ML021610329

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Draft - Section B Operating
ML021610329
Person / Time
Site: Oyster Creek
Issue date: 05/31/2002
From: Hackenberg J
AmerGen Energy Co
To: Conte R
NRC/RGN-I/DRS/OSB
References
50-219/02301
Download: ML021610329 (48)
v • d • e


Text

AmerGen..

An ExelonBnTitish Energy Company JOB PERFORMANCE MEASURE 201.02 Validation Time 15 minutes I Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

Comments I

II i,

Title:

Respond to an Uncoupled Rod at > 10% power Task: Respond to an uncoupled rod at > 10% power 2170401007 KA# 201003 A2.02 RATING:

RO - 3.7 SRO - 3.8 NO C

e 11 I

I I

I I

JPM 201.02 REFERENCE SECTION:

GENERAL TOOLS AND EQUIPMENT:

None GENERAL

REFERENCES:

Procedure 302.2, Control Rod Drive Manual Control System ABN 3200.06, Abnormal Control Rod Motion, RAP H-5-a, Rod Drift TASK STANDARD:

Rod 14-15 returned to position 48 and recoupled CRITICAL ELEMENTS: (*)

2,5,9 I,

TASK CONDITIONS:

Reactor Recirculation Flow Has Been Reduced by 1.5 X 104 to-provide Additional Margin for Thermal Limits during rod maneuvers for core shaping per core engineering guidance. Control rod 14-15 was the last rod maneuvered from notch position 30 to 48 to complete shaping maneuver. Reactor Engineer is present in the control room.

Rev. 18 Rev. 12 Rev. 111 INITIATING CUES:

Rod 14-15 has just been notched from position 30 to 48. As US, I am directing you to perform a rod coupling check in accordance with Procedure 302.2, Control Rod Drive Manual Control System page 2

I page 6 TASK CONDITIONS:

Reactor Recirculation Flow Has Been Reduced by 1.5 X 1 b 4 to provide Additional Margin for Thermal Limits during rod maneuvers for core shaping per core engineering guidance. Control rod 14-15 was the last rod maneuvered from notch position 30 to 48 to complete shaping maneuver. Reactor Engineer is present in the control room.

INITIATING CUES:

Rod 34-27 has just been notched from position 30 to 48. As US, I am directing you to perform a rod coupling check in accordance with Procedure 302.2, Control Rod Drive Manual Control System

JPM 201.02

"`-

PERFORMANCE SECTION:

START TIME page 3 TASK CONDITIONS:

Reactor Recirculation Flow Has Been Reduced by 1.5 X 104to provide Additional Margin for Thermal Limits during rod maneuvers for core shaping per core engineering guidance. Control rod 14-15 was the last rod maneuvered from notch position 30 to 48 to complete shaping maneuver. Reactor Engineer is present in the control room.

INITIATING CUES:

Rod 14-15 has just been notched from position 30 to 48. As US, I am directing you to perform a rod coupling check in accordance with Procedure 302.2, Control Rod Drive Manual Control System PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

1. Obtain current copy of Obtains Procedure 302.2 step 4.3.8 procedure
  • 2 Perform coupling On panel 4F takes rod control switch to check "Rod Out Notch" simultaneous with notch override switch to "Notch Override"
3. Verifies rod is at notch On Panel 4F, observes control rod 14-15 position 48 and coupled indicates no numerical digital readout with BLACK backlighting and annunciator H-5-a, Rod Overtravel, alarms
4. Obtains controlled copy of Obtains Procedure ABN-3200.06, step procedure 3.5
  • 5. Inserts control rod Takes rod control switch to "Rod In" or the notch override switch to the' "Emergency In" position on Panel 4F until a response is observed on the Nuclear Instruments or the rod is full in.

JPM 201.02 PERFORMANCE CHECKLIST 6

Ceases control rod motion 7

Notifies Reactor Engineerihg 8

Monitors nuclear instrumentation and withdraws rod 14-15 to Notch 48 STANDARD INITIAL SAT/UNSAT Releases rod control switch to allow it to spring - return to unlabeled mid position 4-I Informs Reactor Engineering Monitors reactor period and flux level, withdraws rod 14-15 to Notch 48

  • 9 Perform coupling On panel 4F takes rod control switch to check "Rod Out Notch" simultaneous with notch override switch to "Notch Override"
10. Verifies rod is at notch On Panel 4F, observes control rod 14-15 position 48 and coupled indicates a continuous digital readout of "48" with RED backlighting COMPLETION TIME page 4

/

JOB PERFORMANCE MEASURE An Exelon/British Energy Company 259.ON

Title:

Start the Third Feedwater Pump from Control Room Task: Start and Operate the Reactor Feed System.

2590101003 KA# 259001 A4.02 RATING:

RO-3.9 SRO-3.7 Validation Time 15 minutes Time Critical NO DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

4 NOTE: Directions are only required once in a given JPM session.

Comments I1 1

II

JPM 259.ON REFERENCE SECTION:

GENERAL TOOLS AND EQUIPMENT:

none GENERAL

REFERENCES:

Procedure 317, Feedwater System, section 7.0, Rev. 62 TASK STANDARD:

Third Feedwater pump in service.

CRITICAL ELEMENTS: (*)

5, 6, 7, 11, 13, 15,17 2

TASK CONDITIONS:

Plant is at 70% power.

The 'A' & 'C' Reactor Feedwater pumps are in service.

The 'B' Reactor Feedwater pump is in standby INITIATING CUES:

As the Control Room US I am directing you to start the 'B' Reactor Feedwater pump in accordance with Procedure 317, Feedwater System, section 7.0.

JPM 259.ON PERFORMANCE SECTION:

START TIME PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

1. Obtains current copy of Procedure 317, section 7.0 is obtained procedure
2.

Reviews Prerequisites Reviews Prerequisites

3. Reviews Precautions and Reviews Precautions and Limitations.

Limitations

  • 6. Confirms Contrler fork Confirms Contrler fork MRFetvav, V-2D-8, is i Outlet..

v

.LS D

C O E MRFV is in MAN MAN

  • 7. Confirms MRFV is Confirms MRFV is CLOSED, indicating '0.0' CLOSED.

valve position.

8.

Directs Equipment Operator to verify Feed pump status Directs Equipment Operator to verify:

"* Oil level for motor bearings

"* Oil level for pump oil reservoir

  • Ventilation for pump motor 3

TASK CONDITIONS:

Plant is at 70% power.

The 'A' & 'C' Reactor Feedwater pumps are in service.

The 'B' Reactor Feedwater pump is in standby.

INITIATING CUES:

As the Control Room US I am directing you to start the 'B' Reactor Feedwater pump in accordance with Procedure 317, Feedwater System, section 7.0.

JPM 259.ON u PERFORMANCE

  • CHECKLIST I

STANDARDI SINITIAL

9. UE VeruipmCntOproltorm Veprs ily Coevels r aooceptiabtiondsetlt:ni nn indications.
  • Feed pump suction pressure
  • Feed pump discharge pressure_____
10.

Verify sufficient bus Verifies that the bus voltage for the pump to

voltage, be started is at least 4100V. At 8F/9F, verifies 41 60V Bus 1 B voltage is greater than 4100.

"*11.

Start the pump Place pump Start/Stop switch for 'B' Feed pump to START. Release the switch when pumps amps indicate breaker closure

12.

Secure Aux Oil pump When proper operation of the Feed pump is verified, direct the Equipment Operator to secure the Aux Oil pump_____

"*13.

Open the Heater Bank At 5F/6F, open the Heater Bank Outlet valve, Outlet valve V-2-1 1, by holding the control switch to OPEN.

14.

Operate pump for 10 Operate the Feed pump for 10 minutes minutes I

that flow in the other strings automatically/

______________________compensate for the flow change.

16.~~~c T.iyh MnFo

16.

Verify the tl M

Row VWhen flow in the string exceeds 0.5E6 valve closes Ibm/hr, verify the Mn Flow valve, V-2-1 9, closes

"*17. Place controller in AUTO When S & V display are matched, place MFRV Controller in AUTO COMPLETION TIME 4

TASK CONDITIONS:

Plant is at 70% power.

The 'A' & 'C' Reactor Feedwater pumps are in service.

The 'B' Reactor Feedwater pump is in standby.

INITIATING CUES:

As the Control Room US I am directing you to start the 'B' Reactor Feedwater pump in accordance with Procedure 317, Feedwater System, section 7.0.

6

AmerGen.

An Exelon/British Energy Company JOB PERFORMANCE MEASURE 239.01

Title:

Bypass the Lo-Lo Isolation for the Main Steam Isolation Valves Task:

Defeat Reactor Isolation Interlock

-12000501439 KA# 295031 EA1.05 RATING:

RO-- 4.3 SRO-4.3 Validation Time 12 minutes Time Critical I

NO DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

Comments I

I1 II 11

ERENCE SECTION:

TASK CONDITIONS:

Bypassing of the MSIV Lo-Lo level isolation interlock has been directed by the EOPs GENERAL TOOLS AND EQUIPMENT:

EOP Bypass Plugs GENERAL

REFERENCES:

2000-EMG 3200.01 B, RPV Control with ATWS, Rev. 12 Support Procedure 16 TASK STANDARD:

Lo-Lo MSIV isolation bypassed CRITICAL ELEMENTS: (*)

22,3,4,5 INITIATING CUES:

As US, I am directing you to bypass the Lo-Lo MSIV isolation-per 2000-EMG 3200.01 B, RPV Control - With ATWS, Level/Power Leg using Support Procedure 16.

/

239.01

° 1FORMANCE SECTION:

START TIME PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

1.

Obtain controlled copy of Support Procedure 16 obtained procedure

  • 2. Obtain bypass plugs Obtains four(4) bypass plugs from the EOP Station
  • 3. Inserts bypass plugs in Opens EOP bypass panel in the rear of panel 6R Panel 6R.

"* Inserts bypass plug in position BP1

"* Inserts bypass plug in position BP2

  • 4. Inserts bypass plugs in Opens EOP bypass panel in the rear of panel 7R Panel 7R.

"* Inserts bypass plug in position BP1

"* Inserts bypass plug in position BP2

  • 5. Bypasses the At Panel 11 F, places the INSTRUMENT INSTRUMENT AIR AIR ISOLATION VALVE BYPASS switch in ISOLATION BYPASS
6.

Informs LOS Informs LOS that the Lo-Lo level MSIV Isolation interlock has been bypassed COMPLETION TIME

TASK CONDITIONS:

Bypassing of the MSIV Lo-Lo level isolation interlock has been directed by the EOPs INITIATING CUES:

As US, I am directing you to bypass the Lo-Lo MSIV isolation per 2000-EMG 3200.01 B, RPV Control - With ATWS, Level/Power Leg using Support Procedure 16.

/

AmerGen, M An Exelon/British Energy Company JOB PERFORMANCE MEASURE 202.10

Title:

Respond to a Tripped Recirc Pump with 5 Recirc Pumps Operating (Alternate Path)

Task: Respond to a Tripped Recirc Pump with 5 Recirc Pumps 2020401404 Operating KA# 202001 A2.03 RATING:

RO - 3.6 SRO - 3.7 Validation Time - 15 min I Alternate Path - Yes I Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NO TE: Directions are only required once in a given JPM session.

I 11 NO I

I 11 11 t

JPM 202.10 REFERENCE SECTION:

GENERAL TOOLS AND EQUIPMENT:

None GENERAL

REFERENCES:

2000-ABN-3200.02, Recirculation Pump Trip, Rev. 30 TASK STANDARD:

Four pumps running in automatic, the other loop idle.

CRITICAL ELEMENTS: (*)

5,6,8 page 2 TASK CONDITIONS:

Reactor power 100%, all systems operating properly.

JPM 202.10 PERFORMANCE SECTION:

START TIME PERFORMANCE CHECKLIST STANDARD INITIAL RAT/I IN5CAT

1. Confirms discharge At Panel 3F, confirms discharge bypass bypass valve for "E" loop valve for "E" loop open.

open

2. Closes "E" pump discharge valve At Panel 3F, takes "E" recirculation pump discharge valve control switch to close.
3. Obtains controlled copy Procedure ABN 3200.02, Section 3.1 of procedure obtained.

4 Determines Discharge At Panel 3F, Determines Discharge Valve Valve will not close will not close.

page 3 TASK CONDITIONS:

Reactor power 100%, all system operating properly.

INITIATING CUE:

Your task will be associated with Recirculation System operation; you are now to respond to any further alarms that are received.

JPM 202.10 PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

  • 5 Closes "E" pump suction At Panel 3F, takes "E" recirculation pump valve suction valve control switch to close.
  • 6. Dispatches Electrician.
7.

Determines loop configuration Dispatches/directs Electrician to attempt to close the discharge valve lAW attachment 3200.02-01.

Determines that the loop can either be placed in an "IDLE" or "ISOLATED" condition.

  • 8.

Opens the suction valve Re-opens the suction valve by taking its control switch to the OPEN position.

9.

Maintain reactor power At Panels 3F and 4F, verifies below rod below rod block setpoint block on power operation curve.

10. Maintains RPV level 155 At Panel 5F/6F, ensures FWC system to 165" maintaining level.
11.

Monitor NIs for At Panel 4F, monitors APRMs.

indication of power oscillation page 4

JPM 202.10 PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

12. Confirms one of the Selects an operating loop for one of the recirc pump suction temp RECIRC PUMP SUCTION TEMPS.

indicators on 3F is selected to an operating loop

13. Verifies did not enter At Panels 3F and 4F, monitors APRMs and exclusion region of the total recirc flow; verifies not in exclusion power operation curve region of power operation curve.
14. Refer to Tech Spec for Uses Tech Spec Sections 3.3.F to limitations on continued determine no limitation or informs Shift plant operations Supervisor to refer to TS 3.3.F.
15. Notify system dispatcher (No notifications because no limitations) of power limitations
16. Notifies designated Notifies Reactor engineer.

Reactor engineer

17. Diagnose the cause of Diagnose the cause of the pump trip lAW the pump trip OPS-3024.22.

~~~~~' l CUE:

(Evaluator) Inform the candddate that another operator will perform dai...............

i..

COMPLETION TIME page 5

TASK CONDITIONS:

page 7 Reactor power 100%, all systems operating properly.

INITIATING CUE:

Your task will be associated with Recirculation System operation; you are now to respond to any further alarms that are received.

AmerGen..

An Exelon/British Energy Company JOB PERFORMANCE MEASURE 226.01 Validation Time 15 minutes I Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NO TE: Directions are only required once in a given JPM session.

I II

Title:

Manually Initiate Containment Spray Task: Manually Initiate Containment Spray 2260101002 KA# 226001 A4.01 RATING:

RO - 3.5 SRO - 3.4 NO i

I 11 II

JPM 226.01 REFERENCE SECTION:

TASK CONDITIONS:

Reactor scrammed, all rods in FWC in "Auto", EPR controlling pressure Drywell temperature greater than 150 degrees F Torus pressure approaching 14 psig GENERAL TOOLS AND EQUIPMENT:

None GENERAL

REFERENCES:

EMG-3200.02, Primary Containment Control - Pressure Rev. 16 Support Procedure 29 TASK STANDARD:

Spraying down the drywell at > 3000 gpm CRITICAL ELEMENTS: (*)

3, 10,11 INITIATING CUES:

As US, I am directing you to manually initiate Containment Spray System I, place one containment spray and ESW pump in operation and maintain 4-12 psig DW pressure JAW Support Procedure 29.

JPM 226.01 PERFORMANCE SECTION:

START TIME PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSA T

1.

Obtain controlled copy of Support Procedure 29, obtained procedure

2.

Verifies all prerequisites Manual Initiation of drywell sprays has are met been directed by the EOPs.

confirming/placing SYSTEM 1 MODE SWITCH in DW SPRAY position.

4.

Verifies selected System At Panel 1 F/2F, verifies that the TORUS aligns properly CLG DISCHARGE valve closes and the DW SPRAY valve opens I

TASK CONDITIONS:

Reactor scrammed, all rods in FWC in AUTO EPR controlling pressure Drywell temperature greater than 150 degrees F Torus pressure approaching 14 psig INITIATING CUES:

As GOS, I am directing you to manually initiate Containment Spray System I, one containment spray and ESW pump operation and maintain 4-12 psig DW pressure lAW Support Procedure 29.

JPM 226.01 PERFORMANCE CHECKLIST STANDARD INITIAL SAt/UNSAT

5.

Confirms Reactor Recirc Confirms ALL Reactor Recirculation Pumps Tripped.

Pumps Tripped on panel 3F.

6.

Confirm the Drywell Confirms the Drywell Cooling fans tripped Cooling fans tripped, on panel 11 R.

7.

Starts "A" containment Simultaneously place Containment Spray spray pump System I Pumps Manual Start Permissive keylock to Position 'A' and Containment Spray Pump 51A Control Switch to START on Panel F/2F

8.

Monitors system Recognizes that 'A' (or 'B') Containment parameters Spray pump (if started) has tripped.

repeat te~ initi ting~cu

.X...

9.

After trip of cont. spray After trip of cont. spray pump selects pump starts another another pump ("'B") and returns to step 3.3 pump "10 Start 'B' containment Simultaneously place Containment Spray spray pump System 1 Pumps Manual Start Permissive keylock to Position 'B' and Containment Spray Pump 51 B Control Switch to START on Panel 1F/2F "11. Starts an associated Starts ESW pump 52A or 52B after ESW pump starting containment spray pump using its control switch

/

JPM 226.01 PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

12. Monitors System Monitors Containment Spray System parameters parameters for proper operation.
13. Confirm RBCCW isolation valves are closed
14. Observes DW pressure On 1 F/2F, Confirm the following RBCCW isolation valves are closed:

"* V-5-147

"* V-5-148

"* V-5-166 V-5-167 Maintains DW pressure between 4-12 psig COMPLETION TIME I

i

\\

TASK CONDITIONS:

Reactor scrammed, all rods in FWC in AUTO EPR controlling pressure Drywell temperature greater than 150 degrees F Torus pressure approaching 14 psig INITIATING CUES:

As GOS, I am directing you to manually initiate Containment Spray System I, one containment spray and ESW pump operation and maintain 4-12 psig DW pressure lAW Support Procedure 29.

AmerGenrm "An Exelon/British Energy Company JOB PERFORMANCE MEASURE 264.01

Title:

Perform Normal Start of EDG from Control Room Task: Manually Start the Emergency Diesel from the Control room.

640101002 KA# 264000 A4.04 RATING:

RO-3.7 SRO-3.7 Validation Time 15 minutes I Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

SNOTE: Directions are only required once in a given JPM session.

1 II 1

i NO U1 I

I I

I

JPM 264.01 REFERENCE SECTION:

GENERAL TOOLS AND EQUIPMENT:

none GENERAL

REFERENCES:

Procedure 341, Emergency Diesel Generator Operation, section 5.0, Rev. 64 TASK STANDARD:

  1. 1 EDG supplying 4160V Bus IC.

CRITICAL ELEMENTS: (*)

8,9,11,12 TASK CONDITIONS:

Plant is operating at power

  1. 1 EDG must be started and run after maintenance work INITIATING CUES:

As the Unit Supervisor, I am directing you to start #1 EDG in accordance with Procedure 341, Emergency Diesel Generator Operation, section 5.0.

I t

6 TASK CONDITIONS:

Plant is operating at power.

  1. 1 EDG must be started and run after maintenance work.

INITIATING CUES:

As the Unit Supervisor, I am directing you to start #1 EDG in accordance with Procedure 341, Emergency Diesel Generator Operation, section 5.0.

f

JPM 264.01 PERFORMANCE SECTION:

TASK CONDITIONS:

Plant is operating at power.

  1. 1 EDG must be started and run after maintenance work.

INITIATING CUES:

As the Unit Supervisor, I am directing you to start #1 EDG in accordance with Procedure 341, Emergency Diesel Generator Operation, section 5.0.

START TIME PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

1. Obtains current copy of Procedure 341, section 5.0 is obtained procedure
2. Reviews Prerequisites Reviews Prerequisites

-3. Reviews Precautions and Reviews Precautions and Limitations.

Limitations in te SARTposition

  • 9. Verify start condition.

Verify the UNIT IDLE & UNIT START lights have illuminated

10. Verify the EDG syncs to the bus and picks up load.

Verifies that the EDG:

Achieves operating speed

"* Synchronizes with the bus

"* Load breaker closes

"* Picks up load 3

I

JPM 264.01 PERFORMANCE CHECKLIST Confirm EDG load STANDARD I.

t Confirm EDG load is 2750 +/- 50 KW. If not, place mode switch to TRANSFER and adjust load using the Governor Control switch INITIAL SAT/UNSAT

"*12. Adjusts EDG KVAR Uses the VOLTAGE/KVAR Control switch to load control KVAR loading to - +1000 KVAR lagging (with a range of +200 to +-2000 KVAR lagging)

14. Monitors EDG Monitors EDG parameters.

parameters.

I

15. Dispatches EO to monitor EDG.

Dispatches EO to monitor EDG locally.

COMPLETION TIME 4

  • *11.
AmerGen, An Exelon/British Energy Company JOB PERFORMANCE MEASURE 261.ON Validation Time 18 minutes Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

II1I

Title:

Confirm Secondary Containment Initiations and Isolations (Alternate Path)

Task: Place the Standby Gas Treatment System in service manually 2610101003 KA# 290001 A2.03 RATING:

RO - 3.4 SRO - 3.6 NO i

11

JPM 261.01 7ERENCE SECTION:

GENERAL TOOLS AND EQUIPMENT:

None GENERAL

REFERENCES:

Procedure 330, Standby Gas Treatment System, Section 4, Rev. 40

-'IASK STANDARD:

Standby Gas Treatment System I operating CRITICAL ELEMENTS: (*)

7,10 TASK CONDITIONS:

Reactor power 100%, all systems are operating properly.

During Spent Fuel operations on Reactor Building 119', Area Radiation Monitors B9 & C9 have alarmed.

Two minutes has elapsed INITIATING CUES:

You have been directed to confirm all isolations and initiations pertaining to these alarms

r, FORMANCE SECTION:

TASK CONDITIONS:

Reactor power 100%, all systems are operating properly.

During Spent Fuel operations on Reactor Building 119', Area Radiation Monitors BW & C9 have alarmed.

Two minutes has elapsed INITIATING CUES:

You have been directed to alarms confirm all isolations and initiations pertaining to these START TIME PERFORMANCE CHECKLIST STANDARD INITIAL I

ý SATIU NSAT

1.

Refer to RAP 1 OF-3-m, 4-Alarm Response Procedure obtained m

2.

Verify Automatic actions Verify Reactor Building HVAC has tripped and recognize SGTS has failed to start

3.

Obtain controlled copy of Procedure 330, Section 4 obtained procedure

4.

Verifies all prerequisites Verifies prerequisites met met

5.

Reviews all applicable precautions and limitations Applicable precautions and limitations reviewed

JPM 261.01 PERFORMANCE CHECKLIST

6.

Confirm SGTS I is selected

  • 7.

Start Exhaust Fan EF-1 -8 Verify proper start STANDARD INITIAL

,AT/AJNRAT On panel 11 R, Confirm SGTS I is selected on the STANDBY GAS SELECT switch t

  • 1-On panel 11 R, place EF-1-8 control switch to HAND On panel 11 R, verify the following:

"* Exhaust Fan EF-1-8 STARTS

"* Inlet valve V-28-23 OPENS

"* Orifice valve V-28-24 OPENS

"* Outlet valve V-28-26 OPENS

9.

Verify flow established When system flow is established, verify:

"* SGTS I orifice valve V-28-24 CLOSES

"" SGTS II orifice valve V-28-28 OPENS

"*10. Close SGTS Crosstie On panel 11 R, place SGTS Crosstie valve control switch to CLOSE and verify green CLOSE light illuminates "qOMPLETION TIME L _____________________________

I _______

i I

TASK CONDITIONS:

Reactor power 100%, all systems are operating properly.

During Spent Fuel operations on Reactor Building 119', Area Radiation Monitors B9 & C9 have alarmed.

Two minutes has elapsed INITIATING CUES:

You have been directed to confirm all isolations and initiations pertaining to these alarms

AmerGen An Exelon/British Energy Company JOB PERFORMANCE MEASURE 308.04 Validation Time 10 Minutes 1 Time Critical DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence.

Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

11 1

11 1

Page 1 of 4

Title:

Transfer Control to LSP 1A2.

Task: Operate the Main Breaker to the Unit Substation 1A2 from LSP 3080401415 1A2.

3080404408 KA# 295016 AA1.07 RATING:

RO_- 4.2 SRO - 4.3 No 11

JPM 308.04 GENERAL TOOLS AND EQUIPMENT:

MB-1 key GENERAL

REFERENCES:

Procedure 346, Operation of the Local and Remote Shutdown Panels, Section 11.0, Rev. 9 TASK STANDARD:

LSP 1A2 is activated with all indications functioning CRITICAL ELEMENTS: (*)

5,6 Page 3 of 4 TASK CONDITIONS:

T=O min.

Reactor operating at 100% power, with the 1-1 RBCCW pump, A CRD pump operating.

T=10 min.

Control Room has been evacuated and all immediate actions performed in accordance with ABN 3200.30, Control Room Evacuation.

The Remote Shutdown Panel has been manned.

4160V Bus 1C is energized from Bus 1A and Breaker 1A2P is closed.

White "125 VDC ON" light lit on LSP-1A2 INITIATING CUES:

The US has directed you to place LSP-1A2 in service in accordance with procedure 346, Operation of the Remote and Local Shutdown Panels, Section 11.0.

I

JPM 308.04 START TIME PERFORMANCE CHECKLIST STANDARD INITIAL SAT/UNSAT

1.

Obtain controlled copy of Obtain controlled copy of procedure procedure.

346.

2.

Verifies all prerequisites are Verifies all prerequisites are met.

met.

3.

Reviews all applicable Reviews all applicable precautions precautions and limitations, and limitations.

4.

Establish communication with From the 'A' 480 switch gear room the Remote Shutdown Panel.

establishes communication between LSP-1A2 and RSP using either a radio, phone or paging system.

  • 5.

Places the Normal/Bypass At USS 1A2, places the switch for RBCCW pump 1-1 in Normal/Bypass switch for RBCCW the "Bypass" position.

pump 1-1 in BYPASS.

CUEPacs:h NormV~yal/yas AtU Awlceih switch for............pc1 -1Rin Nopmpl/Bypass sitch fo RBC.

  • 6.

Takes local control of LSP 1A2.

Uses local key from padlock to place the "Control Transfer Switch" to ALTERNATE on panel LSP 1A2.

j.~ti.~sudw o~n ui re F

ih

i. t ~CDpm

.e O..

~t

7.

Confirms closed main breaker Confirms 1A2M shut on panel LSP IA2M.

1A2.

e:

g.

t

!iiii iii i iiiiiiiiiii iiiiii i i COMPLETION TIME 11, Page 4 of 4

Page 5 of 4 TASK CONDITIONS:

T=O min.

Reactor operating at 100% power, with the 1-1 RBCCW pump, A CRD pump operating.

T=10 min.

Control Room has been evacuated and all immediate actions performed in accordance with ABN 3200.30, Control Room Evacuation.

The Remote Shutdown Panel has been manned.

4160V Bus 1C is energized from Bus 1A and Breaker 1A2P is closed.

- White "125 VDC ON" light lit on LSP-1A2 INITIATING CUES:

The US has directed you to place LSP-1A2 in service in accordance with procedure 346, Operation of the Remote and Local Shutdown Panels, Section 11.0.

/ /

AmerGen.

An Exelorn/British Energy Company

Title:

Line Up to Vent the Torus Through the Hardened Vent.

Task: Vent the Drywell with Isolation Signals Present.

2230501411 2230504001 KA.# 295024A1. 14 RATING:

RO - a.5 SRO - 3.5 Validation Time 12 minutes I Time Critical NO JOB PERFORMANCE MEASURE 13,311 not DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

Comments II II Page I of 4 1

1I I

JPM 223.03 Task Conditions:

Torus level is 173" Drywell pressure 53 psig Hydrogen concentration less than 1.5 %

CHRRMS indicates 1 x 103 Exhaust fans 1-5 and 1-7 are operating GENERAL TOOLS AND EQUIPMENT:

MB key Radio GENERAL

REFERENCES:

EMG-3200.02, Primary Containment Control, Rev 16 Support Procedure 35 TASK STANDARD:

The Torus is lined up to be vented through the hardened vent CRITICAL ELEMENTS: (*)

2,3,4 Initiating Cues:

The US directs you to prepare the Torus to be vented through the hardened vent per Support Procedure 35.

Page 2 of 4

JPM 223.03 PERFORMANCE SECTION:

START TIME PERFORMANCE STANDARD INITIAL CHECKLIST SAT/

UNSAT

1.

Obtain controlled copy Obtains support procedure 35 of procedure C::::ep:.Z

,: === ====

K=

=

e

.===e=ed th..prov======k sheet

  • 2.

Confirms N2 purge Confirms closed N2 purge valve, V-23-195.

valve, V-23-195, (A rising stem gate valve located outside closed RX Bldg NE corner) purge inlet valve, V operator 90 degrees clockwise.

357 (Outside RX Bldg NE corner) i~~UE..

3O

  • 4.

Unlock and open the Unlocks hardened vent stack isolation Shardened vent stack valve, V-23-358, and rotates operator 90 p isolation valve, V degrees counterclockwise.

358 (Outside RX Bldg NE corner)

5.

Informs US the Torus Uses radio or page system to inform US is ready to vented the hardened vent path is lined up through the hardened vent COMPLETION TIME

/

Page 3 of 4

Task Conditions:

.Page 4 of 4

\\K Torus level is 173" Drywell pressue 53 psig Hydrogen concentration less than 1.5 %

CHRRMS indicates 1 x 103 Exhaust fans 1-5 and 1-7 are operating Initiating Cues:

The GSSlGOS directs you to prepare the Torus to be vented through the hardened vent per Support Procedure 35.

JPM 279.06 JOB PERFORMANCE AmerGen.S MEASURE An Exelon/British Energy Company 279.06

Title:

Manually Scram the Reactor by Venting the Scram Air Header Task: Manually Scram the Reactor by Venting the Scram Air 2790501401 Header 2790504001 KA# 212000 A4.11 RATING:

RO - 3.7 SRO - 3.7 Validation Time 12 minutes Time Critical NO liiame Social Secuiity Number DIRECTIONS TO TRAINEE:

Before you start, I will state the task conditions and initiating cues and fully answer any questions. To complete this task successfully, you must perform or simulate each critical element correctly and demonstrate proper procedural adherence. Peer checking will not be provided during the performance of required tasks.

NOTE: Directions are only required once in a given JPM session.

11 11 Page 1 of 4 i

11

JPM 279.06 GENERAL TOOLS AND EQUIPMENT:

None GENERAL

REFERENCES:

EMG-3200.01 B, RPV Control - with ATWS, Rev. 12 Support Procedure 21, Alternate Insertion of Control Rods, step 4.1 TASK STANDARD:

Rods no longer moving in and system air pressure restored CRITICAL ELEMENTS: (*)

2,3, 5&6 Page 2 of 4 TASK CONDITIONS:

Plant has experienced a failure to scram and de-energizing the scram solenoids was unsuccessful in scramming the reactor INITIATING CUES:

The US directs you to vent the scram air header using support procedure 21, step 4.1.

/

JPM 279.06 START TIME PERFORMANCE CHECKLIST r STANDARD INITIAL I_

SAT/UNSAT

1.

Obtain controlled copy of Obtains support procedure 21, Step procedure 4.1

  • 2.

Close V-6-175, Scram Air Header Isolation.

Closes V-6-175, Scram Air Isolation, Rx Bldg 23' east side of drywell.

  • 3.

Open V-6-409, Scram Air Opens V-6-409, Scram Air Header Header Vent Valve.

Vent, Rx Bldg 23' east side of drywell.

Communicate with the Establishes communication with the Control Room.

Control Room via paging system, radio or telephone and reports scram air header vented. Requests to know when rods are finished moving in.

  • 5.

Close V-6-409, Scram Air Closes V-6-409, (Scram Air Header Header Vent Valve Vent)

  • 6.

Open V-6-175, Scram Air Opens V-6-175, (Scram Air Isolation)

Header Isolation Valve I

COMPLETION TIME Page 3 of 4 4.

'K

Page 4 of 4 TASK CONDITIONS:

Plant has experienced a failure to scram and de-energizing the scram solenoids was unsuccessful in scramming the reactor.

INITIATING CUES:

The US directs you to vent the scram air header using support procedure 21, step 4.1.

!

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