ML022970219

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Draft - Section B Operating
ML022970219
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/23/2002
From: Alfonso M
Exelon Nuclear
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-277/02-302, 50-278/02-302
Download: ML022970219 (63)


Text

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2020050101 K/A: 202002A4.06 URO: 2.7 SRO: 2.6 TASK DESCRIPTION: Ability to manually operate and/or monitor Scoop Tube Power in the Control Room 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.

SJPM 1 - Recirc.doc Page 3 of 3 Reset Recirc MG Set "A"Scoop Tube Lockup. (AlternatePath)

B. TOOLS AND EQUIPMENT

1. None

'C. REFERENCES

1. SO 2D.7.B-2, Recirculation MG Set Scoop Tube Lockup and Reset.

D. TASK STANDARD

1. Satisfactory task completion is indicated when the "A" Recirculation Scoop Tube has been "LOCKED", in accordance with the approved procedure.
2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset the lockup on the "A"Recirc MG Set Scoop Tube in accordance with SO 2D.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset", Step 4.3. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Reactor power is 60% due to a load drop.

"2. The "A" and "B" Recirc pump M/A stations are in manual.

3. A scoop tube lockup has occurred on "A"Recirc MG Set.
4. The cause of the lockup was a component failure in the Jordan Positioner (NOQT a loss of power to the Scoop Tube Positioner).
5. I&C has corrected the problem with the Jordan Positioner.
6. All administrative controls to complete this repair have been cleared.
7. The Scoop Tube Positioner was NOT operated manually while the Recirc Pump Scoop Tube was locked up.

G. INITIATING CUE The Control Room Supervisor directs you to reset the scoop tube lockup on "A" Recirculation MG Set in accordance with SO 2D.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset", Step 4.3.

SJPM I - Recirc.doc Page 4 of 4 Reset Recirc MG Set "A" Scoop Tube Lockup. (AlternatePath)

H. PERFORMANCE CHECKLIST 9TEP STEP ACT STANDARD NO S1 Obtain a copy of the reference P A copy of SO 2D.7.B-2, "Recirculation MG Set procedure and review/utilize the Scoop Tube Lockup and Reset", is obtained.

correct section of the procedure.

Prerequisites & Precautions reviewed.

2 Verify power available to the Scoop P Observes the "M/G Set Scoop Tube Lockout Tube Lockup circuit. Circuit" power light is ON at panel 20C004A.

CUE: If asked by the student after locating the light on the appropriate panel, respond that "the MIG Set Scoop Tube Lockout Circuit" power light is ON."

  • 3 Adjust the "A" MG Set Controller P Adjusts the "A"MG Set Controller as follows:

demand setting to match generator

  • Sets the Moore Controller demand setting speed. near the actual generator speed.
  • Verifies speed demand is at desired setting (CUE: Speed demand is at the using actual and demand speed indications desired setting.) on 20C004A.
  • Verifies 'V' on the Moore Controller (CUE: 'W" on the Moore Controller SPIC-2-02-184-016A has stopped ramping.

has stopped ramping.)

      • Note***

As soon as the "A" Scoop Tube Positioner Lockup Switch 2A-S2A, on 20C004, is placed in the "RESET" position, the "A" Recirculation Pump speed will begin to oscillate. The operator will be expected to recognize the malfunction and take steps to re-lock the "A" MG Set Scoop Tube.

  • 4 Reset the "A" MG Set Scoop Tube P Resets the "A" MG Set Scoop Tube Lockup as Lockup. follows:

"* Places the "A" Scoop Tube Positioner Lockup Switch 2A-S2A, on 20C004, to the "RESET" position, AND

"* Allows it to spring return to the "NORMAL" position.

rage o 01 0 SJPM I - Recirc.doc rage 5 of a Reset Recirc MG Set "A"Scoop Tube Lockup. (AlternatePath)

ISTEP STEP ACT STANDARD NO _ _ _ _ _ _ _ _ _ _ _

5 Recognize "A" Recirculation Pump P Observes the activation of ARC 214 20C204M speed oscillations. D-2, "A" Recirc Speed Control Signal Fail.

Then observes the "A" Recirculation Pump speed is oscillating uncontrollably using any or all of the following instruments:

(CUE: "A" Recirculation Pump

  • SPIC-2-02-184-016A, "A" RR Pump Speed.

speed is oscillating

  • SPI-2-02-184-016A, "A" Generator Speed.

uncontrollably.) , FT-2-02-1 10 A, Loop "A"Flow.

      • Note***

The Student may report the situation on the "A" Recirculation Pump to the CRS prior to taking any steps to stop the condition. If the Student chooses this path use the cues in step 6.

T r

  • 6 Re-lock the "A" MG Set Scoop P Places the Scoop Tube Positioner "Lockup" Tube. switch 2A-S2A at panel 20C004A to the "LOCK" position.

CUE: If the Student Reports the situation concerning the I "A" Recirculation Pump prior to taking steps to mitigate the situation, give the Student the following order: "(Student's name) lock the "A" Recirculation Pump Scoop Tube."

I. I .

7 Reports "A" Recirculation Pump Reports to the CRS that the "A" Recirculation Scoop Tube condition. Pump Scoop Tube has been "LOCKED".

CUE: As the CRS, acknowledge the students report concerning the "A" Recirculation Pump Scoop Tube.

11 ______

Page Ii 07 b SJPM 1 - Recirc.doc Page 6 of Reset Recirc MG Set "A" Scoop Tube Lockup. (Alternate Path)

STEP STEP ACT STANDARD NO 8 As an evaluator ensure that you P Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE:

When the "A" Recirculation Pump Scoop Tube has been "Locked" and the Control Room Supervisor has been informed of the Recirculation System status, the evaluator will terminate the exercise.

J. SPECIAL INSTRUCTIONS:

None SJPM 1 - Recirc.doc Page 7 of 7 Reset Recirc MG Set "A"Scoop Tube Lockup. (Altemate Path)

TASK CONDITIONS/PREREQUISITES

1. Reactor power is 60% due to a load drop.
2. The "A" and "B" Recirc pump M/A stations are in manual.
3. A scoop tube lockup has occurred on "A" Recirc MG Set.
4. The cause of the lockup was a component failure in the Jordan Positioner (NOT a loss of power to the Scoop Tube Positioner).
5. I&C has corrected the problem with the Jordan Positioner.
6. All administrative controls to complete this repair have been cleared.
7. The Scoop Tube Positioner was NOT operated manually while the Recirc Pump Scoop Tube was locked up.

INITIATING CUE The Control Room Supervisor directs you to reset the scoop tube lockup on "A" Recirculation MG Set in accordance with SO 2D.7.B-2, "Recirculation MG Set Scoop Tube Lockup and Reset", Step 4.3.

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2590050101 K/A: 259001A4.02 URO: 3.9 SRO: 3.7 TASK DESCRIPTION: Place the "C" Reactor Feedwater Pump in "Standby" 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.

JPM 2 - RO NRC 259001A4 Page 3 of 11 Place the "C"ReactorFeedwaterPump in Standby. (Altemate Path)

B. TOOLS AND EQUIPMENT

1. None

"*-. REFERENCES

1. SO 6D.2.A-2 Rev. 19, "Reactor Feedwater Pump Shutdown".
2. GP-5, Section 3.0 Rev. 52, "Power Reductions".

D. TASK STANDARD

1. Satisfactory task completion is indicated when the "C" Reactor Feedwater Pump as been properly secured following the manual trip during the operation to place it in "standby".
2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to place the "C" Reactor Feedwater Pump in "standby" in accordance with SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown,"

steps 4.3 through 4.5. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISITES "1. A power reduction, using GP-5, "Power Operations", Section 3.0, is in progress for Control Rod pattern adjustment and Condenser Waterbox work.

2. Total Feedwater flow is between 7.5 x 106 lbs/hr and 11.5 x 106 lbs/hr.
3. All three (3) Reactor Feedwater Pumps are operating within normal parameters.
4. Zinc Injection System is aligned to the "A" Reactor Feedwater Pump.
5. GP-5, "Power Operations", Section 3.0, "Power Reductions" has been completed up to step 3.3.9.
6. An Equipment Operator is standing by in the vicinity of the "C" Reactor Feedwater Pump to support placing the pump in "STANDBY".

G. INITIATING CUE The Control Room Supervisor directs you to place the "C" Reactor Feedwater Pump in "STANDBY" in accordance with SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown", steps 4.3 through 4.5.

JPM 2 - RO NRC 259001A4 Page 4 of 11 Place the "C" Reactor FeedwaterPump in Standby. (AlternatePath)

H. PERFORMANCE CHECKLIST 7EP STEP ACT STANDARD NO 1 Obtain a copy of the reference P A copy of SO 6D.2.A-2 is obtained.

procedure and review/utilize the correct section of the procedure. Prerequisites & Precautions reviewed.

      • Note***

The Student may not verify this condition because it is stated in the Task Conditions that this flow is currently established.

2 Verify Plant Operating Conditions P Verifies Total Feedwater flow is between 7.5 x for placing "C" Reactor Feedwater 106 lbs/hr and 11.5 x 106 lbs/hr by performing Pump in "standby". the following:

Observe "blue" pen reading on FR-2-06 098.

      • Note***

. the Simulator the Feed Pumps bias does not need to be adjusted.

3 If required, minimize "Control P Reports "bias" information for the two Reactor Signal" differences between the Feedwater Pumps that are to remain in Reactor Feedwater Pumps to service.

remain in service.

May requests CRS direction for adjustment of the bias.

CUE: If asked by the RO about "bias" adjustment respond, "Continue to monitor the Reactor Feedwater Pumps bias, but at this time take no action to adjust bias."

raeL r1 JPM 2 - RO NRC 259001A4 P'age 5 of 11 Place the "C"ReactorFeedwaterPump in Standby. (Altemate Path)

ACT STANDARD STEP STEP ACT STANDARD NO ______ I 4 Verify the status of the Zinc P Verifies the Zinc Injection System is aligned to Injection System. either the "A" or "B" Reactor Feed Water Pumps by contacting an Equipment Operator.

CUE: If asked by the RO about the Zinc Injection System, respond by saying:

"The Zinc Injection System is aligned to the "A" Reactor Feedwater Pump."

I I t CUE: If the RO requests an Equipment Operator check for the appropriate number of Condensate Demins, respond by saying:

"There is a sufficient number of Condensate Demins in service for removing "C" RFP from service."

      • Note***

Opening the Recirc Valve will cause a drop in the associated RFP discharge flow and a rise in the Condensate System flow.

  • 5 Open the Reactor Feedwater Pump P OPENS AO-2139C, "RPF 'C' Min Flow Recirc (RFP) Minimum Flow Recirculation Valve", by placing the control switch on Valve. 20C06A-6 in the "OPEN" position.

6 Verifies the Reactor Feedwater Verifies AO-2139C, "RPF 'C' Min Flow Recirc Pump (RFP) Minimum Flow Valve" is OPEN by observing the following; Recirculation Valve is open. * "RED" light ON.

"* "GREEN" light OFF.

(CUE: RED light is "ON" GREEN light is "OFF".)

Page 6 of 11 JPM2-RONRC25900IA4 JPM 2 - RO NRC 259001A4 Page 6 of I I Place the "C"ReactorFeedwaterPump in Standby. (Alternate Path)

STEP ACT STANDARD NO IFSTEP P Verifies stable and/or allows Reactor Water 7 Verify Reactor Water Level and Level to stabilize while monitoring level Total Feedwater Flow.

indicators on 20C05A-3.

Verify stable and/or allow Feedwater Flow to stabilize while monitoring flow on FR-2-06-098.

(CUE: Reactor Water Level and Feedwater Flow have stabilized.)

"CLOSE" position.

P Verifies AO-2147C, "RFP 'C' Disch. Check Verifies the "C" Reactor Feedwater Valve" is CLOSED by observing the following; Pump Discharge Check Valve is closed. "* "RED" light OFF.

"* "GREEN" light ON.

(CUE: RED light is "OFF" GREEN light is "ON".)

I I

    • Note***

however, the AO-2147C, "RFP C Discharge Check Valve" will remain open in this condition, actuator will indicate closed.

II

"*10 Take "MANUAL" control of the "C" P Places the Reactor Feedwater Pump M/A Reactor Feedwater Pump. Station, HCS-2-06-084C, on 20C05A-1 1 in "MANUAL".

P Verifies the Reactor Feedwater Pump M/A 11 Verify the Reactor Feedwater Pump Station, HCS-2-06-084C, on 20C05A-1 1 in M/A Station in manual.

"MANUAL" by observing the following;

  • The "M" on the controller is backlit RED.

(CUE: The "M" on the Controller is backlit RED.)

7 rf 11 JPM 2 - RO NRC 259001A4 P--e= 7 of 1 1 Place the "C" Reactor FeedwaterPump in Standby. (AlternatePath)

ACT STANDARD TEP STEP NO discharge P CLOSES the "C" Feedwater Pump "112 Close "C" Reactor Feedwater Pump valve by performing the following:

Discharge Valve. Pump "Bumps" CLOSED MO-2194C, Feed on C Disch. Valve", using the control switch 20C06A-6.

and o Takes the control switch to close releases to the "NEUTRAL" position.

one o The first bump should be at least (1) second past split indication.

during o Uses short bumps, 2-5 seconds, the second half of the valve's stroke.

I Pump Verifies MO-2194C, "C" Feedwater 13 Verify the "C" Reactor Feedwater discharge valve is CLOSING by observing the Pump Discharge Valve is closing, following:

  • "RED" light ON.

(CUE: RED light is "ON" e "GREEN" light ON.

GREEN light is "ON".)

14 Verify individual Feedwater Pump P Checks flow rate lowering on the "C" RFP pen.

using FR-2565 on 20005A-2, green Flows and Reactor Water Level, flow rateonrising on the "A" & "B" RFP's ChecksFR-2565 20C05A-2, red and blue Fw ausing pens.

is stable and/or Verifies Reactor Water Level monitoring level allows it to stabilize while (CUE: Reactor Water Level is indicators on 20C05A-3.

stable.)

      • Note***

trip of the Reactor prior to step 4.5 of SO 6D.2.A-2 requires an immediate the point The "CAUTION" if its discharge check valve is "SLAMMING". This is "FeedwaterPump being secured "Alternate Path" JPM.

at which this JPM becomes an CUE: Once the RO has taken two or three bumps "CLOSED" on the RFP discharge valve report the following as the EO in the vicinity of the RFP.

"RFP 'C' discharge check valve is slamming." 8 of 11 S~Page NRC 259001A4 JPM 2 - RO in Standby. (Alternate Path)

Place the "C"Reactor FeedwaterPump

STEP STEP ACT STANDARD NO

"*15 Trip the "C" Reactor Feedwater P TRIPS the "C" RFP by depressing, "Feed Pump. Pump Trip, Turbine Trip C" pushbutton PBC1, on 20C05A-10.

16 Verify the "C" RFP tripped. P Verifies that the "C" Feed Pump Turbine has tripped by observing the following:

  • Turbine "RED" light OFF.

(CUE: RED light is "OFF"

  • Turbine "GREEN" light ON.

GREEN light is "ON".)

17 Report Feedwater Pump status to P Reports the following to the CRS; the Control Room Supervisor (CRS).

  • While placing the "C" RFP in standby the discharge check valve was observed to be slamming.

CUE: As the CRS, acknowledge

  • The "C" RFP was immediately tripped per the Student's report the procedural requirement.

concerning the current condition of the "C" Feedwater Pump.

18 As an evaluator ensure that you P Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under "ACT" P - must perform S - must simulate TERMINATING CUE When "C" Reactor Feedwater Pump has been tripped in accordance with SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown" and the Control Room Supervisor has been informed of the Feedwater System status, the evaluator will terminate the exercise.

J. SPECIAL INSTRUCTIONS:

NONE.

JPM 2 - RO NRC 259001A4 Page 9 of 11 Place the "C" Reactor FeedwaterPump in Standby. (Alternate Path)

TASK CONDITIONS/PREREQUISITES

1. A power reduction, using GP-5, "Power Operations", Section 3.0, is in progress for Control Rod pattern adjustment and Condenser Waterbox work.
2. Total Feedwater flow is between 7.5 x 106 lbs/hr and 11.5 x 106 Ibs/hr.
3. All three (3) Reactor Feedwater Pumps are operating within normal parameters.
4. Zinc Injection System is aligned to the "A" Reactor Feedwater Pump.
5. GP-5, "Power Operations", Section 3.0, has been completed up to step 3.3.9.
6. An Equipment Operator is standing by in the vicinity of the "C" Reactor Feedwater Pump to support placing the pump in "STANDBY".

INITIATING CUE The Control Room Supervisor directs you to place the "C" Reactor Feedwater Pump in "STANDBY" in accordance with SO 6D.2.A-2, "Reactor Feedwater Pump Shutdown", steps 4.3 through 4.5.

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: X K/A: 239001A4.01 URO: 4.2 SRO: 4.0 TASK DESCRIPTION: Ability to manually operate and/or monitor the MSIV's in the Control Room 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.

JPM 3 - RO-SRO NRC 239001A4 Page 3 of 13 Main Steam System Recovery following a Group I Isolation.

B. TOOLS AND EQUIPMENT

1. None
  • G.. REFERENCES
1. SO 1A.7.A-2 Rev. 4, Main Steam System Recovery following a Group I Isolation.
2. COL 1A.7.A-2 Rev.2, Main Steam System Lineup after a Group I Isolation.

D. TASK STANDARD

1. Satisfactory task completion is indicated when the MSIV's have been reopened following a Group I Isolation.
2. Estimated time to complete: 12 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to open the Main Steam Isolation Valves following a valid Group I isolation in accordance with SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation". I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. A Group I Isolation signal occurred. The Group I Isolation signal is now clear AND both logic channels are reset in accordance with GP-8.A, "PCIS Isolation - Group I."
2. All SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation",

Prerequisites are met.

3. COL 1A.7.A-2, "Main Steam System Lineup after a Group I Isolation", has been completed.
4. An Equipment Operator is standing by should manual operation or verification be required during the performance of this procedure.

G. INITIATING CUE The Control Room Supervisor directs you to open the Main Steam Isolation Valves (MSIV's) following a valid Group I isolation in accordance with SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation".

JPM 3 - RO-SRO NRC 239001A4 Page 4 of 13 Main Steam System Recovery following a Group I Isolation.

H. PERFORMANCE CHECKLIST 3TEP STEP ACT STANDARD NO 1 Obtain a copy of the reference P A copy of SO 1A.7.A-2, "Main Steam System procedure and review/utilize the Recovery following a Group I Isolation," is correct section of the procedure. obtained.

Prerequisites & Precautions reviewed.

2 Verify the position of the, AO-2 P At Panel 20C03D-3, verifies AO-2-02-086 A, 086 A, Outboard Main Steam Main Steam Line Outboard Isolation Valve, is Isolation Valve (MSIV). OPEN as indicated by each valves; e "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "AUTO/OPEN" position.

3 Verify the position of the, AO-2 P At Panel 20C03D-3, verifies AO-2-02-086 B, 086 B, Outboard Main Steam Main Steam Line Outboard Isolation Valve, is Isolation Valve (MSIV). OPEN as indicated by each valves;

  • "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "AUTOIOPEN" position.

4 Verify the position of the, AO-2 P At Panel 20C03D-3, verifies AO-2-02-086 C, 086 C, Outboard Main Steam Main Steam Line Outboard Isolation Valve, is Isolation Valve (MSIV). OPEN as indicated by each valves;

"* "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".) ° Control switch in the "AUTO/OPEN" position.

5 Verify the position of the, AO-2 P At Panel 20C03D-3, verifies AO-2-02-086 D, 086 D, Outboard Main Steam Main Steam Line Outboard Isolation Valve, is Isolation Valve (MSIV). OPEN as indicated by each valves; e "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".) ° Control switch in the "AUTO/OPEN" position.

JPM 3 - RO-SRO NRC 239001A4 Page 5 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO

      • Note***

-I"he following step equalizes the pressure across the inboard main steam isolation valves AND pressurizes the main steam lines down to the turbine stop valves.

  • Places the control switch in the OPEN position and then allows it to return to the NEUTRAL position 7 Verifies MO-2-02-074, Main Steam P Verifies MO-2-02-074, Main Steam line Drain line Drain Inboard Valve, opened as Inboard Valve is open by observing the requested. following; "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.
  • Places the control switch in the OPEN position and then allows it to return to the NEUTRAL position.

9 Verifies MO-2-02-077, Main Steam Verifies MO-2-02-077, Main Steam line Drain line Drain Outboard Valve, opened Outboard Valve is open by observing the as requested. following;

  • "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".) e Control switch in the "NEUTRAL" position.

JPM 3 - RO-SRO NRC 239001A4 Page 6 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO

      • Note***

-t'he Student will recognize that MO-2-02-078, Main Steam Line Drain Downstream Drain, is already open. It was opened using GP-3, Normal Plant Shutdown.

10 Verify the position of MO-2-02-078, Verifies MO-2-02-078, Main Steam Line Drain Main Steam Line Drain Downstream Drain, on 20C03B-3 is open by Downstream Drain. observing the following; "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.

11 Monitor dip across the Inboard P Observes the dip across the Inboard Main Main Steam Isolation Valves until Steam Isolation Valves using:

less than 50 psid. 9 PI-2-06-090 A, B or C, Reactor Pressure, on 20C005A.

AND o Main Turbine pressure as read on Main Steam pressure "A" AND Main Steam pressure "B" on 20C008A.

Until the d/p is less than 50 psid.

"*12 Open one (1) of the Inboard Main P When the d/p across the Inboard MSIV's is less Steam Isolation Valves (MSIV's). than 50 psid, THEN;

"* OPEN one (1) of the Inboard MSIV's, AND

"* Allow Reactor pressure, water level AND power to stabilize.

" Reports level and pressure trends to the CUE: As the CRS, acknowledge CRS.

the report of level and pressure trending.

13 Verify the position of the operated P Verifies the operated Inboard Main Steam Inboard Main Steam Isolation Valve Isolation Valve (MSIV) is open by observing the (MSIV) following; 0 "RED" light ON.

(CUE: RED light is "ON" e "GREEN" light OFF.

GREEN light is "OFF".) o Control switch in the "AUTO/OPEN" position.

JPM 3 - RO-SRO NRC 239001A4 Page 7 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO

"*14 Open the remaining Inboard Main P When Reactor pressure, water level AND power Steam Isolation Valves (MSIV's) have stabilized, THEN; OPEN the three (3) remaining Inboard MSIV's.

15 Verify the position of the operated P Verifies the operated Inboard Main Steam Inboard Main Steam Isolation Isolation Valves (MSIV's) are open by observing Valves (MSIV's). the following;

"* "RED" lights ON.

(CUE: RED light is "ON" * "GREEN" lights OFF.

GREEN light is "OFF".)

  • Control switches in the "AUTO/OPEN" position.

"*16 Isolate Main Steam Line drain path, P When the Inboard MSIV's have been opened:

Main Steam Line Drain Inboard

  • CLOSES MO-2-02-074, Main Steam Line Valve. Drain Inboard Valve, on 20C03B-3 by placing the control switch in the CLOSE position and then allowing it to return to the NEUTRAL position.

17 Verifies MO-2-02-074, Main Steam P Verifies MO-2-02-074, Main Steam line Drain line Drain Inboard Valve, closed as Inboard Valve is closed by observing the requested. following;

  • "RED" light OFF.

(CUE: RED light is "OFF" * "GREEN" light ON.

GREEN light is "ON".)

  • Control switch in the "NEUTRAL" position.

"*18 Isolate Main Steam Line drain path, P When the Inboard MSIV's have been opened:

Main Steam Line Drain Inboard

  • CLOSES MO-2-02-077, Main Steam Line Valve. Drain Outboard Valve, on 20C03A-6 by placing the control switch in the CLOSE position and then allowing it to return to the NEUTRAL position.

JPM 3 - RO-SRO NRC 239001A4 Page 8 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO 19 Verifies MO-2-02-077, Main Steam P Verifies MO-2-02-077, Main Steam line Drain line Drain Outboard Valve, closed Outboard Valve is closed by observing the as requested. following; e "RED" light OFF.

(CUE: RED light is "OFF" * "GREEN" light ON.

GREEN light is "ON".)

  • Control switch in the "NEUTRAL" position.
  • 20 Open MO-2308, Turbine Inlet Drain P OPENS MO-2308, Turbine Inlet Drain Lead Lead Drain. Drain, on 20C008A by placing the control switch in the OPEN position and then allowing it to return to the NEUTRAL position.

21 Verify MO-2308, Turbine Inlet Drain P Verifies MO-2308, Turbine Inlet Drain Lead Lead Drain open. Drain is open by observing the following;

  • "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.
  • 22 Open MO-2533A, A Stop Valve P OPENS MO-2533A, A SV Above Seat Drain, on (SV) Above Seat Drain. 20C008A by placing the control switch in the OPEN position and then allowing it to return to the NEUTRAL position.

23 Verify MO-2533A, A SV Above Seat P Verifies MO-2533A, A SV Above Seat Drain is Drain open. open by observing the following;

  • "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.
  • 24 Open MO-2533B, B SV Above Seat P OPENS MO-2533B, B SV Above Seat Drain, on Drain. 20C008A by placing the control switch in the OPEN position and then allowing it to return to the NEUTRAL position.

JPM 3 - RO-SRO NRC 239001A4 Page 9 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO 25 Verify MO-2533B, B SV Above Seat P Verifies MO-2533B, B SV Above Seat Drain is Drain open. open by observing the following;

"* "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.
  • 26 Open MO-2533C, C SV Above Seat P OPENS MO-2533C, C SV Above Seat Drain, on Drain. 20C008A by placing the control switch in the OPEN position and then allowing it to return to the NEUTRAL position.

27 Verify MO-2533C, C SV Above P Verifies MO-2533C, C SV Above Seat Drain is Seat Drain open. open by observing the following; e "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".) 0 Control switch in the "NEUTRAL" position.

  • 28 Open MO-2533D, D SV Above Seat P OPENS MO-2533D, D SV Above Seat Drain, on Drain. 20C008A by placing the control switch in the OPEN position and then allowing it to return to the NEUTRAL position.

29 Verify MO-2533D, D SV Above P Verifies MO-2533D, D SV Above Seat Drain is Seat Drain open. open by observing the following; 0 "RED" light ON.

(CUE: RED light is "ON" * "GREEN" light OFF.

GREEN light is "OFF".)

  • Control switch in the "NEUTRAL" position.

30 Reports to the Control Room P Reports to the CRS that the Main Steam Supervisor (CRS). Isolation Valves have been opened in accordance with SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation".

CUE: As the CRS, acknowledge the student's report concerning the Main Steam Isolation Valves.

JPM 3 - RO-SRO NRC 239001A4 Page 10 of 13 Main Steam System Recovery following a Group I Isolation.

STEP STEP ACT STANDARD NO 31 As an evaluator ensure that you P Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under "ACT" P - must perform S - must simulate TERMINATING CUE When Main Steam Isolation Valves have been opened in accordance with SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation," and the Control Room Supervisor has been informed of the Main Steam System status, the evaluator will terminate the exercise.

J. SPECIAL INSTRUCTIONS:

None JPM 3 - RO-SRO NRC 239001A4 Page 11 of 13 Main Steam System Recovery following a Group I Isolation.

TASK CONDITIONSIPREREQUISITES

1. A Group I Isolation signal occurred. The Group I Isolation signal is now clear AND both logic channels are reset in accordance with GP 8.A, "PCIS Isolation - Group I."
2. All SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation", Prerequisites are met.
3. COL 1A.7.A-2, "Main Steam System Lineup after a Group I Isolation",

has been completed.

4. An Equipment Operator is standing by should manual operation or verification be required during the performance of this procedure.

INITIATING CUE The Control Room Supervisor directs you to open the Main Steam Isolation Valves (MSIV's) following a valid Group I isolation in accordance with SO 1A.7.A-2, "Main Steam System Recovery following a Group I Isolation".

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2060140201 / PLOR-077C K/A: 206000G13 URO: 4.2 SRO: 4.0 TASK DESCRIPTION: Startup HPCI in the CST to CST Mode 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.

Page 5 ot :j SJPM 44-- HPCl SJPM csT.doc HPcI CST.doc Page 3 of 3

B. TOOLS AND EQUIPMENT None C. REFERENCES SO 23.1.B-2, Rev. 15, "HPCI System Manual Operation" D. TASK STANDARD

1. Satisfactory task completion is indicated when HPCI is started up in the CST to CST Mode with system flowrate at 5000 gpm at 100 to 300 psig above reactor pressure.
2. Estimated time to complete: 14 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to startup the HPCI system in the CST to CST Mode using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Reactor is at 100% power.
2. The HPCI System is set up for operation in accordance with SO 23.1 .A-2, "HPCI System Setup for Automatic or Manual Operation".
3. Rad Protection has been notified to monitor radiological conditions.
4. The HPCI Lube Oil Tank Level is filled to within two inches of the top of the sightglass.
5. The oil level in both of the HPCI Booster Pump Bearing sightglasses is between the MIN and MAX markings.
6. The HPCI turbine oil temperatures are presently 85 0 F.
7. "B" RHR loop is in Torus Cooling in accordance with SO 10.1.D-2 "RHR System Torus Cooling".
8. SBGT is in service in accordance with SO 9A.1 .B, "Standby Gas Treatment System Manual Startup".
9. ST-O-007-540-2, "Torus Water Temperatures" is in progress.

I-'age 4 01 4 SJPM 4 - HPCI CST.doc Page 40OT 4

'3. INITIATING CUE The Control Room Supervisor directs you to startup the HPCI system in the CST to CST Mode in accordance with SO 23.1..B-2 "HPCI System Manual Operation" with a flowrate of 5000 gpm at 100 to 300 psig above reactor pressure.

Page 5 of 5 SJPM 4-- HPCI CST.doc SJPM 4 Page 5 of 5

H. PERFORMANCE CHECKLIST ISTEP

-- NO STEP ACT STANDARD 1 Obtain a copy of procedure SO 23.1 .B-2. P A copy of procedure SO 23.1 .B-2 is obtained.

2 Verify the HPCI steam lines to AND from P Annunciators 221 D-2 and E-2 verified the Turbine are drained. NOT lit at panel 20C204B.

(Cue: Annunciators 221 D-2 and E-2 are NOT lit.)

3 Start the gland seal condenser vacuum P Gland seal condenser vacuum pump pump 20K002. control switch is placed in the "START" position at panel 20C004B.

(Cue: Acknowledge control switch operation.)

4 Verify the gland seal condenser vacuum P 20K002 red light is verified ON at panel pump 20K002 is running. 20C004B.

(Cue: 20K002 red light is on, green light is off.)

  • 5 Throttle open MO-2-23-021, "Full Flow P MO-2-23-021 control switch is momentarily Test" until the red "OPEN" indicating light placed in the "OPEN" position.

has been lit for 3 to 4 seconds. Approximately 3 to 4 seconds after the red light lit, the red stop travel pushbutton is (Cue: MO-21 green light is on, red light depressed at panel 20C004B.

has been on for 3 to 4 seconds.)

  • 6 Open MO-2-23-024, "Cond. Tank Return" P MO-2-23-024 control switch is valve. momentarily placed in the "OPEN" position at panel 20C004B.

(Cue: Acknowledge control switch operation.)

7 Verify MO-2-23-024, "Cond. Tank Return" P MO-2-23-024 red light is verified ON at opened. panel 20C004B.

(Cue: MO-24 red light is on, green light is off.)

SJPM 4 - HPCl CST.doc Page 6 of 6

STEP ACT STANDARD Simultaneously start the Auxiliary Oil P Auxiliary Oil Pump control switch is placed Pump (20P026), and open MO-2-23-014, in the "START" position and MO-2-23-014 "Supply" valve. control switch is momentarily placed in "OPEN" position simultaneously at panel (Cue: Acknowledge control switch 20C004B.

operation.)

Verify the Auxiliary Oil pump started. P Auxiliary Oil Pump red light is verified ON at panel 20C004B.

(Cue: Auxiliary Oil pump red light is on, green light is off and annunciator 222 D-5 is alarming.)

Verify MO-2-23-014, "Supply" valve P MO-2-23-14 red light verified ON and opened. HPCI speed, discharge pressure, and flow are verified at panel 20C004B.

(Cue: MO-14 red light is on, green light is off, HPCI discharge pressure, flow, speed and exhaust pressure rise, Aux. oil pump red light is off and green light is on.)

Verify the proper start of HPCI. P Verify pump discharge pressure, discharge flow, speed and exhaust (Cue: PI-2-23-109, FI-2-23-108, SPI- pressure increase and then stabilize.

4505, PI-2-23-112 increasing and Aux Oil Verify Aux Oil Pump red light is off, green Pump red light is off, green light is on.) light is ON at panel 20C004B.

Verify pump flowrate of 5000 gpm on FI P FIC-2-23-108 setpoint is adjusted to obtain 23-108. 5000 gpm on FI-2-23-108 at panel 20C004B.

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

IThrottle MO-2-23-021 to obtain desired P MO-2-23-021 control switch is closed to pressure. raise pressure, opened to lower pressure and red stop travel pushbutton is (Cue: Acknowledge control switch depressed to obtain a pressure of 1050 to operation. PI-2-23-109 reads 1250 psig, 1350 psig on PI-2-23-109 while FI-2-23-108 reads 5000 gpm.) maintaining turbine speed greater than 2200 rpm at SPI-4505 at panel 20C004B.

Inform Control Room Supervisor of task P Task completion reported.

completion.

(Cue: Control Room Supervisor acknowledges report.)

Page 7 of 7 SJPM 44-- HPCl SJPM csT.doc HPCI CST.doc Page 7 of 7

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

1. TERMINATING CUE When HPCI is running in the CST to CST Mode at 5000 gpm at 100-300 psig above Reactor Pressure, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

rage e 01 SJPM HPCI CST.doc SJPM 44-- HPCl P-age 8 OT

TASK CONDITIONS/PREREQUISITES

1. Reactor is at 100% power.
2. The HPCI System is set up for operation in accordance with SO 23.1.A-2, "HPCI System Setup for Automatic or Manual Operation".
3. Rad Protection has been notified to monitor radiological conditions.
4. The HPCI Lube Oil Tank Level is filled to within two inches of the top of the sightglass.
5. The oil level in both of the HPCI Booster Pump Bearing sightglasses is between the MIN and MAX markings.
6. The HPCI turbine oil temperatures are presently 85 0 F.
7. "B" RHR loop is in Torus Cooling in accordance with SO 10.1..D-2 "RHR System Torus Cooling".
8. SBGT is in service in accordance with SO 9A.1.B, "Standby Gas Treatment System Manual Startup".
9. ST-O-007-540-2, "Torus Water Temperatures" is in progress.

INITIATING CUE The Control Room Supervisor directs you to startup the HPCI system in the CST to CST Mode in accordance with SO 23.1.B-2 "HPCI System Manual Operation" with a flowrate of 5000 gpm at 100 to 300 psig above reactor pressure.

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2880140401 / PLOR-095C K/A: 272000A4.02 URO: 3.0 SRO: 3.0 TASK DESCRIPTION: Raisinq Main Steam Line Tunnel High Temperature Setpoints 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.

PLOR095C Rev007.doc Page 3 of 6

B. TOOLS AND EQUIPMENT Numac Key for TIS-80547A C. REFERENCES Procedure AO 40B.1-2 Rev. 9, "Raising Main Steam Line Tunnel PCIS Group I High Temp.

Trip Setpoint" D. TASK STANDARD

1. Satisfactory task completion is indicated when the trip setpoint for the TE-4931 A Main 0

Steam Line Tunnel temperature instrument has been raised to 250 F.

2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to raise the Main Steam Line Tunnel high temperature trip setpoint using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES Shift Manager's permission to perform this procedure has been obtained.

G. INITIATING CUE The Control Room Supervisor directs you to raise the trip setpoint for the 'A' Main Steam Line Tunnel Temperature instrument, TE-4931A, using AO 40B.1-2, "Raising Main Steam Line Tunnel PCIS Group I High Temperature Trip Setpoint".

Page 4 of 6 PLOR095C RevOO7.doc PLORO95C Rev007.doc Page 4 of 6

H. PERFORMANCE CHECKLIST l-TEP STEP ACT STANDARD NO

"*1 At Panel 2AC270 insert key in P Key placed in "lnop" position on TIS-80547A, turn to "lnop" mode. TIS-80547A (Cue: Acknowledge key in "lnop" position.)

  • 2 Use the "ETC" key to display "Enter Inop- P "Enter Inop Set" displayed on screen.

Set".

(Cue: Acknowledge "Enter Inop Set" on screen.)

  • 3 Depress "Enter Inop-Set" soft key. P "Enter Inop Set" softkey depressed.

(Cue: Acknowledge pushbutton operation.)

  • 4 Enter password (1234) within 10 seconds P Password entered properly.

and press enter on keypad.

(Cue: Acknowledge password entered properly.)

  • 5 Move cursor to Al-1 and select "Set RTD P Cursor moved to Al-1 position and "Set Parameters". RTD Parameter" is selected.

(Cue: Acknowledge "Set RTD Parameters" on screen.)

  • 6 Use the "Next Parameter" key to get to P Page 4 of 4 is displayed on screen.

page 4 of 4.

(Cue: Acknowledge page 4 of 4 displayed.)

7 Record "As Found isolation Setpoint" on P "As Found Isolation Setpoint" recorded Table 1. on Table 1.

  • 8 Move cursor right to desired "Isolation P "Isolation Setpoint" is raised to 2500 F.

Setpoint" and use the up/down keys to change setpoint to 2500F.

0 (Cue: Acknowledge setpoint at 250 F.)

  • 9 Press "Accept" soft key. P "Accept" softkey depressed.

(Cue: Acknowledge pushbutton operation.)

"*10 Press "Exit" key. P "Exit" softkey depressed.

(Cue: Acknowledge pushbutton P o PLOR operation.)

PLOR095C Rev007.doc Page 5 of 6

STEP STEP ACT STANDARD NO

"*11 Press "Exit Inop-set" key. P "Exit Inop Set" softkey depressed.

(Cue: Acknowledge pushbutton operation.)

"*12 Press the "Yes" key. P "Yes" softkey depressed.

(Cue: Acknowledge pushbutton operation.)

"*13 Place key in "Operate" mode. P Key placed in "Operate" position on TIS-80547A (B, C, D).

(Cue: Acknowledge key in "Operate" I position.)

14 Press "Reset Memory" key. P "Reset-Memory" softkey depressed.

(Cue: Acknowledge pushbutton operation.)

15 Record time and adjusted isolation P Time and isolation setpoint recorded on setpoint temperature on Table 1. Table 1.

16 Inform Shift Supervisor of task P Task completion reported.

completion.

(Cue: Shift Supervisor acknowledges report.)

Under "ACT" P - must perform S - must simulate TERMINATING CUE When the setpoint for the Main Steam Tunnel temperature instrument, TE-4931A, has been adjusted to 250 0 F, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

Page 6 of 6 PLOR095C RevOO7.doc PLORO95C Rev007.doc Page 6 of 6

TASK CONDITIONSIPREREQUISITES Shift Manager's permission to perform this procedure has been obtained.

INITIATING CUE The Control Room Supervisor directs you to raise the trip setpoint for the 'A' Main Steam Line Tunnel Temperature instrument, TE-4931A, using AO 40B.1-2, "Raising Main Steam Line Tunnel PCIS Group I High Temperature Trip Setpoint".

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2640060101 / PLOR-045C K/A: 264000A4.04 URO: 3.7 SRO: 3.7 TASK DESCRIPTION: Unload and Shutdown the Diesel Generator 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.

Page 3 of 3 Shutdown.doc SJPM 66 -Diesel Shutdown.doc Page 3 of 3

B. TOOLS AND EQUIPMENT Synchronizing switch removable handle

  • -C. REFERENCES
1. Procedure SO 52A.1..B, Rev. 24, "Diesel Generator Operations"
2. Procedure SO 33.2.A, Rev. 2, "Emergency Service Water System Setup for Normal Standby Operation" D. TASK STANDARD
1. Satisfactory task completion is indicated when E-4 Diesel Generator is shutdown with 2SUE supplying E-43 bus.
2. Estimated time to complete: 17 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to unload and shutdown the E-4 Diesel Generator using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES "1. E-4 Diesel Generator is in parallel with 2SUE supplying the E-43 bus.

2. E-4 Diesel Generator has been loaded to t 1400 KW and t; 1000 KVAR for its entire run time.
3. "A" ESW pump is supplying D/G cooling water.

G. INITIATING CUE The Control Room Supervisor directs you to unload and shutdown the E-4 Diesel Generator and the running ESW pump in accordance with SO 52A.1 .B, "Diesel Generator Operations" Step 4.5.

rage '4 ul '-4 SJPM 6 -Diesel Shutdown.doc r-a5ge, 01 ,4

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure SO 52A.1 .B. P A copy of procedure SO 52A.1 .B is obtained.

2 Reduce DIG load to 100-150 KW. P E4 D/G load is lowered to 50-200 KW on the E-4 D/G KW meter by taking the (Cue: [COUNTERCLOCKWISE, "GOVERNOR" control switch 165-DG12 to GOVERNOR control switch is taken to "LOWER" at panel 00C026D.

"LOWER"] E-4 D/G KW meter lowers to 100 KW.)

3 Reduce D/G VAR load to 50 KVAR P E-4 D/G load is lowered to 25-100 KVAR on the E-4 D/G VAR meter by taking the (Cue: [COUNTERCLOCKWISE, "AUTO E-4 D/G AUTO VOLT REG. Control VOLT REG" control switch is taken to Switch 90-DG14 to "LOWER" at panel "LOWER"] E-4 D/G VAR meter lowers to 0OC026D.

50 KVAR.)

  • 4 Trip the E-43 Breaker. P E-43 Breaker control switch is momentarily placed in the TRIP position at panel (Cue: Acknowledge control switch 00C026D.

operation.)

5 Verify the E-43 Breaker is open. P E-43 Breaker green light on, E-4 D/G "WATTS" meter indicates 0 KW, VAR (Cue: E-43 breaker green light is on, red meter indicates 0 KVAR are verified at light is off, E-4 D/G "WATTS" meter panel 00C026D.

indicates 0 KW, E-4 D/G VAR meter indicates 0 KVAR.)

  • 6 Shutdown the E-4 D/G by momentarily P E-4 D/G control switch, 101-DG12, is taking the "START/ STOP" switch (101- momentarily placed in the STOP position DG12) to "STOP". at panel 00C026D.

(Cue: Acknowledge control switch operation.)

7 Verify the E-4 D/G shuts down. P E-4 D/G green light verified ON and Voltmeter verified to drop to0 volts at (Cue: E-4 D/G green light on, red light off, panel 00C026D.

E-4 D/G Voltmeter drops to0.)

8 Obtain a copy of procedure SO 33.2.A. P A copy of procedure SO 33.2.A is obtained.

'if Page 5 of 5 SJPM 66 -Diesel Shutdown.doc

-Diesel Shutdown.doc Page 5 of 5

STEP NO STEP ACT STANDARD 9 Stop running "A" Emergency Service water P Turns the "A" ESW pump control switch to pump. "STOP" and allows the control switch to spring return to "NORMAL" at panel (Cue: Acknowledge control switch 00C026B.

operation.)

10 Verify "A" ESW pump is secured. P "A" ESW pump discharge pressure on PI 0236A and amps on "A" ESW pump motor (Cue: "A" ESW pump green light lit, pump ammeter are verified going to zero at control switch is green flagged, pump panel 00C026B.

discharge pressure on PI-0236A and motor amps on "A" ESW pump motor ammeter go to zero.)

11 Inform Control Room Supervisor of task Task completion reported.

completion.

(Cue: Control Room Supervisor acknowledges report.)

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When E-4 Diesel Generator is shutdown, the Control Room Supervisor should be informed.

The evaluator will then terminate the exercise.

-Diesel Shutdown.doc Page 6 of 6 SJPM 66 -Diesel SJPM Shutdown.doc Page 6 of 6

TASK CON DITIONS/PREREQUISITES

1. E-4 Diesel Generator is in parallel with 2SUE supplying the E-43 bus.
2. E-4 Diesel Generator has been loaded to m 1400 KW and , 1000 KVAR for its entire run time.
3. "A" ESW pump is supplying D/G cooling water.

INITIATING CUE The Control Room Supervisor directs you to unload and shutdown the E-4 Diesel Generator and the running ESW pump in accordance with SO 52A.1.B, "Diesel Generator Operations" Step 4.5.

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2610050101 / PLOR-044C K/A: 261000A4.03 URO: 3.0 SRO: 3.0 TASK DESCRIPTION: Manually Start SBGT System 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.

SJPM 7 - Manually start SGTS.doc Page 3 of 3

B. TOOLS AND EQUIPMENT None C. REFERENCES

1. Procedure SO 9A.1.B Rev. 8, "Standby Gas Treatment System Manual Startup"
2. Procedure ST-O-09A-500-2, Rev. 3 "Standby Gas Treatment Filter Train Operation Log" D. TASK STANDARD
1. Satisfactory task completion is indicated when Standby Gas Treatment System in operation with:
a. "A" SBGT fan running.
b. "A" Filter train in service.
2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to manually start the Standby Gas Treatment System using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System is lined up for automatic operation in accordance with SO 9A.1 .A, "Standby Gas Treatment System Lineup for Automatic Operation".
2. Standby Gas Treatment System is required for HPCI System operation.
3. The "B" SBGT filter train run time is greater than the "A" SBGT filter train run time.

G. INITIATING CUE The Control Room Supervisor directs you to start the Standby Gas Treatment System in preparation for HPCI System operation in accordance with SO 9A.1 .B "Standby Gas Treatment System Manual Startup".

Page 4 of 4 SJPM -

start SGTS.doc Manually start SJPM 77 - Manually SGTS.doc Page 4 of 4

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of procedure P A copy of procedure SO 9A.1 .B is SO 9A.1.B. obtained.

2 Notify Health Physics prior to starting P Health Physics has been notified that SBGT for Unit 2 HPCI operations. SBGT is going to be started.

(Cue: Health Physics acknowledges notification.)

  • 3 Open AO-00475-1, SBGT "A" Filter P AO-00475-1 control switch is placed in Inlet damper. the "OPEN" position at panel 20C012.

(Cue: Acknowledge control switch operation.)

4 Verify AO-00475-1 SBGT "A" Filter P AO-00475-1 red light is verified ON at Inlet damper is open. panel 20C012.

(Cue: AO-0475-1 red light is on, green light is off.)

5 Acknowledge the "STAND-BY GAS P The annunciator "ACKNOWLEDGE" TREATMENT FILTERS NOT IN pushbutton is depressed at panel AUTO" annunciator. 20C012.

(Cue: Annunciator 216 A-5 is not lit.)

  • 6 Open AO-00475-2 SBGT "A" Filter P AO-00475-2 control switch is placed in Outlet damper. the "OPEN" position at panel 20C012.

(Cue: Acknowledge control switch operation.)

7 Verify AO-00475-2 SBGT "A" Filter P AO-00475-2 red light is verified ON at Outlet damper is open. panel 20C012.

(Cue: AO-00475-2 red light is on, green light is off.)

8 Verify AO-20469-1 D/W Rx Bldg Equip P AO-20469-1 green light is verified ON at Exh damper is Closed. panel 20C012.

(Cue: AO-20469-1 green light is on, red light is off.)

SJPM 7 - Manually start SGTS.doc P'age 0 OT

STEP NO STEP ACT STANDARD 9 Verify AO-20469-2 D/W Rx Bldg Equip P AO-20469-2 green light is verified ON at Exh damper is Closed. panel 20C012.

(Cue: AO-20469-2 green light is on, red light is off.)

"*10 Start "A"("B") SBGT Fan. P "A"("B") SBGT Fan control switch is placed in the "RUN" position at panel (Cue: Acknowledge control switch 20C012.

operation.)

11 Verify the proper start of the "A"("B") P "A"("B") SBGT Fan red light is SBGT Fan.

(Cue: "A"("B") SBGT Fan red light is on, green light is off.)

        • NOTE SBGT system flows and system differential pressures do not need to be verified in a specific range for HPCI System operation.

12 Log the start time for the filter train in P Log entry made in SBGT Filter Train service in accordance with ST-0-09A- Run Log.

500-2.

(Cue: Log entry made.)

13 Inform Control Room Supervisor of P Task completion reported.

task completion.

(Cue: Control Room Supervisor acknowledges report.)

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

1. TERMINATING CUE When SBGT system is running to support HPCI operation, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

Page 6 of 6 SJPM 77- Manually SJPM - SGTS.doc start SGTS.doc Manually start Page 6 of 6

TASK CONDITIONS/PREREQUISITES

1. Standby Gas Treatment System is lined up for automatic operation in accordance with SO 9A.I.A, "Standby Gas Treatment System Lineup for Automatic Operation".
2. Standby Gas Treatment System is required for HPCI System operation.
3. The "B" SBGT filter train run time is greater than the "A" SBGT filter train run time.

INITIATING CUE The Control Room Supervisor directs you to start the Standby Gas Treatment System in preparation for HPCI System operation in accordance with SO 9A.1.B "Standby Gas Treatment System Manual Startup".

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2001500401/ PLOR-316P K/A: 201001A2.09 URO: 3.2 SRO: 3.1 TASK DESCRIPTION: Low CRD Scram Air Header Pressure - Unit 3 (Alternate Path Standby Regulator Must be Placed In Service)

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.

SJPM 8 - Scram Air Header.doc Page 3 of 3

B. TOOLS AND EQUIPMENT None C. REFERENCES Procedure ON-1 08, Rev. 6, "Low CRD Scram Air Header Pressure" D. TASK STANDARD

1. Satisfactory task completion is indicated when Unit 3 scram air header PCV-5239A is in service and PCV-5239B has been removed from service.
2. Estimated time to complete: 14 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps of ON-108, "Low CRD Scram Air Header Pressure" procedure. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 3 is operating at full power steady state conditions.
2. "SCRAM VALVE PILOT AIR HEADER PRESS HI-LO" annunciator is up on alarm panel 311 D-2.
3. The cause of low scram air header pressure condition is NOT caused by a loss of the Instrument Air system.
4. Scram air header PCV-5239B is presently in service.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to restore the Unit 3 CRD scram air header pressure to approximately 73 psig per procedure ON-108, "Low CRD Scram Air Header Pressure".

Page 4 of 4 SJPM - Header.doc Air Header.doc SJPM 88 - Scram Air Page 4 of 4

H. PERFORMANCE CHECKLIST 3TEP NO STEP ACT STANDARD 1 Obtain a copy of procedure ON-108. P A copy of procedure ON-1 08 is obtained.

2 Verify low scram air header pressure P Scram air header pressure is monitored locally on PI-3-03-229 at CRD flow nest. on PI-3-3-229.

(Cue: PI-3-3-229 indicates 63 psig.)

3 Check normal operation of the inservice P Loading Pressure and control pressure is scram air header pressure control monitored on PCR-3-03-31688B.

regulator by observing loading pressure of approximately 80 psig and control pressure of approximately 75 psig on PCR-3-03-31688B pressure control regulator for PCV-5239B.

(Cue: Loading pressure is approximately 80 psig, control pressure is 63 psig.)

  • 4 Adjust PCR knob (red knob) clockwise to S PCR-3-03-31688B red knob is turned raise scram air header pressure to 67 to clockwise while observe PI-3-3-229 until 75 psig on PI-3-03-229. the knob will not turn further.

(Cue: Red knob on PCR-3-03-31688B is turned (clockwise) until it will not turn further, PI-3-3-229 indicates 65 psig.)

        • NOTE****

If requested the evaluator will serve as the second equipment operator to monitor pressure.

  • 5 Open HV-3-3-31681A, Instr Air Inlet Block S HV-3-3-31681A handwheel is turned Vv to PCV-3-03-5239A. COUNTERCLOCKWISE until resistance of valve backseat is felt.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE] until stem length above valve yoke rises 1 inch, then will not turn.)

  • 6 Open HV-3-3-31682A, Instr Air Outlet S HV-3-3-31682A handwheel is turned Block Vv from PCV-3-03-5239A. COUNTERCLOCKWISE until resistance of valve backseat is felt.

is turned (Cue: Valve handwheel

[COUNTERCLOCKWISE] until stem length above valve yoke rises 1 inch, then will not turn.)

SJPM 8 - Scram Air Header.doc Page 5 of 5

r- ________

STEP NO STEP ACT STANDARD

  • 7 Open HV-3-3-31686A, Instr Air Back S HV-3-3-31686A handwheel is turned Pressure to PCV-5239A. COUNTERCLOCKWISE until resistance of valve backseat is felt.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE] until stem length above valve yoke rises 1 inch, then will not turn.)

  • 8 Slowly open HV-3-3-31685A, Instrument S HV-3-3-31685A handwheel is turned Air Block Valve to PCV-5239A. COUNTERCLOCKWISE slowly until resistance of valve backseat is felt.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE] until stem length above valve yoke rises 1 inch, then will not turn.)

  • 9 Adjust scram air header pressure to S PCR-3-03-31688A is manipulated to between 67 and 75 psig using the red adjust scram air header pressure knob on PCR-3-03-31688A. monitored on PI-3-03-229.

(Cue: Red knob on PCR-3-03-31688A is adjusted. Scram air header pressure is 73

__ _ psig.)

10 Close HV-3-3-31685B, Instrument Air S HV-3-3-31685B handwheel is turned Block Valve to PCV-5239B. CLOCKWISE until resistance of valve seat is felt.

(Cue: Valve handwheel is turned

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

11 Close HV-3-3-31686B, Instr Air Back S HV-3-3-31686B handwheel is turned Pressure to PCV-5239B. CLOCKWISE until resistance of valve seat is felt.

(Cue: Valve handwheel is turned

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

Page 6 of 6 SJPM 88 - Scram Air SJPM - Header.doc Air Header.doc Page 6 of 6

I I STEP NO STEP ACT STANDARD 12 Slowly close HV-3-3-31681B, Instr Air Inlet S HV-3-3-31681B handwheel is Block Vv to PCV-5239B. turned CLOCKWISE slowly until resis tance of valve seat is felt.

(Cue: Valve handwheel is turned

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

13 Close HV-3-3-31682B, Instr Air Outlet S HV-3-3-31682B handwheel is turned Block Vv from PCV-5239B. CLOCKWISE until resistance of valve seat is felt.

(Cue: Valve handwheel is turned

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

14 Verify proper operation of the standby P Loading Pressure and Control Pressure is scram air header PCR, PCR-3-03-31688B monitored on PCR-3-03-31688B.

"Pressure Control Regulator for PCV 5239B" by observing Loading Pressure of approximately 80 psig and Control Pressure of 75 psig.

(Cue: Loading pressure is approximately 80 psig, Control Pressure is 75 psig.)

15 Verify scam air header pressure on PI P Scram air header pressure is monitored 03-229 at the CRD flow nest is satisfactory on PI-3-03-229.

(67 to 75 psig).

(Cue: Scram air header pressure is 73 psig on PI-3-03-229.)

16 Inform Control Room of task completion. S Task completion reported using telephone, hand held radio or GAI-TRONICS page (Cue: Control Room acknowledges system.

report.)

Page 7 of 7 SJPM - Air Header.doc SJPM 88 - Scram Air Page7 of7

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

1. TERMINATING CUE When Unit 3 scram air header PCV-5239A is in service and PCV-5239B has been removed from service, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

Page 8 of 8 SJPM 8 SJPM 8 - Scram Air Header.doc Scram Air Header.doc Page 8 of 8

TASK CONDITIONSIPREREQUISITES

1. Unit 3 is operating at full power steady state conditions.
2. "SCRAM VALVE PILOT AIR HEADER PRESS HI-LO" annunciator is up on alarm panel 311 D-2.
3. The cause of low scram air header pressure condition is NOT caused by a loss of the Instrument Air system.
4. Scram air header PCV-5239B is presently in service.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to restore the Unit 3 CRD scram air header pressure to approximately 73 psig per procedure ON-108, "Low CRD Scram Air Header Pressure".

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2170270499/ PLOR-056P K/A: 21700069 URO: 3.9 SRO: 3.5 TASK DESCRIPTION: Resetting a RCIC Mechanical Overspeed Trip 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.

rage . OT PLOR056P RevOl 4.doc PLORO56P Rev014.doc w-age a oT a

B. TOOLS AND EQUIPMENT None C. REFERENCES SO 13.7.A-2 Rev. 11, "Recovery from RCIC System Isolation or Turbine Trip" D. TASK STANDARD

1. Satisfactory task completion is indicated when the Unit 2 RCIC Trip Throttle Valve is reset.
2. Estimated time to complete: 14 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to reset the Unit 2 RCIC Trip Throttle Valve using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 plant startup in progress; reactor pressure is 150 psig.

__ 2. RCIC turbine overspeed trip occurred during performance of the RCIC flowrate test at 150 psig.

3. The cause of the turbine overspeed trip has been corrected.

G. INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to reset the Unit 2 RCIC Trip Throttle Valve per step 4.3.4 of procedure SO 13.7.A-2, "Recovery from RCIC System Isolation or Turbine Trip". All prior procedure steps have been completed.

Page 4 of 5 RevOl 4.doc PLORO56P Rev014.doc PLOR056P Page 4 of 5

H. PERFORMANCE CHECKLIST iSTEP STEP ACT STANDARD

.NO I Obtain a copy of procedure SO 13.7.A-2. P A copy of procedure SO 13.7.A-2 is obtained.

  • 2 Pull and hold connecting rod toward Trip- S RCIC mechanical overspeed trip Throttle Valve. Connecting Rod is pulled towards the Trip-Throttle Valve.

(Cue: Connecting rod is pulled toward Trip-Throttle Valve and held.)

3 While holding connecting rod, verify P Visually verify tappet is retracted into tappet retracts into housing. housing.

(Cue: Tappet is retracted into housing.)

4 Slowly release connecting rod. S Connecting rod is released slowly.

(Cue: Connecting rod has been released.)

5 Verify proper contact of head lever and P Compare contact of head lever and tappet as shown in Figure 1. tappet with Figure 1.

(Cue: Head lever and tappet show proper contact.)

6 Verify that the Trip-Throttle Valve latch P Compare latch lever fully engaged as lever is fully engaged with the trip hook as shown in Figure 1.

shown in Figure 1.

(Cue: Trip-Throttle Valve latch lever is Ifully engaged.)

7 Inform Control Room Supervisor of task S Task completion reported using hand completion. held radio, GAI-TRONICS page system, or plant telephone.

(Cue: Control Room Supervisor I acknowledges report.)

Under "ACT' P - must perform S - must simulate

1. TERMINATING CUE When the Unit 2 RCIC Trip-Throttle Valve is reset, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

Page 5 of 5 PLORoS6P Rev014.doc PLOR056P RevOl 4.doc Page 5 of 5

TASK CONDITIONS/PREREQUISITES

1. Unit 2 plant startup in progress; reactor pressure is 150 psig.
2. RCIC turbine overspeed trip occurred during performance of the RCIC flowrate test at 150 psig.
3. The cause of the turbine overspeed trip has been corrected.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to reset the Unit 2 RCIC Trip Throttle Valve per step 4.3.4 of procedure SO 13.7.A-2, "Recovery from RCIC System Isolation or Turbine Trip". All prior procedure steps have been completed.

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2390110401 / PLOR-313PA K/A: 239001G.09 URO: X.X SRO: X.X TASK DESCRIPTION: Closing a Stuck Open MSIV - Alternate Path (Unit 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.

MSIv.doc open MSIV.doc Page 3 of 3 SJPM SJPM 10 - Stuck open 10 - Stuck Page 3 of 3

B. TOOLS AND EQUIPMENT

1. Insulated Fuse Pullers
2. Radio C. REFERENCES AO 1A.2-3, Rev. 6, "Closing a Stuck Open Outboard Main Steam Isolation Valve" D. TASK STANDARD
1. Satisfactory task completion is indicated when the Unit 3 Reactor Building 135' Elevation Instrument Air headers have been vented.
2. Estimated time to complete: 22 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to close the stuck open outboard MSIVs using AO 1A.2-3, "Closing a Stuck Open Outboard Main Steam Isolation Valve". I will describe initial plant conditions and provide you access to the materials required to complete this task.

CONDITIONS/PREREQUISITES

1. Unit 3 has just been manually scrammed (by placing the Mode Switch in "Shutdown").
2. RPV level is -175 inches (Group 1 isolation signal is present).
3. All outboard MSIVs failed to isolate.
4. Proper operation of SGIG system has been verified in accordance with SO 16B.8.A-3, "Backup Seismic Instrument Nitrogen System Routine Inspection".
5. Radiological conditions do NOT allow entry into the Outboard MSIV Room.

G. INITIATING CUE The Control Room Supervisor directs you to close the Unit 3 outboard MSIVs in accordance with AO 1A.2-3, "Closing a Stuck Open Outboard Main Steam Isolation Valve", beginning with step 4.1.

MSIV.doc Page 4 of 4 SJPM -

Stuck open 10 - Stuck SJPM 10 open MSIV.doc Page 4 of 4

H. PERFORMANCE CHECKLIST STEP 11 Obtain a copy of procedure AO 1A.2-3 11 a set of insulated fuse pullers.

Examinee should utilize sections 4.1 AND 4.3 of AO IA.2-3.

2 Open panel 30C042 front panel doors. P Door handle turned, doors pulled outward to gain access to the outboard MSIV AC (Cue: Panel 30C042 doors are open.) and DC solenoid valve fuses at the front of panel 30C042 in the Cable Spreading Room.

3 Pull the outboard MSIV AC solenoid valve S Fuse puller is attached to outboard MSIV fuse 16A-F12B. AC solenoid valve fuse 16A-F12B fuse if pulled outward until fuse is free of fuse (Cue: Fuse is removed.) holder.

4 Direct the Unit Reactor Operator to S Unit Reactor Operator is contacted to monitor outboard MSIV position indication, monitor outboard MSIV position indication.

(Cue: Outboard MSIVs are open, continue with the procedure.)

5 Pull the outboard MSIV DC solenoid valve S Fuse puller is attached to outboard MSIV fuse 16A-F11B. DC solenoid valve fuse 16A-F 1 B. Fuse is pulled outward until fuse is free of fuse hnrdlrcr

______ ~Uum I Q QI I~IIIJV%-,... '1..

6 Direct the Unit Reactor Operator to S Unit Reactor Operator is contacted to monitor Main Steam line flow using FI monitor Main Steam line flow on FI-3-06 06-088A,B,C,D on panel 30C008A. 088A,B,C,D at panel 30C008A.

(Cue: Main Steam line FI-3-06 088A,B,C,D are NOT reading downscale.

Position indication for all outboard MSIVs has been lost.)

7 Install fuse 16A-F1 1 B. S Fuse puller is attached to outboard MSIV DC solenoid valve fuse 16A-FI I B. Fuse (Cue: Fuse is installed.) is inserted until fuse is installed in fuse i holder.

8 Close panel 30C042 front panel doors. P Door closed and relatched using handle.

(Cue: Panel 30C042 doors are closed.)

9 Direct the Unit Reactor Operator to verify S Unit Reactor Operator is contacted to RWCU isolation. verify RWCU isolation.

(Cue: RWCU is isolated.)

SJPM 10 - Stuck open MSIV.doc Page 5 of 5

STEP STEP ACT STANDARD NO I 10 Direct the Unit Reactor Operator to open S Unit Reactor Operator is contacted to Backup N2 to ADS valves SV-9130A(B) in verify Backup N2 to ADS valves SV accordance with SO 16A.7.A-3. 9130A(B) in accordance with SO 16A.7.A 3.

(Cue: SV-9130A(B) are open in accordance with SO 16A.7.A-3. If asked to verify proper operation of SGIG system, then report that the SGIG system is operating properly in accordance with SO 16B.8.A-3.)

"*11 Close Instrument Air A(B) Header Isolation S HV-3-36B-56981A and HV-3-36B-56981 B valves HV-3-36B-56981A AND HV-3-36B- handwheels turned clockwise until the 56981 B. resistance of the valve seats are felt at the 3B Recirc MG Set area.

(Cue: The valve handwheels have been turned clockwise until they will turn no further.)

12 Verify open Instrument Air Supply to DT S An attempt is made to turn HV-3-36B 5695 Inlet Block valve HV-3-36B-54642. 54642 handwheel is turned slightly in the clockwise direction and then turned (Cue: The valve handwheel is turned counterclockwise to the original position at slightly in the clockwise direction and then the 3B Recirc MG Set area.

turned counterclockwise to the original position.

13 Verify open Instrument Air Supply to DT S An attempt is made to turn HV-3-363 5696 inlet block valve HV-3-36B-54643. 54643 handwheel is turned slightly in the clockwise direction and then turned (Cue: The valve handwheel is turned counterclockwise to the original position at slightly in the clockwise direction and then the 3B Recirc MG Set area.

turned counterclockwise to the original position.

14 Notify the Control Room that venting is S Unit Reactor Operator is contacted and commencing and to perform more frequent notified of venting and MSIV position monitoring of MSIV position. monitoring.

(Cue: Control Room acknowledges notification.)

"*15 Simultaneously press and hold Drain Trap S Drain Trap Bypass pushbuttons HS-3 Bypass switches HS-3-36B-5695 AND 36B-5695 AND HS-3-36B-5696 are HS-3-36B-5696. simultaneously depressed and held at the 3B Recirc MG Set area.

(Cue: HS-3-36B-5695 AND HS-3-36B 5696 are simultaneously depressed and held. You hear air flowing from both Drain Traps. The sound of the air flowing IN Ithrough the drain traps is diminishing.)

MSIV.doc Page 6 of 6 SJPM SJ PM 10 - Stuck open MSIVMdoc

- Page 6 of 6

STEP STEP ACT STANDARD NO I I I "16 When it is reported that all Unit 3 Outboard S Drain Trap Bypass pushbuttons HS-3 MSIVs are closed, then release both Drain 36B-5695 AND HS-3-36B-5696 are Trap Pushbuttons HS-3-36B-5695 and released in the 3B Recirc MG Set area.

HS-3-36B-5696.

(Cue: You hear a report through your radio that all of the Unit 3 Outboard MSIVs are closed and both Drain Trap Pushbuttons HS-3-36B-5695(6) may be 17 Inform Control Room Supervisor of task S Task completion reported using telephone, completion. hand held radio or GAI-TRONICS page system.

(Cue: Control Room Supervisor acknow ledges report. Outboard MSIVs are closed.)

Under "ACT" P - must perform S - must simulate I. TERMINATING CUE When the Unit 3 outboard MSIVs are closed, the Control Room Supervisor should be

-* informed. The evaluator will then terminate the exercise.

Page 7 017 Stuck open MSIV.doc 10 - Stuck SJPM 10 - Page 7 of 7

TASK CON DITIONS/PREREQUISITES

1. Unit 3 has just been manually scrammed (by placing the Mode Switch in "Shutdown").
2. RPV level is -175 inches (Group 1 isolation signal is present).
3. All outboard MSIVs failed to isolate.
4. Proper operation of SGIG system has been verified in accordance with SO 16B.8.A-3, "Backup Seismic Instrument Nitrogen System Routine Inspection".
5. Radiological conditions do NOT allow entry into the Outboard MSIV Room.

INITIATING CUE The Control Room Supervisor directs you to close the Unit 3 outboard MSIVs in accordance with AO 1A.2-3, "Closing a Stuck Open Outboard Main Steam Isolation Valve", beginning with step 4.1.