ML083540411

Draft - Section B Operating Exam (Folder 2)

ML083540411
Person / Time
Site:	Peach Bottom
Issue date:	11/10/2008
From:	Kelly M Exelon Generation Co
To:	Todd Fish Operations Branch I
Hansell S
Shared Package
ML081060602	List: IR 05000277/2009301 ML082200014 ML083390459 ML083530477 ML083540094 ML083540178 ML083540401 ML083540411 ML083540454 ML090220315 ML090290221 ML090290223 ML090290224 ML090290228 ML090330087
References
TAC U01776
Download: ML083540411 (90)

Text

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

-1 F I CAT1 0 N MAN U A L OJT MODULE APPROVALS:

Signature /Title Date Signature /Title Dak Signature / Title Date Signature / Title Date 11 APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

I I

II NAME:

Last First M.I.

SOC. SEC. NO.

COMMENTS:

ISSUE DATE:

COMPLETION DATE:

Training Review for Completeness:

PlMS CODE:

Signature/Date I

ENTRY:

2008 NRC JPM CR-a(4) (PLOR309CA Rev01 1) Recirc Pp Start-I Page 1 of 7

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-309CA REV. NO.: 011 TITLE:

STARTING A RECIRCULATION PUMP (ALTERNATE PATH - SCOOP TUBE LOCKUP)

TCF #

TCF DATE CHANGED SECTION #

1.

2.

3.

4.

5.

6.

7.

8.

9.

I O.

11.

12.

13.

14.

15.

2008 NRC JPM CR-a(4) (PLOR309CA Rev01 1) Recirc Pp Start-I Page 2 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 20200401 01 / PLOR-309CA WA:

202001A4.01 Unit Reactor Operator/Senior Reactor Operator RO: 3.7 SRO: 3.7 TAS K D E SC R I PT I 0 N :

STARTING A RECIRCULATION PUMP (ALTERNATE PATH - SCOOP TUBE LOCKUP)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management a p prova I.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPhAs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-a(4) (PLOR309CA Rev01 1) Recirc Pp Start-I Page 3 of 7

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT None REFERENCES SO 2A.1.B-2, Rev. 45, Starting the Second Recirculation Pump TASK STANDARD

1.

Performance Location: Simulator

2.

Satisfactory task completion is indicated when the B Reactor Recirculation Pump has been started and subsequently tripped due to a scoop tube lockup.

3.

Estimated time to complete: 14 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to start the B Reactor Recirculation Pump using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1.

The 2B Recirculation pump is being placed in service following a spurious trip.

2.

All the prerequisite steps of SO 2A.1.B-2, Starting the Second Recirculation Pump have been successfully performed.

3.

Steps 4.1 through 4.25 of SO 2A.1.B-2, Starting the Second Recirculation Pump have been successfully performed.

4.

ST-0-02B-510-2, Reactor Coolant Temperatures has been performed. Data from ten minutes ago showed reactor dome to bottom head drain DT is 80°F and the loop to loop DT is 23°F.

5. An Equipment Operator is in place to visually verify relays at Panel 2BC152.

INITIATING CUE The Control Room Supervisor directs you tcu start the B Reactor Recirculation Pump in accordance with SO 2A.1.B-2, Starting the Second Recirculation Pump, beginning at step 4.26.

2008 NRC JPM CR-a(4) (PLOR309CA RevOll) Recirc Pp Start-I Page 4 of 7

H.

PERFORMANCE CHECKLIST I1 STEP I STEP I ACT I STANDARD NO Verify reactor coolant temperatures stated in step 4.17.1 and 4.17.2 are still valid.

(Cue: ST-0-02B-510-2, "Reactor Coolant Temperatures" were performed satisfactorily I O minutes ago. Reactor dome to bottom head drain DT is 80°F I

1 P

r p

Obtain a copy of procedure SO 2A.l.B-2.

"6" Recirc MG Set Drive Motor Breaker control switch is momentarily placed in the START position at panel 20C004A.

A copy of procedure SO 2A.1.B-2 is obtained.

~

• • • NOTE ***

The next step is not applicable if the 'A' Recirc pump speed is already less than 50%. This will depend on simulator initial conditions used.

• 2 3

• 4 Lower "AI Recirc pump speed to less than 50% as read on SPI-2-02-184-016A.

(Cue: SPI-2-02-184-016A is lowering, FR-2-02-154 is lowering, and reactor level is stable.)

Verify the speed of the "AI Recirc pump is less than 50%.

(Cue: SPI-2-02-184-016A indicates 45%.)

Verify closed MO-2-02-053BI Recirc Pump B Discharge Valve.

(Cue: MO-2-02-053B green light is on, red linht is off.)

P Manual control knob is turned COUNTERCLOCKWISE until SPI-2-02-184-016A indicates 50% at panel 20C004A.

This step may not be applicable if initial conditions have the 'A' Recirc. Pump speed already less than 50%.

"Aw Recirc pump speed is verified tcr be less than 50% on SPI-2-02-184-01 ;A at panel 20C004A.

MO-2-02-053B green light is verifieil ON at panel 20C004A.

• • • NOTE ***

Nhen ready to perform a plant announcement to start the Recirc. Pump, inform the Examinee to

@ make the announcement if another JPM is being conducted simultaneously in the simulator.

5

• 6 P

Verifies that ST-0-02B-510-2, "Reactor Coolant Temperatures" were perforlmed within the last 15 minutes indicating that Reactor dome to bottom head drain DT is c 145°F AND the loop to loop DT is 40°F.

I flashing.) I 2008 NRC JPM CR-a(4) (PLOR309CA Rev01 1) Recirc Pp Start-I Page 5 of 7

7 Direct an Equipment operator to verify that relay 2-2A-KO15B de-energized 6 seconds after the field breaker closes.

STEP P

Direct an operator to verify that relay 2-2A-KO1 5B is energized.

(Cue: Equipment operator acknowledges the direction and reports that relay 2-2A-K015B is eneraized.)

Direct an operator to verify that relay 2-2A-K022B energizes 20 seconds after the drive motor starts.

(Cue: Equipment operator acknowledges the direction and reports that relay 2-2A-K022B energized 20 seconds after the drive motor start.)

Verify the "B" Recirc MG Set drive motor starts, generator speed reached 100%

and field breaker closes in 21 seconds.

(Cue: "B" Recirc MG Set Drive Motor Breaker red light is on, green light is off.

SPI-2-02-184-16B indicates an increase to 100%. 21 seconds later, "B" Recirc MG Set Field Breaker red light is on, green liaht is off.)

ACT P

P P

STANDARD Equipment operator directed to verify relay 2-2A-KO15B is energized.

Equipment operator directed to verify rela) 2-2A-K022B energizes 20 seconds after the drive motor starts.

"B" Recirc MG Set Drive Motor Breaker red light is verified ON, MG Set speed is verified to increase to 100% on SPI-2-02-184-16B and the "B" Recirc MG Set Field Breaker red light is verified ON a panel 20C004A.

• • • NOTE ***

The next step may not be performed if the examinee decides to trip the '6' Recirc. Drive Motor first.

10

• I 1 I

(Cue: Equipment operator acknowledges the direction and reports that relay 2-2A-KO1 5B de-energized 2 seconds after the field breaker closes.)

When the field circuit breaker closes, the "B" RECIRC FLUID DRIVE SCOOP TUBE LOCK and "B" RECIRC FLUID DRIVE SCOOP TUBE POSITIONER TROUBLE annunciators a re recognized alarm ing.

(Cue: As soon as the field circuit breaker closes, SPI-2-02-184-016B reading drops to 40% and annunciators 213 C-3 and 214 J-I begin flashing.)

P Equipment operator directed to verify rela) 2-2A-KO15B de-energized 2 seconds after the field breaker closes.

This step may not be performed if the Examinee decides to immediately perform steps 11 & 12.

Recognizes "B" RECIRC FLUID DFWE SCOOP TUBE LOCK and "B" RECjRC FLUID DRIVE SCOOP TUBE POSITIONER TROUBLE annunciaiors art flashing at panels 213 C-3 and 214 J-I.

2008 NRC JPM CR-a(4) (PLOR309CA Rev01 1) Recirc Pp Start-I Page 6 of 7

• I2 13 14 STEP Trip the "B" Recirc Pump Drive Motor (Cue: "B" Recirc Pump Drive Motor breaker green light is on, red light is off.)

Inform Control Room Supervisor of the receipt of the "B" RECIRC FLUID DRIVE SCOOP TUBE LOCK alarm and trip of the "Bll Recirc Pump.

(Cue: Control Room Supervisor acknow-ledaes rePort.)

As evaluator ensure you have positive control of all exam material provided to the examinee (Task Condition / Prerequisites)

AND procedures.

ACT P

STANDARD "B" Recirc Pump Drive Motor breaker control switch is momentarily placed in the STOP position at panel 20C004A.

Receipt of the "B" RECIRC FLUID DRIVE SCOOP TUBE LOCK alarm and trip of the "B" Recirc Pump reported to CRS.

Positive Control established.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE When the "B" Recirculation Pump has been started and subsequently tripped due to a scoop tube lockup, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-a(4) (PLOR309CA RevOll) Recirc Pp Start-I Page 7 of 7

TASK CONDITIONS/PREREQUISlTES

1. The "2B" Recirculation pump is being placed in service following a spurious trip.

2. All the prerequisite steps of SO 2A.1.B-2, "Starting the Second Recirculation Pump" have been successfully performed.

3. Steps 4.1 through 4.25 of SO 2A.l.B-2, "Starting the Second Recirculation Pump" have been successfully performed.

4. ST-0-026-510-2, "Reactor Coolant Temperatures" has been performed. Data from ten minutes ago showed reactor dome to bottom head drain DT is 80°F and the loop to loop DT is 23°F.

5. An Equipment Operator is in place to visually verify relays at Panel 2BC152 INITIATING CUE The Control Room Supervisor directs you to start the "B" Reactor Recirculation Pump in accordance with SO 2A.l.B-2, "Starting the Second Recirculation Pump", beginning at step 4.26.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:

I Signature /Title Date Signature / Title Date

~

Signature I Title Date Signature / Title Date 11 APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

I I

II NAME:

Last First MI. 1 ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

PlMS CODE:

SignatureIDate 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I Page 1 of 7

TEMPORARY CHANGE FORM LOG

1.

CODE NO.: PLOR-300CA REV. NO.: 013 TITLE:

Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails to Opt-&rate)

2.

3.

4.

5.

6.

7.

8.

9.

IO.

11.

12.

13.

14.

15.

1 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I

z of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 20600501 01 / PLOR-300CA WA:

295031 EA1.02 URO: 4.5 SRO: 4.5 TASK DESCRIPTION:

Manuallv Initiate HPCI (Alternate Path - Manual Initiation P u s h b u m Fails to Operate)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available!.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

I )

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-b(1) (PLOR300CA Rev013) HPCI PB Fails-I 3 of 7

B.

TOOLS AND EQUIPMENT I.

None

2.

REFERENCES

1.

RRC 23.1-2, Rev. 5, HPCI System Operation During A Plant Event D.

TASK STANDARD

1.

Satisfactory task completion is indicated when HPCl is injecting to the RPV at 5000 gpm.

2.

Estimated time to complete: 5 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to manually initiate the HPCl system and inject to the Reactor vessel at a flow rate of 5000 gpm using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TAS K C 0 N D IT I 0 N S/P RE R E Q U I S IT E S

1.

RPV Level is -25 inches and lowering slowly G.

INITIATING CUE The Control Room Supervisor directs you to initiate the HPCl system using the HPCl Manual Initiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2 HFCI System Operation During A Plant Event 2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 4 of 7

H.

PERFORMANCE CHECKLIST fi NO 1

2 "3

STEP Obtain copy of RRC 23.1-2 "HPCI System Operation During A Plant Event" Arm and depress the HPCl Manual Initiation Pushbutton 23A-SI 05.

(Cue: Acknowledge pushbutton operation.)

Recognize that the Manual Initiation pushbutton did not function.

(Cue: HPCl discharge pressure, flow and speed indicate zero. Aux oil pump green light is on, red light is off.)

ACT P

P P

STANDARD References Section A "HPCI Injection Using Manual Initiation Push-buttot Y.

HPCl Manual Initiation Pushbutton collar is rotated clockwise to the ARMED position and then the pushbutton is momentarily DEPRESSED at pane, 20C004B.

Manual Initiation pushbutton failure to function is recognized.

• • • • NOTE****

IF NEEDED, REPEAT INITIATING CUE TO GET EXAMINEE TO CONTINUE The Control Room Supervisor directs you to initiate the HPCl system using the HPCl Manual lnitiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2 "HPCI System Operation During A Plant Event"

• • • • NOTE****

Steps 4 through 11 can be performed by the Examinee using either RRC Section A "HPC Injection Using Manual Initiation Push-button" QB RRC Section B "HPCI Injection By Manual Component Operation".

• 4 5

I L

Simultaneously start the Auxiliary Oil Pump, 20P026 and open MO-2-23-014 "Supply" va Ive.

(Cue: Acknowledge control switch operation.)

Verify the Auxiliary Oil Pump started.

(Cue: Auxiliary Oil pump red light is on green light is off and annunciator 222 D-5 is alarming, "HPCI AUXILIARY OIL PUMP RUNNING", Turbine Stop and Control valve red lights are on.)

P P

Auxiliary oil pump control switch is placed in the START position while simultaneously placing MO-2-23-014 "Supply" control switch momentarily in the "OPEN" position at panel 20C004B.

Verify the Auxiliary Oil pump red light is ON at panel 20C004B or annunciator 222 D-5 is alarming at panel 20C204C.

2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PI3 Fails-I 5 of 7

6

• 7 8

9 10 11 12 STEP Verify MO-2-23-014, "Supply" valve is open.

(Cue: MO-14 red light is on, green light is off, HPCl discharge pressure and speed rise.)

Open MO-2-23-019, "To Feed Line" valve.

(Cue: Acknowledge control switch operation.)

Verify MO-2-23-019, "To Feed Line" valve is open.

(Cue: MO-19 red light is on, green light is off, HPCl flow rise.)

Start the HPCl Gland Seal Condenser Vacuum Pump, 20K002.

(Cue: Vac pump red light is on, green light is off.)

Verify pump flowrate of 5000 gpm.

(Cue: Fl-2-23-108 indicates 5000 gpm.)

Adjust HPCl flow controller to maintain level.

(Cue: Level is rising into 5 to 35" band.)

Inform Control Room Supervisor that HPCl was manually started and is injectin{

into the RPV.

(Cue: Control Room Supervisor acknowledges report.)

ACT P

P P

P P

STANDARD VlO-2-23-14 red light verified ON, HPCl jischarge pressure (PI-2-23-1 09) alid iPCI speed (SPI-4505) rising at panel 20C004B.

MO-2-23-019 control switch is momentarily placed in the OPEN position at panel 20C004B.

MO-2-23-019 red light is verified ON and Flow (Fl-2-23-108) rising at panel 20C004B.

HPCl Gland Seal Condenser Vacuum Pump control switch is placed in the START position at panel 20C004B

~ _ _ _ _ _ _ _

A HPCl flowrate of approximately 5000 gpm is verified on Fl-2-23-108 at panel 2 0 COO4 B.

HPCl flow controller setpoint is adjusted as necessary to maintain vessel level 5 to 35 inches at panel 20C004B.

Task completion reported.

2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 6 of 7

13 Under ACT P - must perform S - must simulate As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

I.

TERMINATING CUE When HPCl is injecting into the Reactor vessel at a flow rate of 5000 gpm, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-b(1) (PLOR300CA RevOl3) HPCl PB Fails-I 7 of 7

TASK CONDlTlONSlPREREQUlSlTES

1.

RPV Level is -25 inches and lowering slowly.

INITIATING CUE The Control Room Supervisor directs you to initiate the HPCI system using the HPCI Manual Initiation pushbutton and inject to the Reactor vessel at 5000 gpm using RRC 23.1-2, HPCI System Operation During a Plant Event.

EXELON NUCLEAR Nuclear Generation Group NAME:

Last First M.I.

SOC. SEC. NO.

OJTITPE MATERIAL COVERSHEET ISSUE DATE:

COMPLETION DATE:

-1FICATION MANUAL OJT MODULE lves After a GP I Isolation APPROVALS:

Signature /Title Date Training Review for Completeness:

Signature / Title Date PlMS CODE:

Signature / Title Date Signature / Title Date EFFECTIVE DATE:

I I

I PlMS ENTRY:

Signature/Date 2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 1 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 2000800501 / PLOR-083C K/A:

239001A4.01 Unit Reactor Operator/Senior Reactor Operator RO: 4.2 SRO: 4.0 TASK DESCRl PTI ON :

Reopen the Main Steam Isolation Valves after a GP I Isolation A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing ln-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, c.ompletion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 2 of 7

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT None REFERENCES Procedure T-221-2, Rev. 8, Main Steam Isolation Vale Bypass TASK STANDARD

1.

2.

Estimated time to complete: 10 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reopen the MSIVs using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

Satisfactory task completion is indicated when Inboard MSIVs are open.

TAS K C 0 N D IT I 0 N S/P R E RE Q U I S IT E S

1.

2.

Main Condenser is available.

3.

RPV level is known.

4.

5.

6.

7.

8.

Use of this procedure has been directed by the TRIP procedures.

There is no indication of gross fuel failure.

There is no indication of a Main Stearn Line break.

All T-221 Tool Packages have been obtained.

Inboard and Outboard MSlVs are closed.

Steps 4.1 thru 4.5 of T-221-2, Main Steam Isolation Valve Bypass are complete.

INITIATING CUE The Control Room Supervisor directs you to perform T-221-2, Main Steam Isolation Valve Bypass steps 4.6 through 4.12 in order to reopen the MSIVs.

2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSIVs after Grp 1-1 Page 3 of 7

H.

PERFORMANCE CHECKLIST

" STEP NO 1

• 2 3

• 4 5

• 6 7

• 8 STEP Obtain a copy of procedure T-221-2.

~

~

~

~~

~~~

~

Open AO-2-02-086A "AI Outboard MSIV.

(Cue: Acknowledge control switch operation.)

Verify AO-2-02-086A "Av Outboard MSlV is open.

(Cue: AO-2-02-086A red light is on, green light is off.)

Open AO-2-02-086B "B" Outboard MSlV (Cue: Acknowledge control switch operation.)

Verify AO-2-02-0866 "6" Outboard MSlV is open.

(Cue: AO-2-02-086B red light is on, green light is off.)

Open AO-2-02-086C "C" Outboard MSIV.

(Cue: Acknowledge control switch operation.)

Verify AO-2-02-086C 'IC" Outboard MSlV is open.

(Cue: AO-2-02-086C red light is on, green light is off.)

Open AO-2-02-086D "D" Outboard MSIV.

(Cue: Acknowledge control switch operation.)

P ACT P

P P

P STANDARD A copy of procedure T-221-2 is obtained.

AO-2-02-086A control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-01.

~

AO-2-02-086A red light is verified ON at panel 2OCOO3-01.

AO-2-02-086B control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-01.

AO-2-02-0866 red light is verified ON at panel 2OCOO3-01.

AO-2-02-086C control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-01.

AO-2-02-086C red light is verified ON at panel 2OCOO3-01.

AO-2-02-086D control switch is placed in the "AUTO/OPEN" position at panes 2OCOO3-01.

2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 4 of 7

9

• I 0 11

• I 2 13 14

• I 5 STEP Verify AO-2-02-086D "D" Outboard MSlV IS open.

(Cue: AO-2-02-086D red light is on, green light is off.)

Open MO-2-02-077, Outboard Main Steam Drain valve.

(Cue: Acknowledge control switch operation.)

Verify M0-2-02-077, Outboard Main Steam Drain valve open.

(Cue: MO-77 red light is on, green light is off.)

Open MO-2-02-074, Inboard Main Steam Drain valve.

(Cue: Acknowledge control switch operation.)

Verify MO-2-02-074 Inboard Main Steam Drain valve is open.

(Cue: MO-74 red light is on, green light is Off.)

Close MO-2-02-079, Orifice Bypass to Main Cndr valve.

(Cue: MO-79 green light is on, red light is Off.)

Open MO-2-02-078, Downstream Drain valve.

(Cue: MO-78 red light is on, green light is Off.)

ACT P

P P

P P

P P

STANDARD AO-2-02-086D red light is verified C)N at panel 2OCOO3-01.

MO-2-02-077 control switch is momentarily placed in the "OPEN" position at panel 2OCOO3-03.

MO-2-02-077 red light is verified ON at panel 2OCOO3-03.

MO-2-02-074 control switch is momentarily placed in the "OPEN" position at panel 2OCOO3-03.

MO-2-02-074 red light is verified ON at panel 2OCOO3-03.

MO-2-02-079 green light is verified ON at panel 2OCOO3-03.

MO-2-02-078 control switch is momentarily placed in the "OPEN" positior at panel 2OCOO3-03.

2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 5 cf 7

STEP ACT STANDARD Verify MO-2-02-078 Downstream Drain valve is open.

MO-2-02-078 red light is verified 01"d at panel 2OCOO3-03.

16 17 18 (Cue: MO-78 red light is on, green light is Off.)

Observe pressure differential across the Inboard MSIVs.

Pressure differential across the Inboard MSlVs is determined using PI-2-06-090A(B)(C) at panel 20C005A, and "Steam Line" PR-2865 at panel 20C 008A.

Determine the difference between Reactor pressure on PI-2-06-090A(B)(C) and "Steam Line" pressure on PR-2865 on panel 20C008A.

(Cue: PI-2-06-090A(B)(C) indicates 540 psig and "Main Steam Pressure A I

and "Main Steam Pressure B" indicate 485 psig and rising slowly.)

Verify differential pressure across the inboard MSlVs is less than 150 psid.

P Differential pressure across the inboard MSlVs is verified less than 150 psig on PI-2-06-090A(B)(C) at panel 20C005A, and "Steam Line" PR-2865 at panel 20C008A.

(Cue: PI-2-06-090A(B)(C) is 400 psig and Main Steam Pressure is 300 psig.)

• I 9

~~

Open AO-2-02-080A " A I Inboard MSIV.

P AO-2-02-080A control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-0 1.

(Cue: Acknowledge control switch operation.)

20 Verify AO-2-02-080A "AI Inboard MSlV is open.

P AO-2-02-080A red light is verified ON at panel 2OCOO3-01.

(Cue: AO-2-02-080A red light is on, green light is off.)

• 2 1 Open AO-2-02-080B "6" Inboard MSlV P

AO-2-02-0806 control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-0 1.

(Cue: Acknowledge control switch operation.)

22 Verify AO-2-02-080B "Bll Inboard MSlV is open.

P AO-2-02-080B red light is verified ON at panel 2OCOO3-01.

(Cue: AO-2-02-080B red light is on, green light is off.)

L 2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSIVs after Grp 1-1 Page 6 of 7

• 2 3 24 "25 26 1

Positive control established.

STEP Open AO-2-02-080C "C" Inboard MSlV (Cue: Acknowledge control switch operation.)

Verify AO-2-02-080C "C" Inboard MSlV is open.

(Cue: AO-2-02-080C red light is on, green light is off.)

Open AO-2-02-080D "D" Inboard MSIV.

(Cue: Acknowledge control switch operation.)

Verify AO-2-02-080D "D" Inboard MSlV is open.

(Cue: AO-2-02-080D red light is on, green light is off.)

Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknow-ledges report.)

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

ACT P

P P

P P

P STANDARD AO-2-02-080C control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-01.

AO-2-02-080C red light is verified ON at panel 2OCOO3-01.

AO-2-02-080D control switch is placed in the "AUTO/OPEN" position at panel 2OCOO3-01.

AO-2-02-080D red light is verified ON at panel 2OCOO3-01.

~~

~~

Task completion reported.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE When the MSlVs have been reopened, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-c(2) (PLOR083C RevOO9) Reopen MSlVs after Grp 1-1 Page 7 of 7

TASK CONDITIONS/PREREQUISlTES

1.

Use of this procedure has been directed by the TRIP procedures.

2.

Main Condenser is available.

3.

RPV level is known.

4.

There is no indication of gross fuel failure.

5.

There is no indication of a Main Steam Line break.

6.

All T-221 Tool Packages have been obtained.

7.

Inboard and Outboard MSlVs are closed.

8.

Steps 4.1 thru 4.5 of T-221-2, "Main Steam Isolation Valve Bypass" are complete.

INITIATING CUE The Control Room Supervisor directs you to perform T-221-2, "Main Steam Isolation Valve Bypass" steps 4.6 through 4.12 in order to reopen the MSIVs.

EXELON NUCLEAR Nuclear Generation Group NAME:

Last First M.I.

SOC. SEC. NO.

OJTITPE MATERIAL COVERSHEET 8

ISSUE DATE:

COMPLETION DATE:

Signature / Title Date

~

Signature / Title Date Signature I Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE:

I I

~~

Training Review for Completeness:

IPlMS CODE:

I PlMS ENTRY:

Signature/Date It I

I 2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 1 of 8

TEMPORARY CHANGE FORM LOG TCF #

CODE NO.: PLOR-???CA REV. NO.: @

TCF DATE CHANGED SECTION #

TITLE:

PERFORM CORE SPRAY B PUMP CAPACITY TEST FOR IST (Alternate Path -_

Minimum Flow Valve Fails to Open)

1.

2.

3.

4.

5.

t i

6.

7.

I I

I I

a.

9.

IO.

I

11.

I I

12.

13.

14.

15.

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 2 of 8

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 20901401 01 / PLOR-NEW1 CA WA:

209001A4.04 Unit Reactor Operator/Senior Reactor Operator URO: 2.9 SRO: 2.9 TASK D ESC R I PTI 0 N :

Ability to manually operate and/or monitor Core Spray minimal flow valves in the control room A.

NOTES TO EVALUATOR:

1.

2.

3.

4.

5.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

System cues included in the performance checklist are to be provided to the exarriinee when no system response is available.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing ln-Plant JPMs, no equipment will be operated without Shift Management approval.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPhSs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 3 cf 8

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

None REFERENCES

1.

TASK STANDARD

1.

ST-0-014-212-2, Rev. 1, Core Spray B Pump Capacity Test for IST Satisfactory task completion is indicated when it is recognized that the Core Spray B Pump has no minimum flow protection, the pump is secured, and Core Spray 6 loop is returned to a normal standby lineup, as specified in the performance steps of ST-0-014-212-2, Section 6.0.

Estimated time to complete: 15 minutes Non-Time Critical

2.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perform Core Spray 2B pump capacity test for IST using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CON D IT1 0 N SIPRE REQ U IS ITES 1

I

2.

3.

The plant is operating at 100% power.

An Equipment Operator is standing by in the 2B Core Spray Pump Room.

Communications are available between the Control Room, 2B Core Spray Pump Ftoom, B and D Core Spray Pump Triangle Room, and Cable Spreading Room.

Core Spray pump 2B oil level is between the minimum and maximum lines on the sig htglass.

Core Spray pump 26 static pump suction pressure is 6 psig.

All data recording will be performed (simulated) by a second operator.

4.

5.

6.

INITIATING CUE The Control Room Supervisor directs you to perform Core Spray 2B Pump Capacity Test for IST in accordance with ST-0-014-212-2 (provided).

Provide examinee a copy of ST-0-014-212-2 with the following items completed:

0 Section 1 of the cover page Procedure section 2.0, Test Equipment 0

Procedure section 3.0, Prerequisites I

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 4 of 8

H.

STEP 7

STEP NO 1

ACT STANDARD 2

4 5

PERFORMANCE CHECKLIST CLOSE MO-2-14-011 B Core Spray Outboard Disch.

MO-2-14-011 B control switch is momentarily placed in CLOSE al Panel (Cue: Acknowledge control switch operation)

VERIFY CLOSED MO-2-14-011 B Core Spray Outboard Disch.

P 3

If this JPM is being performed in parallel with another JPM, direct candidate NOT to make the plant page announcement prior to starting 28 Core Spray pump.

6 (Cue: MO-2-14-011 B green light is ON; red light is OFF.)

Verifies that MO-2-14-011 B green light is ON; red light is OFF at Panel 20C003.

START 2BP037 Core Spray B Pump.

(Cue: Acknowledge control switch operation.)

VERIFY Core Spray 2B Pump STARTS and is RUNNING by observing motor current on 14A-MI B and discharge pressure on PI-2-14-048B Core Spray Disch P.

(Cue: Ammeter 14A-MI B indicates 40 amps, PI-2-14-048B indicates 350 psig.)

VERIFY MO-2-14-005B Core Spray B Min Flow automatically OPENS.

(Cue: MO-2-14-005B green light is OFF; red light is ON.)

VERIFY 2DP037 Core Spray D Pump is NOT rotating.

(Cue: When requested, report that the Core Spray D Pump is NOT rotating.)

P P

P P

Starting 2B Core Spray pump is announced on plant page prior to starting Core Spray pump 2B.

2B Core Spray pump control switch is momentarily placed in the START position at Panel 20C003.

2B Core Spray pump green light is verified OFF, red light is verified ON.

Pump motor amps on ammeter 14A-MI B and discharge pressure on PI-2-14-048B are verified rising at Panel 20C003.

MO-2-14-005B green light is verified OFF; red light is verified ON at Panel 20C003.

Directs Equipment Operator to verify Core Spray D Pump is NOT rotating.

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 5 of 8

/j

• 7 STEP OPEN MO-2-14-026B Core Spray Full Flow Test.

(Cue: Acknowledge control switch operation)

VERI FYO P E N MO 1 4-026B Core Spray Full Flow Test.

P (Cue: MO-2-14-0266 green light is OFF; red light is ON)

VERIFY MO-2-14-0056 Core Spray B Min Flow automatically CLOSES.

(Cue: MO-2-14-005B green light is ON; red light is OFF.)

STANDARD

~

~~

~

~

~

MO-2-14-026B control switch is momentarily placed in OPEN at Panel 20C003.

MO-2-14-026B green light is verified OFF; red light is verified ON at Panel 20C003.

MO-2-14-005B green light is verified ON; red light is verified OFF at Panel 20C003.

• I 0

Time-compress by telling the examinee Core Spray B Pump has been running for !5 minutes.

Remind examinee that a second operator has successfully recorded all full flow test data on Data Sheet I.

~

~

~

~~

THROTTLE MO-2-14-026B Core Spray Full Flow Test to obtain Rated Flow of 3125 to 3175 gpm as read on computer point H056.

(Cue: Acknowledge control switch and red pushbutton operation. MO-2-14-026B green light is ON; red light is OFF.

Computer point H056 indicates 0 gpm.)

P MO-2-14-026B control switch is momentarily placed in CLOSE at Panel 20C003. Red pushbutton is depressed to stop valve stroke. Valve control switch and red pushbutton are operated as necessary to achieve 3125 to 3175 gpm as read on PMS computer point H056.

Recognizes that the MO-2-14-026E3 has ramped close unexpectedly and that the green closed light is ON and that the red open light is verified OFF at Panel 20C003.

Report to the CRS that the MO-2 026B full flow test valve for the 28 Core Spray Pump has failed to properly operate 2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 6 of 8

11 P

• I 2 MO-2-14-011 B control switch is momentarily placed in OPEN at Panel 20C003.

13 STEP

~

~~

VERIFY MO-2-14-005B Core Spray B Min Flow automatically OPENS.

(Cue: MO-2-14-005B green light is ON; red light is OFF.)

SHUTDOWN 2BP037 Core Spray B P u m p.

(Cue: Acknowledge control switch operation. Core Spray B Pump green light is ON; red light is OFF. Pump motor amps and pump discharge pressure are zero.)

ACT P

P STANDARD Recognizes that the MO-2-14-0053 green light is ON; red light is OFF at Pariel 20C003. The Min. Flow Valve has not automatically opened.

Report to the CRS that the minimum flow valve for the 2B Core Spray Pump has failed to properly operate.

2B Core Spray pump control switclh is momentarily placed in the STOP position at Panel 20C003.

2B Core Spray pump green light is verified ON, red light is verified OFF.

Pump motor amps on ammeter 14,A-MI 6 and discharge pressure on PI-2-14-048B are verified at zero at Panel 20C003.

As the Control room Supervisor, direct that the 2 6 Core Spray loop be returned to a normal lineup.

14 15 16 L

Open MO-2-14-011 B Core Spray Outboard Disch.

(Cue: Acknowledge control switch operation)

VERIFY OPEN MO-2-14-011 B Core Spray Outboard Disch.

(Cue: MO-2-14-011 B green light is OFF; red light is ON)

P MO-2-14-011 B green light is verified OFF; red light is verified ON at Panel 20C003.

~

~

Inform Control Room Supervisor of task completion.

P Control Room Supervisor notified F40 14-026B malfunction and test being aborted.

As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Cond itions/P rerequisites) AN D procedures.

P Positive control established.

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 7 of 8

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When it is recognized that the Core Spray B Pump has no minimum flow protection, the pump is secured, and Core Spray B loop is returned to a normal standby lineup, as specified in the performance steps of ST-0-014-212-2, Section 6.0, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-d(3) (NEW) Core Spray Test AP -1 Page 8 of 8

TASK CONDITIONS/PREREQUISlTES

1. The plant is operating at 100% power.

2.

An Equipment Operator is standing by in the 2 9 Core Spray Pump Room.

3. Communications are available between the Control Room, 2B Core Spray Pump Room, B and D Core Spray Pump Triangle Room, and Cable Spreading Room.

4.

Core Spray pump 29 oil level is between the minimum and maximum lines on the sig htg lass.

5.

Core Spray pump 2B static pump suction pressure is 6 psig.

6.

All data recording will be performed (simulated) by a second operator.

INITIATING CUE The Control Room Supervisor directs you to perform Core Spray 2B pump capacity test for IST in accordance with ST-Q-014-212-2 (provided).

EXELON NUCLEAR Nuclear Generation Group Training Review for Completeness:

OJTlTPE MATERIAL COVERSHEET PlMS CODE:

Si'gnature /Title Date Signature I Title Date Segnature I Title Date (1 APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

I I

II ISSUE DATE: "

COMPLETION DATE:

NAME:

Last First SOC. SEC. NO.

COMMENTS:

1 PlMS ENTRY:

SignatureIDate I

I 2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page I of 12

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-024C REV. NO.: 008 TITLE:

Perform a Group I PClS Isolation Reset (GP-8A)

TCF 4 l TCF DATE C W G E D SECTION #

1.

9.

I O.

11.

12.

13.

14.

15.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 2 of 12

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 2000490501 / PLOR-024C WA:

223002A4.03 Unit Reactor Operat<rr/Senior Reactor Operator URO: 3.6 SRO: 3.5 TASK DESCR I PTl ON :

Perform a Group I PClS Isolation Reset GP-8A)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Ma nag em en t a p prova I.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed irr paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 3 of 12

B.

C.

D.

E.

F.

TOOLS AND EQUIPMENT Hand the Examinee a copy of C.O.L. GP-8.A with "As Found Position" column initials already filled in.

REFERENCES I.

2.

Procedure GP-8.A, Rev. 10, "PCIS Isolation - Group I" C.O.L. GP-8.A, Rev. 8, "Group I Isolation" TASK STANDARD

1.

2.

Satisfactory task completion is indicated when the PClS Group I Isolation is reset.

Estimated time to complete: 8 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset the PClS Group I isolatioii using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TAS K C 0 N D IT I 0 N S/P R E RE Q U I S IT E S

1.

2.

3.

4.

5.

6.

7.

8.

The plant had been at 100% power.

A PClS Group I isolation has occurred and has been verified to be a result of Main Steam tunnel high temperature.

The cause of the PClS Group I isolation has been corrected.

The plant is in a safe, stable shutdown condition.

CAV (Crack Arrest Verification) System is GP-8.A, "PCIS Isolation - Group I" steps 3.1 and 3.2 have been completed.

There is no indication of fuel damage.

There is no evidence of a steam leak.

in operation.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp I Reset -1 Page 4 of 12

G.

INITIATING CUE The Control Room Supervisor directs you to reset the PClS Group I isolation logic per steps 4.1 through 4.4 of GP-8.A, "PCIS Isolation - Group I".

Page 5 of 12 2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1

H.

PERFORMANCE CHECKLIST 1

STEP NO Obtain copies of procedures GP-8A and COL GP-8A.

P Copies of procedures GP-8A and COL GP-8A are obtained.

~

STEP I

I I

• • NOTE**

Provide examinee with the marked up COL GP-8A.

• 2 3

• 4 5

• 6 7

"8 Place switch to "CLOSE" for AO-2-02-080A.

P (Cue: Acknowledge control switch operation.)

Initial the AO-2-02-080A box in the "CHECKED BY" column on COL GP-8A.

Place switch to "CLOSE" for AO-2-02-0806.

P P

(Cue: Acknowledge control switch operation.)

Initial the AO-2-02-080B box in the "CHECKED BY" column on COL GP-8A.

P AO-2-02-080A control switch placed in the "CLOSE" position at panel 2OCOO3-01.

"CHECKED BY" column for AO-2-02-080A initialed on COL GP-8A.

AO-2-02-080B control switch placed in the "CLOSE' position at panel 2OCOO3-01.

"CHECKED BY" column for AO-2-02-080B initialed on COL GP-8A.

Place switch to "CLOSE" for P

AO-2-02-080C control switch placed AO-2-02-080C.

(Cue: Acknowledge control switch operation.)

in the "CLOSE" position at panel 2OCOO3-01.

Initial the AO-2-02-080C box in the "CHECKED BY" column on COL P

"CHECKED BY" column for AO-2-02-080C initialed on COL GP-8A.

GP-8A.

Place switch to "CLOSE" for P

AO-2-02-080D control switch placed AO-2-02-080D.

(Cue: Acknowledge control switch operation.)

in the "CLOSE" position at panel 2OCOO3-01.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 6 of 12

9 "1 0 11

• I 2 13 "14 15

• I 6 17 ACT STEP STANDARD Initial the AO-2-02-080D box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-2-02-080D initialed on COL GP-8A.

AO-2-02-086A control switch placed in the "CLOSE" position at panel 2OCOO3-01.

Place switch to "CLOSE" for AO-2-02-086A.

P (Cue: Acknowledge control switch operation.)

Initial the AO-2-02-086A box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-2-02-086A initialed on COL GP-8A.

AO-2-02-086B control switch placed in the "CLOSE" position at panel 2OCOO3-01.

Place switch to "CLOSE" for AO-2-02-086B.

P (Cue: Acknowledge control switch operation.)

Initial the AO-2-02-086B box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-2-02-086B initialed on COL GP-8A.

Place switch to "CLOSE" for AO-2-02-086C.

AO-2-02-086C control switch placed in the "CLOSE" position at panel 2OCOO3-01.

P P

(Cue: Acknowledge control switch operation.)

Initial the AO-2-02-086C box in the "CHECKED BY" column on COL GP-8A.

"CHECKED BY" column for AO-2-02-086C initialed on COL GP-8A.

Place switch to "CLOSE" for AO-2-02-086D.

P AO-2-02-086D control switch placed in the "CLOSE" position at panel 2OCOO3-01.

(Cue: Acknowledge control switch operation.)

~

~~

"CHECKED BY" column for AO-2-02-086D initialed on COL GP-8A.

Initial the AO-2-02-086D box in the "CHECKED BY" column on COL GP-8A.

P Page 7 of 12 2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1

18 19 20 21 22 23 24 25 26 27 STEP ACT STANDARD Verify switch in "CLOSE" for 40-2-02-039.

P AO-2-02-039 control switch verified in the "CLOSE" position at panel 20C004A.

(Cue: Switch in 'CLOSE.)

N/A or initial the AO-2-02-039 box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-2-02-039 N/A'd or initialed on COL GP-8A.

Verify switch in "CLOSE" for AO-2-02-040.

P AO-2-02-040 control switch verified in the "CLOSE" position at panel 2 OC004A.

(Cue: Switch in 'CLOSE".)

~

~~

N/A or initial the AO-2-02-040 box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-2-02-040 NIAd or initialed on COL GP-8A.

Verify switch in "CLOSE" for AO-2-02-316.

AO-2-02-316 control switch verified in the "CLOSE" position at panel 2OCOO3-03.

(Cue: Switch in 'CLOSE.)

N/A or initial the AO-2-02-316 box in the "CHECKED BY" column on COL GP-8A.

"CHECKED BY" column for AO-2-02-316 N/Ad or initialed on COL GP-8A.

Verify switch in "CLOSE" for AO-2-02-3 I

7.

AO-2-02-317 control switch verified in the "CLOSE" position at panel 2OCOO3-04.

(Cue: Switch in 'CLOSE".)

N/A or initial the AO-2-02-317 box in the "CHECKED BY" column on COL GP-8A.

"CHECKED BY" column for AO-2-02-317 N/Ad or initialed on COL GP-8A.

Verify MO-2-02-074 is CLOSED.

P MO-2-02-074 green light verified ON at panel 2OCOO3-03.

(Cue: MO-2-02-074 green light is on, red light is off.)

N/A or initial the MO-2-02-074 box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for MO-2-02-074 N/A'd or initialed on COL GP-8A.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 8 of 12

28 Verify MO-2-02-077 is CLOSED.

(Cue: MO-2-02-077 green light is on, red light is off.)

29 N/A or initial the MO-2-02-077 box in the "CHECKED BY" column on COL GP-8A.

30 Verify switch in "CLOSE" for AO-8098A.

(Cue: Switch in 'CLOSE.)

31 N/A or initial the AO-8098A box in the "CHECKED BY" column on COL GP-8A.

32 Verify switch in "CLOSE" for AO-8098C.

(Cue: Switch in 'CLOSE.)

ACT 33 P

N/A or initial the AO-8098C box in the "CHECKED BY" column on COL G P-8A.

P P

34 P

Verify switch in "CLOSE" for AO-8099A.

(Cue: Switch in 'CLOSE".)

P 35 P

N/A or initial the AO-8099A box in the "CHECKED BY" column on COL GP-8A.

STANDARD 36 MO-2-02-077 green light verified ON at panel 2OCOO3-04.

Verify switch in "CLOSE" for AO-8099C.

(Cue: Switch in 'CLOSE".)

"CHECKED BY" column for MO-2-02-077 N/Ad or initialed on COL GP-8A.

37 AO-8098A control switch verified in the "CLOSE" position at panel 2OCOO3-04.

N/A or initial the AO-8099C box in the "CHECKED BY" column on COL GP-8A.

"CHECKED BY" column for AO-8098A N/Ad or initialed on COL GP-8A.

AO-8098C control switch verified in the "CLOSE" position at panel 2OCOO3-04.

"CHECKED BY" column for AO-8098C N/A'd or initialed on COL GP-8A.

AO-8099A control switch verified in the "CLOSE" position at panel 2OCOO3-04.

"CHECKED BY" column for AO-8099A N/Ad or initialed on COL GP-8A.

AO-8099C control switch verified in the "CLOSE" position at panel 2OCOO3-04.

"CHECKED BY" column for AO-8099C N/A'd or initialed on COL GP-8A.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 9 of 12

STEP ACT STANDARD Verify switch in "CLOSE" for AO-8098B P

AO-8098B control switch verified in the "CLOSE" position at panel 2OCOO3-02.

38 (Cue: Switch in 'CLOSE'.)

39

~~~

N/A or initial the AO-8098B box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-8098B N/A'd or initialed on COL GP-8A.

40 Verify switch in "CLOSE" for AO-8098D.

AO-8098D control switch verified in the "CLOSE" position at panel 2OCOO3-02.

(Cue: Switch in 'CLOSE.)

41

~

N/A or initial the AO-8098D box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-8098D N/A'd or initialed on COL GP-8A.

42 Verify switch in "CLOSE" for AO-8099B.

P AO-8099B control switch verified in the "CLOSE" position at panel 2OCOO3-02.

(Cue: Switch in "CLOSE".)

43 N/A or initial the AO-8099B box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-8099B N/Ad or initialed on COL GP-8A.

44 Verify switch in "CLOSE" for AO-8099D.

P AO-8099D control switch verified in the "CLOSE" position at panel 2OCOO3-02.

(Cue: Switch in 'CLOSE.)

~

45 N/A or initial the AO-8099D box in the "CHECKED BY" column on COL GP-8A.

P "CHECKED BY" column for AO-8099D N/Ad or initialed on COL GP-8A.

• • NOTE,**

The C.O.L. steps for AO-2256 "Condenser Offgas to Mechanical Vacuum Pump (MVP)"

and the MVP are not required to be performed and can be marked as N/A.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 10 of 12

• 47

• 48 49 50

_ _ _ _ _ ~

derify isolation signal cleared.

Cue: The following annunciators are not lit: 227 B-2, 228 A-2, 228 E-3, 228 E-4)

Place the Inboard PClS Reset Switch, 16A-S32, in the "GRP I" Dosition.

[Cue: Acknowledge reset switch Dperation.)

~~~

Place the Outboard PClS Reset Switch, 16A-S33, in the "GRP I" position.

(Cue: Acknowledge reset switch Dperation.)

Verify "CHANNEL A and B GROUP I ISOLATION RELAYS NOT RESET" annunciators clear.

(Cue: Annunciators 21 1 H-I and 21 1 J-I are not lit.)

Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

P P

P P

P The following Group I Isolation annunciators are verified not lit:

227 B-2 and 228 A-2, OR 228 E-3 and 228 E-4 3R Verifies no alarms on Steam Leak Detection Panel (located on riverside back wall of simulator)

The Inboard PClS Reset Switch is momentarily placed in the "GRP I" position at panel 20C005A.

The Outboard PClS Reset Switch is momentarily placed in the "GRP I" position at panel 20C005A.

The "CHANNEL A and B GROUP I ISOLATION RELAYS NOT RESET" annunciators 21 1 H-I and 21 1 J-I are verified not lit.

Task completion reported.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 11 of 12

F-

/I As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task ConditionslPrerequisites) AND p roced u res.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the PClS Group I isolation is reset, the Control Room Supervisor should be informed.

The evaluator will then terminate the exercise.

2008 NRC JPM CR-e(1) (PLOR024C Rev008) Grp 1 Reset -1 Page 12 of 12

TASK CONDITIONS/PREREQUISITES

1. The plant had been at 100% power.

2.

A PCIS Group I isolation has occurred and has been verified to be a result of Main Steam tunnel high temperature.

3. The cause of the PCIS Group I isolation has been corrected.

4.

The plant is in a safe, stable shutdown condition.

5. CAV (Crack Arrest Verification) System is not in operation.

6. GP-8.A, "PCIS Isolation - Group I" steps 3.1 and 3.2 have been completed.

7. There is no indication of fuel damage.

8. There is no evidence of a steam leak.

INITIATING CUE:

The Control Room Supervisor directs you to reset the PCIS Group I isolation logic per steps 4.1 through 4.4 of GP-8.A, "PCIS Isolation -

Group I".

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERrAL COVERSHEET LI Fl CAT1 ON MANUAL OJT MODULE APPROVALS:

Signature /Title Date Signature / Title Date Signature / Title Date Signature / Title Date 11 APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE:

I I

NAME:

ISSUE DATE:

Last First SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

1 PlMS CODE:

I PlMS ENTRY:

SignatureIDate 2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 1 of 7

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-031C REV. NO.: QIJ TITLE:

EXCITING THE MAIN GENERATOR, TCF #

TCF DATE CHANGED SECTION #

2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 2 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 23701 101 01 / PLOR-031 C K/A:

262001A4.04 Unit Reactor OperatorISenior Reactor Operator RO: 3.6 SRO: 3.7 TASK DESCRIPTION:

EXCITING THE MAIN GENERATOR A.

NOTES TO EVALUATOR:

1.

2.

3.

4.

5.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

b.

Satisfactory performance of this JPM is accomplished if:

a.

b.

The task standard is met.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated lime (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

2)

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CRf(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 3 i f 7

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT None REFERENCES Procedure SO 50.1.A-2 Rev. 11, Main Generator Synchronizing and Loading (R)

TASK STANDARD

1.

Performance Location: Simulator

2.

Satisfactory task completion is indicated when the Main Generator is excited, generator terminal voltage is adjusted to 22 KV, and the automatic voltage regulator is in service.

3.

Estimated time to complete: 10 minutes (A.5) Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to excite the Main Generator using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES

1.

2.

3.

INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to excite the Main Generator and place the automatic voltage regulator in service in accordance with steps 4.1 throuah 4.8 of SO 50.1.A-2. Main Generator Svnchronizina and Loadina.

Plant startup in progress with reactor power at approximately 18%.

All SO 50.1.A-2, Main Generator Synchronizing and Loading prerequisites are met.

The Power System Director has beer) notified.

2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 4 (of 7

H.

PERFORMANCE CHECKLIST

" STEP NO 1

2 5

6

• 7 8

STEP Obtain a CODV of SO 50.1.A-2.

Verify "GENERATOR INSULATION OVER HEATING" annunciator is clear.

(Cue: Annunciator 206 L-2 is not lit.)

Verify the "Load Selector" pushbutton is selected to REMOTE/AUTO.

(Cue: Load Selector REMOTElAUTO light is on.)

Verify "RegTTransfer" switch 43-0601 in MANUAL.

(Cue: "RegTTransfer" switch is in manual, green light is on, red light is off.)

Verify the Manual DC Volt Regulator 70-0601 set at minimum.

(Cue: Manual DC Volt Regulator green and amber lights are on, red light is off.)

Direct an Equipment Operator to periodically monitor machine gas pressure on PI-4356.

(Cue: Equipment Operator reports PI-4356 indicates 75 Dsia.)

Close the "Alt Exc Fld Bkr" 41-0601.

(Cue: Acknowledge control switch operation, Alt Exciter Field Breaker red light is on, green light is off.)

Verify Field Volts, Amps and Generator Volts-rise and red deexcitation backup light lit.

(Cue: FIELD voltmeter indicates 100 volts, FIELD ammeter indicates 1400 amps, GENERATOR voltmeter indicates 17 kilovolts; DEEXCITATION backup red lighi is on, green light is off.)

ACT P

P P

P STANDARD 4 CODV of SO 50.1.A-2 is obtained

'GENERATOR INSULATION OVER HEATING" annunciator is verified clear on alarm panel 206 L-2.

Load Selector REMOTE/AUTO light is verified ON at panel 20C008A.

Regulator Transfer switch 43-0601 is verified in the MANUAL position at panel 20C009.

Manual DC Voltage Regulator 70-Ci601 green and amber lights are verified ON at Panel 20C009.

Equipment Operator is directed to periodically monitor machine gas pressure on PI-4356.

Alterrex Exciter Field Breaker control switch 41-0601 is momentarily placed in the CLOSE position at panel 20CQ09.

FIELD AMPS and VOLTS and GENERATOR VOLTS are verified to RISE and DEEXCITATION backup red light is verified ON and green light OFF at panel 20C009.

2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 5 of 7

10

• I 1 12 13

• I4 15 16 17 L

I ACT STEP Adjust GENERATOR output voltage to Dbtain 21.5 - 22.5 KV using MAN. DC VOLT REGULATOR 70-0601.

P (Cue: Generator voltmeter indicates 22 Rheostat"(9OP) to obtain a "Reg Man/Auto c KV. Manual DC voltage regulator green light off, yellow light on.)

Verify GENERATOR output voltage is between 21.5 - 22.5 KV.

(Cue: GENERATOR VOLTMETER indicates 22 KV.)

Adjust the "Auto Voltage Reg Deviation" voltage of 0 VDC.

(Cue: Acknowledge CLOCKWISE Rheostat oDeration.)

Verify "Reg Man/Auto Deviation voltage is 0 VDC.

P (Cue: Reg Man/Auto Deviation meter I

indicates 0 VDC.)

Verify "GEN VOLT REG AUTO TO MAN UNBALANCED~I annunciator is clear..

(Cue: Annunciator 220 C-3 is not lit.)

Place the "RegTTransfer" switch 43-0601 in "AUTO".

(Cue: Acknowledge control switch operation.)

auto regulation.

(Cue: The ReglTransfer red light is on, green light is off.)

Inform the Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknow-ledges report.)

As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Cond itions/P rereq uisites) AN D procedures.

Verify the "ReglTransfer" lights indicate P

P P

i STANDARD Manual DC Voltage Regulator 70-0601 is adjusted to obtain a GENERATOP output voltage between 20.9 and 23.1 Kb at panel 20C009.

GENERATOR output voltage is verified between 21.5 and 22.5 KV on GEPI VOLTMETER at panel 20C009.

Auto Voltage Reg Rheostat 9OP is*

adjusted to obtain a reading within 2 volts of 0 on the Reg Man/Auto Deviation meter at panel 20C009.

Reg Man/Auto Deviation voltage is verified to be 0 VDC on the Reg Man/Auto Deviation voltmeter at panel 20C009.

"GEN VOLT REG AUTO TO MAN UNBALANCED" annunciator is verified clear on alarm panel 220 C-3.

Regnransfer switch 43-0601 is placed in the AUTO position at panel 20C009.

Regnransfer red light is verified ON and green light verified OFF at panel 20C009.

Task completion reported.

Positive control established.

2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 6 of 7

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE When the Main Generator exciter field breaker is closed and the automatic voltage regulator is in service, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-f(4) (PLOR031C Rev01 1) Excite Main Generator -1 Page 7 of 7

TASK CONDITIONS/PREREQUISITES

1.

Plant startup in progress with reactor power approximately 1 8 YO.

2.

All SO 50.1.A-2, Main Generator Synchronization and Loading prerequisites are met.

3.

The Power System Director has been notified.

INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to excite the Main Generator and place the automatic voltage regulator in service in accordance with steps 4.1 through 4.8 of SO 50.1.A-2, Main Generator Synchronization and Loading.

I

EXELON NUCLEAR Nuclear Generation Group Training Review for Completeness:

OJTlTPE MATERIAL COVERSHEET PlMS CODE:

I FlCATlON MANUAL OJT MODULE c\\

J APPROVALS:

Signature / Title Date Signature / Title Date

~

Signature /Title Date Signature /Title Date j/ APPROVED FOR USE:

I Signature I Title Date

~

EFFECTIVE DATE:

I 1

ISSUE DATE:

COM P LET1 0 N DATE :

NAME:

Last First SOC. SEC. NO.

COMMENTS:

I PlMS ENTRY:

Signature/Date 2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 1 crf 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 21 200901 01 / PLOR-004C WA:

212000A4.14 Unit Reactor OperatorlSenior Reactor Operator RO: 3.8 SRO: 3.8 TASK DESCRIPTION:

SCRAM RESET A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 2 of 7

6.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT Key for Scram Discharge Volume High Level Bypass Switch.

REFERENCES GP-11.E, Rev. 21 Reactor Protection System - Scram and ARI Reset TASK STANDARD

1.

Satisfactory task completion is indicated when the Reactor Protection System is reset and the Scram Discharge Volume Vent and Drain valves are open.

2.

Estimated time to complete: 19 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset a scram and begin draining the Scram Discharge Volume using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK C 0 N DIT I 0 N S/P R E R EQ U I SITES

1.

2.

3.

4.

T-100, Scram is complete.

5.

6.

7.

8.

9.

ARI was NOT initiated.

IO.

INITIATING CUE The Control Room Supervisor directs you to reset the scram in accordance with GP-11.E, Reactor Protection System - Scram and ARI Reset and begin draining the Scram Discharge Vol u me.

A Main Turbine trip has caused a reactor scram.

Plant conditions have stabilized with RPV level at 23 inches.

RPV pressure is being maintained below 1050 psig with Bypass Valves.

All scram valves are open. All SDV Vent and Drain valves are shut.

A CRD pump is operating.

Both RPS buses are energized.

The Reactor Mode switch is in SHUTDOWN.

No fuel damage is suspected.

7 2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 3 of 7

H.

PERFORMANCE CHECKLIST STEP NO 1

[I 2

• 3 4

5

• 6 7

STEP

~

~~~~

Obtain a copy of GP-11.E, "Reactor Protection System - Scram and ARI Reset".

Verify scram initiating signal clear or bypassed.

(Cue: Annunciator 21 0 A-2 is lit.)

Place Scram Discharge Volume High Water Level Bypass Keylock Switch to "BY PASS".

(Cue: Annunciator C-2 on alarm panel 210 is alarming.)

Acknowledge the "SCRAM DISCHARGE VOLUME HI WATER LEVEL SCRAM BY PASS" ann u nciato r.

(Cue: Annunciator 210 C-2 is lit solid.)

Prior to resetting a full scram, notify Radiation Protection.

(Cue: Evaluator responds as Rad.

Protection management and acknowledges not if icati o n.

Place Scram Reset switch in Group 1 and 4 position then Group 2 and 3 position.

(Cue: Acknowledge reset switch operation.)

Verify the four scram group white lights are lit on both the RPS cabinets.

(Cue: All of the scram group white lights are lit on both 20C015 and 20C017.)

ACT P

P P

P P

P P

STANDARD A copy of GP-11.E, "Reactor Protection System - Scram and ARI Reset is obtained.

"TURBINE STOP VLV. CLOSURE AND CONTROL VLV. FAST CLOSURE SCRAM BYPASS" annunciator is verified lit on alarm panel 210 A-2.

Key is obtained from CRS keybox, inserted into the Scram Discharge Volume High Water Level Bypass Keylock Switch 5A-S8 and placed in the "BYPASS" position at panel 20C005A.

The annunciator "ACKNOWLEDGE" pushbutton is depressed on panel 20C005A.

Contacts Rad. Protection personnel via radio, phone, or plant page.

Scram Reset switch 5A-S9 is takeri to the "GROUP 1 & 4", and then "GROUP 2 & 3" positions at panel 20C005A.

All scram group white lights verified LIT on panels 20C015 and 20C017.

2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 4 of 7

8 9

10 11 12 13 14 STEP Verify "A CHANNEL AUTO SCRAM" and "B CHANNEL AUTO SCRAM" annunciators are clear.

(Cue: Annunciators 211 B-I and 211 C-I are not lit.)

Monitor Scram Air header pressure.

(Cue: Pl-2-3-312 indicated 73 psig.)

Verify "SCRAM VALVE PILOT AIR HEADER PRESS HI-LOWg annunciator is clear.

(Cue: Annunciator 21 1 D-2 is not lit.)

Verify blue scram lights are off.

(Cue: All of the blue scram lights are off on the Full Core Display.)

Verify "ACCUM U LATOR TROUBLE" lights are clear.

(Cue: All of the "ACCUMULATOR TROUBLE" lights are clear on the Full Core Display.)

Verify "CRD ACCUMULATOR LO PRESS HI LEVEL" annunciator is clear.

(Cue: Annunciator 211 E-2 is not lit.)

ACT P

P P

P P

P STANDARD

~

"A CHANNEL REACTOR AUTO SCRAM" and "B CHANNEL REACTOR AUTO SCRAM" annunciators are verifiect clear on alarm panels 21 1 B-I and 21 1 12-1.

~

Scram air header pressure is verified to be approximately 70 psig on Pl-2-3-3 *I 2 on panel 20C205R.

"SCRAM VALVE PILOT AIR HEADER PRESS HI-LOW' annunciator is verified clear on alarm panel 21 1 D-2.

All blue scram lights are verified OFF on the Full Core Display.

AI I "ACC U M U LATO R TRO U B L E" B ig h ts are verified clear on the Full Core Display.

"CRD ACCUMULATOR LO PRESS HI LEVEL" annunciator is verified clear on alarm panel 21 1 E-2.

• • NOTE **

Step 14 will take approximately 5 minutes to complete.

Verify CRD System Cooling Water flow is 55 - 65 gpm.

(Cue: Fl-2-03-306 indicates 60 gpm.)

P CRD System Cooling Water flow is verified to be 55 - 65 gpm on FI-2-03-306 on panel 20C005A.

2008 NRC JPM CR-g(2) (PLOR004C RevOll) Reset Scram - 1 Page 5 of 7

15 16

~

17

• I 8 19

• 20 21 22 L

STEP Place the Rod Drift Alarm Reset switch to the "Reset" position.

(Cue: Acknowledge reset switch operation.)

Verify the rod drift alarm lights are clear.

(Cue: All of the rod drift alarm lights are clear on the full core display.)

Verify "ROD DRIFT annunciator is clear (Cue: Annunciator 21 1 D-4 is not lit.)

Place SDV Inboard Vent and Drain Valves Switch, 5A-S14A, in "OPEN".

(Cue: Acknowledge control switch operation.)

Verify the SDV Inboard Vent and Drain Valves indicate open.

(Cue: SDV Inboard Vent and Drain Valves red lights are on, green lights are Off.)

Place SDV Outboard Vent and Drain Valves Switch, 5A-S14B, in "OPEN".

(Cue: Acknowledge control switch operation.)

Verify the SDV Outboard Vent and Drain Valves indicate open.

(Cue: SDV Outboard Vent and Drain Valves red lights are on, green lights are Off.)

Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

ACT P

P P

P P

P P

P STANDARD Rod Drift Alarm Reset switch 3A47 is momentarily placed to the "RESET" position and then released at pane I 20C005A.

All of the rod drift alarm lights are verified clear on the Full Core Display.

"ROD DRIFT annunciator is verified clear on alarm panel 21 1 D-4.

The SDV Inboard Vent and Drain Valve control switch 5A-SI4A is momentarily placed in the "OPEN" position and then released at panel 20C005A.

SDV Inboard Vent and Drain Valves red lights are verified ON at panel 20C005A.

The SDV Outboard Vent and Drain Valve control switch 5A-SI4B is momentarily placed in the "OPEN" position and then released at panel 20C005A.

SDV Outboard Vent and Drain Valves red lights are verified ON at panel 20CQ05A.

Task completion reported.

2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 6 of 7

STEP NO Positive control established.

control of all exam material provided to the examinee (Task Conditions /

STEP ACT STANDARD Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the scram is reset and the Scram Discharge Volume Vents and Drains are open, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-g(2) (PLOR004C Rev01 1) Reset Scram - 1 Page 7 of 7

TASK CONDlTlONSlPREREQUlSlTES

1.

A Main Turbine trip has caused a reactor scra

2.

Plant conditions have stabilized with RPV levd at 23 inches.

3.

RPV pressure is being maintained below 1050 psig with Bypass Valves.

4.

T-100, "Scram" is complete.

5.

All scram valves are open. All SDV Vent and Drain valves are shut.

6.

A CRD pump is operating.

7.

Both RPS buses are energized.

8.

The Reactor Mode switch is in "SHUTDOWN".

9.

ARI was -

NOT initiated.

I O. No fuel damage is suspected.

INITIATING CUE The Control Room Supervisor directs you to reset the scram in accordance with GP-11.E, "Reactor Protection System - Scram and ARI Reset" and beain draining the Scram Discharge Volume.

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET NAME:

Last First M.I.

SOC. SEC. NO.

APPROVALS:

ISSUE DATE:

COMPLETION DATE:

,~

Signature I Title Date Siignature I Title Date Signature I Title Date Signature I Title Date Date 11 APPROVED FOR USE:

Signature I Title EFFECTIVE DATE:

I I

PlMS CODE:

PlMS ENTRY:

Training Review for Completeness:

Signa tu re/Date 2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 1 of 6

TEMPORARY CHANGE FORM LOG TCF ##

TCF DATE CODE NO.: PLOR-NEW REV. NO.:

TITLE:

Verify Isolation of D w e l l Chilled Water and RBCCW CHANGED SECTION #

9.

IO.

11.

12.

13.

14.

15.

L 2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 2 i>f 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 21 30220401/ PLOR-NEW WA:

295024EA1.07 URO: 3.8 SRO: >3.9 TASK DESCRIPTION:

Verify Isolation of D w e l l Chilled Water and RBCCW A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing %-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JRM, though listed in the task standard, is no1 to be given to the examinee.

2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW.-1 Page 3 of 6

B.

TOOLS AND EQUIPMENT None C.

REFERENCES GP-8.6, Rev. 18, PCIS Isolation - Groups II and 111 (R)

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the RBCCW to Drywell isolation valves MO-2373 and MO-2374 are closed AND both Recirculation Pumps are tripped.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps of GP 8.B PCIS Isolation - Groups II and 111.

I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDlTlONSlPREREQUlSlTES

1.

The Reactor has just been scrammed.

3.

DWCW Return Header pressure as read on PI-20262 is 32 psig.

4.

Drywell pressure is approximately 24 psig.

G.

INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to perform step 5.5 of GP-8.B, PCIS Isolation - Groups II and 111.

2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 4 of 6

H.

PERFORMANCE CHECKLIST NO 1

2 STEP Obtain a copy of procedure GP-8.B.

Verify MO-20245 AND MO-20246 aligned in the "CHILLED WATER" position.

• 3 Return Header pressure.

(Cue: Comparison acknowledged)

(Cue: MO-20245 AND MO-20246 red "CHILLED WATER" lights are lit. MO-20245 AND MO-20246 red "RX BLDG CLG WATER' lights are out.)

Calculate corrected RBCCW pressure (CRP) by taking indicated RBCCW pressure on PI-2350 minus 25 psig.

(Cue: PI-2350 is indicating 40 psig.)

• 5

/1

• 6 ITrip BOTH Recirc pumps.

Compare Drywell pressure to Corrected RBCCW Pressure (CRP) to determine which pressure is greater.

(Cue: PR-2508 indicates 24 psig.)

(Cue: Both Recirc pumps breaker green lights are on and red lights are off.

Annunciators 214 C-3 and H-3 are lit.)

7 Verify BOTH Recirc pumps are tripped.

(Cue: Both Recirc pumps breaker green lights are on and red lights are off.)

• 8 ACT P

P Close MO-2373, RBCCW Isolation valve.

(Cue: Acknowledge control switch operation.)

P P

P P

P P

STANDARD A copy of procedure GP-8.B is obtained.

MO-20245 AND MO-20246 red "CHILLED WATER" lights are lit. MO-20245 AND MO-20246 red "RX BLDG CLG WATER" lights are out at Panel 20C005A.

Indicated RBCCW pressure is checked, then 25 psig is subtracted to determine a CRP of approximately 15 psig.

Recognize that DWCW Return Header pressure is greater than Drywell prga assure and DWCW isolation is not required and not performed.

Corrected RBCCW Pressure (CRP) is determined to be less than PR-2508 or PR-4805 or PR-8102A(B) at panels 20C003/ 20C004C.

The control switches for the Drive Motor Breakers on both A and B Recirc "DRIVE MOTOR" breakers are placed in TRIP at panel 20C004A.

A and B Recirc "DRIVE MOTOR" breaker green lights are verified to be ON at panel 2 0 C 0 04A.

MO-2373 control switch is momentarily placed in the "CLOSE" position at panel 20c012.

2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 5 of 6

(Cue: Acknowledge control switch 12 11 Inform Control Room Supervisor of task completion.

Verify the MO-2374, the RBCCW Isolation valve is closed.

ledges report.)

(Cue: MO-2374 green light is on, red light is off.)

13 As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND Droced ures.

ACT P

P P

P P

STANDARD MO-2373 green light is verified OM red light is verified OFF at panel 2C MO-2374 control switch is moment placed in the "CLOSE" position at 20c012.

MO-2374 green light is verified ON red light is verified OFF at panel 2C Task completion reported.

Positive control established.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE When step 3.5 of GP-8.B has been completed, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM CR-h(3) (2005 NRC Exam) DWCW-RBCCW -1 Page 6 of 6

TASK CONDlTlONSlPREREQUlSlTES

1.

The Reactor has just been scrammed.

2.

DWCW Return Header pressure as read on PI-20262 is 32 psig.

3.

Drywell pressure is 24 psig.

INITIATING CUE The Control Room Supervisor directs you, the Plant Reactor Operator, to perform step 3.5 of GP-8.B, PCIS Isolation - Groups II and 111.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

-I Fl CAT1 ON MANUAL OJT MODULE APPROVALS:

Signature / Title Date Signature I Title Date Signature / Title Date Signature /Title Date APPROVED FOR USE:

I Signature / Title Date EFFECTIVE DATE:

I I

NAME:

1 ISSUE DATE:

SOC. SEC. NO.

COMMENTS:

Last First M.I.

1 COMPLETION DATE:

Training Review for Completeness:

Signature/Date

~

~~

PIMS CODE:

PlMS ENTRY:

2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 1 af 6

TEMPORARY CHANGE FORM LOG TCF #

CODE NO.: PLOR-074P REV. NO.: 013 TITLE:

ISOLATING AND VENTING SCRAM AIR HEADER - UNIT 3 (T-214-3) 7 TCF DATE CHANGED SECTION #

9.

IO.

11.

12.

13.

14.

15.

r 2008 NRC JPM IP (i) (PLOR074P Rev013) Vent Scram Header Page 2 e4 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 200381 0599 / PLOR-074P WA:

295037EA1.03 Unit Reactor Operator/Senior Reactor Operator RO: 4.1 SRO: 4.1 TASK DESCRIPTION:

ISOLATING AND VENTING SCRAM AIR HEADER - UNIT 3 (T-214-3)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

EOP Locker Key

2.

T-214-3 Tool Package REFERENCES Procedure T-214-3, Rev. 7, Isolating and Venting the Scram Air Header TASK STANDARD

1.

Satisfactory task completion is indicated when the Unit 3 scram air header has been isolated and vented.

2.

DIRECTIONS TO EXAMINEE Estimated time to complete: 8 minutes Non-Time Critical When given the initiating cue, perform necessary steps to isolate and vent the Unit 3 scram air header using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISlTES I.

A partial loss of feed flow on Unit 3 results in RPV level dropping below the scram setpoint.

2.

Control Rods did NOT insert.

3.

Blue scram lights on the Full Core Display are NOT lit.

4.

Scram air header Pl-3-03-312 on panel 30C124 reads 70 psig.

5.

TRIP procedures have directed that the scram air header be depressurized.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator to perform T-214-3, Isolating and Venting the Scram Air Header on Unit 3.

2008 NRC JPM IP (i) (PLOR074P Rev013) Vent Scram Header Page 4 cf 6

H.

PERFORMANCE CHECKLIST ACT

" STEP STANDARD NO

• I

• 2 STEP Obtain the key for the Emergency Operating Procedure Tool Locker.

(Cue: When examinee requests EOP Tool Locker key from WECS OR examinee identifies the location of the WECS keybox and its associated key then evaluator should provide the EOP Tool Locker key. Examinee may produce their cow of Tool Locker Kev.)

Open Emergency Operating Procedure Tool Locker and obtain T-214 Tool Kit.

(Cue: Equipment obtained.)

• • • • NC S

Emergency Operating Procedure Tool Locker Key requested from WECS OR examinee identifies the location of the WECS keybox and its associated key.

Produces own copy of Tool Locker Key.

P Tool Locker located on Radwaste IE3uilding El. 165' is unlocked, opened and T-214 Tool Kit located.

I

'E****

When examinee locates tool kit, inform him that he now has the tools to perform the procedure. Provide the examinee with a copy of the T-200 procedure which corresponds to the tool kit that has been chosen. DO NOT allow tools to be removed from the locker.

Relock the locker before leavina the area.

• 3 4

• 5

• 6 L

Close HV-3-3-123, lnstr Air Header Block Vlv to Scram Pilot Valve Header.

(Cue: Valve handwheel is turned

[CLOCKWISE] until stem length above valve yoke lowers 1 inch then handwheel will not turn.)

Verify closed IDV-3-3-312, PS-3-03-230 +

PS-3-03-229 Instrument Drain Valve.

(Cue: [CLOCKWISE] Valve handwheel did not move and stem length above valve voke did not move.)

Remove the cap from IDV-3-3-312.

(Cue: Pipe cap is turned

[COUNTERCLOCKWISE] until cap is removed.)

Open IDV-3-3-312.

(Cue: Valve is turned [COUNTER-CLOCKWISE] until stem length above valve yoke raises % inch then will not turn, flow noise can be heard as valve is opened.

S S

S S

HV-3-3-123 handwheel is turned CLOCKWISE until resistance of valve seal is felt. (Located on RB Unit 3 135' CRD Valve Nest.)

IDV-3-3-312 handwheel movement is attempted in the CLOCKWISE direction.

Pipewrench from Tool Kit is placed on IDV-3-3-312 pipe cap and is turned COUNTERCLOCKWISE until pipe cap is removed from pipe.

IDV-3-3-312 is turned COUNTER-CLOCKWISE until resistance of valve backseat is felt.

2008 NRC JPM IP (I) (PLOR074P Rev013) Vent Scram Header Page 5 of 6

Under ACT P - must perform S - must simulate STANDARD Task completion reported using tet hand held radio, or GAI-TRONICS system.

Positive control established I.

TERMINATING CUE When the Unit 3 scram air header has been isolated and vented, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2008 NRC JPM IP (i) (PLOR074P RevOl3) Vent Scram Header Page 6 clf 6

TASK CONDITIONS/PREREQUISITES

1.

A partial loss of feed flow on Unit 3 results in RPV level dropping below the scram setpoint.

2.

Control Rods did NOT insert.

3.

Blue scram lights on the Full Core Display are NOT lit.

4.

Scram air header PI-3-03-312 on panel 30C124 reads 70 psig.

5.

TRIP procedures have directed that the scram air header be depressurized.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator to perform T-214-3, Isolating and Venting the Scram Air Header on Unit 3.

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET Valve Auto Open Signal APPROVALS:

-~

Signature I Title Date Signature I Title Date

~

Siiy~ature I Title Date Signature I Title Date

// APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE:

I I

NAME:

Last First M.I.

ISSUE DATE:

SOC. SEC. NO.

I COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

Sig natu re/Date

~

PlMS CODE:

PlMS ENTRY:

2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 1 of 6

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-000C REV. NO.: @

TITLE:

Defeat of RClC Torus Suction Valve Auto Open Signal TCF #

TCF CSATE CHANCED SECTfOlrl#

2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 2 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 21 70280401 / PLOR-000C K/A:

217000A2.04 Unit Reactor Operator/Senior Reactor Operator URO: 3.0 SRO: 3.0 TASK DESCRIPTION:

Defeat of RClC Torus Suction Valve Auto Open Signal A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL S are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

EPS

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is no! to be given to the examinee.

2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

2.

REFERENCES

1.

TASK STANDARD

1.

Two (2) electrical boots for HFA relay contacts Two blank Equipment Status tags A 0 13.3-2, Rev. 1, RCIC Torus Suction Valves, Defeat of Auto Open Signal Satisfactory task completion is indicated when the Unit 2 RClC Torus suction valve auto open signal has been defeated.

Estimated time to complete: 15 minutes Non-Time Critical

2.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to defeat the Unit 2 RClC Torus suction valve auto open signal using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CON D IT1 ON S/PRE REQ U IS ITES

1.

2.

3.

4.

Shift Management has given permission to perform this task.

The Unit 2 Reactor Operator has given permission to perform this task.

Annunciator 222 (A-5) LOGIC POWER BUS LOST is in alarm.

Shift Management has changed A 0 13.3-2, Attachment 1 steps 4.1.3 and 4.1.4, from required double verification (DV) to concurrent verification (CV).

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to defeat the auto open signal to MO-2-13-39 and MO-2-13-41, RCIC Torus suction valves, by performing steps 4.1.3 throuah 4.1.6 of A 0 13.3-2. RCIC Torus Suction Valves. Defeat of Auto ODen Sianal.

2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 4 of 6

H.

PERFORMANCE CHECKLIST GF NO STEP I Obtain a copy of procedure A 0 13.3-2, RClC Torus Suction Valves, Defeat of Auto Open Signal.

(Cue: When the Examinee requests the in-progress copy of A 0 13.3-2 OR identifies how to obtain a controlled copy of the procedure, provide a hardcopy of procedure A 0 13.3-2, RClC Torus Suction Valves, Defeat of Auto Open Signal with Attachment 1 steps 4.1. I and 4.1.2, for Shift Management and URO signoffs, already filled in AND steps 4.1.1 and 4.1.2 checked complete).

2 Obtain two electrical HFA relay contact boots and two blank Equipment Status tags.

(Cue: two electrical relay contact boots AND two blank Equipment Status tags are obtained).

ACT P

P E****

STANDARD

~

~~

A copy procedure A 0 13.3-2, RCIC: Torus Suction Valves, Defeat of Auto Open Signal is obtained.

The Examinee obtains two electrical relay contact boots and two Equipment Status tags from the Main Control Room area or an alternate area such as an equipment cage or I&C instrument cage.

Prior to booting the contacts in the next steps the examinee may have to open the back of Panel 20C034 in order to verify the appropriate relay contact locations.

• 3 4

5 L

Boot contacts 1-2 of relay 13A-K55.

(Cue: Contacts 1-2 of relay 13A-K55 are booted)

S In the Cable Spreading Room, panel 20C034, the cover of relay 13A-K55 is removed. A single electrical boot is slid over contacts 1-2 (first relay finger from the right).

Signoff Attachment 1 step 4.1.3.

(Cue: A 0 13.3-2 Attachment 1 step 4.1.3 is signed off on the Initial line)

P A 0 13.3-2 Attachment 1 step 4.1.3 is signed off on the Initial line.

Attach an Equipment Status tag to the boot on contacts 1-2 of relay 13A-K55.

S l

l (Cue: Equipment Status tag is attached to boot on contacts 1-2 of relay 13A-K55).

Equipment Status tag with string is placed on boot of contacts 1-2 of relay 13AK55.

2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open Page 5 of 6

Boot contacts 3-4 of relay 13A-K55.

(Cue: Contacts 3-4 of relay 13A-K55 are booted)

S A single electrical boot is slid over contacts 3-4(second relay finger from the right).

7 8

9 10 Signoff Attachment 1 step 4.1.4.

(Cue: A 0 13.3-2 Attachment 1 step 4.1.4 is signed off on the Initial line)

Under ACT P - must perform S - must simulate P

A 0 13.3-2 Attachment 1 step 4.1.4 is signed off on the Initial line I.

TERMINATING CUE Attach an Equipment Status tag to the boot on contacts 3-4 of relay 13A-K55.

Inform Control Room Supervisor of task completion.

As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

When Attachment 1 of A 0 13.3-2 has been completed, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

~~

S Equipment Status tag with string is placed on boot of contacts 3-4 of relay 13A-K55.

Task completion reported using either the telephone or the plant page systerri.

P P

Positive control established.

Page 6 of 6 2008 NRC JPM IP(j) (NEW) RClC Defeat Suct Auto Open

TASK CONDlTlONSlPREREQUlSlTES

1. Shift Management has given permission to perform this task.

2.The Unit 2 Reactor Operator has given permission to perform this task.

3. Annunciator 222 (A-5) LOGIC POWER BUS LOST is in alarm.

4. Shift Management has changed A 0 13.3-2, steps 4.1.3 and 4.1.4, from required double verification (DV) to concurrent verification (CV).

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to defeat the auto open signal to MO-2-13-39 and MO-2-13-41, RCIC Torus suction valves, by performing steps 4.1.3 through 4.1.6 of A 0 13.3-2, RCIC Torus Suction Valves, Defeat of Auto Open Signal

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date II Signature / Title Date APPROVED FOR USE:

Srgnature I Title Date EFFECTIVE DATE:

I I

I1 NAME:

Last First M I. 1 ISSUE DATE:

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

I PlMS CODE:

I I PlMS ENTRY:

Signature/Date 2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 1 of 6

TEMPORARY CHANGE FORM LOG TCF #

CODE NO.: PLOR-NEWPA I

7 TCF DATE CHANGED SECTION #

REV. NO.:

TITLE:

D w e l l Chilled Water Low Level (Alternate Path - Manual Makeup to D w e l l Chill&

Water System)

1.

2.

3.

4.

5.

6.

7.

8.

9.

I O.

11.

12.

13.

14.

15.

2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 2 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

TASK-JPM DESIGNATOR: 2200020401 / PLOR-NEWPA K/A:

295028EA1.03 Unit Reactor Operator/Senior Reactor Operator URO: 3.9 SRO: 3.9 TASK DESCRIPTION:

Take Actions For Drvwell Chilled Water Low Level A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform std?ps (P) shall be simulated (S).

b.

When performing %-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator deterrnines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is ncst to be given to the examinee.

2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 3 of 6

B.

C.

D.

E.

F.

G.

TOOLS AND EQUIPMENT

1.

ARC 217 H-5 DRYWELL CHILLED VVATER LO LEVEL REFERENCES

1.

2.

TASK STANDARD ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL, Rev. 3 T-223 Drywell Cooler Fan Bypass

1.

Satisfactory task completion is indicated when the drywell chilled water system has been restored to normal presuure.

2.

Estimated time to complete: 15 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to restore the drywell chilled water system to normal pressure. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK C 0 N D IT IO N S/P RE REQ U IS ITE S

1.

Unit 2 was manually scrammed due to rising drywell pressure.

2.

Drywell pressure is 2.1 psig and rising slowly.

3.

Drywell bulk average temperature is 146 degrees F and rising slowly.

4.

5.

T-223 Drywell Cooler Fan Bypass is in progress.

Annunciator 217 H-5 DRYWELL CHILLED WATER LO LEVEL has alarmed and Ihe condition needs to be cleared to support restoring drywell cooling.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform Operator Action

1. 3 of ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL the annunciator is reset.

2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 4 of 6

H.

PERFORMANCE CHECKLIST NO 1

2

• 3 STEP Obtain a copy of ARC 217 H-5 DRYWELL CHILLED WATER LO LEVEL.

(Cue: Hand the Examinee a copy of ARC LO LEVEL) 217 H-5 DRYWELL CHILLED WATER Check drywell chilled water expansion tank pressure at Pl-20265 Chilled Water Expansion Tank.

(Cue: Pl-20265 Chilled Water Expansion Tank is indicating 20 psig and lowering slow I y )

Verify SV-20265 is OPEN.

(Cue: SV-20265 is cold to the touch, there is no humming noise, and there is no flow noise. Pl-20265 Chilled Water Expansion Tank is indicating 19 psig and continues to lower.)

• • • • NO ACT P

P P

E****

STANDARD A copy of procedure ARC 217 H-5 is obtained.

Locate Pl-20265 for Drywell Chilled Water Expansion Tank 20T036 located on Turbine Building 165 elevation near the drywell chillers. Verify Pl-20265 is reading 22 psig.

Locate SV-20265 Solenoid Operated Makeup to Chilled Water System.

Attempt to verify that SV-20265 is energized by listening for humming noise, feeling that the SV is warm to the touch, and listening for system flow.

During the performance of the following steps, if the examinee performs a system kalk search, cue that no leaks were identified.

• 4

• 5 L

OPEN HV-2-44A-23539 Demineralized Water Makeup Bypass To Chilled Water System.

(Cue: The lock and chain have been removed. HV-2-44A-23539 has been turned in the fully counter-clockwise direction and will no longer turn. System flow noise is heard.)

pressure is 28 to 40 psig.

(Cue: Pl-20265 is indicating 30 psig and rising)

Obtain a locked valve key (every Equipment Operator in a posted position has a locked valve key).

Unlock the lock on the valve and remove the chain.

Turn HV-2-44A-23539 in the counter-clockwise direction until the valve handle no longer turns.

Locate Pl-20265 for Drywell Chilled Water Expansion Tank 20T036 located on Turbine Building 165 elevation near the drywell chillers. Verify Pl-20265 is reading 28 psig to 40 psig.

2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 5 of 6

7 8

9 10 CLOSE HV-2-44A-23539 Demineralized Water Makeup Bypass To Chilled Water System.

(Cue: HV-2-44A-23539 has been turned in the fully clockwise direction and will no longer turn. System flow noise has stopped. PI-20265 is indicating 35 psig and steady.)

LOCK HV-2-44A-23539 Demineralized Water Makeup Bypass To Chilled Water System.

(Cue: The lock and chain have been reinstalled.)

Contact main control room and ask if annunciator 21 7 H-5 DRYWELL CHILLED WATER LO LEVEL is reset.

(Cue: Annunciator 217 H-5 DRYWELL CHILLED WATER LO LEVEL is reset.)

Inform Control Room of task completion.

(Cue: Control Room acknowledges report.)

As an evaluator ensure you have positive control of all exam material provided to the examinee (Task ConditionslPrerequisites) AND Drocedu res S

S S

S P

Turn HV-2-44A-23539 in the clockkvise direction until the valve handle no onger turns.

Verify system pressure on PI-20265 for Drywell Chilled Water Expansion lank 20T036 Reinstall the lock and chain on thevalve.

Request using hand held radio, plant page system, or telephone.

Task completion reported using hand held radio, plant page system, or telephone.

~

~

Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When HV-2-44A-23539 has been closed after restoring the Drywell Chilled Water System to normal pressure, and the Control Room reports that Annunciator 217 H-5 is reset, the evaluator will then terminate the exercise.

2008 NRC JPM IP(k) (NEW) DWCW Low Level -AP Page 6 of 6

TASK CONDlTlONSlPREREQUlSlTES

1.

Unit 2 was manually scrammed due to rising drywell pressure.

2.

Drywell pressure is 2.1 psig and rising slowly.

3.

Drywell bulk average temperature is 146 degrees F and rising slowly.

4.

T-223 Drywell Cooler Fan Bypass is in progress.

5. Annunciator 21 7 H-5 DRYWELL CHILLED WATER LO LEVEL has alarmed and the condition needs to be cleared to support restoring drywell cooling.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform Operator Action #3 LEVEL until the annunciator is reset.

of ARC 217 H-5 DRYWELL CHILLED WATER LO