ML051890099

Final - Section B Operating Exam (Folder 3)

ML051890099
Person / Time
Site:	Three Mile Island
Issue date:	03/24/2005
From:	Mccall K AmerGen Energy Co
To:	D'Antonio J Operations Branch I
Conte R
References
Download: ML051890099 (84)

Text

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: 62201023 Task

Title:

Respond to continuous rod motion JPM No.: 2005 NRC NEW JPM A durinq a startup. Bank JPM 060 WA

Reference:

APE 001 AA 1.05 (4.3/4.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: 0 All conditions are met for taking the reactor critical.

- 0 1103-8, APPROACH TO CRITICALITY, has been completed through Step 3.2.2.

0 Group 1 through 4 Safety Rods are withdrawn.

0 Groups 5 and 6 Regulating Rods have been latched.

0 The ECP is calculated at 75% on Group 6.

0 A reactor engineer will perform the 1/M Plot and provide feedback, as requested.

Task Standard: Perform the immediate actions of 1202-8 and initiate a reactor trip.

Required Materials: None General

References:

1103-8, APPROACH TO CRITICALITY, Rev. 48 1202-8, CRD EQUIPMENT FAILURE, Rev. 56 Handouts: 0 Completed ECP 0 1103-8, APPROACH TO CRITICALITY, completed through Step 3.2.2 (Initiate a 1/M Plot ----)

Initiating Cue: Beginning at 1103-8, Step 3.2.3, continue the reactor startup by taking the reactor critical and leveling off power at 10E-08 amps.

Time Critical Task: No 1

Validation Time: 8 minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet

-- SIMULATOR SETUP IC-06 Increase boron concentration 200 PPM, manipulate remote function THR02 to achieve this shutdown margin.

Assign Malfunction RD03A to Event 1.

0 Insert Malfunction RD03A during the second pull.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 1

(Denote Critical Steps with a 4)

Performance Step: 1 Reviews handout.

Standard: Locates Step 3.2.3.

Comment:

Evaluator Cue: Provide handout described on cover sheet.

Performance Step: 2 Withdraw Group 5 rods to 25%

Standard: Using the MANUAL Control Switch on the Diamond Control Panel, withdraws Group 5 rods to approximately 25% while observing NIS count rate, SUR and rod position.

Comment:

Performance Step: 3 Stops rod withdrawal at 25%

Standard: Stops at approximately 25%, allows NIS count rate to stabilize, requests 1/M data.

Comment:

Evaluator Cue: -

As Reactor Engineer If requested, the 1/M Plot predicts criticality at > 100% on Group 7.

As CRS - Continue the startup.

Performance Step: 4 Withdraws Group 5 to 50%

Standard: Using the MANUAL Control Switch on the Diamond Control Panel, withdraws Group 5 rods to approximately 25% while observing NIS count rate, SUR and rod position.

Recognizes rods are continuing out and reports fault to CRS.

Evaluator Cue: -

As CRS Perform the immediate manual actions of 1202-8 for Motor Fault.

Comment: The candidate may initiate a reactor trip based on Step 3.1.8.6 of 1103-8: To take conservative actions, including a manual reactor trip if necessary ifabnormal or unexpected reactor indications are observed. If such is the case, then the candidate has satisfactorily completed the JPM.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance step: 5 Verify that the Diamond Rod Control Panel is in MANUAL.

Standard: Verifies Diamond Rod Control Panel in MANUAL.

Comment:

Select JOG speed on the Diamond Rod Control Panel.

Verify the GROUP and SINGLE SELECT switches are in OFF.

Select SEQ OR (sequence override) on the Diamond Rod Control Panel.

Standard: Selects JOG speed on the Diamond Rod Control Panel. (4)

Verifies the GROUP and SINGLE SELECT switches in OFF.

Selects SEQ OR (Sequence Override) on the Diamond Rod Control Panel. (d)

Comment:

d Performance step: 7 If out motion continues, select that group with the group select switch and place the Manual Command switch in the INSERT position.

Standard: Selects Group 5 on the Group Select Switch. (d)

Places the Manual Command switch in the INSERT position. (4)

Comment:

d Performance Step: 8 If uncontrolled out motion continues, then trip the reactor and go to OP-TM-EOP-001, Reactor Trip.

Standard: Initiates a MANUAL reactor trip by pressing the trip pushbutton and/or DSS pushbutton and verifies Group 1-7 rods inserted.

Comment:

Terminating Cue: When the candidate begins the immediate manual actions of EOP-001 - This JPM is complete.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2O05 NRC NEW JPM A Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITlAL CONDITIONS: All conditions are met for taking the reactor critical.

0 1103-8, APPROACH TO CRITICALITY, has been completed through Step 3.2.2.

0 Group 1 through 4 Safety Rods are withdrawn.

0 Groups 5 and 6 Regulating Rods have been latched.

0 The ECP is calculated at 75% on Group 6 .

0 A reactor engineer will perform the 1/M Plot and provide feedback, as requested.

INITIATING CUE: Beginning at 1103-8, Step 3.2.3, continue the reactor startup by taking the reactor critical and leveling off power at 10E-08 amps.

NUREG 1021, Revision 9, Supplement I

1103-1 58 Revision 35 ENCLOSURE 2 Page 1 of 1 Estimated Critical Rod Position (3.2)

NOTE Individual data entries may be completed in any sequence. Signoff of the Enclosure signifies the completion of the Enclosure calculation.

2 .a CALCULATION IS FOR AN ECP AT 532 ? 2°F ON TAVE -G3L DATEnlME I t 4W /7h-hi T; m G 2.b CYCLE BURNUP 2.c.l FINAL MEASURED BORON CONCENTRATION 2.c.2 BORON DEPLETION CORRECTION FACTOR 2.c.3 2.d 52 PC Control Room Log, Nuclear Engineering)

FI AL CORRECTED BORON CONCENTRATION (2.c.l) X (2.c.2) =

CRG 8 POSITION AT CRITICALITY 3.a FUEL EXCESS REACTIVITY (FIG 1) 3.b CRG 8 REACTIVITY WORTH (FIG 2) 3.c INVERSE BORON WORTH (FIG 3) 3.c.1

[,,,/

BORON REACTIVITY WORTH 3.d InverTcBoron XENON REACTIVITY WORTH @NUCLEAR 1 x (-1) =

ENGR., FIG 4) - o+I %Auk 3.e SAMARIUM AND PLUTONIUM BUILDUP (FIG 5) 0 TIME SINCE LAST SHUTDOWN 0 REACTIVITY DUE TO BUILDUP 4.1 INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW) 4.2

[

(FUEL) 3.a

+

(CRG 8) 3.b

+

(BORON) 3.c.l ESTIMATED CRITICAL ROD POSITION (FIG 6)

+

(XENON) 3.d

+

7 5 (SM) 3.e I x (-1) =

% WD on CRG 6 4.3 CRITICAL ROD POSITION TOLERANCE BAND (FIG 6) 0 CHECK ONE:

Steady State conditions if xenon (3.d) is 0.0 to -0.5% AWk 0.5%AW k 0 Transient conditions if xenon (3.d) is more negative than -0.5% Aklk x 0.8%Ak/k MINIMUM ROD WITHDRAWAL LIMIT @ (4.14.3 IRW) = g2  % WD on CRG s MAXIMUM ROD WITHDRAWAL LIMIT @ (4.1+4.3 IRW) = 70  % WD on CRG 7 Send copy of this Enclosure to Nuclear Engineering Send original to Operations for filing

\

13

1103-15B Revision 35 ENCLOSURE 2 Page 1 of 1 Estimated Critical Rod Position (3.2)

NOTE Individual data entries may be completed in any sequence. Signoff of the Enclosure sianifies the comdetion of the Enclosure calculation.

2.a CALCULATION IS FOR AN ECP AT 532 f 2°F ON TAVE -63 2.b CYCLE BURNUP 2.c.l FINAL MEASURED BORON CONCENTRATION 2.c.2 BORON DEPLETION CORRECTION FACTOR 2.c.3 P PC Control Room Log, Nuclear Engineering)

FI AL CORRECTED BORON CONCENTRATION (2.c.l) X (2.c.2) =

2.d CRG 8 POSITION AT CRITICALITY 3.a FUEL EXCESS REACTIVITY (FIG 1) 3.b CRG 8 REACTIVITY WORTH (FIG 2) 3.c INVERSE BORON WORTH (FIG 3)

[2,, /

3.c.l BORON REACTIVITY WORTH L

lnver;cBoron 1J x (-1) =

3.d XENON REACTIVITY WORTH @NUCLEAR ENGR., FIG 4) 3.e SAMARIUM AND PLUTONIUM BUILDUP (FIG 5) 0 TIME SINCE LAST SHUTDOWN REACTIVITY DUE TO BUILDUP 4.1 INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(FUEL) 3.a

+

(CRG 8) 3.b

+ (BORON) + (XENON) t (SM) x (-1) 3.c.l 3.d 3.e 1 =

4.2 ESTIMATED CRITICAL ROD POSITION (FIG 6) 7 5  % WD on CRG 6 4.3 CRITICAL ROD POSITION TOLERANCE BAND (FIG 6 )

CHECK ONE:

Steady State conditions if xenon (3.d) is 0.0 to -0.5%AWk 0.5%Ak/k 0 Transient conditions if xenon (3.d) is more negative than -0.5% Ak/k x 0.8%Aklk MINIMUM ROD WITHDRAWAL LIMIT @ (4.1-4.3 IRW) = $?2 % WD on CRG ,s MAXIMUM ROD WITHDRAWAL LIMIT @ (4.1+4.3 IRW) = 70 Oh WD on CRG 7 CALCULATED BY: IC

• fl*~4OT E 0t l n i B C DATE/TlME TLA bd/ Th: A+; m x APPROVED BY (SRO): 5 c- m sh-,$+ yM h QYI ci t r- DATEPTIME TO;\fiy,/ Tk\\ 5 4.) Px Send copy of this Enclosure to Nuclear Engineering Send original to Operations for filing 13

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: 004C050101 Task

Title:

Transfer to Reactor Buildinq Sump JPM No.: 2005 NRC JPM B Recirculation WA

Reference:

011 E A 1 . l l 4.214.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: 0 You have been assigned the duties of the Third Reactor Operator (RO).

The instructor/examiner will act as the Unit Reactor Operator (URO) and Control Room Supervisor (CRS).

0 Respond as you would if you were an on-duty Reactor Operator (RO).

0 The Reactor is shutdown with a LOCA in progress.

OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

OP-TM-EOP-010, Guide 20 has been completed.

0 BWST level has dropped below 15 feet and is continuing to lower.

Task Standard: Transfer the Reactor Building Sump to recirculation.

Required Materials: OP-TM-EOP-010, Revision 3 General

References:

OP-TM-EOP-010, Revision 3 Guides 21 and 3, Rule 2 Initiating Cue: The Control Room Supervisor (CRS) has directed you to Transfer the Reactor Building Sump to Recirculation IAW OP-TM-EOP-010, Guide 21.

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: NO Validation Time: 20 minutes 2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1. Reset the simulator to IC 17, if applicable.

NOTE: It is permissible to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMsthat are scheduled to -

be run concurrently.

2. INSERT malfunction TH06, LOCA on RCP discharge at 100% severity.

3. INSERT remote DHR05 IN to energize CF-V-1A Breaker.

4. INSERT remote DHRO6 IN to energize CF-V-1B Breaker.

5. INSERT remote DHR18 IN to energize DH-V-2 Breaker.

6. INSERT remote DHRI 1 at 100% to open DH-V-64.

7. INSERT EXPERT COMMAND: dhvdhv6b > 0.01 on EVENT 2 Command irf dhr25 out.

This will cause the breaker for DH-V-6B to trip when the examinee attempts to open DH-V-6B.

8. PLACE the Simulator in RUN.

9. Using OP-TM-EOP-001 and OP-TM-EOP-006 control and monitor plant conditions.

10. Complete all steps of Guide 20, PRIOR to Transfer to RB Sump when BWST level is approaching 15 feet.

11. WHEN BWST level is approximately 11.5 feet and the RB Flood Level is about 52 inches, PLACE the Simulator in FREEZE.

12. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.

13. This completes the setup for this JPM.

2005 NRC JPM B NUREG 1021, Revision 9

~~ ~

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION

.~

(Denote Critical Steps with a check mark)

START TIME:

I C 0 Cue: When the examinee has assumed the duties of the third RO, place the simulator in RUN and Examiner Cue: Hand the examinee Guide 21 Card (unless already obtained).

ExaminerllCO Cue: Provide repeat backslfeedback, as necessary.

NOTE: The examinee may review the NOTE at the top of Guide 21 and verify BWST level is less than 15 feet prior to starting any action of this Guide.

Performance Step: 1 ANNOUNCE initiation of RB Sump Recirculation over the plant page and radio.

Standard: Announces that he/she is placing the Reactor Building sump in recirculation over the RADIO and the PLANT PAGE system and repeats.

Comment:

Performance Step: 2 VERIFY RB FLOOD LEVEL > 32.

Standard: Verifies Reactor Building Flood level indication on Panels CC and CR greater than 32 inches.

NOTE: Reactor Building Flood Level will be reading about 50 to 52 inches at this time.

Comment:

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION NOTE: From the time that the Simulator is placed in RUN it should take approx. 2 minutes for BWST level to reach 9.5 feet.

Performance Step: 3 WHEN BWST LEVEL reaches 9.5 FT or RB Flood Level > 56 inches, THEN OPEN DH-V-6A and DH-V-6B.

Standard: Observes the RED and GREEN lights for DH-V-6B are both NOT LIT and determines that the breaker has tripped.

Examiners Note: WHEN the pushbutton for DH-V-6B is depressed the breaker for this valve will trip, leaving the valve in the CLOSED position.

Comment:

d Performance Step: 4 SHUTDOWN associated DH pump AND INITIATE Guide 3.

Standard: Enters RNO section for Step 3 of Guide 21 and stops DH-P-1B.

Initiates Guide 3.

Note: The examinee may announce DH-P-1B stopped and Guide 3 initiation.

Comment:

Note: The examinee will enter Guide 3 at Step B due to the conditions of this event. The first Step (B.l) has the examinee stop the LPI Pump on the associated Train, which has already been completed.

Performance Step: 5 STOP the LPI pump in the affected train.

Standard: Verifies Decay Heat Pump DH-P-1B (LPI) stopped by observing running light indication, pump amps and flow indications.

Comment:

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION

~

Performance Step: 6 IF DH-V-38A or B are inaccessible, then GO TO Step C.

Standard:

Evaluators Note: The examinee will NOT be able to determine if DH-V-38A or DH-V-38B are accessible.

Evaluators Cue: DH-V-38A and DH-V-38B ARE ACCESSIBLE.

Comment:

4 Performance Step: 7 CLOSE DH-V-4 on the train with the inoperable pump Standard: Closes DH-V-4B using the CLOSE pushbutton on Panel CR and observes the RED OPEN light is NOT LIT and the GREEN CLOSED light lit.

Comment:

Performance Step: 8 OPEN DH-V-38A and B (Aux. Bldg. 281 El.)

Standard: Dispatches the Primary A 0 to open both DH-V-38A and DH-V-38B.

K O s Cue: Use REMOTE DHR14 and OPEN DH-V-38A and DH-V-38B.

Both are on the same REMOTE number and operate together.

ICOs Cue: Wait about thirty seconds and contact the Control Room to report DH-V-38A and DH-V-38B OPEN.

Comment:

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 9 THROTTLE DH-V-4A and 6 to balance LPI flow between the two trains while maximizing total LPI flow within limits (Rule 2).

Standard: Refers to Rule 2, Step (2.2, since the step fits the event.

Determines total LPI flow must be adjusted and maintained at less than 3,000 gpm.

Using the OPEN, STOP and CLOSE pushbuttons for DH-V-4A and DH-V-4B on Panels CC and CR respectively, stabilizes total flow I 3,000 gpm with 2 1250 gpm per loop.

Examiners Note: Total LPI flow may start out greater than 3,000 gpm and fluctuate above andlor below 3,000 gpm during the adjustment of DH-V-4A and DH-V4B. The goal is to stabilize total flow I 3,000 gpm with 2 1250 gpm per loop.

Comment:

Terminating Cue: When LPI flow is less than 3,000 gpm, each loop is greater than 1250 gpm and total LPI Loop flows are balanced, this JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM 6 NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM B Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Page 9 of 9 form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You have been assigned the duties of the Third Reactor Operator (RO).

The instructor/examiner will act as the Unit Reactor Operator (URO) and Control Room Supervisor (CRS).

Respond as you would if you were an on-duty Reactor Operator (RO).

0 The Reactor is shutdown with a LOCA in progress.

0 OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

0 OP-TM-EOP-010, Guide 20 has been completed.

BWST level has dropped below 15 feet and is continuing to lower.

INITIATING CUE: The Control Room Supervisor (CRS) has directed you to Transfer the Reactor Building Sump to Recirculation IAW OP-TM-EOP-010, Guide 21.

2005 NRC JPM B NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: 0058050101 Task

Title:

Shift DHR Train A To The DHR JPM No.: 2005 NRC JPM C Operatins Mode and Initiate a Cooldown WA

Reference:

005 A4.01 3.6 13.4 Facility Bank JPM 015, Modified Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: A plant shutdown and cooldown is in progress.

0 RCS temperature is 215 O F .

RCS pressure is 285 psig.

0 RC-P-1B operating.

OP-TM-212-111, SHIFTING DHR TRAIN A FROM DHR STANDBY TO DHR OPERATING MODE is in progress through Step 4.7.1.

Task Standard: DHR Train A in service with cooldown initiated and flow c 3500 gpm.

Required Materials: None General

References:

0 OP-TM-212-111, SHIFTING DHR TRAIN A FROM DHR STANDBY TO DHR OPERATING MODE, Revision 2 OP-TM-212451, CONTROL OF DH TRAIN A FLOW AND TEMPERATURES, Revision 2 u Handouts: 0 OP-TM-212-111, signed off through Step 4.7.1 OP-TM-212-451 2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: Beginning at OP-TM-212-111, Step 4.7.2, place DHR Train A in service for cooldown.

Time Critical Task: NO Validation Time: 15 minutes 2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam Setup: IC 257 IC for placing DHR in service for cooldown.

All OP-TM-212-111 Prerequisites met.

Perform OP-TM-212-111 through Step 4.7.1, ENSURE DH-V-19A throttled open or OPEN.

Change PPC plant mode to Cold Shutdown - Go to operator entrieslplant modeldecay heat cooling.

Heat-up and Cooldown Curve on screen.

FREEZE and SNAP.

NOTE: SIMULATOR OPERATOR will be required to operate DH-V-19A and provide A 0 communications.

2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Locate procedure.

Standard: Reviews procedure provided.

Comment:

Evaluators Cue: Provide a copy of OP-TM-212-111, signed off through Step 4.7.1.

Performance Step: 2 Throttle OPEN DH-V-4A for approximately 8 seconds.

Standard: Depresses OPEN PB for DH-V-4A for approximately 8 seconds (CLOSED light should extinguish).

Comment:

4 Performance Step: 3 Start DH-P-1A.

Standard: DH-P-1A started as indicated by red running light illuminated.

Comment:

Performance Step: 4 Monitor pump discharge pressure for oscillations which indicate possible vapor binding.

Standard: Verifies stable discharge pressure on DH-P-1A.

Comment:

2005 NRC JPM C NUREG 1021. Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 If flow on DH-FI-802A exceeds 3500 gpm then throttle closed DH-V4A to achieve 2500-3500 gpm.

Standard: Verifies flow 3500 gpm.

Comment:

d Performance Step: 6 Shift. Decay Heat flow control to DH-V-19A as follows:

0 Establish communications with an operator at DH-V-19A.

0 If DH flow > 3100 gpm then throttle closed DH-V-19A until DH flow has dropped approximately 300 to 400 gpm.

0 Throttle open DH-V-4A until DH flow I 3500 gpm.

0 Repeat previous two steps until DH-V-4A is full open and flow rate is 2500 - 3500 gpm.

Standard: Communicateskoordinates with field operator until DH-V-4A is full OPEN and flow is between 2500 - 3500 gpm.

Comment:

Evaluators Cue: Simulator Operator will provide field operator communications and operate DH-V-19A.

Simulator Operator Remote Function DHRl2 Note:

Performance Step: 7 Depress ALARM ON PB for Loop A on DH-1-MS to energize low flow alarm.

Standard: Depresses ALARM ON PB for Loop A.

Comment:

2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8 Adjust DC-V-2A and DC-V-65A as required to control temperature IAW OP-TM-212451, CONTROL OF DH TRAl N A FLOW AND TEMPERATURES.

Standard :

Comment:

Evaluators Cue: Provide a copy of OP-TM-212451.

0 Initiate a cooldown to 190°F. Assume that DHR Train A is in the operating mode per OP-TM-212-000, Decay Heat Removal System.

Performance Step: 9 Enter OP-TM-212-451.

Standard: Reviews copy provided.

Comment:

Evaluators Cue: Maintaining back pressure with DH-V-4A will not be required at this time.

Performance Step: 10 If maintaining back pressure with DH-V-4A is not required, then open DH-V-4A and throttle DH-V-19A as necessary to maintain DH Train A flow as follows:

2500 - 3500 gpm as indicated by DH-FI-802A for normal DH operations.

IAW ATT. 7.1 during drained down - - -.

Standard: Condition should have been established in OP-TM-212-111 Comment:

2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION PROCEDURE NOTE: Closing DC-V-2A while opening DC-V-65A will raise RCS temperature while maintaining DC System flow.

d Performance Step: 11 Throttle DC-V-2A and DC-V-65A as necessary to maintain the following:

0 Desired RCS temperature as indicated by DH2TI1.

0 Decay Closed System flow approximately 3300 gpm on DC-FI-26.

Standard: Manipulates DC-V-2A and DC-V-65A to establish a temperature reduction.

Comment:

Terminating Cue: When cooldown has been established: This JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM C NUREG 1021, Revision 9

~~

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM C Exarninees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITlAL CONDITIONS: A plant shutdown and cooldown is in progress.

RCS temperature is 215 O F .

RCS pressure is 285 psig.

RC-P-1B operating.

OP-TM-212-111, SHIFTING DHR TRAIN "A" FROM DHR STANDBY TO DHR OPERATING MODE is in progress through Step 4.7.1.

INITIATING CUE: Beginning at OP-TM-212-111, Step 4.7.2, place DHR Train "A" in service for cooldown.

2005 NRC JPM C NUREG 1021, Revision 9

Appendix C Page 1 of 7 Form ES-C-1 PERFORMANCE INFORMATION

\ FaciIit y : Three Mile Island Unit 1 Task No.: 0390080104 Task

Title:

Initiate a natural circulation JPM No.: NRC JPM D cooldown usina the OTSG AtmosDheric Dump Valves (ADV).

K/A

Reference:

041 A4.06 (2.9/3.1)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

SimuIated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

L Initial Conditions: 0 Loss of off-site power resulted in a reactor trip.

0 The Emergency Diesel Generators are each providing power to their respective bus.

0 The RCS is borated to the cold shutdown concentration.

0 PZR Heater Bank 9 is on the Emergency Power Supply (1s 480V Bus).

0 Subcooling Margin is between 30 and 40 "F.

0 Natural Circulation and Primary to Secondary Heat Transfer have been verified.

Task Standard: Cooldown initiated using the Backup Loader ADV control station.

Required Materials: OP-TM-411-451 0 EOP-010, Guide 10 - NATURAL CIRCULATION 0 EOP-010, Guide 11 - COOLDOWN RATE LIMITS EOP-010, FIGURE 1 - RCS PRESSURE-TEMPERATURE LIMITS General

References:

OP-TM-411-451, MANUAL CONTROL OF TBVsIADVs, Rev. 3 Initiating Cue: Reduce OTSG pressures to establish a cooldown rate of 5 "F per hour.

Observe the limits of EOP-010, GUIDE 10 - NATURAL CIRCULATION and GUIDE 11- COOLDOWN RATE LIMITS.

Time Critical Task: No

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION

- Validation Time: 8 minutes

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION

- SIMULATOR SETUP Setup per IC 16 or assigned IC Insert Malfunction ED01 and verify the following:

Reactor Trip Both EDGs supplying their respective bus.

RCS borated to CSD value PZR Heater Group 9 on I S 480V Bus MS-V4A / 4B in AUTO at 1010 Psig Both OTSGs approaching 50% on Operating Range 0 RCS Pressure, Temperature, PZR Level, and MU tank level are stable in normal range Insert the following OVERRIDES:

ZAIICSIOMS Fails Turbine Hdr Pressure Setpoint AS-IS ZDllCSl2BMCS[3] OFF Fails Raise direction on MS-V4B Controller ZDllCSl2BMCS[4] OFF Fails Lower direction on MS-V-4B Controller ZDllCSl2AMCS[3] OFF Fails Raise direction on MS-V-4A Controller ZDllCSl2AMCS[4] OFF Fails Lower direction on MS-V-4A Controller

- Set the Backup Loader demands at 100%.

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Review Guide 1O/Plant Conditions Standard: Determines limits on cooldown ratelfigure 1.

Comment:

Evaluator Cue: 0 Provide a copy of GUIDE I O , GUIDE 11 and FIGURE 1.

0 As Control Room Supervisor, provide feedback as necessary throughout JPM performance.

Performance Step: 2 Adjusts the AUTO setpoint for MS-V-4A and MS-V-4B to establish a cooldown rate.

Standard: Performs actions and recognizes that neither valve responded.

Comment: It is acceptable for the candidate to begin at the next step.

Performance Step: 3 Enters OP-TM-411-451.

Standard: Locates OP-TM-411-451.

Comment:

Evaluator Cue: 0 Provide a copy of OP-TM-411451.

0 Assume that all PREREQUISITES are met.

0 (If necessary) All Auxiliary Operators are performing priority tasks.

Performance Step: 4 Places MS-V-4A and MS-V-4B in HAND and adjusts the demand to establish a cooldown rate.

Standard: Performs actions and recognizes that neither valve responded.

Comment:

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 Determines Backup Loader control is necessary.

Standard: Moves to Step 4.3 and reads NOTE: B/U Loader pushbutton selects both MS-V-4AIB thumb wheels for control.

Comment:

4 Performance Step: 6 VERIFY MS-V-4A and MS-V-4B Backup Loader demands are set for 0% demand or equal to currentlrequired ICs station demands (CC).

Standard: Adjusts the settings to ZERO or matches ICs demand.

Comment:

Performance Step: 7 PRESS B/U LOADER pushbutton Standard: Presses B/U LOADER pushbutton Comment:

.I Performancestep: 8 MAINTAIN Turbine Header pressure within limits by adjusting MS-V-4A and/or MS-V-4B B/U Loader thumb wheel.

Standard: Adjusts MS-V-4A and/or MS-V4B B/U Loader thumb wheel to establish a cooldown rate S50 F/hour.

Comment:

Terminating Cue: When the candidate is in control of the cooldown rate: This JPM is complete.

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: TMI 2005 NRC JPM D Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT ExaminersSignature: Date:

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET 1 NIT1AL CONDITIONS: Loss of off-site power resulted in a reactor trip.

The Emergency Diesel Generators are each providing power to their respective bus.

The RCS is borated to the cold shutdown concentration PZR Heater Bank 9 is on the Emergency Power Supply (1S 480V Bus).

0 Subcooling Margin is between 30 and 40 "F.

0 Natural Circulation and Primary to Secondary Heat Transfer have been verified.

INITIATING CUE: Reduce OTSG pressures to establish a cooldown rate of 5 "Fper hour. Observe the limits of EOP-010, GUIDE 10 - NATURAL CIRCULATION and GUIDE 11- COOLDOWN RATE LIMITS.

Appendix C Job Performance Measure Form ES-C-1 Worksheet

\ Facility: Three Mile Island Task No.: 0220070401 Task

Title:

Perform the Required Actions If JPM No.: 2005 NRC JPM E Containment Temperature Cannot Be Controlled Within Specific Limits K/A

Reference:

022 A4.04 3.1 / 3.2 Facility Bank JPM 079 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: 0 The Plant is at 100% power.

0 ICs is in full AUTO.

There is a small steam leak inside Containment.

0 The Director, Operations is informed of the situation.

Task Standard: RB Emergency Cooling is initiated with system pressure maintained 55-60 psig.

Required Materials: 1104-38, Section 3.2 General

References:

1104-38 Reactor Building Emergency Cooling Water System, Rev. 57 Initiating Cue: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling with RR-P-1A and the A Cooler using 1 104-38, Reactor Building Emergency Cooling Water System.

Time Critical Task: NIA Va Iidation Time: 10 minutes 2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam Setup: IC 256 IC-17 MALFUNCTIONS:

MS02A at 0.1% severity MS02B at 0.1% severity RW08 at 0% severity (to close RR-V-6)

Reduce power as necessary to maintain power less than 100%.

FREEZE the simulator.

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Locates procedure.

Standard: Determines 1104-38, Section 3.2 applies.

Comment:

Evaluators Cue: Provide a copy of 1104-38, Section 3.2 only.

0 Assume that all Section 2.0 LIMITS AND PRECAUTIONS are met.

PREREQUISITES 3.2.1.1 and 3.2.1.2 are met.

- Performance Step: 2 Verify system aligned for E.S. standby per 3.1. I and 3.1.2.

Standard: Verifies via Evaluator Cue.

Comment:

Examiners Cue: Reactor Building Emergency Cooling Water is aligned for E.S. standby.

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Procedure Note: Unless starting of RR Pumps is for emergency operations, verify NS-V-8 and NS-V-85 are closed prior to starting.

Performance Step: 3 Close NS-V-85 and insure NS-V-8 is closed.

Evaluators Cue: (If necessary)This is NOT an emergency situation.

Standard: Contacts A 0 to close NS-V-85 and verify NS-V-8 is closed.

Comment:

Evaluator or Booth NS-V-85 is closed and NS-V-8 is closed.

Operator Cue:

Performance Step: 4 Contacts A 0 to checklverify RR-P-1A packing leak off.

Standard: Verifies via Evaluator Cue.

Comment:

Evaluator or Booth Packing leakoff on RR-P-1A is sufficient to maintain gland Operator Cue: temperature < 200°F.

.( Performance Step: 5 Start RR-P1A and insure recirc valve RR-V-1OA opens.

Standard: 0 RR-P-1A started by rotating the extension control in the clockwise direction and verifying red light illuminated on CC.

(4 0 RR-V1OA verified open by amber light illuminated on PCR.

Comment:

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Verify Open RR-V-3A.

Standard: RR-V-3A opened by depressing the OPEN pushbutton and verifying red OPEN light illuminated.

Comment:

.( Performance Step: 7 Open RR-V-4A.

Standard: RR-V4A opened by depressing the OPEN pushbutton and verifying red OPEN light illuminates.

Comment:

.( Performance Step: 8 Open RR-V-1A and insure RR-V-1OA shuts.

Procedure Caution: Maintain single RR Pump flow (as indicated by total of Computer Points Al049, A1050 and A1051) less than or equal to 5800 gpm if ISPH Pump bay water level (as indicated by SR-LI-1172) is > 277 or less than or equal to 5600 gpm if bay water is I 277. This assures adequate NPSH is achieved, especially if RR-V-6 fails open or if RR-V-5 is throttled open to control backpressure. Normal ISPH Pump bay water level is > 277.

Standard: RR-V-1A opened by depressing the OPEN pushbutton and verifying red OPEN light illuminates. (4)

RR-V-1OA verified closed as indicated by blue light illuminated.

Comment:

Evaluators Cue: ISPH Pump Bay Water Level is 280.

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION

.( Performance Step: 9 Control system pressure by jog button for RR-V-5 (55-60 psig) as indicated on CR, if necessary.

Standard: Recognizes RR-V-6 is failed closed.

Utilizes the RR-V-5 OPEN and CLOSE pushbuttons to maintain 55-60 psig on PI 224 while maintaining total flow I5800 gpm.

Comment:

Terminating Cue: When system pressure and flow are stabilized using RR-Vd:

This JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM E Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT ExaminersSignature: Date:

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET L

INITIAL CONDITIONS: e The Plant is at 100% power.

e ICs is in full AUTO.

e There is a small Steam leak inside Containment.

e The Director, Operations is informed of the situation.

INITIATING CUE: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling with RR-P-1A and the A Cooler using 1 104-38, Reactor Building Emergency Cooling Water System.

2005 NRC JPM E NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet L Facility: Three Mile Island Task No.: 0648000101 Task

Title:

Operate the Station Blackout Diesel JPM No.: 2005 NRC JPM F Generator WA

Reference:

APE 056 AA2.37 3.7 / 3.8 Facility Bank JPM 131 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinn:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: 0 The plant was experiencing problems with the grid.

0 The Turbine tripped due to the power load unbalance relay actuating.

0 The Turbine Trip resulted in a Reactor Trip.

0 OP-TM-EOP-001 has been completed.

0 A loss of offsite power occurred 5 minutes ago.

0 It has been 30 minutes since the Reactor tripped.

0 OP-TM-AOP-020, Loss of Station Power is in progress.

Task Standard: The SBO Diesel Generator has energized both 1C 4160V Bus and 1J 480V Bus and GN-P-1 is operating.

Required Materials: OP-TM-864-901 signed off through step 3.3.2 and all of Sections 4.1 and 4.2 marked N/A.

OP-TM-AOP-020 Attachment 1 Section 4.3 (ONLY)

General

References:

OP-TM-AOP-020, Loss of Station Power, Revision 6 OP-TM-864-901, Revision 2, SBO Diesel Generator Operations, Revision 4 2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet L Initiating Cue: The Control Room Supervisor has directed you to energize 1C 4160V Bus in accordance with OP-TM-864-901, SBO Diesel Generator Operations, Section 4.3.

Time Critical Task: NO Validation Time: 15 minutes 2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet 1

SIMULATOR SETUP Exam Setup: IC 255 -OR-IC 16 and perform the following:

0 Insert the following Malfunctions to control EFW:

IMF FW19A 19 EF-V-30A is at 19%

IMF FW19B 19 EF-V-30B is at 19%

IMF FW19C 0 EF-V-30C is at 0%

IMF FW19D 0 EF-V-30D is at 0%

0 Insert the following to set the voltage and frequency for the SBO Diesel SET EGNSBOSET 865 Lowers output frequency to 57.5 Hz (Normal 900.590)

IRF EGR24 55 SBO Output Voltage set to approximately 4.2 KV.

0 Insert the following for Electrical Blackout IMF ED01 0 OPEN MU-V-14A 0 Start MU-P-lA, DC-P-lA, and DR-P-1A.

0 Start IA-P-1A.

0 Verify IA-V-2104NB OPEN 0 Insert the following to Fail GN-P-2 IOR ZDICSGNP2[2l OFF IOR ZDlCSGNP2[!5l ON 0 Ensure a fire pump is operating.

0 Initiate Global Silence.

0 Freeze the Simulator.

0 Verify Visual Effects are enabled.

0 Snap setup into IC 255 2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluators Cue: Provide a copy of OP-TM-864-901, marked up IAW instruction on the cover page.

Performance Step: 1 Verify 1C 4160V bus is de-energized.

Standard: Reads CAUTION prior to Step 1: Starting EG-Y4 before the loads to be applied to the 1C 4160V bus have been determined may result in diesel damage. Avoid diesel operation for an extended period of time without load.

Verifies no voltage on 1C 4160V bus at meter on panel PR.

Comment:

Performance Step: 2 Verify FS-P-1, FS-P-2 OR FS-P-3 is operating.

Standard: Verifies Fire Service header pressure on panel PL.

Comment:

4 Performance Step: 3 CLOSE Tl-C2.

Standard: Closes T1-C2 by turning pistol grip clockwise and verifies red light illuminates.

Comment:

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Ensure the following breakers are OPEN:

a. 1SA-C2

b. 1SB-C2 C. 1J-02

d. 1K-02

e. 1L-02

f. 1M-02 Standard: Opens/checks open the following breakers by verifying green lights illuminated:

a. 1SA-C2 SAT

b. 1SB-C2 SAT C. 1J-02 SAT

d. 1K-02 SAT

e. 1L-02 SAT

f. 1M-02 SAT

- Comment:

Performance Step: 5 Place the following breakers in PTL:

a. CW-P-1C

b. CW-P-1F

c. co-P-1c

d. CO-P-2C

e. HD-P-1C Standard: Places the pistol grip in PTL for the following breakers:

a. CW-P-1C SAT

b. CW-P-1F SAT

c. co-P-IC SAT

d. CO-P-2C SAT

e. HD-P-1C SAT Comment:

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 6 Press SBO Diesel Generator Start PB.

Standard: Starts SBO DG as indicated by running light illuminated.

Comment:

Note: May request an A 0 to go to SBO diesel. Role play as necessary.

Performance Step: 7 If generator voltage is NOT between 4.1 and 4.3 KV, then adjust Unit Voltage Rheostat (SBO: Inside rear of Exciter Control Cabinet, Key 21).

Standard: Verifies voltage 4.1KV - 4.3KV.

Comment:

4 Performance Step: 8 If generator frequency is NOT between 59 and 61 Hz, then adjust governor.

Standard: Recognizes Generator Frequency outside band and adjusts governor to obtain 59 - 61 Hz.

Comment:

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION J Performance Step: 9 Close G2-12 (EG-Y-4 output breaker).

Standard: G2-12 is closed as indicated by red light illuminated.

Comment:

Evaluators Cue: 0 When I C 4160V Bus is energized, direct the candidate to energize 1J 480V Bus IAW OP-TM-AOP-020, Attachment 1, Section 4.3.

All PREREQUISITES are met.

0 Provide a copy of OP-TM-AOP-020 Attachment 1, Section 4.3.

Performance Step: 10 Place the following switches in PTL:

a. EHC-P-1B

b. GN-P-5B C. IA-P-4

-- d. SC-P-1B Standard: The pistol grips for the following are in PTL:

a. EHC-P-1B SAT

b. GN-P-5B SAT C. IA-P4 SAT

d. SC-P-1B SAT Comment:

Performance Step: I 1 OPEN 1D TURBINE PLANT MCC Unit 4D for SA-P-1B Standard: Contacts A 0 to open breaker SA-P-1B.

Comment:

Evaluator or Booth Breaker SA-P-1B breaker (1D TP MCC Unit 40) is OPEN.

Operator Cue:

I C 0 04AZOSO9-ZLOSAP 1B(1) GRN SAP1B OFF 2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 12 If I C 4160V bus is energized, CLOSE 1J-02.

Standard: Closes 1J-02 as indicated by red light illuminated.

Comment:

4 Performance Step: 13 When 1J 480V bus is energized:

IAAT GN-P-2 is NOT operating, then start GN-P-1.

Standard: Using the pistol grip, starts GN-P-1 as indicated by red light illuminated.

Comment:

Terminating Cue: When GN-P-1 is running: This JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM F Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: 0 The plant was experiencing problems with the grid.

0 The Turbine tripped due to the power load unbalance relay actuating.

0 The Turbine Trip resulted in a Reactor Trip.

0 OP-TM-EOP-001 has been completed.

0 A loss of offsite power occurred 5 minutes ago.

0 It has been 30 minutes since the Reactor tripped.

0 OP-TM-AOP-020, Loss of Station Power is in progress.

INITIATING CUE: The Control Room Supervisor has directed you to energize 1C 4160V Bus in accordance with OP-TM-864-901, SBO Diesel Generator Operations, Section 4.3.

2005 NRC JPM F NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet

-. Facility: Three Mile Island Task No.: 0120090101 Task

Title:

Reset Reactor Protection JPM No.: 2005 NRC JPM G ChannelM after a Trip WA

Reference:

012 A4.04 3.3 / 3.3 Facility Bank JPM 124 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

- Initial Conditions: Both Main Feedwater Pumps Tripped resulting in a Reactor Trip.

Hot Shutdown conditions have been established in preparation for plant recovery.

The "A" RPS Cabinet tripped during the plant transient.

Task Standard: "A"RPS cabinet reset.

Required Materials: OP-TM-641-421 with Section 3.3 and steps 5.1 and 5.2 initialed.

General

References:

OP-TM-641421, Tripping and Resetting RPS Channels, Revision 0 Initiating Cue: The Control Room Supervisor directs you to reset RPS Channel "A" IAW OP-TM-641-421. Assume that all PRECAUTIONS, LIMITATIONS, AND PREREQUISITES are met and that Steps 5.1.1 and 5.2 have been completed.

Time Critical Task: N/A Validation Time: 10 minutes 2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Exam SetuD: IC 254 Any "At Power" Initial Condition.

Trip the reactor (do NOT use the DSS pushbutton) and allow RCS pressure to stabilize greater than 1900 psig.

In the " A RPS Cabinet, ensure the following are tripped:

> Lo Press Trip bistable

> Reactor Trip Subsystem EVENT TRIGGERS: NIA MALFUNCTIONS: NIA REMOTE FUNCTIONS: NIA OVERRIDES: NIA MONITOR: NIA 2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Locate procedure.

Standard: Locates OP-TM-641-421 and determines Section 5.0 applies.

Comment:

Evaluators Cue: Provide a copy of the procedure marked up in accordance with the cover page instructions.

Performance Step: 2 Perform ATTACHMENT 7.1:

+/PN bistable.

Standard: Verifies +/PN bistable reset as indicated by the OUTPUT STATE

__ and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment: ATTACHMENT 7.1 corresponds to JPM Steps 2 - 15.

Performance Step: 3 POWER IMBALANCE FLOW bistable.

Standard: Verifies POWER IMBALANCE FLOW bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Performance Step: 4 Check HIGH BLDG. PRESS. Contact buffer.

Standard: Presses TEST Reset and/or verifies INPUT STATE lamps extinguished.

Comment:

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 5 HIGH FLUX TRIP bistable.

Standard: Verifies HIGH FLUX TRIP bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Performance Step: 6 FLUX > 10% FP bistable.

Standard: Verifies FLUX > 10% FP bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Performance Step: 7 TURB TRIP BYPASS bistable.

Standard: Verifies TURB TRIP BYPASS bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Performance Step: 8 RNP TRIP BYPASS bistable.

Standard: Verifies FWP TRIP BYPASS bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION L

Performance Step: 9 TURB TRIP Contact Buffer.

Standard: If > 45% NI Power, then verify Input State Lamp OFF (N/A STEP

- NOT > 45% Power).

Comment:

Performance Step: 10 FWP TRIP Contact Buffer.

Standard: If > 7% NI Power, then verify input State Lamp OFF (N/A Step -

NOT > 7% power).

Comment:

Performance Step: 11 SHUTDOWN BYPASS bistable.

Standard: N/A - not in S/D Bypass.

Comment:

Evaluator Cue: If necessary - Shutdown Bypass is NOT selected.

Performance Step: 12 HI PRESS Trip bistable.

Standard: Verifies HIGH PRESSURE TRIP bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

2005 NRC JPM G NUREG 1021. Revision 9

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 13 LOW PRESS Trip bistable.

Standard: Momentarily depresses the reset toggle switch for LO PRESS Trip bistable and verifies reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Evaluator Note: When this step is performed the RTM sub-system trip lamp will go dim.

Performance Step: 14 PRESSlTEMP trip bistable.

Standard: Verifies PressurelTemperature trip bistable reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

Performance Step: 15 HI TEMP Trip bistable.

Standard: Verifies HIGH TEMPERATURE TRIP reset as indicated by the OUTPUT STATE and OUTPUT MEMORY lamps illuminating in the DIM condition.

Comment:

4 Performance Step: 16 Press Reactor Trip Module (RTM) SUBSYSTEM Reset Switch.

Standard: Depresses reset toggle switch for Channel A.

Comment:

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 17 Verify the following:

RTM SUBSYSTEM TRIP lamp dim.

0 PROTECTIVE SUBSYSTEM lamp on outside of each RPS cabinet is dim.

Standard: 0 Verifies RTM SUBSYSTEM TRIP lamp dim.

Verifies PROTECTIVE SUBSYSTEM lamp on outside of each RPS cabinet is dim.

Comment:

Terminating Cue: After verifying lamps outside Channel A cabinet(s): This JPM is complete.

STOP TIME:

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM G Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET

\

INITIAL CONDITIONS: 0 Both Main Feedwater Pumps tripped resulting in a Reactor Trip.

0 Hot Shutdown conditions have been established in preparation for plant recovery.

0 The " A RPS Cabinet tripped during the plant transient.

INITIATING CUE: The Control Room Supervisor directs you to reset RPS Channel

" A IAW OP-TM-641-421. Assume that all PRECAUTIONS, LIMITATIONS, AND PREREQUISITES are met and that Steps 5.1.1 and 5.2 have been completed.

2005 NRC JPM G NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: 0000580504 Task

Title:

ResDond to Loss of A DC Bus JPM No.: 2005 NRC JPM I WA

Reference:

063 G2.1.30 3.9 I 3.4 Facility Bank JPM 067 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

Simulated Performance: X Act uaI Performance :

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: 0 The plant is at 100% power.

A loss of the entire A DC distribution system just occurred.

The operating crew has implemented EP 1202-9A, Loss of A DC Distribution System.

EG-Y-1A was in parallel with 1D 4160V bus and loaded for its monthly surveillance run IAW 1303-4.16 when the loss of A DC occurred.

Task Standard: Complete all Immediate Manual Actions of 1202-9A.

Required Materials: 1202-9A General

References:

1202-9A, Loss of ADC Distribution System, Revision 44 Initiating Cue: Another operator has been dispatched to DC Switchgear to investigate the cause. Perform the immediate MANUAL actions of 1202-9A for the affected Emergency Diesel Generator.

Time Critical Task: NIA Validation Time: 20 minutes 2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP:

NIA 2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Evaluator Note: The candidate may selectlrequest safety equipment required for entering the room of a running EDG. If so: Assume that you are wearing the proper safety equipment for a running EDG.

The candidate is expected to perform the immediate manual actions from memory. At the conclusion and if requested, provide a copy of 1202-9A and allow time to verify actions.

Self-correction of errors meets the critical task requirement.

4 Performance Step: 1 Close EG-V-15A to allow lube oil booster pump to refill and starting air receiver to re-pressurize.

Standard : EG-V-15A is located and closed by rotating the handle 90.

Comment:

Evaluators Cue: Inform candidate that EG-V-15A is closed if correctly located and operated.

Performance Step: 2 Verify starting air pressure gages EG-PI-535AIB labeled Starting Air Pressure on the Engine Mounted Instrument Panel (EMIP) decrease to 0 psig.

Standard: EG-PI-535NB labeled Starting Air Pressure on the Engine Mounted Instrument Panel located and pressure verified as decreasing to 0 psig.

Comment:

Evaluators Cue: As each gage is located (EG-PI-535A and EG-PI-535B):

Indication is decreasing to 0 psig.

2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 3 Trip EG-Y-1A fuel rack.

Standard: EG-Y-1A fuel rack trip pushbutton located and depressed.

Comment:

Evaluators Cue: Inform candidate that the fuel rack is tripped if correctly located and tripped.

4 Performance Step: 4 Manually trip generator breaker G1-02.

Standard: Manual pushbutton depressed on BDD at breaker 1D2 on 1D 4160V Bus Comment:

Evaluators Cue: Inform candidate that breaker G I 4 2 indicates tripped if correctly located and tripped.

4 Performance Step: 5 Transfer Excitation Control Alternate Power Supply to B DC power Standard: Simulates opening Alterrex Cabinet door and rotates selector switch to B side DC power.

Comment: Controlled Key # 22 is required to open the Alterrex Cabinet on the 322 elevation in the 4KV switchgear room.

Evaluators Cue: Inform candidate that the Excitation Control Alternate Power supply is transferred to B DC.

Terminating Cue: After the excitation power is transferred: This JPM is complete.

STOP TIME:

2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM I Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT ExaminersSignature: Date:

2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: 0 The plant is at 100% power.

A loss of the entire ADC distribution system just occurred.

0 The operating crew has implemented EP 1202-9A, Loss of A DC Distribution System.

0 EG-Y-1A was in parallel with 1D 4160V bus and loaded for its monthly surveillance run IAW 1303-4.16 when the loss of A DC occurred.

INITIATING CUE: Another operator has been dispatched to DC Switchgear to investigate the cause. Perform the immediate MANUAL actions of 1202-9A for the affected Emergency Diesel Generator.

2005 NRC JPM I NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-I Worksheet

\ Facility: Three Mile Island - Unit 1 Task No.: 0000600501 Task

Title:

Take Corrective Action For An JPM No.: 2005 NRC JPM J Unauthorized Waste Gas Release WA

Reference:

System 071 G2.1.30 3.9 / 3.4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testina:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The unit is at 100% power.

0 An authorized release is in progress from Waste Gas Decay Tank "A".

0 Three sets of readings have been completed on 1104-27, Waste Disposal - Gaseous, ENCLOSURE 2.

Task Standard: Release alignment terminated.

Required Materials: N/A General

References:

1104-27, Waste Disposal - Gaseous, Revision 73 Initiating Cue: Perform the fourth set of 1104-27, ENCLOSURE 2 readings at the local' panel.

Handouts: 1104-27, ENCLOSURE 2, with three sets of prior readings 1104-27, Section 3.17 (to be provided to candidate after the problem is recognized) 2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet

- Time Critical Task: N/A Validation Time: 10 minutes 2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION

\

(Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Review handout.

Standard: Reviews 1104-27, ENCLOSURE 2 Comment:

Evaluators Cue: Provide a copy of ENCLOSURE 2 with three sets of prior readings.

Performance Step: 2 Enter the RCA and proceed to the Waste Gas Panel.

Standard: Observes proper RCA entry requirements and locates Waste Gas Panel.

Comment:

Evaluators Cue: Locate each instrument or simulate communications and I will then provide a reading value.

Evaluators Note: As each instrument is located or the control room is contacted, provide the instrument reading cues as listed for Time 4 on the attached EVALUATOR ENCLOSURE 2.

2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Locate each instrument on the local panel and simulate contacting the control room for the radiation monitor readings.

Standard: 0 Logs readings.

0 Recognizes unexplained pressure drop in Waste Gas Decay Tank 6.

0 Informs control room.

0 Implements section 3.17.

Comment:

Evaluators Cue: Provide a copy of 1104-27, Section 3.17 when necessary and as shift management, direct the candidate to implement the required actions.

Performance Step: 4 Bleed off air from WDG-V-47.

Standard: Bleeds off air from WDG-V-47 by turning the control valve (knob) on the panel in the counter-clockwise direction.

Comment:

Evaluators Cue: The WDG-V-47 bleed control valve is open and pressure is lowering to ZERO.

4 Performance Step: 5 Close WDG-V-47 by depressing the CLOSE pushbutton (PB).

Standard: Depresses WDG-V-47 CLOSE PB and verifies closed indication.

Comment:

Evaluators Cue: If the bleed valve was opened in the previous step -

WDG-V-47 indicates closed.

2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Reset WDG-FR-123 setpoint to ZERO.

Standard: Adjusts WDG-FR-123 setpoint to ZERO Comment:

Evaluators Cue: WDG-FR-123 is set at ZERO.

4 Performance Step: 7 Close and lock closed the applicable manual outlet valve on the tank being released. (N/A the valves not open.)

0 WDG-V-30 for WDG-T-1A 0 WDG-V-31 for WDG-T-1 B WDG-V-32 for WDG-T-1C Standard : 0 Locates and simulates closing WDG-V-30 by turning it in the clockwise direction.

0 Discusses re-installing the locking device.

0 May choose to locate and simulate checking WDG-V-31 closed.

Comment: Closing WDG-V-30 is the critical task.

Evaluators Cue: Provide valve closed and locking device status cues for any valve operated.

Performance Step: 8 Notify the control room to update the locked valve entry.

Standard :

Comment:

Terminating Cue: After the control is notified to update the locked valve entry, this JPM is complete.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM J Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2005 NRC JPM J NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITlAL CONDITIONS: The unit is at 100% power.

0 An authorized release is in progress from Waste Gas Decay Tank A.

0 Three sets of readings have been completed on 1104-27, Waste Disposal - Gaseous, ENCLOSURE 2.

INITIATING CUE: Perform the fourth set of 1104-27, ENCLOSURE 2 readings at the local panel.

2005 NRC JPM J NUREG 1021. Revision 9

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No Waste DisDosal - Gaseous 73 ENCLOSURE 2 Page 1 of 1 Waste Gas Release Data Sheet Permit

1. If a l any time any other gas tank has an unexplained pressure decrease other than the tank being released then perform the following. (N/A this step if no pressure drop occurs)

Inform Shift Management of the problem.

G o to section 3.17 to terminate the gas release.

Release Complete Opera tor Signa tu re Date

1 Number TMI - Unit 1 Operating Procedure I 104-27 Title Revision No.

Waste DisDosal Gaseous I 73 ENCLOSURE 2 Page 1 of 1 Waste Gas Release Data Sheet Permit 1 if at any time any other gas tank has an unexplained pressure decrease other than the tank being released then perform the following: (NIA this step if no pressure drop occurs)

Inform Shift Management of the problem.

Go to section 3.17 to terminate the gas release Release Complete 0 perat or Signature Date

~~

Appendix C Job Performance Measure Form ES-C-1 Worksheet

- Facility: Three Mile Island Task No.: 056A010104 Task

Title:

Place 8thStaqe Heatinq On-Line JPM No.: 2005 NRC JPM K K/A

Reference:

039 G2.1.30 3.9 / 3.4 Facility Bank JPM 099 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

1 Initial Conditions: 0 A plant startup is in progress following a maintenance outage.

0 The feedwater system is cold.

Task Standard: 8h Stage Feedwater Heating String A in Service.

Required Materials: OP-TM-421-102 with all Prerequisites signed.

General

References:

OP-TM-421-102, Placing 8 Stage Feedwater Heating String A in Service, Revision 0 Initiating Cue: Place 8h Stage Feedwater Heating String A in service in accordance with OP-TM-421-102. Assume that you have all required equipment.

Time Critical Task: NIA Validation Time: 15 Minutes 2005 NRC JPM K NUREG 1021, Revision 3

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION 1

(Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Locates procedure.

Standard: Locates OP-TM-421-102 and verifies PREREQUISITES are signed.

Comment:

Evaluators Cue: Provide a copy of the procedure marked up in accordance with the cover sheet directions.

Performance Step: 2 Proceeds to the 8h stage heating panel.

Standard: Located directly north of the 8hstage heaters 4h floor turbine building.

Comment: May establish communications at this time.

Performance Step: 3 Verify the following:

AS-V-1A AUTO/MANUAL station is in MANUAL and 0 psig setting on the manual gauge.

AS-V-1 B AUTO/MANUAL station is in MANUAL and 0 psig setting on the manual gauge.

Auxiliary Steam Heating Switch to OFF (AS-V-1114).

Standard: AS-V-1A and AS-V-1B AUTO/MANUAL stations in MANUAL with 0 psig on the manual gauge.

Auxiliary Steam Heating Switch to OFF(AS-V-1114)

Comment:

Evaluators Cue: If the as found condition is different than above then provide the necessary feedback when the proper position is selected.

2005 NRC JPM K NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION d Performance Step: 4 Open AS-V-213A.

Standard : Locates and opens AS-V-213A by rotating the handwheel in the counter-clockwise direction.

Comment:

Evaluators Cue: The valve has stopped rotating in the counter-clockwise direction.

d Performance Step: 5 Open AS-V-13A.

Standard: Locates and opens AS-V-13A by rotating the handwheel in the counter-clockwise direction.

Comment:

Evaluators Cue: The valve has stopped rotating in the counterclockwise direction.

Performance Step: 6 Establish communications between the CR and the Auxiliary Boiler Operator.

Standard: Simulates radio contact.

Comment:

Evaluators Cue: When the candidate simulates establishing communications, inform himlher that communications are established and you will provide all feedback.

2005 NRC JPM K NUREG 1021. Revision 3

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 7 Open CO-V-375B.

Standard: Locates and opens CO-V-375B by rotating the handwheel in the counter-clockwise direction.

Comment:

Evaluators Cue: The valve has stopped rotating in the counterclockwise direction.

Performance Step: 8 Contacts Control Room to close CO-V-3B.

Locally verify valve closed.

Standard: Locates and verifies CO-V-3B closed or describes indication that the valve is closed.

Comment:

Evaluators Cue: CO-V3B indicates closed.

Performance Step: 9 Contacts control room to verify closed the following:

EX-V-5A EX-V-5B EX-V-5C EX-V-5D Standard: Contacts control room to verify EX-V-5A through D closed or performs local position verification.

Comment:

Evaluators Cue: EX-VdA, ByC, and D are all closed.

d performance Step: 10 Place AS-V-1114 to ON (Auxiliary Steam Heating Switch).

Standard: Selects Auxiliary Steam Heating Switch to the ON position.

Comment:

2005 NRC JPM K NUREG 1021, Revision 3

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

.- Evaluators Cue: If the as found condition is different than above then provide the necessary feedback.

.I Performance Step: 11 Slowly raise AS-V-1A MANUAL LOADER setting until steam flow is established.

Standard: AS-V-1A MANUAL LOADER setting is slowly raised until steam flow is established and then held at that point.

Comment:

Evaluators Cue: If steamlcontrols alignment has been performed properly then - the Auxiliary Boiler Operator reports that boiler steam flow is slowly rising.

Terminating Cue : When steam flow is established and being held, this JPM i s complete.

STOP TIME: TIME CRITICAL STOP TIME:

2005 NRC JPM K NUREG 1021. Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2005 NRC JPM K Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2005 NRC JPM K NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: 0 A plant startup is in progress following a maintenance outage.

0 The feedwater system is "cold".

INITIATING CUE: Place 8'h Stage Feedwater Heating String "A" in service in accordance with OP-TM-421-102. Assume that you have all required equipment.

2005 NRC JPM K NUREG 1021. Revision 9