MA or MC Instrument bus and the other feeds MB or MD instrument bus). (.5)

CANDIDATES RESPONSE l

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K/A: 062K2.01 Importance: 3.3 / 3.4 i

References:

0711503,"..120V Instrument AC System" sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 8 l

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JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) l l

Question: A. What is the purpose of the mechanicalinterlock located on the instrument bus breakers in the Maintenance Bypass bus?

B. What would be the plant response of the loss of 1B Instrument Bus I while at power?

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ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE l PAGE 9 l i

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JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) i l

Question: Describe the Unit differences in the 120V Instrument AC System conceming alternate power sources.

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JOB PERFORMANCE MEASURE l PAGE 10 j I

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I CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK) l lNITIAL CONDITIONS: l Unit 1 is at 100% power and stable with each instrument bus aligned to receive power from its respective inveder.

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INITIATING CUE- l The ANPS has directed you to take tbs 1B 120 volt instrument inverter out of service for i preventative maintenance IAW OP 1-0970020. l 1

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JOB PERFORMANCE MEASURE PAGE 11 I

\

s REGION 11 INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT OPEN CCW RETURN VALVE TO THE RCPS WITH FAILED SOLENOID VALVE - UNIT 1 CANDIDATE EXAMINER l

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- - .- .-. = - . . - - . .. -- - - .-

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REGION 11 i INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE l ST LUCIE NUCLEAR PLANT Task: Perform lineups of the CCWS ]

Alternate Path: Yes X No Facility JPM #: New j Task Standard: Successfully reestablish CCW to the RCPs i

l Preferred Evaluation Location:

Simulator Control Room In-Plant X Preferred Evaluation Method:

Perform Simulate X

References:

ONP 1-0120034," Reactor Coolant Pump", Appendix A i Validation Time 10 minutes Time Critical No Candidate: Time Start Name Time Finish l

Performance Rating: Sat Unsat Question Grade Examiner: Signature:

Name ST. LUCIE TRAINING DEPT.

f Tools / Equipment / Procedures Needed:

ONP 1-0120034," Reactor Coolant Pump", Appendix A ,

Read to Candidate Directions to candidate for in-Plant or Control Room JPMs: ,

I will explain the initial conditions and state the task to be performed. All in-plant or control room JPM steps, including any communications, shall be simulated for this JPM. -

Under no circumstances, unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you finish your assigned task by returning the handout sheet I provided you.

Directions to candidate for Simulator JPMs:

I will explain the initial conditions and state the task to be performed. All simulator JPM steps, including any communications, shall be performed for this JPM. You are you to operate any plant equipment that is necessary for the completion of this JPM. The simulator will provide the cues as you perform this JPM. Ensure you indicate tom' e when you finish your assigned task by retuming the handout sheet I provided you.

Initial Conditions: Unit 1 is at 100% power. Annunciators J-9, J-12, J-27, and J-30, "RCP Low Cooling Water Flow" have alarmed. Initial indications are -

that the air supply solenoid valve to HCV-14-2, CCW retum valve has failed. The ANPS has directed that actions be taken to restore ;

CCW to the RCPs. Instrument air is availablo at this time. !

Initiatina Cues: The ANPS has directed that actions be taken to restore CCW to the RCPs LAW ONOP 1-0120034 i

l ST. LUclE TRAINING DEPT. 4 job PERFORMANCE MEASURE l PAGE 3 i

Start Time Ejen 1: Enter the RCA, review RWP, obtain Merlin Gerlin monitor, consult survey map, inform H.P. of intentions and request further radiological protection requirements. Sat Standard: Operator remains in compliance with H.P. precautions and Unsat recommendations. '

,Qugl (This is not a rapid entry into the RAB)

All HP requirements have been met Comments:

Step 2: Close the solenoid vent ball valve (step 2A of Appendix A) Critical Step Standard: Operator simulates closing the solenoid vent ball valve located on Sat the air supply solenoid on HCV-14-2 Unsat Cue: (Pipe pen room,6'in the overhead) l Solenoid vent ball valve handle horizontal ,

Comments: l 1

Step 3: Attach the HCV solenoid vent line male flex hose to the female quick Critical Step disconnect fitting downstream of the air sup'ply regulator (step 2B of Appendix A) Sat

^

Standard: Operator simulates connecting the HCV solenoid vent line mile Unsat flex hose to the female quick disconnect fitting downstream of the air supply regulator on HCV-14-2 ,

Cue: (Pipe pen room,6'in the overhead) !

Hose connected from solenoid to air supply J

Comments-l Step 4: Verify HCV 14-2 opens (step 2C of Appendix A)

Standard: Operator observes HCV-14-2 to open Sat Cue: (Pipe pen room,6'in the overhead) Unsat HCV 14 2 does not open, control room reports instrument air to the RAB has been lost (Altemate Path begins)

Comments:

l sT. LUClE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 4 1 i

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l Step 5: Close instrument air supply to HCV-14-2 (step 3A) Critical Step Standard: Operator simulates closing the instrument air supply to HCV-14-2 Sat Cue: (Pipe pen room,6'in the overhead) Unsat Air supply to HCV-14-2 rotated until hard stop is reached Comments-1 Step 6: Close the solenoid vent ball valve (step 3B) Critical Step i

Standard: Operator sirnulates closing the solenoid vent ball valve located on Sat j the air supply solenoid on HCV-14-2 Unsat Gej (Pipe pen room,6'in the overhead)

Solenoid vent ball valve handle horizontal i Comments: I i

Step 7; Remove the solenoid supply hose from the instrument air supply, Critical Step j attach the male hose fitting on HCV-14-2 solenoid vent line to the l female flex hose fitting on the nitrogen supply line (step 3C) Sat ;

Standard: Operator simulates removing the solenoid supply line from the U .I ,

instrument air fitting and reattaching it to the nitrogen supply line l fitting Cue: (Pipe pen room,6'in the overhead)

Hose connected from solenoid to nitrogen supply Comments:

Step 8: Verify HCV-14-2 opens (step 3D) i Standard: Operator observes HCV-14-2 to open Sat hej (Pipe pen room,6'in the overhead) Unsat );

HCV-14-2. stem rises to upper stop Comments:

sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 5

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Step 9; ; Notify control room HCV-14-2 is open [

i Standard: Operator simulates calling control room and notifying them HCV 14- Sat 2 is open

'i Unsat h Control room acknowledges Comments: ;

End of Task l Stop Time !

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JOB PERFORMANCE MEASURE i PAGE 6 l i

JPM QUESTION # 1 REFERENCE ALLOWED: X YES NO Question: If an RCS leak occurred in the RCP seal cooler, what indications / automatic actions would the operator see in the control room .

and how would he verify that it was an actual leak?

ExDected ResDonse: The seal cooler CCW outlet valve would go closed upon high outlet temperature. (.5) The operator would then reset the seal cooler outlet valve and place the control switch back to auto. If the valve recloses after a time delay (1 minute),

an actual leak has occurred. (.25) The operator would also check for increasing CCW activity. (.25)

CANDIDATES RESPONSE K/A: 008K1.02 Importance: 3.3 / 3.4 i

References:

0711209, " Component Cooling Water" ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE l PAGE 7 i

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JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: If an SIAS were to occur on Unit 1, which four CCW containment loads would be effected due to the SIAS? (assume no operator action)

Ennected Response: RCPs, CEDM Coolers, Containment Instrument Air Compressors, Quench tank cooling blanket (.25 each) :

CANDIDATES RESPONSE r

K/A: 008A3.08 Importance: 3.6 / 3.7

References:

P&lD 8770-G-083 sheets 1 A and 1B sT.LUClf TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 8

,M

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JPM QUESTION # 1

]

CANDIDATE COPY ;

REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) i Question: If an RCS leak occurred in the RCP seal cooler, what !

indications / automatic actions would the operator see in the control room and how would he verify that it was an actual leak? l l

ST. LUCIE TRAINING DEPT, i JOB PERFORMANCE MEASURE PAGE 9 .

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i JPM QUESTION # 2 l 1

CANDIDATE COPY l l

REFERENCE ALLOWED: X YES NO i (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: If a SIAS were to occur on Unit 1, which four CCW containment loads would be inoperable due to the SIAS? (assume no operator action) l l

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job PERFORMANCE MEASURE PAGE 10

CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK) i r

INITIAL CONDITIONS:

i Unit 1 is at 100% power. Annunciators J-9, J-12, J-27, and J-30, "RCP Low Cooling l Water Flow" have alarmed. Initial indications are that the air supply solenoid valve to :

HCV-14-2, CCW return valve has failed. The ANPS has directed that actions be taken !

to restore CCW to the RCPs. Instrument air is available at this time.

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INITIATING CUE:

The ANPS has directed that actions be taken to restore CCW to the RCPs IAW ONOP i

1-0120034 l

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ST. LUCIE TRAINING DEPT. i JOB PERFORMANCE MEASURE l PAGE 11 1

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.4*aae,.p-A...SJ._..a.- -->%,--e.,L ..e.d.m.ee..-_A., 4 en ...J -#4s A44 A REGION ll lNITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT OPERATE THE HYDROGEN PURGE SYSTEM UNIT 1 CANDIDATE EXAMINER l

REGION ll I INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ST LUCIE NUCLEAR PLANT Task: Perform lineups on the HPRS Alternate Path: None i

Facility JPM #: 0821098 Task Standard: HVE 78 is placed in service j

Preferred Evaluation Location: l Simulator Control Room In-Plant X

]

Preferred Evaluation Method: 1 l

Perform Simulate X l

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References:

1-EOP-99, Appendix N, " Hydrogen Purge System Operation" Validation Time 30 minutes Time Critical No Candidate: Time Start !

Name Time Finish Performance Rating: Sat Unsat Ouestion Grade Examiner: Signature:

Name i ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 2 4

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Tools / Equipment / Procedures Needed: i 1-EOP-99, Appendix N !

- Step Ladder :

Road to Candidate !

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- Directions to candidate for In-Plant or Control Room JPMs:

I will explain the initial conditions and state the task to be performed. All in-plant or ,

control room JPM steps, including any communications, shall be simulated for this JPM !

l Under no circumstances, unless directed by the examiner, are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by ;

you. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you.

Directions to candidate for Simulator JPMs:

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I will explain'the initial conditions and state the task to be performed. All simulator JPM i steps, including any communications, shall be performed for this JPM. You are to '

operate any plant equipment that is necessary for the completion of this JPM. The simulator _will provide the cues as you perform this JPM. Ensure you indicate to me when you finish your assigned task by retuming the handout sheet I provided you, !

Initial Conditions:- !

A large break LOCA has occurred on Unit 1. SIAS has been reset and HVE-10B is l runningJ The TSC and Chemistry has given permission to vent the containment. j initiatina Cueen l I

You have been directed by the ANPS to locally operate the Hydrogen Purge System ,

using 1-EOP-99, Appendix N. Establish a 100 CFM flowrate using HVE 78.

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ST. LUCIE TRAtNING DEPT. '

' job PERFORMANCE MEASURE PAGE 3 ;

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1 Start Time Step 1 Verify locked closed V-25015 and V-25-16. " Pen 58 to HVE 7A/7B Gate I Filter Bypass"(step B)

Sat

_ Standard: Operator checks valve position and ensures lock is present.

Unsat p_ygt; (penetration 58 between filter train and containment)

V-25015 and V-25-16 are fully clockwise and locked Comments:

Step 2: Unlock and open V-25013 and V-25-14,"" Pen 57 to HVE Critical Step J 7N78 Gate suction"(step C) ,

Sat Standard: Operator simulates unlocking and opening V-25013 and V-25-14 l Unsat :

Cue: (penetration 57 between filter train and containment)

V-25013 and V-25-14 are unlocked and rotated until they come to a hard stop.

Commerits:

SteD 3: Partially open FCV-25-9," Pen 57 to HVE 7N78 intake"(step Critical Step D)

Sat Standard: Operator simulates partially opening FCV-25-9.

Unsat ___,

Cue: (Above HVE 6A filter train, north end, control panel on column)

FCV 25-9 partially counterclockwise Comments:

ST. LUCIE TRAINING DEPT.

31g,3; Open V-25-17, "HVE 7A/78 disch gate to vent stack" (step E) Critical Step Standard: Operator simulates opening FCV-25-17. Sat l

Cue: (15-20 ft in the overhead on fan end of HVE 6B filter train) Unsat V-25-17 rotated until it comes to a hard stop Comments: i Step 5; Verify closed V-25-18,"HVE 7A/&B disch gate to vent stack" (step F)

Sat Standerd; Operator checks valvo position to be closed Unsat Cue: (next to V-25-17 in the overhead)

V-2518 is fully clockwise Comments:

Step 6: Unlock and Open V25011 and V-25-12. " Makeup air before Critical Step Pen 56 gate"(step G)

Sat Standard: Operator simulates unlocking and opening V25011 and V-25-12 Unsat Cue: (Purge valve room,19.5' elevation, between RAB and FHB)

V25011 and V-25-18 unlocked and rotated until hard stop is reached J i

Comments:

Sten 7: Partially open FCV 25-10,"HVS-4 plenum to HVE-7 Intake" Critical Step (step H)

Sat Standard: Operator simulates partially opening FCV-25-10 Unsat Cue: (Control panel on column near north end of the filter)

FCV-25-10 is partially counterclockwise Comments:

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE5

l Steo 8: Start Hydrogen Purge fans HVE-7A or HVE-7B (step l} Critical Step Standard: Operator simulates starting HVE-7B by placing the control switch to Sat

" Start" Unsat Cue: (control panel on column next to fans)

Red light for HVE-7B is illuminated Comments:

Steo 9: Adjust FCV-25-9 for the desired purge rate on FR-25-1, ' Local Critical Step Flow Recorder". (Step J)

Sat 1 Standard: Operator simulates adjusting FCV 25-9 to obtain 100 CFM on FR 1 Unsat Cue: (Above north filter end)

Flowrate is 100 CFM, control room requests temperature to be maintained < 190'F Comments:

Step 10: Adjust FCV-25-10 to maintain charcoal absorber temperature below Critical Step alarm setpoint on TR-25-2 (RTGB 106) (step K)

Sat Standard: Operator adjusts FCV-25-10 to maintain temperature < 190 F Unsat Cue: Control Room reports temperature is 160*F ,

Comments:

Sten 11: Periodically check vent stack radiation monitor. (Step L)

Sat Standard: Operator requesis control room to monitor plant vent radiation monitor Unsat Cue: Radiation levels higher than normal, not exceeding limits Comments:

i END OF TASK Stop Time ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 6 1

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l JPM QUESTION # 1 ;

REFERENCE ALLOWED: X YES NO i i

Question: Describe the difference between the Unit 1 Hydrogen Purge System and the Unit 2 Hydrogen Purge System filter trains and the reason for the difference.

Expected Response: Unit 2 Hydrogen Purge System utilizes the Shield Building Ventilation System filter train when purging hydrogen from containment. (.25) This is because the Unit 2 Hydrogen Purge System filter train is not rated for accident cond tions. (.25)

Unit 1 Hydrogen purge system uses it's own filter train when .

purging hydrogen from containment because it is rated for accident conditions. (.5) ;

i CANDIDATES RESPONSE i

K/A: 028K1.01 Importance: 2.5 / 2.5 j

References:

0711602, " Containment Ventilation Systems" ,

sT. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 7 l

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i JPM QUESTION # 2 REFERENCE ALLOWED: X YES NO Question: State the three sources of hydrogen production during a large break LOCA in the order in which they are produced. (Greatest to least)

Expected ResDonsm Zirc-water reaction, corrosion of metals, radiolytic decomposition of water CANDIDATES RESPONSE l

l K/A: 028K5.03 l 1

Importance: 2.9 / 3.6 l

References:

0711602, " Containment Ventilation System" ST. LUCIE TRAINING DEPT.

JOD PERFORMANCE MEASURE PAGE 8 i

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JPM QUESTION # 1 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: Describe the difference between the Unit 1 Hydrogen Purge System and the Unit 2 Hydrogen Purge System filter trains and the reason for the difference.

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ST. LUCIE TRAINING DEPT.

JPM QUESTION # 2 CANDIDATE COPY REFERENCE ALLOWED: X YES NO (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Question: State the three sources of hydrogen production during a large break LOCA in the order in which they are produced. (Greatest to least) b ST. LUCtE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 10 a

CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK) l INITIAL CONDITIONS:

l A large break LOCA has occurred on Unit 1. SIAS has been reset and HVE-10B is running. The TSC and Chemistry has given permission to vent the containment. ;

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INITIATING CUE: I l

You have been directed by the ANPS to locally operate the Hydrogen Purge System using 1-EOP-99, Appendix N. Establish a 100 CFM flowrate using HVE 7B.

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ST. LUCIE TRAINING DEPT. l job PERFORMANCE MEASURE i' PAGE 11 i

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_. m . ._m_ ._ ..~ . _ _ _ . . . _ _ _ _ _ . _ . . . - _ - _ . _ . . _ , _ _ . _ _ _ . _ _ . _

-s

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s l ES-401 PWR RO Examination Outline Form ES-401-4 l

l Facility: St. Lucie Date of Exam: 11slN98 Exam Level: RO

, vc.

K/A Category Points Tier Group Point K K K .K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 1, 1 2 4 3 s $ \ 3 2 al G 2 16 :

Emergency &

2 3 2- 3 -

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1 3 en Tier Totals 5 7 7 7 5 S 36 l

l '1 3 2 2 2 2 2 2 2 2 2 2 23 2' 2 2 2 2 2 2 1 2 2 2 2 1 20 Plant 3 1 1 1 1 1 1 1 1 8 Systems Tier Tota!s 6 4 5 5 4 3 5 5 5 5 4 51 3, Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 3 3 3 13 Note: -

Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.

Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

Systems / evolutions within each group are identified on the associateci outline.

- The shaded areas are not applicable to the category / tier.

I NUREG-1021 30 of " Interim Rev. 8, January 1997 l

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ES-401 PWR RO Exannation outilne Form ES-401-4 -i Emergency and Abnormal Plant Evoluhons - Tier 1/ Group 1 ,

E/ APE # 1Name 1 Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) Imp. Points .j 000005' inoperable / Stuck Control Rod / I 000015/17 RCP Malfunctions 1IV X X AK2.10 / RCP insiummtation malfunction 2.8 1 AA1.06 # RCP tripping strategy 3.1 1 ,

BWE09; CE/A13, WE09&E10 Natural Cire.1IV X AK1.2 i Cooldown rate w/SG isolated 3.2 1 000024 Emergency Boration /I X X AK2.011 Loss of power, method of Emergency Boration 2.7 1' !

4.0 1 i G2 4 .491 Method of rapid dcwnpower 000026 Loss of Component Cooling Water / Vill X AA1.02 Ilint difference of CCW cooled cGJ,~,eds 3.2 1' .

i 000027 Pressurizer Pressure Control System X AK2.03 i Effect on solid operation with letdown failure 2.6 - 1 i Malfunction i til

(

000040 Rupture(BWE05; CEE05;ransfer)/

. Excessive Heat TVWE12 Steam Line X AK1.05 I reactivity effects of steam line break 4.1 1 j

CE/A11; W/E08 RCS t.Nercooling - PTS / IV X K3.011 Actions to prevent PTS 32 1'

_000051 Loss of Condenser Vacuum IIV X AA2.02 / loss of vacuum requenng a reactor trip

.[

000055 Station Blackout / VI X EK3 02 / method of ca'culating SDM in SBO 4.3 1 r

000057 Loss of Vital AC Elec. Inst Bus / VI X AK3 01 / actions if fire and secur#y sups is lost 4.1 1

.[

000062 Loss of Nuclear Servic* 'fater / IV ,

000067 Plant Fire On-sNeIIX X' G2.4 27 / use of protected traa equipment during fire 30 1 l 0000G8 (BW/A06) Control Room Evac. IVift X AK2 011 ava#atility of equipment at HSDCP during fire 39 1 000069 (W/E14) Loss of CTMT Integrity i V

i 000074 (W/E06&E07) Inad Core Cooling IIV X EA1.06 7 instrumentation accuracy with RCPs runnmg 36 1 !

BW/E03 Inadequate Subcooling Margin / IV ,

000076 High Reactor Coolant ActivityiIX X AA2 021 reason for shutdown and tavg reduction 2.8 1

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BW/A02&A03 Loss of NNi-X/Y / Vit f f

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I K/A Cateoory Totat 2 4 3 3 2 2 Group Point Total: 16 i f

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ES-401 PWR RO Eramination Outline Form ES-401-4 Emercency and Abnormal Plant Evolutions - Tier 1/ Group 2 1

E/ APE # / flame / Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) Imp. Poines 000001' Continuous Rod WMhdrawal / I X AK103 / Efrects of continuous rod withdrawal on Rx power 3.9 1 000003 Dropped Control Red / I X AK2 05 / power supply failure effect on CEA 2.5 1 000007 {BWE02aE10; CE/E02) Reactor Trip - X X EK3.01/ Anafysis of RCS HR safety function 4.0 1 Stabd:ra ton - Recovery / I EA1.04 / seat enrecteon requirements in EOP-1 3.6 1 000008 Pressurizer Vaper Space AccidentItil X AA2 20 / temperature r>f talipipe prior to rupture disc blowout 34 1 000009 Small Break LOCA / lil X EK102 / characteristics of steam exiting the leak 3.5 1 000011 Large Break LOCA / tit X EK312 / flowpath for safeguard sump afignment 44 1 WE04 LOCA Outside Containment / til BWE08. W/E03 LOCA Cooldown/ Depress. / IV W/E11 Loss of Emergency Coolant Recire. / IV W/E02 Si Termiaation I fit 000022 loss of Reactor Coolant Makeup / ff X AA101/ response of CVCS to leak with insufficient makeup 3.4 1 000025 Loss of RHR System / IV X AK2 01/ response of SDC to loss or instrument air 29 1 000029 Anheipated Transient w/o scram / I X EA1.12 / DSS Muation with instrument failure 000032 Loss of Source Ranoe NT / VII X G2.1.12 / Actx... statement dunng refueling 2.9 1 000037 Steam Generator Tube Leak / !!! X AK3 07 / indications of SGTL and reactor trip 42 1 000038 Steam Generator Tube Ruphire / ll1 X EA2 01 / paramders considered when isolating SIG 41 1 000054 (CE/E06) Loss of Main Feedwater / IV X G2 4 07 / Use of condensate pump in TLOF 3.1 1 BW/E04 W/EOS Inadequate Heat Transfer - Loss of Seconda Heat Sink / tv .

000058 Loss of DC Power / VI X AA2 03 / effect of DC power loss on AFW system 3.5 1 000059 Accidentalliquid RadWaste Ref. / IX 000060 Accidental Gaseous Radwaste Ret / IX 000061 ARM System Alarms / Vil X AA101/ Auto start of SBVS on high fuel pool rad 3.6 1 W/E16 High Containment Radiation / IX CE/E09 Functonal Recovery X E K1.2 / Actions after once through cooling is accomplished 32 1 K/A Category Point Totats- 3 2 3 4 3 2 Group Point Total: 17

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ES-401 PWR RO Exammatam outree Plant Systems . Tier 2/ Group 1 Form ES-401-4 System # I Name K1 K2 K3 K4 K5 K6 At A2 A3 A4 G K/A Topic (s) Imp Point?

001 C$ trol Rod Drive X' X K1.03ICEDM to withdraw signal 3.4 1 A2.021 ctosureMwith tie breaker open 38 1 003 Reacter Coolant Pump X X X K2.01/ loss of DC bus affect on RCPs 3.1 1 K6.14 / startmg permksive for RCP 2.6 1 K4.03 Iog hft pump status on LOOP /SIAS 2.5 1 004 Chemical and Volume Control X X X K3.05IChargog pump faGure 3.8 1 A1,111 Auto actons for Letdown leak 30 1 t A4 01 I reactrvity effects of controller fa#ure 38 1 _,

013 Engineered Safety Features Actuation X X K1.05 I failed channet and CSAS actuation 4.1 1' K5.021SIAS block logic 2.9 1 l

015 Nuclear Instrumentation X X K4.07 / operation of the nuclear startup channel 3.2 1 fr A1.03 toperaton of the Enear controlcha --& 3.7 1 017 in-core Temperature Monitor X K1.01/ Unit 2 incore system description 3.2 1 022 Containment Coolmg X X K2.01/ power supply f ailure affecting coolers 3.0 1 ;

A4 01 Iresponse of CCS to LOOP 3.6 1 t 025 fee Condenser 056 Condensate X G2 4.48 / condensate needed for cooldown 3.5 1 !

i

. 059 Main Feedwater X X K3 03 Iloss of instrument air to FRVs 35 1 f A2.04 Iacton after feed is restored post dryout 2.9 1 t

\

061 Audary/EmergencyFeedwater X X A3.04 / response of afas with failed channels 32 1 !

G2 4 48 / use of the AB bypass switch 3.5 1 j

068 liquid Radwaste X F K6.101 Actions if rad monMor is lost 25 1 ;

071 Waste Gas Disposat X K5 04 I hydrogen I owygm limitations in WGS 25 1 t 072 Area Radation Monitoring X '

A3 01/ auto actions of ARMS channels 2.9 1 r

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t K/A Category Point Totats: 3 2 2 2 2 2 2 2 l? 2 2 Group Point Total: 23

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t ES-401 PWR RO Examination Outline Form ES-4014 Plant Systems - Tser 2/ Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic (s) Imp. Points 002 Reactor Coolant X X A1.05 / RCS tow flow trip inputs 34 1 A3 01/ RCS leak detection method 3.7 1 006 Emercency Core Cooling X K2 01/ Loading of HPSI amer power loss 36 1 010 Pressurizer Pressure Control X A3 02Isystem response eten drawmg a 36 1 bubble Oil Pressuriter level Controi X K2 02 / Avaliability of heaters on bus loss 31 1 012 Reactor Protection X K5 01/ ASGT trip parameters 33 1 .

014 Rod Posdion Indication X A2 07 / failure of reed switches 26 1 016 Non-nuctear instrumentation 026 Contamment 5 pray X G2 212 / Differences in CSS sury. fU-1, U-2) 30 1 029 Containtnent Purge X K3 02 / Loss of purge effect on entry to cont. 2.9 1 033 Spent Fuel PorA Cooling X K4 03 / Fuel Pool minimum level with leak 26 035 Steam Generator X KS 01/ Affect of SGBD actustment 34 1 039 Main and Reheat Steam X X K1.02 / Operation of ADVs with LOOP 3.3 1 A4 01 I sequence of opening reheat valves 2.9 1 055 Condenser Air Removat 062 AC Electreat Distributen X K3 02 / undervotaf age response by EDG 41 1 063 DC Electrcal Distr.bution X K4 02 / non-vitat to vital alignment 2.7 1 064 Emergency D+sel Generator X X K6 08 / storage / day tank capacity 32 1 A4 01/ EDG response to LOOP durino test 40 1 073 Process Radiaton Monitoring X K1.01/ toss of CCW rad monitor 36 1 075 Circulating Water X A2 02 / CWP trips 2.5 1 079 Station Ar 086 Fire Protection X A1.05 / Unit 2 FPS water source 2.9 1 K/A Category Point Totals: 2 2 2 2 2 1 2 2 2 2 1 Group Point Total: 20 u_... _ _ _ . _ _ . . _ _ . _ _ . _ _ _ ._ _ _ _ . _ _ _ . . _ _ . _ _ _ _ . . . _ _ _ . . _ _ . _ . . . _ _ _ _ _ . . . _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _

ES-401 PWR RO Examination Outfine Form ES-401-4 Plant Systems - Tier 2tGrou) 3 System s t Name K1 K2 K3 K4 K5 K6 At A2 A A G K/A Topic (s) Imp. Points 3 4 005 Residual Heat Removal X G2.1.28 / SDC requirements at mid loop 3.2 1 007 Pressurizer Retief/Ouench Tank 008 Component Cooling Water X A2.051 System response to leak with surge 2.9 1 tank auto features OOS __

027 Containment todine Removal X K1.01/ Flowpath with valve OOS 34 028 Hydrogen Rnv 1M and Purge Control X A101/ Ac' ions for H2 levels (%) 34 1 034 Fuel Handtog Equipment 041 Steam Dump / Turbine Bypass Controt 045 Man Turbine denerator X A3 05 / Latching turbine 26 1 076 Service Water X K4 02 / interfocks for auto start 29 1 078 instrument Air X K3 01/ loss of I/A to containment 3.1 1 103 Containment X A4 01/ vacuum relief valve failure criteria 32 1 K/A Category Point Totats- 1 ! 1 1 1 1 1 1 1 Group Point Total: 8

_ _ _ _ . _ _ _ , , . ___ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ - . _ _ _______-.,m___-_-m.-._-__________.______.._-_______.-._---._m. _ _ . _ _ _ _ . _ _ m_.__-s-____m__ ____ m-_ _ _ ______.m ._______m

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ES41 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: St. Lucie Date of Exam' 6-22-98 Exam level: RO Category K/A # Topic Imp Points 2.1.12 Actions for pcmer excursion 2.9 1 2.1.18 Log entries during event 29 1 Conduct of

- 2.1.7 Manual ESFAS initiation 37 1 2.1.2 Qualifcations for assuming the shift 30 1 2.1.

21.

Total 2 2.11 Temporary changes expiration 2.5 1 2.2.13 Clearance requirements 36 1 hA[o7'*' 2.2 26 Time to be suberitical prior to refueling 25 1 2.2.

2.2.

Total 23.1 Entry into a very high radiation area 26 1 23.1 Calculation of TEDE 26 1 Radiation Control 2.32 When is a TEDE ALARA review required 25 1 23 23 l l

2.3. I Total 2443 Method of communication during a hurncane 2.8 1 Emer 2429 Route of evacuation considering wind direction 26 1 k[*gency 2431 Annunciator response 3.3 1 24 24 24 Total 13 l

Ter 1 Target Point Total (RO/Si O) 13/17 l I

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l ES401 PWR SRO Examination Outline Form ES-401-3 Facility: St. Lucie Date of Exam:11-30 98 Exam Level: SRO K/A Category Points Tier Group Point K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TM

1. 1 3 4 5 I k 4 4 kkhb 4 24 Emergen@

2 2 2 3 I 3 3 bbl 3 16 '

Evo i 3 1 1 i b i 3 Tier Totals 5 7 9 b h bkkh 7 7 hbbb' bhh 8 43 1 2 2 2 2 2 1 2 1 1 2 2 19 2 2 2 1 1 2 1 2 1 1 2 2 17 Plant

. Systems 3 1 1 1 _1 4 Tier Totals 5 4 3 3 4 2 4 3 3 4 5 40

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 j 5 4 4 4 I

Note:

Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within I each tier.

Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities. j Systems / evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the category / lier.

NUREG-1021 23 of 39 Interim Rev. 8, January 1997 l

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3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Ter 1/ Group 1 E/ APE # / Name 1 Safety Functirm K1 K2 K3 A1 A2 G K/A Topic (s) imp. Points 000001 Continuous Rod Withdrawal / I X AK103 / CRW effect on reactor power 38 1 000003 Dropped Control Rod / i X AK2 05 / power supph failure effect on CEA 28 1 0000051noperable/ Stuck Cor*cf Re 1 X AA2 03 / actions for two mechanically bound CEAs 44 1 000011 Large Break I OCA

X EK312 / fbwpath for safeguard sump alignment 46 1 000015/17 RCP Malfunc - s / IV X X AA1.06 / RCP tripping strategy 2.9 1 I

AK2.10 / RCP instrumentation malfunction 2.8 1 BW/E09; CE/A13; W/E L&E10 Na'. ural Cire / IV X AK12 / Co)ldown rate w/SG isolated 35 1 000024 Emergency Def-. m/1 X X AK7.01 i Loss of method of Emergency Boration 2.7 1 G2 4 .49 i Met of re downpower 40 1 000026 Loss of Co'mponent Cooting Water i VIII X G2 4 21/ Safety functions effected by loss of CCW 43 1 000029 Anticipated Transent w/o Scram / I X EA1.12 i DSS actuation with instrument failure 3.9 1 Steam Line X AK1.05 / reactivity effects of steam line break 4.4 000040 Rupture(BW/E05;

- Excessive CE/EOS Heat fransfer W/E12)/ IV 1 CE/A11; W/E08 RCS Overcooling - PTS / IV X K3.1/ Actions to prevent PTS 35 1 000051 toss of Condenser Vacuum / IV X AA2 02110ss of vacuum requiring a reactor trip 4.1 1 000055 Station Blackout / VI X X EA2 03 / method of offsite power restoration post SBO 4.7 1 EK3.02 / method of calculating SDM in 580 44 1 000057 Loss of Vital AC Elec. Inst Bus / VI X AK3 01/ actions if fire and security sups is lost 44 1 000059 Accidentalliquid RadWaste Ret /IX X AK3 04 I actions if release terminates on high rad 4.3 1 000052 Loss of Nuctear Service Water / IV X AA1021 equipment effected by loss of ICW 33 1 000067 Plant Fire On-site /1X X G2 4.27 I use of protected train equipment during fire 3.5 1 000068 (BW/A06) Control Room Evac / Vill X AK2.011 availability of equipment at HSDCP during fire 40 1 000069 (W/E14) Loss of CTMT Integrity / V X G21 12 I Loss of integrity while refueling 40 1 000074 (W/E06&E07) Inad. Core Cooting I tv X EA1.06 / instrumentation accuracy with RCPs runn*ng 1 3 {.

000076 Hiah Reactor Coolant ActrvityIlX X AA2 02 / reason for shutdown and tavg reduction 3 BW/A02& A03 toss of NN1-X/Y / Vit +

l K/A Catego y Totats- 3 4 5 4 4 4 Group Point Total: 24

ES-401 PWR SRO Examination Outline F~ orm ES-401-3 Emergency and Abnormal Plant Evefutions - Tier 1/ Group 2 E/ APE # / Name 1 Safety Function K1 K2 K3 A1 A2 G K/A Topic (s) Imp. Points 000007(BW/E02&E10;/ X EA1.04 / sealinjection requirements in EOP-1 37 Stabehzation - Recovery ICE /E02) Reactor Trip -

1 BW/A01 Plant Runback 11 BW/A04 Turbine Trip tIV 000008 Pressurizer Vapor Space Accident / Ill X AK3 03 / actions for leaking safety watve 46 1 000009 Smaf: Break LOCA 1 '11 X EK102 / Characteristics of steam exitrg break 42 1 BW/E08; W/E03 LOCA Cookfown - Depress / IV W/E11 Loss of Emeroency Coolant Recire. / IV 000022 Loss of Reactor Coolant Makeup /11 X AA101/ response of CVCS to leak with insufreient makeup 33 1 '

000025 Loss of RHR System / IV X G2.123 / time to boil with loss of SDC 40 1 6 000027 Pressurizer Pressure Control System X AK2.03 I Effect on solid operation with letdown failure 3.2 1 Maffunction / Ill 000032 !.oss of Source Rance NI / Vil X G21 12 / Action statement during refueling 40 1 000033 Loss of intermediate Range NI / Vil X AA2 07 / conditions that will cause a reactor trin 42 1 ;

i 000037 Steam Generator Tube Leak /111 X AK3 071 indications of SGTL and reactor trip 44 1 000038 Steam Generator Tube Rupture i fit X EA2 01 lisolation of S/G when ESD and SGTR are present 4.7 1 l

000054 (CE/E06) Loss of Main Feedwater / IV X G2.4.07 / use of a condensate pump in TLOF ,

3.0 1 i.

00009 Loss of DC Power / VI X AA2.03 / effect of DC power loss on AFW system 39 1 000060 Accidentaf Gaseous Radwaste Ret /IX 000061 ARM System AlarmsIVil X_ AA1.01 I Auto start of S8VS on high fuel pool rad 36 1 L

W/E16 Hioh Containment Radiation I fX 000065 Loss of Instrument Air / Vill X AK3 04 i System response with valve failure 3.2 1 CE/E0w Functional Recovery X X EK1.2 / actions after once through cooling is accomplished 40 1 EK2.2 / actions if HPSI flow inaaequate 4.2 1 K/A Cateoory Point Totals: 2 2 3 3 3 3 Group Point Totat: 16 L_ _ _ - _ __ .-. _ . _ - . . - _ _ _ - - - . - - - _ - --- - - - - - . - - . - - - - - - - - - - - - - . - - - - - - . - - - - - - - - - - - - - - -

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6 ES-401 PWR SPO Examinaten Outline Form ES-401-3 Plant System - Tier 2/ Group 1 System # I tJame K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic (s) Imp. Points 001 Cokrol Rod Drive X X K1.03 / CEDM response to withdrawal signal . 3.6 1 A2 02 / closure of TCBs with te breaker open 43 1 003 Reactor Coolant Pump X X K2.01 f;oss of DC bus affect on RCPs 3.1 1 A4 03 tod bff pump statut post LOOP 2.5 1 004 Chemical and Volume Control X X K3.05 / Char 9ing pump failure 42 1 A1.11/ Auto'acfions fer Le*down leak 30 1 013 Engineered Safety features Actuation X X K1.05 / faaed channet and CSAS actuation 4.4 1 K5 02 / SIAS block loge 33 1 014 Rod Positen Indication -

015 Muclear instrumentation X X K4.07 at' ion of the nuclear startup chanrW 3.8 1 A1.03 atton of the hnear control channels 3.7 1 017 fn-core Temperature Mor-jtor X K6.01/ power reduction with faaed detectors 3.0 1 022 Containment Cooling X X K2.01/ 3.1 1 A4 01/ power suppy.

response failure of CCS to affecting LOOP coolers 36 1 025 tce Condenser 026 Containment Spray _ X G2.212 / unit differences in CSS surveiHance 3.4 1 056 Condensate X G2.2 25 / tech spec bases for CST volume 3.7 1 059 Mair* Feedwater X K3 03 floss of instrument air to FRVs 3.7 1 061 Audiary/ Emergency Feedwater X A3 04 / response of afas with failed channets 44 1 063 DC Electrical D:stnbution. X K4 01/ a'ignment of AB bus 30 1 068 Uguid Radwsste 071 Waste Gas Disposal X KS 04 / hdrogen / oxygen limitations in WGS 3.1 1 072 Area Radiation Monitorinq K/A Category Point Totats: 2 2 2 2 2 1 2- 1 1 2 2 Group Point Total: 19

ES-401 PWR SRO Exar-*wtion Outline Form ES-401-3 Plant Systems - Tier 2/ Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic (s) Imp. Points 002 Reactor Coolant . X X A1.05 / low flow trip inputs 3.7 1 A3 01/ RCS leak detection methods 3.9 1 006 Emergency Core Cooling X K2 01/ HPSI loading on power loss 39 1 010 Pressurizer Pressure Contro! _ G2.2 25 / bases for pressurizer water level 3.7 1 011 Pressurizer Level Controf X K2 02 / Avaliabifity of heaters on bus loss 32 1 012 Reactor Protection X K5 01/ ASGT trip parameters 38 1 016 Non-nuclear Instrumentaten 027 Containment lodine Remova! X K101/ (Jnit 1 IRS with vaW 005 37 1 028 Hydrocen Recornbiner and Purge Control X A101/ Actions for H2 levels (%) 3.8 1 029 Containment Purge X G2.2.25 / bases for valves being closed at 3.7 1 power 033 Spent Fuel Pool Cooting X K4 03 / fuel pool minimum level with leak 29 1 034 Fuel Handimg Ecuipment 035 Steam Generator X K5 01/ Affect of SGBD adjustme .s 39 1 039 Marn and Reheet Steam X X A2.05 / response of plant to MSR leak 36 1 A4.01 i sequence of reheat valves openmg 28 1 055 Condenser Air Removal OG2 AC Electrical Ostnbution X K3 02 / undervotatage response by EPG 44 1 064 Emergency Diesel Generator X X K6 08 / storage I day tank capacity 3.3 1 A4.01 I EDG response to LOOP during test 4.3 1 073 Process Radtation Monitoring X K1.01/ loss of CCW rad monitor 39- 1 075 Circulating Water 079 Station Air 086 Fire Protection 103 Containment i

K/A Categor; Point Totals: 2 .2 1 1 2 1 2 1 1 2 2 Group Point Total: 17 l

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. Facility: St. Lucie Date of Exam 11 30-98 Exam Level SRO

' Category K/A # Topic imp. Points 21.12 Actions for power excursion 40 1 Conduct of 2.1.18 Log entries during event 30 1 2.1.7 Manual ESFAS initiation 37 1 l'

2.1.2 Qualifications for assuming the shift 4.0 1 2.1.11 Action statements c 1 hr descrimination 38 1 Total 2211 Temporary changes expiration 34 1 2.2.13 Clearance requirements 3.8 1 Equipment I Control 2 2.24 LCO with EDG out of service 38 1 l

l 2226 Time to be subentical pnor to refueling 37 1 i Total 2.3.1 Entry into a very high radiation area 3.0 1

)

- 1 2.3.1 Calcutation of TEDE 30 1 Radiation Control 232 When is a TEDE ALARA review required 29 1

'239 Release permit requirements of containment purge operation 34 1 l l

l l

l Total 2440 Classification of event after termination 40 1 I

Emergency 2429 Route of evacuation considering wind direction 40 1 Procedures and ,

Plan 2431 Annunciator response 34 1 j 1

2429 Mjnimum pars for terrorist takeover 40 1 l l

I Total 17 Tier 1 Target Point Total (RO/SRO) 13/17 l

1 1

l l

l 1

l

7. ..

l App'endix D Scenario Outline Form ES-D-1 Facility: St. Lucie Scenario No.: 2 Op-Test No.: 2 Objectives: To evaluate the students ability to implement the ONOPs for various instrument and component failures; perform a normai plant power reduction; and to execute the EOPs for a Small Break LOCA combined with a Loss of Offsite Power and subsequent total loss of High Pressure Safety injection. (Functional Recovery) initial Conditions: Unit 2 is i:it 100% power MOC Turnover: The plant is operating at 100% power, MOC. The 2B Heater Drain Pump has developed a discharge flange leak and management has made the decision to reduce power to 90% in order to facilitate repairs. 2A Emergency Diesel Generator is out of service foi relay replacement, expected back in four hours. 2A Auxiliary Feedwater Pump is out of service for bearing replacement, not expected back this shift. Instructions to the shift is to reduce power to 90% and remove the 2B Heater Drain Pump from service.

Preexisting Malfunctions: 2B HPSI pump becomes air bound 10 minutes after SIAS Event Malf. Event Event No. No. Type

Description 1 0 N-BOP Power decrease from 100% to 90%

R-RO 2 1 l-RO PT-1100X setpoint (selected pressurizer pressure controller) drifts low 3 2 l-BOP LT-9011(2A steam generator level controller) fails high 4 3 C-RO Reference leg for LT-1110X ruptures (common leg failure)

S 4 C-BOP DEH power supply failure, turbine control swaps to manual (rapid downpower in progress) 6 5 M-RO Small break LOCA, Loss of Offsite Power on reactor trip M-BOP 7 6 C 2B HPSI pump becomes air bound 10 minutes after SIAS, loss of all High Pressure Safety injection (N)o'rmal,- (R)eactivity, (1)nstrument, (C)omponent, (M)ajor

I Appbndir D Scenario Outline Form ES-D-1 Facility: St. Lucie Scenario No.: 3 Op-Test No.: 3 l Objectives: To evaluate the students ability to implement the ONOPs for various instrument and component failures; perforrn a normal plant power reduction; and to execute the EOPs for an Excess Steam Demand combined with loss of two of three Auxiliary Feedwater Pumps and totalloss of instrument Air.

Initial Conditions: Unit 2 is at 100% power MOC Turnover: The plant is operating at 100% power, MOC. The 28 Main Feedwater Pump has developed a crack in an oilline and is leaking approximately .3 GPM. Maintenance is standing by and adding oil as needed. Management is in the process of evaluating the problem and will make a decision within the next hour whether or not to reduce power and repair the leak. 2B Auxiliary Feedwater Pump is out of service for bearing replacement, not expected back this shift. The Steam Jet Air Ejector Radiation Monitor is out of service, not expected back this shift. Chemistry reports a .5 GPD' tube leak in the 2A Steam Generator.

Instructions to the shift are to maintain 100% power.

Preexisting Malfunctions: ' oss of instrument air on reactor trip 2C Auxiliary Feedwater pump trips 10 minutes after AFAS actuation Event Malf. Event Event No. No. Type

Description 1 1 C-BOP PCV-8801 (Steam bypass control valve) leaks by 2 0 N-BOP Power reduction to 45%

R-RO 3 2 l-RO HIC-1100 (pressurizer spray controller) input fails high 4' 3 C-RO LCV-2110P (pressurizer level control valve) drifts closed 5 0 N-BOP Restoration of charging and letdown 6 4 l-BOP PT-10-8 (condenser vacuum pressure transmitter) sensing line failure 7 5 M-RO Reactor trip on loss of vacuum, V-8201 and V-8202 (2A S/G M-BOP main steam safety valves) stick fully open on the reactor trip 8 6 C Loss of instrument air

'(N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor l

i l

1

Apppndix D Scenario Outline Form ES-D-1 Facility: St. Lucie Scenario No.: 4 Op-Test No.: 4 :

Objectives: To evaluate the students ability to implement the ONOPs for various instrument and component failures; perform a normal plant power increase; and to execute the EOPs for a Steam Generator Tube Ruptura in conjunction with a steam line break inside containment ,

with no secondary radiation monitoring capability. (Functional Recovery) '

initial Conditions: Unit 2 is at 50% power MOC Tumover: The plant is operating at 50% power, MOC. Repairs on the 28 Main Feedwater )

Pump oilleak have just been completed and 2B Main Feedwater Pump has been started and i is currently running. Management has given the approval to increase power to 100%. 2B Auxiliary Feedwater Pump is out of service for bearing replacement, not expected back this shift. The Steam Jet Air Ejector Radiation Monitor is out of serv .ce, not expected back this. '

shift. Chemistry reports a .5 GPD tube leak in the 2A Steam Generator. Instructions to the shift are to increase power to 100%.

Preexisting Malfunctions: 2A1480V Load Center deenergizes on reactor trip B train MSIS fails to actuate on high containment pressure Event Malf. Event Event :

No. No. Type

Description 1 '1 N-BOP Power increase from 50% to 100%

R-RO - _

i 2 2 C-RO ' Inadvertant 8 train SIAS actuation- -

3~ ' 3. I-BOP LT 9021 (2B steam generator level transmitter) drifts low -

4 4 1-RO LT-1110X (selected pressurizer level control channel) fails high 5 5 C-BOP 2B CCW pump trips 6 6 M-RO 2A Steam Generator tube rupture (250 GPM),2A main M-BOP steam line break inside containment on reactor trip C Loss of the 2A1480V Load Center C B train MSIS faiis to actuate l

l

(N)ormal, (R)eactivity, (1)nstrument. (C)omponent, (M)ajor

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1 Appendix D Scenario Outline Form ES-D-1 6

Facility: St. Lucie Scenario No.: 5 Op-Test No.: 5 Objectives: To evaluate the students ability to implement the ONOPs and take manual control of systems due to various instrument and component failures; perform a normal plant power reduction; and to execute the EOPs for a totalloss of all feedwater, recoverable by use of the 28 Condensate pump initial Conditions: Unit 2 is at 30% power BOC Tumover: The plant is operating at 30% power, BOC. The unit is returning from a 30 day refueiing outage and has been on a chemistry hold. Chemistry has determined that RCS chemistry values are not acceptable and has recommended to Management that the unit be taken off line, Management will make a decision within one hour. 2A Main Feedwater Pump is out of service for oil replacement after water was found in the oil, expected back in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ,

)

Instruction to the shift is to maintain 30% power Preexisting Malfunctions: Differential current lockout of 2A3 4160 V bus on reactor trip 28 Auxiliary Feedwater Pump develops a sheared shaft l 2C Auxiliary Feedwater pump trips 2 minutes after start Event Malf., Event ' Event No. No. Type

Description 1 0. C-RO FCV-2210 X and V2525 (reactor rnakeup water valves) leak by.

2- 1 l-BOP FT-8011 (2A steam generator steam flow transmitter) fails low 3 2- 1-RO LT-2226 (VCT level transmitter) fails low 4 3 C-BOP # 4 Governor Valve drifts open 5 4 R-RO Power Reduction from 30% to 0% l N-BOP .

i 6 5 M-RO 28 main feed line break outside containment !

M-BOP 7 6 C 2A3 4160 V bus deenergizes on reactor trip (differential current lockout) j 8 C- 2B Auxiliary Feedwater Pump' develops a sheared shaft I l

9 .C 2C Auxiliary Feedwater pump trips 2 minutes after start i (N)ormal, (R)eactivity, - (1)nstrument, (C)omponent, (M)ajor j l

, .. .i

- -. - . - - .- . ..-...-.. .. - .- - - ~ . - .

o' ES-301 Individual Walk-Through Test Outline Form ES-301-2 Facility: Gt.Lucie .

Date of Examination: 11 30-98 Exam Level (circle one): RO / SRO(l) Operating Test No.: 1 System / JPM Title / Type Codes

Safety Planned Follow-up Questions:

Function K/A/G - Importance - Description

1. RHRS 005 / Resetablish Shutdown 4P a. K1.04 - 2.9 / 3.1 - unit differences in SDC Cooling Unit 2 (20 minutes) D S,L purification I

b. G2.1.25 - 2 8 / 3.1 - time to boil calculation

2. PZRPCS 010 / Depressurize the RCS 03 a. K4.01 - 2.7 / 2.9 - prots -tion from thermal (15 minutes) N,S,L shock to sprsy valves

b. A1.07 - 3.7 / 3.7 - method of RCS depress with all spray out of service

3. PRTS 007/ Cool the Quench Tank Unit 05 a. A2.01 - 3.9 / 4.2 - Response of RCS to Code 2 Safety leak (10 minutes) N,S,A

b. K4.01 - 2.6 / 2.0 - Quench tank unit differences 4.EDG 064 / Restore Offsite Power to 2A3 06 a. K1.05 - 3.4 / 3.9 - differences in air start l 4.16 KV bus (15 minutes) N,S systems

b. K4.02 - 3.9 / 4.2 - EDG trips 5.CVCS 004 / Establish and Attemate 01 a.K2.01 - 2.9 / 3.1 - Alternate flowpath with Charging Flowpath through the A HPSI LOOP Header (20 minutes) .

N,C b. K5.06 - 3.0 / 3.3 - worth of boron added

6. AFW 061/ Manually Activate AFAS unit 04S a. A2.02 - 3.1/ 3.4 - AFAS response to loss of 1 DC bus (10 minutes) M, C, A i

b. K4.02 - 4.5 / 4.6 - AFW response to LOOP l with concurrent SIAS '

7. CPS 029 l Perform a Containment 08 a K4.03 - 3.2 / 3.5 - CPS /ESFAS . interface Purge Unit 1" (15 minutes) N,C, A

b. G2.1.12 - 2.9 / 4.0 - Action if rad monitor fails

8. AC Elec 062 / Disconnect Instrument 06 a. K4.03 - 2.8 / 3.1, K3.01 3.5 / 3.9 - Purpose ,

inverter 1B for Preventive Maintenance of mechanicalinterlock, response of plant to loss I Unit 1 (10 minutes) D,P of bus j

b. V2.01 - 3.3 / 3.4 - Unit differences in 120V Instrument AC alternate sources l

9. CCW 008 / Open CCW Supply Valve 08 a. K1.02 - 3.3 / 3.4 - Response of system to RCP !

to the RCPS with Failed Solenoid Valve cooler leak (15 minutes) N,R,A

b. A3.08 - 3.6 / 3.7 - SlAS affect on CCW

10. HRPS 028 / " Operate the H2 Purge 05 a. K1.01 - 2.5/2.5 - Unit difference in H2 purge System Unit 1"(30 minutes) D,R systems l 1

b. K5.03 - 2.9 / 3.6 - Sources of H2 during a LOCA l

l l

1-

p-o e-L' L

!. ES-301 _

Administrative Topics Outline Form ES-301-1 l^

Facility: St. Lucie Date of Examination: .11-30-98 ,

Examination Level (circle one): RO/SRO I l Operating Test Number: 1 i

\

Administrative Topic / Subject Describe method of evaluation: l Description 1. ONE Administrative JPM, OR l

2. TWO Administrative Questions A.1 Plant Parameter JPM/ Perform SDM Calculation Unit 2 Verification K2.17 - 3.7/4.4 l Ability to interpret JPM / Verify BAM Tank Operability graphs which contain plant performance data l K2.1.25 - 2.8 / 3.1 !

l A .2 Tagging and JPM/ Initiate a Clearance Unit 1 l Clearances l K2.2.13 - 3.6/3.8 i A.3 Knowledge of 10 CFR 20 and facility radiation control Question 1/ Determine Posting Requirements from a {

Survey i requirements i

~

Question 2 / Dress Requirements for Posted Area A.4 Knowledge of the Question 1/ EAL Verification emergency plan l K2.4.29 - 2.6 / 4.0 Question 2 / Notification Criteria i

A.4 Knowledge of the SRO JPM / Make Protective Action Recommendations responsibility in the (SRO) emergency plan K2.4.40 - 2.3 / 4.0

EAL classification for SRO simulator scenarios may be substituted for questions.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Date of Examination: 11-30-98 Examination Level (circle one): RO/SRO Operating Test Number: 1 Administrative Topic / Subject Describe method of evaluation:

Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 Plant Parameter JPM/ Perform SDM Calculation Unit 2 Verification '

K2.17 - 3.7/4.4 Ability to interpret JPM / Verify BAM Tank Operability graphs which contain plant performance data K2.1.25 - 2.8 / 3.1 A.2 Tagging and JPM/ Initiate a Clearance Unit 1 Clearances K2.2.13 - 3.6/3.8 A.3 Knowledge of 10 -

CFR 20 and facility Question 1/ Determine Posting Requirements from a radiation control Survey requirements >

K2.3.1 - 2.6 / 3.0 Question 2 / Dress Requirements for Posted Area A.4 Knowledge of the Question 1/ EAL Verification emergency plan K2.4.29 - 2.6 / 4.0 Question 2 / Notification Criteria A.4 Knowledge of the SRO JPM / Make Protective Action Reccmmendations responsibility in the (SRO) emergency plan K2.4.40 - 2.3 / 4.0 l l

EAL classification for SRO simulator scenarios may be substituted for questions.

I I ;

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?

REGION ll lNITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT ,

PERFORM A SHUTDOWN MARGIN CALCULATION UNIT 2 I

l CANDIDATE EXAMINER I 4

REGION ll lNITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE ST LUCIE NUCLEAR PLANT KA Statement: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior and instrument interpretation KA #: K2.1.7 - 3.7 / 4.4 Facility JPM #: New Task Standard: Perform a shutdown margin surveillance Unit 2 Preferred Evaluation Location:

Simulator Control Room X NTC X Preferred Evalur, tion Method:

Perform X Simulate Beforences: OP 2-0110056, " Surveillance Requirements for Shutdown Margin Modes 2,3,4,5, (subcritical)", St. Lucie Unit 2 Plant Physics Curves Validation Time _15 minutes Candidate: Time Start Name Time Finish _

Performance Rating: Sat Unsat Examiner: Signature:

Name ST. LUCIE TRAINING DEPT.

. . . . . . - .. -- . . - . . . . - - .- . . - . . . . . . . . ~ _ _ - - .

Reference Material Needed:. i

) .OP 2-0110056," Surveillance Requirements for Shutdown Margin Modes 2,3,4,5, _

,(subcritical)", St. Lucie Unit 2 Plant Physics Curves Road to Candidate Directions to candidate for' Administrative JPMs:

I will explain the initial conditions and state the task to be performed. You will be l allowed tho use of any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by retuming the material needed for the task that i provided you.

Initial' Conditions: Unit 2 tripped from 100% power 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months ago and is currently in

. Hot Standby. Core bumup is 10,000 EFPH and current RCS boron i is 193 ppm. CEA # 44 did not insert when the reactor tripped and :

l&C reports it to be mechanically bound. Reactor Engineering reports a reactivity deviation of + 287 pcm. ,

Initiatina Cues: . The ANPS.has directed you to perform a Shutdown Margin Calculation for the current plant conditions.

t ST LUCIE TRAINING DEPT.

job PERFORMANCE MEASURE PAGE 3

4 CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 2 tripped from 100% power 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months ago and is currently in Hot Standby. Core bumup is 10,000 EFPH and current RCS boron is 193 ppm. CEA # 44 did not insert when the reactor tripped and l&C reports it to be mechanically bound. Reactor ,

Engineering reports a reactivity deviation of + 287 pcm.

INITIATING CUE:

The ANPS has directed you to perform a Shutdown Margin Calculation for the current plant conditions.

l i

1 l

I 1

'I j

I ST. LUclE TRAINING DEPT. 1 job PERFORMANCE MEASURE !

PAGE 4 I

I i

u__ . _ _ . .

. .-. .=- - - . . . _ _ - . - - . - - - - _ - - - _ ---

,~

REGION ll INITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE ST. LUCIE NUCLEAR PLANT MAKE PROTECTIVE ACTION RECOMMENDATIONS :

1 (SRO)

CANDIDATE , j l

EXAMINER l

I l

l l,

REGION ll l INITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE i

ST LUCIE NUCLEAR PLANT KA Statement: Knowledge of the SROs responsibilities in emergency plan implementation i KA #: K2.4.40 - 2.3 / 4.0 i Facility JPM #: New Task Standard: Using the provide plant conditions, make protective action recommendations Preferred Evaluation Location:

Simulator Control Room X NTC X t

Preferred Evaluation Method:

Perform X Simulate .

References:

EPIP-02," Duties and Responsibilities of the Emergency Coordinator" Validation Time _ 15 minutes l

Candidate: Time Start '

Name Time Finish Performance Rating: Sat Unsat Examiner: Signature: !

Name l sT. LUCIE TRAINING DEPT, job PERFORMANCE MEASURE PAGE2 l

l I

i Reference Material Needed:

EPIP-02," Duties and Responsibilities of the Emergency Coordinator" ,

Read to Candidate Directions to candidate for Administrative JPMs:

I will explain the initial conditions and state the task to be performed. You will be ,

allowed the use of ar,y reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by retuming the material needed for the task that I provided you.

i Initial Conditions: A LOCA with containment impairment has occurred on Unit 2. The EC has declared a General Emergency. The following is the OCDM release data as reported by Chemistry: ;

1 Wind Direction: 168 Wind Speed: 15 mph.

TEDE RD_Ei 1 mile 5400 mr 24500 mr 2 miles 2700 mr 10600 mr 5 miles 975 mr 5075 mr 10 miles 480 mr 1245 mr initiatina Cues: Analyze the above data and make the appropriate Protective 1 Action Recommendations.

sT. LUCIE TRAINING DEPT.

job PERFo3MANOE MEASURE PAGE 3 j

F CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS: A LOCA with containment impairment has occurred on Unit ;

2. The EC has declared a General Emergency. The ,

following is the OCDM release data as reported by Chemistry:

Wind Direction: 108 Wind Speed: 15 mph.

TEDE CDE 1 mile 5400 mr 24500 mr 2 miles 2700 mr 10600 mr 5 miles 975 mr 5075 mr j 10 miles 480 mr 1245 mr i

INITIATING CUE: Analyze the above data and make the appropriate Protective l Action Recommendations l l

1 ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 4 j l

l I

l

_. . . . . - . . . . - - . . - . . _ . . - . = - - . . . _ . --

. Answer Key -

1 mile: E(CR) 2 miles: E(ORAB)+S(RS) 5 miles: E(QRAB)+S(RS) 10 miles - TBD: S(QRAB) k i

l l

ST. LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 5

REGION 11 I INITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE

~

ST. LUCIE NUCLEAR PLANT VERIFY BAM TANK OPERABILITY I l

l CANDIDATE EXAMINER l

l i

1 l

- 4 i

REGION ll !

INITIAL LICENSE EXAMINATION 4

ADMINISTRATIVE JOB PERFORMANCE MEASURE I ST LUCIE NUCLEAR PLANT KA Statement: Ability to interpret graphs which contain plant performance data l

KA #: K2.1.25 - 2.8 / 3.1 Facility JPM #: New I

l Task: Using the information provided, verify BAM tank operability l

Preferred Evaluation Location:

Simulator Control Room X NTO X Preferred Evaluation Method:

Perform X Simulate

References:

OP 1-0010125A, Data Sheet 4, " Verification of Boration Flow Paths" l

Validation Time 15 minutes Candidate: Time Start Name Time Finish Performance Rating: Sat Unsat l

Examiner: Signature:

Name I

l ST. LUCIE TRAINING DEPT. I job PERFORMANCE MEASURE PAGE 2

I Reference Me'.orial Needed: * '

OP 1-001f' r25A, Data Sheet 4, " Verification of Boration Flow Paths" Read to Candidate Directions to candidate for Administrative JPMs: !

I will explain the initial conditions and state the task to be performed. You will be .

allowed the use of any reference needed to complete the task. Ensure you indicate to !

me when you finish your assigned task by retuming the material needed for the task that i provided you. l I

initial Conditions: Unit 2 is at 100% power. The following are the current BAM tank pararneters: ;

Level Temperature Boron Concentration l

2A BAMT 75 % 110 F 5675 ppm 2B BAMT 92 % 115 F 4140 ppm )

Initiatina Cues: The ANPS has directed you to verify BAM tank operability LAW OP 2-0010125A Data Sheet 4 :

I j

l ST. LUCIE TRAINING DEPT, JOB PERFORMANCE MEASURE !

PAGE 3

CANDIDATE CUE SHEET t (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

Initial Conditions: Unit 2 is at 100% power. The following are the current BAM tank parameters: '

Level Temperature Boron Concentration 2A BAMT 75 % 110 F 5675 ppm 2B BAMT 92 % 115 F 4140 ppm i

Initiatina Cues: The ANPS has directed you to verify BAM tank operability LAW !

OP 2-0010125A Data Sheet 4 l l

1 I

ST.LUCIE TRAINING DEPT.

JOB PERFORMANCE MEASURE PAGE 4

)

REGION ll .

INITIAL LICENSE EXAMINATION ADMINISTRATIVE SECTION A3 QUESTIONS ST. LUCIE NUCLEAR PLANT !

CANDIDATE f EXAMINER l

J 4

i

REGION 11 INITIAL LICENSE EXAMINATION ADMINISTRATIVE SECTION A3 QUESTIONS ST.LUCIE NUCLEAR PLANT KA Statement: Knowledge of 10 CFR 20 and facility radiation control requirements KA #: K2.3.1 - 2.6 / 3.0

References:

HP-02, "FPL Health Physics Manual" .

Candidate: Time Start Name Time Finish Performance Rating: Question 1 Sat Unsat Question 2 Sat Unsat Examiner: Signature:

Name .

Comments ST. LUCIE TRAINING DEPT.