Text

Initial Exam 2011-301 Draft Sim/IN-Plant JPMs
	ML110980772
Person / Time
Site:	Browns Ferry
Issue date:	04/04/2011
From:	; NRC/RGN-II/DRS/OLB
To:	; Tennessee Valley Authority
References
	50-259/11-301, 50-260/11-301, 50-296/11-301
	Download: ML110980772 (237)
	v • d • e

JPM a PAGE 1 OF 7 OPERATOR:

RO SRO DATE:________

JPM NUMBER: a TASK NUMBER: U-085-AB-03 TASK TITLE: CRD Pump Trip at <900 psig Reactor Pressure KJA NUMBER: 201001 A2.01 KJA RATING: RO 3.2 SRO 3.3 TASK STANDARD: Withdraws Control Rod, if withdrawn to position 48; performs a coupling check, ranges IRMs to prevent a full scram signal, and inserts a manual scram; when unable to restore CRD drive water pressure >940 psig.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-01-85 and 2-AOI-85-3 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are the Reactor Operator. Plant startup is in progress. Last completed Control Rod was 3 8-43 from 16 to 48, Sequence A2 Group 12. Other Operators are assigned heat up rate monitoring and Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to continue withdrawing controls rods for plant startup, the next control rod is 30-35. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

JPM a PAGE 3 OF 16 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are the Reactor Operator. Plant startup is in progress. Last completed Control Rod was 3 8-43 from 16 to 48, Sequence A2 Group 12. Other Operators are assigned heat up rate monitoring and Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to continue withdrawing controls rods for plant startup, the next control rod is 30-3 5. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

NRC Examiner Steps 1 through 5 are for single notch withdrawal, steps 6 through 15 are for continuous withdrawal.

JPM a PAGE 4 OF 16 START TiME____

Performance Step 1: Critical X Not Critical 6.6.3 Control Rod Notch Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 2-XS-85-40.

Standard:

Selects Control Rod 3 8-43 by depressing 3 8-43 pushbutton.

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 2: Critical Not Critical

[2] OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMiNATED.

White light on the Full Core Display ILLUMiNATED.

Rod Out Permit light ILLUMINATED.

Standard:

Observes the above indications.

SAT UNSAT N/A COMMENTS:

JPM a PAGE 5 OF 16 Performance Step 3: Critical Not Critical X

[3] VERIFY ROD WORTH MINIMIZER operable and LATCHED in to correct ROD GROUP, when Rod Worth Minimizer is enforcing.

Standard:

Verifies Rod Worth Minimizer responded correctly and verified Control Rod 3 8-43 is going from position 16 to 48.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 4: Critical X Not Critical

[4] PLACE CRD CONTROL SWITCH, 2-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[5] OBSERVE the control rod settles into the desired position and the ROD SETTLE light extinguishes.

Standard:

Withdraws control rod 3 8-43.

SAT UNSAT N/A COMMENTS:

JPM a PAGE 6 OF 16 Performance Step 5: Critical X Not Critical

[6] IF control rod is notch withdrawn to rod notch Position 48, THEN PERFORM control rod coupling integrity check as follows:

[6.1] PLACE CRD CONTROL SWITCH, 2-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[6.2] CHECK control rod coupled by observing the following:

Four rod display digital readout AND the full cores display digital readout AND background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 2-XA-55-5A, Window 14, does NOT alarm.

[6.3] CHECK the control rod settles into Position 48 and the ROD SETTLE light extinguishes.

Standard:

If Control Rod is withdrawn to position 48, performs a coupling check.

SAT UNSAT N/A COMMENTS:____________________________

JPM a PAGE 7 OF 16 Performance Step 6: Critical X Not Critical 6.6.4 Continuous Rod Withdrawal NOTES

1) Continuous control rod withdrawal maybe used when a control rod is to be withdrawn greater than three notches.

2) When in areas of high notch worth, single notch withdrawal should be used instead of continuous rod withdrawal. Information concerning high notch worth is identified by Reactor Engineering in Control Rod Coupling Integrity Check, 2-SR-3.1.3.5A.

3) When continuously withdrawing a control rod, the CRD Notch Override Switch is held in the Override position and the CRD Control Switch is held in the Rod Out Notch position.

Both switches should be released when the control rod reaches two notches prior to its intended position.

(Example: If a control rod is to be withdrawn from position 00 to position 12, the CRD Notch Override Switch and the CRD Control Switch would be used to move the control rod until reaching position 08, then both switches would be released.)

If the rod settles in a notch prior to the intended position, the CRD Control Switch should be used to withdraw the rod to the intended position.

(using the above example; If the control rod settles at a notch prior to the intended position of 12, the CRD Control Switch would be used to withdraw the control rod to position 12.

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT

pushbutton, 2-XS-85-40.

Standard:

Selects Control Rod 30-35 by depressing 30-35 pushbutton.

SAT UNSAT N/A COMMENTS:_______________________________

JPM a PAGE 8 OF 16 Performance Step 7: Critical Not Critical X

[2] OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED.

White light on the Full Core Display ILLUMINATED.

Rod Out Permit light ILLUMiNATED.

Standard:

Observes the above indications.

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 8: Critical Not Critical X

[3] VERIFY ROD WORTH MiNIMIZER operable and LATCHED in to correct ROD GROUP, when Rod Worth Minimizer is enforcing.

Standard:

Verifies Rod Worth Minimizer responded correctly.

SAT UNSAT N/A COMMENTS:___________________________

Performance Step 9: Critical Not Critical X

[4] VERIFY Control Rod is being withdrawn to a position greater than three notches.

Standard:

Verifies Control Rod 30-35 is going from position 16 to 48.

SAT_ UNSAT N/A COMMENTS:____________________________

JPM a PAGE 9 OF 16 Performance Step 10: Critical Not Critical X

[5] IF withdrawing the control rod to a position other than 48, THEN PERFORM the following: (Otherwise N/A)

Standard:

Step is NA.

SAT UNSAT N/A COMMENTS:

JPM a PAGE 10 OF 16 Performance Step 11: Critical X Not Critical NOTE When continuously withdrawing a control rod to position 48, the control rod coupling integrity check can be performed by one of the two following methods:

1) Coupling integrity check while maintaining the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position. If this method is selected, perform Step 6.6.4[6] and N/A Step 6.6.4[7].

2) Coupling integrity check after releasing the CRD Notch Override Switch and the CRD Control Switch. If this method is selected, perform Step 6.6.4[7] and N/A Step 6.6.4[6].

[6] IF continuously withdrawing the control rod to position 48 and performing the control rod coupling integrity check in conjunction with withdrawal, THEN PERFORM the following: (Otherwise N/A)

[6.1] PLACE and HOLD CRD NOTCH OVERRIDE, 2-HS-85-47, in NOTCH OVERRRIDE.

[6.2] PLACE and HOLD CRD CONTROL SWITCH, 2-HS-85-48, in ROD OUT NOTCH.

Standard:

Continuously withdraws Control Rod 30-35 by holding switch, 2-HS-85-47, in Notch Override and, 2-HS-85-48, in Rod Out Notch.

SAT UNSAT N/A COMMENTS:______________________________

Driver: At direction of Evaluator, after or during withdraw of control rod 3O35, trip operating CUE Jf<çeqnired hace operator take ihe actions Qf2-AOI-85-3 CRD System Failure.

I

JPM a PAGE 11 OF 16 Performance Step 12: Critical X Not Critical

[6.3] MAINTAIN the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position, with the control rod at position 48.

[6.4] CHECK control rod coupled by observing the following:

Four rod display digital readout AND the full core display digital readout AND background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 2-XA-55-5A, Window 14, does NOT alarm.

[6.5] RELEASE both CRD NOTCH OVERRIDE, 2-HS-85-47, and CRD CONTROL SWITCH, 2-HS-85-48.

[6.6] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

Standard:

If control rod is withdrawn to position 48, performs a coupling check.

SAT UNSAT N/A COMMENTS:___________________

JPM a PAGE 12 OF 16 Performance Step 13: Critical Not Critical

[7] IF continuously withdrawing the control rod to position 48, the control rod coupling integrity check will be performed after the CRD NOTCH OVERRIDE, 2-HS-85-47, and CRD CONTROL SWITCH, 2-HS-85-48 are to be released. THEN PERFORM control rod coupling integrity check as follows (otherwise N/A):

[7.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 2-HS-85-47, in NOTCH OVERRRIDE.

[7.2] PLACE AND HOLD CRD CONTROL SWITCH, 2-HS-85-48, in ROD OUT NOTCH.

Standard:

Continuously withdraws Control Rod 30-3 5 by holding switch, 2-HS-85-.47, in Notch Override and, 2-HS-85-48, in Rod Out Notch.

SAT UNSAT N/A _COMMENTS:_____________________________

Driver At direction ofEvaluator, after or during withdraw of control rod 30-35, trip operating CRD Pump.

CUE If required have operator take the actions of2-AO1-85-3 CRD System Fai1ure

JPM a PAGE 13 OF 16 Performance Step 14: Critical Not Critical X

[7.3] WHEN position 48 is reached, THEN RELEASE CRD NOTCH OVERRIDE, 2-HS-85-47, and CRD CONTROL SWITCH, 2-HS-85-48.

[7.4] VERIFY control rod settles into position 48.

Standard:

Stops withdraw of Control Rod 30-35 at position 48 by releasing hand switches and verifies rod settles at position 48.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 15: Critical X Not Critical

[7.5] PLACE CRD CONTROL SWITCH, 2-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[7.6] CHECK control rod coupled by observing the following:

Four rod display digital readout AND full core display digital readout AND background light will remain illuminated.

CONTROL ROD OVERTRAVEL annunciator (2-XA-55-5A, Window

14) does NOT alarm.

[7.7] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

Standard:

If control rod is withdrawn to position 48, performs a coupling check.

SAT UNSAT N/A COMMENTS:______________________________

JPM a PAGE 14 OF 16 Performance Step 16: Critical X Not Critical Operator Ranges IRMs as necessary; to maintain greater than the downscale reading of 7.5/1 25 and less than the upscale reading of 90/1 25.

Note: the High-High of 116.4/125 will produce a scram signal.

Standard:

Ranges IRMs to clear or prevent a Rod Block signal.

Note: A Full Scram signal from IRMs while withdrawing control rods wifi be a failure.

SAT_ UNSAT N/A COMMENTS:_____________________________

Driver: 4t direction of Evaluator, after or during wftbdraw of control rod 3 0-35, trip operating CR1) Pump.

CUE: Ifrquired have operator take the actions of2-AOI-85-3 CRD System Failure.

JPM a PAGE 15 OF 16 Performance Step 17: Critical Not Critical X 4.1 Inunediate Actions

[1] IF operating CRD PUMP has failed AND the standby CRD Pump is available, THEN PERFORM the following at Panel 2-9-5:

[1.1] PLACE CRD SYSTEM FLOW CONTROL, 2-FIC-85-11, in MAN at minimum setting.

Standard:

Places CRD System Flow Control in Manual and at Minimum setting.

SAT UNSAT N/A COMMENTS:____________________________

Performance Step 18: Critical Not Critical X

[1.2] START associated standby CRD Pump using one of the following:

CRD Pump 1B, using 2-HS-85-2A

CRD Pump 2A, using 2-HS-85-.1A Standard:

Attempts to start standby CR1) Pump and may also attempt to start tripped CRD Pump.

SAT UNSAT N/A COMMENTS:________________________________

JPM a PAGE 16 OF 16 Performance Step 9: Critical X Not Critical

[2] IF Reactor Pressure is less than 900 PSIG and either of the following conditions exists:

In-service CRD Pump tripped and neither CRD Pump can be started, OR

Charging Water Pressure can NOT be restored and maintained above 940 PSIG, THEN PERFORM the following:

[2.1] MANUALLY SCRAM Reactor, IMMEDIATELY PLACE the reactor mode switch in the SHUTDOWN position.

Standard:

Insert a Manual Scram and places Mode Switch in Shutdown.

SAT UNSAT N/A COMMENTS:_____________________________

CUE: After Scram rçport another operator will continue in 2-AO1-IO0-1.

END OF TASK STOP TIME

JPM a PAGE 1 OF 7 OPERATOR:

RO___ SRO___ DATE:*

JPM NUMBER: a TASK NUMBER: U-085-AB-03 TASK TITLE: CRD Pump Trip at <900 psig Reactor Pressure K/A NUMBER: 201001 A2.01 K/A RATING: RO 3.2 SRO 3.3 TASK STANDARD: Withdraws Control Rod, if withdrawn to position 48; performs a coupling check, ranges IRMs to prevent a full scram signal, and inserts a manual scram; when unable to restore CRD drive water pressure >940 psig.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-01-85 and 3-AOI-85-3 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are the Reactor Operator. Plant startup is in progress. Last completed Control Rod was 38-43 from 16 to 48, Sequence A2 Group 12. Other Operators are assigned heat up rate monitoring and Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to continue withdrawing controls rods for plant startup, the next control rod is 30-3 5. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

JPM a PAGE 3 OF 16 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

iNITIAL CONDITIONS:

You are the Reactor Operator. Plant startup is in progress. Last completed Control Rod was 3 8-43 from 16 to 48, Sequence A2 Group 12. Other Operators are assigned heat up rate monitoring and Reactor Level Control.

INITIATiNG CUE:

The Unit Supervisor directs you to continue withdrawing controls rods for plant startup, the next control rod is 30-3 5. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

NRC Examiner Steps 1 through 5 are for single notch withdrawal, steps 6 through 15 are for continuous withdrawal.

JPM a PAGE 4 OF 16 START TIME____

Performance Step 1: Critical X Not Critical 6.6.3 Control Rod Notch Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

Standard:

Selects Control Rod 30-35 by depressing 30-3 5 pushbutton.

SAT UNSAT N/A COMMENTS:____________________________

Performance Step 2: Critical Not Critical X

[2] OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED.

White light on the Full Core Display ILLUMiNATED.

Rod Out Permit light ILLUMiNATED.

Standard:

Observes the above indications.

SAT UNSAT N/A COMMENTS:

JPM a PAGE 5 OF 16 Performance Step 3: Critical Not Critical X

[3] VERIFY ROD WORTH MINIMIZER operable and LATCHED in to correct ROD GROUP, when Rod Worth Minimizer is enforcing.

Standard:

Verifies Rod Worth Minimizer responded correctly and verified Control Rod 30-35 is going from position 16 to 48.

SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 4: Critical X Not Critical

[4] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[5] OBSERVE the control rod settles into the desired position and the ROD SETTLE light extinguishes.

Standard:

Withdraws control rod 30-35.

SAT UNSAT N/A COMMENTS:______________________________

Driver: At direction ofEva1uatot, aft# or during withdraw of controt rod 30-35, trip operating CR1) Pump.

CUE: If requfred, have operttor take the actions of3-AOI-85-3 CR1) System Failure.

JPM a PAGE 6 OF 16 Performance Step 5: Critical X Not Critical

[6] IF control rod is notch withdrawn to rod notch Position 48, THEN PERFORM control rod coupling integrity check as follows:

[6.1] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[6.2] CHECK control rod coupled by observing the following:

Four rod display digital readout AND the full cores display digital readout AND background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does NOT alarm.

[6.3] CHECK the control rod settles into Position 48 and the ROD SETTLE light extinguishes.

Standard:

If Control Rod is withdrawn to position 48, performs a coupling check.

SAT UNSAT N/A COMMENTS:______________________________

JPM a PAGE 7 OF 16 Performance Step 6: Critical X Not Critical 6.6.4 Continuous Rod Withdrawal NOTES

1) Continuous control rod withdrawal may be used when a control rod is to be withdrawn greater than three notches.

2) When in areas of high notch worth, single notch withdrawal should be used instead of continuous rod withdrawal. Information concerning high notch worth is identified by Reactor Engineering in Control Rod Coupling Integrity Check, 3-SR-3.1 .3.5A.

3) When continuously withdrawing a control rod, the CRD Notch Override Switch is held in the Override position and the CRD Control Switch is held in the Rod Out Notch position.

When the control rod reaches two notches below its intended position, both switches should be released.

If the rod settles in a notch below the intended position, the CRD Control Switch should be used to withdraw the rod to the intended position.

EXAMPLE: If a control rod is to be withdrawn from position 00 to position 12, the CRD Notch Override Switch and the CRD Control Switch would be used to move the control rod until reaching position 08, then both switches would be released. If the control rod settles at a notch below the intended position of 12, the CRD Control Switch would be used to withdraw the control rod to position 12.

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3 -XS-85-40.

Standard:

Selects Control Rod 30-35 by depressing 30-35 pushbutton.

SAT UNSAT N/A COMMENTS:____________________________

JPM a PAGE 8 OF 16 Performance Step 7: Critical Not Critical X

[2] OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED.

White light on the Full Core Display ILLUMINATED.

Rod Out Permit light ILLUMINATED.

Standard:

Observes the above indications.

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 8: Critical Not Critical

[3] VERIFY ROD WORTH MINIMIZER operable and LATCHED in to correct ROD GROUP, when Rod Worth Minimizer is enforcing.

Standard:

Verifies Rod Worth Minimizer responded correctly.

SAT UNSAT N/A COMMENTS:____________________________

Performance Step 9: Critical Not Critical

[4] VERIFY Control Rod is being withdrawn to a position greater than three notches.

Standard:

Verifies Control Rod 30-35 is going from position 16 to 48.

SAT UNSAT N/A COMMENTS:____________________________

JPM a PAGE 9 OF 16 Performance Step 10: Critical Not Critical X

[5] IF withdrawing the control rod to a position other than 48, THEN PERFORM the following: (Otherwise N/A)

Standard:

Step is NA.

SAT UNSAT N/A COMMENTS:

JPM a PAGE 10 OF 16 Performance Step 11: Critical X Not Critical NOTE When continuously withdrawing a control rod to position 48, the control rod coupling integrity check can be performed by one of the two following methods:

1) Coupling integrity check while maintaining the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position. If this method is selected, perform Step 6.6.4[6] and N/A Step 6.6.4[7].

2) Coupling integrity check after releasing the CRD Notch Override Switch and the CRD Control Switch. If this method is selected, perform Step 6.6.4[7] and N/A Step 6.6.4[6].

[6] IF continuously withdrawing the control rod to position 48 and performing the control rod coupling integrity check in conjunction with withdrawal, THEN PERFORM the following: (Otherwise N/A)

[6.1] PLACE and HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[6.2] PLACE and HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

Standard:

Continuously withdraws Control Rod 30-35 by holding switch, 3-HS-85-47, in Notch Override and, 3-HS-85-48, in Rod Out Notch.

SAT_ UNSAT N/A COMMENTS:______________________________

Driver: At direction of Evaluator, after or during withdraw of confrol rod 3Q-35, trIp operating CR1) Ptm.

CUE: Ifrequiredhave operator take the ,tions of 3-AOI-85-3 CR1) System Failure.:

JPM a PAGE 11 OF 16 Performance Step 12: Critical X Not Critical

[6.3] MAINTAIN the CRD Notch Override Switch in the Override position and the CRD Control Switch in the Rod Out Notch position, with the control rod at position 48.

[6.4] CHECK control rod coupled by observing the following:

. Four rod display digital readout AND the full core display digital readout AND background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does NOT alarm.

[6.5] RELEASE both CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[6.6] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

Standard:

If control rod is withdrawn to position 48, performs a coupling check.

SAT_ UNSAT N/A COMMENTS:___________________

JPM a PAGE 12 OF 16 Performance Step 13: Critical X Not Critical

[7] IF continuously withdrawing the control rod to position 48, the control rod coupling integrity check will be performed after the CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48 are to be released. THEN PERFORM control rod coupling integrity check as follows (otherwise N/A):

[7.1] PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRRIDE.

[7.2] PLACE AND HOLD CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

Standard:

Continuously withdraws Control Rod 30-35 by holding switch, 3-HS-85-47, in Notch Override and 3-HS-85-48, in Rod Out Notch.

SAT_ UNSAT N/A COMMENTS:______________________________

Driver; At directio qfl3viuator, after o;during witbd,raw oCcontrol rc 30-35, trip operang CRDPUmj CUE ifrequired. have operator take the actions of3-AOI-85-3 CRD System Failure,

JPM a PAGE 13 OF 16 Performance Step 14: Critical Not Critical X

[7.3] WHEN position 48 is reached, THEN RELEASE CRD NOTCH OVERRIDE, 3-HS-85-47, and CRD CONTROL SWITCH, 3-HS-85-48.

[7.4] VERIFY control rod settles into position 48.

Standard:

Stops withdraw of Control Rod 30-35 at position 48 by releasing hand switches and verifies rod settles at position 48.

SAT_ U1JSAT N/A COMMENTS:______________________________

Performance Step 15: Critical X Not Critical

[7.5] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[7.6] CHECK control rod coupled by observing the following:

Four rod display digital readout AND full core display digital readout AND background light will remain illuminated.

CONTROL ROD OVERTRAVEL annunciator (3-XA-55-5A, Window

14) does NOT alarm.

[7.7] CHECK control rod settles into position 48 and ROD SETTLE light extinguishes.

Standard:

If control rod is withdrawn to position 48, performs a coupling check.

SAT_ UNSAT N/A COMMENTS:_______________________

JPM a PAGE 14 OF 16 Performance Step 16: Critical Not Critical Operator Ranges IRMs as necessary; to maintain greater than the downscale reading of 7.5/1 25 and less than the upscale reading of 104.6/125.

Note: the High-High of 116.4/125 will produce a scram signal.

Standard:

Ranges IRMs to clear or prevent a Rod Block signal.

Note: A Full Scram signal from IRMs while withdrawing control rods wifi be a failure.

SAT UNSAT N/A COMMENTS:______________________________

Driver: At direction of Evaluator, after or during withdraw of control rod 30-35, trip operating CR]) PUfl1p CUE: if required have operator take the actions f3-AOI-85-3 CR]) System Failure.

JPM a PAGE 15 OF 16 Performance Step 17: Critical Not Critical X 4.1 Inunediate Actions

[1] IF operating CRD PUMP has failed AND the standby CRD Pump is available, THEN PERFORM the following at Panel 3-9-5:

{1.1] PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, in MAN at minimum setting.

Standard:

Places CRD System Flow Control in Manual and at Minimum setting.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 18: Critical Not Critical

[1.2] START associated standby CRD Pump using one of the following:

CRD Pump 3B, using 3-HS-85-2A

CRD Pump 3A, using 3-HS-85-1A Standard:

Attempts to start standby CR1) Pump and may also attempt to start tripped CRD Pump.

SAT UNSAT N/A COMMENTS:_____________________________

JPM a PAGE 16 OF 16 Performance Step 19: Critical X Not Critical

[2] IF Reactor Pressure is less than 900 PSIG and either of the following conditions exists:

In-service CRD Pump tripped and neither CRD Pump can be started, OR

Charging Water Pressure can NOT be restored and maintained above 940 PSIG, THEN PERFORM the following:

[2.1] MANUALLY SCRAM Reactor, IMMEDIATELY PLACE the reactor mode switch in the SHUTDOWN position.

Standard:

Insert a Manual Scram and places Mode Switch in Shutdown.

SAT UNSAT N/A COMMENTS:____________________________

CUE: Afier Scram report another operator will cQntinue in 3-AOI-100-l END OF TASK STOP TIME

JPM b PAGE 1 OF 9 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: b TASK NUMBER: U-003-AL-16 TASK TITLE: RFPT Trip recovery K/A NUMBER: 259001 A2.01 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: RFPT Recovered and restoring Reactor Level prior to an automatic Reactor Scram on Level.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-AOI 1 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Reactor Operator. Plant startup is in progress. RFPT C has tripped and it is needed to maintain level.

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control in accordance with 2-AOI-3-l Loss of Reactor Feedwater or Reactor Water Level HighlLow starting at step 8.

JPM b PAGE 3 OF 9 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Reactor Operator. Plant startup is in progress. RFPT C has tripped and it is needed to maintain level.

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control in accordance with 2-AOI-3-l Loss of Reactor Feedwater or Reactor Water Level HighlLow starting at step 8.

JPM b PAGE 4 OF 9 START TIME____

Performance Step 1: *Critical X Not Critical

[8] IF RFPT has tripped and needed to maintain level, THEN PERFORM the following:

[8.1] OBTAIN SRO permission to restart RFPT.

¶8.2] RESET trip by using pushbutton.

Standard:

Resets trip by depressing reset pushbutton for RFPT C SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 2: Critical X Not Critical

[8.3] DEPRESS RFPT Speed Control Raise/Lower switch to MANUAL GOVERNOR position.

Standard:

Depresses RFPT C Speed Control Raise/Lower switch to Manual Governor position.

SAT_ UNSAT N/A _COMMENTS:_____________________________

JPM b PAGE 5 OF 9 Performance Step 3: Critical X Not Critical

[8.4] PLACE RFPT StartJLocal enable switch to START.

Standard:

Places RFPT C Start/Local enable switch to Start.

SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 4: Critical Not Critical X

[8.5] VERIFY RFPT accelerates to approximately 600 rpm.

Standard:

Verifies RFPT C accelerates SAT_ UNSAT N/A COMMENTS:

JPM b PAGE 6 OF 9 Performance Step 5: Critical Not Critical X

[8.6] For Fast Recovery of RFPT, PERFORM the following:

[8.6.1] OBTAIN SROs permission to perform fast recovery of RFPT.

[8.6.2] VERIFY Reactor Water Level Control PDS in AUTO and SELECT Column 2.

[8.6.3] VERIFY Reactor Water Level Control PDS level setpoint set at desired level.

Standard:

Verifies Reactor Water Level Control PDS in AUTO and set at desired level SAT UNSAT N/A COMMENTS:____________________________

CUE: IF asked you have permission to peifonn fast recovery, Operator mayproceed to step 8.7 Performance Step 6: Critical Not Critical

[8.6.4] PULL individual RFPT Speed Control Raise/Lower switch to FEEDWATER CONTROL position and CHECK amber light at switch is extinguished.

Standard:

Pulls RFPT C Speed Control Raise/Lower switch to Feedwater Control position SAT UNSAT N/A COMMENTS:____________________________

JPM b PAGE 7 OF 9 Performance Step 7: Critical Not Critical

[8.6.5] PLACE individual RFPT Speed Control PDS in AUTO.

Standard:

Places RFPT C Speed Control PDS in Auto and verifies speed increasing and Reactor level maintained SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 8: Critical Not Critical

[8.7] For Slow Recovery of RFPT in MANUAL GOVERNOR, RAISE RFPT speed using RFPT Speed Control Raise/Lower switch until desired flow is obtained.

Standard:

Raises speed of RFPT C using RFPT Speed Control switch and restores and maintains Reactor Level SAT_ UNSAT N/A COMMENTS:_____________________________

JPM b PAGE 8 OF 9 Performance Step 9: Critical Not Critical

[8.8] For Slow Recovery of RFPT using individual RFPT Speed Control PDS, PERFORM the following:

[8.8.1] VERIFY Colunm 3 selected and MANUAL selected on individual RFPT speed Control PDS.

Standard:

Verifies Column 3 selected and Manual selected on RFPT C speed Control PDS SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 10: Critical X Not Critical

[8.8.2] PULL individual RFPT Speed Control Raise/Lower switch to FEEDWATER CONTROL position.

Standard:

Pulls RFPT C Speed Control Raise/Lower switch to Feedwater Control position.

SAT UNSAT N/A COMMENTS:_____________________________

JPM b PAGE 9 OF 9 Performance Step 11: Critical X Not Critical

[8.8.3] RAISE RFPT speed using Ramp Up/Ramp Down pushbuttons to obtain desired flow.

Standard:

Raises speed of RFPT C using Ramp Up/Ramp Down pushbuttons and restores and maintains Reactor Level SAT UNSAT N/A COMMENTS:_______

END OF TASK STOP TIME

JPM b PAGE I OF 9 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: b TASK NUMBER: U-003-AL-16 TASK TITLE: RFPT Trip recovery K/A NUMBER: 259001 A2.01 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: RFPT Recovered and restoring Reactor Level prior to an automatic Reactor Scram on Level.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-AOI-3 -1 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Reactor Operator. Plant startup is in progress. RFPT C has tripped and it is needed to maintain level.

iNITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control in accordance with 3-AOI 1 Loss of Reactor Feedwater or Reactor Water Level HighlLow starting at step 11.

JPM b PAGE 3 OF 9 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Reactor Operator. Plant startup is in progress. RFPT C has tripped and it is needed to maintain level.

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control in accordance with 3-AOI-3-l Loss of Reactor Feedwater or Reactor Water Level High/Low starting at step 11.

JPM b PAGE 4 OF 9 START TIME____

Performance Step 1:

Critical Not Critical

[11] IF RFPT has tripped and it is needed to maintain level, THEN PERFORM the following:

[11.1] OBTAIN Unit Supervisor permission to restart RFPT.

[1 1.2] RESET trip by using pushbutton.

Standard:

Resets trip by depressing reset pushbutton for RFPT C SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 2: Critical Not Critical

[11.3] DEPRESS RFPT Speed Control Raise/Lower switch to MANUAL GOVERNOR position.

Standard:

Depresses RFPT C Speed Control Raise/Lower switch to Manual Governor position.

SAT_ UNSAT N/A COMMENTS:____________________________

JPM b PAGE 5 OF 9 Performance Step 3: Critical X Not Critical

[11.4] PLACE RFPT Start/Local enable switch to START.

Standard:

Places RFPT C Start/Local enable switch to Start.

SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 4: Critical Not Critical X

[11.5] VERIFY RFPT accelerates to approximately 600 rpm.

Standard:

Verifies RFPT C accelerates SAT UNSAT N/A COMMENTS:

JPM b PAGE 6 OF 9 Performance Step 5: Critical Not Critical X

[11.6] IF Fast Recovery of RFPT is desired, THEN PERFORM the following:

[11.6.1] OBTAIN Unit Supervisors permission to perform fast recovery of RFPT.

[11.6.2] VERIFY Reactor Water Level Control PDS in AUTO and SELECT Column 2.

[11.6.3] VERIFY Reactor Water Level Control PDS level setpoint set at desired level.

Standard:

Verifies Reactor Water Level Control PDS in AUTO and set at desired level SAT_ UNSAT N/A COMMENTS:____________________________

CUE: IF asked you have permission to perform fast recovery, Operator may proceed to step 11.7 Performance Step 6: Critical Not Critical

[11.6.4] PULL individual RFPT Speed Control Raise/Lower switch to FEEDWATER CONTROL position AND VERIFY amber light at switch is extinguished.

Standard:

Pulls RFPT C Speed Control Raise/Lower switch to Feedwater Control position SAT_ UNSAT N/A COMMENTS:____________________________

JPM b PAGE 7 OF 9 Performance Step 7: Critical X Not Critical

[11.6.5] PLACE individual RFPT Speed Control PDS in AUTO.

Standard:

Places RFPT A Speed Control PDS in Auto and verifies speed increasing and Reactor level maintained SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 8: Critical X Not Critical

[11.7] IF Slow Recovery of RFPT in MANUAL GOVERNOR is desired, THEN RAISE RFPT speed using RFPT Speed Control Raise/Lower switch until desired flow is obtained.

Standard:

Raises speed of RFPT C using RFPT Speed Control switch and restores and maintains Reactor Level SAT UNSAT N/A COMMENTS:_____________________________

3PM b PAGE 8 OF 9 Performance Step 9: Critical Not Critical X

[11.8] IF Slow Recovery of RFPT using individual RFPT Speed Control PDS is desired, THEN PERFORM the following:

[11.8.1] VERIFY Column 3 selected and MANUAL selected on individual RFPT speed Control PDS.

Standard:

Verifies Column 3 selected and Manual selected on RFPT C speed Control PDS.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 10: Critical X Not Critical

[11.8.2] PULL individual RFPT Speed Control Raise/Lower switch to FEEDWATER CONTROL position.

Standard:

Pulls RFPT C Speed Control Raise/Lower switch to Feedwater Control position.

SAT_ UNSAT N/A COMMENTS:_____________________________

JPM b PAGE 9 OF 9 Performance Step 11: Critical X Not Critical

[11.8.3] RAISE RFPT speed using Ramp Up/Ramp Down pushbuttons to obtain desired flow.

Standard:

Raises speed of RFPT C using Ramp Up/Ramp Down pushbuttons and restores and maintains Reactor Level SAT UNSAT N/A COMMENTS:________

END OF TASK STOP TIME

JPM c PAGE 1 OF 7 OPERATOR:_____________________

RO___ SRO___ DATE:

JPM NUMBER: c TASK NUMBER: U-000-EM-50 TASK TITLE: 2-EOI APPENDIX-i 1D Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains K/A NUMBER: 239001 A1.08 K/A RATING: RO 3.8 SRO 3.8 TASK STANDARD: Establish alternate pressure control with Main Steamline drains, Turbine and RFPT drains LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI APPENDIX-i 1D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 reactor has scrammed. Emergency depressurization is not required but alternate means of pressure control is required. Turbine Bypass valves are NOT available. EOI- 1 has been followed to RC/P- 11. Another Operator is assigned Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 2-EOI Appendix 1 1D Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 600 to 1000 psig.

JPM c PAGE 3 OF 7 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 reactor has scrammed. Emergency depressurization is not required but alternate means of pressure control is required. Turbine Bypass valves are NOT available. EOI- 1 has been followed to RC/P- 11. Another Operator is assigned Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 2-EOI Appendix liD Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 600 to 1000 psig.

JPM c PAGE 4 OF 7 START TIME____

Perfomiance Step 1: Critical Not Critical X

1. IF BOTH of the following exist:

Emergency RPV Depressurization is required, AND

Group 1 Isolation Signal exists, THEN EXIT this procedure and ENTER EOI Appendix 1 1H.

Standard:

Given in initial conditions, does not exit procedure SAT UNSAT N/A COMMENTS:___________________________

Performance Step 2: Critical Not Critical X

2. VERIFY hotwell pressure below -7 in. Hg.

Standard:

Verifies hotwell pressure less than -7 in. Hg.

SAT UNSAT N/A COMMENTS:____

JPM c PAGE 5 OF 7 Performance Step 3: Critical Not Critical

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset.

Standard:

Verifies PCIS Reset SAT UNSAT N/A COMMENTS:__________________________

Performance Step 4: Critical X Not Critical

b. OPEN the following valves (Panel 9-3):

2-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV

2-FCV-l-56, MN STM LINE DRAIN OUTBD ISOLATION VLV

2-FCV-l-58, UPSTREAM MSL DRAIN TO CONDENSER Standard:

Opens 2-FCV-l-55, 2-FCV-1-56, and 2-FCV-l-58 SAT_ UNSAT N/A COMMENTS:_______

JPM C PAGE 6 OF 7 Performance Step 5: Critical X Not Critical

4. THROTTLE 2-FCV-l-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate.

Standard:

Throttles 2-FCV-l-59 open and control cooldown rate SAT UNSAT N/A _COMMENTS:__________

CUE: Jf necessary when 2-FCY-1-59 is full open, Direct Operator that Additional RPVPressure Control is necessary Performance Step 6: Critical X Not Critical

5. IF At least one main steam line is open AND EITHER of the following exist:

Turbine bypass valves are NOT available, OR Additional RPV pressure control is necessary, THEN CONTROL RPV pressure with Main Turbine and RFPT drains as follows:

a. OPEN the following Main Turbine Drain valves (Panel 9-7):

2-FCV-6-lOO, STOP VALVE 1 BEFORE SEAT DR VLV

2-FCV-6-lOl, STOP VALVE 2 BEFORE SEAT DR VLV

2-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV

2-FCV-6-l03, STOP VALVE 4 BEFORE SEAT DR VLV Standard:

Opens 2-FCV-6-lOO, 2-FCV-6-lOl, 2-FCV-6-102, and 2-FCV-6-103 SAT_ UNSAT N/A COMMENTS:_______________________________

JPM c PAGE 7 OF 7 Performance Step 7: Critical X Not Critical

b. OPEN the following RFPT drain valves (Panel 9-6):

2-FCV-6-122, RFPT 2A HP STOP VLV ABOVE SEAT DR

2-FCV-6-127, RFPT 2B HP STOP VLV ABOVE SEAT DR

2-FCV-6-132, RFPT 2C HP STOP VLV ABOVE SEAT DR Standard:

Opens 2-FCV-6-122, 2-FCV-6-127, and 2-FCV-6-132 SAT UNSAT N/A COMMENTS:________

END OF TASK STOP TIME____

JPM c PAGE 1 OF 7 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: c TASK NUMBER: U-000-EM-50 TASK TITLE: 2-EOI APPENDIX-i 1D Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains KIA NUMBER: 239001 A1.08 KJA RATING: RO 3.8 SRO 3.8 TASK STANDARD: Establish alternate pressure control with Main Steamline drains, Turbine and RFPT drains LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI APPENDIX-i 1D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Unit 3 Operator. Unit 3 reactor has scrammed. Emergency depressurization is not required but alternate means of pressure control is required. Turbine Bypass valves are NOT available. EOI- 1 has been followed to RC/P- ii. Another Operator is assigned Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 3-EOI Appendix-i iD Alternate RPV Pressure Control Systems Main Steam Line Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 600 to 1000 psig.

JPM C PAGE 3 OF 7 IN-SIlIULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit 3 Operator. Unit 3 reactor has scrammed. Emergency depressurization is not required but alternate means of pressure control is required. Turbine Bypass valves are NOT available. EOI-i has been followed to RCIP-1 1. Another Operator is assigned Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 3-EOI Appendix-i iD Alternate RPV Pressure Control Systems Main Steam Line Drains andJor Turbine and RFPT Drains and maintain Reactor Pressure 600 to 1000 psig.

JPM c PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical X

1. IF BOTH of the following exist:

Emergency RPV Depressurization is required, AND

Group 1 Isolation Signal exists, THEN EXIT this procedure and ENTER EOI Appendix 1 1H.

Standard:

Given in initial conditions, does not exit procedure SAT UNSAT N/A COMMENTS:__________________________

Performance Step 2: Critical Not Critical X

2. VERIFY hotwell pressure below -7 in. Hg.

Standard:

Verifies hotwell pressure less than -7 in. Hg.

SAT UNSAT N/A _COMMENTS:____

JPM c PAGE 5 OF 7 Performance Step 3: Critical Not Critical X

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset.

Standard:

Verifies PCIS Reset SAT_ U1SAT N/A COMMENTS:____________________________

Performance Step 4: Critical X Not Critical

b. OPEN the following valves (Panel 3-9-3):

3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV

3-FCV-l-56, MN STM LINE DRAiN OUTBD ISOLATION VLV

3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER Standard:

Opens 3-FCV-1-55, 3-FCV-l-56, and 3-FCV-l-58 SAT UNSAT N/A COMMENTS:_______

JPM c PAGE 6 OF 7 Performance Step 5: Critical Not Critical

4. THROTTLE 3-FCV-l-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate.

Standard:

Throttles 3-FCV-1-59 open and control cooldown rate SAT UNSAT N/A COMMENTS:___________

CU1: Ifnecessary when 3jjV-1-59 >is full open, Direct Operator that Additional PPresswe Gontr9 isieceaiy Performance Step 6: Critical X Not Critical

5. IF At least one main steam line is open AND EITHER of the following exist:

Turbine bypass valves are NOT available, OR Additional RPV pressure control is necessary, THEN CONTROL RPV pressure with Main Turbine and RFPT drains as follows:

a. OPEN the following Main Turbine Drain valves (Panel 3-9-7):

3-FCV-6-100, STOP VALVE 1 BEFORE SEAT DR VLV

3-FCV-6-l0l, STOP VALVE 2 BEFORE SEAT DR VLV

3-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV

3-FCV-6-103, STOP VALVE 4 BEFORE SEAT DR VLV Standard:

Opens 3-FCV 100, 3-FCV 101, 3-FCV 102, and 3-FCV 103 SAT_ UNSAT N/A COMMENTS:______________________________

JPM c

PAGE7OF7 Performance Step 7: Critical X Not Critical

b. OPEN the following RFPT drain valves (Panel 3-9-6):

3-FCV-6-122, RFPT 3A HP STOP VLV ABOVE SEAT DR

3-FCV-6-127, RFPT 3B HP STOP VLV ABOVE SEAT DR

3-FCV-6-132, RFPT 3C HP STOP VLV ABOVE SEAT DR Standard:

Opens 3-FCV-6-122, 3-FCV-6-127, and 3-FCV-6-132 SAT UNSAT N/A _COMMENTS:_______

END OF TASK STOP TIME____

JPM d PAGE 1 of9 OPERATOR:

RO___ SRO DATE:

JPM NUMBER: d TASK NUMBER: U-000-EM-50 TASK TITLE: EOI APPENDIX-8F Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation KJA NUMBER: 295032 EA1 .03 KIA RATING: RO 3.7 SRO 3.7 TASK STANDARD: Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation PERFORMANCE LOCATION: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-8F VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

JPM d PAGE 2 of 9 INITIAL CONDITIONS:

You are an Operator. Unit 3 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-l has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

The Unit Supervisor directs you to restore reactor and refuel zone ventilation as directed by 3-EOI Appendix-8F. SGTS is required for Operation and fast speed operation is desired for Reactor and Refuel Zone Ventilation.

JPM d PAGE 3 of 9 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator. Unit 3 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-l has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

The Unit Supervisor directs you to restore reactor and refuel zone ventilation as directed by 3-EOI Appendix-8F. SGTS is required for Operation and fast speed operation is desired for Reactor and Refuel Zone Ventilation.

JPM d PAGE 4 of 9 START TIME____

Performance Step 1: Critical X Not Critical

1. VERIFY PCIS Reset.

Standard:

Resets PCIS SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 2: Critical X Not Critical

2. PLACE Refuel Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch is in OFF.

Standard:

Places 3-HS-64-3A in the Off position.

SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 3: Critical X Not Critical

b. PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch to SLOW A (SLOW B).

Standard:

Places 3-HS-64-3A to SLOW A or SLOW B position.

SAT_ UNSAT_ N/A_COMMENTS:______________________________

JPM d PAGE 5 of 9 Performance Step 4: Critical Not Critical X

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

Standard:

Verifies proper combination of lights On and Off above 3-HS-64-3A.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 5: Critical Not Critical X

d. VERIFY OPEN the following dampers:

3-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR

3-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR

3-FCO-64-1O, REFUEL ZONE EXH INBD ISOL DMPR Standard:

Verifies Red position indicating iamps On for dampers listed above SAT_ UNSAT N/A COMMENTS:

JPM d PAGE 6 of 9 Performance Step 6: Critical Not Critical

3. PLACE Reactor Zone Ventilation in service as follows (Panel 3-9-25):

a. VERIFY 3-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch is in OFF.

Standard:

Places 3-HS-64-l 1A in the Off position.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 7: Critical X Not Critical

b. PLACE 3-HS-64-l 1A, REACTOR ZONE FANS AND DAMPERS, control switch in SLOW A (SLOW B).

Standard:

Places 3-HS-64-1 1A to SLOW A or SLOW B position.

SAT_ UNSAT N/A COMMENTS:___________

JPM d PAGE 7 of 9 Performance Step 8: Critical Not Critical X

c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

Standard:

Verifies proper combination of lights On and Off above 3-HS-64-3A.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 9: Critical Not Critical

d. VERIFY OPEN the following dampers:

3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR

3-FCO-64-14, REACTOR ZONE SPLY TNBD ISOL DMPR

3-FCO-64-42, REACTOR ZONE EXH INBD ISOL DMPR

3-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR Standard:

Verifies Red position indicating lamps On for dampers listed above SAT UNSAT_ N/A COMMENTS:_________________

JPM d PAGE 8 of 9 Performance Step 10: Critical Not Critical X

4. IF SGTS is NOT required for operation, THEN SECURE SGTS as follows:

Standard:

Given in Initial conditions that SGTS is required.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 11: Critical Not Critical X

5. IF Reactor Zone Fan fast speed is desired following 5 minutes of slow speed operation, THEN PLACE 3-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch in FAST A (FAST B).

Standard:

Places 3-HS-64-1 1A in either FAST A or FAST B position in accordance with which set of fans were started in slow SAT UNSAT N/A _COMMENTS:______________________________

CUE: Five Minutes has elapsed

JPM d PAGE 9 of 9 Performance Step 12: Critical Not Critical X

6. IF Refuel Zone Fan fast speed is desired following 5 minutes of slow speed operation, THEN PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch in FAST A (FAST B).

Standard:

Places 3-HS-64-3A in either FAST A or FAST B position in accordance with which set of fans were started in slow.

SAT UNSAT N/A COMMENTS:

CUE: Five Minutes has elapsed END OF TASK STOP TIME:

JPM d PAGE 1 of9 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: d TASK NUMBER: U-000-EM-50 TASK TITLE: EOI APPENDIX-8F Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation K/A NUMBER: 295032 EA1 .03 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation PERFORMANCE LOCATION: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-8F VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TiME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

JPM d PAGE 2 of 9 INITIAL CONDITIONS:

You are an Operator. Unit 2 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-l has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

The Unit Supervisor directs you to restore reactor and refuel zone ventilation as directed by 2-EOI Appendix-8F. SGTS is required for Operation and fast speed operation is desired for Reactor and Refuel Zone Ventilation.

1PM d PAGE 3 of 9 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator. Unit 2 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-l has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

The Unit Supervisor directs you to restore reactor and refuel zone ventilation as directed by 2-EOI Appendix-8F. SGTS is required for Operation and fast speed operation is desired for Reactor and Refuel Zone Ventilation.

JPM d PAGE 4 of 9 START TIME____

Performance Step 1: Critical Not Critical

1. VERIFY PCIS Reset.

Standard:

Resets PCIS SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 2: Critical X Not Critical

2. PLACE Refuel Zone Ventilation in service as follows (Panel 2-9-25):

a. VERIFY 2-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch is in OFF.

Standard:

Places 2-HS-64-3A in the Off position.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 3: Critical X Not Critical

b. PLACE 2-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch to SLOW A (SLOW B).

Standard:

Places 2-HS-64-3A to SLOW A or SLOW B position.

SAT_ UNSAT_ N/A COMMENTS:_____________________________

JPM d PAGE 5 of9 Performance Step 4: Critical Not Critical X

c. CHECK two SPLY/EXH A(B) green lights above 2-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

Standard:

Verifies proper combination of lights On and Off above 2-HS-64-3A.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 5: Critical Not Critical X

d. VERIFY OPEN the following dampers:

2-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR

2-FCO-64-6, REFUEL ZONE SPLY TNBD ISOL DMPR

2-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR

2-FCO-64-lO, REFUEL ZONE EXH 1NBD ISOL DMPR Standard:

Verifies Red position indicating lamps On for dampers listed above SAT UNSAT N/A COMMENTS:_____________________

JPM d PAGE 6 of 9 Performance Step 6: Critical X Not Critical

3. PLACE Reactor Zone Ventilation in service as follows (Panel 2-9-25):

a. VERIFY 2-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch is in OFF.

Standard:

Places 2-HS-64-1 1A in the Off position.

SAT_ UNSAT N/A _COMMENTS:______________________________

Performance Step 7: Critical X Not Critical

b. PLACE 2-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch in SLOW A (SLOW B).

Standard:

Places 2-HS-64-1 1A to SLOW A or SLOW B position.

SAT UNSAT N/A COMMENTS:___________

JPM d PAGE 7 of 9 Performance Step 8: Critical Not Critical X

c. CHECK two SPLY/EXH A(B) green lights above 2-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH A(B) red lights illuminate.

Standard:

Verifies proper combination of lights On and Off above 2-HS-64-3A.

SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 9: Critical Not Critical X

d. VERIFY OPEN the following dampers:

2-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR

2-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR

2-FCO-64-42, REACTOR ZONE EXH 1NBD ISOL DMPR

2.-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR Standard:

Verifies Red position indicating lamps On for dampers listed above SAT_ UNSAT N/A COMMENTS:

JPM d PAGE 8 of 9 Performance Step 10: Critical Not Critical X

4. IF SGTS is NOT required for operation, THEN SECURE SGTS as follows:

Standard:

Given in Initial conditions that SGTS is required.

SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 11: Critical Not Critical X

5. IF Reactor Zone Fan fast speed is desired following 5 minutes of slow speed operation, THEN PLACE 2-HS-64-1 1A, REACTOR ZONE FANS AND DAMPERS, control switch in FAST A (FAST B).

Standard:

Places 2-HS-64-1 1A in either FAST A or FAST B position in accordance with which set of fans were started in slow SAT UNSAT N/A COMMENTS:

CUE: Five Minutes has elapsed

JPM d PAGE 9 of 9 Performance Step 12: Critical Not Critical X

6. IF Refuel Zone Fan fast speed is desired following 5 minutes of slow speed operation, THEN PLACE 2-HS-64-3A, REFUEL ZONE FANS AND DAMPERS, control switch in FAST A (FAST B).

Standard:

Places 2-HS-64-3A in either FAST A or FAST B position in accordance with which set of fans were started in slow.

SAT UNSAT N/A COMMENTS:

CUE: Five Minutes has elapsed END OF TASK STOP TIME:

JPM e PAGE 1 OF 10 OPERATOR:______________________

RO___ SRO___ DATE:________

JPM NUMBER: e TASK NUMBER: U-000-SS-25 TASK TITLE: Energize 4 KV SD BDs A, C, and D from Unit 3 DGs K/A NUMBER: 264000 A4.04 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: 4 KV SD BDs A and C energized from Unit 3 DGs during a Unit 1 and 2 Diesel Generator Building Fire. DG D Emergency Shutdown due to Low Lube Oil Pressure LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 0-S SI-20 VALiDATION HME: 15 minutes MAX. TiME ALLOWED: 20 minutes PERFORMANCE TiME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

IMTIAL CONDITIONS:

You are an Operator on Unit 3, the plant is operating in O-SSI-20 Unit 1 and 2 Diesel Generator Building fire. All three units have been scrammed. An Assistant Unit Operator has been dispatched to the DGs.

INITIATING CUE:

The Unit Supervisor directs you to complete attachment 6, Unit 3 Panel 9-23 Actions of O-SSI-20.

Time Critical

JPM e PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 3, the plant is operating in O-SSI-20 Unit 1 and 2 Diesel Generator Building fire. All three units have been scrammed. An Assistant Unit Operator has been dispatched to the DGs.

INITIATING CUE:

The Unit Supervisor directs you to complete attachment 6, Unit 3 Panel 9-23 Actions of O-SSI-20.

Time Critical

JPM e PAGE 4 OF 11 START TIME____

Performance Step 1: Critical X Not Critical 1.0 ENERGIZING 4KV SHUTDOWN BOARDS A, C, AND D FROM UNIT 3 DIESEL GENERATORS 3A, 3C, AND 3D USING UNIT INTERTIE (20 Mm)

NOTE The following steps will energize 4KV Shutdown Boards A, C, and D from Unit 3 Diesel Generators as the only source.

[1] Notification has been received from the Unit 2 Unit Supervisor to perform this section.

[2j PROCEED TO Panel 3-9-23, AND PERFORM the following to align Shutdown Board 3 EA:

[2.1] VERIFY DG 3A CONTROL switch, 3-HS-82-3A/1A, in START.

Standard:

Starts DG 3A SAT_ UNSAT N/A _COMMENTS:

JPM e PAGE 5 OF 11 Performance Step 2: Critical X Not Critical

[2.2] VERIFY 4KV SD BD 3EA AUTO TO MANUAL TRIP pushbutton, 3-HS-21 1-3EA, in MANUAL.

Standard:

Depresses 3-HS-21 1-3EA SAT UNSAT N/A COMMENTS:____________________________

Performance Step 3: Critical X Not Critical

[2.3] VERIFY 4KV SD BD 3EA NORM FDR BKR 1334, 3-HS-21 1-3EA/7A, in TRIP.

Standard:

Trips Normal Feeder Breaker 1334 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 4: Critical Not Critical X

[2.4] VERIFY DG 3A BKR 1838 CLOSED.

Standard:

Verifies DG Breaker 1838 closes SAT UNSAT N/A COMMENTS:

JPM e PAGE 6 OF 11 Performance Step 5: Critical X Not Critical

[2.5] PLACE 4KV SD BD 3EA EMER FDR BKR 1844, 3-HS-211-3EA/1A, in CLOSE.

Standard:

Closes Emergency Feeder Breaker 1844 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 6: Critical X Not Critical

[3] PERFORM the following to align 4KV Shutdown Board 3EC:

[3.1] VERIFY DG 3C CONTROL switch, 3-HS-82-3C/1A, in START.

Standard:

StartsDG3C SAT UNSAT N/A COMMENTS:____________________________

Performance Step 7: Critical X Not Critical

[3.2] VERIFY 4KV SD BD 3EC AUTO TO MANUAL TRIP pushbutton, 3-HS-21 1-3EC, in MANUAL.

Standard:

Depresses 3-HS-21 1-3EC SAT_ UNSAT N/A _COMMENTS:

JPM e PAGE 7 OF 11 Performance Step 8: Critical X Not Critical

[3.3] VERIFY 4KV SD BD 3EC NORM FDR BKR 1338, 3-HS-21 1-3EC/12A, in TRIP.

Standard:

Trips Normal Feeder Breaker 1338 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 9: Critical Not Critical X

[3.4] VERIFY DG 3C BKR 1832 CLOSED.

Standard:

Verifies DG Breaker 1832 closes SAT UNSAT N/A COMMENTS:______________________________

Performance Step 10: Critical Not Critical

[3.5] PLACE 4KV SD BD 3EC EMER FDR BKR 1834, 3-HS-211-3EC/6A, in CLOSE.

Standard:

Closes Emergency Feeder Breaker 1834 SAT_ UNSAT N/A COMMENTS:_______________________________

JPM e PAGE 8 OF 11 Performance Step 11: Critical X Not Critical

[4] PERFORM the following to align 4KV Shutdown Board 3ED:

[4.1] VERIFY DG 3D CONTROL switch, 3-HS-82-3D/1A, in START.

Standard:

Starts DG 3D SAT UNSAT N/A COMMENTS:_______________________________

rJ Performance Step 12: Critical Not Critical X

[4.2] VERIFY 4KV SD BD 3ED AUTO TO MANUAL TRIP pushbutton, 3..HS-21 1-3ED, in MANUAL.

Standard:

Depresses 3-HS-21 1-3ED SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 13: Critical Not Critical X

[4.3] VERIFY 4KV SD BD 3ED NORM FDR BKR 1342, 3-HS-21 1-3ED/8A, in TRIP.

Standard:

Trips Normal Feeder Breaker 1342 SAT UNSAT N/A COMMENTS:

JPM e PAGE 9 OF 11 Performance Step 14: Critical Not Critical X

[4.4] VERIFY DG 3D BKR 1836 CLOSED.

Standard:

Closes DG Breaker 1836 SAT UNSAT N/A COMMENTS:____________________________

Performance Step 15: Critical Not Critical X

[4.5] PLACE 4KV SD BD 3ED EMER FDR BKR 1846, 3-HS-21 1-3ED/4A, in CLOSE.

Standard:

Closes Emergency Feeder Breaker 1846 SAT_ UNSAT N/A COMMENTS:____________________________

diI&1&fter Lu! sureIan Jyecetyd d4magç4!

JPM e PAGE 10 OF 11 Performance Step 16: Critical Not Critical RESPONDS to the Alarm 9-23D WIN 4 (DIESEL GEN D LUBE OIL ABNORMAL) and notices the AMBER LIGHT (LOW LOW OIL PRESSURE)

Standard:

Responds per the ARP and Verifies the AMBER LIGHT is lit.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 17: Critical Not Critical SHUTS DOWN the DG with the Emergency Stop Pushbutton per the ARP.

Standard:

Shuts Down the DG with the Emergency Stop Pushbutton.

SAT U1.JSAT N/A COMMENTS:_____________________________

Examiner note: ALARMon 9-23D win 4 DO D LUBE OIL ABNORMAL will alarm and LOW LOW OIL PRESSURE LIGHT forD DO will illuminate, the operator should respond per the ARP.

JPM e PAGE 11 OF 11 Performance Step 18: Critical Not Critical X

[5] NOTIFY Unit 2 Unit Supervisor of the completion of this section.

[6] PROCEED TO 480V RMOV Board 3C in preparation of performing Section 2.0.

Standard:

Notifies Unit Supervisor SAT UNSAT N/A COMMENTS:_____________________________

CUE: ]

1 RainControiRoomanotheO&atrhasbendispatchedto48OVRMO END OF TASK STOP TIME

JPM f PAGE 1 OF 6 OPERATOR:

RO SRO DATE:

JPM NUMBER: f TASK NUMBER: U-090-NO-1 1 TASK TITLE: Inhibit trip signal for NTJMAC 1-RM-90-141/143 KJA NUMBER: 272000 K3.06 KIA RATING: RO 3.4 SRO: 3.6 TASK STANDARD: Trip signal inhibited for NUMAC l-RM-90-141/143 LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 1-01-90 VALIDATION flME:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INiTIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 1-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 1-RE-90-141A!B. The trip signal will not reset and has been confirmed to be valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 1-01-90 Radiation Monitoring System section 6.6, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

3PM f PAGE 3 OF 6 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. SELF CHECKING may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. Observe ALL plant radiological and safety precautions. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied.

When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 1-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 1-RE-90-141AJB. The trip signal will not reset and has been confirmed to be not valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 1-01-90 Radiation Monitoring System section 6.6, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM f PAGE 4 OF 6 START TIME Performance Step 1: Critical Not Critical X 6.6 NUMAC Radiation Monitor Operation NOTES

1) The section is applicable to Main Steam Line Radiation Monitors 1-RM-90-136 & 137 and RX & REFUEL ZONE EXH CH A(B) RAD MON RTMR, 1-RM-90-140/142 (1-RM-90-141/143).

2) A screen saver activates on the monitor after 30 minutes of constant display.

3) There are two detectors for each channel of the Reactor Zone/Refuel Zone monitors and are indicated on each monitor as follows:

l-RM-90-140/142 Display Description CH 2A CH 2A RX ZONE DET A, 1-RE-90-142A CH 2B CH 2B RX ZONE DET B, 1-RE-90-142B CH OA CH OA REFUEL ZONE DET A, 1-RE-90-140A CH OB CH OB REFUEL ZONE DET B, 1-RE-90-140B 1-RM-90-141/143 Display Description CH 3A CH 3A RX ZONE DET A, l-RE-90-143A CH 3B CH 3B RX ZONE DET B, 1-RE-90-143B CH 1A CH 1A REFUEL ZONE DET A, 1-RE-90-141A CH lB CH lB REFUEL ZONE DET B, 1-RE-90-141B

4) Only the A detector of each channel described above has input to radiation recorder 1 -RR 144.

[1] IF the screen saver is activated, THEN DEPRESS any of the prompt keys at the bottom of the screen to display the monitored channels.

Standard:

May depress prompt key to activate display SAT UNSAT N/A COMMENTS:

CUE: If dispIayis checked detector 141 A and B indicate Upscale Trips

Yotihave the necessaly tools to cómplte th task..

JPM t PAGE 5 OF 6 Performance Step 2: Critical X Not Critical CAUTION A Reactor Zone isolation can cause a unit scram in less than five minutes due to high temperature in the steam tunnel.

NOTES

1) Step 6.6[2j is to be performed in the event of a trip signal that will NOT reset to prevent further impact to plant operation due to reactor zone isolation. This is only considered appropriate when the signal is believed to be invalid.

2) Technical Specifications only allow one trip channel at a time to be out of service. This section provides directions for removing both trip channels from service but should only be performed on one channel at a time. Reference Technical Specification 3.3.6.2 for limiting conditions.

3) Any active trip condition will be indicated by a highlighted TRIP at the top of the screen. A non-highlighted TRIP at the top of the screen indicates that there are one or more past trip condition that have been acknowledged.

4) Trips on the Reactor Zone/Refuel Zone Radiation monitors will automatically reset when the alarming condition resets.

5) Downscale trips take more than one trip channel to activate the logic.

[2] PERFORM the following to immediately reset a Group 6 Isolation Due to Reactor Zone Radiation Monitors:

[2.1] PLACE affected monitor keylock switch to INOP position.

Standard:

Simulates placing monitor l-RM-90-141/143 keylock switch to INOP SAT U14SAT N/A COMMENTS:

JPM f PAGE 6 OF 6 Performance Step 3:

Critical X Not Critical NOTE Step(s) 6.6[2.2] and 6.6[2.3] place jumpers to inhibit the upscale trips for a monitor.

[2.2] IF the affected monitor is l-RM-90-140/142, THEN PLACE jumper across the following terminals in the back of Panel 9-10 to inhibit the upscale trip:

TB HH terminals 49 and 50

¶2.3] IF the affected monitor is l-RM-90-141/143, THEN PLACE jumper across the following terminals in the back of Panel 9-10 to inhibit the upscale trip:

TB DD terminals 59 and 60 Standard:

Simulates performing step 2.3, places a jumper across terminals 59 and 60 on TB DD SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM f PAGE 1 OF 7 OPERATOR:

RO SRO DATE:

JPM NUMBER: f TASK NUMBER: U-090-NO-1 1 TASK TITLE: Inhibit trip signal for NUMAC 2-RM-90-141/143 KIA NUMBER: 272000 K3.06 K/A RATING: RO 3.4 SRO: 3.6 TASK STANDARD: Trip signal inhibited for NUMAC 2-RM-90-141/143 LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 2-01-90 VALIDATION TIME:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 2-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 2-RE-90-14 lA/B. The trip signal will not reset and has been confirmed to be not valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 2-01-90 Radiation Monitoring System section 6.6, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM f PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. SELF CHECKING may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. Observe ALL plant radiological and safety precautions. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied.

When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 2-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 2-RE-90-14 lA/B. The trip signal will not reset and has been confirmed to be i valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 2-01-90 Radiation Monitoring System section 6.6, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM f PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical X 6.6 NUMAC Radiation Monitor Operation NOTES

1) This section is applicable to Main Steam Line radiation monitors 2-RM-90-136, 137 and Reactor Zone/Refuel Zone radiation monitors 2-RM-90-140/142 and 2-RM-90-141/143.

2) A screen saver activates on the monitor after 30 minutes of constant display.

[1] IF the screen saver is activated, THEN DEPRESS any of the prompt keys at the bottom of the screen to display the monitored channels.

Standard:

May depress prompt key to activate display SAT_ UNSAT N/A COMMENTS:__________________

CUE: if display is checked detector 141 A and B indicate Upscale Trips You have the necessary too1s1Qcomp1ete the task.

JPM f PAGE 5 OF 7 NOTES

1) There are two detectors for each channel of the Reactor Zone/Refuel Zone Monitors and are indicated on each monitor as follows:

2-RM 140/142 Display Description 2A 2-RE-90-142A, Reactor Zone channel A detector A.

2B 2-RE-90-142B, Reactor Zone channel A detector B.

OA 2-RE-90-140A, Refuel Zone channel A detector A.

OB 2-RE-90-140B, Refuel zone channel A detector B.

2-RM-90-141/143 Display Description 3A 2-RE-90-143A, Reactor Zone channel B detector A.

3B 2-RE-90-143B, Reactor Zone channel B detector B.

1A 2-RE-90-141A, Refuel Zone channel B detector A.

lB 2-RE-90-141B, Refuel Zone channel B detector B.

2) Only the A detector of each channel described above has input to radiation recorder 2-RR-90-144 Reactor & Refuel Zone Exhaust Radiation.

3) Any active trip condition will be indicated by a highlighted TRIP at the top of the screen. A non-highlighted TRIP at the top of the screen indicates that there are one or more past trip conditions that have not been acknowledged.

4) Trips on the Reactor Zone/Refuel Zone Radiation monitors will automatically reset when the alarming condition resets.

JPM f PAGE 6 OF 7 Performance Step 2: Critical X Not Critical

[2] Immediate Resetting of Group 6 Isolation Due to Reactor Zone Radiation Monitors CAUTION A Reactor Zone isolation can cause a unit scram in less than five minutes due to high temperature in the steam tunnel.

NOTES

1) This section is to be performed in the event of a trip signal that will not reset in order to prevent further impact to plant operation due to reactor zone isolation. This is only considered appropriate when the signal is believed to be invalid.

2) Technical Specifications only allow one trip channel at a time to be out of service. This section provides directions for removing both trip channels from service but should only be performed on one channel at a time. Reference Technical Specification 3.3.6.2 for limiting conditions.

3) This section places jumpers to inhibit the upscale trips for a monitor.

4) Downscale trips take more than one trip channel to activate the logic.

[2.1] PLACE affected monitor keylock switch to fNOP position.

Standard:

Simulates placing monitor 2-RM-90-141/143 keylock switch to INOP SAT UNSAT N/A COMMENTS:__________________

CUE: Keylock switch is-in the OP position for monitor 2-RM-90-14 11143. -

JPM f PAGE 7 OF 7 Performance Step 3:

Critical X Not Critical

[2.2] IF the affected monitor is 2-RM-90-140/142, THEN PLACE jumper across the following terminals in the back of Panel 2-9-10 to inhibit the upscale trip:

TB HH terminals 49 and 50

[2.3] IF the affected monitor is 2-RM-90-141/143, THEN PLACE jumper across the following terminals in the back of Panel 2-9-10 to inhibit the upscale trip:

TB DD terminals 59 and 60 Standard:

Simulates performing step 2.3, places a jumper across terminals 59 and 60 on TB DD SAT_ UNSAT N/A COMMENTS:__________________________

CUE: Jumperis placed across terminals 59 and6O oiiTB DD END OF TASK STOP TIME

OPERATOR:

RO SRO DATE:

JPM NUMBER: f TASK NUMBER: U-090-NO-1 1 TASK TITLE: Inhibit trip signal for NUMAC 3-RM-90-141/143 KIA NUMBER: 272000 K3.06 KIA RATING: RO 3.4 SRO: 3.6 TASK STANDARD: Trip signal inhibited for NUMAC 3-RM-90-141/143 LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 3-01-90 VALIDATION TIME:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

JPM f PAGE 2 OF 7 INITIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 3-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 3-RE-90-141AIB. The trip signal will not reset and has been confirmed to be valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 3-01-90 Radiation Monitoring System section 6.4, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM f PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. SELF CHECKING may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. Observe ALL plant radiological and safety precautions. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied.

When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit Operator. The RX & REFUEL ZONE EXH CH B RAD MON RTMR 3-RM-90-141/143 has an upscale trip locked in on REFUEL ZONE DET A and B, 3-RE-90-14 lA/B. The trip signal will not reset and has been confirmed to be valid.

INITIATING CUE:

The Unit Supervisor directs you to inhibit the upscale trip per 3-01-90 Radiation Monitoring System section 6.4, to prevent further impact to plant operation due to the reactor zone isolation.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM f PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical 6.4 NUMAC Radiation Monitor Operation NOTES

1) This section is applicable to Main Steam Line radiation monitors 3-RM-90-136, 137 and Reactor Zone/Refuel Zone radiation monitors 3-RM-90-140/142 and 3 -RM 141/143.

2) A screen saver activates on the monitor after 30 minutes of constant display.

[1) IF the screen saver is activated, THEN DEPRESS any of the prompt keys at the bottom of the screen to display the monitored channels.

Standard:

May depress prompt key to activate display SAT UNSAT N/A COMMENTS:____

CUE: if display is checked detector 141 A and B indicate Upscale Trips Youhave the necessary ools to comp1etthetask.

JPM f PAGE 5 OF 7 NOTES

1) There are two detectors for each channel of the Reactor Zone/Refuel Zone Monitors and are indicated on each monitor as follows:

3 -RM 140/142 Display Description 2A 3-RE-90-142A, Reactor Zone channel A detector A.

2B 3-RE-90-142B, Reactor Zone channel A detector B.

OA 3-RE-90-140A, Refuel Zone channel A detector A.

OB 3-RE-90-140B, Refuel zone channel A detector B.

2-RM-90-141/143 Display Description 3A 3-RE-90-143A, Reactor Zone channel B detector A.

3B 3-RE-90-143B, Reactor Zone channel B detector B.

1A 3-RE-90-141A, Refuel Zone channel B detector A.

lB 3-RE-90-141B, Refuel Zone channel B detector B.

2) Only the A detector of each channel described above has input to radiation recorder 3-RR-90-144 Reactor & Refuel Zone Exhaust Radiation.

3) Any active trip condition will be indicated by a highlighted TRIP at the top of the screen. A non-highlighted TRIP at the top of the screen indicates that there are one or more past trip conditions that have not been acknowledged.

4) Trips on the Reactor Zone/Refuel Zone Radiation monitors will automatically reset when the alarming condition resets.

JPM f PAGE 6 OF 7 Performance Step 2: Critical X Not Critical

[2] PERFORM the following to immediately Reset Group 6 Isolation Due to Reactor Zone Radiation Monitors.

CAUTION A Reactor Zone isolation can cause a unit scram in less than five minutes due to high temperature in the steam tunnel.

NOTES

1) This section is to be performed in the event of a trip signal that will NOT reset in order to prevent further impact to plant operation due to reactor zone isolation. This is only considered appropriate when the signal is believed to be invalid.

2) Technical Specifications only allow one trip channel at a time to be out of service. This section provides directions for removing both trip channels from service but should only be performed on one channel at a time. Reference Technical Specification 3.3.6.2 for limiting conditions.

3) This section places jumpers to inhibit the upscale trips for a monitor

[2.1] PLACE affected monitor keylock switch to 1NOP position.

Standard:

Simulates placing monitor 3-RM-90-141/143 keylock switch to INOP SAT UNSAT N/A COMMENTS:

JPM f PAGE 7 OF 7 Performance Step 3: X Not Critical

[2.2] IF the affected monitor is 3-RM-90-140/142, THEN PLACE jumper across the following terminals in the back of Panel 3-9-10 to inhibit the upscale trip:

TB HH terminals 49 and 50

[2.3] IF the affected monitor is 3-RM-90-141/143, THEN PLACE jumper across the following terminals in the back of Panel 3-9-10 to inhibit the upscale trip:

TB DD terminals 59 and 60 Standard:

Simulates performing step 2.3, places a jumper across terminals 59 and 60 on TB DD SAT UNSAT N/A COMMENTS:_________________________

CUE: Jumper is placed across terminals 59 and 60 on TB DD END OF TASK STOP TIME

JPM g PAGE 1 OF 8 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: g TASK NUMBER: U-000-EM-74 TASK TITLE: Crosstie CAD to Drywell Control Air KIA NUMBER: 218000 A2.03 KJA RATING: RO 3.4 SRO: 3.6 TASK STANDARD: Align Containment Air Dilution systems A and B to the Drywell Air System and then isolates CAD System B.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-8G VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator. The Unit 2 reactor has scrammed. EOI-l has been followed to RC/P-8.

INITIATING CUE: The Unit Supervisor has directed you to perform 2-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g PAGE 3 OF S IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. The Unit 2 reactor has scrammed. EOI-1 has been followed to RCIP-8.

INITIATiNG CUE: The Unit Supervisor has directed you to perform 2-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g PAGE 4 OF 8 START TIME____

Performance Step 1: Critical X Not Critical

1. OPEN the following valves:

O-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 1, Panel 9-54)

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 1, Panel 9-55)

Standard:

Opens 0-FCV-84-5 and 16 SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 2: Critical Not Critical X

2. VERIFY 0-PI-84-6, N2 VAPORIZER A OUTLET PRESSURE, and 0-PI-84-17, N2 VAPORIZER B OUTLET PRESSURE, indicate approximately 100 psig (Unit 1, Panel 9-54 and 9-55)

Standard:

Verifies 0-PI-84-6 and 0-PI-84-17 (Located on back of Unit 2 Panel 9-54 in simulator) indicating approximately 100 psig.

SAT UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 5 OF 8 Performance Step 3: *Critical Not Critical

3 PLACE keylock switch 2-HS-84-48, CAD A CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-54)

4. CHECK OPEN 2-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR, (Unit 2, Panel 9-54)

Standard:

Places keylock switch 2-HS-84-48 in Open and verifies 2-FSV-84-48 is open SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 4: *Critical X Not Critical

5* PLACE keylock switch 2-HS-84-49, CAD B CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-55)

6. CHECK OPEN 2-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-55)

Standard:

Places keylock switch 2-HS-84-49 in Open and verifies 2-FSV-84-49 open SAT_ UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 6 OF 8 Performance Step 5: Critical X Not Critical

7. CHECK MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 2-PA-32-31, alarm cleared (2-XA-55-3D, Window 18)

Standard:

Recognizes MAN STEAM RELIEF VLV AIR ACCUM PRESS LOW (2-XA-55-3D, Win. 18) still in Alarm (would Not clear) and continues with procedure.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 6: Critical Not Critical

8. IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 2-PA-32-31, annunciator is or remains in alarm (2-XA-55-3D, Window 18), THEN DETERMINE which Drywell Control Air header is depressurized as follows:

a. DISPATCH personnel to Unit 2, RB, El 565 ft, to MONITOR the following indications for low pressure:

2-PI-84-51, CAD N2 PRESSURE TO DWCA indicator, for CAD A (R- 10 S-line, by Drywell Access Door)

2-PI-84-50, DW CONT AIR N2 SUPPLY PRESS indicator, for CAD B (R-12 U-line, behind 480V RB Vent Board 2B)

Standard:

Dispatches personnel to Reactor Building to monitor 2-PI-84-51 and 2-PI-84-50 for low pressure.

SAT UNSAT N/A COMMENTS:____________________________

CUE: [When dispatched, as AUO, report] 2-PI-84-51, CAD N 2 Pressure to DWCA indicator, for CAD A is reading 110 psig. 2-PI-84-50 for CAD B is reading 5 psig.

JPM g PAGE 7 OF 8 Performance Step 7: Critical X Not Critical

b. MONITOR 0-FI-84-7(l 8), CAD lINE A(B) N2 FLOW, on Unit 1, Panel 1-9-54(55) for high flow.

Standard:

Recognizes 0-FI-84-7 flow 0 scfm and 0-FI-84-l 8 flow 90 scfln SAT_ UNSAT N/A COMMENTS:_______________________________

NOTE CAD System A to Drywell Control Air supplies the following MSIVs:

2-FCV-l-14, MSIV LINE A INBOARD

2-FCV-l-26, MSIV LINE B INBOARD NOTE CAD System B to Drywell Control Air supplies the following MSIVs:

2-FCV-l-37, MSIV LINE C INBOARD

2-FCV-l-51, MSIV LINE D INBOARD Performance Step 8: Critical Not Critical X

c. MONITOR inboard MSIV indication status for valves drifting closed.

Standard:

Recognizes 2-FCV-l-37 and 51 closed SAT UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 8 OF 8 Performance Step 9: Critical Not Critical X

9. IF Drywell Control Air header supplied from CAD System A shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 1, Panel 9-54)

2-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-54)

Standard:

N/A No indications of being depressurized SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 10: Critical X Not Critical

10. IF Drywell Control Air header supplied from CAD B shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 1, Panel 9-55)

2-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-5 5)

Standard:

Closes 0-FCV 16 and 2-FSV-84-49 SAT_ UNSAT N/A COMMENTS:______

STOP TIME____

END OF TASK

JPM g PAGE 1 OF 8 OPERATOR:____________________

RO___ SRO___ DATE:

JPM NUMBER: g TASK NUMBER: U-000-EM-74 TASK TITLE: Crosstie CAD to Drywell Control Air K/A NUMBER: 218000 A2.03 K/A RATING: RO 3.4 SRO: 3.6 TASK STANDARD: Align Containment Air Dilution systems A and B to the Drywell Air System and then isolates CAD System B.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-8G VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TiME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator. The Unit 3 reactor has scrammed. EOI-1 has been followed to RC/P-8.

INITIATING CUE: The Unit Supervisor has directed you to perform 3-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. The Unit 3 reactor has scrammed. EOI-1 has been followed to RC/P-8.

INITIATING CUE: The Unit Supervisor has directed you to perform 3-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g PAGE 4 OF 8 START TIME____

Perfonnance Step 1: Critical X Not Critical

1. OPEN the following valves:

0-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Panel 3-9-54)

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Panel 3-9-55)

Standard:

Opens 0-FCV-84-5 and 16 SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 2: Critical Not Critical X

2. VERIFY 0-PI-84-6/3, VAPOR A OUTLET PRESS, and 0-PI-84-17/3, VAPOR B OUTLET PRESS, indicate approximately 100 psig (Unit 3, Panel 3-9-54 and 3-9-55)

Standard:

Verified 0-PI-84-6/3 and 0-PI-84-17/3 (Located on Unit 3, Panel 3-9-54 and 3-9-55) indicating approximately 100 psig.

SAT UNSAT N/A COMMENTS:

JPM g PAGE 5 OF 8 Performance Step 3: X Not Critical

3 PLACE keylock switch 3-HS-84-48, CAD A CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 3, Panel 3-9-54)

4. CHECK OPEN 3-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR, (Unit 3, Panel 3-9-54)

Standard:

Places keylock switch 3-HS-84-48 in Open and verifies 3-FSV-84-48 open SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 4: *Critical X Not Critical

5 PLACE keylock switch 3-HS-84-49, CAD B CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 3, Panel 3-9-55)

6. CHECK OPEN 3-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3-9-55)

Standard:

Places keylock switch 3-HS-84-49 in Open and verifies 3-FSV-84-49 SAT UNSAT N/A _COMMENTS:______________________________

JPM g PAGE 6 OF 8 Performance Step 5: Critical X Not Critical

7. CHECK MAiN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 3-PA-32-3 1, alarm cleared (3-XA-5 5-3D, Window 18)

Standard:

Recognizes MAiN STEAM RELIEF VLV AIR ACCUM PRESS LOW (3-XA-55-3D, Win. 18) still in Alarm (would NOT clear) and continues with procedure.

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 6: Critical Not Critical X

8. IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 3-PA-32-31, annunciator is or remains in alarm (3-XA-55-3D, Window 18), THEN DETERMINE which Drywell Control Air header is depressurized as follows:

a. DISPATCH personnel to Unit 3, RB, El 565 ft. to MONITOR the following indications for low pressure:

3-PI-84-51, CAD A CROSSTIE TO DWCA PRESS INDR, for CAD A (R-17 S-line, by Drywell Access Door)

3-PI-84-50, DW CONT AIR N2 SUPPLY PRESS indicator, for CAD B

((R-19 U-line, behind 480V RB Vent Board 3B)

Standard:

Dispatches personnel to Reactor Building to monitor 3-PI-84-51 and 3-PI-84-50 for low pressure.

SAT UNSAT N/A _COMMENTS:_____________________________

CUE: lWhen dispatched, as AUO, report] 3-PI-84-51, CAD N 2 Pressure to DWCA indicator, for CAD A is reading 110 psig and 3-PI-84-50 reading 5 psig.

JPM g PAGE 7 OF 8 Performance Step 7: Critical Not Critical

b. MONITOR 0-FI-84-7/3(1 8/3), CAD A(B) N2 SYSTEM FLOW, on Panel 3-9-54(55) for high flow.

Standard:

Recognizes 0-FI-84-7/3 flow is 0 scfm and that 0-FI 18 flow is 50 scffii SAT UNSAT N/A COMMENTS:_______________________________

NOTE CAD System A to Drywell Control Air supplies the following MSIVs:

3-FCV-1-14, MSIV LINE A INBOARD

3-FCV-1-26, MSIV LINE B INBOARD NOTE CAD System B to Drywell Control Air supplies the following MSIVs:

3-FCV-1-37, MSIV LINE C INBOARD

3-FCV-1-51, MSIV LINE D INBOARD Performance Step 8: Critical Not Critical X

c. MONITOR inboard MSIV indication status for valves drifting closed.

Standard:

Recognizes 3-FCV-1-37 and 51 closed SAT_ UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 8 OF 8 Performance Step 9: Critical Not Critical X

9. IF Drywell Control Air header supplied from CAD System A shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 3, Panel 3-9-54)

3-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3-9-54)

Standard:

N/A No indications of being depressurized SAT_ UNSAT N/A _COMMENTS:____________________________

Performance Step 10: Critical Not Critical

10. IF Drywell Control Air header supplied from CAD B shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 3, Panel 3-9-55)

3-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3 55)

Standard:

Closes 0-FCV-84-16 and 3-FSV-84-49 SAT UNSAT N/A _COMMENTS:______

STOP TIME____

END OF TASK

JPM h PAGE 1 OF 8 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: h TASK NUMBER: U-000-EM-60 TASK TITLE: 1-EOI Appendix-i 1H Alternate Pressure Control KIA NUMBER: 271000 A2.04 K/A RATING: RO 3.7 SRO: 4.1 TASK STANDARD: l-EOI Appendix-i 1H simulated complete with bypass valves depressurizing the RPV LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: i-EOI Appendix-i iH VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator on Unit 1, the Unit Supervisor has transitioned to 1-C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HJ11NOP (1 -XA-55-4C) is sealed in.

Offgas System Isolation Valve 1 -FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform 1-EOI Appendix-i iH Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 3 OF 8 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator on Unit 1, the Unit Supervisor has transitioned to 1 -C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HI/INOP (1 -XA-55-4C) is sealed in.

Offgas System Isolation Valve 1-FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform i-EOI Appendix-i iH Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 4 OF 8 START TIME____

Performance Step 1: Critical Not Critical X

1. IF ANY indication of gross fuel failure exists, THEN BEFORE continuing in this procedure, NOTIFY SED that offsite release rate limits may be exceeded.

Standard:

Given in initial conditions that a gross fuel failure does not exist.

SAT_ UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

2. VERIFY Main Condenser Off-Gas is aligned to the stack as follows:

a. IF OG POST TRTMT RAD MONITOR HI-HI-HI/INOP 1-RA-90-265C Annunciator (1-XA-55-4C, Window 35) is sealed in, THEN JUMPER Off-Gas Post Treatment Radiation Hi-Hi-Hi Isolation to l-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, as follows:

1) REFER to Attachment 1 and OBTAIN one banana jack jumper from Control Room EOI Equipment Storage Box.

Standard:

Identifies where to obtain the banana jack jumper SAT UNSAT N/A COMMENTS:

JPM h PAGE 5 OF 8 Performance Step 3: Critical X Not Critical

2) LOCATE terminal strip BB, Panel 1-9-53 Bay 1 Rear.

3) JUMPER BB-59 to BB-60 (Panel 1-9-53).

Standard:

Simulates installing jumper on terminal strip BB from BB-59 to BB-60 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 4: Critical Not Critical X

b. VERIFY OPEN l-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE (Panel 1-9-53).

Standard:

Checks position of 1-FCV-66-28 SAT UNSAT N/A COMMENTS:

JPM h PAGE 6 OF 8 Performance Step 5: Critical Not Critical X

3. VERIFY SJAE 1A or lB in service and aligned to Main Condenser (Panel 9-7).

Standard:

Given in initial conditions SAT USAT N/A _COMMENTS:_______________________________

Performance Step 6: Critical Not Critical X

4. IF EITHER of the following exists:

l-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, CANNOT be opened, OR

SJAEs CANNOT be placed in service or aligned to Main Condenser, Standard:

Step is NA, Operator just opened 1 -FCV-66-28 SAT_ UNSAT N/A COMMENTS:_____________________________

JPM h PAGE 7 OF 8 Performance Step 7: Critical X Not Critical

5. IF ANY Main Steam Line is NOT isolated, THEN CONTINUE in this procedure at Step 12.

Standard:

Continues in procedure at step 12 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 8: Critical X Not Critical

12. OPEN Turbine Bypass valves as necessary to rapidly depressurize RPV.

Standard:

Simulates opening Turbine Bypass Valves by depressing Bypass Valve Opening Jack raise pushbutton until all 9 Turbine Bypass valves are Open.

SAT_ UNSAT N/A COMMENTS:____________________________

CUE: Pushbu4qn dressed. b passva1e 1 indication going oim 0% to 100% red ItondgeeiIight og bypass vave 4#3, #4, #5, #6, #7, #2 an4z#9 red

. light on green light off 0% to 100%. Reactor Pressure is lowering.

JPM h PAGE 8 OF 8 Performance Step 9: Critical Not Critical NOTIFY Unit Supervisor that 1-EOI Appendix-i iH is complete and rapidly depressurizing the RPV.

Standard:

Notifies Unit Supervisor SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME____

JPM h PAGE 1 OF 8 OPERATOR:______________________

RO___ SRO___ DATE:

JPM NUMBER: h TASK NUMBER: U-000-EM-60 TASK TITLE: 2-EOI Appendix-i iH Alternate Pressure Control KIA NUMBER: 271000 A2.04 KJA RATING: RO 3.7 SRO: 4.i TASK STANDARD: 2-EOI Appendix-i 1H simulated complete with bypass valves depressurizing the RPV LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-i iH VALIDATION TIME:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator on Unit 2, the Unit Supervisor has transitioned to 2-C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HI/INOP (2-XA-55-4C) is sealed in.

Offgas System Isolation Valve 2-FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform 2-EOI Appendix-i 1H Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 3 OF 8 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be can-ied out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator on Unit 2, the Unit Supervisor has transitioned to 2-C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HIIINOP (2-XA-55-4C) is sealed in.

Offgas System Isolation Valve 2-FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform 2-EOI Appendix-i iH Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 4 OF 8 START TIME____

Performance Step 1: Critical Not Critical X

1. IF ANY indication of gross fuel failure exists, THEN BEFORE continuing in this procedure, NOTIFY SED that offsite release rate limits may be exceeded.

Standard:

Given in initial conditions that a gross fuel failure does not exist.

SAT_ UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

2. VERIFY Main Condenser Off-Gas is aligned to the stack as follows:

a. W OG POST TRTMT RAD MONITOR HI-HI-HI/INOP Annunciator (2-XA-55-4C, Window 35) is sealed in, THEN JUMPER Off-Gas Post Treatment Radiation Hi-Hi-Hi Isolation to 2-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, as follows:

1) REFER to Attachment 1 and OBTAIN one banana jack jumper from Control Room EOI Equipment Storage Box.

Standard:

Identifies where to obtain the banana jack jumper SAT UNSAT N/A COMMENTS:

JPM h PAGE 5 OF 8 Performance Step 3: Critical X Not Critical

2) LOCATE terminal strip BB, Panel 9-53, Rear.

3) JUMPER BB-59 to BB-60, Panel 9-53.

Standard:

Simulates installing jumper on terminal strip BB from BB-59 to BB-60 SAT UNSAT N/A COMMENTS:_____________________________

CUE: Whøn snuWedjtáper inst11çd om BB-59to13B-60 Performance Step 4: Critical Not Critical X

b. VERIFY OPEN 2-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE Panel 9-53.

Standard:

Checks position of 2-FCV-66-28 SAT UNSAT N/A COMMENTS:

CUE: 2-FcV-66-28is1 Red lightOnand Green light Off*Va ye is Open

JPM h PAGE 6 OF 8 Performance Step 5: Critical Not Critical X

3. VERIFY SJAE 2A or 2B in service and aligned to Main Condenser (Panel 9-7).

Standard:

Given in initial conditions SAT UNSAT N/A COMMENTS:______________________________

Performance Step 6: Critical Not Critical X

4. IF EITHER of the following exists:

2-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, CANNOT be opened, OR

SJAEs CANNOT be placed in service or aligned to Main Condenser, Standard:

Step is NA, Operator just opened 2-FCV-66-28 SAT UNSAT N/A _COMMENTS:______________________________

JPM h PAGE 7 OF 8 Performance Step 7: Critical X Not Critical

5. IF ANY Main Steam Line is NOT isolated, THEN CONTINUE in this procedure at Step 12.

Standard:

Continues in procedure at step 12 SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 8: Critical X Not Critical

12. OPEN Turbine Bypass valves as necessary to rapidly depressurize RPV.

Standard:

Simulates opening Turbine Bypass Valves by depressing Bypass Valve Opening Jack raise pushbutton until all 9 Turbine Bypass valves are Open.

SAT_ UNSAT N/A COMMENTS:

[ CUE: Puslibitton depressed, bypassva1ve #i iiid>eation going form 0% to) 00% red 1ihton and green1ight qft. bypass vthe #2, #3, #4, #5#6, #7, #8 and #9 red light oh green light off 0% to 100%. Reactor Pressure is lowering.

JPM h PAGE 8 OF 8 Performance Step 9: Critical Not Critical X NOTIFY Unit Supervisor that 2-EOI Appendix-11H is complete and rapidly depressurizing the RPV.

Standard:

Notifies Unit Supervisor SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME____

OPERATOR:__________________

RO___ SRO___ DATE:

JPM NUMBER: h TASK NUMBER: U-000-EM-60 TASK TITLE: 3-EOI Appendix-i 1H Alternate Pressure Control K/A NUMBER: 271000 A2.04 K/A RATING: RO 3.7 SRO: 4.1 TASK STANDARD: 3-EOI Appendix-i ill simulated complete with bypass valves depressurizing the RPV LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-i 1H VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

JPM h PAGE 2 OF 8 INITIAL CONDITIONS: You are an Operator on Unit 3, the Unit Supervisor has transitioned to 3-C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HJ/[NOP (3-XA-55-4C) is sealed in.

Offgas System Isolation Valve 3-FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform 3-EOI Appendix-i iH Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 3 OF 8 iN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator on Unit 3, the Unit Supervisor has transitioned to 3-C-2 Emergency RPV Depressurization. During Emergency Depressurization only 1 MSRV could be opened, RPV pressure remains greater than 90 psig above Suppression Chamber Pressure. Offgas Post Treatment Radiation Monitor HI-HI-HLINOP (3-XA-55-4C) is sealed in.

Offgas System Isolation Valve 3-FCV-66-28 is closed. A gross fuel failure does not exist. SJAE A is in service and aligned to the Main Condenser. Main Steam Line D is not isolated.

INITIATING CUE: The Unit Supervisor directs you to perform 3-EOI Appendix-11H Alternate RPV Pressure Control Systems Main Condenser and rapidly depressurize the RPV.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM h PAGE 4 OF 8 START TIME____

Performance Step 1: Critical Not Critical X

1. IF ANY indication of gross fuel failure exists, THEN BEFORE continuing in this procedure, NOTIFY SED that offsite release rate limits may be exceeded.

Standard:

Given in initial conditions that a gross fuel failure does not exist.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 2: Critical X Not Critical

2. VERIFY Main Condenser Off-Gas is aligned to the stack as follows:

a. IF OG POST TRTMT RAD MONITOR HI-HI-HI/INOP Annunciator (3-XA-55-4C, Window 35) is sealed in, THEN JUMPER Off-Gas Post Treatment Radiation Hi-Hi-Hi Isolation to 3-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, as follows:

1) REFER to Attachment 1 and OBTAIN one banana jack jumper from Control Room EOI Equipment Storage Box.

Standard:

Identifies where to obtain the banana jack jumper SAT UNSAT N/A COMMENTS:

CUE: When location ofbananajack jumper identified, Qperator has the jumper

JPM h PAGE 5 OF 8 Performance Step 3: Critical X Not Critical

2) LOCATE terminal strip BB, Panel 3-9-53, Rear.

3) JUMPER BB-59 to BB-60 Panel 3-9-53.

Standard:

Simulates installing jumper on terminal strip BB from BB-59 to BB-60 SAT UNSAT N/A COMMENTS:_____________________________

CUE: when simuIate4jumpe insIfiorn BB-59 to B-6O Performance Step 4: Critical Not Critical

b. VERIFY OPEN 3-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE Panel 3-9-53.

Standard:

Checks position of 3-FCV-66-28 SAT UNSAT N/A COMMENTS:

CUE: 3-PCV--28is1iasRed1igl%Onarni Green 1ightOff Va1ves Open .

JPM h PAGE 6 OF 8 Performance Step 5: Critical Not Critical

3. VERIFY SJAE 3A or 3B in service and aligned to Main Condenser (Panel 3-9-7).

Standard:

Given in initial conditiOns SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 6: Critical Not Critical X

4. IF EITHER of the following exists:

3-FCV-66-28, OFFGAS SYSTEM ISOLATION VALVE, CANNOT be opened, OR

SJAEs CANNOT be placed in service or aligned to Main Condenser, Standard:

Step is NA, Operator just verified open 3-FCV-66-28 SAT UNSAT N/A COMMENTS:____________________________

JPM h PAGE 7 OF 8 Performance Step 7: Critical X Not Critical

5. IF ANY Main Steam Line is NOT isolated, THEN CONTINUE in this procedure at Step 12.

Standard:

Continues in procedure at step 12 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 8: Critical X Not Critical

12. OPEN Turbine Bypass valves as necessary to rapidly depressurize RPV.

Standard:

Simulates opening Turbine Bypass Valves by depressing Bypass Valve Opening Jack raise pushbutton until all 9 Turbine Bypass valves are Open.

SAT UNSAT N/A COMMENTS:______________________________

C1XE ushbutton deessed, bypass valve #i indication going form 0% to 100% red light on and greewlight o bypass valve #3, #4, #5, #G, #7, #8 and #9 rcd light on greenit off0% totO0%. Rcactor Pressure is lowering.

JPM h PAGE 8 OF 8 Performance Step 9: Critical Not Critical X NOTIFY Unit Supervisor that 3-EOI Appendix-11H is complete and rapidly depressurizing the RPV.

Standard:

Notifies Unit Supervisor SAT UNSAT N/A COMMENTS:

UI3 Mka9wicdge notification :*

END OF TASK STOP TIME____

JPM +/-

PAGE 1 OF 7 OPERATOR:________________________

RO___ SRO___ DATE:

JPM NUMBER: i TASK NUMBER: U-000-EM- 19 TASK TITLE: 1-EOI Appendix-lA Removal of RPS SCRAM Fuses KJA NUMBER: 212000 A2.20 K/A RATiNG: RO 4.1 SRO 4.2 TASK STANDARD: Simulate removal of SCRAM Fuses lAW 1-EOI Appendix-lA LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1-EOI Appendix-lA VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are the Extra Operator. The Unit 1 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-1 has been entered and followed to RC/Q-23. The Scram Discharge Volume VentlDrain Valves indicate closed on panel 1-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 1-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM I PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are the Extra Operator. The Unit 1 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-l has been entered and followed to RC/Q-23. The Scram Discharge Volume Vent/Drain Valves indicate closed on panel 1-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with l-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM +/-

PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical

1. VERIFY CLOSED Scram Discharge Volume Vent and Drain Valves at the SCRAM DISCHARGE VOLUME VENT/DRAIN VLVS display on panel 1-9-5.

Standard:

Given in initial conditions SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 2: Critical Not Critical

2. DISPATCH personnel to the Auxiliary Instrument Room to perform the following:

a. REFER to Attachment 1 and OBTAIN fuse pullers from EOI Equipment Storage box.

Standard:

Simulate unlocking EOI Equipment storage and obtaining fuse pullers SAT_ UNSAT N/A COMMENTS:______________________________

CU1 When locafion ofBOl Storage Box identified/Operator has the fuse pullers

JPM +/-

PAGE 5 OF 7 Performance Step 3: Critical Not Critical

b. LOCATE Terminal Strip CC inside 1-PNLA-009-0015, Bay 2, Rear.

c. REMOVE the following fuses (located at bottom of terminal strip CC, 1 -PNLA-009-OO 15):

RPS BUS A BLOCK NUMBER FUSE ID CC FOUR (4) 1-FU1-085-0037AA CC FiVE (5) 1-FU1-085-0039A/2 CC SIX (6) 1-FU1-085-0039A/3 CC SEVEN (7) 1-FU1-085-0039A/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT UNSAT N/A COMMENTS:_____________

CUE When location ofproper Fuse is indicated the Fuse has beenremoved

JPM +/-

PAGE 6 OF 7 Performance Step 4: Critical X Not Critical

d. LOCATE Terminal Strip CC inside 1-PNLA-009-0017, Bay 2, Rear.

e. REMOVE the following fuses (located at bottom of terminal strip CC, 1 -PNLA-009-OO 17):

RPS BUS B BLOCK NUMBER FUSE ID CC FOUR (4) 1-FU1-085-0037BA CC FIVE (5) 1-FU1-085-0039B/2 CC SIX (6) 1-FU1-085-0039B/3 CC SEVEN (7) 1-FU1-085-0039B/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT_ UNSAT N/A COMMENTS:_______________________________

CUE When location ofproper Fuse is indicated the Fuse has beentemoved

JPM +/-

PAGE 7 OF 7 Performance Step 5: Critical Not Critical X

f. WHEN ALL fuses are removed, THEN NOTIFY Unit Operator.

Standard:

Notifies Unit 1 Operator All RPS Fuse removed SAT UNSAT N/A COMMENTS:______

END OF TASK STOP TIME____

JPM +/-

PAGE 1 OF 7 OPERATOR:________________________

RO___ SRO___ DATE:

JPM NUMBER: i TASK NUMBER: U-000-EM-19 TASK TITLE: 2-EOI Appendix-lA Removal of RPS SCRAM Fuses K/A NUMBER: 212000 A2.20 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Simulate removal of SCRAM Fuses JAW 2-EOI Appendix-lA LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-lA VALIDATION TiME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are the Extra Operator. The Unit 2 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-l has been entered and followed to RC/Q-23. The Scram Discharge Volume Vent/Drain Valves indicate closed on panel 2-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 2-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM i PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WThL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are the Extra Operator. The Unit 2 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-l has been entered and followed to RC/Q-23. The Scram Discharge Volume Vent/Drain Valves indicate closed on panel 2-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 2-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM +/-

PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical

1. VERIFY CLOSED Scram Discharge Volume Vent and Drain Valves at the SCRAM DISCHARGE VOLUME VENT/DRAiN VLVS display on panel 9-5.

Standard:

Given in initial conditions SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 2: Critical Not Critical X

2. DISPATCH personnel to Unit 2 Auxiliary Instrument Room to perform the following:

a. REFER to Attachment 1 and OBTAIN fuse pullers from EOI Equipment Storage box.

Standard:

Simulate unlocking EOI Equipment storage and obtaining fuse pullers SAT_ UNSAT N/A COMMENTS:_____________________________

JPM +/-

PAGE 5 OF 7 Performance Step 3: Critical Not Critical

b. LOCATE Terminal Strip CC inside Panel 9-15, Bay 2, Rear.

c. REMOVE the following fuses (located at bottom of terminal strip CC, Panel 9-15):

RPS BUS A BLOCK NUMBER FUSE ID CC FOUR (4) 2-FU1-085-0037AA CC FIVE (5) 2-FU1-085-0039A/2 CC SIX (6) 2-FU1-085-0039A/3 CC SEVEN (7) 2-FUI-085-0039A14 Standard:

Identifies terminal strip and simulates removing listed fuses SAT UNSAT N/A COMMENTS:_____________

CUE: hen .10 ion of prpr Fue s indicated the Fuse has been removed

JPM +/-

PAGE 6 OF 7 Performance Step 4: Critical X Not Critical

d. LOCATE Terminal Strip CC inside Panel 9-17, Bay 2, Rear.

e. REMOVE the following fuses (located at bottom of terminal strip CC, Panel 9-17):

RPS BUS B BLOCK NUMBER FUSE ID CC FOUR (4) 2-FU1-085-0037BA CC FIVE (5) 2-FU1-085-0039B/2 CC SIX (6) 2-FU1-085-0039B/3 CC SEVEN (7) 2-FU1-085-0039B/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT_ UNSAT N/A COMMENTS:_____________________

CUE: When 1ocátion Qf properFuse is indicated the Fuse has been removed

JPM +/-

PAGE 7 OF 7 Performance Step 5: Critical Not Critical X

f. WHEN ALL fuses are removed, THEN NOTIFY Unit Operator.

Standard:

Notifies Unit 2 Operator All RPS Fuse removed SAT_ UNSAT N/A COMMENTS:______

CUE: Acknowledge Notification, SRO Does not directreplacement of fuses END OF TASK STOP TIME

JPM +/-

PAGE 1 OF 7 OPERATOR:________________________

RO___ SRO___ DATE:

JPM NUMBER: i TASK NUMBER: U-000-EM-19 TASK TITLE: 3-EOI Appendix-lA Removal of RPS SCRAM Fuses KJA NUMBER: 212000 A2.20 KIA RATING: RO 4.1 SRO 4.2 TASK STANDARD: Simulate removal of SCRAM Fuses lAW 3-EOI Appendix-lA LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-lA VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are the Extra Operator. The Unit 3 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-1 has been entered and followed to RC/Q-23. The Scram Discharge Volume Vent/Drain Valves indicate closed on panel 3-9-5.

INITIATiNG CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 3-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

3PM +/-

PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are the Extra Operator. The Unit 3 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-l has been entered and followed to RC/Q-23. The Scram Discharge Volume VentJDrain Valves indicate closed on panel 3-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 3-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM +/-

PAGE 4 OF 7 START TIME____

Performance Step 1: Critical Not Critical

1. VERIFY CLOSED Scram Discharge Volume Vent and Drain Valves at the SCRAM DISCHARGE VOLUME VENT/DRAiN VLVS display on panel 9-5.

Standard:

Given in initial conditions SAT UNSAT N/A _COMMENTS:____________________________

Performance Step 2: Critical Not Critical X

2. DISPATCH personnel to Unit 3 Auxiliary Instrument Room to perform the following:

a. REFER to Attachment 1 and OBTAIN fuse pullers from EOI Equipment Storage box.

Standard:

Simulate unlocking EOI Equipment storage and obtaining fuse pullers SAT_ UNSAT N/A COMMENTS:_______________________________

CUE: When 1ocatiónofEOIStorageBoiden1ified, Operator has the fuse pullers

JPM +/-

PAGE 5 OF 7 Performance Step 3: Critical Not Critical

b. LOCATE Terminal Strip CC inside Panel 9-15, Bay 2, Rear.

c. REMOVE the following fuses (located at bottom of terminal strip CC, Panel 9-15):

RPS BUS A BLOCK NUMBER FUSE ID CC FOUR (4) 3-FU1-085-0037AA CC FIVE (5) 3-FU1-085-0039A/2 CC SIX (6) 3-FU1-085-0039A/3 CC SEVEN (7) 3-FU1-085-0039A14 Standard:

Identifies terminal strip and simulates removing listed fuses SAT_ UNSAT N/A COMMENTS:_____________

CUE: When locationofproper Fuse is indicated the Fuse has been removed

JPM +/-

PAGE 6 OF 7 Performance Step 4: Critical X Not Critical

d. LOCATE Terminal Strip CC inside Panel 9-17, Bay 2, Rear.

e. REMOVE the following fuses (located at bottom of terminal strip CC, Panel 9-17):

RPS BUS B BLOCK NUMBER FUSE ID CC FOUR (4) 3-FU1-085-0037BA CC FIVE (5) 3-FU1-085-0039B/2 CC SIX (6) 3-FU1-085-0039B/3 CC SEVEN (7) 3-FU1-085-0039B/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT_ UNSAT N/A _COMMENTS:_____________________

CUE hen1aton of properFuse is indicated theFuse bs been removed

JPM +/-

PAGE 7 OF 7 Performance Step 5: Critical Not Critical X

f. WHEN ALL fuses are removed, THEN NOTIFY Unit Operator.

Standard:

Notifies Unit 3 Operator All RPS Fuse removed SAT UNSAT N/A COMMENTS:______

END OF TASK STOP TIME____

JPM j PAGE 1 OF 6 OPERATOR:_______________________

RO___ SRO___ DATE:

JPM NUMBER: j TASK NUMBER: U-00l-AL-06 TASK TITLE: Field actions for stuck open SRV K/A NUMBER: 239002 A2.03 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Stuck Open SRV is closed when power is removed from the SRV by opening the breakers LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 2-AOl-i-i VALIDATION TIME: 25 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 2-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 2-PCV- 1-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 2-PCV- 1-22 from outside the Control Room in accordance with 2-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 3 OF 6 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 2-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 2-PCV-l-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 2-PCV-l-22 from outside the Control Room in accordance with 2-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 4 OF 6 START TIME____

Performance Step 1: Critical X Not Critical NOTES

1) 2-PCV-1-22 is an ADS Valve

2) 2-PCV-1-22 has two power supplies, it will auto transfer on loss of power and is Normal Seeking.

3) Attachment 1 may be addressed for fuse and breaker information.

[2] IF 2-PCV-1-22 is NOT closed, THEN PERFORM the following:

[2.1] On Panel 2-25-32 PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 2-XS-1-22 in EMERG position.

Standard:

Simulate placing 2-XS-1-22 in emergency SAT UNSAT N/A COMMENTS:_______________________________

Wheii si ated2-X is in Enirgency, Róaetor Pressure is Stab1,Greeh light On and Red light Off for SRV 1-21

JPM j PAGE 5 OF 6 Performance Step 2: Critical Not Critical X

[2.2] IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 2-PCV-l-22 on the Acoustic Monitor:

CYCLE the MAiN STM LiNE B RELIEF VALVE, 2-HS-1-22C to the following positions several times.

CLOSE/AUTO to OPEN to CLOSE/AUTO Standard:

Simulates cycling 2-HS-l-22C from CLOSE/AUTO to OPEN to CLOSE/AUTO SAT UNSAT N/A COMMENTS:

CVE 2-HS.4-22C is. in CLOSE/AUTO to OPEN to CLQSE/AUTO Sitchis bcing.

cycled, Red light On and Green light Off When switch is m Open aniGreen light On mid Red lIght Off When switch is m Close/Auto Reactor Pressure remains stable, when Control Room called SRV fails to close or remains open.

Performance Step 3:

Critical X Not Critical

[2.3] IF the SRV does NOT close, THEN PERFORM the following:

A. VERIFY the MAN STM LINE B RELIEF VALVE, 2-HS-l-22C, in the CLOSE/AUTO position.

B. PLACE the associated transfer switch MAN STM LINE B RELIEF VALVE XFR, 2-XS-1-22 in NORM position.

Standard:

Simulates verifying 2-HS-1-22C is in Close/Auto and simulates placing 2-XS-l-22 in Norm SAT UNSAT N/A COMMENTS:

se -2 Grig flff

_1,

JPM j PAGE 6 OF 6 Performance Step 4: Critical X Not Critical

[2.4] IF the SRV does NOT close, THEN REMOVE the power from 2-PCV-l-22 by performing one of the following: (Opening breakers are the preferred method)

A. OPEN the following breakers: (Preferred method)

2A 250V RMOV, Compartment 1 1C2

2B 250V RMOV, Compartment 1C1 Standard:

Simulates opening Compartment 11C2 at 2A 250V RMOV and Compartment 1C1 at 2B 250V RMOV SAT_ UNSAT N/A COMMENTS:______________________________

CUEI .

flO2a2A25d OVisopenaid1i 7RMOVisopep 1

B25Q When Control Room called SKV as Closed If Operator slinulates closmg

. breakers, breakers are closed SkY as Open JPM Failure -

STOP TIME____

END OF TASK

OPERATOR:__________________

RO___ SRO___ DATE:

JPM NUMBER: j TASK NUMBER: U-00 1 -AL-06 TASK TITLE: Field actions for stuck open SRV K/A NUMBER: 239002 A2.03 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Stuck Open SRV is closed when power is removed from the SRV by opening the breakers LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 3-AOl-i-i VALIDATION TIME: 25 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

JPM j PAGE 2 OF 6 INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 3-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 3-PCV-i-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 3-PCV-i-22 from outside the Control Room in accordance with 3-AOl-i-i step 4.2.3[2j.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 3 OF 6 iN-PLANT: I will explain the initial conditions and state the task to be perfonned. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 3-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 3-PCV-1-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 3-PCV-1-22 from outside the Control Room in accordance with 3-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 4 OF 6 START TIME____

Performance Step 1: Critical Not Critical NOTES

1) 3-PCV-l-22 is an ADS Valve

2) 3-PCV-l-22 has two power supplies, it will auto transfer on loss of power and is Normal Seeking.

3) Attachment 1 may be addressed for fuse and breaker information.

[2] IF 3-PCV-l-22 is NOT closed, THEN PERFORM the following:

[2.1] On Panel 3-25-32 PLACE the associated transfer switch MAN STM LNE B RELIEF VALVE XFR, 3-XS-l-22 in EMERG position.

Standard:

Simulate placing 3-XS-l-22 in emergency SAT UNSAT N/A COMMENTS:

CIJE:[ When simulate&3XS4-Z2 is in Emergcny, Reactor Pressire is Stable, (freen tO#ndedligtOffforSRV1-Q2

JPM j PAGE 5 OF 6 Perfonnance Step 2: Critical Not Critical X

[2.2] IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 3-PCV-l-22 on the Acoustic Monitor:

CYCLE the MAIN STM LINE B RELIEF VALVE, 3-HS-1-22C to the following positions several times.

CLOSE/AUTO to OPEN to CLOSE/AUTO Standard:

Simulates cycling 3-HS-l-22C from CLOSE/AUTO to OPEN to CLOSE/AUTO SAT UNSAT N/A COMMENTS:

CUE: B-HS-22C iia CLOSE/ABTO4o OPENto CLOSE/AUTO witth is being OfiwswOped/G1ea ig1 edIigp$4 bsWAtjeaetorressi tntabIetwen opmImV i1s oor;emains,en Performance Step 3:

Critical X Not Critical

[2.3] IF the SRV does NOT close, THEN PERFORM the following:

A. VERIFY the MAIN STM LINE B RELIEF VALVE, 3-HS-l-22C, in the CLOSE/AUTO position.

93 PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 3-XS-l-22 in NORM position.

Standard:

Simulates verifying 3-HS-1-22C is in Close/Auto and simulates placing 3-XS-l-22 in Norm SAT UNSAT N/A COMMENTS:

JPM j PAGE 6 OF 6 Performance Step 4: Critical X Not Critical

[2.4] IF the SRV does NOT close, THEN REMOVE the power from 3-PCV-1-22 by performing one of the following: (Opening breakers are the preferred method)

A. OPEN the following breakers: (Preferred method)

3A 250V RMOV, Compartment 1 1C2

3B 250V RMOV, Compartment 1C1 Standard:

Simulates opening Compartment 1 1C2 at 3A 250V RMOV and Compartment 1C1 at 3B 250V RMOV SAT_ UNSAT N/A COMMENTS:____________________________

C1JF9 -:1:iCat4A25QTRMOV is open and 1Oitt3B 25OVRMOV is bpen.

When Control Room called SRV is Closed If Operatorsunulates elosmg breakers, breakers are closed SRV is Open JPM Failure STOP TIME END OF TASK

JPM j PAGE 1 OF 6 OPERATOR:_______________________

RO___ SRO___ DATE:

JPM NUMBER: j TASK NUMBER: U-001-AL-06 TASK TITLE: Field actions for stuck open SRV K/A NUMBER: 239002 A2.03 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Stuck Open SRV is closed when power is removed from the SRV by opening the breakers LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1 -AOl- 1-1 VALIDATION TiME: 25 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 1-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 1-PCV-l-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 1-PCV-1-22 from outside the Control Room in accordance with 1-AOl-i-i step 4.2.3[2j.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 3 OF 6 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 1-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV i-PCV-1-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV i-PCV-i-22 from outside the Control Room in accordance with i-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j PAGE 4 OF 6 START TiME____

Performance Step 1: Critical X Not Critical NOTES

1) 1-PCV-1-22 is an ADS Valve

2) 1-PCV-1-22 has two power supplies, it will auto transfer on loss of power and is Normal Seeking.

3) Attachment 1 may be addressed for fuse and breaker information.

[2] IF 1-PCV-1-22 is NOT closed, THEN PERFORM the following:

[2.1] On Panel 1-25-32 PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 1-XS-l-22 in EMERG position.

Standard:

Simulate placing 1-XS-1-22 in emergency and calls Control Room to check whether SRV remains Open SAT_ UNSAT N/A COMMENTS:______________________________

.1-22is n Ethergeiiy, Reáctór Press re is Stab1e, (freeii r SRV 1-22k

JPM j PAGE 5 OF 6 Performance Step 2: Critical Not Critical X

[2.2] IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 1-PCV-1-22 on the Acoustic Monitor:

CYCLE the MAIN STM LINE B RELIEF VALVE, l-HS-l-22C to the following positions several times.

CLOSE/AUTO to OPEN to CLOSE/AUTO Standard:

Simulates cycling l-HS-1-22C from CLOSE/AUTO to OPEN to CLOSE/AUTO SAT UNSAT N/A COMMENTS:_________________________

CUE: cLosE/AuTo o OPENto OLOSWTOS*itvlii&behig cycI4d JihfOiand n4h Off Øien s,itc1in Opeaai4Greeii remains stb1, wben ControMRoom caIledS1 fails to 1oor remftis open Performance Step 3:

Critical X Not Critical

[2.3] IF the SRV does NOT close, THEN PERFORM the following:

A. VERIFY the MAIN STM LINE B RELIEF VALVE, 1-HS-1-22C, in the CLOSE/AUTO position.

B PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 1-XS-1-22 in NORM position.

Standard:

Simulates verifying 1-HS-1-22C is in Close/Auto and simulates placing 1-XS-1-22 in Norm SAT UNSAT N/A _COMMENTS:_____________________________

cIJE* .;G llghtUsethe 1 rp

JPM j PAGE 6 OF 6 Performance Step 4: Critical X Not Critical

[2.4] IF the SRV does NOT close, THEN REMOVE the power from 1-PCV-1-22 by performing one of the following: (Opening breakers are the preferred method)

A. OPEN the following breakers: (Preferred method)

1A25OVRMOV, Compartment 11C2

lB 250V RMOV, Compartment 1C1 Standard:

Simulates opening Compartment 1 1C2 at 1A 250V RMOV and Compartment 1C1 at lB 250V RMOV SAT_ UNSAT N/A COMMENTS:_____________________________

CUE: 4iC2atiAZOVRMOVIsopenand1C1zatIB25OVRMQVisopen.

When ControRoi called SRV is Closed If Operator simulates closmr Ifreakers, breers are dosed SRV is Open. JPM Failure STOP TIME____

END OF TASK

JPM k (25+/- op6)

PAGE 1 OF 12 OPERATOR:_________________________

RO___ SRO___ DATE:

JPM NUMBER: k (25i op6)

TASK NUMBER: U-000-SS-30 TASK TITLE: Operator 6 Manual Actions 0-SSI-251 K/A NUMBER: 600000 AA2.16 K/A RATING: RO 3.0 SRO 3.5 TASK STANDARD: Operator 6 Manual Actions 0-SSI-251 section 1.0 completed LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 0-SSI-251 VALIDATION TIME: 30 minutes MAX. TIME ALLOWED: 10 minutes for step 1.1, 20 minutes for step 1.2, 20 minutes for step 2.1 to 2.3, 10 minutes for step 3.1, 20 minutes for step 3.2, 20 minutes for step 4.

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are Operator 6, the plant is operating in O-SSI-251 Turbine Building, Cable Tunnel, Intake Pumping Station and Radwaste Building.

INITIATING CUE: The Unit Supervisor directs you as Operator 6 to commence Attachment 6 Operator 6 Manual Actions of O-SSI-25L Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (25+/- op6)

PAGE 3 OF 12 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are Operator 6, the plant is operating in O-SSI-25I Turbine Building, Cable Tunnel, Intake Pumping Station and Radwaste Building.

INITIATING CUE: The Unit Supervisor directs you as Operator 6 to commence Attachment 6 Operator 6 Manual Actions of 0-S SI-251.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (25+/- op6)

PAGE 4 OF 12 START TIME____

Performance Step 1: *Ciitica1 Not Critical NOTE Performance of this section will cause the Diesel Generators to Start and Tie onto their respective 4KV Shutdown Board. The relay operations with subsequent output breaker closure are an expected result of aligning the board normal feeder breakers to the trip position.

[1] PROCEED TO 4KV Shutdown BD 3EA, AND PERFORM the following:

NOTE If pump fails to start, pushbutton on breaker must be used.

[1.1] PROCEED TO Compt 5, 0-BKR-023-0085 RHRSW PUMP A3, AND PERFORM the following:

(10 Mm)

[1.1.l] PLACE RHRSW PUMP A3 EMER/NORM CONT TRANS SWITCH, 0-43-023-0085 in EMERG.

[1.1.2] PLACE RHRSW PUMP A3 EECW NORTH HDR, 0-HS-023-0085C, in CLOSE.

[1.1.3] VERIFY RHRSW Pump A3 has started by observing breaker ammeter indications.

Standard:

Simulates placing 0-43-023-0085 in Emergency and 0-HS-023-0085C in Close SAT UNSAT N/A COMMENTS:_____________________________

CUFF 043-023-0085 is pmergency and 0-HS023-005C is in Close, Red Light

- Off, GreeirLighOn, Yellow LightRemamed On-if asked no breaker trips indicate& -

JPM k (25+/- op6)

PAGE 5 OF 12 Performance Step 2:

Critical X Not Critical NOTE

Jf pump fails to start, pushbutton on breaker must be used.

[1.1] PROCEED TO Compt 5, O-BKR-023-0085 RHRSW PUMP A3, AND PERFORM the following:

[1.1.3] VERIFY RHRSW Pump A3 has started by observing breaker ammeter indications.

Standard:

Simulates depressing Close pushbutton on Compt 5 RHRSW PUMP A3 SAT UNSAT N/A COMMENTS:____________________________

cuE: si4qd tied Uh eeniJQff,11ow 1ight?Off 3

d 9

flms edjh STOP TIME

JPM k (25+/- op6)

PAGE 6 OF 12 START TIME____

Performance Step 3: Critical X Not Critical (20 Mm)

[1.2] PROCEED TO Compt 7, 3-BKR-211-O3EA/007 NORM FDR BKR 1334 TIE FROM BKR 1326 4KV UNIT BD 3A, AND PERFORM the following:

[1.2.1] PLACE BKR 1334 EMER APP R ISOL SEL SWITCH (43AR),

3-43BU-21 1-O3EA/07, in EMER.

[1.2.2] PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-211-O3EA/07, in EMER.

[1.2.3] PLACE BREAKER CONTROL SWITCH, 3-HS-211-O3EA/07B, in TRIP.

Standard:

Simulates placing 3-43BU-21 1-O3EA/07 and 3-43-2 1 1-O3EA/07 in Emergency, and 3-HS-21 1-O3EA/07B in Trip SAT_ UNSAT N/A COMMENTS:___________________________

I I dU* 3jB3BAO STOP TIME____

JPM k (25+/- op6)

PAGE 7 OF 12 START TIME____

Performance Step 4: Critical X Not Critical

[2] PROCEED TO 4KV Shutdown Board 3EC.

(20 Mm)

[2.1] PROCEED TO Compt 12, 3-BKR-21 1-O3EC/012 NORM FDR BKR 1338 TIE FROM BKR 1332 4KV UNIT BD 3B, AND PERFORM the following:

[2.1.1] PLACE BKR 1338 EMER APP R ISOL SEL SWITCH (43AR),

3-43BU-21 1-O3EC/12, in EMER.

[2.1.2] PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-21 l-O3EC/12, in EMERG.

[2.1.3] PLACE BREAKER CONTROL SWITCH 52, 3-HS-211-O3EC/12B, in TRIP.

Standard:

Simulates placing 3-43BU-21 1-O3EC/12 and 3-43-21 1-O3EC/12 in Emergency and 3-HS-211-O3EC/12B in Trip SAT_ UNSAT N/A COMMENTS:

JPM k (25+/- op6)

PAGE 8 OF 12 Performance Step 5: Critical X Not Critical

[2.2] PROCEED TO Compt 8, 0-BKR-023-0015 RHRSW PUMP Bl, AND PERFORM the following:

[2.2.1] PLACE RHRSW PUMP Bi EMER1NORM CONT TRANS SWITCH, 0-43-023-0015, in EMERG.

[2.2.2] PLACE RHRSW PUMP Bi MOTOR, 0-HS-023-0015C, in TRIP.

Standard:

Simulates placing 0-43-023-0015 in Emergency, and 0-HS-023 -001 5C in Trip SAT_ U1JSAT N/A COMMENTS:_______________________________

CUE meigenqy,. O-flS-O23-O0I5Gis iaTii, freeniht On p43orbo16s IedJ]it O Green gti switeb.

Performance Step 6: Critical X Not Critical

[2.3] PROCEED TO Compt 9, 3-BKR-024-0016 RAW COOLiNG WATER PUMP 3D, AND PERFORM the following:

[2.3.1] PLACE BREAKER CONTROL TRANSFER SWITCH, 3-XS-024-0016, in EMERG.

[2.3.2] PLACE RCW PUMP 3D, 3-HS-024-0016C, in TRIP.

Standard:

Simulates placing 3-XS-024-0016 in Emergency and 3-HS-024-0016C in Trip SAT UNSAT N/A COMMENTS:____________________________

JPM k (25i op )

6 PAGE 9 OF 12 STOP TIME____

START TIME____

Performance Step 7:

Critical X Not Critical

[3] PROCEED TO 4KV Shutdown Board 3EB.

NOTE If Pump fails to start, pushbuttons on breaker must be used.

[3.1] PROCEED TO Compt 10, 0-BKR-023-0091 RHRSW PUMP C3 AND PERFORM the following:

(10 Mm)

[3.1.1] PLACE RHRSW PUMP C3 EMER!NORM CONT TRANS SWITCH, 0-43-023-0091, in EMERG.

[3.1.2] PLACE RHRSW PUMP C3 EECW NORTH HEADER, 0-HS-23-91C, in CLOSE.

[3.1.3] VERIFY RHRSW Pump C3 has started by observing breaker ammeter indications.

Standard:

Simulates placing 0-43-023-0091 in Emergency and 0-HS-23-91C in Close SAT_ U1JSAT N/A COMMENTS:_______________________________

I C EjfO4 cireiit1yrpadmg O STOP TIME____

JPM k (25+/- op6)

PAGE 10 OF 12 START TIME____

Performance Step 8: Critical X Not Critical (20 Mm)

[3.2] PROCEED TO Compt 14, 3-BKR-211-O3EB/014 BKR 1336 NORM FDR FROM 4KV UNIT BD 3A BKR 1326 & 4KV S/D BD 3EA BKR 1334, AND PERFORM the following:

[3.2.1] PLACE BKR 1336 EMER APP R ISOL SEL SWITCH (43AR),

3-43BU-2l 1-O3EB/14, in EMER.

[3.2.2] PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-211-O3EB/14, in EMERG.

[3.2.3] PLACE BREAKER CONTROL SWITCH, 3-HS-21 1-O3EB/14B, in TRIP.

Standard:

Simulates placing 3-43BU-21 1-O3EB/14 and 3-43-21 1-O3EB/14 in Emergency and 3-HS-21 1-O3EB/14B in Trip SAT UNSAT N/A COMMENTS:

STOP TIME____

JPM k (251 op6)

PAGE 11 OF 12 START TIME____

Performance Step 9: Critical X Not Critical

[4] PROCEED TO 4KV Shutdown Board 3ED.

[4.1] PROCEED TO Compt 8, 3-BKR-21 1-O3ED/008 NORM SUPPLY BKR 1342 TIE FROM BKR 1332 4KV UNIT BD 3B VIA PNL 11,4KV S/D BD 3EC, AND PERFORM the following:

(20 Mm)

[4.1.1] PLACE BKR 1342 EMER APP R ISOL SEL SWITCH (43AR),

3-43BU-21 1-O3ED/08, in EMER.

[4.1.2] PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-2 1 1-03ED/08, in EMERG.

[4.13] PLACE BREAKER CONTROL SWITCH, 3-HS-21 1-O3ED/08B, in TRIP.

Standard:

Simulates placing 3-43BU-21 1-O3ED/08 and 3-43-21 1-O3ED/08 in Emergency and 3-HS-21 1-O3ED/08B in Trip SAT_ UNSAT N/A COMMENTS:_____________________________

qwd 4Bi-p$thibs d 3-43QII OLfO8 nergenç

JPM k (25+/- op6)

PAGE 12 OF 12 Performance Step 10: Critical X Not Critical

[4.2] PROCEED TO Compt 6, 0-BKR-023-0023 RHRSW PUMP Dl, AND PERFORM the following:

[4.2.1] PLACE RHRSW PUMP Dl EMER/NORM CONT TRANS SWITCH, 0-43-023-0023, in EMERG.

[4.2.2] PLACE RHRSW PUMP Dl, 0-HS-23-23C, in TRIP.

Standard:

Simulates placing 0-43-023-0023 in Emergency and 0-HS-23-23C in Trip SAT_ UNSAT N/A COMMENTS:_______________________________

STOP TiME____

Performance Step 11: Critical Not Critical X

[5] NOTIFY Unit 3 Unit Supervisor of the completion of this section.

[6] PROCEED TO 4KV Shutdown Board A in preparation of performing Section 2.0.

Standard:

Notifies Unit 3 Unit Supervisor SAT UNSAT N/A COMMENTS:

JPM k (16+/- op3)

PAGE 1 OF 9 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: k (16 op6)

TASK NUMBER: U-000-SS-08 TASK TITLE: Operator 3 Manual Actions 0-SSI-16 K/A NUMBER: 600000 AA2.16 K/A RATING: RO 3.0 SRO 3.5 TASK STANDARD: Operator 3 Manual Actions 0-SSI-16 section 2.0 and 3.0 steps 1 and 2 completed LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 0.-SSI-16 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: 20 minutes for section 2.0 PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are Operator 3, the plant is operating in 0-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 3 Manual Actions Section 1.0 is complete.

INITIATING CUE: The Unit Supervisor directs you as Operator 3 to continue Attachment 3 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (16 op3)

PAGE 3 OF 9 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR maybe carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are Operator 3, the plant is operating in 0-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 3 Manual Actions Section 1.0 is complete.

INITIATiNG CUE: The Unit Supervisor directs you as Operator 3 to continue Attachment 3 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (16 op3)

PAGE 4 OF 9 START TIME____

Performance Step 1: *Critical X Not Critical 2.0 START RIIR PUMP 2C (20 Mm)

[1] Notification has been received from the Unit 2 Unit Supervisor to perform this section.

NOTE If RHR pump fails to start, pushbutton on breaker must be used.

[2] PROCEED TO 4160V Shutdown Board B, Compt 17, 2-BKR-074-0016 RESIDUAL HEAT REMOVAL PUMP 2C, AND PERFORM the following:

[2.l] VERIFY RHR PUMP C BREAKER CONTROL TRANSFER SWITCH 43, 2-43-074-0016, in EMERG.

[2.2] PLACE RHR PUMP 2C, 2-HS-074-0016C, in CLOSE.

[2.3] VERIFY RHR Pump 2C has started by observing breaker AMMETER indications.

Standard:

Simulates placing 2-43-074-00 16 in Emergency and 2-HS-074-0016C in Close SAT UNSAT N/A COMMENTS:______________________________

JPM k (16 op3)

PAGE 5 OF 9 Performance Step 2: *Critjcal Not Critical 2.0 START RHR PUMP 2C (20 Mm)

NOTE

IfRHR pump fails to start, pushbutton on breaker must be used.

[2] PROCEED TO 4160V Shutdown Board B, Compt 17, 2-.BKR-074-0016 RESDUAL HEAT REMOVAL PUMP 2C, AND PERFORM the following:

[2.3] VERIFY RHR Pump 2C has started by observing breaker AMMETER indications.

Standard:

Simulates depressing pushbutton on 2-BKR-074-00l 6 and verifies Amps SAT UNSAT N/A _COMMENTS:_____________________________

CUE: BrakrQ-BKR-074-OOl6pushbutton is depressed, AMPS pcgged high, Red 1j an&G 7

4 /

W STOP TIME____

JPM k (16 op3)

PAGE 6 OF 9 Performance Step 3: Critical Not Critical

[3] NOTIFY Unit 2 Unit Supervisor of completion of this section.

[4] REMAIN at 4160V Shutdown Board B in preparation of performing Section 3.0.

Standard:

Notifies Unit 2 Unit Supervisor and proceeds to 4160 SD BD B SAT_ UNSAT N/A COMMENTS:_______________________________

[ CUE: peiform seotio3,9

JPM k (16 op3)

PAGE 7 OF 9 START TIME____

Performance Step 4: *Critical Not Critical 3.0 EECW ALIGNMENT AND START OF UNIT 1 & 2 CONTROL BAY VENTILATION SYSTEM

[1] Notification has been received from the Unit 2 Unit Supervisor to perform this section.

(120 Mm)

[1.1] PROCEED TO 4160V Shutdown Board B Compt 12C, 0-BKR-067-0049 RHRSW PUMP Cl SPLY TO EECW FCV--67-49, AND PERFORM the following:

[1.1.1j PLACE RHRSW PUMP Cl CROSSTIE VLV TRANSFER, 0-XS-067-0049 in EMERG.

[1.1.2] VERIFY CLOSED RHRSW Cl CROSSTIE TO EECW, 0-HS-067-0049C.

Standard:

Simulates placing 0-XS-067-0049 in Emergency and Verifies Closed RHRSW Cl CROSSTIE TO EECW SAT_ UNSAT N/A COMMENTS:_________________________

&E OS-O679O49 is Enprgency nd1ERSVtCf çrosstieo QedLiht

. Off; Gre C1osed 4 F

STOP TIME____

JPM k (16 op3)

PAGE 8 OF 9 START TIME____

Performance Step 5: Critical X Not Critical (240 Mm)

[2] PROCEED TO 41 60V Shutdown Board B Compt 18, 0-BKR-03 1-21004KV SUPPLY FOR 1&2 CONTROL BAY CHILLER A, AND PERFORM the following:

[2.1] PLACE CB CHILLER A TRANSFER SWITCH, 0-XS-031-2100A, in EMERG.

[2.2] PLACE CONTROL BAY CHILLER A, 0-HS-031-2100B, in CLOSE.

Standard:

Simulates placing 0-XS-03 1-21 OOA in Emergency and 0-HS-.03 1-21 OOB in Close SAT UNSAT N/A COMMENTS:_____________________________

CUE:. 0-O31-2iQOnergencyari&0-HS-O3I-210OBis inC1Qse, Breaker Closed, Red Light On Green Light Off, Amps indicate 25 Amps STOP TIME____

JPM k (16 op3)

PAGE 9 OF 9 Performance Step 6: Critical Not Critical X

[3] PROCEED TO the Control Bay Chiller enclosure above the Unit 1 & 2 DG Building.

Standard:

Operator starts to Control Bay Chiller Enclosure SAT UNSAT N/A COMMENTS:______

CUE Another qpertoris dispa&thed to theCqdroU3ay dhiI1erEa1bsure END O)T4

JPM k (16+/- op6)

PAGE 1 OF 9 OPERATOR:_______________________

RO___ SRO___ DATE:

JPM NUMBER: k (16 op6)

TASK NUMBER: U-000-SS-08 TASK TITLE: Operator 6 Manual Actions 0-SSI-16 K/A NUMBER: 600000 AA2.16 K/A RATING: RO 3.0 SRO: 15 TASK STANDARD: Operator 6 Manual Actions 0-SSI-16 section 2.0 and 3.0 completed LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 0-SSI-1 6 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: 20 minutes for section 2.0 and 120 minutes for section 3.0.

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER

INITIAL CONDITIONS: You are Operator 6, the plant is operating in O-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

1NITL4TING CUE: The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (16 op6)

PAGE 3 OF 9 iN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are Operator 6, the plant is operating in 0-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

INITIATING CUE: The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k (16 ops)

PAGE 4 OF 9 START TIME____

Performance Step 1: Critical Not Critical 2.0 480V REACTOR MOV BOAR]) 3B ALIGNMENT (20 Mm)

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

[2] PERFORM the following to align 480V Reactor MOV Board 3B:

[2.1] PROCEED TO Compt 2A, AND PLACE NORMAL FEEDER CONTROL SWITCH, 3 -HS-268B/2A-A, in TRIP.

[2.2] PROCEED TO Compt 16A, AND PLACE EMERGENCY FEEDER CONTROL SWITCH, 3-HS-268-B/16A-A, in CLOSE.

Standard:

Simulates placing 3-HS-268B/2A-A in Trip and 3-HS-268-B/l 6A-A in Close SAT UNSAT_ N/A COMMENTS:_______________________

Ic c

JPM k (16 op6)

PAGE 5 OF 9 Performance Step 2:

Critical X Not Critical

[2.3] PROCEED TO Compt 1C, AND PERFORM the following:

[231] PLACE RCIC STM LINE EMER TRANS SWITCH 3-XS-071-0002, in EMERG.

[2.3.2] VERIFY OPEN RCIC STM LINE TNBD ISOL VALVE, 3-HS-071 -0002B.

Standard:

Simulates placing 3-XS-071-0002 in Emergency and verifies RCIC STM LINE LNBD ISOL VALVE Open SAT UNSAT N/A COMMENTS:

Performance Step 3: Critical X Not Critical

[2.4] PROCEED TO Compt 4C, AND PLACE O-BKR-084-0016A CONTAINMENT ATMOSPHERE DILUTION SYSTEM B HEATER, breaker in OFF.

Standard:

Simulates placing O-BKR-084-OO1 6A in Off SAT UNSAT N/A COMMENTS:

STOP TIME____

JPM k (16 op6)

PAGE 6 OF 9 Performance Step 4: Critical Not Critical

[3] NOTIFY Unit 3 Unit Supervisor of completion of this section.

[4] PROCEED TO 4160V Shutdown Board 3EA in preparation of performing Section 3.0.

Standard:

Notifies Unit 3 Unit Supervisor and proceeds to 4160 SD BD 3EA SAT UNSAT N/A COMMENTS:_______________________________

JPM k (16 op6)

PAGE 7 OF 9 START TIME____

Performance Step 5:

Critical X Not Critical 3.0 RHR PUMP 3A LOCAL START (120 Mm)

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

NOTE If RHR pump fails to start, pushbutton on breaker must be used.

[2] PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.1] PLACE RHR PUMP 3A TRANSFER, 3-43-074-0005, in EMERG.

[2.2] PLACE RHR PUMP 3A, 3-HS-074-0005C, in CLOSE.

[2.3] VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

Standard:

Simulates placing 3-43-074-0005 in Emergency and 3-HS-074-0005C in Close SAT_ UNSAT N/A _COMMENTS:_____________________________

CUE 3-43O74-OOO5 is in Emergency and 3-HS-074-0005C is utCiose, No AMPS are indicated, Red light OFF Green Light On Yellow light remained On, If

- asked No breaker trips are indicated

JPM k (16 op6)

PAGE 8 OF 9 Performance Step 6:

Critical X Not Critical 3.0 RHR PUMP 3A LOCAL START (120 Mm)

NOTE

IfRHR pump fails to start, pushbutton on breaker must be used.

[2] PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.3] VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

Standard:

Simulates depressing pushbutton on 3-BKR-074-0005 and verifies Amps SAT UNSAT N/A COMMENTS:_____________________

CUE: :Brçakr 3-BKR-014-0005 j slabutton is dpiesed, AMPS pegedbigh, Red ht Oj eenJi E 7

yreakc s 8O STOP TIME____

JPM k (16 op6)

PAGE 9 OF 9 Performance Step 7: Critical Not Critical X

[3] NOTIFY Unit 3 Unit Supervisor of the completion of this section.

[4] PROCEED TO 4160 Shutdown Board A in preparation of performing Section 4.0.

Standard:

Notifies Unit 3 Unit Supervisor SAT UNSAT N/A COMMENTS:______________________________

CUE Another qppra&or will cpnfihue with section 4Q 1 1LND Orr4sç

ML110980772

Text

Navigation menu

Search