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302 Draft Simulator & In-plant JPMs
	ML14049A015
Person / Time
Site:	Browns Ferry
Issue date:	02/18/2014
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	U-085-AB-03
	Download: ML14049A015 (181)
	v • d • e

JPM a OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: a- ALTERNATE PATH 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900 psig Reactor Pressure K/A NUMBER: 201001 A2.01 K/A RATING: RO 3.2 SRO 3.3 TASK STANDARD: Withdraws Control Rod, if withdrawn to position 48; performs a coupling check, ranges IRMs to prevent a full scram signal, and inserts a manual scram; when unable to restore CRD drive water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: 2-OI-85 and 2-AOI-85-3 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

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 30-35. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

JPM a 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 "That's Correct". (OR "That's 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 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 30-35. 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.

3

JPM a 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 30-35 by depressing 30-35 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:

4

JPM a 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, 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 30-35.

SAT UNSAT N/A COMMENTS:

5

JPM a 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:

6

JPM a 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, 2-SR-3.1.3.5A.

3) When continuously withdrawing a control rod to a position other than position 48 the CRD Notch Override Switch is held in the Override position and then 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:

7

JPM a 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:

8

JPM a 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:

9

JPM a 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 30-35, trip operating CRD Pump.

CUE: If required, have operator take the actions of 2-AOI-85-3 CRD System Failure.

10

JPM a 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 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:

11

JPM a 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, 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 30-35 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 30-35, trip operating CRD Pump.

CUE: If required, have operator take the actions of 2-AOI-85-3 CRD System Failure.

12

JPM a 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:

13

JPM a Performance Step 16: Critical X Not Critical Operator Ranges IRMs as necessary; to maintain greater than the downscale reading of 7.5/125 and less than the upscale reading of 90/125.

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 will be a failure.

SAT UNSAT N/A COMMENTS:

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

CUE: If required, have operator take the actions of 2-AOI-85-3 CRD System Failure.

14

JPM a Performance Step 17: Critical Not Critical X 4.1 Immediate Actions

[1] IF operating CRD PUMP has failed AND 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 CRD Pump and may also attempt to start tripped CRD Pump.

SAT UNSAT N/A COMMENTS:

15

JPM a 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 report another operator will continue in 2-AOI-100-1.

END OF TASK STOP TIME 16

JPM a OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: a- ALTERNATE PATH 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-OI-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 1

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 30-35. Rod Out Notch Override is authorized, complete the withdrawal of group 12 and then continue with group 13.

JPM a 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 "That's Correct". (OR "That's 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 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 30-35. 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.

3

JPM a 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 30-35 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:

4

JPM a 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 of Evaluator, after or during withdraw of control rod 30-35, trip operating CRD Pump.

CUE: If required, have operator take the actions of 3-AOI-85-3 CRD System Failure.

5

JPM a 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:

6

JPM a 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:

7

JPM a 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:

8

JPM a 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:

9

JPM a 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 control rod 30-35, trip operating CRD Pump.

CUE: If required, have operator take the actions of 3-AOI-85-3 CRD System Failure.

10

JPM a 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:

11

JPM a 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 direction of Evaluator, after or during withdraw of control rod 30-35, trip operating CRD Pump.

CUE: If required, have operator take the actions of 3-AOI-85-3 CRD System Failure.

12

JPM a 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 UNSAT 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:

13

JPM a Performance Step 16: Critical X Not Critical Operator Ranges IRMs as necessary; to maintain greater than the downscale reading of 7.5/125 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 will be a failure.

SAT UNSAT N/A COMMENTS:

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

CUE: If required , have operator take the actions of 3-AOI-85-3 CRD System Failure.

14

JPM a Performance Step 17: Critical Not Critical X 4.1 Immediate 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 X

[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 CRD Pump and may also attempt to start tripped CRD Pump.

SAT UNSAT N/A COMMENTS:

15

JPM a 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: After Scram report another operator will continue in 3-AOI-100-1.

END OF TASK STOP TIME 16

JPM b OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: b- ALTERNATE PATH TASK NUMBER: U-003-AL-01 TASK TITLE: Remove RFPT A from Service K/A NUMBER: 259001 A4.04 K/A RATING: RO 3.1 SRO 2.9 PRA:

TASK STANDARD: Removes RFPT A from service, trips RFPT A and closes discharge valve LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-OI-3 VALIDATION TIME: 20 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS: You are the Unit Operator. An oil leak has been identified on RFPT 2A.

RFPT 2A needs to removed from service.

INITIATING CUES: The Unit Supervisor directs you to remove RFPT 2A from service in accordance with 2-OI-3, Reactor Feedwater System section 7.1. Precautions and Limitations have been reviewed.

JPM b 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 "That's Correct". (OR "That's 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 Unit Operator. An oil leak has been identified on RFPT 2A.

RFPT 2A needs to removed from service.

INITIATING CUES: The Unit Supervisor directs you to remove RFPT 2A from service in accordance with 2-OI-3, Reactor Feedwater System section 7.1. Precautions and Limitations have been reviewed.

3

JPM b START TIME Performance Step 1: Critical Not Critical X 7.1 RFP/RFPT Shutdown CAUTIONS

1) FAILURE to monitor SJAE/OG CNDR CNDS FLOW, 2-FI-2-42, on Panel 2-9-6 for proper flow (between 2 x 106 and 3 x 106 lbm/hr) may result in SJAE isolation.

2) Changes in Condensate System flow may require adjustment to SPE CNDS BYPASS, 2-FCV-002-0190.

3) When isolating the Reactor Feedwater Pump(s) for maintenance, the associated injection water should also be isolated to prevent high seal differential pressure and allow the RFW Pump shafts to rotate freely. (BFNPER123395)

4) When a Reactor Feed Pump is isolated (suction, discharge, and minimum flow valve closed) with injection water aligned to the pump, there is a potential of rising pump casing pressure and seal water leakoff flows reaching the point where seal water drains are overcome and seal water is forced into the oil system through the bearing housings. Therefore, the time that a RFP is isolated with injection water aligned to the pump should be minimized.

[1] REFER TO Section 3.0 and REVIEW Precautions and Limitations.

[2] Verify Reactor Power is 95%. (Ref. P&L 3.0 VV)

[3] IF any Condensate or Condensate Booster Pump is NOT in service, THEN (Otherwise N/A).

[4] IF RFP being removed from service is last operating RFP, THEN (Otherwise N/A)

Standard:

Given in initial conditions that step 1 is complete Operator verifies Reactor Power is <95%

Given in initial conditions that step 3 and 4 are N/A.

SAT UNSAT N/A COMMENTS:

4

JPM b Performance Step 2: Critical Not Critical X

[5] VERIFY in AUTO, RFPT 2A TURNING GEAR MOTOR, 2-HS-3-101A.

Standard:

Verifies 2-HS-3-101A in AUTO SAT UNSAT N/A COMMENTS:

5

JPM b Performance Step 3: Critical Not Critical X NOTES

1) When selected, Column 1 on individual RFPT Speed Control Panel Display Stations (PDS) displays actual pump speed and is not controlled in any mode.

2) When selected, Column 2 on individual RFPT Speed Control PDS displays pump flow bias and is changed with the Ramp Up/Ramp Down pushbuttons with the controller in AUTO.

3) When selected, Column 3 on individual RFPT Speed Control PDS displays RFPT speed demand and is changed with the Ramp Up/Ramp Down pushbuttons with the controller in MANUAL.

4) Illustration 2 can be referred to for additional information on the RFPT Speed Control PDSs.

[6] LOWER speed of RFPT/RFP being removed from service by either of the following methods:

IF Using individual RFPT Manual Governor switch, THEN GO TO Step 7.1[7].

IF Using individual RFPT Speed Control PDS in MANUAL, THEN GO TO Step 7.1[8].

Standard:

Operator proceeds to step 7 or step 8. NOTE most operators will go to step 7 (performance step 4).

SAT UNSAT N/A COMMENTS:

6

JPM b Performance Step 4: Critical X Not Critical

[7] SLOWLY LOWER speed of RFPT, using individual RFPT 2A SPEED CONT RAISE/LOWER switch, 2-HS-46-8A on Panel 2-9-5, by performing the following:

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

CHECK amber light at switch illuminated.

Standard:

Depresses 2-HS-46-8A to Manual SAT UNSAT N/A COMMENTS:

Performance Step 5: *Critical X Not Critical

[7.2] SLOWLY LOWER RFPT speed, by placing RFPT Speed Control switch in RAISE and LOWER positions, as necessary.

[7.3] IF this is the NOT the last operating feed pump, THEN OBSERVE rise in speed of any remaining RFPT operating in AUTO.

Standard:

Lowers speed of RFPT 2A and verifies RFPT 2B and 2C respond SAT UNSAT N/A COMMENTS:

7

JPM b Performance Step 6: Critical X Not Critical

[8] SLOWLY LOWER speed of RFPT, using individual RFPT 2A SPEED CONTROL PDS, 2-SIC-46-8 by performing the following (Panel 2-9-5):

[8.1] PLACE PDS in MANUAL AND VERIFY Column 3 is selected.

Standard:

Places 2-SIC-46-8 in Manual SAT UNSAT N/A COMMENTS:

Performance Step 7: *Critical X Not Critical

[8.2] SLOWLY LOWER RFPT speed, using Ramp Up/Ramp Down pushbuttons as necessary.

[8.3] IF this is the NOT the last operating feed pump, THEN OBSERVE rise in speed of any remaining RFPT operating in AUTO.

Standard:

Lowers speed of RFPT 2A and verifies RFPT 2B and 2C respond SAT UNSAT N/A COMMENTS:

ALTERNATE PATH STARTS ON THE NEXT STEP 8

JPM b Performance Step 8: Critical X Not Critical CAUTION RFP Discharge Check Valve may fail to close when removing a RFP from service.

[9] IF at any time RFP Discharge Check Valve failure is experienced while removing RFP from service, THEN REFER TO Step 7.1[15].

Standard:

When Operator lowers speed far enough they will notice the failure of RFP Discharge Check Valve due to check valve failing to close and Reactor Water level lowering. Operator will transition to step 7.1[15].

SAT UNSAT N/A COMMENTS:

Performance Step 9: Critical Not Critical X

[10] CONTINUE to slowly lower RFPT speed to minimum speed setting (approximately 600 rpm).

Standard:

Operator will continue to lower speed, once speed has lowered far enough that RFPT 2A discharge pressure is below the discharge pressure of RFPT 2B and 2C, the operator will respond to a failure of RFPT 2A Discharge Check Valve Failure SAT UNSAT N/A COMMENTS:

9

JPM b Performance Step 10: Critical Not Critical X

[15] IF RFP Discharge Check Valve failure is experienced, THEN

[15.1] DEPRESS RFP 2A(2B)(2C) DISCHARGE TESTABLE CK VLV pushbutton, 2-HS-3-94A.

VERIFY Discharge Check Valve closed.

Standard:

Operator depresses 2-HS-3-94A, Check Valve fails to close SAT UNSAT N/A COMMENTS:

Performance Step 11: Critical Not Critical X

[15.2] IF RFP Discharge Check Valve failure is still being experienced, THEN PERFORM either of the following:

[15.2.1] IMMEDIATELY RETURN RFP to service.

Standard:

Operator may raise speed of RFPT 2A and attempt to return to service.

SAT UNSAT N/A COMMENTS:

CUE: Remove RFPT 2A from service.

10

JPM b NOTE: Operator may lower pump speed to 600 RPM prior to tripping pump.

Performance Step 12: *Critical X Not Critical

[15.2.2] PERFORM the following:

A. VERIFY OPEN RFP 2A MIN FLOW VALVE, 2-FCV-3-20

B. CLOSE RFP 2A DISCHARGE VALVE using 2-HS-3-19A

C. VERIFY RFP tripped.

Standard:

Verifies RFP 2A min flow valve Open, Closes RFP 2A Discharge Valve 2-HS-3-19A AND Trips RFPT 2A.

SAT UNSAT N/A COMMENTS:

CUE: This completes the task.

END OF TASK STOP TIME 11

JPM b OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: b- ALTERNATE PATH TASK NUMBER: U-003-AL-01 TASK TITLE: Place RFPT A in Service K/A NUMBER: 259001 A4.04 K/A RATING: RO 3.1 SRO 2.9 PRA:

TASK STANDARD: Removes RFPT A from service, trips RFPT A and closes discharge valve LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-OI-3 VALIDATION TIME: 20 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 1

INITIAL CONDITIONS: You are the Unit Operator. An oil leak has been identified on RFPT 3A.

RFPT 3A needs to removed from service.

INITIATING CUES: The Unit Supervisor directs you to remove RFPT 3A from service in accordance with 3-OI-3, Reactor Feedwater System section 7.1. Precautions and Limitations have been reviewed.

JPM b 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 "That's Correct". (OR "That's 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 Unit Operator. An oil leak has been identified on RFPT 3A.

RFPT 3A needs to removed from service.

INITIATING CUES: The Unit Supervisor directs you to remove RFPT 3A from service in accordance with 3-OI-3, Reactor Feedwater System section 7.1. Precautions and Limitations have been reviewed.

3

JPM b START TIME Performance Step 1: Critical Not Critical X 7.1 RFP/RFPT Shutdown CAUTIONS

1) FAILURE to monitor SJAE/OG CNDR CNDS FLOW, 3-FI-2-42, on Panel 3-9-6 for proper flow (between 2 x 106 and 3 x 106 lbm/hr) may result in SJAE isolation.

2) Changes in Condensate System flow may require adjustment to SPE CNDS BYPASS, 3-FCV-002-0190.

3) When isolating the Reactor Feedwater Pump(s) for maintenance, the associated injection water should also be isolated to prevent high seal differential pressure and allow the RFW Pump shafts to rotate freely. (BFNPER123395)

[1] REFER TO Section 3.0 and REVIEW Precautions and Limitations.

[2] VERIFY Reactor power is less than 80% prior to removing RFP from service.

NOTE It may be necessary to switch to SINGLE ELEMENT mode from THREE ELEMENT mode earlier than recommended if Feedwater control becomes unstable.

[3] IF RFP being removed from service is last operating RFP OR IF at any time Feedwater control becomes unstable, THEN (Otherwise N/A).

Standard:

Given in initial conditions that step 1 is complete and step 2 is NA.

Operator verifies Reactor Power is <80%

Given in initial conditions that step 3 is NA SAT UNSAT N/A COMMENTS:

4

JPM b Performance Step 2: Critical Not Critical X

[4] VERIFY in AUTO, RFPT 3A TURNING GEAR MOTOR, 3-HS-3-101A.

Standard:

Verifies 3-HS-3-101A in AUTO SAT UNSAT N/A COMMENTS:

5

JPM b Performance Step 3: Critical Not Critical X NOTES

1) When selected, Column 1 on individual RFPT Speed Control Panel Display Stations (PDS) displays actual pump speed and is not controlled in any mode.

2) When selected, Column 2 on individual RFPT Speed Control PDS displays pump flow bias and is changed with the Ramp Up/Ramp Down pushbuttons with the controller in AUTO.

3) When selected, Column 3 on individual RFPT Speed Control PDS displays RFPT speed demand and is changed with the Ramp Up/Ramp Down pushbuttons with the controller in MANUAL.

4) Illustration 2 can be referred to for additional information on the RFPT Speed Control PDSs.

[5] LOWER speed of RFPT/RFP being removed from service by either of the following:

IF Using individual RFPT Manual Governor switch, THEN GO TO Step 7.1[6].

IF Using individual RFPT Speed Control PDS in MANUAL, THEN GO TO Step 7.1[7].

Standard:

Operator proceeds to step 6 or step 7. NOTE most operators will go to step 6 (performance step 4).

SAT UNSAT N/A COMMENTS:

6

JPM b Performance Step 4: Critical X Not Critical

[6] LOWER speed of RFPT, using individual RFPT 3A SPEED CONT RAISE/LOWER switch, 3-HS-46-8A as follows (Panel 3-9-5):

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

VERIFY illuminated amber light at switch.

Standard:

Depresses 3-HS-46-8A to Manual SAT UNSAT N/A COMMENTS:

Performance Step 5: *Critical X Not Critical

[6.2] SLOWLY LOWER RFPT speed, by placing RFPT Speed Control switch in RAISE or LOWER positions, as necessary.

[6.3] IF this is the NOT the last operating feed pump, THEN OBSERVE rise in speed of any remaining RFPT operating in AUTO as RFW Control System maintains Reactor water level.

Standard:

Lowers speed of RFPT 3A and verifies RFPT 3B and 3C respond.

SAT UNSAT N/A COMMENTS:

7

JPM b Performance Step 6: Critical X Not Critical

[7] SLOWLY LOWER speed of RFPT, using individual RFPT 3A SPEED CONTROL PDS, 3-SIC-46-8 as follows (Panel 3-9-5):

[7.1] PLACE PDS in MANUAL AND VERIFY Column 3 is selected.

Standard:

Places 3-SIC-46-8 in Manual.

SAT UNSAT N/A COMMENTS:

Performance Step 7: *Critical X Not Critical

[7.2] SLOWLY LOWER RFPT speed, using Ramp Up/Ramp Down pushbuttons as necessary.

[7.3] IF this is the NOT the last operating feed pump, THEN OBSERVE rise in speed of any remaining RFPT operating in AUTO as RFW Control System maintains Reactor water level..

Standard:

Lowers speed of RFPT 3A and verifies RFPT 3B and 3C respond.

SAT UNSAT N/A COMMENTS:

8

JPM b ALTERNATE PATH STARTS ON THE NEXT STEP Performance Step 8: *Critical X Not Critical CAUTION RFP Discharge Check Valve failure may be experienced while removing RFP from service.

[8] IF at any time RFP Discharge Check Valve failure is experienced while removing RFP from service, THEN PERFORM the following: (Otherwise N/A)

[8.1] DEPRESS RFP Discharge Testable Check valve push-button for approximately ten seconds (Panel 3-9-6).

Standard:

When Operator lowers speed far enough they will notice the failure of RFP Discharge Check Valve due to check valve failing to close and Reactor Water level lowering. Operator will complete step 7.1[8].

Operator depresses 3-HS-3-94A, Check Valve fails to close.

SAT UNSAT N/A COMMENTS:

9

JPM b Performance Step 9: Critical Not Critical X

[8.2] CHECK reverse flow through check valve has stopped.

[8.3] IF RFP Discharge Testable Check Valve failure is still being experienced, THEN PERFORM one of the following:

[8.3.1] IMMEDIATELY RETURN RFP to service.

Standard:

Operator may raise speed of RFPT 3A and attempt to return to service.

SAT UNSAT N/A COMMENTS:

CUE: Remove RFPT 3A from service.

10

JPM b NOTE: Operator may lower pump speed to 600 RPM prior to tripping pump.

Performance Step 10: *Critical X Not Critical

[8.3.2] PERFORM the following:

A. VERIFY open RFP Minimum Flow Valve.

B. CLOSE RFP Discharge Valve.

C. TRIP RFPT.

Standard:

Verifies RFP 3A min flow valve Open, Closes RFP 3A Discharge Valve 3-HS-3-19A AND Trips RFPT 3A.

SAT UNSAT N/A COMMENTS:

CUE: This completes the task.

END OF TASK STOP TIME ________

11

JPM c OPERATOR: ________________________________

RO SRO DATE: _______

JPM NUMBER: c- ALTERNATE PATH TASK NUMBER: U-001-AB-01 TASK TITLE: RESPOND TO STUCK OPEN SRV K/A NUMBER: 239002A2.03 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Perform control room operations necessary to respond to a stuck open SRV as directed by 2-AOI-1-1 LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-AOI-1-1 VALIDATION TIME: 6 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

JPM c INITIAL CONDITIONS: You are an Operator. Unit 2 is at 100% power. Annunciator MAIN STEAM RELIEF VALVE OPEN, 2-XA-55-3C, Window 25 is in alarm.

INITIATING CUE: The Unit Supervisor directs you to respond to the alarm as directed by 2-AOI-1-1.

2

JPM c 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 "That's Correct". (OR "That's 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 is at 100% power. Annunciator MAIN STEAM RELIEF VALVE OPEN, 2-XA-55-3C, Window 25 is in alarm.

INITIATING CUE: The Unit Supervisor directs you to respond to the alarm as directed by 2-AOI-1-1.

3

JPM c START TIME Simulator Driver: This JPM requires SRV 1-31 stuck open (imf ad01e 100).

Performance Step 1: Critical Not Critical X NOTE Once a MSRV is operated, a time delay of 15 to 30 seconds can be expected before a response can be detected on 2-TR-1-1, MSRV DISCHARGE TAILPIPE TEMPERATURE.

ICS can be used to monitor the discharge tailpipe temperature, but the appropriate indications on 2-TR-1-1 must be confirmed.

4.1 Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 2-FMT-1-4, on Panel 2-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE recorder, 2-TR-1-1 on Panel 2-9-47.

Standard:

Identified MSRV 1-31 OPEN as indicated on 2-FMT-1-4 SRV Tailpipe Flow Monitor on Panel 2-9-3 or elevated tailpipe temperature as indicated on 2-TR-1-1, Panel 2-9-47.

SAT UNSAT N/A COMMENTS:

4

JPM c Performance Step 2: Critical X Not Critical

[2] IF relief valve transient occurred while operating above 90%

power, THEN REDUCE reactor power to 90% RTP with recirc flow.

(Otherwise N/A)

Standard:

Operator Reduces reactor power to 90% RTP with recirc flow.

SAT UNSAT N/A COMMENTS:

Performance Step 3: Critical X Not Critical

[3] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch as required up to three times:

CLOSE to OPEN to CLOSE positions Standard:

Placed 2-HS-1-31 in the CLOSE-OPEN-CLOSE position up to three times. Determines valve DID NOT close as indicated by MSRV TAILPIPE FLOW MONITOR or NO indicated increase in generator Mwe.

SAT UNSAT N/A COMMENTS:

5

JPM c Performance Step 4: Critical Not Critical X

[4] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Verified that the SRV did not close and continues in the procedure at step 4.2.1 SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical Not Critical X NOTES

1) Once initial transient of SRV opening has stabilized (pressure regulator compensation) the Heat balance will indicate bad data.

2) The SRV TAILPIPE FLOW MONITOR may seal-in an OPEN position indication.

4.2 Subsequent Action 4.2.1 Action if a fire exists with SRV stuck open

[1] IF an SRV is open and a fire exists in ANY Appendix R fire area, THEN (Otherwise N/A):

INITIATE a manual scram before the Suppression Pool temperature exceeds 95°F.

Standard:

No fire is indicated. This step is not applicable.

SAT UNSAT N/A COMMENTS:

6

JPM c Performance Step 6: Critical X Not Critical 4.2 Subsequent Action 4.2.2 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position.

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position.

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the off position (Critical) and verifies the power is off (Not Critical). Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON Position (Critical) and verifies SRV 1-31 did not close (Not Critical) and continues at step [4].

SAT UNSAT N/A COMMENTS:

7

JPM c Driver: When the MSRV AUTO ACTUATION LOGIC SWITCH is in INHIBIT, dmf ad01e Performance Step 7: Critical X Not Critical

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 2-XS-1-202 in INHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 2 SRV Solenoid Power Breaker/Fuse Table).

Standard:

Placed MSRV AUTO ACTUATION LOGIC INHIBIT, 2-XS-1-202 in INHIBIT.

Verifies SRV 1-31 closes. Directs AUO/US to open the breaker 8B2 on 250V RMOV Board 2B, or pull fuses FU2-1-31 (Fuse holder 1FU) and FU2-1-31 (Fuse Holder 2FU).

SAT UNSAT N/A COMMENTS:

Performance Step 8: Critical Not Critical X

[6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 2-XS-1-202, in AUTO.

Standard:

Places MSRV AUTO ACTUATION LOGIC INHIBIT 2-XS-1-202, in AUTO. If switched is placed in Auto prior to power being removed this would be a failure.

SAT UNSAT N/A COMMENTS:

Driver: If 2-XS-1-202 is placed in auto imf ad01e to open SRV CUE: That completes this task.

END OF TASK STOP TIME:

8

JPM c OPERATOR: ________________________________

RO SRO DATE: _______

JPM NUMBER: c- ALTERNATE PATH TASK NUMBER: U-001-AB-01 TASK TITLE: RESPOND TO STUCK OPEN SRV K/A NUMBER: 239002A2.03 K/A RATING: RO 4.1 SRO 4.2 TASK STANDARD: Perform control room operations necessary to respond to a stuck open SRV as directed by 3-AOI-1-1 LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-AOI-1-1 VALIDATION TIME: 6 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

JPM c INITIAL CONDITIONS: You are an Operator. Unit 3 is at 100% power. Annunciator MAIN STEAM RELIEF VALVE OPEN, 3-XA-55-3C, Window 25 is in alarm.

INITIATING CUE: The Unit Supervisor directs you to respond to the alarm as directed by 3-AOI-1-1.

2

JPM c 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 "That's Correct". (OR "That's 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 is at 100% power. Annunciator MAIN STEAM RELIEF VALVE OPEN, 3-XA-55-3C, Window 25 is in alarm.

INITIATING CUE: The Unit Supervisor directs you to respond to the alarm as directed by 3-AOI-1-1.

3

JPM c START TIME Simulator Driver: This JPM requires SRV 1-31 stuck open (imf ad01e 100).

Performance Step 1: Critical Not Critical X NOTE Once a MSRV is operated, a time delay of 15 to 30 seconds can be expected before a response can be detected on 3-TR-1-1, MSRV DISCHARGE TAILPIPE TEMPERATURE.

ICS can be used to monitor the discharge tailpipe temperature, but the appropriate indications on 3-TR-1-1 must be confirmed.

4.1 Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT-1-4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE recorder, 3-TR-1-1 on Panel 3-9-47.

Standard:

Identified MSRV 1-31 OPEN as indicated on 3-FMT-1-4 SRV Tailpipe Flow Monitor on Panel 3-9-3 or elevated tailpipe temperature as indicated on 3-TR-1-1, Panel 3-9-47.

SAT UNSAT N/A COMMENTS:

4

JPM c Performance Step 2: Critical X Not Critical

[2] IF relief valve transient occurred while operating above 90%

power, THEN REDUCE reactor power to 90% RTP with recirc flow.

(Otherwise N/A)

Standard:

Operator Reduces reactor power to 90% RTP with recirc flow.

SAT UNSAT N/A COMMENTS:

Performance Step 3: Critical X Not Critical

[3] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch as required up to three times:

CLOSE to OPEN to CLOSE positions Standard:

Placed 3-HS-1-31 in the CLOSE-OPEN-CLOSE position up to three times. Determines valve DID NOT close as indicated by MSRV TAILPIPE FLOW MONITOR or NO indicated increase in generator Mwe.

SAT UNSAT N/A COMMENTS:

5

JPM c Performance Step 4: Critical Not Critical X

[4] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Verified that the SRV did not close and continues in the procedure at step 4.2.1 SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical Not Critical X NOTES

1) Once initial transient of SRV opening has stabilized (pressure regulator compensation) the Heat balance will indicate bad data.

2) The SRV TAILPIPE FLOW MONITOR may seal-in an OPEN position indication.

4.2 Subsequent Action 4.2.1 Action if a fire exists with SRV stuck open

[1] IF an SRV is open and a fire exists in ANY Appendix R fire area, THEN (Otherwise N/A):

INITIATE a manual scram before the Suppression Pool temperature exceeds 95°F.

Standard:

No fire is indicated. This step is not applicable.

SAT UNSAT N/A COMMENTS:

6

JPM c Performance Step 6: Critical X Not Critical 4.2 Subsequent Action 4.2.2 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position.

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position.

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the off position (Critical) and verifies the power is off (Not Critical). Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON Position (Critical) and verifies SRV 1-31 did not close (Not Critical) and continues at step [4].

SAT UNSAT N/A COMMENTS:

7

JPM c Driver: When the MSRV AUTO ACTUATION LOGIC SWITCH is in INHIBIT, dmf ad01e Performance Step 7: Critical X Not Critical

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 3-XS-1-202 in INHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 3 SRV Solenoid Power Breaker/Fuse Table).

Standard:

Placed MSRV AUTO ACTUATION LOGIC INHIBIT, 3-XS-1-202 in INHIBIT.

Verifies SRV 1-31 closes. Directs AUO/US to open the breaker 8C1 on 250V RMOV Board 3B, or pull fuses 3-FU1-001-0031A and 3-FU1-001-0031B.

SAT UNSAT N/A COMMENTS:

8

JPM c Performance Step 8: Critical Not Critical X

[6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 3-XS-1-202, in AUTO.

Standard:

Places MSRV AUTO ACTUATION LOGIC INHIBIT 3-XS-1-202, in AUTO. If switched is placed in Auto prior to power being removed this would be a failure.

SAT UNSAT N/A COMMENTS:

Driver: If 3-XS-1-202 is placed in auto imf ad01e to open SRV CUE: That completes this task.

END OF TASK STOP TIME:

9

JPM d OPERATOR: ________________________________

RO ____ SRO DATE: ___________

JPM NUMBER: d- ALTERNATE PATH TASK NUMBER: U-047-NO-20 TASK TITLE: Control Valve Tightness Test K/A NUMBER: 245000 A3.08 K/A RATING: RO 3.0 SRO: 3.1 TASK STANDARD: Control Valve Tightness Test IAW 2-OI-47 section 6.9, responds to high turbine vibrations and trips the Main Turbine LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-OI-47 VALIDATION TIME: 20 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS: You are an Operator on Unit 2. The Turbine-Generator has been operating at 200 MWe for the past 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 45 minutes ago the Generator was taken off line. The Precautions and Limitations in of 2-OI-47 Turbine-Generator System have been reviewed. The Main Turbine Vibration Trip Bypass, 2-HS-47-26, is in Trip Bypass. The Turbine Turning Gear Motor control switch, 2-HS-47-10A, is in On. Steps 1 through 8 of section 6.9 are complete.

INITIATING CUE: The Unit Supervisor directs you to complete the Control Valve Tightness Test IAW 2-OI-47 section 6.9 starting at step 9.

JPM d 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 "That's Correct". (OR "That's 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 Turbine-Generator has been operating at 200 MWe for the past 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 45 minutes ago the Generator was taken off line. The Precautions and Limitations in of 2-OI-47 Turbine-Generator System have been reviewed. The Main Turbine Vibration Trip Bypass, 2-HS-47-26, is in Trip Bypass. The Turbine Turning Gear Motor control switch, 2-HS-47-10A, is in On. Steps 1 through 8 of section 6.9 are complete.

INITIATING CUE: The Unit Supervisor directs you to complete the Control Valve Tightness Test IAW 2-OI-47 section 6.9 starting at step 9.

3

JPM d START TIME ________

Performance Step 1: Critical X Not Critical 6.9 Control Valve Tightness Test

[9] DEPRESS Turbine TRIP pushbutton 2-HS-47-67D.

Standard:

Trips the Turbine.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

[10] DEPRESS Turbine RESET pushbutton 2-HS-47-67E.

Standard:

Resets the Turbine.

SAT UNSAT N/A COMMENTS:

Performance Step 3: Critical Not Critical X

[11] VERIFY ISVs are full open prior to continuing with the next step.

Standard:

Verifies ISVs FULL Open prior to step 12 SAT UNSAT N/A COMMENTS:

CUE: If a question is raised whether the ISVs are Full Open, inform the Operator that the ISVs are Full Open 4

JPM d Performance Step 4: Critical X Not Critical

[12] DEPRESS the Start Up Rate FAST pushbutton, 2-HS-47-77C.

Standard:

Depresses the Start Up Rate Fast pushbutton.

SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical Not Critical X

[13] VERIFY CV POSITION LIMIT, 2-XI-47-157, is set to approximately 66%.

Standard:

Verifies CV Position Limit set to about 66%

SAT UNSAT N/A COMMENTS:

Performance Step 6: Critical X Not Critical

[14] DEPRESS SYNC SPEED pushbutton, 2-HS-47-77H.

Standard:

Depresses Synch Speed pushbutton.

SAT UNSAT N/A COMMENTS:

5

JPM d Performance Step 7: Critical Not Critical X

[15] WHEN turbine speed is greater than 900 RPM, THEN PLACE Bearing Lift Pumps in Auto by placing the TURBINE TURNING GEAR MOTOR control switch, 2-HS-47-10A, in AUTO.

Standard:

When turbine speed > 900 RPM places bearing lift pumps in Auto.

SAT UNSAT N/A COMMENTS:

Driver: When Turbine Speed is greater than 900 RPM insert bat NRC/turbvibe Performance Step 8: Critical Not Critical X

[16] OBSERVE turbine speed is rising and the TURBINE ACCEL light, 2-ZI-47-77A, illuminates.

Standard:

Observe turbine speed is rising and Turbine Acceleration light On SAT UNSAT N/A COMMENTS:

6

JPM d Performance Step 9: Critical X Not Critical Monitors and Recognizes a High Vibration Condition exists.

Standard:

Determines that a Turbine Trip is required with Turbine Vibration greater than 12 Mils.

SAT UNSAT N/A COMMENTS:

7

JPM d Performance Step 10: Critical X Not Critical NOTE Step 6.9[4] and 6.9[5] contain conditions for tripping the turbine.

[4] IF any of the following conditions are met, THEN DEPRESS turbine TRIP pushbutton, 2-HS-47-67D:

THRUST/JOURNAL BRG TEMPERATURE, 2-TR-47-23, indicates thrust bearing metal temperature exceeding 180°F.

TURB DIFF EXPANSION, 2-XR-47-20, Point 14, located on Panel 2-9-8, indicates less than 100 Mi (Mils) or greater than 400 Mi.

THRUST/JOURNAL BRG TEMPERATURE, 2-TR-47-23, indicates bearing metal temperatures exceeding 225°F.

[5] MONITOR Turbine Vibrations AND IF any of the vibration limits listed in the following Table 1 or Table 2 (as applicable) are exceeded, THEN ,

DEPRESS turbine TRIP pushbutton, 2-HS-47-67D. (otherwise N/A)

Standard:

Depresses Turbine Trip Pushbutton SAT UNSAT N/A COMMENTS:

8

JPM d Performance Step 11: Critical Not Critical X

[17] WHEN turbine speed reaches 1800 RPM, THEN OBSERVE AT SET SPEED light, 2-IL-47-77B, illuminates and the TURBINE ACCEL light, 2-IL-47-77A extinguishes.

Standard:

At 1800 RPM observes at Set speed light On and Turbine Acceleration light Off SAT UNSAT N/A COMMENTS:

Performance Step 12: Critical Not Critical X

[18] RECORD test results in the Narrative Log.

[19] NOTIFY Unit Supervisor of test results.

Standard:

Narrative Logs are not modeled on the simulator. Step [18] is not applicable.

Notifies the Unit Supervisor of Turbine Trip.

SAT UNSAT N/A COMMENTS:

STOP TIME ________

END OF TASK 9

JPM d OPERATOR: ________________________________

RO ____ SRO DATE: ___________

JPM NUMBER: d- ALTERNATE PATH TASK NUMBER: U-047-NO-20 TASK TITLE: Control Valve Tightness Test K/A NUMBER: 245000 A3.08 K/A RATING: RO 3.0 SRO: 3.1 TASK STANDARD: Control Valve Tightness Test IAW 3-OI-47 section 6.9, responds to high turbine vibrations and trips the Main Turbine LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-OI-47 VALIDATION TIME: 20 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS: You are an Operator on Unit 3. The Turbine-Generator has been operating at 200 MWe for the past 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 45 minutes ago the Generator was taken off line. The Precautions and Limitations in of 3-OI-47 Turbine-Generator System have been reviewed. The Main Turbine Vibration Trip Bypass, 3-HS-47-26, is in Trip Bypass. The Turbine Turning Gear Motor control switch, 3-HS-47-10A, is in On. Steps 1 through 8 of section 6.9 are complete.

INITIATING CUE: The Unit Supervisor directs you to complete the Control Valve Tightness Test IAW 3-OI-47 section 6.9 starting at step 9.

JPM d 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 "That's Correct". (OR "That's 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 Turbine-Generator has been operating at 200 MWe for the past 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 45 minutes ago the Generator was taken off line. The Precautions and Limitations in of 3-OI-47 Turbine-Generator System have been reviewed. The Main Turbine Vibration Trip Bypass, 3-HS-47-26, is in Trip Bypass. The Turbine Turning Gear Motor control switch, 3-HS-47-10A, is in On. Steps 1 through 8 of section 6.9 are complete.

INITIATING CUE: The Unit Supervisor directs you to complete the Control Valve Tightness Test IAW 3-OI-47 section 6.9 starting at step 9.

3

JPM d START TIME ________

Performance Step 1: Critical X Not Critical 6.9 Control Valve Tightness Test

[9] DEPRESS Turbine TRIP pushbutton 3-HS-47-67D.

Standard:

Trips the Turbine.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

[10] DEPRESS Turbine RESET pushbutton 3-HS-47-67E.

Standard:

Resets the Turbine.

SAT UNSAT N/A COMMENTS:

4

JPM d Performance Step 3: Critical Not Critical X

[11] VERIFY ISVs are full open prior to continuing with the next step.

Standard:

Verifies ISVs FULL Open prior to step 12 SAT UNSAT N/A COMMENTS:

CUE: If a question is raised whether the ISVs are Full Open, inform the Operator that the ISVs are Full Open Performance Step 4: Critical X Not Critical

[12] DEPRESS the Start Up Rate FAST pushbutton, 3-HS-47-77C.

Standard:

Depresses the Start Up Rate Fast pushbutton.

SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical Not Critical X

[13] VERIFY CV POSITION LIMIT, 3-XI-47-157, is set to approximately 66%.

Standard:

Verifies CV Position Limit set to about 66%

SAT UNSAT N/A COMMENTS:

5

JPM d Performance Step 6: Critical X Not Critical

[14] DEPRESS SYNC SPEED pushbutton, 3-HS-47-77H.

Standard:

Depresses Synch Speed pushbutton.

SAT UNSAT N/A COMMENTS:

Performance Step 7: Critical Not Critical X

[15] WHEN turbine speed is greater than 900 RPM, THEN PLACE Bearing Lift Pumps in Auto by placing the TURBINE TURNING GEAR MOTOR control switch, 3-HS-47-10A, in AUTO.

Standard:

When turbine speed > 900 RPM places bearing lift pumps in Auto.

SAT UNSAT N/A COMMENTS:

Driver: When Turbine Speed is greater than 900 RPM insert bat NRC/turbvibe 6

JPM d Performance Step 8: Critical Not Critical X

[16] OBSERVE turbine speed is rising and the TURBINE ACCEL light, 3-ZI-47-77A, illuminates.

Standard:

Observe turbine speed is rising and Turbine Acceleration light On SAT UNSAT N/A COMMENTS:

Performance Step 9: Critical X Not Critical Monitors and Recognizes a High Vibration Condition exists.

Standard:

Determines that a Turbine Trip is required with Turbine Vibration greater than 12 Mils.

SAT UNSAT N/A COMMENTS:

7

JPM d Performance Step 10: Critical X Not Critical NOTE Step 6.9[4] and 6.9[5] contain conditions for tripping the turbine.

[4] IF any of the following conditions are met, THEN DEPRESS turbine TRIP pushbutton, 3-HS-47-67D:

THRUST/JOURNAL BRG TEMPERATURE, 3-TR-47-23, indicates thrust bearing metal temperature exceeding 180°F.

TURB DIFF EXPANSION, 3-XR-47-20, Point 14, located on Panel 3-9-8, indicates less than 100 Mi (Mils) or greater than 400 Mi.

THRUST/JOURNAL BRG TEMPERATURE, 3-TR-47-23, indicates bearing metal temperatures exceeding 225°F.

[5] MONITOR Turbine Vibrations and DEPRESS the turbine TRIP pushbutton, 3-HS-47-67D, if any vibration limits listed in the above Table 1 or Table 2 (as applicable) are exceeded.

Standard:

Depresses Turbine Trip Pushbutton SAT UNSAT N/A COMMENTS:

8

JPM d Performance Step 11: Critical Not Critical X

[17] WHEN turbine speed reaches 1800 RPM, THEN OBSERVE AT SET SPEED light, 3-IL-47-77B, illuminates and the TURBINE ACCEL light, 3-IL-47-77A extinguishes.

Standard:

At 1800 RPM observes at Set speed light On and Turbine Acceleration light Off SAT UNSAT N/A COMMENTS:

Performance Step 12: Critical Not Critical X

[18] RECORD test results in the Narrative Log.

[19] NOTIFY Unit Supervisor of test results.

Standard:

Narrative Logs are not modeled on the simulator. Step [18] is not applicable.

Notifies the Unit Supervisor of Turbine Trip.

SAT UNSAT N/A COMMENTS:

STOP TIME ________

END OF TASK 9

JPM e OPERATOR: ___________________________

RO ____ SRO DATE:

JPM NUMBER: e TASK NUMBER: U-064-NO-03 TASK TITLE: Vent Drywell IAW 2-AOI-64-1 K/A NUMBER: 223001 EA1.14 K/A RATING: RO 4.2 SRO: 4.1 TASK STANDARD: Vent the Drywell with Standby Gas Treatment Fan.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-AOI-64-1 VALIDATION TIME:

PERFORMANCE TIME:

COMMENTS: _________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ___ UNSATISFACTORY ___

SIGNATURE: _________________________ DATE: __________

EXAMINER

INITIAL CONDITIONS: You are a Reactor Operator. The Unit 2 reactor is at 100%. 2-EOI-2 has been entered on suppression pool water level high. All available drywell cooling is in service.

Drywell pressure is 1.8 PSIG and rising slowly.

INITIATING CUE: The Unit Supervisor has directed you to vent the drywell in accordance with 2-AOI-64-1.

2

JPM e 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 "That's Correct". (OR "That's 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 is at 60%. 2-EOI-2 has been entered on suppression pool water level high. All available drywell cooling is in service.

Drywell pressure is 1.8 PSIG and rising slowly.

INITIATING CUE: The Unit Supervisor has directed you to vent the drywell in accordance with 2-AOI-64-1.

JPM e START TIME Performance Step 1: Critical Not Critical X 4.2 Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s). (Otherwise N/A)

Standard:

N/A.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical Not Critical X

[2] IF Drywell Pressure is High, THEN PERFORM the following: (Otherwise N/A)

[2.1] CHECK Drywell pressure using multiple indications.

[2.2] IF Drywell pressure rising rate indicates Reactor Scram at 2.45 psi is imminent, THEN REDUCE Reactor power via Recirc flow to minimize the impact of a scram from high power.

[2.3] CHECK Drywell pressure using multiple indications.

[2.4] ALIGN and START additional Drywell coolers and fans as necessary. REFER TO 2-OI-64.

Standard:

Given in initial conditions.

SAT UNSAT N/A COMMENTS:

JPM e Performance Step 3: Critical X Not Critical CAUTION Stack release rates exceeding 1.4 X 107 ci/sec, or a SI-4.8.B.1.a.1 release fraction above one will result in ODCM release limits being exceeded.

[2.5] VENT Drywell as follows:

[2.5.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 2-FCV-64-34 (Panel 2-9-3).

Standard:

Closes 2-FCV-63-34.

SAT UNSAT N/A COMMENTS:

Performance Step 4: Critical Not Critical X

[2.5.2] VERIFY OPEN, DRYWELL INBD ISOLATION VLV, 2-FCV-64-31 (Panel 2-9-3).

Standard:

Verifies 2-FCV-64-31 is open.

SAT UNSAT N/A COMMENTS:

JPM e Performance Step 5: Critical Not Critical X

[2.5.3] VERIFY 2-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 2-9-55).

Standard:

Verifies 2-FIC-84-20 is in AUTO and SET at 100 scfm.

SAT UNSAT N/A COMMENTS:

Performance Step 6: Critical X Not Critical

[2.5.4] VERIFY RUNNING a Standby Gas Treatment Fan STGTS TRAIN C(A)(B)

(Panel 2-9-25).

Standard:

Starts SGTS TRAIN C FAN (Panel 2-9-25).

SAT UNSAT N/A COMMENTS:

Driver: If requested as Unit 1 Operator to start SGTS Fan A or B, report: Unit 1 Control Room Staff are unavailable to start the SGTS fans.

JPM e Performance Step 7: Critical Not Critical X

[2.5.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas Treatment Fans A or B. (Otherwise N/A)

CAUTION If 2-FCV-84-20 closes after 2-HS-64-35 is opened, the reason for valve closure must be cleared and 2-HS-64-35 must be returned to OPEN in order for 2-FCV-84-20 to re-open.

[2.5.6] IF required, THEN RECORD venting data in 2-SI-4.7.A.2.a (Otherwise N/A)

Standard:

N/A SAT UNSAT N/A COMMENTS:

CUE: IF asked as Unit Supervisor, then report: 2-SI-4.7.A.2.a is NOT required.

Performance Step 8: Critical X Not Critical

[2.5.7] PLACE 2-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 2-HS-64-35, in OPEN (Panel 2-9-3).

Standard:

Places 2-HS-64-35, in OPEN.

SAT UNSAT N/A COMMENTS:

JPM e Performance Step 9: Critical Not Critical X

[2.5.8] MONITOR stack release rates to prevent exceeding ODCM limits.

Standard:

Calls for rounds operator to perform 0-SI-4.8.B.1.a.1, Airborne Effluent Release rate (Gas Log).

SAT UNSAT N/A COMMENTS:

CUE: As rounds operator when requested to perform the Gas Log, report: The rounds operator is performing 0-SI-4.8.B.1.a.1, Airborne Effluent Release rate (Gas Log).

Performance Step 10: Critical X Not Critical

[2.5.9] WHEN Drywell pressure has been reduced as required, THEN STOP SGT Train(s).

Standard:

Stops the running SBGT Train.

SAT UNSAT N/A COMMENTS:

CUE: When Performance Step 9 is complete, and at the discretion of the evaluator: Report to the candidate that time compression will be used and Drywell Pressure has lowered to 1.5 PSIG .

Drywell venting is no longer required.

JPM e Performance Step 11: Critical X Not Critical

[2.5.10] VERIFY 2-HS-64-35, in AUTO and 2-FCV-84-20 CLOSED (Panel 2-9-3).

Standard:

Verifies 2-HS-64-35 in AUTO Verifies 2-FCV-84-20 CLOSED (Green Light ON and Red Light OFF on 2-ZI-84-20)

SAT UNSAT N/A COMMENTS:

Performance Step 12: Critical X Not Critical

[2.5.11] OPEN SUPPR CHBR INBD ISOLATION VLV 2-FCV-64-34 (Panel 2-9-3).

Standard:

Opens 2-FCV-64-34.

SAT UNSAT N/A COMMENTS:

Performance Step 13: Critical Not Critical X

[2.5.12] VERIFY Drywell DP compressor operates correctly to maintain required Drywell to Suppression Chamber DP.

Standard:

Monitors Drywell to Suppression Chamber DP.

SAT UNSAT N/A COMMENTS:

JPM e Performance Step 14: Critical Not Critical X

[2.5.13] RECORD SGTS Train(s) run time in appropriate Control Room Reactor narrative log for transfer to 1-SR-2.

Standard:

Narrative Logs are not modeled on the simulator. Step [2.5.13] is not applicable.

Records SGTS Train C run time in narrative log.

SAT UNSAT N/A COMMENTS:

STOP TIME END OF TASK

JPM f OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: f TASK NUMBER: S-57A-NO-01 TASK TITLE: Perform Control Room Transfer of 4kV Unit Board 2B Power Supplies K/A NUMBER: 262001A4.03 K/A RATING: RO 3.2 SRO 3.4 TASK STANDARD: Perform control room operation required to successfully transfer 4kV unit board 2B power supply from normal to alternate power supply.

LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 0-OI-57A VALIDATION TIME: 8 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS:

You are the Reactor Operator. Preventative maintenance is required on 4kV Unit Board 2B Normal Feeder Breaker, 1214.

INITIATING CUE:

The Shift Manager has directed you to transfer 4kV Unit Board 2B from the USST to the Start Bus per 0-OI-57A, section 8.13.1.

JPM f 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 "That's Correct". (OR "That's 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. Preventative maintenance is required on 4KV Unit Board 2B Normal Feeder Breaker, 1214.The Precautions and limitations of 0-OI-57A, Switchyard and 4160V AC Electrical System, have been reviewed.

INITIATING CUE:

The Shift Manager has directed you to transfer 4kV Unit Board 2B from the USST to the Start Bus per 0-OI-57A, section 8.13.1.

3

JPM f START TIME Performance Step 1: Critical Not Critical X 8.13 Control Room Transfer of 4kV Unit Board 2B Power Supplies 8.13.1 Transfer 4kv Unit Board 2B from USST to Start Bus

[1] REVIEW all Precautions and Limitations.

[2] NOTIFY NSS of possible loss of power to Security Systems prior to transferring 4kV UNIT BD 2B.

Standard:

Review of precautions and limitations given in initial conditions.

Notifies NSS of possible loss of power to security systems.

SAT UNSAT N/A COMMENTS:

CAUTIONS

1) Capacitor bank fuses are subject to clearing when the unit boards are being supplied from the 161 source and large pumps are started. Unit Supervisors should evaluate placing the Capacitor Banks in Manual prior to starting Condensate, CBP, RHR, CS or CCW pumps.

2) If 4kV Unit Board 2B is fed from the Alternate Power Supply, then Auto Transfer must be blocked for 4kV Unit Boards: 1A, 1B, 2A, 3A and 3B. (Ref. 2-45E721 OPL3

& 1-45E721 OPL5)

3) If 4kV Unit Board 2B is fed from the Alternate Power Supply (Start Bus), then Shutdown Bus 1 Auto transfer must be blocked.(Ref. 2-45E721 OPL3)\

4) If either 4kV UNIT BD 1A, 1B, 2A, 3A or 3B is aligned to a Start Bus, prior to aligning UNIT BD 2B to Start Bus, check Technical Specifications 3.8.1.a and 3.8.2.a to determine operability of qualified AC circuits between the offsite transmission network and the onsite Class 1E Electrical Power Distribution System.

4

JPM f NOTES

1) All procedural steps are performed from Control Room Panel 2-9-8.

2) This procedure section contains actions to ensure electrical load restrictions are not exceeded when 4kV UNIT BD 2B is placed on the Alternate Supply (Start Bus).

Performance Step 2: Critical Not Critical X

[3] ENSURE 4kV Start Busses are aligned Normal:

[3.1] On Panel 9-23-2, VERIFY 4kV Start Bus 1A ALT FDR BKR 1518 OPEN.

[3.2] On Panel 9-23-2, VERIFY 4kV Start Bus 1B ALT FDR BKR 1414 OPEN.

Standard:

Verifies Start Busses are aligned normal by Verifying the alt bkrs 1518 and 1414 are open.

SAT UNSAT N/A COMMENTS:

5

JPM f Performance Step 3: Critical Not Critical X

[4] On panel 0-9-23-7, VERIFY Shutdown Bus 1 is fed from Normal Supply (4kV Unit Board 1A).

Standard:

Verifies Shutdown Bus 1 is fed from Normal Supply.

SAT UNSAT N/A COMMENTS:

Performance Step 4: *Critical X Not Critical

[5] On panel 0-9-23-7, MOMENTARILY DEPRESS 0-HS-211-AB1, 4kV SD BUS 1 AUTO TO MANUAL TRIP push-button, and CHECK the following:

A. 0-HS-211-AB1, 4kV SD BUS 1 AUTO TO MANUAL TRIP push-button, light extinguished.

B. 0-43-211-AB1, 4kV SD BUS 1 AUTO/LOCKOUT RESET, trips.

Standard:

Depresses 0-HS-211-AB1 Verifies the light extinguished and 0-43-211-AB1 trips SAT UNSAT N/A COMMENTS:

6

JPM f Performance Step 5: Critical Not Critical X

[6] RE-ALIGN 4kV Auto Transfers to meet Load Restrictions.

[6.1] On Panel 1-9-8, VERIFY 1-XS-57-4, 4kV UNIT BD 1A MAN/AUTO SELECT switch to MAN.

[6.2] On Panel 1-9-8, VERIFY 1-XS-57-7, 4kV UNIT BD 1B MAN/AUTO SELECT switch to MAN.

Standard:

Contacts Unit 1 Operator to place 1-XS-57-4 and 1-XS-57-7 to Manual on panel 1-9-8.

SAT UNSAT N/A COMMENTS:

CUE: [As Unit 1 Operator, Report] 1-XS-57-4 and 1-XS-57-7 are in Manual.

Performance Step 6: Critical X Not Critical

[6.3] VERIFY 2-XS-57-4, 4kV UNIT BD 2A MAN/AUTO SELECT switch to MAN.

[6.4] VERIFY 2-XS-57-7, 4kV UNIT BD 2B MAN/AUTO SELECT switch to MAN.

Standard:

Places 2-XS-57-4 and 2-XS-57-7 switch to manual.

SAT UNSAT N/A COMMENTS:

7

JPM f Performance Step 7: Critical Not Critical X

[6.5] On Panel 3-9-8, VERIFY 3-XS-57-4, 4kV UNIT BD 3A MAN/AUTO SELECT switch to MAN.

[6.6] On Panel 3-9-8, VERIFY 3-XS-57-7, 4kV UNIT BD 3B MAN/AUTO SELECT switch to MAN.

Standard:

Contacts Unit 3 Operator to place 3-XS-57-4 and 3-XS-57-7 to Manual on panel 3-9-8.

SAT UNSAT N/A COMMENTS:

CUE: [As Unit 3 Operator, Report] 3-XS-57-4 and 3-XS-57-7 are in Manual.

8

JPM f Performance Step 8: Critical Not Critical X

[7] TRANSFER 4kv UNIT BD 2B to the ALT FDR, BKR 1526

[7.1] PLACE 2-XS-202-1, 4kV BD/BUS/XFMR VOLTAGE SELECT switch to START BUS 1B.

[7.2] CHECK START BUS 1B Voltage on 2-EI-57-28 is between 3950 and 4400 Volts.

Standard:

Placed 2-XS-202-1 switch to START BUS 1B.

Checked START BUS 1B Voltage on 2-EI-57-28 is between 3950 and 4400 Volts.

SAT UNSAT N/A COMMENTS:

Performance Step 9: Critical X Not Critical

[7.3] PLACE and HOLD 2-HS-57-8, 4kV UNIT BD 2B ALT FDR BKR 1526 switch to CLOSE.

Standard:

Places and Holds 2-HS-57-8, 4kV UNIT BD 2B ALT FDR BKR 1526 switch to CLOSE.

SAT UNSAT N/A COMMENTS:

9

JPM f Performance Step 10: Critical X Not Critical

[7.4] PLACE 2-HS-57-6, 4kV UNIT BD 2B NORM FDR BKR 1214 switch to TRIP.

Standard:

Places 2-HS-57-6, 4kV UNIT BD 2B NORM FDR BKR 1214 switch to TRIP.

SAT UNSAT N/A COMMENTS:

Performance Step 11: Critical Not Critical X

[7.5] CHECK CLOSED the 4kV UNIT BD 2B, ALT FDR BREAKER 1526.

[7.6] CHECK OPEN the 4kV UNIT BD 2B, NORM FDR BREAKER 1214.

[7.7] RELEASE BKRs 1526 and 1214 control switches.

Standard:

Checked CLOSED the 4kV UNIT BD 2B, ALT FDR BKR 1526.

Checked OPEN the 4kV UNIT BD 2B, NORM FDR BREAKER 1214 RELEASED BKRs 1526 and 1214 control switches SAT UNSAT N/A COMMENTS:

10

JPM f Performance Step 12: Critical Not Critical X

[7.8] PLACE 2-XS-202-1, 4kV BD/BUS/XFMR VOLTAGE SELECT SWITCH TO UNIT BD 2B.

[7.9] CHECK 4kV UNIT BD 2B voltage is between 3950 and 4400 Volts.

Standard:

Places 2-XS-202-1, 4kV BD/BUS/XFMR VOLTAGE SELECT SWITCH to UNIT BD 2B Checked 4kV UNIT BD 2B voltage is between 3950 and 4400 Volts.

SAT UNSAT N/A COMMENTS:

Performance Step 13: Critical Not Critical X

[7.10] VERIFY LOCALLY 4kV BKR 1526 closing spring target indicates charged and the amber breaker spring charged light is on.

Standard:

Dispatched AUO to verify breaker 1526 closing spring recharged.

SAT UNSAT N/A COMMENTS:

CUE: [After Dispatched, the AUO Reports] Breaker 1526 closing spring target indicates charged and the amber breaker spring charged lamp is illuminated.

CUE: That completes this task.

END OF TASK STOP TIME 11

JPM g 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: 2-EOI Appendix-8G VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS: _________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ___ UNSATISFACTORY ___

SIGNATURE: _________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS: You are an Operator. The Unit 2 reactor has scrammed. EOI-1 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 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 "That's Correct". (OR "That's 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 RC/P-8.

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

3

JPM g START TIME Performance Step 1: Critical X Not Critical

1. OPEN the following valves:

0-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:

4

JPM g Performance Step 3: *Critical X 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:

5

JPM g 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 MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW (2-XA-55-3D, Window 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, 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: Do NOT report unless directed by NRC. When dispatched, as AUO, report] 2-PI 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.

6

JPM g Performance Step 7: Critical X Not Critical

b. MONITOR 0-FI-84-7(18), 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-84-18 flow 90 scfm.

SAT UNSAT N/A COMMENTS:

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

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

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

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

2-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 2-FCV-1-37 and 51 closed.

SAT UNSAT N/A COMMENTS:

7

JPM g 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 9-55)

Standard:

Closes 0-FCV-84-16 and 2-FSV-84-49.

SAT UNSAT N/A COMMENTS:

STOP TIME END OF TASK 8

JPM g 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 PERFORMANCE TIME:

COMMENTS: _________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ___ UNSATISFACTORY ___

SIGNATURE: _________________________ DATE: __________

EXAMINER 1

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 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 "That's Correct". (OR "That's 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.

3

JPM g START TIME Performance 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:

4

JPM g Performance Step 3: *Critical 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:

5

JPM g Performance Step 5: Critical X Not Critical

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

Standard:

Recognizes MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW (3-XA-55-3D, Window 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: Do NOT report unless directed by NRC. When 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.

6

JPM g Performance Step 7: Critical X Not Critical

b. MONITOR 0-FI-84-7/3(18/3), 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-84-18 flow is 50 scfm.

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:

7

JPM g 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 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 3, Panel 3-9-55)

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

Standard:

Closes 0-FCV-84-16 and 3-FSV-84-49.

SAT UNSAT N/A COMMENTS:

STOP TIME END OF TASK 8

JPM h OPERATOR:

RO SRO DATE:

JPM NUMBER: h TASK NUMBER: U-090-NO-01 TASK TITLE: Returning DW Radiation Monitor CAM, 2-RM-90-256 to service K/A NUMBER: 272000 A2.10 K/A RATING: RO 3.9 SRO: 4.1 TASK STANDARD: DW Radiation Monitor CAM, 2-RM-90-256 is in service LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-AOI-100-1 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY _____ UNSATISFACTORY_____

SIGNATURE: ____________________ DATE: _____

EXAMINER 1

JPM h 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 "That's Correct". (OR "That's 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. Plant conditions are as found. The Unit Supervisor is operating in 2-AOI-100-1, Reactor Scram.

INITIATING CUES: The Unit Supervisor directs you to perform step 33 of 2-AOI-100-1, Reactor Scram, to return the Drywell DP Air Compressor, the Drywell Floor and Equipment Drains, and the Drywell Continuous Air Monitor to service.

2

INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 2-AOI-100-1, Reactor Scram.

INITIATING CUES: The Unit Supervisor directs you to perform step 33 of 2-AOI-100-1, Reactor Scram, to return the Drywell DP Air Compressor, the Drywell Floor and Equipment Drains, and the Drywell Continuous Air Monitor to service.

JPM h START TIME Performance Step 1: Critical X Not Critical

[33] VERIFY the following systems/equipment in service or RETURN them to service at standby readiness, as necessary, in accordance with the following or the appropriate OI:

[33.1] PLACE Drywell DP Air Compressor in service at Panel 2-9-3 as follows:

PLACE DRYWELL INBD ISOLATION VLV switch, 2-HS-64-31, in AUTO after OPEN.

PLACE SUPPR CHBR INBD ISOLATION VLV switch, 2-HS-64-34, in AUTO after OPEN.

Standard:

Places 2-HS-64-31 and 34 in Auto after Open.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

DEPRESS DRYWELL DP COMP SUCTION VLV RESET switch, 2-HS-64-139A.

DEPRESS DRYWELL DP COMP DISCH VLV RESET switch, 2-HS-64-140A.

Standard:

Depresses 2-HS-64-139A and 2-HS-64-140A to reset.

SAT UNSAT N/A COMMENTS:

4

JPM h Performance Step 3: Critical X Not Critical

[33.2] PLACE Drywell Floor and Equipment Drains in service at Panel 2-9-4 as follows:

PLACE DW EQPT DRAIN INBD ISOL VALVE switch, 2-HS-77-15A, in AUTO after OPEN.

PLACE DW EQPT DRAIN OUTBD ISOL VALVE switch, 2-HS-77-15B, in AUTO after OPEN.

Standard:

Places 2-HS-77-15A and 2-HS-77-15B in Auto after Open.

SAT UNSAT N/A COMMENTS:

Performance Step 4: Critical X Not Critical

PLACE DW FLOOR DRAIN INBD ISOL VALVE switch, 2-HS-77-2A, in AUTO after OPEN.

PLACE DW FLOOR DRAIN OUTBD ISOL VALVE switch, 2-HS-77-2B, in AUTO after OPEN.

Standard:

Places 2-HS-77-2A and 2B in Auto after Open.

SAT UNSAT N/A COMMENTS:

5

JPM h Performance Step 5: Critical X Not Critical

[33.3] PLACE DRYWELL RAD MONITOR in service at Panel 2-9-2 by DEPRESSING the following RESET pushbuttons:

UPPER INBD SUPPLY ISOL VALVE RESET, 2-HS-90-254A-A

LOWER INBD SUPPLY ISOL VALVE RESET, 2-HS-90-254B-A

INBD RETURN ISOL VALVE RESET, 2-HS-90-257B-A

OUTBD SUPPLY ISOL VALVE RESET, 2-HS-90-255A

OUTBD RETURN ISOL VALVE RESET, 2-HS-90-257A-A Standard:

Depresses the five listed reset pushbuttons to return the Drywell Rad Monitor to service SAT UNSAT N/A COMMENTS:

6

JPM h Performance Step 6: Critical X Not Critical

[33.4] PERFORM the following to place the Drywell Atmosphere Monitor (H202) in service:

[33.4.1] DEPRESS H2/O2 ANALYZER ISOLATION RESET pushbutton, 2-HS-76-91 on Panel 2-9-54.

Standard:

Depresses 2-HS-76-91to reset H2/O2 Analyzer SAT UNSAT N/A COMMENTS:

CUE: Another operator is going to place the H2/O2 Analyzer in service. This completes your task.

END OF TASK STOP TIME ______

7

JPM h OPERATOR:

RO SRO DATE:

JPM NUMBER: h TASK NUMBER: U-090-NO-01 TASK TITLE: Returning DW Radiation Monitor CAM, 3-RM-90-256 to service K/A NUMBER: 272000 A2.10 K/A RATING: RO 3.9 SRO: 4.1 TASK STANDARD: DW Radiation Monitor CAM, 3-RM-90-256 is in service LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-AOI-100-1 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY _____ UNSATISFACTORY_____

SIGNATURE: ____________________ DATE: _____

EXAMINER 1

JPM h 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 "That's Correct". (OR "That's 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. Plant conditions are as found. The Unit Supervisor is operating in 3-AOI-100-1, Reactor Scram.

INITIATING CUES: The Unit Supervisor directs you to perform step 33 of 3-AOI-100-1, Reactor Scram, to return the Drywell DP Air Compressor, the Drywell Floor and Equipment Drains, and the Drywell Continuous Air Monitor to service.

2

INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 3-AOI-100-1, Reactor Scram.

INITIATING CUES: The Unit Supervisor directs you to perform step 33 of 3-AOI-100-1, Reactor Scram, to return the Drywell DP Air Compressor, the Drywell Floor and Equipment Drains, and the Drywell Continuous Air Monitor to service.

JPM h START TIME Performance Step 1: Critical X Not Critical

[33] VERIFY the following systems/equipment in service or RETURN them to service at standby readiness, as necessary, in accordance with the following or the appropriate OI:

[33.1] PLACE Drywell DP Air Compressor in service at Panel 3-9-3 as follows:

PLACE DRYWELL INBD ISOLATION VLV switch, 3-HS-64-31, in AUTO after OPEN.

PLACE SUPPR CHBR INBD ISOLATION VLV switch, 3-HS-64-34, in AUTO after OPEN.

Standard:

Places 3-HS-64-31 and 34 in Auto after Open.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical

DEPRESS DRYWELL DP COMP SUCTION VLV RESET switch, 3-HS-64-139A.

DEPRESS DRYWELL DP COMP DISCH VLV RESET switch, 3-HS-64-140A.

Standard:

Depresses 3-HS-64-139A and 3-HS-64-140A to reset.

SAT UNSAT N/A COMMENTS:

4

JPM h Performance Step 3: Critical X Not Critical

[33.2] PLACE Drywell Floor and Equipment Drains in service at Panel 3-9-4 as follows:

PLACE DW EQPT DRAIN INBD ISOL VALVE switch, 3-HS-77-15A, in AUTO after OPEN.

PLACE DW EQPT DRAIN OUTBD ISOL VALVE switch, 3-HS-77-15B, in AUTO after OPEN.

Standard:

Places 3-HS-77-15A and 3-HS-77-15B in Auto after Open.

SAT UNSAT N/A COMMENTS:

Performance Step 4: Critical X Not Critical

PLACE DW FLOOR DRAIN INBD ISOL VALVE switch, 3-HS-77-2A, in AUTO after OPEN.

PLACE DW FLOOR DRAIN OUTBD ISOL VALVE switch, 3-HS-77-2B, in AUTO after OPEN.

Standard:

Places 3-HS-77-2A and 2B in Auto after Open.

SAT UNSAT N/A COMMENTS:

5

JPM h Performance Step 5: Critical X Not Critical

[33.3] PLACE DRYWELL RAD MONITOR in service at Panel 3-9-2 by DEPRESSING the following RESET pushbuttons:

UPPER INBD SUPPLY ISOL VALVE RESET, 3-HS-90-254A-A

LOWER INBD SUPPLY ISOL VALVE RESET, 3-HS-90-254B-A

INBD RETURN ISOL VALVE RESET, 3-HS-90-257B-A

OUTBD SUPPLY ISOL VALVE RESET, 3-HS-90-255A

OUTBD RETURN ISOL VALVE RESET, 3-HS-90-257A-A Standard:

Depresses the five listed reset pushbuttons to return the Drywell Rad Monitor to service SAT UNSAT N/A COMMENTS:

6

JPM h Performance Step 6: Critical X Not Critical

[33.4] PERFORM the following to place the Drywell Atmosphere Monitor (H202) in service:

[33.4.1] DEPRESS H2/O2 ANALYZER ISOLATION RESET pushbutton, 3-HS-76-91 on Panel 3-9-54.

Standard:

Depresses 3-HS-76-91to reset H2/O2 Analyzer SAT UNSAT N/A COMMENTS:

CUE: Another operator is going to place the H2/O2 Analyzer in service. This completes your task.

END OF TASK STOP TIME ______

7

JPM i OPERATOR: ____________________________________

RO SRO DATE:

JPM NUMBER: i TASK NUMBER: U-000-SS-32 TASK TITLE: Reactor Pressure Control at Panel 2-25-32 K/A NUMBER: 295016 AA1.08 K/A RATING: RO 4.0 SRO: 4.0 TASK STANDARD: Reactor Pressure control established at panel 2-25-32 and MSIVs closed.

PRA:

LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 2-AOI-100-2 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS: You are a Unit Operator Unit 2 Control had to be abandoned. The Unit Supervisor is operating in 2-AOI-100-2 Control Room Abandonment. All control rods inserted when RPS was actuated. Another operator has Attachment 9 at Panel 2-25-32.

INITIATING CUE: The Unit Supervisor directs you establish pressure control at Panel 2-25-32 and to close the MSIVs. The directed Reactor Pressure band is 800 to 1000 psig.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT

JPM i 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 "That's correct" (or That's 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 Unit 2 Control had to be abandoned. The Unit Supervisor is operating in 2-AOI-100-2 Control Room Abandonment. All control rods inserted when RPS was actuated. Another operator has Attachment 9 at Panel 2-25-32.

INITIATING CUE: The Unit Supervisor directs you establish pressure control at Panel 2-25-32 and to close the MSIVs. The directed Reactor Pressure band is 800 to 1000 psig.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT 3

JPM i START TIME Performance Step 1: Critical Not Critical X 4.2 Unit 2 Subsequent Actions

[1] IF ALL control rods were NOT fully inserted AND RPS failed to deenergize, THEN:

(Otherwise N/A)

Standard:

N/A SAT UNSAT N/A COMMENTS:

4

JPM i Performance Step 2: Critical Not Critical X NOTES

1) The following transfers Reactor Pressure Control to Panel 2-25-32 to allow for pressure control while completing the Panel Checklist.

2) Attachment 9, Alarm Response Procedure Panel 2-25-32, provides for any alarms associated with this instruction.

CAUTION

1) Failure to place control switch in desired position prior to transferring to emergency position may result in inadvertent actuation of the component.

2) Operation from Panel 2-25-32 bypasses logic and interlocks normally associated with the components.

[2] PLACE the following MSRV control switches in CLOSE/AUTO at Panel 2-25-32:

Switch No. Description 2-HS-1-22C MAIN STM LINE B RELIEF VALVE 2-HS-1-5C MAIN STM LINE A RELIEF VALVE 2-HS-1-30C MAIN STM LINE C RELIEF VALVE 2-HS-1-34C MAIN STM LINE C RELIEF VALVE Standard:

Simulates placing 2-HS-1-22C, 5C, 30C, and 34C in Close /Auto SAT UNSAT N/A COMMENTS:

Cue: Switch is in Close/Auto, or as found. If Asked Reactor Pressure is stable at 960 psig 5

JPM i Performance Step 3: Critical X Not Critical

[3] PLACE the following MSRV disconnect switches in DISCT at Panel 2-25-32:

Switch No. Description 2-XS-1-18 MAIN STM LINE B RELIEF VALVE DISCT 2-XS-1-4 MAIN STM LINE A RELIEF VALVE DISCT 2-XS-1-42 MAIN STM LINE D RELIEF VALVE DISCT 2-XS-1-23 MAIN STM LINE B RELIEF VALVE DISCT 2-XS-1-41 MAIN STM LINE D RELIEF VALVE DISCT 2-XS-1-180 MAIN STM LINE D RELIEF VALVE DISCT Standard:

Simulates placing 2-XS-1-18, 4, 42, 23, 41, and 180 in Disct SAT UNSAT N/A COMMENTS:

Cue: Switches are in DISCONNECT.

6

JPM i Performance Step 4: Critical X Not Critical

[4] PLACE the following MSRV transfer switches in EMERG at Panel 2-25-32:

Switch No. Description 2-XS-1-22 MAIN STM LINE B RELIEF VALVE XFR 2-XS-1-5 MAIN STM LINE A RELIEF VALVE XFR 2-XS-1-30 MAIN STM LINE C RELIEF VALVE XFR 2-XS-1-34 MAIN STM LINE C RELIEF VALVE XFR Standard:

Simulates placing 2-XS-1-22, 5, 30 and 34 in Emergency SAT UNSAT N/A COMMENTS:

CUE: Switches are in Emergency.

7

JPM i Performance Step 5: Critical X Not Critical NOTE Use of the following sequence when opening MSRVs should distribute heat evenly in the Suppression Pool.

[5] MAINTAIN Reactor Pressure between 800 and 1000 psig using the following sequence at Panel 2-25-32:

A. 2-HS-1-22C, MAIN STM LINE B RELIEF VALVE B. 2-HS-1-5C, MAIN STM LINE A RELIEF VALVE C. 2-HS-1-30C, MAIN STM LINE C RELIEF VALVE D. 2-HS-1-34C, MAIN STM LINE C RELIEF VALVE Standard:

Simulates cycling SRVs as necessary to maintain reactor pressure 800 to 1000 psig SAT UNSAT N/A COMMENTS:

CUE: Initial Reactor Pressure is 960 psig, when the Inboard MSIVs are closed in the next step begin to raise and lower pressure depending upon actions of the applicant. Until JPM complete cycle reactor pressure between 800 to 1000 psig every two minutes. If candidate fails to check or ask give a high or low pressure as warranted.

8

JPM i Performance Step 6: Critical X Not Critical CAUTION Failure to place control switch in desired position prior to transferring to emergency position may result in inadvertent actuation of the component.

[6] CLOSE MSIVs using the following switch sequence at Panel 2-25-32:

[6.1] PLACE control switch in CLOSE.

[6.2] PLACE transfer switch in EMERG.

Standard:

Simulates placing control switch in close and then the transfer switch for each MSIV SAT UNSAT N/A COMMENTS:

CUE: Control switch is in Close, Transfer switch is in Emergency, MSIV green light On and Red light Off.

When the D Inboard MSIV is closed Reactor Pressure begins to rise.

When applicant demonstrates pressure control terminate JPM, once all MSIV are closed.

END OF TASK STOP TIME 9

JPM j OPERATOR: ________________________________

RO SRO DATE:

JPM NUMBER: j TASK NUMBER: U-000-SS-10 TASK TITLE: Reset Battery Charger 1, 2B and 3 K/A NUMBER: 295004 A1.01 K/A RATING: RO 3.3 SRO 3.4 TASK STANDARD: Resets battery chargers 1, 2b, and 3 during a fire in the unit 1 reactor building EL 621 and 639 North of column line R.

LOCATION OF PERFORMANCE: Control Bay REFERENCES/PROCEDURES NEEDED: 0-SSI-1-5 VALIDATION TIME: 20 minutes PERFORMANCE TIME: 60 minutes maximum COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

INITIAL CONDITIONS:

A fire has occurred in Unit 1 Reactor Building. The Shift Manager has directed entry into the SSIs.

INITIATING CUE:

The Unit Supervisor directs you to perform Operator 2 Manual Actions, Section 2.0, of 0-SSI-1-5, Unit 1 Reactor Building Fire EL 621 and 639 North of Column Line R.

This JPM is Time Critical.

JPM j 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 "That's Correct". (OR "That's 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:

A fire has occurred in Unit 1 Reactor Building. The Shift Manager has directed entry into the SSIs.

INITIATING CUE:

The Unit 2 Unit Supervisor directs you to perform Operator 2 Manual Actions, Section 2.0, of 0-SSI-1-5, Unit 1 Reactor Building Fire EL 621 and 639 North of Column Line R.

This JPM is Time Critical.

3

JPM j START TIME Performance Step 1: Critical Not Critical X 0-SSI-1-5 2.0 RESET BATTERY CHARGERS 1, 2B AND 3

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

Standard:

Given in initial conditions.

SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical (60 Min)

[2] PROCEED TO 250V BATTERY CHARGER 1, 1-CHGA-248-0001, AND PLACE POWER ON, 1-HS-248-0001, in EMERG.

Standard:

Simulates placing 1-HS-248-0001 POWER ON in EMERG at Battery Charger 1.

SAT UNSAT N/A COMMENTS:

CUE: The POWER ON handswitch is in EMERGENCY.

4

JPM j Performance Step 3: Critical X Not Critical

[3] PROCEED TO 250V BATTERY CHARGER 3, CHGA-248-0003, AND PLACE POWER ON, 3-HS-248-0003, in EMERG.

Standard:

Simulates placing 1-HS-248-0003 POWER ON in EMERG at Battery Charger 3.

SAT UNSAT N/A COMMENTS:

CUE: The POWER ON handswitch is in EMERGENCY.

Performance Step 4: *Critical X Not Critical

[4] PROCEED TO 250V BATTERY CHARGER 2A, 2-CHGA-248-0002A, AND PERFORM the following:

[4.1] PLACE POWER ON, 2-HS-248-0002A, in OFF.

[4.2] VERIFY ALTERNATE SUPPLY INPUT FROM 480V CMN BD 1/3A, 2-BKR-248-0002AB, in OFF.

Standard:

Simulates placing POWER ON, 2-HS-248-0002A, in OFF. Verifies ALTERNATE SUPPLY INPUT FROM 480V CMN BD 1/3A in OFF.

SAT UNSAT N/A COMMENTS:

CUE: The POWER ON handswitch is in OFF and the ALTERNATE SUPPLY INPUT is in OFF.

5

JPM j Performance Step 5: Critical X Not Critical

[4.3] PLACE NORMAL SUPPLY INPUT FROM 480V SD BD 2A/6D, 2-BKR-248-0002AA, in OFF.

[4.4] PLACE DC BREAKER, 2-BKR-248-0002A/DC, in OFF.

Standard:

Simulates placing the NORMAL SUPPLY INPUT in OFF. Places the DC BREAKER 2-BKR-248-0002A/DC, in OFF.

SAT UNSAT N/A COMMENTS:

CUE: The NORMAL SUPPLY INPUT is in OFF and the DC BREAKER is in OFF.

6

JPM j Performance Step 6: Critical X Not Critical

[5] PROCEED TO BATTERY CHARGER 2A OUTPUT TRANSFER SWITCH, 2-XSW-248-0002A, AND PLACE OUTPUT XFER SW TO BKR 608, 2-BKR-248-0002AE, in OFF.

Standard:

Simulates placing OUTPUT XFER SW TO BKR 608, 2-BKR-248-0002AE, in OFF.

SAT UNSAT N/A COMMENTS:

CUE: The OUTPUT XFER SW TO BKR 608, 2-BKR-248-0002AE, is in OFF.

Performance Step 7: Critical Not Critical X

[6] PROCEED TO 250V BATTERY BOARD 2 Breaker 607, AND PLACE 0-BKR-280-0002/607 250V BATTERY CHARGER 2B EMER TIE TO DC BD 2, in ON.

Standard:

Simulates placing BATTERY CHARGER 2B EMER TIE TO DC BD 2 in ON.

SAT UNSAT N/A COMMENTS:

CUE: The BATTERY CHARGER 2B EMER TIE TO DC BD 2 is in ON.

7

JPM j Performance Step 8: Critical X Not Critical

[7] PERFORM the following at BATTERY CHARGER 2B OUTPUT TRANSFER SWITCH 2B, 0-XSW-248-0002B:

[7.1] PLACE BATTERY CHARGER 2B OUTPUT TRANSFER SWITCH 2B, 0-XSW-248-0002B, Mechanical interlock, in TO BATTERY BD 2 BKR 607 position.

[7.2] PLACE TO BATTERY BD 2 BKR 607 breaker, in ON.

Standard:

Simulates sliding the Mechanical Interlock left to the TO BATTERY BD 2 BKR 607 position, and placing TO BATTERY BD 2 BKR 607 breaker in ON.

SAT UNSAT N/A COMMENTS:

CUE: The Mechanical interlock, is in TO BATTERY BD 2 BKR 607 position, and TO BATTERY BD 2 BKR 607 breaker is in ON.

8

JPM j Performance Step 9: Critical X Not Critical

[7.3] PROCEED TO 250V BATTERY CHARGER 2B, 0-CHGA-248-0002B, AND PERFORM the following:

[7.3.1] PLACE NORMAL SUPPLY INPUT FROM 480V SD BD 2B/6D, 0-BKR-248-0002BA, in ON.

[7.3.2] PLACE DC BREAKER, 0-BKR-248-0002B/DC, in ON.

Standard:

Simulates placing NORMAL SUPPLY INPUT FROM 480V SD BD 2B/6D in ON, and placing DC BREAKER in ON.

SAT UNSAT N/A COMMENTS:

CUE: The NORMAL SUPPLY INPUT FROM 480V SD BD 2B/6D is in ON, and the DC BREAKER is in ON.

9

JPM j Performance Step 10: Critical X Not Critical NOTE The following step will place Battery Charger 2B in service with the 480V load shed logic trip bypassed.

[7.3.3] PLACE POWER ON, 0-HS-248-0002B, in EMERG.

Standard:

Simulates placing POWER ON, 0-HS-248-0002B, in EMERG.

SAT UNSAT N/A COMMENTS:

CUE: The POWER ON handswitch is in EMERGENCY.

10

JPM j Performance Step 11: Critical __ Not Critical X

[8] NOTIFY Unit 2 Unit Supervisor of completion of this section.

Standard:

Notifies the Unit 2 Unit Supervisor of completion of this section.

SAT UNSAT N/A COMMENTS:

CUE: Another Operator will perform Section 3.0. This completes your task.

END OF TASK STOP TIME 60 Minutes is the time-critical allowed maximum 11

JPM k OPERATOR: _________________________________

RO ____ SRO ____ DATE: __________

JPM NUMBER: i TASK NUMBER: U-000-EM-19 TASK TITLE: 1-EOI Appendix-1A 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 IAW 1-EOI Appendix-1A LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1-EOI Appendix-1A VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

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 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 1-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k 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 "That's correct" (or That's 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-1 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 1-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

3

JPM k START TIME Performance Step 1: Critical Not Critical X

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 X

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:

CUE: When location of EOI Storage Box identified, Operator has the fuse pullers 4

JPM k Performance Step 3: Critical X 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-009-0015):

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 of proper Fuse is indicated the Fuse has been removed 5

JPM k 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-009-0017):

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 of proper Fuse is indicated the Fuse has been removed 6

JPM k 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:

CUE: Acknowledge Notification, SRO Does not direct replacement of fuses END OF TASK STOP TIME 7

JPM k OPERATOR: _________________________________

RO ____ SRO ____ DATE: __________

JPM NUMBER: i TASK NUMBER: U-000-EM-19 TASK TITLE: 2-EOI Appendix-1A 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 IAW 2-EOI Appendix-1A LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-1A VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

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-1 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 k 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 "That's correct" (or That's 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-1 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!

3

JPM k START TIME Performance Step 1: Critical Not Critical X

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:

CUE: When location of EOI Storage Box identified, Operator has the fuse pullers 4

JPM k Performance Step 3: Critical X 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-FU1-085-0039A/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT UNSAT N/A COMMENTS:

CUE: When location of proper Fuse is indicated the Fuse has been removed 5

JPM k 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 location of proper Fuse is indicated the Fuse has been removed 6

JPM k 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 direct replacement of fuses END OF TASK STOP TIME 7

JPM k OPERATOR: _________________________________

RO ____ SRO ____ DATE: __________

JPM NUMBER: i TASK NUMBER: U-000-EM-19 TASK TITLE: 3-EOI Appendix-1A 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 IAW 3-EOI Appendix-1A LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-1A VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS: __________________________________________________________

Additional comment sheets attached? YES ___ NO ___

RESULTS: SATISFACTORY ____ UNSATISFACTORY ____

SIGNATURE: __________________________ DATE: __________

EXAMINER 1

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!

JPM k 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 "That's correct" (or That's 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-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!

3

JPM k START TIME Performance Step 1: Critical Not Critical X

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 location of EOI Storage Box identified, Operator has the fuse pullers 4

JPM k Performance Step 3: Critical X 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-FU1-085-0039A/4 Standard:

Identifies terminal strip and simulates removing listed fuses SAT UNSAT N/A COMMENTS:

CUE: When location of proper Fuse is indicated the Fuse has been removed 5

JPM k 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: When location of proper Fuse is indicated the Fuse has been removed 6

JPM k 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:

CUE: Acknowledge Notification, SRO Does not direct replacement of fuses END OF TASK STOP TIME 7

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ML14049A015: Difference between revisions

Latest revision as of 23:08, 5 February 2020

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